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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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- lilinois Power Company Clinton Power Station P.O. Box 678 Clinton. IL 61727 Tel 217 935-8881 ILIJN#IS I P9WER #fE" ,
e June 9,1997 !
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Docket No. 50-461 10CFR50.L0
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l Document Control Desk
' Nuclear Regulatory Commission Washington, D.C. 20555
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Subject:
Clinton Power Station Withdrawal of Proposed Amendment I of Facility Operating License No. NPF-62 (LS-97-001) I
Dear Madam or Sir:
By letter U-602714 dated April 1,1997, Illinois Power (IP) requested amendment of Operating License NPF-62 for Clinton Power Station (CPS). This amendment was to incorporate a requirement to maintain in effect interim administrative ,
controls and contingent operator actions until IP completes the modifications to !
upgrade the degraded voltage protection instrumentation and distribution system for all three divisions of safety-related AC power. That letter also recognized that use of the interim administrative controls constituted an unreviewed safety question (USQ).
IP's April 1,1997 amendment request identified that IP would be performing adjustments to the CPS distribution system prior to restart from the current refueling outage (RF-6) to ensure that with offsite power at the minimum expected voltage, f ,
adequate voltage will be provided to all Class IE equipment. That letter also identified j ;
I ;
that IP was performing calculations to reconfirm the adequacy of the minimum required voltages at the limiting 120 VAC level and that the results of these calculations would
. be provided when they become available. The Attachment to this letter describes the 4 required distribution system adjustments and the results of the supporting calculations.
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The results of the calculations have shown that with the distribution system i adjustments described in the Attachment to this le4er, coupled with the new degraded l voltage relays set at the setpoints approved in Amendment No. I10 to the CPS l Operating License, manual operator actions are no longer necessary to provide l protection for Class IE loads from an undervoltage condition. Since IP has now l concluded that automatic degraded voltage protection will be provided for all Class IE equipment down to the 120-VAC level, IP has determined that a USQ will no longer 9706170332 970609 -'
PDR ADOCK 05000461 P PDR , billbhhhhli:lh
4 U-602714 1 Page 2 exist for plant restart from the current refueling outage, and processing of the Technical Specification changes proposed in IP's April 1,1997 letter is no longer required. As a result, IP is requesting withdrawal ofits April 1,1997 amendment request.
l Sincerely yours, v-oseph V. Sipek irector-Licensing .
i DAS/krk Attachment cc: NRC Clinton Licensing Project Manager NRC Resident Office, V-690 Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety l
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. Attachment 1
.. to U-602756 Page 1 of 5 Back_ ground As identified in Clinton Power Station (CPS) Licensee Event Report (LER)94-005 (Illinois Power letter U-602296 dated June 3,1994), Illinois Power (IP) personnel . .
identified that the second level undervoltage (degraded voltage) instrumentation at CPS '
j was not adequate to automatically ensure that sufficient voltage would be provided to all L Class IE loads, particularly at several 120-VAC distribution panels. As interim corrective action, IP installed an alarm for the Division 1, 2, and 3 4.16-kV buses and established contingent operator actions in order to minimize the potential that the Class IE loads >
would not receive adequate voltage.
L Longer-term actions were initiated to develop design change options for restoring the plant to within its licensing basis for automatic degraded voltage protection. The design change option selected involved upgrading the degraded voltage relays and installing ,
voltage-regulating transformers for various 120-VAC distribution panels. These changes were scheduled to be installed one division at a time in separate refueling outages ' ;
beginning in the sixth refueling outage (RF-6). The proposed use of the upgraded .
degraded voltage relays and their setpoints in the new configuration was reviewed by the :
NRC staff. These changes were subsequently approved by the NRC in Amendment No. .
I10 to the CPS Operating License, dated December 4,1996.
During installation of the modification for Division 2 (i.e., modification AP-028) during i the current refueling outage (RF-6), problems were experienced with the new voltage -
regulating transformers. The new transformers were determined to be susceptible to radio ;
frequency / electro-magnetic interference (RFI/EMI) and as a result, the internal protective :
circuitry for one of the transformers was causing spurious trips. After an extended and unsuccessful attempt to resolve the tripping problems, it was decided to reinstall the ,
- original non-regulating transformers for the 120-VAC distribution panels. However, it i was recognized that utilization of the new, more accurate relays calibrated to the setpoints approved in Amendment No. I10 would be appropriate, from a safety point of view, for improving automatic protection for the Class IE loads. In fact, it was determined that plant safety _would be enhanced by installing the new, more accurate relays in all three divisions prior to startup from the current refueling outage rather than installing them one division per refueling outage. Because the adequacy of this configuration was dependent -
on continued use of the interim administrative controls and contingent operator actions, the NRC staff requested IP to submit a license amendment request to acknowledge the continued use of the interim administrative controls and contingent operator actions until RF-7.
l By letter U-602714 dated April 1,1997, IP requested amendment of the CPS operating L
license to incorporate the requirement to maintain in effect the interim administrative controls and contingent operator actions until completion of the modifications to upgrade I the degrad_ed voltage protection instrumentation and distribution system for all three divisions of safety-related AC power. That letter also recognized that use of the interim administrative controls constituted an unreviewed safety question (USQ).
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Attaclunent 1
. to U-602756 i i Page 2 of 5 IP's April 1,1997 amendment request identified that IP would be performing adjustments i to the CPS distribution system prior to restart from the current refueling outage (RF-6) to l ensure that with offsite power at its minimum expected voltage, adequate voltage will be provided to all Class IE equipment, including the most limiting 120-VAC loads. That letter also identified that IP was performing calculations to reconfirm the adequacy of the minimum required voltages at the 120-VAC level and that the results of these calculations will be provided when they become available. This letter provides the results of the noted distribution system adjustments and supporting calculations.
Overview IP has completed the calculations to determine the minimum required voltage for Class lE 120-VAC loads (i.e., CPS calculation 19-AJ-72). The voltage requirements were used as input to/ acceptance criteria for the Loss-of-Coolant Accident (LOCA) block-start voltage calculation (i.e.,19-AQ-02) previously reviewed by the NRC as part of Amendment No.
110. Completion of the calculations established the final adjustments required to the CPS distribution system. The established changes are based on an optimum resolution to ensure adequate voltage, provide fully automatic degraded voltage protection and yet minimize the potential for overvoltage. These adjustments involve increasing the Reserve Auxiliary Transformer (RAT) tap settings to provide a voltage boost of 2.5%, decreasing i the Emergency Reserve Auxiliary Transformer (ERAT) tap settings to provide a voltage drop of 2.5%, increasing the tap settings on several 480/120-VAC distribution I I
transformers by 5%, and moving some loads to existing voltage regulating transformers that have adequate load margin. Each of these changes will be reviewed under the requirements of 10 CFR 50.59 prior to installation.
l The results of the calculations have also shown that with the above-described distribution I system adjustments, coupled with the new degraded voltage relays set at the setpoints approved in Amendment No. I10, manual operator actions are no longer necessary to provide protection for Class IE loads from an undervoltage condition. Since IP has now i concluded that automatic degraded voltage protection will be provided for all Class IE 1 equipment down to the 120-VAC level, IP has determined that a USQ will no longer exist i for plant restart from the current refueling outage, and processing of the Technical !
Specification changes proposed in IP's April 1,1997 letter is no longer required. As a result, IP is requesting withdrawal ofits April 1,1997 amendment request. Summaries of the calculational methods and assumptions supporting these conclusions are provided l below.
I Summary of 120-VAC Calculations (19-AJ-70.19-AJ-71 and 19-AJ-72)
There are approximately 200120-VAC level circuits containing Class lE equipment required to operate following a LOCA block-start, which are fed from nine 120-VAC Class IE distribution panels. The end-use devices, associated minimum pick-up voltages, and cable lengths for these circuits were tabulated in calculation 19-AJ-72 to determine
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L Attachment I to U-602756 Page 3 of 5
, the most limiting circuits with respect to required voltage. The limiting components were l
determined to be relays, solenoids, and solid-state devices (i.e., transmitters, recorders, and power supplies). The most limiting components were determined to be Westronic
, recorders which require a minimum voltage of 105.3 vohs. - Additionally, the circuits l containing Class IE equipment required to operate following a LOCA block-start were l reviewed to determine the extent of any interlocking (which would contribute to additional !
voltage drop due to extensive cabling to jumper between panels and devices). Based on these reviews, two circuits from each of five distribution panels containing a large number of circuits, and one circuit from each of four distribution panels containing only a few .I circuits, were selected for further detailed evaluation. Thus, detailed evaluations were i L performed on 14 circuits associated with the nine Class IE distribution panels. Based on L the selection criteria, these evaluations are considered to be representative or bounding ,
with respect to the remaining circuits.
Calculation 19-AJ-71 provides voltage drop analyses for the control circuits which are fed from the 480/120-VAC control transformers in the motor control center (MCC) buckets.
A detailed analysis was performed on several circuits that have long cable lengths. .The calculation determined that the highest minimum voltage required at the 480-VAC level for the control devices to function properly is 420 VAC. ' Although these calculations were based on actual cable lengths, the voltage drops were calculated in a very conservative manner since the calculations assumed a conservative cable impedance for all the circuits and assumed that the motor contactor coils were drawing in-rush current. In ,
contrast, the minimum voltage used in previous calculations for determining the maximum allowable length of control circuit cables.was 427 VAC. The assumed 427 VAC was the i expected minimum voltage level available as determined during the original design phase of CPS. However as discussed above, the highest minimum voltage required for the control circuits has now been determined to be 420 VAC based on the actual installed i control circuit cable lengths. This conclusion was also confirmed by analyzing, via calculation 19-AJ-70, all the control circuits for a few selected MCCs. The minimum voltages required for these circuits were determined to all be less than 420 VAC.
Summary of LOCA Block-Start Calculation (19-AO-02) i' To verify that the voltage requirements determined in the detailed circuit evaluations described above are met under worst-case accident conditions, the LOCA block-start calculation (i.e.,19-AQ-02) was re-performed assuming post-LOCA offsite power voltage corresponding to the new relay minimum analyticallimit value (i.e.,3870 VAC). During the preparation of calculations 19-AJ-72 and 19-AQ-02, IP determined that six distribution transformers, of the nine that feed Class IE distribution panels, needed to have their taps raised to provide adequate voltage. The most limiting voltage at the 480-VAC level for the circuits associated with the six distribution transformers was determined to be 421 VAC. This is conservative since the most limiting sample circuit required 421 VAC while most of the remaining sample circuits required less than 415 VAC. For one of the three remaining Class IE distribution panels, all of the loads were transferred to an l . existing voltage regulating transformer. The circuits associated with the two remaining
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.- to U-602756 Page 4 of 5 Class 1E distribution panels required more than 421 VAC in order to support the results of 19-AJ-72. All circuits in these panels (AB MCC 1 A4 and AB MCC IB4) were evaluated. The most limiting circuits were determined to require 425 VAC and 424 VAC, l respectivelyc It should be noted that the required voltages for AB MCC 1 A4 and AB l MCC IB4 distribution panels were not limiting for establishing the minimum required upstream voltages. The Auxiliaiy Power system analysis performed in calculation 19-AQ-02 supports the required minimum voltage to all the circuits fed from the Class IE distribution panels under post-LOCA conditions.
- l. With the completion of the noted distribution system adjustments, calculation 19-AQ-02 demonstrates that the new degraded voltage relays, set at the setpoints approved in Amendment No.110, will provide adequate degraded voltage protection to all Class 1E loads, including loads at the 120-VAC level. More specifically, these calculations demonstrate that: (1) the upper analytical limit for the relay reset setpoint is below the minimum steady-state expected offsite power voltage following a postulated LOCA for operating cycle 7 (2) the lower analytical limit for the relay reset setpoint is above the j minimum voltage required for proper starting and continued operation of all Class 1E j loads required for mitigation of a LOCA, (3) the upper Allowable Value for the relay trip setpoint is below the lower Allowable Value for the relay reset setpoint, and (4) the lower analytical limit for the relay trip setpoint is above the value required to protect Class 1E equipment from degraded voltage conditions under non-LOCA and post-LOCA steady-state conditions. Thus, the bases for the relay setpoints established under Amendment No.110 to the CPS Operating License continue to be met for operating cycle 7.
Additional nformation The adjustments being made to increase selected distribution transformer tap settings by ;
5%, raising the RAT tap setting by 2.5%, and lowering the ERAT tap setting by 2.5%
l result in an overallincrease in voltages applied to Class lE components. As stated above, these changes are based on considerahons given to ensuring adequate voltage, providing
- fully automatic degraded voltage protection and minimizing the potential for overvoltage l
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until a permanent resolution is achieved in RF-7. The above-described calculations have demonstrated that Class 1E components will not be adversely affected for the duration of operating cycle 7, provided 4.16-kV voltage is maintained below 4300 VAC. Calculations demonstrate that this condition will be met for the expected offsite power voltage range j with the plant on line, during postulated LOCA block-start conditions, with the plant off ;
line when the Class' IE buses are powered from the ERAT, and with the plant offline when the Class IE buses are powered from the RAT with approximately 11 MVA ofload on the RAT. When the plant is offline, the Class IE buses will normally be powered from j '
l the ERAT. In the event that the ERAT is unavailable, procedures will require frequent i monitoring of bus voltage by plant operators to ensure adequate load is on the RAT to .
{ prevent an overvoltage condition. These controls will ensure that the 4300-VAC limit is not exceeded. l ae - - - - - + t- gm -gwwww- i
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. to U-602756 1 Page 5 of 5 Prior to plant restart from RF-7, IP will install additional modifications to provide .
adequate voltage regulation for affected Class IE loads. '
Conclusion l
Based on the above, IP has concluded that manual operator actions will no longer be necessary to provide protection for Class 1E loads from a degraded voltage condition following restart from the current refueling outage, and thus, no USQ will exist. As a .
result, IP is requesting withdrawal ofits request to amend the CPS Operating License, dated April 1,1997.
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