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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217J4331999-10-15015 October 1999 Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station ML20217A9881999-10-0101 October 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A7361999-10-0101 October 1999 Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs ML20217J1251999-09-30030 September 1999 Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC ML20217J1421999-09-30030 September 1999 Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC ML20212G6751999-09-22022 September 1999 Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability ML20217H3421999-09-17017 September 1999 Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed ML20211Q2671999-09-0808 September 1999 Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000 U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 ML20211D2201999-08-23023 August 1999 Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired ML20211A8931999-08-19019 August 1999 Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 ML20210U3771999-08-12012 August 1999 Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210A4401999-07-16016 July 1999 Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations ML20209G7671999-07-12012 July 1999 Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed ML20209D5691999-07-0707 July 1999 Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20196J9651999-07-0202 July 1999 Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements ML20196J7131999-06-30030 June 1999 Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1 U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology ML20196A3471999-06-16016 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology 05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed 05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors ML20209G7731999-05-27027 May 1999 Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999 Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999 Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5 U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999 Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999 Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999 Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999 Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999 Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999 Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999 Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f) U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999 Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3) 05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999 Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999 Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999 Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired 1999-09-22
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L6571990-09-19019 September 1990 Advises That Dp Hall No Longer Associated W/Facility Since Dec 1989.Mail Should Be Addressed to Js Perry JSP-739-90, Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump1990-09-12012 September 1990 Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump U-601729, Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn1990-08-27027 August 1990 Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn JSP-676-90, Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event1990-08-23023 August 1990 Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event U-601723, Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.711990-08-16016 August 1990 Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.71 U-601722, Forwards Reissued NPDES Permit IL00369191990-08-10010 August 1990 Forwards Reissued NPDES Permit IL0036919 U-601721, Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators1990-08-0808 August 1990 Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators U-601716, Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))1990-08-0303 August 1990 Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2)) U-601715, Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly1990-08-0202 August 1990 Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly U-601708, Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 19891990-07-19019 July 1990 Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 1989 U-601702, Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990 Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20044A3001990-06-22022 June 1990 Forwards Update to 890817 Response to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Unisolable Piping Connected to RCS Identified & Evaluated to Determine Which Piping Could Be Subj to Stratified Flow Phenomena ML20044A4601990-06-22022 June 1990 Provides Followup to 900622 Request for Waiver of Compliance Re Tech Spec Limiting Condition for Operation Concerning Standby Emergency Diesel Generator 1B.Rev to Attachment 1 of Original Request for Waiver Encl ML20043H5021990-06-19019 June 1990 Requests Changes to License NPF-62,correcting Typos, Refs to Fsar,Testing to Be Done During Initial Plant Startup & Incorporating Revised Operating Power/Flow Map for Two Reactor Recirculation Loop Operation ML20043G8221990-06-0707 June 1990 Provides Update to Util Response to Item 1 of Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. ML20043F0591990-06-0606 June 1990 Forwards Endorsements 44-50 to Nelia Policy NF-261 & 25-31 to Maelu Policy MF-121 & 10 & 11 to Maelu Policy N-85 & M-85,respectively ML20043D0531990-05-31031 May 1990 Forwards 1989 Annual Rept for Illinois Power Co & Soyland Power Cooperative,Inc ML20043C7501990-05-25025 May 1990 Forwards Rev 20 to Illinois Power Nuclear Program QA Manual. Rev Evaluated by Util as Not Reducing Quality Program Commitments ML20043B4891990-05-21021 May 1990 Informs NRC of Plant Initiatives for 1990 to Improve Corrective Action Program Effectiveness,In Response to SALP Rept & Violations Noted in Insp Rept 50-461/89-32. Centralized Commitment Tracking Sys Upgraded ML20043B1141990-05-17017 May 1990 Suppls 900330 Response to Station Blackout Rule.Calculation of Heatup of Main Control Room Due to Loss of Ventilation Following Station Blackout Revised to Properly Account for Heat Sinks & Credit Existing Masonry Walls ML20043D9901990-05-14014 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Rept 50-461/90-02.Corrective Actions:Safety Evaluation Prepared & Reviewed for Level Instrumentation & Annunciators Identified in Updated SAR ML20043A9811990-05-14014 May 1990 Notifies That Wc Metzner Resigned from Position of Licensed Operator W/Util,Effective 900430 ML20042E6181990-04-13013 April 1990 Updates 890406 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Condition Rept Initiated to Address Issue to Drain Instrument Air Filter Regulators ML20012E8991990-03-27027 March 1990 Forwards Rev 9C to Physical Security Plan.Rev Does Not Decrease Effectiveness of Plan.Rev Withheld (Ref 10CFR73.21) ML20012D9451990-03-20020 March 1990 Informs of Current Activities Re Restoration of Shutdown Svc Water (SX) Sys to Operability Following Cleaning of Div I HX Per Generic Ltr 89-13.SX Sys to Be Restored by Returning Sys Flows to Design Values ML20012D9641990-03-19019 March 1990 Lists Present Levels of Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w)(2) ML20012D9901990-03-19019 March 1990 Responds to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-461/89-38.Corrective Actions:Maint Supervision Added Critical Points to Existing Maint Work Requests & Preventive Maint Activities & Training Program Updated ML20012D4321990-03-16016 March 1990 Responds to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Detailed Analytical Review & Proposed Schedule for Implementing Required Actions Scheduled to Be Completed by 900625 ML20012A2771990-02-28028 February 1990 Forwards Final Response to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded Case Circuit Breakers. Actions Taken by Util Have Established That All safety-related Circuits Remaining in Stock Can Be Verifiably Traced to Mfg ML20012C2511990-02-23023 February 1990 Responds to Ninth SALP Rept 50-461/89-01 for Sept 1988 - Oct 1989.Rept Concluded That Overall Performance Satisfactory & Identified Strengths in Areas of Emergency Preparedness U-601611, Notifies That Gd Setser Resigned Position W/Util,Effective 9002131990-02-20020 February 1990 Notifies That Gd Setser Resigned Position W/Util,Effective 900213 ML20011F6501990-02-12012 February 1990 Responds to NRC 900112 Ltr Re Violations Noted in Insp Rept 50-461/89-37.Corrective Actions:Radiation Protection Technicians Provided W/Method for Identifying Radiation Work Permits Which Change Radiological Conditions ML20006C6721990-02-0505 February 1990 Responds to NRC 891207 Ltr Re Violations Noted in Insp Rept 50-461/89-35.Corrective Actions:Emergency Planning Bulletin Issued to All Emergency Response Organization Members Emphasizing Importance of Attending Required Training ML20006D1951990-01-30030 January 1990 Responds to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Util Intends to Discontinue Sending Ack Upon Receipt of Vendor Manual Matls ML20006A8291990-01-23023 January 1990 Forwards Rev 3 to Inservice Exam Plan. Changes to Text Described.Approval of Changes by 900601 to Allow Time to Plan Refueling Outage Activities Re Inservice Exam Program Requested ML20005H2711990-01-12012 January 1990 Advises That Licensee Will Remove Terminal Blocks for Control Circuits within 100% Relative Humidity Harsh Environ at Plant by End of Second Refueling Outage Currently Scheduled to Begin in Sept 1990 ML20006A7121990-01-10010 January 1990 Forwards Revised Pages to 1987 Radiological Environ Monitoring Rept ML20005F0001990-01-0505 January 1990 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Util Revised Plant Operating Procedures for Hpcs,Lpcs & RHR Pumps & Vibration Monitoring Program Expanded to Include ECCS Pumps at Plant ML20006A7921989-12-29029 December 1989 Responds to 891129 Ltr Which Forwarded Insp Rept 50-461/89-31,requesting Identification of Actions Underway to Ensure That Falsification of Interim Security Screening Records Would Be Detected in Timely Manner in Future U-601573, Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently1989-12-29029 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently ML20005E0891989-12-27027 December 1989 Advises That Revised Fitness for Duty Program Will Meet 10CFR26 Requirements,Effective 900103.Util Intends to Test for Substances Listed at Indicated cut-off Levels ML20006C2961989-12-21021 December 1989 Responds to NRC 891121 Ltr Re Violations Noted in Insp Rept 50-461/89-32.Corrective Actions:Review Performed to Identify Surveillances Which Require Lifting of Leads in Main Control Room ML20005D9521989-12-15015 December 1989 Forwards Monthly Operating Rept for Nov 1989 for Clinton Power Station Unit 1 & Corrections to Oct 1989 Rept ML20005E7781989-12-12012 December 1989 Advises That False Alarm Criteria Will Be Implemented by 900131,per Insp Rept 50-461/89-31.Util Established New Criterion of 100 False Alarms for Security Sys in 24 H Period ML20011D1741989-12-0707 December 1989 Informs of Changes Made to Util Fitness for Duty Program Procedure.Change Specifies That Supervisor - Medical Programs,Assistant Director - Labor Relations or Manager - Nuclear Planning & Support Will Generate Computer List ML19332F0071989-11-30030 November 1989 Responds to Violations Noted in Insp Rept 50-461/89-29. Corrective Actions:Preventive Maint for Ph Monitor & Liquid & Gaseous Gamma Monitors Added to Appropriate Tracking Programs ML19332E9431989-11-29029 November 1989 Forwards Executed Amends 4 & 5 to Indemnity Agreement B-91, Reflecting Change in Ownership of License,Effective 890327 ML19332D5031989-11-27027 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Results of Util Review & Reporting of Status of Implementation of USIs Encl ML19332D0291989-11-22022 November 1989 Informs That Effective 891201,JS Perry Will Assume Responsibility for Mgt of Nuclear Program at Util ML19332D0431989-11-22022 November 1989 Informs NRC of Change in Schedule for Providing Info Re Environ Qualification Testing of Terminal Blocks for Control Circuits of Conax Electrical Penetrations.Wyle Labs Test Results & Util Review of Results Will Be Sent by 900112 1990-09-19
[Table view] |
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, U-601218
. L30-88 ( 0 6- 2 9) -LP
, 1A.120 ILLINDIS POWER 00MPANY CLINTON NMER STATION. P.O. BOX 678, CLINTON, ILLINOIS 61727 DPH-0621-88 June 29, 1988
' Docket No.'50-461 Mr. James Lieberman, Director Office of Enforcement ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Response to Notice of Violation and Proposed Imposition of Civil Penalty Dated June 1, 1988, Docket No. 50-461, EA 88-90
Dear Mr. Lieberman:
On June 1, 1988, the Nuclear Regulatory Commission (NRC) issued a Notice of Violation and Proposed Imposition of Civil Penalty, EA 88-90, to Illinois Power Company (IP). That Notice was based upon items described in NRC Inspection Reports No.
87026 and 88010. The Notice proposes to impose a' civil penalty upon IP in the amount of $75,000.
Attachment A to this letter provides IP's reply to the items listed in the Notice of Violation, and Attachment B provides IP's answer to the Proposed Imposition of Civil Penalty. These attachments describe the actions IP has taken to correct the noted items, to address their generic implications, and to prevent their recurrence.
As described in Attachments A and B, two of the conditions, those relating to electrical butt splices and wire caps, cited by the NRC as the basis for the Notice of Violation and subsequent civil penalty, involve a new interpretation by the NRC of environmental qualification regulations and standards. IP was not notified of this new interpretation prior to the time the NRC identified these conditions during its inspection of IP's Environmental Qualification Program in August 1987. IP believes that it was in compliance with the standards applicable to these items that existed at the time and notes that the NRC did not ins identify any noncompliance components during containing the wire priotAlso,pections caps. as described of thein Attachment A, testing of the butt splices and wire caps demonstrated that there was no immediate safety concern and that continued operation was justified. Therefore, although IP has 6q taken extensive action in response to the NRC's concerns with respect to the butt splices and wire caps, IP denies that a g g violation occurred wi,th" respect to these two items.
8807060594 880629 gDR ADOCK 050004 1
e ,
U-601218 L30-88 ( 06- 2 9) -LP 1A.120 IP also submits that issuance of a violation relating to the butt splices and wire caps was inconsistent with sound regulatory practice. To the extent that the NRC identified a previously unknown safety concern that was serious enough to warrant a civil penalty, it would have been appropriate for the NRC to notify licensees so that they would have the opportunity to resolve this concern as soon as possible. Some form of generic notification, such as a telegram, or an IE Information Notice, Bulletin or Generic Letter would have given licensees appropriate notice of this issue and would have provided the speediest means to address the issue on an industry-wide basis. Instead, the NRC imposed a civil penalty on an individual licensee based upon a new interpretation of the industry standards applicable to the environmental qualification of these items, without providing any prior notice of the NRC's concerns. This is a less-than-effective method for resolving safety concerns in a timely fashion.
As noted in Inspection Report 87026, the NRC has found IP's environmental qualification program to be generally sound, with limited exceptions. In addition, IP has taken vigorous corrective action to resolve the issues identified in the Notice.
As a result, IP is requesting remission of the proposed civil penalty.
I trust that this response is satisfactory. If you have any questions, please call me or Frank Spangenberg, Manager of Licensing and Safety.
Sincerely yours, D. . Hall Vice President DPH/krm Attachments cc: Regional Administrator, Region III, USNRC NRC Clinton Licensing Project Manager NRC Resident Office Illinois Department of Nuclear Safety
a STATE.OF ILLIN0IS COUNTY OF DEWITT DONALD P. HALL, being first duly sworn, deposes and says: I am the Vice President of Illinois Power Company. The foregoing Response to Notice of Violation and Proposed Imposition of Civil Penalty (Letter No. U-601218), dated June 29 , 1988, and the
-attached Reply to Notice of Violation (Attachment A) and Answer to-Proposed Imposition of Civil Penalty (Attachment B), were prepared.under my suaervision and direction. I know the contents thereof, and to the best of my knowledge and belief the facts contained therein are true and correct.
Donald P. Hall Dated: JuneA[,1988 Subscribed and sworn to before me thisM&/; day of June, 1988 -
K 7W 4b Notary Public "t3 PFICI A L S EAL" My Commission Expires: UNDA B CH AMSIRLAIN NOYARY PUBLIC, STATE OF ILLINDIS MY COMMISSION
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EXPIRES 21190 f _ ll- [
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Attachment A Illinois Power Company's Reply to Notice of Violation (EA 88-90)
The Notice of Violation describes three alleged examples of violation of 10 CFR 50.49(f). These examples concern (1) AMP KYNAR electrical butt splicess (2) electrical junction boxes: and (3) Thomas and Betts nylon wire caps used inside Limitorque motor operated valve actuators. Illincis Power Company's (IP) reply pursuant to 10 CFR 2.201 is accordingly organized into three parts, each corresponding to one of the cited examples. Within each of these parts, the specific issues recuired to be addressed by:10 CFR 2.201, the Notice of Violation anc the accompanying
-cover letter are addressed.
I. AMP KYNAR Electrical Butt Splices The Notice of Violation states in part:
Contrary to (10 CFR 50.49(f)], as of August 19, 1987, the following equipment important to safety was not qualified by testing and/or analysis which reflected the installed configuration:
A. One hundred and ninety-six AMP KYNAR electrical butt splices installed in valve actuators, solenoid valves and electrical junction boxes affecting multiple safety systems.
This example was described in NRC Inspection Report No.
87026 as item 87026-02 and in NRC Inspection Report No.
88010 as item 88010-01.
A. Admission or Denial of the Violation The AMP KYNAR electrical butt splices were qualified by testing and/or analysis which reflected the installed configuration of these items at the Clinton Power Station (CPS). IP reviewed and accepted a qualification test report that demonstrated that these butt splices would perform their intended function under the most severe temperature, pressure, humidity, and radiation conditions, including thermal and radiation aging, anticipated in the event of a design basis accident (DBA). (See Wyle Laboratories Test Report Number 17955-1, Revision 0, dated January 29, 1988:
AMP Qualification Test Report 110-11004, Revision 0, dated February 2, 1982.) The testing reviewed and accepted by IP was consistent with industry practices, and the butt splices were mounted, positioned and connected in a fashion similar to their actual installation. Additionally, the AMP test conditions were more severe than worst cave conditions expected during a Clinton DBA. As described in section C of
- 1-
the attached Answer to Proposed Imposition of Civil Penalty, IP believes that the environmental qualification testing of the butt splices met applicable NRC regulations and industry standards. IP also believes that the NRC's view that environmental qualification testing of these items was not adequate is a result of a new interpretation by the NRC of industry standards, of which IP was not informed until during the inspection (87026) in which the NRC identified this item. Therefore, IP does not consider that there was a violation for this item.
B. Reasons for the Condition Described The AMP environmental qualification testing of the KYNAR butt splices accounted for the most severe temperature, pressure, humidity and radiation conditions expected to be encountered at CPS, accounted for thermal and radiation aging, and appropriately simulated the installed configuration of the butt splices in the plant. The test of the splices did not account for contact with a metal ground, because the design use of the splices does not contemplate installation of the splices in a configuration in which they are in contact with a metal ground. When a walkdown of butt splices used in high humidity areas was performed, none were found in contact with a metal ground. The NRC informed IP, during its inspection of the CPS environmental qualification program on August 17-21, 1987, that the reason for testing the splices in contact with a metal ground is that there exists some possibility that such a ground could occur during accident conditions.
C. Steps Taken to Correct the Problem and Results Achieved Upon being notified by the NRC during the week of August 17, 1987 that the fact that the failure to have tested the materials in contact with a metal ground called into question the adequacy of the environmental qualification of the butt splices, IP arranged for further testing. On August 21, 1987, Wyle Laboratories nerformed testing of AMP KYNAR butt splices. The test conditions simulated the most severe temperature, pressure and humidity conditions likely to be experienced during a design basis accident at CPS, and the butt splices were restrained in contact with a metal ground. All of the tested butt splices performed satisfactorily during these tests. Thus, the tests determined that there was no immediate safety concern with use of the butt splices. IP submitted these test resulte to the NRC on August 28, 1987, in conjunction with IP's t
Justification for Continued Operation (JCO) which demonstrated that continued operation of CPS was justified until further testing on the butt splices was performed.
s Because the qualification tests performed on August 21, 1987, did not account for thermal or radiation aging of the butt splices, IP commissioned further tests, which were performed by Wyle Laboratories on October 9 though November 19, 1987. These tests were performed using AMP KYNAR butt splices that had been artificially aged for eight (8) years and for forty (40) years. Again, the splices were restrained in contact with a metal ground under the most severe temperature, pressure and humidity conditions that would be experienced during a design basis accident at CPS.
A number of the splices in both groups failed to retain adecuate insulating capacity under these extended service conc itions . However, as discussed above, this presented no immediate safety concern.
Uaon learning of these test results on November 10, 1987, while CPS was in cold shutdown, IP immediately initiated a walkdown of electrical devices in areas where 100% humidity could occur. During this walkdown, 196 AMP KYNAR butt splices in these areas were located. Each of these was reworked using qualified tape or Raychem tubing, resulting in a configuration that the NRC agrees is qualified. See NRC Inspection Report 88010, Item 88010-01. The walkdown and rework of all butt splices in high humidity areas was completed on November 18, 1987, prior to the time power ascension from the shutdown commenced.
D. Corrective Steps to Avoid Further Violation As described in C above, the scope of this problem has been identified and it has been completely corrected. Therefore, no additional specific action in response to this item is required to avoid further violation.
However, it should be noted thct, in addition to the environmental qualification program that was audited by the NRC, IP is engaged in a number of activities to ensure that plant equipment at CPS is properly qualified and to monitor industry sources that provide information that could affect the qualification status of equipment at CPS. IP receives, reviews, tracks and responds to Institute of Nuclear Power Operations (INPO) Significant Event Reports and Significant Operating Event Reports, General Electric Service Information Letters, NRC Generic Letters, IE Information Notices and IE Bulletins. Where requested, written responses to these documents are provided to the NRC. Any l
of these industry and NRC items containing information relating to environmental qualification are provided to the appropriate group within the CPS Nuclear Station Engineering Department (NSED) so that the potential impact on the environmental qualification of equipment at CPS can be addressed. File packages documenting IP'a actions in response to such items are prepared and maintained, l
IP also participates in industry groups that provide information relating to environmental qualification issues.
For example, IP receives reports and attends meetings of the Environmental Qualification Advisory Group of the Electric Power Research Institute. IP also is a member of the Regional Utility Group for Region III. Environmental qualification information obtained from IP's participation >
in these groups is provided to appropriate personnel and reviewed for applicability to equipment installed at CPS.
Finally, IP reviews violations issued in Region III to Jetermine whether they contain information that might pertain to CPS. Such violations relating to environmental qualification are provided to the appropriate group within NSED to review for potential impact at CPS. Thus, IP has in place a number of programs designed to keep it abreast of developments in the area of environmental qualification and to assure that events that might affect the qualification of equipment at CPS are addressed. IP believes that these pro vioframswillhelppreventenvironmentalqualification ations in the future.
E. Date When Full Compliance Will Be Achieved IP is in compliance.
II. Electrical Junction Boxes The Notice of Violation states in part:
Contrary to (10 CFR 50.49(f)], as of August 19, 1987, the following equipment important to safety was not qualified by appropriate testing and/or analysis which reflected the installed configuration:
B. One hundred and fifty-six junction boxes without drainage openings (weep holes) affecting multiple safety systems.
This item was discussed in NRC Inspection Report No. 87026 as item 87026-03b and in NRC Inspection Report No. 88010 as
! item 88010-02, and was described in Licensee Event Report l No. 87-066-00, submitted by IP to the NRC on December 4, 1987.
l A. Admission or Den,ial of the Violation IP admits that this item occurred as stated in the Notice of l Violation.
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B. Reason for the Violation This problem was caused by the failure of the constructor, Baldwin Associates (BA), to install required weep holes in the electrical junction boxes. BA failed to include the requirement for the weep holes in the construction travelers for these junction boxes. The requirement for the weep holes was not clearly defined by the architect / engineer, Sargent & Lundy, in the installation specification for the junction boxes.
In addition, corrective action for the nonconformance documents that initially identified junction box drainage problems in some junction boxes, and corrective action for an NRC noncompliance (87026-03b) relating to a junction box that lacked a drainage hole, was limited to the junction boxes in question.
C. Steps Taken to Correct the Problem and Results Achieved This problem was identified as a generic condition on November 5, 1987, while the plant was in cold shutdown. IP ordered that the plant remcin in cold shutdown until all of the junction boxes were reoaired. A walkdown was conducted to identify all junction boxes lacking required weep holes.
A total of 156 boxes were identified as lacking wee, holes.
These were reworked by drilling a drain hole in each box.
This work was completed on November 12, 1987, prior to initiating power ascension from the shutdown.
D. Corrective Steps to Avoid Further Violation Engineering Change Notices have been issued for the construction drawings for the affected junction boxes to show the requirement for weep holes in the boxes. In addition, the CPS Quality Assurance and Nuclear Station Engineering departments, and Sargent & Lundy, performed a review of the Sargent & Lundy electrical installation specification to determine whether other cases existed where requirements in the installation specification might have been misunderstood. No other instances were identified.
A training program was developed to ensure tFac engineering and quality assurance personnel responsible for performing reviews of nonconformance documents and defining corrective action are aware of the need to look for possible generic implications of problems and to take a broad view of remedial action for hardware deficiencies. The training reinforced that all conditions, including those that are themselves determined not to be significant, should be evaluated for generic implications. In particular, personnel were instructed to consider applications for l
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9 4 2 similar items that are located elsewhere in the plant or in a different environment, or that perform different functions,-as well as to consider the cause of the condition to determine whether a widespread condition may be indicated. This training was administered pursuant to a written plan. This training was completed on December 18, 1987.
In addition, as described in subsection I.D above, IP is engaged in a number of other activities to avoid environmental qualification violations in the future.
E. Date When Full Compliance Will Be Achieved IP is in compliance.
III. Thomas and Betts Nylon Wire Capa Used Inside
'Limitorque Motor Operated Valve Actuators The Notice of Violation states in part:
Contrary to (10 CFR 50.49(f)], as of August 19, 1987, the following equipment important to safety was not qualified by appropriate testing and/or analysis which reflected the installed configuration:
C. Two hundred and seventy Thomas and Betts nylon wire caps installed in ninety dual voltage Limitorque actuators affecting multiple pieces of equipment important to safety.
This item was discussed in NRC Inspection Report No. 87026 as item 87026-01 and in NRC Inspection Report No. 88010 as item 88010-03.
A. Admission or Denial of the Violation i
The Thomas and Betts nylon wire caps installed in Limitorque motor operated valve actuators were cualified by appropriate testing which reflected the installec configuration at CPS.
The motor operated valve actuators were tested by Limitorque under temperature, pressure, humidity and radiation l conditions, including thermal and radiation aging, which exceeded those anticipated to occur during their use at CPS.
The actuators tested utilized the same type of Thomas and .
Betts nylon wire caps as those used at CPS. Limitorque has confirmed that no other types of wire caps were ever used in its actuators. Thus, the Thomas and Betts nylon wire caps were appropriately qualified in the same configuration as they are installed in the plant. As described in section C of the attached Answer to Proposed Imposition of Civil Penalty, IP believes that the environmental qualification i testing of the wire cans met applicable NRC regulations and
industry standards. IP also believes that the NRC's view that environmental qualification testing of these items was not adequate is the result of a new interpretation by the NRC of industry standards, of which IP was not informed until during the inspection (87026) in which the NRC identified this item. Therefore, IP does not consider that there was a violation for this item.
B. Reason for the Condition Described Limitorque's environmental qualification testing of the Thomas and Betts wire caps accounted for the most severe temperature, pressure, humidity, and radiation conditions expected to be encountered during a design basis accident at CPS, accounted for thermal and radiation aging, and aimulated the installed configuration of the wire caps in the plant. The test of the wire caps did not account for contact with a metal ground because the design of the actuators does not contemplate use of the wire caps in a configuration in which they are in contact with a metal ground. The NRC informed IP during its inspection of the CPS environmental qualification program on August 17-21, 1987 that the reason for testing the splices in contact with a metal ground is that there exists some possibility that such a ground could occur during accident conditions.
C. Steps Taken to Correct the Problem and Results Achieved Upon being notified by the NRC during the week of August 17, 1987 that the fact that the wire caps were not tested in contact with a metal ground called into question the adequacy of the environmental qualification of the Thomas and Betts nylon wire caps, IP arranged for further testing.
Cn August 21, 1987, Wyle Laboratories performed testing of I. the nylon wire caps. The test conditions simulated the most severe temperature, pressure and humidity conditions likely to be experienced during a design basis accident at CPS, and the wire caps were restrained in contact with a metal j ground. All of the tested wire caps performed satisfactorily during the tests. IP submitted these test results to the NRC on August 28, 1987, in conjunction with
! IP's JC0 which demonstrated that continued operation of CPS i was justified until further testing of the wire caps could be performed.
Because the qualification tests performed on August 21, 1987, did not account for thermal or radiation aging of the
- nylon wire caps, IP commissioned further tests, which were performed by Wyle Laboratories on January 29, 1988. These tests were performed using Thomas and Betts nylon wire caps
! that had been artificially aged for eight years and forty years. Again, the wire caps were restrained in contact with I a metal ground under the most severe temperature, pressure and humidity conditions that would be experienced during a t
i design basis accident at CPS. The test of wire caps in the
' forty-year group was discontinued after a number of wire caps failed the test. All of the wire caps in the eight-year group functioned properly. Analysis of the test results demonstrated a minimum of a 9.9-year qualified life for the wire caps. IP has either reworked the wire caps with qualified Okonite tape or will replace them prior to the expiration of their qualified life.
D. Corrective Steps to Avoid Further Violation As described in C above, the_ scope of this problem has been identified and it has been completely corrected. Therefore, no additional specific action in response to this item is required to avoid further violation. However, as described in subsection I.D above, IP is engaged in a number of activities that should prevent environmental qualification violations in'the future.
E. Date When Full Compliance Will Be Achieved IP is in compliance. ,
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ATTACHMENT B Illinois Power Company's Answer to Proposed Imposition of Civil Penalty (EA 88-90)
The Notice of Violation and Proposed Imposition of Civil Penalty describes three items which were collectively considered a single violation, and states:
This is a Severity Level III violation (Supplement I).
Civil Penalty - S75,000 The letter accompanying the Notice of Violation and Proposed Imposition of Civil Penalty states that:
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Aapendix C (Enforcement Policy), the violation described in the enclosed Notice has been categorized at a Severity Level III. The escalation and micigation factors in the Enforcement Policy were considered and the base civil penalty amount has been increased by 50%. Your prompt and extensive corrective action once the problem was identified to you is offset by the arior notices you have had concerning the junction aoxes in the forn. of IE Information Notice 84-57, a previous NRC violation (50-461/87026-03(b))
and your own Nonconforming Material Report written on September 16, 1986, and the multiple examples found for each violation involving numerous safety-related systems.
The Civil Penalty Should Not Have Been Escalated: Remission of the Civil Penalty is Appropriate 10 CFR Part 2, Appendix C describes factors to be considered by the NRC in determining whether to mitigate a proposed civil penalty. These include prompt and effective corrective action and good past performance in the area where the violation occurred. In addition, with respect to two of the items cited as the basis for the violation in EA 88-90, IP believes that no violation occurred and that other extenuating circumstances exist which make escalation of the civil penalty unwarranted and render remission of the penalty appropriate.
A. Past Performance IP's performance in the area of environmental qualification (EQ) of equipment at CPS has been generally good. The staff performed an audit of IP EQ files and a walkdown of installed equipment between March 11 and 14, 1985. Only one file with discrepancies was identified, and no discrepancies t
i between the qualification files and the hardware were l
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identified. Similarly,-during August-October of 1987, the i
NRC conducted an in-depth evaluation of the EQ program for CPS, and found that IP s program complies with NRC EQ requirements, and with limited specific exceptions, was properly implemented. Furthermore, NRC inspectors on several occasions have remarked that IP has a "strong EQ program."
B. Prompt and Effective Corrective Action For two of the examples cited in the alleged violation (AMP KYNAR butt splices and the nylon wire caps), IP's corrective action, described in subsections I.C. and D. and III.C. and D. of the Reply to the Notice of Violation, was prompt and effective, resulting in completion of correction action with no impact on plant operation. Corrective action was designed to identify the scope of the problem and to identify and correct each instance where the problem appeared. In addition, IP is engaged in a number of activities, described in subsection I.D. of the Reply to the Notice of Violation, that should prevent future violations.
The NRC recognized in the cover letter accompanying the Notice of Violation that IP's corrective action in response to these items was "prompt and effective."
As described in subparts II.C. and D. of IP's Reply to the Notice of Violation, corrective action for the violation involving the electrical junction boxes included a determination of the scope of the problem, included action to assure that similar problems did not exist elsewhere, and included training to assure that personnel involved in
- responding to nonconforming hardware conditions address aossible generic implications of those conditions. IP 3elieves that it has taken thorough corrective action which 4
should preclude this type of problem in the future.
1 C. Other Extenuating Circumstances The citation of a violation involving the AMP KYNAR butt splices and the Thomas and Betts nylon wire caps represents 4
a change in the NRC's interpretation of its regulatiuns and industry standards. As required by 10 CFR $ 50.49, the environmental go fication testing of these items reviewed and accepted by IP accounted for the most severe pressure, temperature, humidity and radiation conditions that would be experienced by these items in the event of a design basis accident at CPS. In addition, these items were tested in a configuration that appropriately simulated the mounting method, positioning, and connection of these items as installed at CPS.
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As noted on page 2 of the letter accompanying the Notice of Violation, NRC Region III has' concluded that the tests reviewed and accepted by IP were not adequate because the butt splicus and wire caps were not tested while restrained to a grounded metal surface. However, as installed in the plant, these items are not restrained to a grounded metal surface. When walkdowns of the 196 butt splices were performed at CPS, no indication was found that these items were in contact with a metal surface. Furthermore, when testing the nylon wire caps in the fashion required by the NRC, the only way that the wire caps could be held in contact with metal was to physically restrain them to the actuator casings otherwise contact could not be maintained.
Thus, contact of these items with metal is only a speculative possibility that is unsupported by the design r'quirements or by the installations actually observed in tie plant.
The NRC states that its position that the butt solices and wire caps should have been tested in contact with metal is supported by IEEE Standard 323-1974, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations. That standard states that during environmental qualifications tests:
6.3.1.2 Mounting. Equipment shall be mounted in a manner and in a position that simulates its expected installation when in actual use....
6.3.1.3 Connections. Equipment shall be connected in a manner that simulates its expected installation when in actual use....
The qualification tests reviewed and accepted by IP satisfied these requirements. Testing the butt splices and wire caps while restrained in contact with metal, as now required by the NRC, appears contrary to a straight-forward interpretation of IEEE 323-1974, because these items are not expected to be restrained in contact with metal in actual use, and indeed have not been found in that configuration at CPS.
In the cover letter accompanying the Notice of Violation, the NRC states that the butt splices and wire nuts should have been tested in contact with a ground "since that is a possible configuration and failure mode" (emphasis added).
The requirement here imposed by the NRC is not supported by IEEE 323-1974. As noted above, that standard does not require testing of plant equipment in all "possible" configurations, but the expected configuration. According to Webster's Ninth New Collegiate Dictionary (1986),
"expect" means "to consider probable or certain." Based upon the design and installation of the butt splices and wire caps, contact of these items to a metal ground was not probable ur certain, and in fact was not a condition found in the plant. Thus, the argument that the butt splices and O'
wire caps should have been tested it: contact with metal is inconsistent with the plain language of IEEE 323-19'/4 IP is not aware that the NRC has applied this type of interpretation to environmental qualification of items until now, and believes it should not be penalized for this new departure from the customary reading of the IEEE standard.
In this connection, it should be noted that in 1985 the NRC audited the CPS environmental qualification file for the Limitorque motor operated valve actuators, including internal components of the actuators, and concluded in SSER 6 (after IP resolved certain discrepancies in the file) that environmental qualification of the actuators and their internal components had been adequately demonstrated (See IP letter U-600429 from F. A. Spangenberg (IP) to W. R Butler (NRC) dated February 14, 1986: CPS SSER 6 at pp. 3-8 to 3-9). Thus, the interpretation of EQ requirements being proposed by the NRC is not only unprecedented, but is in contradiction to be IP has sought to findings madetoearlier responsive the NRC by's the NRC concer. ns with respect to the butt splices and wire caps, and has taken action to bring CPS into conformance uith the NRC's new interpretation of how these items should have been tested, as described in subptrts I.C and D and III.C and D of IP's Reply to the Notice of Violation. However, IP believes that it is unfair to penalize individual licensees on the basis of new interpretations of which the licensees were not notified, especially when there interpretations are not consistent with earlier findings made by the NRC and are not apparent from a plain reading of the interpreted standard.
IP therefore denies that any violation occurred with respect to the AMP KYNAR butt splices and the nylon wire caps inside Limitorque motor operated valve actuators. Thus, two of the three examples listed in the Notice of Violation should not be used in calculating the amount of civil penalty to be assessed against IP. Based upon the one remaining item, which has been thoroughly corrected by IP (see subsections II.B. and C. of the Reply to the Notice of Violation), and l upon the fact that IP's environmental qualification program is generally sound, IP submits that it is inappropriate to .
escalate the civil penalty for the items contained in the l Hotice of Violation, and that remission of the penalty is warranted.
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