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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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llhnois Power Company Chnton Power Sta: ion P.O. Box 678
. Chnton, IL 61727 Tel 217 935-8881 R u-602255 4F.190 June 5,1997 Docket No. 50-461 PRIORITY ROUflNG l.
First { Second Mr. A. Bill Beach RA RC Regional Administrator, Region III DRA ElC U. S. Nuclear Regulatory Commission SGA, gfj / jap 801 Warrenville Road gg pgo 04 Lisle, Illinois 60532-4351 DNMS PAO (
DRMA
Subject:
Clinton Power Station Response to Circuit Breaker Ouestions pi g k N _
Dear Mr. Beach:
On May 21,1997, Illinois Power personnel discussed with members ofyour staff plans to assess the adequacy of various voltage circuit breakers at CPS to perform their function. Subsequent to that meeting a list of questions from members of your staff were proposed to Illinois Power relating to this issue. The question and a response to the question that was asked is provided in an attachment to this letter.
If you would like to discuss this matter with me funher please contact me at .
(217) 935-8881 extension 3178.
incerely yours, a
0 Richar P ares Assistant to the Vice President MRS/kk t
cc: James L. Caldwell, USNRC, Region III Geoffrey C. Wright, USNRC, Region III Mark Ring, USNRC, Region III i NRC Senior Resident l Dave Zemel, T-31Z 9706170297 970605 llMMgj\,\(({\,\h\((hkk.kk PDR ADOCK 05000461 Ilum u, m ,
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U .
i Attachment to '
U-602755
- Page 1 of 7 I
' Answers to Circuit Breaker Questions
- 1. Critical non-safety related circuit breakers - What is their impact on safety system j operability? Are they important to safety or to operation? l Response: Critical non-safety related circuit breakers is a term used by the CPS
~ Breaker Team for circuit breakers that Illinois Power has deemed important to operating the plant. These circuit breakers are not required for the operation of safety related equipment or do they affect the safe operation of the plant. ..
- 2. 'No 4160 volt Westinghouse or GE circuit breakers are being refurbished prior to ,
l startup. How does this affect our position on reasonable assurance?. ;
L, Response: One safety related GE circuit breaker was replaced with a fully refurbished circuit breaker and one GE circuit breaker had its operating mechanism i i refurbished during this refuelir.g outage. One safety related Westinghouse circuit l breaker was refurbished in 1995. Prior to startup all five safety related GE circuit ;
! breakers are undergoing'a comprehensive inspection and testing plan based on - !
l industry and vendor information. All inservice safety related Westinghouse circuit j breakers, excluding one previously refurbished and one cannibalized spare, will be l subjected to a range of testing and inspections that was also developed from .l industry and vendor information. The testing and inspections as well ;
- refurbishment, as applicable, will contribute to determining the answer to i reasonable assurance of circuit breaker material condition. !
i
- 3. During the Engineering and Technical Support Inspection, Inspection Report 97003, information was revealed regarding undocumented circuit breaker failures.
a) Is it accurate that there were undocumented breaker failures?
b) Has this issue been addressed? This wouli. inclade Maintenance involvement in failures to close.
c) Can CPS create a goad equipment history to shew i: reliability factor? If possible, please provide the equipment history that was mited.
Response
a) Yes. ,
b) Yes. Operations has incorporated the requirements to document on a l Condition Report any failures of a circuit breaker to perforn. on its first attempt, 1 l
and to obtain engineering and maintenance imolvenant prie.r to attempting to- )
- operate the circuit breaker a second time unless it is an emergency situation into a j training seminar. This seminar is currently beiag presented t'a plant operators in a
- self study format and is expected to be complne prior to startup.
l c) No. CPS cannot recreate equipment history based on undocumented failures. ;
1 4
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1 Attachment to U-602755 Page 2 of 7 4 What is the basis for the 100 msee timing criteria for circuit breaker closure and :
trip testing?
1 l Resoonse: The 100 msec criteria was chosen as a value based on nominal voltage timing as extrapolated to minimum voltage testing. Westinghouse specifies time '
ranges for mechanical closing and opening performed at nominal (nameplate)
L control voltage (125 VDC for CPS). However, they do not provide time value i
! specifications at lower voltages. 100 msec is approximately 85% of the upper ,
close time limit for 4.16 KV breakers and approximately 67% of the upper time i
. limit for 6.9 KV breakers if tested at 125 VDC. 100 msec is also approximately double the upper open time limit if tested at 125 VDC. ;
l CPS records response time values during minimum voltage tests (90 VDC Close, l 70 VDC open). The lower the voltage used, the longer the response time should be. Thus, testing mechanical closing at 90 VDC (72% of 125 VDC) or mechanical l opening at 70 VDC (56% of 125 VDC) will result in longer times than if performed at nominal voltage (125 VDC). The 100 msec is within the nominal voltage band, thus is conservative for low voltage closing testing. The 100 msec is ;
a postulated value for low voltage opening timing, based on the value of voltage -
(70 VDC) used (i.e. - while testing at approximately one half the nominal voltage ,
it is reasonable to expect close to double the nominal time value). The 100 msec i value is also a trigger point for CPS maintenance to contact Engineering for analysis. All time values are recorded and trended. ,
i CPS GE 4.16 KV breakers have similar design specifications to that of Westinghouse, thus the 100 msec criteria that is reasonable to Westinghouse circuit breakers can be applied to the GE circuit breakers as well From testing performed on Westinghouse circuit breakers so far, typical 90 VDC j closing times have been in the 75-90 msec range and 70 VDC opening times have ,
been in the 50-63 msec range.
Also, it is postulated that if the mechanism was degraded to the point that I
functionality was is question, either the timing values would be orders of magnitude larger than the 100 msee or the breaker mechanism would not close or !
open. This was substantiated by testing.
i 5. For 480V ABB circuit breakers- What post-refurbishment testing is being l L performed?
Response: All post-refurbishment testing at ABB is performed in accordance with their proprietary Quality Assurance Procedures (QAP) and CPS's Refurbishment Specification. Upon arrival at CPS and prior to plant installation all 480V ABB
, i 4
Attachment to U 602755 Page 3 of 7 ;
I circuit breakers are required to pass CPS receipt inspection / testing. Specifically, j CPS checks 24 attributes of the breaker to primarily verify that the vendor i performed refurbishment as required and th: shipping damage did not occur. The ,
24 items include performing trip device testing, ductoring, meggering, wiring l configuration checks, tripper bar movement and general inspections such as wiring integrity, escutcheon plate gasket installation, arc chutes, contacts, hardware, etc..
- 6. In 480V ABB circuit breakers (Perry Issue) wiring problems were discovered on ;
returned refurbished circuit breakers (current transformers?). Would post J refurbishment testing that CPS performs on circuit breakers have identified this -
problem?
Response: Post-refurbishment testing performed at CPS would probably not identify this problem but the 10 CFR Part 21 program would have alerted CPS to this condition. ABB issued a 10 CFR Part 21 notification on this issue on 4/24/97 (received by CPS on 5/19/97). CPS is currently evaluating this information in accordance with our 10 CFR Part 21 notification. The refurbishment vendor for CPS's 480V ABB breakers (ABB, Houston, TX) is currently inspecting / testing the CPS breakers in accordance with ABB procedures that include tests to detect this problem.
- 7. Some ABB refurbishments had a trip device change out. Did this change out of trip devices occur at CPS. What actions have been taken regarding this issue?
Post Mod Testing?
Response: CPS believes the background for this question is the industry issue concerning the change-out of older oil-dashpot (OD) trip devices with solid state trip devices during ABB refurbishments. Original units supplied to CPS were all ,
.. of the solid state type and therefore, a replacement of the oil-dashpot trip device to ;
the new solid state type was not necessary. For all present and future work, trip ;
devices that are found to not meet acceptance criteria in accordance with ABB literature are either replaced or refurbished. I I
- 8. For the remaining safety related 480V circuit breakers that have not been I l refurbished. What is the schedule for refurbishment? On-line or not?
Response: There are 13 safety related ABB 480 volt circuit breakers at CPS that have yet to be refurbished. All 13 will either be tested or replaced with refurbished circuit breakers prior to startup. Those that are not refurbished prior to startup will be refbibished prior to the end of the next refueling outage. This is an increase of the nu;nber of circuit breakers that were previously planned to be tested or l refurbished during this outage. This increase in scope is based on the results of
! test data for the ABB 480 volt circuit breakers Some of these breakers will be l
-. . . - ..- - -. - . - . ~ . - . . . - . . - - . - - . - - . _ . - . . ~ . . ~ . ~ . - -.-. - -
e q ^. Attachment to i U-602755 I Page 4 of 7 4
- _ replaced with refurbished circuit breakers when the plant is on-line, others will require a bus outage with the plant off-line.
i 9. What is the schedule for the remaining GE 4160V circuit breakers?
i Response: CPS has five GE 4160V circuit breakers. Three of the circuit breakers
- have passed a comprehensive inspection n test procedure. Two of the circuit 2
breakers did not meet the criteria. One c .ne circuit breakers that did not pass the
? inspection and test procedure was replacea with a fully refurbished circuit breaker I
, and the other that did not pass was replaced with a circuit breaker that had its i operating mechanism refurbished. Current plans are that all five installed GE circuit breakers will have been fully refurbished within six months of startup.-
i 10. GE inspection items 9 What is the basis for the acceptance criteria of <1 ohm i switch contact resistance?
1 l Response: The <1 ohm contact resistance check for the switches is based on j ensuring that the voltage drop across the switch under the full range of voltages
] will not impact the voltage that is applied to circuit breaker components such as the close coil or charging motor, or auxiliary control circuit y, thus allowing
- - proper operation of the circuit breaker.
i
!' 11. Item 46 discusses high voltage testing at 1000 volts. We (NRC) are used to seeing
- this testing performed at 2500 volts. What is the rationale for 1000 volts?
} Response: CPS standard practice is to megger at 500VDC or 1000VDC as
! governed by the circuitry or test equipment limitations. 1000 volt meggers provide
! adequate assurance in identifying low resistance conditions that would indicate
- insulation degradation. Any low readings are investigated. Note that megger i results are trended.
i 12. Item 47 - with respect to the performance of a ductor test. What is the amperage of the'ductor being used?
4 Response: A 10 amp ductor is used for this test.
l l- 13. Hi Pot test - Why did we not do one? !
l Response: High potential (Hi-Pot) testing is considered a potentially destructive test and is neither a CPS standard practice, nor a vendor recommended routine j j test. Currently only the Westinghouse DVP vacuum bottles arc Hi-Pot tested as ;
[ specified by the vendors instructions. This test is conducted in this specific !
- application to ensure vacuum integrity. !
d
- - , v. , ,m# ,, , -r-.3- ,,---+- .-- - - ,.. -
. Attachment to U-602755 Page 5 of 7
- 14. Westinghouse 4160V - Illinois Power is purchasing 11 from GPU. Are they being bought safety or commercial and then dedicated?
Response: Illinois Power is purchasing eleven additional Westinghouse 4160 volt circuit breakers. The decision as to whether they will be purchased safety related of purchased commercial and then dedicated has not been made.
- 15. Schedule for repbceraent of 11 safety-related Westinghouse.
Response: One Division of Westinghouse DHP circuit breakers will be replaced with new or refurbished circuit breakers prior to the end of the next refueling outage. Breakers removed will be refurbished and used to replace other divisional circuit breakers until all divisional circuit breakers are refurbished. This will be complete prior to the end of the following refueling outage.
- 16. There is a significant difference between the Westinghouse and the GE checklists.
Why the big difference between the two types of circuit breakers? Why aren't we doing more on Westinghouse circuit breakers?
Response: GE breakers have a poor industry reputation with over 100 known industry documents that describe concerns of the breakers. Westinghouse breakers have only a few. CPS has little equipment experience and history on GE breakers.
The CPS experience with Westinghouse breakers is substantial due to the population and total number of preventive maintenance tasks that have been performed. Thus, the Westinghouse and the GE checklists are commensurate with vast differences in available data for each circuit breaker type, and therefore, will provide essential data for the assessment ofissues and concerns specific to each breaker manufacturer.
- 17. la and 2a (Westinghouse 4160V) - Are they being done at 70V or 90V, respectively? It is clear for Ib and 2b. It is not clear for steps la and 2a. .
l Response: CPS Inspection Plan Item la (Closing at minimum voltage, 90 VDC) and Ib (Record time during closing at minimum voltage) are performed simultaneously. Likewise, CPS Inspection Plan Item 2a (Opening at minimum voltage, 70 VDC) and 2b (Record time during opening at minimum voltage) are also performed simultaneously.
l
- 18. Page 4, Items 6 and 7 - Criteria for inspecting others in failure.
- 7. failure of any
- 6. failure of 8 Does this mean all or any?
(Need clarification on what is meant)
p _ .__ .
.- Attachment to
- j. U-602755 Page 6 of 7 i
j i '
i t
4 Response: The original plan was to test a sample of 8 circuit breakers. The ;
! number of breakers that will be tested has been expanded to include all j
- Westinghouse safety related circuit breakers. Since all safety related circuit
breakers will be tested, Items 6 and 7 of the General Inspection Criteria no longer l apply. l l
l j~ 19. Item 6 - same as the 1 ohm resistance check. What is thejustification? l l
! Response: The <10 contact resistance check for the motor cut-off switch is based on ensuring that the voltage dropped across the switch under the full range of ;
- voltages will not impact the voltage that is applied to the close coil or charging -
l
, motor, thus allowing proper operation of the circuit breaker. For example, if the ;
bus voltage was 95V which is lower than the postulated minimum battery voltage j j at the bus, the resistance of the switch could be as high as 1.90 (i.e. 5 volt drop) j
- with a 34Q (coil resistance value from Westinghouse) close coil to ensure that - ;
i 90V (minimum nameplate voltage) was present at the coil. Ifbus voltage is i higher, the allowable switch resistance also increases (13.20 allowable at nominal !
125Vdc bus voltage). This assures that adequate voltage is present at the coilif
~
switch resistance is < 10. Therefore, the <10 criteria is conservative. Other .;
j utilities contacted also use the 10 criteria. !
4
- 20. What does item 12 in the General Inspection Criteria mean? Does it require CPS to inspect "all" safety-related circuit breakers?
4 Resoonse: Yes. If during inspections on Westinghouse breakers, Inspection Item 5 (Slow Close Checks) fail then all safety related Westinghouse breakers are required to be tested / inspected per Inspection Item 1a, Ib, 2a, 2b, (Low voltage tests) and Item 5 (Slow Close Checks).
- 21. Specific to Westinghouse circuit breakers; are megger and ductor testing being ;
conducted? If this is not being performed, why is it not being performed?
^
Response: CPS has little equipment experience and history on GE breakers. !
However, the CPS experience with Westinghouse breakers is substantial due to the l population and total number of preventive maintenance tasks that have been performed.
Megger and Ductor testing is a normal part of the CPS preventive maintenance ,
tasks for both breakers. Due to the CPS experience on Westinghouse circuit breakers it was not deemed necessary to be included in the Westinghouse ;
inspection plan. Conversely, it was considered necessary to assess GE circuit :
breaker performance using megger and ductor testing since CPS has little experience and history on GE circuit breakers.
- 4 '.W W q NY
9
. Attachment to U-602755 Page 7 of 7 4
- 22. Westinghouse 6.9 kV - What inspection and testing is done after rework of these breakers. (DVP?)
Response: ARer refurbishment and subsequent replacement of the contact roller .
assemblies for the vacuum bottles on the CPS DVP breakers several inspections and tests were performed. These tests included checking contact wear gap,
- vacuum integrity, contact resistance and, mechanical timing tests. As a conservative measure several of the DHP circuit breaker inspection plan items were applied to the DVP circuit breakers to provide additional assurance of .'
satisfactory material condition.
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