ML18003A295
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| ML18003A295 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/22/1978 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18003A294 | List: |
| References | |
| NUDOCS 7812070188 | |
| Download: ML18003A295 (2) | |
Similar Documents at Harris | |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 April 1999
[Table view]Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 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 ML18022A9701995-09-29029 September 1995 Part 21 Rept Re Failure of Charging SI Pump Miniflow Check Valves.Caused by Cocking of Piston Towards Valve Outlet Port Due to Large Hydraulic Surge.Valves That Experienced Failures Replaced ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites 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 ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed 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 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 ML17289A6971992-06-26026 June 1992 Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours ML18010A5701992-03-23023 March 1992 Initial Part 21 Rept Re Defect in Anchor Darling Supplied Main Feedwater Preheater Bypass Isolation Valves.On 920112, All non-Q Components Replaced W/Suitable Components & Tested Satisfactorily.Next Rept Will Be Submitted by 920214 ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML18010A5071992-01-16016 January 1992 Initial Part 21 Rept Re Deficiency in Actuator to Main Feedwater Preheater Bypass Isolation Valves.On 920107,2 H Surveillance Interval Was Commenced to Verify Actuator Components Were Functioning Properly ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML18005B0321989-08-25025 August 1989 Potential Part 21 Rept Re ITE-Siemens molded-case Circuit Breakers Not Holding Required Load,Resulting in Inoperability.Motor in-rush Current Tests Will Be Performed on S-4 Motor to Determine If Correct Breaker Utilized ML18005B0081989-07-26026 July 1989 Part 21 Rept Re Potential Failure of Main Steam PORVs Supplied by Control Components,Inc.Initially Reported on 890719.Cause of Failure Speculated to Be Dirt or Corrosion Particles Preventing Ring from Sealing.Porv Trim Modified 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 ML20207P0451988-10-0505 October 1988 Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015 ML18005A6551988-09-29029 September 1988 Part 21 Rept Re Deficiency in Control & Power Circuits for Dc motor-operated Valves Due to Lack of Surge Protection. Initially Reported on 880518.Interim Measures Established to Ensure Proper Operation of Valves Until Surge Installed ML18005A4401988-05-18018 May 1988 Part 21 Rept Re Dc Motor Failure on Auxiliary Feedwater Limitorque Operated Valves.Plant Mod Will Be Implemented to Install Surge Protection for Shunt Coil Circuitry of Subject Dc Motors ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML18004B9461987-09-22022 September 1987 Part 21 Rept Re Failure to Postulate Unavailability of Vital Dc Bus in Conjunction W/Auxiliary Feedwater (AFW) Isolation Design.Afw Isolation Logic Modified W/Westinghouse Involvement.Operation Will Resume Upon Completion of Mods ML18004B8701987-07-0101 July 1987 Part 21 & Deficiency Rept Re LOCA Occurring During Modes 3 & 4.Initially Reported on 860815.Completion Date for Item Cannot Be Determined Due to Continued Westinghouse Owners Group Effort ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure ML20207R7031987-03-11011 March 1987 Part 21 Rept Re Potential Defect in Static Exciter Voltage Regulator (Sevr) Reset Design.Recommends Mod to Control Circuits to Energize Sevr Upon Receipt of Emergency Start Signal.Mods Will Be Completed by 870331 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 ML20210E7901987-02-0404 February 1987 Part 21 Rept Re Incorrect Operation of Hfa Auxiliary Relays, Per 861114 GE Svc Advice Ltr 188.1.Relays Installed in Standby Diesel Generator Sys Af Plant.Svc Ltr Forwarded to Util ML20215F0041986-12-12012 December 1986 Final Deficiency Rept,Item 233 Re Quantity of Electrical Separation Interactions That Remained Undetected After Installation Insp.Initially Reported on 860822.Remaining Separation Interactions Identified,Reworked & Reinspected ML20213F8101986-11-10010 November 1986 Interim Deficiency Rept,Item 233,re Electrical Separation. Initially Reported on 860822.Addl Time Necessary to Submit Final Rept.Final Rept Expected on 861210 ML20215K5301986-10-14014 October 1986 Deficiency Rept,Item 234 Re Structural Steel Welds Not Meeting Project Acceptance Criteria.Initially Reported on 860921.Item Not Reportable Per 10CFR50.55(e) & 10CFR21, Confirming 861014 Telcon ML20215K5651986-10-14014 October 1986 Deficiency Rept,Item 231 Re Use of Hylomar Thread Sealant in Stainless Steel Applications.Initially Reported on 860814. Item Not Reportable Per 10CFR50.55(e) Confirming 861014 Telcon 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 ML20214K4131986-10-0303 October 1986 Interim Deficiency Rept,Item 233 Re Electrical Separation. Initially Reported on 860822.Final Rept Will Be Issued by 861110 ML20214K8581986-09-29029 September 1986 Interim Deficiency Rept,Item 231 Re Hylomar Thread Sealant Exceeding Acceptable Chloride Limits.Initially Reported on 860814.Addl Time Required to Complete Testing.Next Rept Delayed Until 861010 ML20206U6661986-09-19019 September 1986 Interim Deficiency Rept,Item 233 Re 12 Electrical Separation Interactions on Two Conduits in Fuel Handling Bldg.Initially Reported on 860822.Separation Interactions Reworked & Reinsp.Next Rept Will Be Submitted by 861003 ML20210D6301986-09-11011 September 1986 Part 21 & Deficiency Rept,Item 232 Re LOCA Occurring During Modes 3 & 4.Initially Reported on 860815.Util Will Pursue Resolution W/Westinghouse Owners Group.Next Rept Will Be Submitted by 870701 ML20210D5301986-09-11011 September 1986 Deficiency Rept,Item 231 Re Hylomar Thread Sealant Used in Stainless Steel Applications Found to Exceed Acceptable Chloride Limits.Initially Reported on 860814.Testing Underway.Item Reportability Will Be Submitted by 860926 ML20212P3171986-08-14014 August 1986 Final Part 21 & Deficiency Rept,Item 230 Re Foreign Objects in Steam Generators B & C.Initially Reported in 860814 Telcon.Evaluation Completed.Condition Nonreportable Per 10CFR50.55(e) & 10CFR21 ML20205F6141986-08-13013 August 1986 Part 21 Rept Re Connecting Rod Bolts for Dsrv Engines.Listed Procedures Recommended for Next Connecting Rod Insp, Including Replacement of Bolts Due to Cracked Threads & Large Grooves & Galls in Threads ML20212B5831986-08-0101 August 1986 Part 21 Rept Re Technical Noncompliance W/Matl Certification of Krueger (Div of Phillips Industries) Aluminum Extrusions Used at Nuclear Plants.Vendor to Perform Tensile Tests from Each Heat Number If use-as-is Condition Unacceptable ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20212D0081986-07-0909 July 1986 Final Deficiency Rept,Item 229,re Emergency Svc Water Pump a Trip.Initially Reported on 860609.Caused by Failure of Penetration Seal at Intake Structure.Seal Design Modified. Pump Disassembled & Inspected 1999-04-12 Category:TEXT-SAFETY REPORT MONTHYEARML18017A9181999-10-0808 October 1999
[Table view]LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML18017A9151999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML18017A8621999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised ML18017A8361999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr ML18016B0151999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18016A9801999-06-0404 June 1999 LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr ML18016A9851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr ML18017A8981999-05-12012 May 1999 Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines. ML18016A9581999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML18016A9111999-04-12012 April 1999 LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr ML18016A8971999-04-0808 April 1999 LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr ML18016A8941999-04-0505 April 1999 Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760 ML18016A9101999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr ML18016A8661999-03-31031 March 1999 Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept. ML18017A8931999-02-28028 February 1999 Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant. ML18016A8551999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr ML18016A8261999-02-22022 February 1999 LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr ML18016A8531999-02-18018 February 1999 Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'. ML18016A8111999-02-12012 February 1999 LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr ML18016A7971999-02-0505 February 1999 LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr ML18022B0631999-02-0404 February 1999 Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings ML20202J1161999-02-0101 February 1999 SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program ML18016A8041999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr ML18016A7941999-01-29029 January 1999 LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor ML18016A7801998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr ML18016A7671998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr ML18016A9731998-11-28028 November 1998 Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr ML18016A8351998-11-28028 November 1998 ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1. ML18016A7411998-11-25025 November 1998 Rev 1 to Shnpp Cycle 9 Colr. ML18016A7211998-11-17017 November 1998 LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr ML18016A7071998-11-0303 November 1998 Rev 0 to Harris Unit 1 Cycle 9 Colr. ML18016A7201998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves ML18016A6201998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr ML18016A5971998-09-21021 September 1998 Rev 1 to Harris Unit 1 Cycle 8 Colr. ML18016A5881998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr ML18016A5071998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr ML18016A9431998-07-0707 July 1998 Rev 1 to QAP Manual. ML18016A4841998-07-0707 July 1998 LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys ML18016A9371998-06-30030 June 1998 Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp. ML18016A4861998-06-30030 June 1998 Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr ML18016A4701998-06-30030 June 1998 LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11 ML18016A4491998-06-0808 June 1998 LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr ML18016A4521998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr ML18016A7711998-05-26026 May 1998 Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'. 1999-09-30 |
Text
SHEARON HARRIS NUCLEAR POMER PLANT UNIT NO. 1 Deletion of Bond Breaker and Void at the Base of the Containment Liner Mall Final Report November 22, 1978 Reportable Under 10CFR50.55(e)
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BOND BREAKER AND VOID AT BASE OP CONTAIRiENT LINER MALL Introduction The Shearon Harris Nuclear Power Plant contains a reinforced concrete, steel-lined containment. This containment is described in the SHNPP PSAR. The design of this containment requires some flexibility of the containment liner during periods when the containment is pressurized, such as containment tests and LOCA conditions.
Descri tion Dr'awings for construction of the SHNPP liner were issued. These drawings did not contain all of the design details necessary to ensure that the containment liner would function under all conditions of operation. Specifically, some details of construction of the containment liner were not included in the drawings released for construction. The details specifically missing were details regarding the installation of a bond breaker to the lower portion of the containment liner cylindrical wall, and the provision of a small concrete void at the )unction of the containment liner cylindrical wall and the containment liner base.
Safet Im lications If the containment had been constructed utilizing the originally released constxuction drawings, thexe could have been a safety implication in this item. Pressurizing the containment to conditions experienced in containment testing and in loss of cooling accidents could result in overstress of the containment liner at the )oint between the containment liner cylindrical wall and the containment liner base. This could have resulted in the containment liner not fulfilling its design purpose.
Corrective Actions Ebasco identified that the detail was inadvertently deleted from the design drawings during the drafting process and issued a design change notice to correct those drawings. This action was initiated and completed prior to any actual construction relating to the placing of concrete liner. The design change notice is being implemented and the containment is being constructed in accordance with design. No additional action is anticipated in supplying additional information regarding the containment liner design or in modifying construction. This item has been discussed with Ebasco, and they have been requested to check their drawings more closely prior to issue for construction.
LSW/dlw/sdh (159/250)
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