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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217J4331999-10-15015 October 1999 Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station ML20217A9881999-10-0101 October 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A7361999-10-0101 October 1999 Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs ML20217J1251999-09-30030 September 1999 Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC ML20217J1421999-09-30030 September 1999 Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC ML20212G6751999-09-22022 September 1999 Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability ML20217H3421999-09-17017 September 1999 Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed ML20211Q2671999-09-0808 September 1999 Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000 U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 ML20211D2201999-08-23023 August 1999 Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired ML20211A8931999-08-19019 August 1999 Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 ML20210U3771999-08-12012 August 1999 Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210A4401999-07-16016 July 1999 Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations ML20209G7671999-07-12012 July 1999 Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed ML20209D5691999-07-0707 July 1999 Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20196J9651999-07-0202 July 1999 Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements ML20196J7131999-06-30030 June 1999 Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1 U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology ML20196A3471999-06-16016 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology 05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed 05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors ML20209G7731999-05-27027 May 1999 Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999 Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999 Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5 U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999 Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999 Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999 Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999 Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999 Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999 Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999 Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f) U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999 Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3) 05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999 Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999 Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999 Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired 1999-09-22
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L6571990-09-19019 September 1990 Advises That Dp Hall No Longer Associated W/Facility Since Dec 1989.Mail Should Be Addressed to Js Perry JSP-739-90, Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump1990-09-12012 September 1990 Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump U-601729, Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn1990-08-27027 August 1990 Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn JSP-676-90, Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event1990-08-23023 August 1990 Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event U-601723, Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.711990-08-16016 August 1990 Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.71 U-601722, Forwards Reissued NPDES Permit IL00369191990-08-10010 August 1990 Forwards Reissued NPDES Permit IL0036919 U-601721, Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators1990-08-0808 August 1990 Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators U-601716, Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))1990-08-0303 August 1990 Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2)) U-601715, Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly1990-08-0202 August 1990 Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly U-601708, Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 19891990-07-19019 July 1990 Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 1989 U-601702, Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990 Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20044A3001990-06-22022 June 1990 Forwards Update to 890817 Response to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Unisolable Piping Connected to RCS Identified & Evaluated to Determine Which Piping Could Be Subj to Stratified Flow Phenomena ML20044A4601990-06-22022 June 1990 Provides Followup to 900622 Request for Waiver of Compliance Re Tech Spec Limiting Condition for Operation Concerning Standby Emergency Diesel Generator 1B.Rev to Attachment 1 of Original Request for Waiver Encl ML20043H5021990-06-19019 June 1990 Requests Changes to License NPF-62,correcting Typos, Refs to Fsar,Testing to Be Done During Initial Plant Startup & Incorporating Revised Operating Power/Flow Map for Two Reactor Recirculation Loop Operation ML20043G8221990-06-0707 June 1990 Provides Update to Util Response to Item 1 of Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. ML20043F0591990-06-0606 June 1990 Forwards Endorsements 44-50 to Nelia Policy NF-261 & 25-31 to Maelu Policy MF-121 & 10 & 11 to Maelu Policy N-85 & M-85,respectively ML20043D0531990-05-31031 May 1990 Forwards 1989 Annual Rept for Illinois Power Co & Soyland Power Cooperative,Inc ML20043C7501990-05-25025 May 1990 Forwards Rev 20 to Illinois Power Nuclear Program QA Manual. Rev Evaluated by Util as Not Reducing Quality Program Commitments ML20043B4891990-05-21021 May 1990 Informs NRC of Plant Initiatives for 1990 to Improve Corrective Action Program Effectiveness,In Response to SALP Rept & Violations Noted in Insp Rept 50-461/89-32. Centralized Commitment Tracking Sys Upgraded ML20043B1141990-05-17017 May 1990 Suppls 900330 Response to Station Blackout Rule.Calculation of Heatup of Main Control Room Due to Loss of Ventilation Following Station Blackout Revised to Properly Account for Heat Sinks & Credit Existing Masonry Walls ML20043D9901990-05-14014 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Rept 50-461/90-02.Corrective Actions:Safety Evaluation Prepared & Reviewed for Level Instrumentation & Annunciators Identified in Updated SAR ML20043A9811990-05-14014 May 1990 Notifies That Wc Metzner Resigned from Position of Licensed Operator W/Util,Effective 900430 ML20042E6181990-04-13013 April 1990 Updates 890406 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Condition Rept Initiated to Address Issue to Drain Instrument Air Filter Regulators ML20012E8991990-03-27027 March 1990 Forwards Rev 9C to Physical Security Plan.Rev Does Not Decrease Effectiveness of Plan.Rev Withheld (Ref 10CFR73.21) ML20012D9451990-03-20020 March 1990 Informs of Current Activities Re Restoration of Shutdown Svc Water (SX) Sys to Operability Following Cleaning of Div I HX Per Generic Ltr 89-13.SX Sys to Be Restored by Returning Sys Flows to Design Values ML20012D9641990-03-19019 March 1990 Lists Present Levels of Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w)(2) ML20012D9901990-03-19019 March 1990 Responds to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-461/89-38.Corrective Actions:Maint Supervision Added Critical Points to Existing Maint Work Requests & Preventive Maint Activities & Training Program Updated ML20012D4321990-03-16016 March 1990 Responds to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Detailed Analytical Review & Proposed Schedule for Implementing Required Actions Scheduled to Be Completed by 900625 ML20012A2771990-02-28028 February 1990 Forwards Final Response to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded Case Circuit Breakers. Actions Taken by Util Have Established That All safety-related Circuits Remaining in Stock Can Be Verifiably Traced to Mfg ML20012C2511990-02-23023 February 1990 Responds to Ninth SALP Rept 50-461/89-01 for Sept 1988 - Oct 1989.Rept Concluded That Overall Performance Satisfactory & Identified Strengths in Areas of Emergency Preparedness U-601611, Notifies That Gd Setser Resigned Position W/Util,Effective 9002131990-02-20020 February 1990 Notifies That Gd Setser Resigned Position W/Util,Effective 900213 ML20011F6501990-02-12012 February 1990 Responds to NRC 900112 Ltr Re Violations Noted in Insp Rept 50-461/89-37.Corrective Actions:Radiation Protection Technicians Provided W/Method for Identifying Radiation Work Permits Which Change Radiological Conditions ML20006C6721990-02-0505 February 1990 Responds to NRC 891207 Ltr Re Violations Noted in Insp Rept 50-461/89-35.Corrective Actions:Emergency Planning Bulletin Issued to All Emergency Response Organization Members Emphasizing Importance of Attending Required Training ML20006D1951990-01-30030 January 1990 Responds to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Util Intends to Discontinue Sending Ack Upon Receipt of Vendor Manual Matls ML20006A8291990-01-23023 January 1990 Forwards Rev 3 to Inservice Exam Plan. Changes to Text Described.Approval of Changes by 900601 to Allow Time to Plan Refueling Outage Activities Re Inservice Exam Program Requested ML20005H2711990-01-12012 January 1990 Advises That Licensee Will Remove Terminal Blocks for Control Circuits within 100% Relative Humidity Harsh Environ at Plant by End of Second Refueling Outage Currently Scheduled to Begin in Sept 1990 ML20006A7121990-01-10010 January 1990 Forwards Revised Pages to 1987 Radiological Environ Monitoring Rept ML20005F0001990-01-0505 January 1990 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Util Revised Plant Operating Procedures for Hpcs,Lpcs & RHR Pumps & Vibration Monitoring Program Expanded to Include ECCS Pumps at Plant ML20006A7921989-12-29029 December 1989 Responds to 891129 Ltr Which Forwarded Insp Rept 50-461/89-31,requesting Identification of Actions Underway to Ensure That Falsification of Interim Security Screening Records Would Be Detected in Timely Manner in Future U-601573, Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently1989-12-29029 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently ML20005E0891989-12-27027 December 1989 Advises That Revised Fitness for Duty Program Will Meet 10CFR26 Requirements,Effective 900103.Util Intends to Test for Substances Listed at Indicated cut-off Levels ML20006C2961989-12-21021 December 1989 Responds to NRC 891121 Ltr Re Violations Noted in Insp Rept 50-461/89-32.Corrective Actions:Review Performed to Identify Surveillances Which Require Lifting of Leads in Main Control Room ML20005D9521989-12-15015 December 1989 Forwards Monthly Operating Rept for Nov 1989 for Clinton Power Station Unit 1 & Corrections to Oct 1989 Rept ML20005E7781989-12-12012 December 1989 Advises That False Alarm Criteria Will Be Implemented by 900131,per Insp Rept 50-461/89-31.Util Established New Criterion of 100 False Alarms for Security Sys in 24 H Period ML20011D1741989-12-0707 December 1989 Informs of Changes Made to Util Fitness for Duty Program Procedure.Change Specifies That Supervisor - Medical Programs,Assistant Director - Labor Relations or Manager - Nuclear Planning & Support Will Generate Computer List ML19332F0071989-11-30030 November 1989 Responds to Violations Noted in Insp Rept 50-461/89-29. Corrective Actions:Preventive Maint for Ph Monitor & Liquid & Gaseous Gamma Monitors Added to Appropriate Tracking Programs ML19332E9431989-11-29029 November 1989 Forwards Executed Amends 4 & 5 to Indemnity Agreement B-91, Reflecting Change in Ownership of License,Effective 890327 ML19332D5031989-11-27027 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Results of Util Review & Reporting of Status of Implementation of USIs Encl ML19332D0291989-11-22022 November 1989 Informs That Effective 891201,JS Perry Will Assume Responsibility for Mgt of Nuclear Program at Util ML19332D0431989-11-22022 November 1989 Informs NRC of Change in Schedule for Providing Info Re Environ Qualification Testing of Terminal Blocks for Control Circuits of Conax Electrical Penetrations.Wyle Labs Test Results & Util Review of Results Will Be Sent by 900112 1990-09-19
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U-0828 L37-8 5 ( 0 3-2 9) -L ILLINDIS POWER COMPANY 1A.120 CLINTON POWER STATION, P.O. BOX 678. CLINTON, ILLINOIS 61727 March 29, 1985
$0' l Mr. James G. Keppler Regional-Administrator -- j slj Region III d' U. S. Nuclear Regulatory Commission ;
799-Rooseveit Road Glen Ellyn, Illinois 60137 h{!(igb' "
Subject:
Proposed changes in the Illinois Power (IP) .
Company Overinspection Program
References:
- 1. Letter C. E. Norelius to W. C. Gerstner of November 21, 1984, forwarding letter for USNRC Mee ting Report No. 50-461/84-37 (DRP)
- 2. Letter D. P. Hall to H. R. Denton/J. G.
Keppler of February 13, 1985, forwarding letter for "Results of Quality Programs for Construction of Clinton Power Station".
Dear Mr. Keppler:
On October 25, 1984, Illinois Power met with members of your staff in your offices in Glen Ellyn, Illinois to discuss proposed changes to the IP Overinspection Program. Specifically, it was proposed that piping and mechanical supports be removed from the scope of the Overinspection Program. This proposal was based upon information resulting from program implementation which verified the quality of the piping and mechanical supports at Clinton Power Station. Therefore, continuation of the Overinspection Program for these types of items was unnecessary.
During the course of the meeting IP was requested to provide information on three additional topics to the NRC staff in order for the staff to evaluate the IP proposal. The requested infor-cation is described in notes of the meeting which were forwarded to.IP by reference 1 and is as follows:
The Overinspection Program was designed to be continu-ing activity until turnover of structures, systems and components to IPs however, criteria was not defined for termination of (re] inspections by category. Open item (461/84-37-03).
There was no information provided that showed the safety significance of the problems identified to date gugg g3gi 'APR 11985 8l#
a 2tO/
P during the Overinspection Program of large and small bore piping and piping supports. Such information is necessary to draw conclusions as to the safety signifi-cance of terminating the program before completing the overinspection of all lots of large and small bore piping. Open Item (461/84-37-02).
The data on page 15 of Attachment 1 was not sufficient to determine the actual percentage of total work that had been completed in any area. Open item (461/84-37-01).
This letter forwards, by attachment, the information re-quested by the NRC in support of IP's conclusion that removal of safety related piping and mechanical supports from the Overinspection Program is warranted. Attachment 1 provides the criteria for termination of inspection by category (Commodity) in response to NRC open item 461/84-37-03. Attachment 2 provides information specifically on safety related piping and mechanical supports in response to open items 461/84-37-02 and 461/84-37-01.
Attachment 3 demonstrates that these items meet the criteria in Attachment 1. It is to be noted that Sargent & Lundy performed an overall evaluation of results of the Overinspection Program, which was provided to the NRC, under cover of reference 2, as Chapter V and appendix D of the report "Results of Quality Programs for the construction of Clinton Power Station". The information and data contained in Attachments 2 and 3 to this letter is taken from that report and is a refinement and expansion of the information presented to the NRC on October 25, 1984. Attachments 2 and 3 also account for revisions made to the data presented in the report subsequent to its issue.
Your review of the attachment and your concurrence with the picposal to remove safety related piping and mechanical supports from the Overinspection Program is requested, if further information or clarification of the information already presented is necessary for evaluation of this request, please contact us at your earliest conveniance.
Sincerely yours, D. . all Vice President ATTACHMENTS JEK/skt cc: Director, Office of I&E, US NRC, Washington, DC 20555 NRC Resident Office Illinois Department of Nuclear Safety
m m
ATTACHMENT 1 RESPONSE TO NRC OPEN ITEM' 461/84-37-03 I. NRC Request The Overinspection Program was designed to be a.
continuing activity until turnover of structures, systems and components to IPs however, criteria was not defined for termination of [re] inspections by category.
II. IP Response IP has established the following criteria for termination of reinspections by category (commodity). These are a combination of numerical, statistical and engineering evaluation criteria and provide a high degree of confidence in decisions regarding the scope of the Overinspection Program.
III. Criteria All of the following three criteria shall be satisfied before reinspection of a safety-related commodity under the Overinspection Program is terminated.
A. A sufficient number of reinspections have been conducted to provide high confidence that the results of reinspections are representative of overall quality for a specific' commodity. This criterion will be satisfied for a commodity if at least 10,000 attributes have been reinspected for the commodity or at least 5% of the total number of items within the commodity have been inspected.
B. In the aggregate, the reinspections for a commodity did not identify a significant number of nonconforming attributes. This criterion will be satisfied if the rate of conforming attributes is at least 95%.
C. The reinspections for a commodity did not identify any nonconformance which had safety-significance with generic implications. A safety-significant nonconformance is defined as a nonconformance which, were it to have
- 7 remained unidentified by the Overinspection Program, could have resulted in the loss of
. capability of structure, system, or component to perform its intended safety function.
This criterion will be satisfied by an engineering evaluation, similar to that performed for the "Results of Quality Program,s for Construction of Clinton Power Sta tion
ATTACHMENT 2 Response to NRC Open Item 461/84-37-02 and -01 I. Open Item 461/84-37-02 A. NRC Request There was no information provided that showed the safety significance of the problems identified to date during the Overinspection Program of large and small bore piping and piping supports. Such information is necessary to draw conclusions as to the safety significance of terminating the program before completing the overinspection of all lots of large and snall bore piping.
B. IP Response IP requested Sargent & Lundy (with input from General Electric as necessary for GE designed components) to evaluate each Nonconformance Report to determine whether any of the nonconformances identified by the Overinspection Program were safety significant.
In general, S&L evaluated each nonconformance by one of three methods. First, many nonconformances on their face have little or no impact on the integrity of an item. Nonconformances in this ca tegory , for example , typically include minor documentation errors and cosmetic defects such as those arc strikes which do not reduce base metal thickness. These nonconformances can be designat-ed as having no safety significance, with no need to conduct more detailed evaluations.
Second, there are many types of nonconformances which do not adversely affect the function of an item because of the inherent conservatism of the design for the item. Many of these nonconform-ances, such as minor cases of undercut and surface slag on welds, are readily identifiable from engineering experience and knowledge of the design without the need to conduct detaile.1 calculations.
Finally, any nonconformance not falling within one of the above two categories was subject to detail-ed engineering evaluations to determine whether the nonconformance adversely affected the capabil-ity of a structure, system, or component to perform its intended safety function.
l Although S&L evaluated each nonconformance identi-fied by the Overinspection Program to determine whether it was safety significant, it should be emphasized that most of the nonconforming items u -
have been reworked in accordance with applicabic design drawings and specifications and the remaind-er have been determined to be acceptable as they are. Consequently, the evaluations below were performed to determine the safety significance of the nonconformances assuming they had been left uncorrected.
- 1. Piping The Overinspection Program identified 667 noncon-forming attributes on piping. As is discussed below, none of these nonconforming attributes was determined to be safety significant.
The majority (396) of the nonconforming attributes involved minor damage to pipe walls. Damage to pressure-retaining components was evaluated by considering if the reduction in the wall thickness was acceptable considering the minimum allowable wall thickness. Arc strikes constituted almost all of this ty,e of damage and were determined to be acceptable aased on the minimum allowable wall rec uirements for piping. The gouges, scratches, anc, cuts in piping also were judged to be accept-able based on minimum allowable wall thickness requirements.
Ninety-nine welding nonconformances affecting piping were evaluated. About one-fourth of the nonconformances were determined to be localized cosmetic surface defects, such as concavity, porosity, and surface slag. For more severe welding problems involving overlaps, undercut, lack of fusion, and undersized welds, localized pipe stresses were examined to determine the adequacy of the weld under all loading conditions.
In no case was the applicable code allowable stresses exceeded. There were 55 installation nonconforming attributes identified. These items were mostly small installation tolerance nonconformances that were acceptable. One hundred three documentation and procedural nonconformances were examined which required only " paper" corrections that had no impact on the physical design.
- 2. Mechanical (Piping) Supports A total of 4,576 nonconforming attributes were identified by the Overinspection Program in piping supports. The largest number (2,049) of noncon-forming attributes identified were in the welding
area. The next most prevalent nonconforming attributes are in the area of arc strikes (1,299) and installation nonconformances (924) .
Velding nonconformances on pipe supports primarily involved undersized welds, overlap, undercut, and slag inclusion. When the nonconforming welds could not be determined to be acceptable by other means, the nonconforming welds were evaluated by comparing the actual stresses (imposed on the weld without taking credit for damaged areas) to maximum stresses allowed by design. This comparison verified that sufficient margin existed in the nonconforming weld and the remaining welds on the support to preclude failure of the support.
Over 28% of the nonconforming attributes involved arc strikes. The majority of the remaining damage was comprised of gouges, defects caused by grind-ing, and bent component items. Arc strikes and gouges were evaluated to determine the effect of the reduction in base metal on the support's design capacity. No sup) ort was found to have sufficient reduction in aase metal to cause any piping support to fail. None of the remaining damage was determined to be safety-significant.
Installation nonconformances on pipe supports involved loose or incomplete hardware installa-tion, incorrect adjustment of supports, lack of clearance or interference, and construction tolerance nonconformances. Each nonconforming condition was evaluated to determine if the nonconformance was of a type that would be specifically examined in subsequent preoperational testing. For example, inspections that specifi-cally check for hot and cold positions of adjust-able support components would ensure that proper construction tolerances and construction complete-ness are verified prior to operation. Consequent-ly, these nonconformances were not significant because they would not have been left unidentified and uncorrected if the Overinspection Program had not been performed. For supports which are not adjustable, such as rigid or welded supports, specific preoperational programs to inspect for proper installation and fitup do not exist (other than 79-14 walkdowns conducted on plaing and support systems). In these cases, tae nonconform-ing attributes were evaluated for their impact on the structural integrity of the support. In no case was a safety-significant condition found to exist.
m Documentation-related nonconformances accounted
! for less than 2% of pipe support nonconforming attributes and typically pertained to the lack of a welder ID or hardware ID tag. Since evaluations j determined that all identifications required for safety-related hardware were recoverable from other records, there were no safety-significant nonconformances in this group.
II. Open item 461/84-37-01 ,
A. NRC Request The data on page 15 of Attachment 1 was not sufficient to determine the actual percentage of
- total work that had been completed in any area.
< B. IP Response Percentage complete and number of attributes '
reinspected for safety related piping and
' mechanical supports by both BA Field Verification and IP Overinspection are tabulated below. J l
Percent Inspected Attributes Inspected FV OI FV OI i
Large Bore Pipe 13 6 19,376 7,634 Small Bore Pipe 10 10 32,114 5,938 i
Mechanical Supports 23 8 178,435 63,690 p-
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ATTACHMENT 3 Criteria For Terminating Reinspection of Commodities Piping and Mechanical Supports The information presented in this attachment demonstrates that safety-related piping and mechanical supports meet or exceed the criteria presented in Attachment 1 to this letter for termination of reinspection of commodities under the Overinspection program.
Criterion A: At least 10,000 attributes have been inspected for a commodity or at least 5% of the total number of items within the commodity have been inspected.
As is demonstrated by the table presented in attachment 2 to this letter -(NRC Open Item 461/84-37-01) large bore piping, small bore piping and mechanical supports meets or exceeds this criterion.
Criterion B: The rate of conforming attributes is at least 95%.
The following tables demonstrate compliance with this criterion in several different ways: Table 3.1 provides conformance rates based on FV data only, Table 3.2 provides conformance rates based on OI data only and Table 3.3 provides a com)arison of conformance rates for old and new wor (. Data in table 3.3 on old and new work utilizes only FV data since this is the first level of reinspection and therefore is the most conservative.
Table 3.1 Field Verification Conformance Rates Attributes Nonconforming Conformance Commodities Inspected Attributes Rates (%)
Large Bore 19,376 330 98.3 Pip e Small Bore 32,114 298 99.1 Pipe Mechanical 1 178,435 4083 97.7 Supports
- 1. Includes anchor plates, expansion anchors and hangers.
- o. ..
Table 3.2 Overinspection Conformance Rates Attributes Nonconforming Conformance Commodities Inspected Attributes Rates (%)
Large Bore 7,634 25 99.7 Pip e Small Bore 5 ,938 14 98.8 Pipe Mechanical 1 63,690 493 99.2 Supports
- 1. Includes anchor plates, expansion anchors and hangers.
Table 3.3 Field Verification Conformance Rates for Old and New Work Attributes Nonconformance Conformed Commoditics Work Ins pe cte d Attributes Rates (%)
Large Bore Old 4,612 49 98.9 Pipe New 14,764 281 98.1 Small Bore Old 7,094 53 99.3 Pipe New 25,020 245 99.0 Mechanical 1 Old 18,060 597 96.7 Supports New 160,375 3486 97.8
- 1. Includes anchor plates, expansion anchors and hangers.
Criterion C: The reinspections for a commodity did not identify any nonconformance which had safety significance with generic implications.
As is discussed in Attachment 2 to this letter (NRC Open Item 461/84-37-02), an engineering evaluation was conducted of all nonconformances identified in safety related piping and mechanical j support. No nonconformance identified had any 1 safety significance. l 1
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