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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] |
Text
nanvis Fonter t.,umpany Chnton Power Station
. P.O. Box 678
. Chnton,IL 61727 i e
Tel 217 935 5623 i Fax 217 935-4632 l Wilfred Connell i Vice President l ILLIN9BS Pt#WER I l
U-602670 1 A.120 WC-370-96 J December 9, 1996 !
Docket No. 50-461 Mr. A. Bill Beach !
Regional Administrator Region III U.S. Nuclear Regulatory Commission i 801 Warrenville Road Lisle, Illinois 60532-4351 l
Subject:
Clinton Power Station Startup Readiness Action Plan
Dear Mr. Beach:
By letters dated September 17 and 24,1996, we submitted our corrective action plan in response to the September 5,1996, reactor recirculation pump seal failure event and the associated September 11,1996, Confirmatory Action Letter. Since then, we have completed a number of the actions described in our corrective action plan.
In addition, based upon further evaluations, including the results of the NRC's Special Inspection and Operational Safety Team Inspection, our plans have been revised ,
and additional actions incorporated into them. We clearly recognize the need to l accomplish a major shift in the safety culture at CPS to ensure that decisions and actions !
in the plant are made with safety as the first and overriding concern. To this end, we have l included in our startup readiness plan several specific actions to ensure that CPS personnel clearly understand that safety must be our constant focus and takes priority over other considerations.
1)
A "l 120024 ,
9612130051 961209 PDR ADOCK 05000461 p PDR
U-602670
, Page 2 Attachment 1 is our Startup Readiness Action Plan which describes more fully the actions we plan to accomplish prior to startup of CPS, along with the current status of i
completion of these actions. As noted in the Startup Readiness Action Plan, we intend to
, perform formal assessments to verify completion ofpre-startup actions and to monitor the effectiveness of corrective actions to ensure readiness prior to startup. Attachment 2 includes additional technical actions involving plant equipment which will also be resolved l
prior to startup of CPS. Detailed records of the accomplishment of actions are being kept !
at CPS and are available for NRC review. We are also developing a set oflonger-term actions to be taken after startup to further improve our performance in areas of weakness identified by the September 5,1996, event and related assessments and inspections, including methods to monitor the effectiveness of the corrective actions. The Long Term Action Plan is expected to be issued by December 13,1996. This plan will continue to be evaluated for additional action items, and revised, as necessary. We will keep the NRC Senior Resident informed of our progress in completing these activities.
Please call me if you would like to discuss these plans or require any further information.
Sincerely yours, Wil Vice President WEB /csm Attachments cc: NRC Clinton Licensing Project Manager ,
NRC Resident Office, V-690 i Document ControlDesk i Illinois Department ofNuclear Safety l l
l
, Attachment 1
. to U-602670 Page1of15 Startuo Readiness Action Plan Summary This at*=4mant describes the actions included in the Clinton Power Station (CPS) Startup Readiness Action Plan (SRAP). The SRAP encompasses actions to ensure that CPS can be returned to service safely and reliably.
The SRAP was developed based upon Illinois Power Company investigations and reviews of the September 5,1996 Reactor Recirculation pump seal failure event, results of other recent Illinois ,
Power Company assessments and reviews, and results of the NRC Special Inspection and l Operational Safety Team Inap~* ion conducted following the September 5 event. The SRAP incorporates all actions from Ilhnois Power Company's September 17 and 24,1996 Confirmatory l Action Letter responses.
The SRAP covers four areas determined to have caused the September 5,1996 event:
. Procedure Compliance / Adequacy -- includes actions to ensure that procedures are clear and consistent, and that arpa *=* ions for procedure compliance are understood and implemented.
- Conservative Decision Making / Human Performance - includes actions to ensure that personnel understand that safety focus is our top priority and implement this understanding l through conservative decisions. Also, this area includes actions to ensure that plant equipment operating limits reflect this conservative approach.
. Management Oversight - includes actions to ensure that managers and supervisors understand their oversight roles and maintain a conservative " big picture" view of plant and a l focus on operational safety.
- Plant Material Conditions - includes actions to ensure that plant equipment is maintained to support safe and reliable operations.
In each of these areas, the SRAP defines specific actions to be taken, and designate the CPS l department responsible for accomplishment of the action. As stated earlier, these actions will be l completed prior to startup. l In addition to specific actions to be taken, the SRAP describes the assessments that will be performed to ensure startup readiness, including the Nuclear Assessment Department verifying completion of SRAP actions, and a formal assessment for determining readiness for startup.
l Startup will be accomplished utilizing a startup plan which includes hold points at which startup l progress and performance will be assessed prior to proceeding further. A startup readiness self-assessment will also be conducted at the direction of the Assistant Plant Manager-Operations.
Those actions in this attachment that were included in Illinois Power's earlier Confirmatory ,
l Action Letter response are indicated by (CAL] in parentheses after the action, along with a j reference to the portion of the response in which the action originally appeared.
1
, Attachment 1 to U-602670 Page 2 of15 Startup Readiness Action Plan L Procedure Compliance / Adequacy l NA Action Items Responsible Depaumfat i i
, 1. The adequacy ofpolicy statements and general Management Team procedures regarding conduct ofoperations and i procedure compliance will be reviewed, and changes I made as necessary to ensure that expectations and !
, requirements regarding conservative decision-making i
and procedure compliance are clearly set forth. ,
)
- (CAL II.1)
Status: Verificationin process.
j 2. A seminar on procedure compliance including Main Nuclear Training Control Room activities, turnover, log keeping, and Department l communications will be provided to the following
- personnel
- (CAL II.2)
- Site Managers e Plant StaffDirectors/ Assistant Director-Operations
- Work Control Team Leaders e Facility Review Group Members e Licensed and non-licensed Operations personnel
. Shift Technical Advisors
. System Engineers
- e- Active operatorlicense holders
- Management monitors l Status: Verification complete.
.l J
_ _ .__ __ ._. . _ . _ - - _ . _ . _ _ _ . _ _ _ . . _ _ _ . . _ _ . _ _ _ _ _ _ . _ - ___-_m-.
I, Attachment 1 ts U-602670 Page 3 of15 1
ML Action Items Responsible Department
- 3. Procedures used in the following activities will be Plant StaffDepartments j reviewed to ensure clarity, consistency, and ease ofuse,
{ and changes will be made as warranted. (CAL II.3)
. plant startup
, e single loop operation
! e leak detection
. reactor coolant leakage e procedure adherence e long cycle lineup and operations
)
e conservative decision making
. management oversight
. RR seal problems Status: Verificationin process. 1 1
- 4. Operating crews will receive simulator practice on Plant Staff normal plant operation and startup activities to ensure Departments / Nuclear l familiarity with associated procedures, and identify any Training Department areas for procedure revision or enhancement. (CAL II.4)
)
Status: Verification complete.
- 5. The critique process will be revised to include: (CAL Plant Staff II.5)
. Appropriate, independent and objective inputs from other departments
. In-depth fact finding
. Expectations for timalia= of the evaluation and documentation are clear and enforced
. Specific detenninations on whether procedure noncompliances or nonconservative operations I occurred
. A timely review and concurrence of the facts by appropriate senior management Status: Verification complete.
. Attachment 1 to U-602670 Page 4 of15 h Action Items Responsible Department
- 6. Site personnel will participate in a seminar on procedure Nuclear Training compliance. (CALLTII.1) Department Status: Verification complete.
- 7. A review of procedures used for (a) movement of new Plant StaffDepartments fuel and (b) movement of fuel during refueling will be I conducted to ensure clarity, consistency, and ease ofuse and changes will be made as warranted. (CAL LT II.2)
Status: (a) verification complete, (b) verification '
complete.
- 8. Current methods to monitor and measure procedure Nuclear Assessment compliance program effectiveness will be assessed and Department revised. (CALLTII.3)
Status: Activities in progress;
- 9. Evaluate procedure process (use, revision, backlog). Independent Safety (CAL LTII.4) Engineering Group Status: Activities in progress. Procedure Assessment Plan issued.
- 10. Review of System Operating Procedures Operations Operations Department personnel will perform a review /walkdown of system operating procedures. The l purpose of this walkdown is to identify and correct j procedure inadequacies that prohibit successful l completion of an operational evolution. l l
Status: Activity in progress. Project began 11/1/96. l i
I
~ '
Attachment 1 to U-602670 Page 5 of15 Hg Action Items Responsible Denartment
- 11. Review of Station Surveillance Procedures Operations Maintenance The operating crew personnel will review scheduled surveillances prior to their performance to identify and correct inadequacies that prohibit successful completion of the surveillance activities. This review will be conducted in accordance with Operations Standing Order (OSO)-92.
Status: Activityin progress. Currently, surveillances are being reviewed 1-2 weeks in advance.
- 12. Maintenance Electrical Control and Instrumentation (EC&I) senior maintenance personnel who have experience with the performance of surveillances will review a random sample of the procedures, including at least 25% ofnli RF-6 surveillances to identify problems with methods or criteria.
Status: Activityin progress.
- 13. EC&I senior maintenance personnel who have Maintenance experience with performance of surveillances will review all outstanding comment control forms on surveillance procedures to assess if changes are timely and if significant problems exist which might call into question the effectiveness of the results.
1 Status: Activity in progress.
- 14. An assessment will be made of the EC&I maintenance Maintenanc' personnel who are qualified to perform surveillances to assure the combination of skills, procedures and training sufficiently prepares our technicians to properly perform surveillances. This will be accomplished by performing walk throughs of various surveillances by personnel with different levels ofexperience.
Status: Activity in progress.
1 J
Attachment 1
, to U-602670 Page 6 of15 l
& Action Items Responsible Denartment
- 15. EC&I supervision will review the last 35-50 TPDs or Maintenance PACS to determine the significance of the changes and affect on training, previous acceptability and effectiveness of the change.
Status: Activity in progress.
- 16. Field observations of RF-6 EC&I surveillances will be Maintenance performed to assess the actual quality of performance of the package. 4
~
l Status: Activityin progress. l
- 17. Provide training to appropriate personnel on Licensing 10CFR50.59 purpose, process and applicability. !
Status: Under development.
i 1
9
1 Attachment 1 j ,
to U-602670 Page 7 of15 l
- IL Conservative Decision-Making / Human Performance !
- & Action Items Responsible Denartment i
- 1. Expectations of conseivative decision making CPS Management Team l emphasizing safety of operation will be clearly defined and provided in writing to the following personnel:
(CAL I.1)
. Site Managers
. Plant StaffDirectors/ Assistant Director-Operations
. Work Control Team Leaders
. Facility Review Group Members
. Licensed and non-licensed Operations personnel
. Shift Technical Advisors
. System Engineers
. Active operatorlicense holders
. Management monitors Status: Verification complete.
- 2. A seminar on conservative decision making emphasizing Nuclear Training safety of operation will be provided to: (CAL I.2) Department / CPS Management Team /
. Site Managers Nuclear Station
. Plant StaffDirectors/ Assistant Director-Operations Engineering Department
. Work Control Team Leaders
. Facility Review Group Members
. Licensed and non-licensed Operations personnel
. Shift Technical Advisors
. System Engineers
. Active operatorlicense holders
. Management monitors Status: Verification complete. I
- 3. Plant or equipment condition limits will be provided to Plant Staff Dcpartments ensure conservatism: (CAL I.3)
. Operation of the plant at power, with Reactor Recirculation pump seal degradation exceeding conservatively established limits will not be permitted.
Status: Verification complete.
, . Attachment 1 l
. to U-602670 l Page 8 of15 l 1
& Action Items Resoonsible Department
- 4. Personnelinvolved have recognized and acknowledged Plant Staff their roles and errors made in this event. The Plant
', Manager will personally discuss elements of this event l
with each shift crew. (CAL VI.1) l I
~
Status: Activityin progress.
S. Plant Manager will meet with each crew member to Plant Staff ensure the following: (CAL VI.2)
. understanding of safe and conservative operation ,
e impact of operator actions and possibility for negative plant response e responsibility for placing plant in safe configuration
. planning for the n=rpacted
. procedural compliance is required even when no one is watching
. understanding of plant material conditions which impact plant operations Status: Activityin progress.
- 6. Additional plant or equipment condition limits will be Plant StaffDepartments developed as appropriate based on CPS and industry operating experience, to ensure conservatism. (CAL LT I.4)
. Turbine Vibration Status: Activityinprogress.
~ 7. Review April 1996 incident corrective actions for Licensing adequacy, timeliness and effectiveness. (CAL LT IV.1) ;
i Status: Verification in process.
- 8. Review SOER 92-01, " Reducing the Occurrence ofPlant Licensing Events Through Improved Human Performance,"
response for adequacy. (CAL LT IV.2)
Status: Verification complete.
,y
Attachment 1 ts U-602670 Page 9 of15 ML Action Items Responsible Departmut
- 9. Simulator Restan Training Operations / Nuclear Training Department Active licensed operators and Shift Technical Advisors / Shift Engineers will participate in startup training on the simulator. This training session will reinforce expectations on management oversight and roles, procedure compliance, conservative decision making and reactivity management. The simulator session will be conducted with the intended crew composition as we rotate into normal shift compliments and will include management monitors.
Status: Activity has not started.
i
- . . . ~ - - . - . _---.._-- --.-.--. ..-.. . . - - - -
I I
' Attachment 1 j -
to U-602670 Page 10 of15 i
i 1 l III. Management Oversight !
j No Action Items Responsible Department i
] 1. Roles, duties and expectations of personnel involved in Plant StaffDepartments operational oversight activities will be reviewed and revised. (CALIII.1)
Status: Veri 6 cation complete.
l 2. Provide a briefing on operational oversight roles and Plant StaffDepartments/
j responsibilities to the following personnel: (CAL III.2) Nuclear Training Department i e Operating crews
! . Active Operator License Holders j 1 . Shift Technical Advisor {
- e System Ragia-s j e Assistant Plant Manager-Operations and Assistant i
! Director-Operations
- . Plant Manager t e Management monitors j Status: Verification complete.
i
- 3. During restart activities and until stable power operation Plant StaffDepartments i is achieved, myerier.ced plant personnel will be assigned l to monitor main control room activities. They will be j specifically be charged with assessing the proper oversight functions by line management. (CAL III.3)'
i
)
Status: Activity in progress, and will continue through
- startup to stable power. Also awaiting revised
- work schedule for Management monitors. Draft Management monitors objectives is presently i j being reviewed.
l l 4. A startup plan will be developed which provides " hold Plant StaffDepartments !
l points" at which progress in the startup, equipment i
- conditions and appropriate next steps are evaluated by Operations management and the shift crews. (CAL III.4)
Status: Verification in process.
i 1
1 1
l ,
~
Attachment 1
. to U-602670 Page 11 of15 l
h Action Items Responsible Department i
- 5. Methods will be developed to monitor operational Nuclear Assessment decision making to ensure that expectations continue to Department be met and are reinforced. (CAL LT I.3) l Status: Verification in process.
- 6. A process will be established to ensura that personnel Plant StaffDepartment ,
who may be assigned to operational positions which have oversight responsibilities will be briefed on those {
4 responsibilities prior to assuming the position. (CAL LT III.1)
Status: Verification complete.
- 7. The Senior Management Team will conduct a self- Vice President and Senior critique of personal performance related to this event and Management Team identify areas for improvement. (CAL LT VI.1)
Status: Activities in progress.
- 8. Establish a lower threshold for initiating assessments Nuclear Assessment based on events, conditions or trends. (CAL LT VI.2) Department Status: Activityinprogress.
1 Attachment 1 to U-602670 Page 12 of15 l l
IV. Plant Material Conditions
& ActionItems Responsible Deoartment
- 1. The "B" Reactor Recirculation (RR) pump seal was Nuclear Station !
replaced and will be tested. (CAL V.1) Engineering Department 1
Status: Verification process, a) Assembly and l preliminary testing activities have been verified.
l b) This item cannot be verified as complete until PMT is performed at plant startup.
l 2. The Drywell Floor Drain (RF) leak detection and flow Nuclear Station measurement instrumentation was made operable and Engineering Department l testei (CAL V.2) 1 j Status: Verification complete.
- 3. The Drywell Equipment Drain (RE) leak detection and Nuclear Station 4
flow measurement instrumentation was made operable Engineering Department j and tested. (CAL V.3) !
! Status: Verification complete.
I
- 4. Outstanding corrective MWRs will be reviewed to Facility Review Group
} evaluate material conditions that impact plant operations.
(CAL V.4)
Status: Verification complete.
- 5. Develop and implement the following actions for RF leak Nuclear Station detection systems
- (CAL LT V.3) Engineering Department e Incorporate the leak detection calculation method (based on RF sump fill times) into the process
- computer.
. Perform complete and thorough cicW g of the RF
- weir V-notch system.
- e Determine and implement float setpoints change for
i improved time response for the alternate (LD-027)
- leak detection system which is based on RF sump pump discharge flow measurements.
l Status: Activityin progress.
l l
. l l
Attachment 1 to U-602670 l Page 13 of15 j f
j Ng Action Items Responsible Denartment
- 6. Incorponte the leak detection calculation method (based Nuclear Station
- on RE sump fill times) into the process computer. (CAL Engineering Department i i
LT V.5) i i
- Status
- Activityin progress.
+
l t
a 7. The Vice President, Manager-CPS and Manager-NSED Senior Management Team i i will assess long term material deficiencies on a quarterly i i basis to ensure that corrective actions are being pursued
! aggressively and operational needs are clearly being met.
l (CAL LT V.6) (This will satisfy the initial assessment.
- The quarterly assessment will be a long term action.)
- At a minimum this assessment will address
f 1
. Main Control Room Deficiencies j . Operator Work Arounds j e Maintenance Rule Category A.I. Systems
. . Top 10 Long Standing Material Problem List i i
j Status: Activities in progren 1
j 8. Review 1995 and 1996 NRC Inspection Report material Licensing i condition items for adequate response. (CAL LT V.7)
Status: Verification complete.
l 4
l
l l
' Attachment 1
, ts U-602670 .
i Page 14 of15 i
& Action Items Responsible Department j
- 9. Operabilitv/ Generic Letter 91-18 Review adequacy of past operability evaluations and Eng*meering and determinations. Identify and resolve any open issues Operations ;
which would result in equipment operability being questionable.
Status: Activities in progress. !
Develop Operability Determination Program for Clinton Power Station. Engineering and Operations Status: Activities in progress.
Develop guideline for Reportability.
Licensing l Status: Activities in progress. j Train appropriate engineering personnel on Operability Engineering !
Determination Program.
Status: Under development.
Train appropriate operations personnel on Operability Operations Determination Program.
Status: Under development.
l t
l f
Attachment 1 )
to U-602670 i Page 15 of15 l
Na Action Items Responsible Department
, 10. Action Plans Review adequacy ofpast action plans and determine if Engineering any actions are required.
- Revise CPS 1010.0' accedure on action plans.
Determine if any changes are needed to action plan process / program.
Status: Activities in progress.
Provide guidance to appropriate site personnel on action Operations plan use as it pertains to manipulation of plant equipment. !
Status: Under development.
- 11. Butterfly Valves Perform bounding analyses for pipe stress and supports, Engineering and update seismic analyses to validate initial operability evaluation and to determine if any further RF6 actions .
are required to assure operability is maintained.
Status: Engineering evaluation completed. Awaiting '
completion ofECN 29942 and 29943 for FC pipe i supports.
I
- 12. Conduct a review of open MWRs (except CM-MWRs) Maintenance / Operations /
older than 6 months old to verify no material deficiencies Engineering exist that significantly affect plant operations.
Status: Activities in progress.
Attachment 2 l
. to U-602670 l Page1of2 i Technical Actions Reautred for Startun This attachment describes the technical actions required to be resolved for startup of Clinton
?
Power Station. Although these actions are not described in the Startup Readiness Action Plan, i they will be complete prior to startup. These actions include those required by Technical Specifications or equipment operability concerns.
- No. Action Items Responsible Department
- 1. Resolve immediate operability issues with feedwater NSED check valves 10 A/B and 32 A/B.
t J
Status: In progress. ,
1 i 2. Provide assurance that feedwater check valves will NSED i remain operable for one operating cycle. This will be i required within 60 days of plant startup.
4 Status: Not started.
1 1
- 3. Determine and resolve operability issues within the scope NSED {
i of GL 96-06. Written response will be provided in !
4 accordance with the generic letter reportmg l
- requirements.
i I. Status:In progress.
- 4. Ensure that AR/PR system is an effective tool for Operations l j identifying radiological conditions within CPS. Provide !
l training and expectations to Radiation Protection and i Operations personnel on monitoring and use of the l system.
Status: In progress.
- 5. Review the current population ofidentified operator Operations workarounds for proper priority and scheduling of resolution. Ensure adequatejustification for those that will not be corrected in RF-6.
Status: In progress.
Attachment 2 to U-602670 Page 2 of 2
& Action Items Responsible Department
- 6. Review the current population ofidentified Main Control Operations Room deficiencies for proper priority and scheduling of resolution. Ensure adequatejustification for those that !
are not scheduled in RF-6.
Status:In progress.
l l