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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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L6571990-09-19019 September 1990 Advises That Dp Hall No Longer Associated W/Facility Since Dec 1989.Mail Should Be Addressed to Js Perry JSP-739-90, Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump1990-09-12012 September 1990 Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump U-601729, Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn1990-08-27027 August 1990 Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn JSP-676-90, Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event1990-08-23023 August 1990 Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event U-601723, Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.711990-08-16016 August 1990 Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.71 U-601722, Forwards Reissued NPDES Permit IL00369191990-08-10010 August 1990 Forwards Reissued NPDES Permit IL0036919 U-601721, Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators1990-08-0808 August 1990 Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators U-601716, Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))1990-08-0303 August 1990 Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2)) U-601715, Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly1990-08-0202 August 1990 Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly U-601708, Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 19891990-07-19019 July 1990 Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 1989 U-601702, Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990 Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20044A3001990-06-22022 June 1990 Forwards Update to 890817 Response to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Unisolable Piping Connected to RCS Identified & Evaluated to Determine Which Piping Could Be Subj to Stratified Flow Phenomena ML20044A4601990-06-22022 June 1990 Provides Followup to 900622 Request for Waiver of Compliance Re Tech Spec Limiting Condition for Operation Concerning Standby Emergency Diesel Generator 1B.Rev to Attachment 1 of Original Request for Waiver Encl ML20043H5021990-06-19019 June 1990 Requests Changes to License NPF-62,correcting Typos, Refs to Fsar,Testing to Be Done During Initial Plant Startup & Incorporating Revised Operating Power/Flow Map for Two Reactor Recirculation Loop Operation ML20043G8221990-06-0707 June 1990 Provides Update to Util Response to Item 1 of Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. ML20043F0591990-06-0606 June 1990 Forwards Endorsements 44-50 to Nelia Policy NF-261 & 25-31 to Maelu Policy MF-121 & 10 & 11 to Maelu Policy N-85 & M-85,respectively ML20043D0531990-05-31031 May 1990 Forwards 1989 Annual Rept for Illinois Power Co & Soyland Power Cooperative,Inc ML20043C7501990-05-25025 May 1990 Forwards Rev 20 to Illinois Power Nuclear Program QA Manual. Rev Evaluated by Util as Not Reducing Quality Program Commitments ML20043B4891990-05-21021 May 1990 Informs NRC of Plant Initiatives for 1990 to Improve Corrective Action Program Effectiveness,In Response to SALP Rept & Violations Noted in Insp Rept 50-461/89-32. Centralized Commitment Tracking Sys Upgraded ML20043B1141990-05-17017 May 1990 Suppls 900330 Response to Station Blackout Rule.Calculation of Heatup of Main Control Room Due to Loss of Ventilation Following Station Blackout Revised to Properly Account for Heat Sinks & Credit Existing Masonry Walls ML20043D9901990-05-14014 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Rept 50-461/90-02.Corrective Actions:Safety Evaluation Prepared & Reviewed for Level Instrumentation & Annunciators Identified in Updated SAR ML20043A9811990-05-14014 May 1990 Notifies That Wc Metzner Resigned from Position of Licensed Operator W/Util,Effective 900430 ML20042E6181990-04-13013 April 1990 Updates 890406 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Condition Rept Initiated to Address Issue to Drain Instrument Air Filter Regulators ML20012E8991990-03-27027 March 1990 Forwards Rev 9C to Physical Security Plan.Rev Does Not Decrease Effectiveness of Plan.Rev Withheld (Ref 10CFR73.21) ML20012D9451990-03-20020 March 1990 Informs of Current Activities Re Restoration of Shutdown Svc Water (SX) Sys to Operability Following Cleaning of Div I HX Per Generic Ltr 89-13.SX Sys to Be Restored by Returning Sys Flows to Design Values ML20012D9641990-03-19019 March 1990 Lists Present Levels of Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w)(2) ML20012D9901990-03-19019 March 1990 Responds to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-461/89-38.Corrective Actions:Maint Supervision Added Critical Points to Existing Maint Work Requests & Preventive Maint Activities & Training Program Updated ML20012D4321990-03-16016 March 1990 Responds to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Detailed Analytical Review & Proposed Schedule for Implementing Required Actions Scheduled to Be Completed by 900625 ML20012A2771990-02-28028 February 1990 Forwards Final Response to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded Case Circuit Breakers. Actions Taken by Util Have Established That All safety-related Circuits Remaining in Stock Can Be Verifiably Traced to Mfg ML20012C2511990-02-23023 February 1990 Responds to Ninth SALP Rept 50-461/89-01 for Sept 1988 - Oct 1989.Rept Concluded That Overall Performance Satisfactory & Identified Strengths in Areas of Emergency Preparedness U-601611, Notifies That Gd Setser Resigned Position W/Util,Effective 9002131990-02-20020 February 1990 Notifies That Gd Setser Resigned Position W/Util,Effective 900213 ML20011F6501990-02-12012 February 1990 Responds to NRC 900112 Ltr Re Violations Noted in Insp Rept 50-461/89-37.Corrective Actions:Radiation Protection Technicians Provided W/Method for Identifying Radiation Work Permits Which Change Radiological Conditions ML20006C6721990-02-0505 February 1990 Responds to NRC 891207 Ltr Re Violations Noted in Insp Rept 50-461/89-35.Corrective Actions:Emergency Planning Bulletin Issued to All Emergency Response Organization Members Emphasizing Importance of Attending Required Training ML20006D1951990-01-30030 January 1990 Responds to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Util Intends to Discontinue Sending Ack Upon Receipt of Vendor Manual Matls ML20006A8291990-01-23023 January 1990 Forwards Rev 3 to Inservice Exam Plan. Changes to Text Described.Approval of Changes by 900601 to Allow Time to Plan Refueling Outage Activities Re Inservice Exam Program Requested ML20005H2711990-01-12012 January 1990 Advises That Licensee Will Remove Terminal Blocks for Control Circuits within 100% Relative Humidity Harsh Environ at Plant by End of Second Refueling Outage Currently Scheduled to Begin in Sept 1990 ML20006A7121990-01-10010 January 1990 Forwards Revised Pages to 1987 Radiological Environ Monitoring Rept ML20005F0001990-01-0505 January 1990 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Util Revised Plant Operating Procedures for Hpcs,Lpcs & RHR Pumps & Vibration Monitoring Program Expanded to Include ECCS Pumps at Plant ML20006A7921989-12-29029 December 1989 Responds to 891129 Ltr Which Forwarded Insp Rept 50-461/89-31,requesting Identification of Actions Underway to Ensure That Falsification of Interim Security Screening Records Would Be Detected in Timely Manner in Future U-601573, Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently1989-12-29029 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently ML20005E0891989-12-27027 December 1989 Advises That Revised Fitness for Duty Program Will Meet 10CFR26 Requirements,Effective 900103.Util Intends to Test for Substances Listed at Indicated cut-off Levels ML20006C2961989-12-21021 December 1989 Responds to NRC 891121 Ltr Re Violations Noted in Insp Rept 50-461/89-32.Corrective Actions:Review Performed to Identify Surveillances Which Require Lifting of Leads in Main Control Room ML20005D9521989-12-15015 December 1989 Forwards Monthly Operating Rept for Nov 1989 for Clinton Power Station Unit 1 & Corrections to Oct 1989 Rept ML20005E7781989-12-12012 December 1989 Advises That False Alarm Criteria Will Be Implemented by 900131,per Insp Rept 50-461/89-31.Util Established New Criterion of 100 False Alarms for Security Sys in 24 H Period ML20011D1741989-12-0707 December 1989 Informs of Changes Made to Util Fitness for Duty Program Procedure.Change Specifies That Supervisor - Medical Programs,Assistant Director - Labor Relations or Manager - Nuclear Planning & Support Will Generate Computer List ML19332F0071989-11-30030 November 1989 Responds to Violations Noted in Insp Rept 50-461/89-29. Corrective Actions:Preventive Maint for Ph Monitor & Liquid & Gaseous Gamma Monitors Added to Appropriate Tracking Programs ML19332E9431989-11-29029 November 1989 Forwards Executed Amends 4 & 5 to Indemnity Agreement B-91, Reflecting Change in Ownership of License,Effective 890327 ML19332D5031989-11-27027 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Results of Util Review & Reporting of Status of Implementation of USIs Encl ML19332D0291989-11-22022 November 1989 Informs That Effective 891201,JS Perry Will Assume Responsibility for Mgt of Nuclear Program at Util ML19332D0431989-11-22022 November 1989 Informs NRC of Change in Schedule for Providing Info Re Environ Qualification Testing of Terminal Blocks for Control Circuits of Conax Electrical Penetrations.Wyle Labs Test Results & Util Review of Results Will Be Sent by 900112 1990-09-19
[Table view] |
Text
_.
s U-601235 L30-08(o7-26)-LP 1A.120.
ILLIN0/8 POWER COMPANY IP -
CUNTON POWER STATION, P.o. b04 678, CLINTON, ILLINots 61727 f
July 26, 1988 Docket No. 50-461 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Clinton Power Station Environmental Protection Plan
Dear Sir:
In accordance with Section 3.2 of the Environmental Protection Plan (EPP) for the Clinton Power Station, attached is a copy of a requested' variance to the National Pollutant Discharge Elimination System (NPDES) permit. Please contact me if you have any questions on this submittal.
Sincerely yours,
~
F. A. Spa genbe I, III Manager - icen Lng and 3afety DW/krm Attachment cc: NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety Coo l 8808030375 880726 .) I [
PDR ADOCK 05000461 1 P PDC V
s ILLINDIS POWER 00MPANY j gyg {
i"" , 500 SOUTH 27TH STREET, DECATUR, ILLINOIS 62525-1805 July 25, 1988 HAND-DELIVERED Illinois Environmental P'otection Agency Division of Water Pollution Control 2200 Churchill Road Springfield, Illinois 62706 Attention: Mr. Mark T. Books Environmental Protection Specialist Compliance Assurance Section
Dear Mr. Books:
Clinton Power Station Application for Provisional Variance In accordance with the provisions of Sections 35 through 38 of Title IX of the Illinois Environmental Protection Act (the "Act"), and the requirements of Part 180 of Title 35, Subtitle A, Chapter II, Procedures ;
and Criteria for Reviewing Applications for Provisional Variances of the l Illinois Environmental Protection Agency (the "IEPA"), Illinois Power Company ("IPC") submits this application for a-provisional variance to temporarily suspend, for a period of 45 days, the effluent temperature limitations currently applied at the end of _the discharge flume for i 1
discharges to Clinton Lake at IPC's Clinton Power Station ("Station"). IPC !
requests a provisional variance, for a period of 45 days from the date of granting, from the effluent tempoature limitations imposed by the Illinois Pollution Control Board ("Board") in its Order of May 28, 1981 under PCB 81-82 (the "Order"), which states that the daily average discharge temperature of discharges to Clinton Lake from the Station shall not l
_ . . . - . ._ 1
l .
o ,
i l exceed 99 F during more than 12 percent of the hours (approximately 44 days) in twelve-month periods ending with any month and at no time exceed 108.3*F. The information required by the IEPA provisional variance application procedure in support cf IPC's request is presented as follows:
- 1. Applicable Thermal Limitations The effluent temperature limitations for discharges to Clinton Lake at the Station were imposed by the Board in the Order, as stated above. The Order was issued by the Board on May 28, 1981, and it provided that "the daily average discharge temperature [for effluent discharges to Clinton Lake from the Station] shall not exceed 99*F during more than twelve percent of the hours in twelve-month periods ending with any month and shall at no time exceed 108.3*F." Monitor'ng for determining compliance with these limitations is performed at the end of the discharge fiume.
With the instant application, IPC requests a provisional variance from these limitations at that point. As of July 21, 1988, IPC had experienced 25 days in which the discharge temperature at the station exceeded 99*F since July 22, 1987 with 19 more days allowed through July 31, 1988 under current limitations (a). The maximum daily average discharge temperature observed recently was 106 F on July 19, 1988.
(a) Actually 21 more days would be allowed as of July 31, 19E8 as two days will be recovered from the period July 22 through July 31, 1987.
Similarly three more days will be recovered in August (August 1, 2, and 3) before the Board's next meeting on August 4.
IPC recognizes that, as of the date hereof, there are 19 days remain-ing of the 44 days allowed. However, because of a current station operating situation (only two circulating water pumps are presently in service) IPC believes this count will be reduced to 11 by August 4. This is certainly not sufficient for operating the station through September, nor may it be sufficient to operate the station until the Board's next meeting on August 18 even if full cooling water flow is restored shortly after the August 4 Board meeting. Similarly, because only two circulating water pumps are currently in service, cooling water flows are reduced and the station is thermally constrained by the Board's thermal limitations.
Power levels are currently limited to approximately 93 percent. However, even though discharge flume temperatures may currently approach the limitations of the Board Order, the quantity of heat energy (btu /hr) being discharged to the Clinton Lake is substantially reduced.
On June 3, IPC f'iled with the Board, pursuant to Section.37(a) of the Act and 35 Ill. Adm. Code Part 104, a Petition for Variance, (the "Peti-tion") requesting relief, until October 1, 1990, from both of the limita-tions in: posed by the Board on its Order. A copy of the Petition and Exhibits A through H thereto (collectively, the "Exhibits") were served upon the 12PA on that date. The Petition was docketed for hearing as PCB
1 .
The Petition and the Exhibits are hereby incorporated by reference l 88-97.
as if fully set forth herein. The primary purpose of the variance !
I requested in the Petition was to enable IPC to collect two years of actual !
I operating data from the Station and lake temperature and meteorological data. This data will be evaluated with a refined, more sophisticated thermal model and, based on this evaluation, IPC will formulate long-term strategies with respect to thermal effluent discharges at the Station. See paragraph 16 of the Petition. l l
However, since IPC has continued the scheduled hearing of PCB 88-97(a), the Petition, if granted at all, will not be granted in time to enable IPC to avoid exceeding the 44-day limitation, a highly probable occurrence for the reasons noted previously, as well as the 108.3*F limitation which could certainly be exceeded under current operating conditions and would likely be exceeded under normal plant operations if prolonged dry and warm sunner conditions persist. Thus, the instant provisional variance is needed to avoid the almost certain exceeding of the 44-day limitation before the onset of cooler fall weather and to allow the Clinton Power Station to be operated in a less constrained mode under current conditions and without constraint when full circulating cooling water flow can be restored.
(a) On July 20 IPC filed with the Board its Motion for Continuance of Hearing and its Waiver of Decision Date; and on July 22 IPC filed its :
i Amended Waiver of Decision Date. With the Motion and the Amended Waiver l IPC extended its hearing until December, 1988 and extended the decision date until Februt.ry 2,1989.
.. -. . .-- . .. . .. 1
- 2. Station and System Descriptions The major process components of the nuclear-fueled electrical generat-ing station at Clinton include one boiling-water reactor, one steam-turbine generator, normal operating and emergency shut down heat dissipation systems and various electrical transmission facilities. The instant application is primarily concerned with the circulating cooling water system, which is a part of the normal operating heat dissipation system.
The circulating cooling water system is designed to deliver water from Clinton Lake to the main condenser in sufficient quantities to condense the turbine exhaust steam, the turbine bypass steam, and other turbine cycle flows. (The individual components of the circulating cooling water system are discussed in somewhat greater detail in Exhibit H to the Petition.)
The heat from the turbine cycle flows is then transferred to the circulat-ing cooling water system flow, which is pumped to the discharge fiume and thereby conveyed to Clinton Lake, together with the service water flow.
(The service water also is drawn from Clinton Lake.) The lake then acts as a heat sink, dissipating the heat transferred from the condenser and down the discharge fiume by the combined service water and circulating water flows. These combined flows constitute the thermal effluent discharge which is subject to the Board's Order.
l l
o e
- 3. Activity Description (Materials Used and Wastewaters Discharged)
The thermal effluent discharge which is subject to regulation by the Board is basically attributable to the normal operation of the Station.
The Station is designed to generate 933 net megawatts of electricity. This 9
corresponds to a heat rejection rate to the discharge flume of 6.71 x 10 btu /hr. This is the amount of heat which, after allowing for some heat dissipation in the discharge fiume itself, is eventually transferred to Clinton Lake by the combined service water and circulating cooling water flows (collectively, these flows are hereinafter referred to as the "dis-charge flume flow"). The magnitude of flows is approximately 1470 cfs (950 MGD) at normal lake elevation (690.0 f t. m.s.l.).
IPC has been monitoring water intake temperatures at the Station screenhouse and flume discharge to (1) characterize the severity of the 1988 summer with res'pect to the 1955 sumrrer (the summer historically used for modeling), and (2) anticipate when the thermal limitations of the Board will be approached. Monitoring data for the month of July are tabulated on Attachment 1.
During the first 17 days of the month, intake water temperatures ranged from a minimum of 75 F to a maximum of 84*F. Average daily flume discharge temperatures during this period ranged from 94*F to 103 F.
Reactor power levels ranged from 18 percent (a) to 100 percent.
l (a) A scram of the reactor occurred on July 12 for an unrelated reason.
1 .
l
On July 18, 1988 at approximately 12:45 a.m., a circulating water pump failed resulting in a reduction of approximately 446 cfs (288 MGD) of circulating cooling water flow. Since that time only two circulating water pumps have been in service. Station management personnel believe this pump will remain out of service until August 6.
The effect of the reduced circulating cooling water flow is obvious.
Referring again to Attachment 1, power levels were reduced to (1) avoid exceeding the 108.3*F maximum daily average temperature limitation, and (2) maintain power cycle efficiency. Average daily flume discharge temper-atures rose 106*F on July 19. Instantaneous flume discharge temperature reached 107*F. Intake temperatures varied only slightly, however, after July 17. During the period of two circulating water pump operation, average daily fiume discharge temperatures have and will continue to exceed 99 F.
i i
i
Actual and predicted daily average cooling water intake temperatures are plotted on Figure 1. The predicted values for 1955 (red line) and 1978 (blue line) are based on the modeling performed for the Petition.
Temperatures observed in 1988 since June 1 are plotted as the black line.
For much of July actual intake temperatures have most closely approx-imated those simulated for 1978 meteorological conditions, the fourth warmest summer during the 26 period of record from 1953 to 1978. On two days, however, those being July 10 and July 16, intake temperatures closely )
approached the temperatures simulated for these days in 1955. This is significant with regard to the maximum daily average temperature limitation l of 108.3*F. l Depending upon the cooling that may occur in the discharge flume, !
discharge flume temperatures should approach the 108.3 F limitation of the Board under normal t'hree circulating water pump operation as intake water temperatures approach 84'F. The most recent modeling suggests this might ;
occur by mid to late July, based on 1955 meteorologini conditions, and extend throughout the third week in August. IPC is concerned that because the summer of 1988 may be is dry as 1955, actual intake water temperatures
]
will approach the simulated temperatures thus resulting in discharge flume !
temperatures approaching 108.3 F even during normal three circulating water ,
l pump operation. During two circulating water pump operation, such as I currently exists, discharge flume temperatures could quickly exceed 108.3 F i due obviously to the reduced circulating water flow.
I
Clinton Power Station ACTUAL AND PREDICTED CW INLET TEMPS 92 -
91 -
90 -
89 - l 153' ,
88 -
87 -
86 -
m 85 -
b 84 -
IL 83 -
b 82 - #77# ;
F 81 -
80 -
Z 79 - ,
2: 78 - N ll ~
19 82 76 - g 75 -
74 -
73 -
72 -
71 -
70 -f m ummmmrm,mmT ' ' ' ' ' ' ' ' m n '
"' i ' m'm"I'Tmmm7i ' i -
06/01 07/01 07/31 08/30 09/29 ,
DATE (1988)
ACTUAL PREDICTED-1955 DATA PLANT PERF/LSB PREDICTED-1978 DATA FIGURE I
IPC contacted the Springfield, Illinois office of the National Weather Service (NWS) to obtain their 90-day outlook for the period of July I s
through September 30, 1988. The NWS has predicted that air temperatures for central Illinois have a 60 percent chance of being at least 1*F above normal during this period. The NWS has also predicted that precipitation for central Illinois has only a 50 percent chance of reaching normal levels during this period. These predictions suggest that the current severe meteorological conditions may only moderate at best through September.
- 4. Assessment of Adverse Environmental Impacts IPC retained J. E. Edinger Associates, Inc. ("Edinger") to perform a hydrothermal modeling study to determine the impact which normal operation of the Station under the 1955 meteorological conditions specified in paragraph 3, above, would have upon water temperatures at Clinton Lake, t
The modeling study utilized the Laterally Averaged Reservoir Model ("LARM")
to generate two-dimensional temperature profiles of Clinton Lake at a number of locations. The results of Edinger's newly-generated LARM study, together with a brief description of the modeling technique and the underlying assumptions, are included as Exhibit E to the Petition.
As is clear from the Exhibit, LARM predicts the maximum daily average discharge temperature under one-unit operation at 100 percent load and full circulating water flow during the worst case summer to be 111.7 F (44.3*C).
This value is subject to an allowance of 1.5*F to account for the use of
_g.
9 v , e
l 1
off-site (Springfield, Illinois) average daily meteorological data. This predicted maximum exceeds the present maximum limitation imposed by the Order, 108.3*F, by only 3.4 F. (The 108.3*F value also derives from the assumption of one-unit operation at 100 percent load.) In addition, LARM also predicts that the daily average discharge temperatures will exceed 99'F (37.2'C) during 18.9 percent of the hours in the twelve-month period encompassing the worst case summer (with an allowance of 2.5 percent), as compared to the limitation imposed by the Order of 12 percent of the hours in twelve-month periods ending with any month. A direct comparison of the 13.9 percent value with the 12 percent limitation is deceptive, however, in that the 18.9 percent value corresponds to operation at 100 percent load over the course of the entire worse-case sumer, whereas the 12 percent limitation derives from the assumption of a 92 percent load over that summer. See paragraph 10 of Petition. (Please note that while this brief sumary of the LARM results focuses on the impact which operating the Station under the above-specified conditions will have on temperatures at the discharge, the newly-generated LARM results also estimate water temper-aturesatvariouspointsthroughoutthelake.)
Currently, IPC is operating the station at approximately 93 percent power at a circulating cooling water flow of approximately 660 MGD. This abnormal operating configuration was not investigated during the LARM 3 modeling effort (but wou;d be as part of the modeling to be performed during the period of variance). Edinger estimates, however, that at a 90 percent level for 1955 meteorological conditions, discharge fiume ,
temperatures could reach 113.9'F. In segment 16 (the lake segment to which l the flume discharges) water temperatures at the surface could reach 108.9*F.
With regard to the updated modeling study, IPC also retained Environ-
- mental Science and Engineering ("ESE") as its consultar.t to assess the biological impacts of the thermal effects expected under the new-ly-generated LARM results. The results of ESE's biological study are included as Exhibit F to the Petition. Sections 5 and 7 of Exhibit F contain the impact analysis of thermal addition to Clinton Lake fish using U.S.E.P.A. protocol and procedures. The U.S.E.P.A. protocol and procedures are, by their very nature, conservative. In spite of these conservatisms the analysis shows that bluegill, largemouth bass, gizzard shad, carp, and channel catfish are expected to produce and maintain good populations in Clinton Lake under worst-case meteorologic conditions like those of 1955, the worst-case summer. According to the U.S.E.P. A. protocol white crappie could be eliminated from the lake during the warmest sunner. The protocol would also indicate white crappie may be eliminated from the lake with no Station heat load under 1955 conditions. However, projections based on the protocol may be overly pessimistic. Data from another Illinois cooling lake indicates crappie have survived temperatures higher than those pre-dicted under 1955 conditions. -
Recent creel studies indicate white crappie constitute approximately 94 percent of the Clinton Lake sport fish harvest. In the past six years -
anglers have harvested an average of 241,579 white crappie each year. The American Fisheries Society has determined that $2,00 is an appropriate I reimbursement value for a nine-inch white crappie. Based on the average annual harvest IPC estimates the annual value of the white crappie in Clinton Lake to be approximately $483,157.
Ongoing monitoring and fish management programs by the Illinois Department of Conservation and IPC will assure maintenance of a diverse fishery. If a kill of white crappie occurs as a result of discharging cooling waters to Clinton Lake consistent with the conditioned provisional variance requested in this application, IPC will mitigate the damage.
The results of the above analysis are similar to those predicted under the current thermal limitations in effect at Clinton Lake. See Section 6 of Exhibit F to the Petitior.. Therefore, IPC believes that allowing the Station to operate under the conditions requested by this provisional variance (which are discussed in Section 7) will not result in effects which are significantly different or worse than the effects already found to be acceptable by the Board, in its Opinion of June 25,1981(the"Opinion")
supporting the present limitations. The Opinion was filed as Exhibit B to the Petition. See Opinion at 4 ("The Board is satisfied that one-unit operation will not pr'oduce unacceptable lake conditions.")
- 5. Hardship Created Residential, commercial, and industrial electrical demand is generally ,
greatest during the months of July, August, and September. To meet that demand, the Station must be operated at or near full capacity. During the month of June, IPC's own demand could not have been satisfied 18 of 30 days without the full generating capacity of the station. Therefore, the primary and unreasonable hardship created by the existing thermal
4 8 limitations is that they require IPC to derate even though the effects of the elevated fiume discharge temperatures on the lake may be inconsequen-tial.
So far as IPC has been able to determine, the 99'F value for the temperature limitation is a historical result from earlier Board thermal proceedings and is not biologically necessary or significant. The current modeling result suggests derating of as much as 20 percent may be required to maintain compliance with the existing 108.3*F thermal limitation at full circulating cooling water flow. A derating of as much as 55 percent at full circulating cooling water flow would be required to maintain daily average flume discharge below 99 F if intake temperatures reach 89'F,the temperature predicted by the LARM 3 modeling for ambient 1955 conditions.
Tnis derating could be avoided if the present thermal limitations were suspended and IPC was allowed to operate the Station for the duration of the 45-day provisional variance period subject 'o the conditions described in Section 7.
The cost of derating the station by 20 percent with respect to IPC's investment costs to build the Station are summarized on Attachment 2. For l
each day of such a reduction approximately $450,000 of investment costs i l
must be paid for the idle generating capacity from which no customer benefit is being obtained. This is not a hypothetical situation, however. l The power station is thermally co strained at this time. Power station management personnel estimate power levels could be increased and the station could maintain a reasonable power cple efficiency. The extent of increase would be subject to the conditions of Section 7. l 4
- 6. Proposed and Alternate Methods to Achieve Compliance IPC presently lacks both sufficient data to select the most efficient method of achieving compliance with the 44-day limitation and with the 108.3 F maximum temperature limitation imposed by the Board, and sufficient time to implement such a method yet this summer. Sargent and Lundy Con-sulting Engineers were recently contacted to estimate the costs of install-ing three supplemental cooling systems to reduce predicted maximum flume discharge temperatures to 108.3*F. Their preliminary report is enclosed as Attachment 3. Capital costs for these systcms heve been estimated to range from six million to 18 million dollars. At the very least, inany months would be required to install such systems. Supplemental cooling systems other than those evaluated in this preliminary study may be more feasible for the station but such determinations cannot now realistically be made on the basis of existing information.
IPC also considered the feasibility of increasing service water flows to the d4 charge flume as a short term measure for reducing discharge flume tempera tures. Three service water pumps are mounted at the screenhouse for providing cooling water to equipment that is not safety related. This would include turbine oil coolers, generating conlers, and ceponent cooling heat exchangers. Two pumps are typically operated while the other is maintained on standby as a spare.
Increasing service water flows to the fiume is not feasible for the following reascns. First, ali flows must go through the system. Direct bypass to the flun.e is not possible. Second, service water flows may be as
l wann as the circulating cooling water flow. And third, starting the third service water pump would not result in additional flow to the flume as flows through the system are regulated by air and motor operated outlet control valves. These valves would close with the hydraulic overload to maintain the balance of flow to and from all equipment.
Until IPC obtains the data necessary to satisfactorily assess its options for ensuring compliance with the thermal limitations at Clinton Lake, its only alternative to seeking this provisional variance would be to derate and operate the Station at less than full capacity. However, this alternative is uneconomical and the biological evaluations demonstrate that the effects of the elevated flume discharge te.nperatures will be inconse-quential (see Exhibit F to the Petition). Furthermore, IPC presently lacks the necessary data to precisely determine the extent that it must derate at the Station to achieve compliance with the existing thermal limitations or to determine the duration over which this derating must continue. Unless and until IPC obtains additional Station operating data IPC will not be able to derate the Station in the most efficient and cost-effective manner.
Given the above considerations, IPC's proposed plan for achieving long-term compliance is as follows: IPC would rely on the instant provi-sional variance and the conditions noted in Section 7 to negate the pos- !
sibility of exceeding the 44-day and 108.3*F limitation at the end of the i discharge flume until after the Board has had an opportunity to render a l l
decision on the pending Petition. Assuming the Board grants the Petition, )
IPC would then be able to operate the Station under normal conditions until October 1, 1990 free from existing thermal limitations. During this !
l
interim period of approximately two years, IPC would be monitoring Clinton
~
Lake, and obtaining actual station operating data and lake temperature and meteorological data for use in assessing its long-term options for achiev-ing compliance with the thermal effluent limitations at the lake. These options could include, without limitation, adding another pump to increase t: e water flow, and thus reduce the temperature of the discharge; operating the plant at less than full capacity under specified conditions; seeking regulatory relief from the Board; or installing another supplemental cooling system,
- 7. Provisional Variance IPC requests a 45-day provisional variance period beginning on the day such provisional variance is granted by the Board, and terminating 45 days thereafter. IPC also requests that the provisional variance be conditioned as follows:
- 1. That IPC be authorized to monitor temperatures at the edge of a 23-acre mixing zone centered around the flume discharge point in Clinton Lake. A sketch of the proposed mixing zone and temperature monitoring polints is attached as Figure 2. IPC's proposed monitoring program is described on Attachment 4.
- 2. That the 108.3 F maximum daily average thermal limit be applied at the edge of this mixing zone.
1
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, 188811888153111111111111lllllllllllllllg3lllgggggggggggj gggggggggygg g ,
7 Illinois Power Company '
Clinton Lake
- Proposed Mixing Zone O 5000 i
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FIGURE 2
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- 3. That the 99'F average daily temperature limitation on the fiume discharge be suspended, i.e. if the daily average tenperature of the discharge flume exceeds 99"F on any days during the provisional variance period'such days shall not be counted toward the 44-day limitation imposed by the Board's Order.
- 4. That the 99 F average daily temperature limitation also not be applied at the mixing zone edge.
As noted previously, IPC will mitigate the loss of fish, if such should occur, as the result of relocating the 108.3*F neximum daily average temperature limitation to the edge of the mixing zone.
In the pending variance (PCB 88-97) .IPC has not proposed any interim temperature limitation but has proposed that the Clinton Station be required to operate in its normal operating mode except during malfunctions or breakdowns. IPC will therefore return to service the tnird circulating water pump as quickly as possibic,
- 8. Current Provisional Variance IPC has not been granted any other provisional variances by the Board in 1988.
I
- 9. Current Status of Thermal Limitations As stated previously, the current limitations on thermal effluent discharges from the Station to Clinton Lake were imposed by the Board's Order of Mcy 28, 1981, underPCB81-82(R81-82). The terms of the present limitations are set out in paragraph 1 of this application, supra. These limitations remain in effect at Clinton Lake, although IPC presently has a Petition for Variance pending before the Board in regard to these limita-tions. See paragraph 1 of the application, supra.
- 10. Other Related Board Orders and Matters Currently Pending The Board order (R81-82) and the proceeding currently pending before the Bo.rd (PCB 88-97) which are most relevant to the instant application are discussed in paragraph 9, supra, and elsewhere throughout the applica-tion. There have been numerous other Board orders issued regarding IPC's activities but there are none currently in effect involving the Station.
In addition, although IPC has participated in a number of pending rule-making proceedings, where only the proponent is generally considered a party, it is not a party to any per. ding Board proceeding other than PCB l 1
F8-97.
l 1
4
4 I
Illinois Power Company appreciates the Agency's consideration of this request for a provisional variance. Please call this office at (217)424-6834 if you should have any questions regarding this request. We would be happy to meet with you and other members of the Agency staff to discuss this matter if that is believed necessary.
Respectively, ILLIN0IS POWER COMPANY W
Jene L. Robinson Manager Environmental Affairs Department JLR8:lem cc: Michael W. Conlin, Illinois Department of Conservation e
l
bc: P. J. Womeldorff - B-20 D. P. Hall /J. S. Perry - V-275 J. Wilson - T-31A R. Freeman /E. Kant - V-928C F. A. Spangenberg/D. W. Wilson - V-920
- 0. Logan - V928B J. A. Smithson - T-33 J. L. Robinson /R. L. Cruse / CPS Hydrothermal Modeling File - A-17 l
1 I
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Attachment 2 Illinois Power Company Decatur, Illinois Clinton Power Station Derated "Investment Costs (1)
Yearly Revenue Requirement Daily Revenue Requirement Daily Revenue Requirement Full Investment Full Investment 20% Derated Capacity Yea r (Millions $) (Millions $) (Millions $) (2) 1988 825.6 2.26 0.452 1989 718.7 1.97 0.394 1990 684.7 1.88 0.376 (1) Installed Cost of Clinton Power Station: 4.245 billion dollars.
(2) Dollars which must be spent to pay off the installed costs of the idle capacity for which no benefit is being obtained.
4
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8 ARGENT & LUNDY ENGINEERS -
A T TACriM E N T 3 couwocoieen
$5 EAST MONRog STRLET cn4Aoo, twwelt sesos talesseo.nooo twr oo.sai.teo, 1988 July 18,No.
Pro 3ect 7949-46 SLMI-22650 Illinois Power company Clinton Power Station - Unit 1 Supplemental cooling Study Mr. R. D. Freeman Manager Nuclear Station Engineering Illinois Power company Clinton Power Statlon l P.O. Box 678 - '
Clinton, Illinois 61727 Attention Mr. A. Ruwe Dear Mr. Freeman As requested on July 15, 1988, we have prepared order-of- l' magnitude capital cast estimates for three specific supplemental cooling schemes that could be applied to the Clinton Power ,
Station (CPS). Based on Mr. T. L. Davis' nemorandum of July 14, 1988 to Mr. F. A. Spangenberg, the three schemes investigated were: (1) trimming cooling tower, (2) discharge flune spray modules, and (3) dilution by the addition of circulating water.
For these schemes, the following design criteria were specified!
for the cooling tower and spray nodules, a heat rate reduction of 1 billion Btu /hr; and for incroaced circulating water, an additional 125,000 gal / min. In addition, our study is based on a vetbulb temperature of 79 *F which vas used in previous studies.
Other supplemental cooling system studies and cost estinates have been developed for the CPS. However, prior studies were based on reducing the circulating water temperature from 108.9 'F at'the condenser discharge to 96 'F at the discharge to the cooling lake. At full load for Unit 1, this temperature reduction ,
/,\ ,
l _ _ _ _ - _ __
""EdM5E""
- July 18, 1988 Illinois Power Company Page 2 Mr. R. D. Freenan I
l requires a heat rejection rate of approximately 3.3 billion Btu /hr.
The heat rejection criteria specified for this study is approximately 1/3 of the rate in the previous studies; therefore, the previous However the studies could not simply be updated to 1988 levels.The design concepbs used previous studies were used for reference.
to prepara the estimates are presented below, .
gappleerntal coolina Tower System The supplemental cooling tower system consists of one mechanical !
The system was sized for draft tower with seven (7) Cells.
100,000 gal / min flow, two 50,000 gal / min pumps, a temperature
'F, tower inlet range of 20 *F, an approach temperature of 10 The temperature of 108.9 'F, and a wetbulb temperature of 79
'F.
water is pumped from the discharge flume through the cooling tower and returned to the discharge flume. Design features were l estimated based on previous Neither work theand no attempt cooling towerwassizemade to of nor any l optimise the design.tne cooling tower design parameters have been reviewed w manufacturers.
Supplemental Soray Modules l
The supplemental spray module system consists of 32 spray modules of a type assumed to have similar performance CharacteristicThe 5 to the spray modules used at other power plants in Illinois.
number of modules was estimated based on a condenser discharge temperature of 108.9 'F, a wetbulb temperature of 79 'F, and a I Design features were l NTU estimated heat based transfer on coef ficient previous of 0.18.
work and no attampt was made to optimise the design. Neither the number of spray modules nor any of the spray module design parameters have been reviewed with manufacturers.
Increased Circulatina Water Flow In this scheme, the additional 125,000 gal / min flow is pumped f rom the cooling lake and added to the water in the discharge flume asing, in part, the currently unused circulating The assumed water design concept system that was installed for Unit 2.includas one pump, which would be Circulating pumps, to be installed in the existing intake structure.
The oversized pump was selected to provide redundancy with the Unit 1 circulating The water pumps and to minimize spare pump was assumed to operate with reduced parts requirements this . design concept includes installation of Also, cutput. feet of 6 foot diareter pipe and a seal well
,' approximately 400that smuld connect the currently installed sognents of the Unit 2 circulating water pipe. Design features were estimated based on previous work and no attempt was made to optimize the design.
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5 ARGENT a LUNDY ... l ENGINEtRS
- "" July 18, 1988 Illinois Power Company ,
l Page 3 Kr. R. D, Freeman i
Caoltal cost Estleates The following capital cost estimates are based on installed costs I
in 1988 dollars. Since the CPS is an operating nuclear plant implementation of any'of these retrofit schemes would require, smecial construction procedures. Based on our experience with oiber operating nuclear plants in Illinois and around the country, we have included an adjustment factor for these conditions. The period required to installEscalation each of the schemes has been was assumed to be 40 months from today.
based on 24Amcnths and escalation rates of 4.5% for both natorial period of 12 months and a rate of 9.5% have beenThe and labor.
used for APUDc. Indirect costs have been estinated at 25%.
cost estimates are presented in Exhibit 1 and summarized below; cooling Spray Increased Tower Modules _
Flov -
Capital Cost 16,566,000 5,658,000 3,970,000 1
A detailed breakdown of those estimates is attached.
Fuel Costs For Auxiliary Power An operating period of 25 days /yr was specified. A levellzad fix !
charge rate of 11,962% and a levelized fuel cost of 41 n111s/ Kwhr ,
have been used to estimate an equivalent capital cost for I suxiliary power. These costs are presented in Exhibit 1, l c_anability charce A capability charge of These $500/Xw hasare costs been presented used to estimatein Exhibit 1.
capellity charges.
_sutrary We suggest that these estimates be discussed with Illinois Power Company and Sargent & Lundy since they were prepared in a short '
i time. In addition, specific schedules must .se developed to determine whether special station outages way be required to implement any or all of the schemes. Time has not permitted these factors to be considered and, therefore, potential cost Also engineering Costs implications have not been included.However, we believ,e that the design have not been included.
concepts evaluated are feasible and that the capital cost estimates developed are eppropriate order-of-magnitude costs.
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. SARGENT C LUNDY '
GN agnuno ...
Illinoic Pr. Wor Compnny July 18, 1988 Mr. R. D. Freeman- ,
Page 4 If additional information is required, please contact us.
Yours very truly, i l
- { f! ? v M// Ah 5 M' J. W. Blattner Project Site Manager JWB/DPW/cd Enclosure-All Recipients Copies
D. P. Hall F. A. Spangenberg T. Davis D. Logan CPS DRC H. M. Sroka P. L. Wattelet R. C. Heider D. K. Schopfer l
D. P. Ward )
M. Zar J. G. Petrich l l
e 4
. ~, _,,,.,_.__,..._m,.._.-,- ,. . ,. _ . . _ _ . . , . . _ . _ . _
. Sargent & Lun9y Exhibit i Engineers CAPITAL COSTS ESTIMATE 7-18-88 Chicago SUPPLEMENTAL COOLING Cooling Tower Spray Modules Dilution 13,596,000 4,580,000 3,258,000 Total Construction Cost $
$ 1,502,000 536,000 360,000 Escalation.............
1,468,000 542,000 352,000 l AFUDC.................. $
16,566,000 5,658,000 3,970,000 Tota 1.................. $
Fuel cost for Aux. 467,805 368,198 799,709 Pover.................. $
1,137,376 895,200 1,944,333 capability............. $
Total Equialent 6,714,042 Capital Investment. . . . . $ 18,171,181 6,921,398 i
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l Attachment 4 Illinois Power Company Decatur, Illinois I
Clinton Power Station Proposed Mixing Zone Monitoring Program Mixing Zone Size: 23 acres (a semicircle of 800 ft radius)
~
Monitoring Points: Three Temperature Monitors: Continuous recorders (DataSondes) submerged to a depth of 0.5m.
Monitoring Frequency: Temperatures at each site will be monitored at 30 minute intervals, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day, 7 days / week.
Period of Monitoring: 45 days Frequency of Reporting: Data from each recorder will be compiled and evaluated at 10 day intervals. A composite ,
average daily temperature will be computed for each day based upon the daily readings of all three recorders. Composite daily average values will be reported with the NPDES Permit Discharge Monitoring Report.
Assu ance of Compliance: Prior to August 4, instantaneous temperature measurements will be made periodically at the mixing zone edge to determine an approximate relationship with flume temperatures at the second drop structure. Power levels will be adjusted based on this initial relationship.
Power levels will subsequently be adjusted based upon the developed data.
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