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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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Ilknois Power Cornpany Chnton Power Station P.o. Box 678 Chnton. IL 61727 Tel 217 9350501 ILLIN9IS P9WER Ef@ 22 y 8E.100 July 22, 1996
)
Docket No. 50-461 10CFR50.90 Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Clinton Power Station Response to Request for AdditionalInformation Related to Proposed Amendment ,
of Facility Operating License No. NPF-62 (LS-95-007) l l
Dear Sir:
l By letter dated December 14,1995 (letter number U-602520), Illinois Power (IP) {
submitted an application for amendment ofthe Clinton Power Station (CPS) Operating License (License No. NPF-62) to incorporate proposed changes to the CPS Tecnnical Specifications (Appendix A). That request proposed changes to eliminate periodic esponse time testing of Analog Trip Modules (ATMs) associated with selected Reactor Protection System (RPS) and Main Steam Line (MSL) isolation instrument channels.
Elimination of periodic response time testing of the pressure transmitter sensors associated with these instrument channels was previously proposed in IP letter U-602376 dated knuary 27,1995 and subsequently approved by the NRC via Amendment No. 98 dated March 9,1995.
The above-noted requests were supported by analyses documented in NEDO-32291, " System Analyses for Elimination of Selected Response Time Testing Requirements," dated January 1994. That Topical Report was developed by the Boiling Water Reactor Owners' Group (BWROG), of which IP is a member, and demonstrated that other periodic tests required by Technical Specifications, such as channel calibrations, channel functional tests and logic system functional tests, are adequate to ensure channel response times remain within acceptable limits. By letter dated December 28,1994, the NRC staff provided their acceptance ofNEDO-32291(-A), subject to cenain conditions, for reference in license amendment submittals.
IP's January 27,1995 request was based directly on NEDO-32291-A while the December 14,1995 request was merely supported by the analyses in the Topical Report.
Extension of the Topical Report analyses to analog trip modules (ATMs) in the RPS and
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9600090185 960722 PDR P
ADOCK 05000461 PDR I 0Ok k\\
. U-602608 Page 2 MSL isolation instnament channels previously addressed in IP's January 27,1995 request prompted a number of questions by the NRC staff reviewer. By letter dated April 17, 1996, the NRC staff transmitted these questions to IP in the form of a request for additional information (RAI). IP's response to each of the questions contained in the RAI i is provided in the attachment to this letter. l As a reminder, due to the resource savings that can be realized by implementation of the proposed Technical Specification changes associated with this request, IP is requesting that this application be reviewed on a schedule sufficient to support the sixth refueling outage which is currently scheduled to begin October 13,1996.
Sincerel ours, Michael W. Ly Director-Licensing DAS/csm Attachment
)
cc: NRC Clinton Licensing Project Manager l NRC Resident Office, V-690 ;
Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety j i
.. l
- q. Attachment to U-602608 LS-95-007 >
Page 1 of 9 By letter dated April 17,1996, the NRC staffrequested additional information related to Illinois Power's (IP's) December 14,1995 request (letter number U-602520) to amend the Operating License for Clinton Power Station (CPS). In its request IP proposed changes to eliminate periodic response time testing of Analog Trip Modules (ATMs) associated with selected Reactor Protection System (RPS) and Main Steam Line (MSL) isolation instrument channels. Elimination of periodic response time testing of the pressure transmitter sensors associated with these instrument channels was previously proposed in IP letter U-602376 dated January 27,1995 and subsequently approved by the NRC via Amendment No. 98 dated March 9,1995. IP's response to each of the questions
- contained in the NRC staffs April 17,1996 request for additional information (RAI) is
- provided below.
1 i Quegipns and Responses
- 1. "[ Provide] a detailed FMEA of the trip unit showing each component's l
failure modes, and the effect that failure mode will have on the performance '
of the trip unit. This should show that for each failure mode which has the possibility of affecting response time, the calibration of the unit is also affected, and the failure will thereby be detected. It will be important to note !
in this analysis that the failur:is such that a mere adjustment of the l calibration is insuihien4 but that replacement or repair of the system will be l required in the event of this failure. If mere adjustment will be sufficient to l mask the problem,it is highly likely that a technician vill not notice a small change in response time of under 5 secods, and only adjust the instrument until it is within calibration, rather than replace the instrument as failing to meet its required response time."
Response: IP's request to eliminate periodic response time testing of ATMs in selected RPS and MSL isolation instrument channels is based on analyses documented in NEDO-32291-A, " System Analyses for Elimination of Selected Response Time Testing Requirements," October 1995. As discussed in Section 4.0 ofNEDO-32291-A and acknowledged in Section 3.0 of the NRC staffs safety evaluation of NEDO-32291(-A), the approach taken by the Boiling Water Reactor Owners' Group (BWROG) in NEDO-31229-A utilized lead plants as the basis for the analyses. After the Technical Specification trip functions were identified for the lead plants, a detailed listing of specific loop components was compiled for each loop.
All components in the affected instmmentation loops which could potentially affect the loop response time were identified. Detailed failure mode evaluations were then conducted for all instrumentation loop components in order to determine whether failures could affect response time. When it was determined that failure modes could affect instrument
~, Attachment to U-602608 LS-95-007 Page 2 of 9 ;
loop response times, the consequences of such failures were evaluated. An analysis was then made to determine whether other surveillance testing ,
would identify these potential response time degradations. As part of the j failure mode evaluations, component experts and vendors were contacted i to assist with and verify the analysis. '
A review of component failure experience was also performed by conducting BWR-specific surveys, and by researching the Nuclear Plant Reliability Data System (NPRDS), NRC Bulletins, NRC Information Notices, and General Electric Company (GE) Service Information Letters (SILs). This review was used to determine if actual response time testing failures could be reasonably detected by surveillance testing other than response time testing.
As discussed in Section 4.0 of NEDO-32291-A, plant-specific verifications were subsequently performed for each of the other panicipating plants following completion of the lead plant baseline response time testing analyses. Component and instrumentation loop differences were identified and dispositioned either by showing that the baseline analyses adequately cover the differences or by conducting additional failure mode and effects analyses.
With respect to the ATMs within the scope ofIP's December 14,1995 request, the applicable lead plant component is the Rosemount 710DU trip unit. (See Figure 1 attached.) Section 7.3 ofNEDO-32291-A summarizes the results of the failure modes analyses for the trip units in general and Appendix D identifies the results of performance history reviews. The results of detailed failure modes analyses for the Rosemount trip units is provided in Section K.l.1 of Appendix K of NEDO-32291-A. The latter section states that "Rosemount Models 510DU/710DU are very fast devices with respect to response time. The nominal response time for this master trip unit is of the order of 2 milliseconds. The master trip unit is designed such that it either trips or does not trip. When the circuitry associated with the master trip unit fails, it does not provide the normal observable trip function indication. Furthermore, there were no failure modes identified that lead to a degraded cor.dition that significantly affects the response time of the trip function." That section concludes that "no failure modes were identified within the master trip unit that could potentially increase its response time above the millisecond range." Section 7.3 of NEDO-32291-A also concludes that "no failure modes that delay the
l l
Attachment to U-602608 LS-95-007 j Page 3 of 9 l normal response time were identified without also affecting calibration or l
causing misoperation detected in functional tests" and " failure modes '
(resistance increase) which can extend the response time, can be detected by loss of DC performance and misoperation during functional tests."
The plant-specific ATMs within the scope ofIP's December 14,1995 request are GE Model 147D805G004 as indicated on Table G-2 of NEDO-32291-A. (See Figure 2 attached.) As shown on Table G-2 (note 3), it was intended that NEDO-32291-A provide a plant-specific failure modes analysis for these ATMs since they are a non-lead plant component.
However, an incorrect reference to Section 5.3.1.2 was provided on Table G-2. The correct reference is Section K.1.2 of Appendix K to NEDO-32291-A. Notwithstanding, Section K.l.2 refers to a GE Model i 184C5988 master trip unit. Thus, it was not clear to the NRC reviewer I
that the GE Model 147D805G004 ATM used at CPS was in fact addressed by the failure modes analyses of NEDO-32291-A. Discussions with GE at ;
the time ofIP's January 27,1995 request, and again at the time ofIP's i December 14 1995 request, confirmed that the GE Model 147D805G004 ATM used at CPS was specifically evaluated by GE during the development of NEDO-32291-A, via the evaluation for the GE Model 184C5988 trip unit contained in Section K.l.2. Notwithstanding, and to avoid any further confusion, IP has performed a direct comparison of the GE Model 147D805G004 ATM used at CPS with the Rosemount Model 710DU trip unit for which a detailed failure modes analysis was performed and documented in NEDO-32291-A for the lead plants. The results of that comparison are presented below.
As discussed in the December 14,1995 request, the RPS and MSL .
isolation logic used at CPS is a two-out-of-four " solid-state" design. As I described in Section 7.2.1.1.4.8 of the CPS Updated Safety Analysis Report, the solid-state logic is automatically tested by the self-test system (STS). Because the STS test pulses are less than 1 millisecond in duratior.,
the response time of the STS-tested portion of the ATM must be less than 1 millisecond or the STS will report a logic fault. In Section 7.2.3.3 of Supplement No. 2 to the CPS Safety Evaluation Report (SSER 2), the NRC found the CPS STS to be acceptable for use in performing surveillance testing required by the Technical Specifications, including response time testing. As shown on Figure 2, some, but not all, of the ATM circuitry is tested by the STS. Any failures of the ATM circuitry within the scope of the STS that can result in a response time degradation above the millisecond range will automatically be detected. Those ATM
' Attachment to U-602608 LS-95-007 Page 4 of 9 components that are not within the scope of the STS are identified on Table 1, attached, along with the corresponding componeats of the Rosemount Model 710DU trip unit.
As can be seen from Table 1 and a comparison of Figures 1 and 2, the only l circuitry that exists in the GE Model 147D805G004 ATMs used at CPS '
that does not also exist in the Rosemount Model 710DU trip units is the gain adjustmerit circuit. This circuit is composed of components (i.e.,
resistors) that are contained in the Rosemount Model 710DU trip units.
CPS has confirmed that the individual components of the GE Model :
147D805G004 ATMs not within the scope of the STS can only fail in the same manner as the corresponding components in the Rosemount Model 710DU trip units. Since the gain adjustment circuit is in series with the remaining ATM input circuits, it has been concluded that there are no additional failure modes for the GE Model 147D805G004 ATMs that were not previously evaluated in NEDO-32291-A for the Rosemount Model 710DU trip units. Therefore, the detailed failure modes analyses documented in Section K.l.1 of Appendix K of NEDO-32291-A and the component failure history evaluations provided in Appendix D ofNEDO-32291-A for the Rosemount Model 710DU trip units are directly applicable and envelope the potential failure modes for the GE Model 147D805G004 l ATMs used at CPS. l Since the noted failure modes analyses do not identify any failure modes that could significantly affect ATM response time without also resuhing in a failure being detected by the STS or routine surveillance, the concerns identified in the remainder of Question 1 are not applicable to CPS. 4
- 2. "Since the response time requirements for the systems in which the trip unit is being used is rapid compared to the 5 second technician awareness limit,
[ provide] an analysis of each accident where this unit is required, and a determination that an additional 5 seconds added to the response time will not introduce a safety problem, and that there is no added increase in the risk of release of radiation to the public."
Response: As discussed above, the ATMs within the scope of this request are associated with selected RPS and MSL isolation instrumentation channels for which periodic response time testing was previously eliminated. That testing was eliminated based on IP's request dated January 27,1995 (letter number U-602376) which was subsequently approved by the NRC via Amendment No. 98 dated March 9,1995. IP's January 27,1995 letter aflirmed the applicability NEDO-32291-A to CPS, including the overall
Attachment i to U-602608 l LS-95-007 Page 5 of 9 :
I conclusion of the realistic safety evaluations presented in Appendix J of i NEDO-32291-A that elimination of periodic response time testing of the selected instmment channels does not result in a significant impact on plant ,
safety. The basis for that conclusion is presented more fully below.
Appendix J of NEDO-32291-A provided a realistic evaluation of the effects of a five-second delay in the response of associated systems and their mitigation functions. As recognized in Section 2.0 of the NRC staffs safety evaluation of NEDO-32291(-A), that evaluation was a " realistic" assessment and was not intended to be a rigorous, bounding analysis. As such, the evaluation was not based on the very conservative assumptions that are required for design basis accident and transient analyses. In addition, a five-second delay in any particular actuation signal would require a delay to occur simultaneously in multiple channels.
With respect to RPS and AfSL isolation instrument channel (s), the logic for the RPS and hiSL isolation instrumentation at CPS is two-out-of-four for each actuation parameter. As a result, the response time of at least three channels for a single parameter would have to be delayed in order to result in a delay in the system response time. As noted in Section 3.0 of the NRC staffs safety evaluation ofNEDO-32291(-A)(and as supported in response to Question 1 above), a response time failure without a corresponding channel failure is unlikely. The possibility of such an undetected failure occurring in two channels for the same parameter at the same time is even more unlikely. IP believes that the simultaneous failure ofyet a third undetected RPS or hfSL isolation channel failure for the same parameter is exceedingly unlikely. This occurrence concurrent with a postulated accident or transient is not credible.
Notwithstanding, the conclusion of Appendix J of NEDO-32291-A and the NRC staffs safety evaluation of NEDO-32291(-A) that there is no significant impact on overall plant safety as a result of the changes ,
proposed in NEDO-32291-A was based on the realistic evaluation of a 5- !
second delay in the instrument channel response time. Sections 3.0 and 4.0 l of the NRC staffs safety evaluation of NEDO-32291(-A) specifically state l that this " includes the selected RPS and hiSIV actuation features which l have overall Technical Specification response time requirements of 0.33 to 2 seconds." This evaluation was performed for automatic actuation based on the specific parameters identified in NEDO-32291-A. Because the instrument channels within the scope ofIP's December 12,1995 request are within the scope ofIP's January 27,1995 request, NEDO-32291-A, and the NRC staffs safety evaluation of NEDO-32291(-A), the above l
4
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{ Attachment 9
to U-602608 LS-95-007 Page 6 of 9 f
conclusion remains valid whether the channel delay is caused by a delay in l the transmitter response, ATM response, or a combination of the I j transmitter and ATM. Further, as stated in IP's December 12,1995 4 request, the channel response being monitored at CPS during calibration ,
includes the ATM responsc in addition to the transmitter response. l
{ Based on the above, IP has concluded that the proposed elimination of - .
1' periodic response time testing of the selected ATMs does not result in a significant impect on plant safety, consistent with the overall conclusions of .
l Appendix J of NEDO-32291-A.
- j. I I
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Page 7 of 9 l Table 1 Comparison ofInput Circuitry for GE and Rosemount Trin Units (circuitryjust prior to isolation amplifier)
Number Rosemount 710DU GE 147D8505 1 Transmitter Excitation Filter L1,C25,F1,R47,C28,L4 F3,R150,C51,L3 2 Transmitter Return Filter L5,C29 L4,C50 3 Calibration Relay K1 K1 4 Precision Dropping Resistors R48,R49 R172,R173 1 5 Low Pass Input Filter R50,R52,C36,C16 R170,R171,C56,C57 6 Gain Adjustment Circuit N/A R15,R28 i
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