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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217J4331999-10-15015 October 1999 Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station ML20217A9881999-10-0101 October 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A7361999-10-0101 October 1999 Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs ML20217J1251999-09-30030 September 1999 Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC ML20217J1421999-09-30030 September 1999 Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC ML20212G6751999-09-22022 September 1999 Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability ML20217H3421999-09-17017 September 1999 Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed ML20211Q2671999-09-0808 September 1999 Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000 U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 ML20211D2201999-08-23023 August 1999 Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired ML20211A8931999-08-19019 August 1999 Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 ML20210U3771999-08-12012 August 1999 Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210A4401999-07-16016 July 1999 Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations ML20209G7671999-07-12012 July 1999 Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed ML20209D5691999-07-0707 July 1999 Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20196J9651999-07-0202 July 1999 Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements ML20196J7131999-06-30030 June 1999 Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1 U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology ML20196A3471999-06-16016 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology 05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed 05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors ML20209G7731999-05-27027 May 1999 Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999 Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999 Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5 U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999 Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999 Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999 Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999 Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999 Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999 Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999 Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f) U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999 Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3) 05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999 Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999 Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999 Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired 1999-09-22
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Text
1 llunois Power Company Chnton Power Staton
,- P O. Box 673 Chnton. IL 61727 Tel 217 935-BBB1. Ext 3200 John G. Cook V.Ce Presirient .
U-602284 -l ILLIN#)lS L30-94(05-0 6)LP 1 POWER 8G. i20 JGC-055-94 l
-l Docket 'No. 50-461 May 6, 1994 l Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Illinois Power's (IP's) Submittal of Additional Information for the Requested Extension to Generic Letter (GL) 89-10 Activities
Dear Sir:
This letter submits additional information for a schedule extension of Clinton ;
Power Station's (CPS's) GL 89-10 activities. This additional information was requested in )
an NRC letter dated February 28,1994. The information requested was also discussed during a February 24,1994, teleconference among R. L. IIague and C. A. Gainty (NRC Region 111); T. G. Scarbrough, D. V. Pickett, et al (NRR); and R. F. Phares, J. A. -!
Puzauskas, et al (IP). This information was requested prior to the NRC granting an extension of the completion date for CPS's GL 89-10 Program. The requested extension will be from June 28,1994, to the end of the sixth refueling outage (RF-6), scheduled to l
begin in October 1996. '
The additional information requested for extension approval is provided in Attachment 2. On the basis of this information and IP's initialletter (U-602225), sent January 13,1994, IP believes it is acceptable to extend the GL 89-10 requirements through -
RF-6. If there are any questions regarding this submittal, please contact us. Attachment i provides an amdavit supporting the facts set forth in this letter and its attachments.
Sincerely yours,
(
- G. Ook ice President JSP/csm Attachments cc: NRC Clinton Licensing Project Manager NRC Resident Omce, V-690 '
Regional Administrator, Region III, USNRC lilinois Department of Nuclear Safety 100CU1 9405160113 94o506 -
f#
gDR ADOCK 05000461 "
r PDR '
Attachment I to U-602284 J. G. Cook, being first duly sworn, deposes and says: That he is Vice President of the Nuclear Program at Illinois Power; that this letter supplying additional information for the Generic Letter 89-10 extension has been prepared under his supervision and direction; that he knows the contents thereof; and that to the best of his knowledge and belief said letter and the facts contained therein are true and correct.
Date: This k day ofMay 1994.
Signed: K J.G. Cook i
STATE OF ILLINOIS l SS.
f
.htd+F COUNTY J Subscribed and sworn to before me this _lo[ day ofMay 1994.
'OfflCIALSEAL' Notary mais , a<dedE d 2 j MyCommission Expires 114447 (Notary Pubfic) c::::::::::::::::.:::::::
Attachment 2 to U-602284 Listed below is a synopsis of the questions contained in NRC letter dated February 28,1994, and discussed during a February 24,1994 teleconference and the information required to fully answer them.
ERC Ouenippn_1; Which of the 70 Motor Operated Valves (MOVs) for which this extension is requested need to be extended to RF-67 IP Rtsgqnse:
Listed below are tables describing which MOVs are scheduled for RF-6, MOVs scheduled for RF-6 that have the potential to be rescheduled for RF-5, and MOVs scheduled for RF-5 that have the potential to be rescheduled for RF-6. This latitude is required to provide flexibility in outage scheduling so that a single MOV -
such as ll321F067A (outboard main steam isolation valve [MSIV] above seat drain valve) would not force a considerable extension to RF-5 if scheduling constraints became an issue within RF-5.
MOVs to be Completed in RF-6 VALVE AS-LEFT VS. Valve EQUIPMENT DESCRIPTION VALVE REQUIRED AP (psi)
ID NUMBER SIZE THRUST (EIN) Required A s-le ft includes Mmimum Minimum water Thrust Obs) Thrust Obs) hammer Globe 1E32F002J MSIV LEAKAGE CONTROL SYSTEM INBOARD VALVE 1.5" 1,000 9,510 25 1E32F002N MSIV LEAKAGE CONTROL SYSTEM INBOARD VALVE 1.5" 1,000 6,536 25 1E32F003A MSIV LEAKAGE CONTROL SYSTEM INBOARD 1.5" 1,000 6,635 25 DEPRESSURIZATION VALVE 1E32F003E MSIV LEAKAGE CONTROL SYSTEM INBOARD 1.5" 1,000 8,566 25 DEPRESSURIZATION VALVE 1E32F003) MSIV LEAKAGE CONTROL SYSTEM INBOARD 1.5" 1,000 8,633 25 DEPRESSURIZATION VALVE 1E32F003N MSIV LEAKAGE CONTROL SYSTEM INBOARD 1.5" 1,000 9,164 25 DEPRESSURIZATION VALVE Gate (Flex Wedge) 1E32F006 MSIV LEAK CONTROL SYSTEM OUTBOARD BLLED VALVE 2.5" 768 4,242 25 1E32F007 MSIV LEAK CONTROL SYSTEM OUTBOARD BLEED VALVE 2.5* 768 4,387 25 1E32F008 MSIV LEAK CONTROL SYSTEM OUTBOARD 2.5" 762 3,664 ~22 DEPRESSURIZATION VALVE 1E32F009 MSIV LEAK CONTROL SYSTEM OUTBOARD 2.5" 762 5,069 22 DEPRESSURIZATION VALVE MOVs to be Completed in RF-6 with the Potential to be Rescheduled for RF-5 Globe 1E32F001A MSIV LEAKAGE CONTROL SYSTEM INBOARD VALVE 1.5" 1,000 6,489 25 1E32F001J MSIV LEAKAGE CONTROL SYSTEM INBOARD VALVE 1.5" 1,000 9,440 25 1E32F001N MSIV LEAKAGE CONTROL SYSTEM INBOARD VALVE 1.5" 1,000 7,660 25 1E32F002E MSIV LEAKAGE CONTROL SYSTEM INAOARD VALVE 1.5" 1,000 6,887 25 1
_. - - - - . - - - . - - - - .- - -. - . -- -- . ~.
Attachment 2 ,
to U-602284 l
. f\10Vs to be Completed in RF-5 with the Potential to be Rescheduled for RF-6 1
l AS-LEFT VS, Valve l DESCRIPTION VALVE REQUIRED AP (psi) '
SIZE THRUST VALVE EIN Requwed As left includes Muumum Minunum water Thrust Obal Thrust Obs) hommer Globe 1021F067A OUTBOARD MSIV ABOVE SEAT DRAIN VALVE 1.5" 3,625 8,040 1190 1821F0678 OUTBOARD MSIV ABOVE SEAT DRAIN VALVE 1,5* 3,625 8,693 1190 1821F067C OUTBOARD MSIV ABOVE SEAT DRAIN VALVE 1,5" 3,625 7,895 1190 1B21F067D OUTBOARD MSIV A50VE SEAT DRAIN VALVE 1.5" 3,625 7,714 1190 NILChuntion_2; The licensee's submittal should provide more information justifying that the valve factor, the diameter used in calculations / evaluations, stem friction coeflicient and packing load assumed are appropriate. Discuss the applicability of the Electric Power Research Institute (EPRI) test data on globe valves to its valve factor assumptions. Which butterfly valves will need an extension past June 28,1994?
IP Ikspnom l
1 Valve Fagfoi- Page two, Paragraph two, of NRC Generic Letter 89-10, Supplement 6, states, "As a mimmum, i the stafrexpects all licensees to have their valves set up with the best available industry data by the original completion date accepted by the stafT, whether or not all testing has been completed." Early in 1993, during preparation for the fourth refueling outage that began in September 1993, IP recognized that the GL 89-10 requirements for all MOVs could not be completed by June 1994. At that time, IP selected the assumptions to be used in evaluating the capability of MOVs based on available Clinton-specific and industry information. IP ensured that safety-significant MOVs, as determined by the probabilistic risk assessment (PRA), as well as low ,
safety-signiGcant MOVs that did not have margin to meet the selected assumptions, would be completed prior to June 28,1994. Additionally, those valves that could be completed during non-outage periods were also )
scheduled for completion prior to June 28,1994. This left 70 low safety-signi6 cant MOVs that were planned ;
for extension to subsequent refueling outages.
Based on the information at that time, the selection of a 0.5 valve factor for final setting of Anchor Darling (A/D) gate valves was believed to be a bounding value for all MOVs except those with significant hardware problems.
The selection of a 0.45 valve factor was believed to be a nearly bounding value that would be reasonable for !
interim settings for the population of the low safety significant valves that would be extended to the fifth and sixth refueling outages to complete final settings. (Note: Low safety-signiGcant MOVs collectively contribute less than 0.01% of the MOV contributions to core damage frequency and failure to isolate containment, and provide for containment heat removal, containment venting, and containment / reactor pressure vessel flooding.)
Since that time, IP has completed dynamic testing of 18 A/D gate valves with resuhing closing valve factors ranging from 0.14 to 0.84, with an average closing valve factor of 0.49 based on the highest recorded thrust, up l to and including harJ seat contact. IP has carefully reviewed these test results and determined that 0.45 is still a l reasonable valve factor for interim setting oflow safety-signi6 cant valves. This chosen valve factor is high enough that it covers the range of A/D gate valves as long as the valve internal condition is good. The higher 2
l Attachment 2 i to U-602284 i valve factors obtained were attributed to the particular valve internal condition, not the specific group of valves (e.g., size, pressure class, etc.) For valves in good internal condition,0.45 is a nearly bounding value for closing valve factor. This value is also supported by the EPRI test results for A/D gate valves that show an average closing valve factor of 0.44 based on the highest measured thrust, up to and including hard seat contact.
IP maintains that the use of a 0.45 valve factor is appropriate for the interim period of the extension. In addition to the low safety significance of the valves and the test data discussed above, the probability of the occurrence of an accident during this brief period, coincident with the conditions that would result in these valves experiencing their maximum difTerential pressure, is very low.
Ripmeter u3ed in calcul_ations/evahtations - CPS uses the mean seat diameter for actuator sizing and switch setting calculations. The mean seat diameter is also used to calculate valve factors from data obtained during CPS dynamic testing.
1 SirrfriclinnggsDicierit - The average stem friction coeflicient obtained during dynamic testing at CPS is below 0.15. The 0.18 value used in the evaluation provides conservative estimates of the actuator, motor, and vsive torques associated with the as-lef1 thmst values. ,
hckialaad nsumption - CPS test data shows that the average packing load for CPS valves is approximately 40% of standard packing load assumptions provided in the Limitorque sizing criteria (SELs). Therefore, the 70% assumption used for the interim reasonable-assurance evaluation is conservative.
EPRllesLdma_codehtvalves - A 1.1 valve factor was used in this evaluation for globe valves. IP's test data supports a 1.1 valve factor. All but two of the globe valves for which this extension is requested have more than twice the calculated minimum required thrust. The two that do not (lE12F037A and IE12F037B) are closed and are in their safe position during normal plant operation. Therefore, reasonable-assurance exists for all globe valves for this inteiim evaluation. IP is aware of EPRI globe valve testing efTorts and will continue to i review EPRl's results for impact on IP's GL 89-10 switch setting calculations.
Rutted]y_valyeji- This extension request did not include butterfly valves as IP intends to complete butterfly valves to GL 89-10 requirements by June 28,1994.
NRC_Que31igrL3; The licensee should discuss more specifically its assumptions in determining degraded voltage capability of the extended-schedule MOVs.
IP_RtsPanst The degraded voltage methodology used for GL 89-10 a:tuator sizing and switch setting calculations is listed below:
The application factor is set at 0.9. This value is specified in the Limitorque SELs.
3
Attachment 2 to U-602284 The available voltage during valve operation would be the minimum voltage identified in CPS degraded voltage calculations.
The motor torque is reduced by the square of the voltage when the available voltage drops below 100%
Motor torque is based on rated name plate torque.
The degraded voltage methodology used for this interim, reasonable-assurance evaluation is listed below:
The application factor is set equal to 1.0. Limnorque permits a 1.0 application factor for evaluation purposes. In addition, Limitorque Technical Update 93-03 indicates that use of a 1.0 application factor is allowable when voltage is degraded from 100%
The available voltage during valve operation would be the minimum voltage identified in CPS degraded voltage calculations.
The motor torque is reduced by the square of the voltage when the available voltage drops below 100%
Motor torque is based on rated name plate motor torque.
The torque switch settings for some valves were above rated motor torque at degraded voltage conditions. This was considered acceptable, provided that the minimum required thrust is supplied at the degraded voltage condition and the valve has no active opening safety function. 1 Seven MSIV Leakage Control system valves had torque switch settings above rated motor torque at !
degraded voltage conditions (1E32-F006,1E32-F009,1E32-F001J,1E32-F002J,1E32-F003E, IE32-F003J and IE32-F003N). In addition, the switch settings for two of these valves were above motor stall torque at degraded conditions. These seven MOVs were considered acceptable because the minimum required thrust is provided at the degraded voltage condition and it is unlikely that these valves would be required to be reopened once they are closed.
Note: All DC MOVs have been completed (extension request does not include DC MOVs).
MLC_Questien 4:
The licensee should provide justincation for not including diagnostic inaccuracy. This justifcation is limited to l those MOVs whose thrust setting is less than 25% above the minimum thrust requirements per discussion during the February 24,1994, teleconference.
LP Re3 pang l
This evaluation is for an interim period until such time as the actuator switches can be readjusted in RF-5 or RF-6 to current switch setting criteria which accounts for potential diagnostic inaccuracy. On the basis of the Febmary 24,1994, teleconference,60 of the 70 MOVs for which this extension is requested are acceptable 4
Attachment 2 to U-602284 because the measured thrust is at least 25% greater than the minimum required thrust. The ten MOVs listed below have adequate margin for the interim period until RF-5, which is scheduled to begin in March 1995. i Justification of acceptability, with a margin less than 25%, for the required nine-month extension period is ,
included with each of the ten MOVs (including ICCl27 discussed below). l l
N'ote: A minor error was found in the Component Cooling Water (CC) differential pressure calculation since the original reasonable-assurance evaluation. As a result, one additional MOV (ICCl27) was identified with less than a 25% margin, and the remainder of the CC MOV margins decreased slightly.
ICC054 - Oulbaard CC ContainmenLisolation Valve PRA analysis determined that the worst-case scenario used to develop the CC differential pressure (dP) calculation was not credible. This scenario did not take credit for the motor operated valves located upstream of ICC054 having shorter stroke times. As such, the upstream MOVs will close prior to ICC054. The dP calculation will be revised with an appropriate credible scenario which will result in the setpoint for this valve having greater than 25% margin.
ICC049 - Outboard CC_Cantainment Isolation Valve PRA analysis determined that the worst-case scenario used to develop the CC dP calculation was not credible Reanalysis using a credible worst-case scenario will reduce the dP such that the as-left switch setting will have greater than 25% margin. The dP calculation will be revised accordingly.
LCC060. LCCl21and ICCl28 - Initoard CC Containment Isolation Valves The original evaluation did not take credit for flow through other flow paths such as fuel pool cooling, auxiliary toiler and other smaller alternate paths. In reality, flow will always be present through these paths when the system is in service. When credit is taken for these alternate flow paths, the differential pressure across these valves is reduced and the current setpoint provides greater than 25% margin. The differential pressure calculation will be revised to take credit for flow through these alternate flow paths.
11H2-F028 A - Inhaard ConJainmqnJJpnyJsolation Valve The thrust value for this MOV was measured using a VOTES calibrator clamp as an auxiliary sensor during RF-3 and has an overall potentialinaccuracy of 9.2% including torque switch repeatability and torque correction factor (TCF). This MOV has adequate margin in the opening direction. - The motor has capability to close the valve, but the existing torque switch setting provides less than a 9.2% margin. However, reasonable-assurance of the MOV ftmetioning for this interim period is provided below.
This valve has two closing safety functions: 1) isolate containment, and 2) divert Low Pressure Coolant injection (LPCI) flow to the reactor when containment spray is terminated.
- 1) The containment isolation function will be met because the valve is normally closed. The only time it is i opened during plant operation is fo'r quarterly stroke time testing. Consideration of an accident requiring containment isolation during stroke time testing is not credible based on the short time that the MOV is out of position.
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Attachment 2 to U-602284 2)_ The valve has adequate capacity to perform its second safety ftmetion of diverting flow to the reactor. The limit switch will remain in the circuit until the valve is essentially closed (valve stroke time is 74 seconds and the limit switch remains in the closing circuit until the last 200 to 1000 milliseconds of stem travel). At this point, the valve will be sufriciently closed to ensure that Dow is diverted back to the reactor.
IE12-F028B -Inboard Containment Spray Isolation Valve ,
The thrust value for this MOV was measured using a VOTES calibrator clamp as an auxiliary sensor during RF.3 and has an overall potential inaccuracy of 9.2% including torque switch repeatability and TCF. The current 13,5% switch setting margin envelops the 9.2% potential inaccuracy.
IFP079 - Inh _oard Drywell Isolation Valve The original assumption for IFP079 thrust requirements is no longer appropriate due to modification FP-087 installed during RF-4. This modification changed the position of the upstream isolation valve to closed during nonnal plant operation. As a result, this valve will have little or no dP to close against, and the existing switch setting will provide greater than 25% margin. Additionally, a design change to maintain this valve in a normally-closed position will be issued. At that time, this MOV will be deleted from the GL 89-10 scope since it would no longer have an active safety function.
IVP004hQuthgani VP Containment isolation Valyg The thrust value for this MOV was measured using a VOTES calibrator clamp as an auxiliary sensor during RF-3 and has an overall potential inaccuracy of 9.3% including torque switch repeatability and TCF. The current 8.7% switch setting margin is considered acceptable for this interim reasonable-assurance evaluation.
LEjl2-1037B - Inhgard ReiduaLLigat Removal (RIIR) Containment Isolation Valve The safety function of this valve is to close to provide containment isolation. This containment isolation function will be met because the valve is normally closed during plant operation. The only time it is opened is for quarterly stroke time testing. Consideration of an accident requiring containment isolation during stroke time testing is not credible based on the short time that the MOV is out of position. Therefore, since the MOV will be out ofits safety position for only a short time and there exists a 23% margin, reasonable-assurance l exists that this MOV will function. l MLC_Qugitio_qi The licensee's submittal does not justify that its planned method for periodic verification will ensure that safety- )
- related MOVs continue to be capable of performing their design-basis safety function. l IP3Acan_nx Illinois Power understands that approval of this request for extension is not to be construed or interpreted as approval ofIP's method for periodic verification that safety-related MOVs continue to be capable of performing i their design-basis safety function.
6 gm y p- y - -
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Attachment 2 to U-602284 ADDENDUNLTD_QRIGINAL LETTER . U-6022U As described in IP's original letter requesting an extension to GL 89-10 activities (U-602225), dated January 13, 1994, IP has continued to review the MOVs within our program to determine ifIP's identified MOV scope is consistent with the Generic Letter and its supplements. Subsequently, IP has determined that eight MOVs contained in the original extension request meet the requirements of" position-changeable" as defined in ,
Supplement 4 to Generic Letter 89-10 and will be deleted from the 89-10 scope. These valves are listed below:
VALVE EIN DESCRIPTION Gate (Flex Wedge) 1E12F006A RHR SHUTDOWN COOLING SUCTION VALVE 1E12F0060 RHR SHUTDOWN COOLING SUCTION VALVE 1E21F001 LOW PRESSURE CORE SPRAY SUCTION FROM SUPPRESSION POOL VALVE Globe 1E51F076 REACTOR CORE ISOLATION COOLING STEAM LINE WARM-UP INBOARD ISOLATION VALVE 1VOOO6A CONTAINMENT BUILDING EXHAUST OUTBOARD ISOLATION BYPASS VALVE 1VOOO68 CONTAINMENT BUILDING EXHAUST INBOARD ISOLATION BYPASS VALVE 1VR002A CONTAINMENT BUILDING VENTILATION SUPPLY OUTBOARD ISOLATION VALVE 1VR002B CONTAINMENT BUILDING VENTILATION SUPPLY INBOARD ISOLATION VALVE Additionally, these reviews determined that two MOVs that were previously deleted from the 89-10 scope were evaluated incorrectly. These MOVs have been added back to the GL 89-10 scope and are therefore included in IP's extension request for RF-5. Listed below are valve equipment identification number, MOV description, valve size, the required minimum actuator thrust, the as-left actuator thrust, the pressure drop across the valve (AP) and the design basis safety function during accident conditions.
AS-LEFT VS. Valve Close VALVE REQUIRED THRUST AP (psi) (CI,Open SIZE (0) Both VALVE EIN DESCRIPTION Required As-left includes (B)
Minimum Minimum water Thrust Thrust hammer Safety
{lbs) (Ibs) Direction GATE (Flex Wedge) 1G33F028 REACTOR WATER CLE ANUP TO CONDENSER INBOARD 4.0" 6,023 8,554 750 C ISOLATION VALVE 1G33F034 REACTOR WATER CLEANUP TO CONDENSER OUTBOARD 4.0" 6,023 7,843 750 C l IsOLATloN VALVE l The dP calculated for these va!ves prior to removing them from the GL 89-10 program was 1085 psi.
However, this calculation took no credit for the four containment isolation valves located upstream of IG33F028 (F028) and 1G33F034 (F034). As such, no credit was taken for the reduction of dP that these
~
MOVs would provide to F028 and F034. Insersice inspection (ISI) and valve diagnostic test data determined that the stroke times for the upstream valves are one to one and one-half seconds faster than F028 and F034, In addition, two of the upstream valves have a smaller flow capacity (a lower Cy). Therefore, the upstream valves will reduce the dP across F028 and F034. Analysis of these conditions indicates that the dP across F028 and F034 will be less than 750 psi. Since the existing switch settings provide for greater than 25% margin at 750 psi, reasonable-assurance that F028 and F034 will function for this interim period has been established.
In conclusion, with the addition of the two reactor water cleanup MOVs and deletion of the above eight, the total number of MOVs for which an extension is requested is revised to 64.
7