|
---|
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
[Table view] |
Text
.
, . . . . - -- --~ . - . - - - - -~ .- - + ~ - - - -
F .
..A 4
- n ilhnois Power Company l Chnton Power Station !
P.o. Box 678 i Chnton, IL 61727 Tel 217 935-8881 ILLIN915 u-6026t3 P6MR u7.%( 07. 24 )Lp i 8E.100a L
l- . Docket No. 50-461 10CFR50.90 l l Document Control Desk l Nuclear Regulatory Commission l Washington, D.C. 20555 l
Subject:
Clinton Power Station Response to Request for AdditionalInformation Related to Proposed Amendment i
, of Facility Operating License No. NPF-62 (LS-94-013) I
Dear Sir:
I By letter dated February 22,1996 (letter number U-602554), Illinois Power (IP)
' Company proposed an amendment to the Clinton Power Station (CPS) Operating License ;
(License No. NPF-62) to revise the setpoint for the degraded voltage protection I l instrumentation and modify or delete other Loss of Power Instrumentation Technical l Specification (TS) requirements. Additionally, changes were proposed to the minimum l~
required diesel generator voltage specified for certain diesel generator surveillances.
i To support review ofIP's application for amendment, the NRC has requested (via NRC letter dated June 13,1996)IP to provide additionalinformation. Attachment I to
'this letter provides IP's response to each of the questions contained in the NRC's request.
Also please find Attachment 2, IP Calculation 19-AN-19.
l -It should be noted that proposed modifications associated with this request cannot be implemented until NRC approval of the proposed TS changes. Because these modifications will enhance the safety of CPS with regard to the degraded voltage protection, IP is requesting that the February 22,1996 application for amendment, as supported by this letter, continue to be reviewed on a schedule sufficient to support implementation of these modifications beginning during the sixth refueling outage, currently scheduled to begin October 13,1996.
l Sincerely yours, l
9608010006 960001 l PDR ADOCK 05000461 M b. EkX.
P PDR
! Michael .L on /
Director-Licensing dCD/ '/ I
.- AJP/csm
.. -. . - . . . - . . . . . . _ . . . . . ~ . _ . . . . - _ . . . _ . . - . ~ . _ , .
U-602613 Page 2
- Attachments cc: NRC Clinton Licensing Project Manager NRC Resident Office, V-690 Regional Administrator, Region III, USNRC Illinois Department ofNuclear Safety i
4.
l 1
I Attachment 1 to U-602613 LS-94-013 i Page1 of9 l l
By letter dated June 3,1996, the NRC staff requested additional information related to Illinois Power's (IP's) February 22,1996 request to amend the Operating License for Clinton Power Station (CPS). IP's request involved proposed changes to the Technical
. Specification (TS) requirements related to the degraded voltage protection system at CPS.
IP's response to each of the NRC's questions is provided below.
- 1. "With regard to the proposed deletion of the channel check requirement every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, are there alarms in the control room or elsewhere that would prevent a single undervoltage relay, which has failed to the tripped state, from going undetected for a significant length of time (as much as the 31 day frequency between channel functional tests)? If there are no such alarms, please discuss the significance of a single relay being in an undetected tripped state for up to 31 days."
Response: There is no indication of Loss of Power (LOP) degraded voltage relay trip status in the Main Control Room (MCR) for the individual relays.
However, if both relays for a division trip and the timer times out, the automatic actuation sequence is initiated which will result in a diesel generator (DG) start and breaker actuation. These actions would generate '
an alarm in the MCR. There is however, local indication of trip status (i.e.,
a flag) for each individual degraded voltage relay at the electrical panel where the relay is installed. There is no TS surveillance requirement for ,
checking these trip flags. However, these flags are routinely checked by operators each shift during operator rounds as currently required by plant procedures.
- The significance of a single relay being in an undetected tripped state is that i the "two-out-of-two" trip logic will become a "one-out-of-one" trip logic. )
The LOP degraded voltage relays have been chosen for high reliability. As l
a result, the probability of relay failure in a 31-day period is small. The l probability of two relays failing would equal the square of the probability for one relay failure. Because the failure rate for one relay is low, the probability of the second relay in the same trip system failing during this time period is very low. In addition, the failure of a single relay will neither cause an inadvertent trip to occur nor prevent a valid trip from occurring.
As a result, IP has concluded that elimination of the 31-day channel check requirement is acceptable.
- 2. "The submittal indicates that the setpoint proposed to be specified for the degraded voltage function was determined using a setpoint methodology which has been approved by the NRC. Identify the staffs evaluation which .
approved this methodology. Also, provide the setpoint calculations used to determine the analytical limits, trip setpoints, and allowable values."
I
4 a
Attachment 1 i to U-602613 LS-94-013
- Page 2 0f 9 j Response
- The setpoints were calculated and are shown in IP calculation 19-AN-19 contained in Attachment 2 to this letter. The calculation methodology
, utilized by CPS for calculation 19-AN-19 is delineated in Nuclear Station i Engineering Department Standard CI-01.00, " Instrumentation Setpoint
! Calculation Methodology." This standard is based on ISA S67.04, j "Setpoints for Nuclear Safety-Related Instrumentation," and NEDC-31336, j " General Electric Improved Setpoint Methodology," October 1986. The j methodology employed within these documents was reviewed by the NRC
] as documented in Regulatory Guide 1.105 and NRC letter from Bruce A.
, Boger, Director Division of Reactor Controls and Human Factors to
, Robert A. Pinelli of the Boiling Water Reactor Owner's Group dated November 6,1995, respectively.
j 3. "The proposed technical specifications indicate an allowable degraded i voltage value for Divisions 1 & 2 (3876V) that is identical to Division 3.
l Because the Division 3 distribution system is rubstantially different from i Divisions 1 & 2, please verify that this value is correct."
i I Response: While the Division III distribution system is different from Division I and
=
II, the present and the proposeo setpoint were both determined by a j calculation that is based on the worst case with all divisions considered.
! The current setpoint for the Division III degraded voltage trip function is
- different solely due to a different type of relay for the Division III degraded l voltage trip function from the relays that are currently used for the Division f I and Division II degraded voltage trip function.
The proposed TS change will support planned modifications to the degraded voltage instrumentation. After installation of the planned plant modifications, the relay types for the degraded voltage trip function will be identical for all three divisions. Since the Division III channel will no longer be different from Division I and Division II, all three divisions have the same proposed allowable value.
- 4. "The submittai indicates that the degraded voltage relay reset value is the appropriate value to specify in the Technical Specifications. The submittal further states that the drop-out voltage that is associated with these relays are more appropriately specified in the Operational Requirements Manual (ORM) and controlled under 10CFR50.59. It is the staffs view that the allowable value ofhgih. the relay reset point and dropout point should be specified in the Technical Specifications. A correct reset point is necessary to ensure the safety buses will not separate from the offsite system during sequencing of safety loads when the offsite voltages are sufficient to support the loads. A correct dropout point is necessary to ensure the safety buses will
Attachment 1 to U-602613 LS-94-013 Page 3 of 9 l separate from the offsite system when the voltages are insufficient to support l the safety loads. Therefore, please change the technical specification l submittal to include both a lower bound (allowable value for the dropout point) and upper bound (allowable value for the reset point)."
- Response
- The approved configuration for the CPS offsite power source is described l
within Section 8 of the CPS Safety Evaluation Report (NUREG-0853) and Supplement 7 (SSER 7). These documents and Chapter 8 of the Updated Safety Analysis Report (USAR) contain the CPS commitments regarding offsite power and degraded voltage protection. The current requirements l for the degraded voltage trip function and the associated setpoints were established based on NRC requirements stated in Standard Review Plan (NUREG-0800) Section 8.2. Those requirements ensure proper operation of equipment in response to postulated accidents (i.e., LOCA). CPS TS 3.3.8.1 currently specifies the allowable values for the degraded voltage trip functions. The CPS-specific configuration has been reviewed and accepted by the NRC (reference SSER 7 Section 8) as meeting the requirements in effect at the time of receiving an Operating License for CPS.
In support of the above requirements, analyses have been performed which demonstrate that all safety-related equipment receives adequate voltage at i the second-level undervoltage relay reset point to start under accident I conditions (i.e., under LOCA block-start conditions). These analyses also demonstrate that all safety-related equipment receives adequate voltage at the second-level undervoltage relay trip point to continue to operate following an accident. These requirements fulfill the current Licensing Bases for CPS. Further, analyses have been performed which demonstrate that all safety-related equipment will start and continue to operate at the minimum expected offsite voltage level under accident conditions.
As explained on page 4 of Attachment 2 ofIP's February 22,1996 submittal (letter U-602554), the current setting for the relay reset is based on a LOCA block start scenario. The original design is such that the drop-out and the reset values are not independently adjustable and thus, only one setpoint value was specified in the TS. The TS Table 3.3.8.1-1 item 1.c and 2.c allowable value is currently specified as 2 3762 V and s 3832 V.
These two values represent the high and low limit for the allowable value for the relay drop-out (i.e., trip) point only. Since the difference between
- the relay drop-out and the relay reset are constant, the reset setpoint was specified by specifying only the setpoint for the drop-out in the TS.
l
f r . .
, Attachment 1 to U-602613 l LS-94-013 I Page 4 of 9 l After implementation of planned modifications to replace the degraded l
! voltage relays, IP will have the capability to adjust the degraded voltage l l drop-out voltage independent of the reset voltage. The characteristics of I' l the voltage decrease during starting oflarge AC motors following a postulated accident is such that the setpoint of the relay drop-out is not critical for ensuring the timer for the degraded voltage trip is initiated.
)
l What is critical is the voltage to which the bus recovers following the block-start voltage transient. This voltage must be high enough to ensure safety loads will start and continue to run post-LOCA. Thus, the proposed TS change requires the degraded voltage relay reset allowable value to be 2 3876 volts.
As stated in your question, a correct relay drop-out setting is necessary to ensure the safety buses will separate from the offsite power system when ,
the voltages are insufficient to support the safety loads. . As stated above, I the characteristics of the voltage decrease during starting oflarge AC l motors following a postulated accident is such that the setpoint of the relay drop-out is not critical for ensuring the timer for the degraded voltage trip l is initiated (i.e., a drop-out setpoint which is adequate for equipment safety will be sufficient to ensure initiation of the timing sequence during a LOCA block start scenario) . Thus, the minimum drop-out voltage has been 1 chosen to ensure continued operation of safety loads. Because, as discussed above, recovery of adequate bus voltage is ensured by the l degraded voltage relay reset setpoint, the minimum relay drop-out voltage l j is not part of the current Licensing Basis for CPS.
, - It should also be noted that, in accordance with the General Design Criteria l of 10CFR50, Appendix A, accidents are postulated to occur "with or without offsite power available." Thus, demonstrating proper equipment operation with offsite power available is met by demonstrating proper equipment operation with offsite power at the minimum expected offsite i
voltage. Accidents are not required to be postulated to occur with offsite l
voltage below the minimum expected offsite voltage. Thus, inclusion of protection requirements to mitigate the consequences of accidents with
, offsite voltage below the minimum expected offsite voltage does not meet j the criteria of 10CFR50.36(c)(2)(ii) for inclusion in TS [i.e., the function is not (1) installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant
[ pressure boundary; (2) a process variable, design feature, or operating
. restriction that is an initial condition of a design basis accident or transient I analysis that either assumes the failure of or presents a challenge to the j integrity of a fission product barrier; (3) a structure, system, or component I
i i
f i 1 . .
. Attachment 1 j to U-602613 l
LS-94-013 '
Page 5 of 9 that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; nor (4) a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.] Therefore, to allow for changes to the relay drop-out setpoint as required by changes in equipment load characteristics and when required because of changes in the minimum expected offsite voltage conditions, the ;
l minimum relay drop-out voltage will be specified within the ORM and j controlled under 10CFR50.59.
l
- 5. "The submittal states that the allowable value is specified to provide j adequate safety margin from the analyticallimit. Provide the amount of
( safety margin between the lower bound analytical limit (generally based on >
l the most limiting steady-state or transient equipment terminal voltage) and j the allowable value. Provide the amount of safety margin between the upper l l
bound analyticallimit (generally based on the minimum expected switchyard i operating voltage) and the allowable value. Identify what the analytical
- limits are based upon and where they are used in the setpoint calculations
! provided in response to question 2 above."
r Resoonse: The lowe- Sound analytical limit at the 4 kV level is 3.870 kV and is high l l enough to ensure proper starting of safety loads folicwing a postulated l accident. This is the lower bound analytical limit used for calculating the i relay reset setpoint. The proposed Allowable Value is 3.876 kV and the l safety margin is the difference which is 6 volts. l The upper bound analytical limit at the 4 kV level is 3.938 kV and is based l on the minimum expected offsite voltage levels following a postulated l l accident. This is the upper bound analytical limit used for calculating the l relay reset setpoint. Since the degraded voltage trip timer is started based l
on the relay drop-out setting which is well below the minimum expected offsite voltage, there is not a Technical Specification Allowable Value specified for the degraded voltage relay drop-out point. The maximum reset calibration limit is chosen to povide a 95 percent confidence level that there will not be a spurious transfer due to offsite voltage being at or above the minimum expected offsite voltage following a postulated accident. The maximum reset calibration limit is 3.890 kV. The safety margin is the difference between'the upper bound analytical limit, 3.938 kV, and the maximum pick-up calibration limit, 3.890 kV, which is 48 volts. For further discussion, please see Calculation 19-AN-19 contained in Attachment 2 to this letter, beginning at " Evaluation" on page 13.
l
. Attachment 1 to U-602613 LS-94-013 Page 6 of 9
- 6. "The submittal also states that the calibration setpoints are determined considering calibration errors and anticipated drift. Besides calibration errors and drift, were other uncertainties considered; such as PT accuracy, repeatability, temperature effect, power supply variation, and test equipment accuracy?"
Response: Nuclear Station Engineering Department Engineering Standard CI-01.00,
" Instrument Setpoint Calculation Methodology," requires that the various conditions under which an instrument may operate be taken into consideration and evaluated when establishing instrument setpoints.
Calculation 19-AN-19, Rev. 2, Volume C considered the following as potential contributing errors when establishing the degraded voltage relay setpoints:-
e Relay repeatability e Relay repeatability with respect to temperature e Relay repeatability with respect to the control voltage e Relay drift with time e Radiation effects
- Seismic effects e RFI effects e Calibration instrument and calibration loop accuracies e Potential transformer accuracy, including the impacts of change in PT burden See Section I, " Inputs," of Calculation 19-AN-19 contained in Attachment 2 to this letter for more information.
- 7. "Because the degraded voltage setpoints themselves are not specified in the Technical Specifications, discuss how the trip setpoints and changes to the setpoints are controlled by plant procedures."
Response: In the same manner as all TS-required instruments with allowable values specified in the TS, the degraded voltage relay nominal trip setpoints will be specified in the CPS Operational Requirements Manual (ORM).
Contrei f these degraded voltage setpoints will be in accordance with the design control procedures. Presently, the method for controlling setpoints '
included in the ORM requires changes to be submitted, approved and processed in accordance with the ORM revision procedurr, CPS No.
1038.03, " Revising the USAR and ORM." All changes a c required to be evaluated in accordance with 10CFR50.59. The setpoints recorded in the I
.A
I
., Attachment 1 I to U-602613 j l LS-94-013 Page 7 of 9 ORM must also agree with the appropriate design documents, including the l trip setpoint calculations. As stated above, design documents are !
controlled in accordance with design control procedures and calculations 1 are prepared, reviewed, and approved in accordance with design control l procedures
- 8. "The Technical Specifications require a montbly channel functional test to be performed on the Loss of Power Instrumentation to verify operability. If the results of a monthly channel functional test should indicate that a degraded voltage relay's actual setpoint is within the allowable value but very near to it; what action,if any, would be taken on that specific relay? Would the relay's actual setpoint be adjusted back to its specified nominal setpoint?"
Rgsponse The following response is provided with the understanding that "a degraded voltage relay's actual setpoint" refers to the "as-found" data obtained during instrument calibration. In accordance with the standard TS requirements for Channel Functional Tests, the monthly Channel Functional Test for the degraded voltage instmmentation does not determine the as-found setting. The as-found setting is required to be determined only
, during Channel Calibrations which are at 18-month intervals. The as-found setting for the degraded voltage instrumentation must fall within the calibration limit as defined within the applicable surveillance procedure.
If an as-found setting is found outside the calibration limit, then the instrument setting must be adjusted in accordance with the applicable procedure so as to be within the calibration limit. However, if the as-found setting is within calibration limits, then no adjustment is required. The !
calibration limit takes into account appropriate drift characteristics and i other possible sources of error so that equipment drift will not result in exceeding the allowable value in the interval between calibrations.
- 9. " Discuss the coordination of downstream breakers, thermal overload devices, and fuses during degraded voltage conditions prior to the offsite source !
breakers being opened by the degraded voltage relays. Also discuss the coordination between downstream overcurrent devices and the degraded voltage relays during fault conditions to ensure faults are not transferred to other sources."
Response: Regarding the coordination of downstream breakers, thermal overload devices, and fuses during degraded voltage conditions prior to the offsite source breakers being opened by the degraded voltage relays, CPS has j specifically evaluated the relaying associated with the 4.160 kV Emergency Safety Feature (ESP) motors during the LOCA block-start scenario.
i Assuming the worst case is a transient where the block-start voltage i
- Attachm:nt I to U-602613 LS-94-013 Page 8 of 9 recovers to a valuejust below the relay reset point and the buses subsequently transfer to the on-site sources, IP has verified that the overcurrent relaying will not trip the 4.160 kV ESF motors during the transient nor will the motors be damaged by this transient.
The control fuses for the 120 volt control circuits in five Motor Control Centers have been analyzed in a similar fashion at the contactor minimum pickup voltage. The conclusion of this analysis is that the control fuses will not open as a result of the degraded voltage during the block start transient. The coordination of other breakers and relays have been evaluated using standard coordination curve analyses. No specific transient analyses are required nor could they be economically performed due to the large number of possible permutations.
The coordination between downstream overcurrent devices and the upgraded voltage relays during fault conditions has been evaluated to ensure faults are not transferretto other sources. Faults of the magnitude that would drop the voltage on the 4.160 kV bus low enough to initiate the degraded voltage relaying scheme would require high currents. Faults of this magnitude would rapidly be sensed by the overcurrent devices and the appropriate breakers would open prior to the 15-second degraded voltage time delay relay timing out. This time delay allows time for both faults to clear as well as large motors to start. The time delay will prevent spurious transfer to the onsite power source unless a true degraded voltage condition exists. 1 I
- 10. "The submittalindicates that, as a result of the calculations performed for the degraded voltage setpoints, CPS determined that the required minimum steady state voltage specified for certain diesel generator surveillances should be increased to 3870 volts. Provide the calculations that were used to determine this diesel generator minimum voltage."
Response: A new Diesel Generator (DG) calculation was not performed. The voltage ;
ranges currently specified for the DG surveillances are equal to 4.160kV 1 10 percent in accordance with the recommendations ofRegulatory Guide '
1.19. Despite the broad range of allowable voltages specified in the DG surveillance requirements, CPS surveillance procedures and good operating practices ensure that the DGs are always run with a voltage as close to the nominal required voltage of 4.160kV as practical. However, ongoing work on the revised degraded voltage relay setpoint calculations led to the observation that the lower voltage limit for operation of the DGs as specified in several DG surveillance requirements was below the lower bound analytical limit for the degraded voltage reset setpoint. In order to
%->. , .. x - ..
. Attachment I to U-602613 4 l LS-94-013 Page 9 of 9 l 4
establish a more appropriate lower limit voltage for the DGs, IP is I proposing to increase the required minimum steady-state voltage specified l in these DG surveillance requirements to be consistent with the lower bound analytical limh for the degraded voltage relays. (The basis for the l lower bound analytical limit was previously presented in response to Question five.) j l
i l
I l
l