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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217J4331999-10-15015 October 1999 Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station ML20217A9881999-10-0101 October 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A7361999-10-0101 October 1999 Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs ML20217J1251999-09-30030 September 1999 Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC ML20217J1421999-09-30030 September 1999 Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC ML20212G6751999-09-22022 September 1999 Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability ML20217H3421999-09-17017 September 1999 Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed ML20211Q2671999-09-0808 September 1999 Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000 U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 ML20211D2201999-08-23023 August 1999 Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired ML20211A8931999-08-19019 August 1999 Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 ML20210U3771999-08-12012 August 1999 Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210A4401999-07-16016 July 1999 Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations ML20209G7671999-07-12012 July 1999 Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed ML20209D5691999-07-0707 July 1999 Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20196J9651999-07-0202 July 1999 Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements ML20196J7131999-06-30030 June 1999 Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1 U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology ML20196A3471999-06-16016 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology 05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed 05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors ML20209G7731999-05-27027 May 1999 Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999 Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999 Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5 U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999 Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999 Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999 Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999 Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999 Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999 Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999 Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f) U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999 Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3) 05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999 Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999 Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999 Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired 1999-09-22
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1 August 1,1997 i
. P!tlORrrY ROUTING Firsi Second i k $A de 2_.11C !
Docket No. 50-461 M99A LV24_ ElG _
Mr. A. Bill Beach nic:tI d (DRS A A? EGA Of Regional Administrator, Region 111 DNMS PAO "
t U S. Nuclear Regulatory Commission OfSAA l l
801 Warrenville Road Lisle, Illinois 605324351 FILE NLv *
Subject:
Update on Westinghouse 4160-Volt -
Citpuit Breakers at Clinton Power Stat ion ;
i i
Dear Mr. Beach:
This letter is an update to previous letters providing rationale that our safety-related circuit breakers will continue to meet operational requicements in light of the recent problems we have identified with Westinghouse 4160-volt circuit breakers at Clinton Power Station. These problems were originally detailed in Illinois Power letter i U 602799 dated July 25,1997. The impact on circuit breaker operability from each of l' these problems is discussed below.
This letter contains the following commitments.
. - Drawings for the undervoltage relay seal in circuit will be revised to clearly show the removal of the internaljumper for the seal in circuit. This will be completed by August 30,1997. (
1
- Maintenance and vendor personnel will review the Westinghouse circuit breaker
-vendor maintenance instructions against plant procedures for consistency. This ,
will_ be completed prior to startup Rom the current outage. -- t
- Maintenance procedures that perform maintenance on ABB 480 volt and
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General electric 4160-volt circuit breakers will be reviewed for consistency'with the vendor instructions. This will completed by August 30,1997. i
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A sample of electrical, mechanical, and control and instmmentation procedures will be reviewed for conformance with vendor instructions. This wi;l be completed by August 1,1998.
Westinghouse 4160 volt safety-related circuit breakers will be inspected dier switching operations to ensure they have operated completely and the charging springs are charged This inspection will be performed on each circuit breaker prior to startup from the current outage. Operating procedures will be revised to initiate this inspection.
The failed safety related Westinghouse circuit breaker will not be placed back in service unless the cause of the failure can be determined.
- An independent circuit breaker expert will assist in determining the cause of the Westinghouse safety related circuit breaker failure.
En11nshauss Sakty Es. lated circuit 11rukstlillute To Trip On July 22,1997, a Westinghouse 4160 volt safety related circuit breaker failed to open when required. Failure of this circuit breaker during plant operation would not have caused the plant to trip offline. Inspection of the circuit breaker while it remained in the cubicle revealed it was in an intermediate position (photographs of the circuit breaker in the intermediate position are enclosed). In this position the circuit breaker is still able to carry electrical load. In order to remove the circuit breaker from the cubicle, it was fully closed and was successibily opened from that position.
The cause of the circuit breaker to operate to the intermediate position could not be conclusively determined. The circuit breaker was inspected onsite by Westinghouse and lilinois Power personnel and dismantled offsite by Cutler llammer (the current manufacturer of the circuit breaker).
Illinois Power analyzed the as found intermediate position of the circuit breaker and determined the possible deficiencies that could cause the circuit breaker to be in this position. The possible deficiencies that would cause the circuit breaker to be in the intermediate position when operating in either the closed or open directions are: bent or misaligned operating linkages, degraded lubricant, binding of operating mechanism, debris preventing circuit breaker operation, weak closing or opening springs, malfunction of the trip latch.
During the offsite di: mantling of the circuit breaker the possible causes of the circuit breaker being in the intermediate position afler a trip signal was received (i.e.
failure in the opening direction.' were investigated. The operating linkages were checked for misalignment or physical damage. No damage of tbse linkages was noted. The puffer tube assembly was found slightly out of alignment. The pufTer tube assembly was readjusted with no affect on circuit breaker operation. The lubricated portions of the operating mechanism were inspected for degraded lubricant. Some dry, sticky lubricant was found on the pivot points for the circuit breaker's contact operating rods. However,
~ . -- - - - _ _ _ - . - - - - - . _ - -- - . - - _ _.
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. U403803 Page 3 l
these pivot points have fairly loose tolerances and still operated freely. Inspection of the circuit breaker bearing lubricant disclosed that the lubricant was in like new condition.
Extensive examination and testing of the operating mechanism was conducted. No binding or abnormal operation was observed. No debris was found during the inspection '
which could have caused the circuit breaker to fail to operate. The spring strength and alignment were checked with no abnormalities noted.
During the offsite dismantling of the circuit breaker the possible causes of the circuit breaker being in the intennediate position afier a close signal (i.e., failure in the closing direction) was also investigated. The operating linkages were checked for misalignment or physical damage. No damage of these linkages was noted. The puffer ,
tube assembly was found slightly out of alignment. The puffer tube assembly was readjusted with no affect on circuit breaker operation. The lubricated portions of the operating mechanism were inspected for degraded lubricant. Some dry, sticky lubricant was found on the pivot points for the circuit breaker's contact operating re,ds. Ilowever, these pivot points have fairly loose tolerances and still operated freely, inspection of the circuit breaker bearing lubricant disclosed that the lubricant was in like-new condition.
Extensive examination and testing of the operating mechanism was conducted. No binding or abnormal operation was observed. No debris was found during the inspection which could have caused the circuit breaker to fail to operate. The spring strength and alignment were checked with no abnormalities noted. The trip latch was inspected for a condition which may have caused it to properly latch when attempting to close the circuit breaker. The inspection revealed that the trip latch was slightly out of specification but we could not make it fail to operate on several subsequent cycles.
During testing of the circuit breaker it was consistently demonstraced that if the circuit breaker was fully open or closed it would operate when required. Illinois Power believes that the circuit breaker was m the intermediate position when it was closed prior to the failure of the circuit breaker to open. A failure of the circuit breaker to completely close can be detected by a visual inspection of the circuit breaker local mechanical position )
indication.
l The vendor analysis of the condition of the circuit breaker afler testing and I
disassembly stated that the previous preventive maintenance activities performed on the circuit breaker were satisfactory to maintain the circuit breaker and should be continued. 1 The vendor also noted that, based on the condition of this circuit breaker, the other )
in service Westinghouse circuit breakers will operate satisfactory on demand. No l abnormalities were detected through tests or inspections that could have caused the circuit breaker to fall to open. (Attached is a copy of the Westinghouse preliminary report).
In order to ensure that circuit breakers at Clinton Power Station will operate when required the Westinghouse 4160-volt safety-related circuit breakers will be inspected aller switching operations and prior to startup from the current outage. This inspection will verify that the circuit breaker has operated completely to the expected position and that the charging springs are fully charged. Operating procedures will be revised to require ;
notification of electrical maintenance to verify the mechanical indication of circuit breaker l
l
. i
. U 602803 Page 4 position and charging springs. Electrical maintenance personnel will conduct, document, and track this inspection in accordar cc with the maintenance work request procedure.
This inspection will continue to be performed by electrical maintenance technicians that have been specifically trained for this inspection. This inspection will be performed until the Westinghouse 4160-volt safety-related circuit breakers have been replaced with new or refurbished circuit breakers. Ah.o, the circuit orcaker that failed on July 22,1997 will not be placed back into senice at Clinton Power Station unless the cause of the failure to open can be determined.
Illinois Power is continuing to pursue the cause of the failure of this circuit breaker. An independent circuit breaker expert will review the failure mode and inspection and test data to assist in cause determination.
As detailed in Illinois Power letter U 602787, dated July 16,1997, Illinois Power plans to have installed new or refurbished Westinghouse 4160 volt safety-related circuit breakers in scr ice in all Division 11 circuit breaker cubicles before the start of a planned mid cycle outage. This mid cycle outage is scheduled for April 1998. Nine of the ten Division I Westinghouse 4160-volt safety related circuit breakers will be replaced with new or refuibished circuit breakers by September 25,1998. The remaining Westinghouse 41t* wit safety related circuit breakers will be replaced with a new or refurbished circuit breaur during the next refueling outage. This outage is scheduled for the spring of 1999.
Hased on the opinion of the circuit breaker vendor that performed the tests and inspections,Illina's Power's review of the circuit breaker's condition, and compensatory actions lilinois Power is taking to ensure proper circuit breaker operation, there is reasonable assurance that the in service safety related Westingbouse 4160-volt circuit breakers wih operate when required.
Failure of Westinnhouse 4160-Volt Circuit Breaker Due to Relav Mis-Wiring in a separate event on July 22,1997, during restoration from an electrical bus outage, two non safety related Westinghouse 4160 volt circuit breakers failed to close on demand. The first failure of a Westinghouse non-safety related circuit breaker to close on demand was because a contact for a seal-in circuit in an undervoltage relay on the electrical bus was mis-wired. This caused the circuit breaker tu not receive the signal to close, it is suspected that the seal-in circuit mis wiring may have been caused by a lack of clarity in the design drawings. Removal of the contact from the scal in circuit can be accomplished by either moving the contact out of the way, so it does not make contact when the relay actuates, or removing an internaljumper in the relay. The drawings for this circuit do not show that the contacts for the scal-in function are enabled. The drawings also slo not describe the method to disable the seal-in function of the relay. The contact for this electrical bus undervoltage relay has been rewired (i.e. jumper removed) so the seal in function is disabled. The applicable drawings will be revised to clearly indicate that
- thejumper should be removed to disable the seal in function for these relays.
A review of the potential for the seal in function of this relay to be enabled on safety-related and non safety related electrical distribution systems was performed. There
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. U-603803 Page$
are seven relays in the safety-related electrical distribution system and forty six in the non-safety related electrical distribution systern that could cause this problem. The results of this review disclosed that the safety related electrical busses have had the internaljumper removed from the undervoltage relay to prevent the seal in ftmetion frora operating. The removal of thisjumper is periodically verified for the safety related relays during the performance of surveillance procedures. Ilowever, these surveillances are not performed on the non safety related distribution system. A maintenance work request has been issued to remove thejumper or verify that no jumper exists on all forty six of the affected non safety related relays. Because the safety-related relays are periodically verifled to not have the seal in circuit activated this condition does not affect the associated safety related Westinghouse circuit breakers.
Eailure ofWes1Lnghoms 4160-Volt Circuit Breaker Due to Latch Check Adjustmeal The cause of the second failure of a non safety related Westinghouse circuit breaker to close was that the contacts on the latch check switch, which provides a permissive to close the circuit breaker, did not make-up as required. This was caused by the latch check switch being out of adjustment. During preparation for the adjustment of the latch check switch it was discovered, with assistance frora Westinghouse personnel, that the method used in the plant procedure to adjust the latch check switch was incorrect.
This correct method was used to check and readjust the switch as necessary on both safety and non safety related circuit breakers. Ilowever, prior to the procedure being revised in April 1997, the instructions in the procedure were correct and consistent with those in the vendor manual. Review of maintenance history showed that only one circuit breaker was checked for proper latch check switch adjustment using the deficient procedure. This circuit breaker was subsequently checked for proper latch check switch adjustment.
Adjustment of this latch check switch was not required.
Because the latch check switch was found out of adjustment on the non safety
- related circuit breaker, and CPS procedures are the same for safety related circuit breakers, all of the safety-related circuit breakers that are needed to actively close to perform their safety function (twenty-two of twenty four in service safety related circuit breakers) have been checked for proper latch check switch adjustment. Those that were not properly adjusted have been corrected. To date, the check of the adjustment of the latch check switches has revealed that twenty of twenty-eight checked (this includes some non-safety related circuit breakers) were out of adjustment. The procedure that checks this adjustment has been revised to reflect the correct method of performing this task and is nonually performed during circuit breaker preventive maintenance activities.
Therefore, since this condition has been corrected on those circuit breakers that are needed to actively close to perform their safety function there is no impact on the ability of these circuit breakers to perform their safety function.
Illinois Power is also taking actions to determine if there are additional problems with maintenance procedures that implement vendor instructions. Maintenance personnel will review the Westinghouse circuit breaker vendor maintenance instructions against the instructions in the maintenance procedure to determine if there are other instances where the circuit breaker maintenance procedures are not consistent with those in the vendor i . -
. i U403803 I Page 6 l manual. Also, an independent contractor will perform the review described above separately from maintenance personnel. Any discrepancies found will be reviewed for potentialimpact on circuit breaker operability. This review will be complete prior to start-up from the current outage. In addition, the procedures that perform maintenance on the AllB 480 volt and General Electric 4160-volt circuit breakers will be reviewed in the same manner to that of the Westinghouse circuit breakers. This review will be complete by August 30,1997. l In an overall effort to improve the quality of maintenance procedures a sample of electrical, mechanical, and control and instrumentation procedures will be reviewed for '
confonnance with vendor instructions. The results of this review will determine the necessity to increase the scope of this review to include all or some additional portion of maintenance procedures based on vendor instructions. The review of the sample of procedures will be complete by August 1,1998.
In summary, in light of our recent corrective actions and plant'ed compensatory measures, Illinois Power has reasonable assurance that our 4160 volt circuit breakers will perform their safety function, if you have any questions about the resolution of these circuit breaker problems please contact me at (217) 935 8881 extension 3400.
Sincerely yours, (D a y."
g ;L,b,f Wayne D. Romberg Assistant Vice President MRS/krk Enclosure ec: J. L Caldwell, USNRC, Region ill G. C. Wright, USNRC, Region til M. A. Ring, USNRC, Region 111 NRC Resident Omce, V 690 Document Control Desk, USNRC Dave Zemel, T-31Z
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Mr. Don Lukach Illinois Power and Light Company Clinton Station ,
P.O. Box 678 Clinton,IL 61727
Subject:
Prelissinary Report DHP Breaker Failure Analysis Illinois Power Co. Clinton Power Plant .
Sleop Order 01YN005B4 Serial #2 De.4r Mr. Lukach:
This is a preliminary failure analysis report. His analysis was conducted in the Greenwood manufacturing plant, Greenwood, South Caroline on Saturday, July 25, 1997.
De scope of the failure analysis was performed following purchase order instructions (P.O. # 705276), General Order # ST30665. N.3.E.D. Attachment #1,90356 Rev. #1.
Psior to beginning the failure analysis, the analysis steps to be performed were reviewed and approved by Illinois power and Cutler.liammer representatives.
The circuit breaker was removed from tbc shipping container and visually inspected.
He breaker appeared to be in good condition and the only noticeable sign the breaker had failed was the blackened open coil. The circuit breaker operations counter indicated
$51 operations. The breaker was exercised mechanically without failure. Main contact gaps were checked and found to be slightly wider than outlined in DlIP circuit breaker 1.L 32 2534B. Main contacu and arching contacts showed minimal wear, contact alignment was good, contact synchronization good and contact penetration good. The puffer adjust,nent was checked and found to be slightly over the recommended setting.
He contacts were not adjusted for this analysis. De mechanism mechanically operated freely which is a good measure of the effectiveness of past preventative maintenance.
The open coil (tip coil) was replaced including the complete trip solenoid assembly.
Tais was done because the open coil could not be removed from the assembly without further damaging the assembly. The close coil was also replaced because it had a black mark on the coil insulation caused when the open coil overheated and open. The breaker was electrically operated,5 times at normal voltage,5 times at maximum voltaBe, S
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times at minimum voltage and 5 this at normal voltage to verify tbc anti pump feature.
All electrical operations were crisp and without failure.
The circuit breaker opening and closing intervals were recorded using a PROGRAMA Circuit Breaker Test Device. Tbc close interval was wit * ' ' in sp- .ific-tion and the trip interval was just out (or stichtly slower) than the specifuden tiraits.
In order to detennine if any mechanical component may have contnbuted to the failure o! the breaku, we changed opening springs, main contact Lick off spnng;, adjusted the main contact hinge bolts and puffer. These replacements and adjustments were cnade in ,
sequence and timing was performed after each event. The results were inconclusive in that tbc effect of each adjustamt of par 1 change had very little effect on the opening or closing speed of the mechanism. The snain contacts we e not adjusted for this anal >ils because the slightly wider main contact gaps would promote quicker releap and contact opening, ne mechanism was dismantled and each part associated upth tbc opening or closing of
^
the main contacts visually inspected. We found that the main shaA bearings were still in very good condition with original factory lubrkation (breaker was manufactured in -
1978). The pint connecting the main shaft to the main contact push rods were removed and found to have some lubricant on the pins, but,the lubrication felt st;cky indicating the lubrication was drying. We found the same condition on the puffer operating lirJc pivot pins. The re maining parts in the snechanism were visually inspected and found to be in very good condition.
Conclusion 1he circutt breaker was operated a total of $1 times without failure. Part replacement and mechanism tear down d.d not provide evidence that would identify one particular cause for the in service failure There is r.o evidence found to indicate a mechanical deficiency or a generic problem with this circuit breaker or with the existing preventative maintenance program. The cause of the breaker failure to open has not boca determined at this time.
We will continue the analysis by mearunnF mechanism parts to determine if any part associated with the opening of the mechanism is out of tolerance or wom to the point where replacement would be recommended. The analysis should be completed by the end of this week with a final repoti a few days later.
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I ItsiB N t j At th's point, based on the prelkainey la@ of this ckcuit breaker, k 1s my opinion the reventet.5 maintenance pwformed on this circuit tweaker was adequate to maintain the propw oparadon of the breaker. Using this circuit breaks as a aanple of one, I believe 'hst the remaining circuit breakers at the Clinton Power Plant. maintained under de same program should provide safe and eNective operation. ,
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No recornmendatlots at this time. Continue to operate under existing procedures and ;
guidelmes.
Sincerely, i
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' Thomat R. Critchlow, Enpirwe, Distribet)Srues :Engiercing ,
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