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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
. _ _ _ -_- -___ _
.' U-600506 L30-86 (04 - 16) -L 1A.120 ILLINDIS POWER COMPANY CLINTON POWER STATION. P.O. BOX 678, CLINTON, ILLINOIS 61727 April 16, 1986 Docket No. 50-461 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Clinton Power Station Readiness to Load Fuel
Dear Mr. Denton:
Illinois Power Company (IP) is submitting this letter to provide you with the current status of the design, construction, and preoperational phasq testing of the Clinton Power Station (CPS) in i accordance with the TPS Final Safety Analysis Report- (FSAR) and NRC regulations. This letter describes the project status as revised from ,
the February 17, 1986, letter on " Readiness to Load Fuel" (IP letter U-600455). The status of each major activity needed to support Fuel :
Load and subsequent startup/ power ascension testing is described below.
On March 18, 1986, Illinois Power announced that Fuel Load at CPS l would be later than expected. The target previously established for l the milestone event was the end of March. Two major factors are contributing to the delay. Because of experiences at other nuclear power plants in about the same stage of completion as Clinton, more tests are being required by the Nuclear Regulatory Commission than previously anticipated. Also, Illinois Power Company management has determined that the completion of testing and preparing the plant for i operation is more difficult and requires more time than was scheduled.
Illinois Power management, which includes the Board of Directors, has made an absolute commitment to the building of a safe operating plant at Clinton. IP is in the final process of testing the plant in preparation for Fuel Load. IP will seek to load fuel when management is satisfied all conditions are properly met to the satisfaction of l the NRC. It is anticipated that Fuel Load at CPS will occur in the l late June to early July timeframe.
A. Project Readiness Initiatives L __
In the last update of the " Readiness to Load Fuel" letter, as referenced above, several management initiatives were described which have been taken to ensure a rigorous ap roach to management commitment and involvement in the control of lant activities.
\
8604180097 860416 PDR ADOCK 05000461 q A PDR g i
l The particular initiatives described in theclast uadate of this letter included various changes in organization, the formation-of a Project Control Center (PCC), the. Site-Wide Statusing System-(SWSS), an Operational Readiness Assessment (ORA) and the process of-identifying systems required operable for Fuel Load. The' details of.these program initiatives-are not repeated herein the status of key results in-these'and other areas is discussed below.
(1) Project Control Center (PCC)
The PCC continues.to focus on the resolution of restraints- 1 to system preoperational phase testing activities.' The involvement of.the PCC in resolving these restraints has improved.this area. In February, ten system releases were made from Startup to Plant Staff.- In March, one system 9!> release was made to Plant Staff. System. releases in March -
decreased due to management's decision that open system punchlist items will be cleared prior to release. The PCC is also focusing more attention on the readiness of systems to support operation.
I ;
(2) Site-Wide Statusing System (SWSS)
The SWSS provides the consolidated-listing of.all open work documents at CPS. The-assignment of completion. milestones to all open work items is essentially complete. This effort has and will continue to provide a common framework, relative to required plant systems and areas, needed to t support timely planning and scheduling of these activities.
The SWSS is updated daily _and charts are maintained in the PCC and in other site-wide locations.-
(3) Operational Readiness Assessment-(ORA)
The~ internal assessment of CPS conducted _by IP was completed in February, 1986. The_results of this OPA were provided by.
the assessment team to management in a' report. This report has been reviewed by each' department manager, and responses have been provided to the ORA team for final assessment.
~
For the following significant items identified ~by the' ORA team, corrective action has been taken,.as noted below:
Criteria for System Release from Startup-to Plant Staff
- more definitive criteria have been established and are now in use. As noted in the above PCC discussion, efforts to make each system as operational ~as possible, prior to the release to Plant Staff, are underway.
Housekeeping - Daily supervisory inspections of plant areas are being conducted. Designated eating and smoking areas have been established.
- e. .2 ._ . . _ _ ._ _. w a...__._
t 1
d Post Maintenance Testing - Procedures'are being revised
-to provide. clearer. guidelines to the-Shift Supervisor-2 -in the areasHof ASME repair / replacement, Inservice.
Testing, Pump and Valve Operability requirements, equipment qualification.and leak testing requirements of 10CFR50, Appendix J. ,
Technical Specification. Surveillance Procedures - a
- cross-reference is being actively pursued.to ensure all. '
requirements will be met.
Area / Process Radiation Monitoring (AR/PR)' System -
several actions-are being taken to. ensure the AR/PR system will be ready for Fuel Load. .These actions
- include the establishment of.an.AR/PR' manager to i coordinate all activities, the preparation of-
- procedures and the performance of radiation monitor i calibrations. All open work documents.are being reviewed and scheduled for completion.
]
Closure Rate of Open NRC Inspection &, Enforcement (I&E)
{ Items - increased management attention has been given to this area to support timely and complete I&E closure packages and the increased Region III inspection
. activities as Fuel Load at CPS approaches.
. (4) Systems Completion Status Work on all plant systems, with the exception'of those
'r systems related to the test deferrals identified in IP' Letter U-600469, dated March 12,.1986, will be completed
- prior to Fuel Load. As of-the end of March, there were a 1 total of 38. full systems and 3 partial systems' declared j operable (out of 133). As required by CPS Technical'
- Specifications, surveillances will-be performed on'affected i- systems, up to and including, Operational-Condition l ,
4 requirements, prior to Fuel Load, except.for those systems in which testing is deferred ~(March- 12, 1986' letter),'or
. where plant conditions ~ preclude such surveillances.
This area is receiving a high level.of management attention.
)!
An action plan has been established including ~the_
implementation of'a plant procedure which establishes a
~
rigorous system readiness checklist requiring. departmental ~
- managers / directors to~ sign-off on the' completion of all-necessary work prior to declaring the system operable and
" cleaning up" of systems prior-to release _to Plant-Staff-p '
from Startup. Systems which have been previously released-are being reevaluated on a case-by-case basis using these-checklists. All work documents, modifications, and punchlist items are being examined, prioritized and scheduled for completion cn1 a total system basis.-
1 i
=-B. Critical Path' Analysis
- As of March 21, 1986, the CPS critical path analysis indicates the most limiting systems restraining Fuel Load are'the Control Room Ventilation, Fuel Handling,-Fire Protection, Off Gas, Diesel Generator, Standby Gas Treatment,'High Pressure. Core Spray, and Combustible. Gas Control-Systems.
Restraints to completion of these systems include startup test activities, equipment repairs, p design. modifications,-preparation of procedures.and surveillance procedure performance.
The PCC is resolving-these restraints so'as to complete the required work'in-a safe and timely manner.
The only remaining major-project milestone requiring completion 1
-prior to Fuel Load is the Integrated Emergency. Core Cooling System / Loss of.0ffsite Power-(ECCS/ LOOP) Test.. The ECCS/ LOOP-
- Test is currently scheduled.to be started in May'1986.
C. Construction Status l
As of March 25,.1986, construction of CPS is essentially complete based on all commodities except as noted below:
)
i Piping Insulation = 95.05%
Conduit = 98.47% .
Conduit Hangers = 99.45%
Penetration Seals = 96.05%
! Painting = 98.39%
1 i All systems have been turned over from Construction to Startup I
for testing. Completion of remaining plant areas required for Fuel Load.is proceeding on a schedule consistent with IP's goals.
All required areas will be completed by April-1986. ' The j following provides the status of remaining. plant areas, as of 4 March.26, 1986:
4 i Total Physical Plant Areas = 659 i Plant Areas Completed = 586 1
4 Plant Areas Remaining = 73 i
i Remaining Areas Required for Fuel Load = 26 i
Remaining Areas After Fuel Load = 47 i The 26 required plant areas remaining.will be completed prior to Fuel Load.- The data reported'above represents an increase of 51.
1.
I
- i
, M
~
, , - - . - =,-r- ,,1---y.,% - - - -, .,-,-~yw. -ew cw. ,. -- , +~ c-- ,- .m -r - -- e-m.- ~- . ~ . ,~,e5 ---mri--,.- -, -. .-.-,-r- --r areas completed since the last update of this letter. Final commodity turnovers will be based on building completion Trends for completion of Construction Work Requests, Field Chan e Requests, Area Punchlist Items, Travelers and Plant Modi ications continue to support timely plant completion.
Several other key construction completion activities warrant mention. During the month of February 1986, construction work on the Control Room elevation of the Control Building was completed.
All fire wrapping and fire damper modifications were completed in March. The piping department completed the construction portion of IE Bulletin 79-14 and the balance of plant hanger arograms in March. Finally, additional management attention has been directed towards removing restraints, such as testing related work, from the completion of remaining area commodities (e.g.,
insulation and painting).
D. Preoperational Testing A total of six (6) Preoperational Tests, all of which are required for Fuel Load, were completed in February, 1986. Eight (8) Preoperational Tests were completed in March. As of March 31, 1986, Preoperational Test Procedure (PTP) and Acceptance Test Procedure (ATP) performance status is as follows:
Total PTPs/ATPs = 157 PTPs/ATPs Required for Fuel Load = 148 PTPs/ATP Completed = 109 (approximately 74% of the total required for Fuel Load)
Through the beginning of March, approximately 98% of all Checkout and Initial Operation (C&IO) phase testing has been completed.
In addition, over 98% of the test procedures required for C&IO, Preoperational, and Startup phase testing are approved for use.
On March 12, 1986, IP Letter U-600469 was submitted to the NRC which provided detailed technical evaluations of several preoperational phase tests being deferred until after Fuel Load.
The referenced letter identifies a total of 17 PTPs/ATPs (9 full :
PTPs/ATPs and 8 partial PTPs/ATPs) affected by these test deferral requests. The technical evaluations performed indicate that the affected test activities can be deferred until after Fuel Load with no undue risk to the health and safety of the public and no impact on the safe and reliable operation of CPS during the low power phase of the plant startup program.
Preliminary discussions with the Staff in,dicate that the NRC will l approve these test deferrals. IP has established measures for controlling the deferred test activities in a manner that will i minimize the impact on power ascension activities and result in l no unwarranted burden on plant operations and testing 1
personnel. IP Letter U-600510, dated March 27, 1986, submitted five (5) specific exemption requests to the requirements of 10CFR50, Appendix A, General Design Criteria, in accordance with 10CFR50.12, rela *ive to the safety-related systems affected by the test deferraio.
E. Personnel and Staffing Currently, there are 46 personnel licensed to operate CPS [34 Senior Reactor Operators (SR0s) and 12 Reactor Operators (R0s)].
This includes the 10 candidates that passed the NRC examinations in February, 1986. The current number of licensed operators exceeds that required to fulfill the shift complement levels of the CPS Technical Specifications.
F. Nuclear Reactor Regulation (NRR) Licensing Issues IP has maintained active communications with the NRR Clinton Licensing Project Manager to assure expeditious and satisfactory resolution of open licensing issues. The status (as of April 4, 1986) of the CPS Closure of Licensing Issues Program (" CLIP"),
which is a comprehensive tracking system for all SER and other NRR-related issues, is as follows:
Total Number of " CLIP" Issues Open = 13 Require NRC Action to Close = 5 Require IP Action to Resolve = 8 Since the last update of this letter, 22 " CLIP" issues have been resolved by the Staff.
The major issues requiring continued management attention to ensure timely closure are as follows:
(1) Hydrogen Management (SER License Condition f5)
Pursuant to 10CFR50.44, IP has submitted, via letter dated November 4, 1985, a preliminary hydrogen analysis to the Staff. The NRC's review and approval of the CPS preliminary analysis is expected to be addressed in SSER #6 (prior to
! Fuel Load).
(2) Mark III Containment Issues (SER Outstanding Licensing Issue
, 19 and Confirmatory Licensing Issue #71)
- This item includes Suppression Pool hydrodynamic loads during a Loss of Coolant Accident (LOCA) and Humphrey-related issues. Recent discussions with the NRC reviewer indicate no further information will be required to close these issues. IP anticipates that the remaining issues will i
, be resolved in SSER f6 prior to Fuel Load. i a
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(3) Pump and-Valve Operability Review (PVOR)
'(Portion of SER Outstanding Licensing Issue #7) l IP has developed plans and' actions to close issues-resulting-
. from NRC PVOR audits performed during the week of August 26,
< and November 19-21, 1985. As of March 31,_1986, 120.out of
!- 121 PVOR packages have been reviewed and. vaulted as complete by IP. 1Rie remaining package will be completed and vaulted
- in April. A PVOR completion letter will be submitted to the ,
'NRC after all of the packages are completed. ;
(4) Equipment Seismic and Environmental Qualification l (SER Outstanding Licensing Issue f-7)
Electrical ecuipment environmental qualification issues were l addressed anc essentially resolved in SSER #5. The CPS i . mechanical equipment environmental qualification program is i expected to be closed by the NRC Staff in SSER f6. ,
~I Environmental and seismic qualification packages are now complete. As of April 4, 1986, 20 items remain to be installed. The installation work-for 10 of the items is forecasted to be complete in April, 151e remaining 10_ items
, relate to installation of high efficiency particulate air filters and reactor vessel head spray components (which will i be installed-following reactor vessel head set). A
- completion letter to the Staff, as required by SSER f5, will i be provided by IP after all work has been completed. NRC Staff closure of the remaining issues is anticipated in SSER
- 6. No' impact on Fuel Load from these issues is expected.
] (5) Safeguards and Security j SSER f5, Section 13.7, concludes that the CPS Safeguards and Security Plan meets the requirements of 10CFR73. Security screening of personnel requiring unescorted access for Fuel
- Load is underway.. The CPS security screening program is i
based on accepted industry standards and includes a
- background investigation, psychological evaluation,
- and a i continuing observation program. A-second security screening
. contractor has been hired to provide additional capacity and j screening priorities have been established in order to i complete.this effort prior to Fuel Load. As of March 7,
- 1986, access authorization had been granted for over 76% of i the personnel required for Fuel Load.
4 (6) Fire Protection
, SSER #5, Section 9.5, addressed certain aspects of the l updated CPS Fire Protection Evaluation Report (FPER) and
{ Safe Shutdown Analysis:(SSA) report submitted by' letter i dated September 6, 1985. These matters were identified as l Outstanding Licensing Issue #21 in SSER #5. IP Letter i-i 4
U-600448, dated March 4, 1986, provided Amendment #1 to the SSA/FPER. Resolutions to five of eight " CLIP" fire protection issues have been achieved. As of April 4, 1986, IP has completed a:tions to resolve 19 of the 24 Region III open items from the September 1985 NRC audit. IP Letter U-600461, dated March 7, 1986, provided responses to NRR's audit concerns. IP actions on the remaining audit items will be completed in April 1986.
(7) Technical Specifications All CPS Technical Specifications have received substantial internal review and the applicable Grand Gulf Nuclear Station experience has been incorporated at CPS. The NRC Staff issued the " Proof and Review" copy of the CPS Technical Specifications in a September 4, 1985, letter to IP. Upon Staff issuance of the final copy of CPS Technical Specifications, conformance reviews will be completed and all necessary certifications will be provided to support Fuel Load.
(8) Remote Shutdown System (RSS)
In the letter U-600460, dated March 10, 1986, IP agreed to implement, prior to restart from the first refueling outage, plant design modifications to eliminate the use of jumpers, rewiring, or disconnecting circuits such that Division II equipment can be locally operated in accordance with NUREG-0800, the Standard Review Plan (SRP), Section 7.4.
All Division II controls and equipment are being included in the CPS Technical Specifications, Section 3/4.3.7.4 and the associated Limiting Conditions for Operation / Surveillance Requirements will be implemented coincident with the design modifications. Plant operators will be trained on the procedures for remote shutdown using Division II controls and equipment prior to plant operation above 5% of rated reactor power. In addition, IP will provide a followup submittal committing to perform a one-time test, prior to Fuel Load, of the affected Division II equipment noted above.
G. Emergency Planning and Preparedness During the period November 12-21, 1985, NRC Region III personnel conducted a special appraisal of the onsite emergency preparedness at CPS. NRC Region III Inspection Report 50-461/
85039, dated December 20, 1985, listed 47 open items and 32 improvement items that were identified during the appraisal. By letter dated February 5, 1986, IP has provided Region III with our assessment of the 32 improvement items and planned action (s) ,
for the 47 open items. As of March 20, 1986, actions have been '
completed on 40 of the 47 items. Actions on the 7 remaining open i items, with one exception, will be completed in April 1986. IP j will provide documentation closure packages, to verify completion '
of these actions, to the CPS NRC Resident Inspector's Office as ;
these items are completed. !
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The Integrated Emergency Exercise was. held on December 4, 1985.
Of the six findings noted by the NRC, two were stated (NRC letter dated December 24, 1985) as required to be resolved before Fuel Load. IP actions on these two items are complete with the exception of training on one of the two items which will be completed in April. IP actions required to resolve a third item are also complete (contamination control practices in the Emergency Operations Facility Environmental Lab). No major deficiencies were noted by the Sraff or FEMA from the exercise.
A formal report from FEMA has not yet been received.
H. Exemptions The FSAR documents CPS conformance to the NRC rules and regulations set forth in 10CFR50 including Appendix A (General Design Criteria). A request for exemption from 10CFR50, Appendix J, leak test requirements was submitted by IP in a letter dated December 9, 1985. These exemptions relate to the Main Steam Isolation Valves and the Containment Air Lock. Additional
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information relative to this request was submitted by IP Letter U-600468, dated March 11, 1986. The Staff's notice of environmental assessment and finding of no significant impact for this request was issued il Federal Register Volume 51, No. 32, page 5816, dated February 18, 1986.
I. Design and Construction Assurance Reviews CPS has undergone a series of reviews beyond the normal Quality
, Assurance Program to assure that CPS design and construction conform to applicable requirements. The current status of each of the major reviews is as follows:
'1)
, Independent Design Review (IDR)
Bechtel Power Corporation completed the IDR in 1985 and concluded the CPS design is adequate. Through March 1986, IP actions have been completed on 125 of the 128 IDR action ;
items. The Staff noted in SSER f5, Section 17.5.5, that any l further independent design review of CPS is considered unwarranted.
- (2) NRC Construction Appraisal Team (CAT) Review ,
i The NRC CAT team appraised CPS construction activities on l May 20-31 and June 10-21, 1985. The CAT concluded that i hardware and documentation for CPS construction activities were generally in accordance with NRC requirements and Illinois Power program commitments. In the CAT Report i provided in the Staff's letter dated August 15, 1985, deficiencies requiring additional Illinois Power management attention were identified. Subsequently, Region III issued, by letter dated August 30, 1986, six Notices of Violation.
IP responded to these six Notices of Violation by letter I
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dated October 1, 1985. Currently, IP actions on five of the six Notices of Violation are complete. Of these five, two have been formally closed by the NRC and three'have received NRC reviews and will be closed in a future inspection report. The last item will be completed in April 1986.
(3) Overinspection Program By letter (U-600514) dated April 3, 1986, IP informed the NRC that it has concluded the Overinspection Program for all items remaining in the scope of the program [radwaste (Augmented D), fire protection, structural steel, mechanical / electrical equipment, instrumentation, and instrument piping) and will make the results available at CPS for NRC review.
J. NRC I&E Items IP maintains a formal system for tracking and resolution of all l NRC I&E inspection items, 10CFR50.55(e) items, and 10CFR Part 21 items. As of April 4, 1986, the status of these items is summarized as follows:
NRC 50.55(e) Part 21 Inspection Pending NRC Action for Closure 14 8 102 Require IP Abtion for Closure 2 4 91 4
Total Open Items 16 12 193 Significant progress has been achieved on closure of I&E items in
- the last two months. Additional management attention has been given to this area by IP, and continued management attention by the NRC will be required.
L. Allegations IP maintains three programs for addressing employee concerns. IP
, does not seek any credit for these programs in meeting require--
ments relative to issuance of the Operating License. IP will review all safety-related concerns and will take actions to assure that any concerns that are still open at the time of Fuel l Load will not challenge the safe operation.of the Clinton Power Station.
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If you have any questions or comments concerning the above information, please contact me or Frank Spangenberg of my staff. We will be prepared to discuss the above items with you at your Convenience.
e, yours,
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'.Vice President s . all TLR/cke cc: Director, Office of Inspection and Enforcement, USNRC
- R. M. Bernaro, Director BWR DOL Dr. W. R. Butler, BWR Project Directorate #4 B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety i
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