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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217J4331999-10-15015 October 1999 Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station ML20217A9881999-10-0101 October 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A7361999-10-0101 October 1999 Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs ML20217J1251999-09-30030 September 1999 Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC ML20217J1421999-09-30030 September 1999 Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC ML20212G6751999-09-22022 September 1999 Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability ML20217H3421999-09-17017 September 1999 Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed ML20211Q2671999-09-0808 September 1999 Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000 U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 ML20211D2201999-08-23023 August 1999 Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired ML20211A8931999-08-19019 August 1999 Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 ML20210U3771999-08-12012 August 1999 Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210A4401999-07-16016 July 1999 Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations ML20209G7671999-07-12012 July 1999 Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed ML20209D5691999-07-0707 July 1999 Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20196J9651999-07-0202 July 1999 Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements ML20196J7131999-06-30030 June 1999 Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1 U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology ML20196A3471999-06-16016 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology 05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed 05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors ML20209G7731999-05-27027 May 1999 Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999 Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999 Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5 U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999 Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999 Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999 Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999 Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999 Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999 Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999 Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f) U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999 Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3) 05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999 Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999 Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999 Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired 1999-09-22
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., _ _ - _ . . _ .
ilhnois Ponet Company
Chn10n, IL 61727 !
- Tel 217 935MP6 J. Stephen Perry Woe Preudent ILLIpleDI!E NMR "~6' 87*
L4 7-91 ( 09 -06 ) -LP 8E.100a I
September 6, 1991 10CFR50.91(a) (5) l 10CFR50.91 t i
l Docket No. 50-461 !
Mr. A. B. Davis ;
Regional Administrator .
Region III !
U.S. Nuclear Regulatory Commission ;
799 Roosevelt Road :
Glon Ellyn, Illinois 60137
(
SUBJECT:
Request for Waiver of Compliance Regarding Technical Specification Limiting Condition for i operation Related to Standby Emergency Diesel Generator 1B
Dear Mr. Davis:
Events have occurred at Clinton Power Station (CPS) which requiro your prompt attention as Illinois Power !
(IP) requests a waiver of compliance regarding the Technical Specification Limiting condition for operation l specified for the Division II Standby Emergency Diesel l Generator (DG1B). IP specifically requests that the l current limit of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the allowed out-of-service time specified in Action "b" of CPS Technical Specification 3.8.1.1 be waived, as IP desires additional time to offect repairs in response .o the discovery of microbiologically induced corrosion (MIC) in the jacket l
water heat exchanger for the 12-cylinder engine of DG1B.
In order to implement a complete and thorough (short-term) fix to the MIC problem for DG1B, IP ;
currently plans to replace both jacket water heat exchangers associated with DG1B. Therefore, IP requests l
that this waiver of compliance remain in effect until both jacket water heat exchangers for DG1B are replaced and operability of DG1B has been restored and verified.
IP estimates that, despite IP's continuous efforts to complete repair of DG1B, this work may require additional time beyond the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed by the CPS Technical Specifications. Therefore, IP reqtests that Ai v \
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9to9170229 910906 eDR noock 0so00461 1 kO {' I p DR
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I 4
DG1D be allowed to remain inoperable until 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> on ,
f September 9, 1991, for a total of four days (i.e., 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> beyond the 72-hour allowed out-of-service timo ,
i specified in tho Technical Specification Action Statomont). If this request is.not approved, CPS must be i in at Itact a Hot Shutdown condition by 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br /> on l September-9, 1991. i A more detailed description of thn condition, including the circumstancos surrounding the event, an ovaluation of the safety significance, justification for :
i this request, and a discussion of why this roquest does not involvo a significant hazards consideration is provided in Attachmont 1 of this lotter. Copios of the rolovant portions of CPS Technical Specification 3.8.1.1 are provided in Attachment 2 for reference.
IP has reviewed this request against.the critoria of 10CFR51.22 for categorical exclusion from environmental impact considerations. The roquest does not involvo a significant hazards consideration, or significantly increaso the amounts or change the types of offluents that may be released offsito, nor doos it significantly
-increase individual or cumulativo occupational radiation oxposures. Based on the foregoing, IP concludes that the proposed request moots the critoria given in 10CFR51.22 (c) (9) for a categorical exclusion-from the requiremont for an Environmental Impact Statement and thoroforo does not involve irreversiblo environmental consequences.
This request has boon reviewed and approved by the CPS Facility Review Group.
Sincoroly,
[
h S. Perry Vice President DAS/alh Attachments cc: NRC Clinton Licensino Project Manager NRC Resident Offico Illinois Department of Nuclear Safety NRC Document Control Desk i
i 1
' ,' Attachment I to U-601879
. Pago 1 of 7 Ilencription of Condition /Reangp for Reqqggt During normal shift roundo at approximately 2030 hourn on September 4, 1991, a plant operator dincovered that the jacket cooling water expansion tank on the 12-cylinder orgine for the Division II diocol generator (DG1D) at Clinton Power Station (CPS) was overflowing into tho floor drain at a rato of approximately one gallon /minuto.
(A heat exchanger in provided for each of the two tandom enginen (ono 16-cylinder and ono 12-cylinder) annociated with DG1D.) From earlier experienco, Illinclu Power (IP) suppocted that this may be caused by nervice water leaking through the diocol gonorator heat exchangor tuben into the jacket water cooling system. Although thin condition would not provont the DG from performing its cafety function (since the diosol can function with direct service water flow into the engino water jacket),
DG1D wan-romoved from nervico at 2050 hourn on September 5, 1991 for investigation and repair. Subcoquent inopoction revealed the prononco of microbiologically induced corrosion (MIC) which in believod to bo the cause of the tubo leakago.
MIC was first identiflod in the DG heat oxchangora at CPS in 1989 as IP was developing and implomonting its responco to Generic Lottor 09-13 and the associated supplomont.* As an immodiato correctivo action, cleaning and closed loop chemical treatment of the DGlu hoat exchangoro woro performed during the third planned outago (PO-3) at CPS (February 1990) to temporarily arront the MIC problom for DG1D. Rotubing of tho heat exchangora for the Division I diocol generator (DGIA) and oddy-current testing of the tubos in the heat exchangora for the Division III diesel generator (DG1C) wore also completed during Po-3. Subsequent to Po-3, IP chemically treated the Division II norvicu water syntom twico on an open-loop basic to provent further growth of MIC.
Howevor, IP replaced the tubon in the heat exchangers for DG1D in July 1990 following diccovery of a nimilar tubo leak (roference IP letter U-601696 dated June 22. 1990).
With the discovery of further MIC attack in the DG1D heat exchangor, it now appears that the current treatment schemo has not boon as offectivo ao IP originally bolloved and further ovaluation in required.
The oporability requiremento (during operational Conditions 1,2, and 3) for the omorgency standby diocol generators, including the actions to be taken if one (or more) 10 inoperablo, are speciflod in CPS Technical Specification 3.8.1.1. (Sco Attachment 2 of thic submittal.) Action "b" requiron that with either diocol generator-1A or 1D inoperablo, oporability of the required AC offsito sources must be demonstrated,
- Roforenco: IP Lottor U-601574 dated January 29, 1990
Attachment I to U-601879
. Pago 2 of 7 operability of the remaining oporablo diosol generators must bo demonstrated (unless the DG boca.no inoporablo solely duo to proplanned proventivo maintenanco or testing), and the inoperablo DG must be rostored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the inoporablo DG cannot be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the plant must be brought to a Hot Shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to a cold Shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Based on visual inspection of the tubos within the heat exchangor associated with the 12-cylindor engine of DG1B and previous experience with HIC at CPS, IP datormined that replacement of the heat exchanger was required.
Based on the sirallar service environment and operating history of the DG1B heat exchangers, IP determined that tho heat exchanger associated with the 16-cylinder engine of-DG1D should also be replaced. Sinco the heat exchangers are being replaced concurrently, this decision will not significantly alter the total timo required to complete the replacomant. Although replaceront heat oxchangers are currently availabic on sito and IP in working on a' continuous basis to comploto the replacement, the replacement and subsequent rotestw may not be able to be completed before the 72-hour time limit expironiat 2050 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.80025e-4 months <br /> on September 8, 1991. It is currently estimated that up to four days may be nooded to complete replacement of the heat exchangers, verify adequato service water system flow through the replacement heat exchangers, and complete testing required to rever'efy operability of_DG18.
Ilescrintion/ Sequence of Work _to be Performed As indicated above, the work plan for replacement of the heat exchangers for DGlB is such that both heat exchangers will be replaced concurrently. Both replacement heat exchangers are currently onsito. After installation of the replacement heat exchangers, pressure testing and service water flow verification will be required, followed by performance of a post-maintenanco surveillance test. IP currently estimates that all of the above may take up to an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> beyond tho-out-of-sorvice timo normally allowed by the CPS Technical Specifications.
Justification for Pronosed Roauest The IP electrical system design providos a diversity of power supplies. This request for waiver of complianco is L justified partially on this diversity. The 138-k
! offsito power system provides power to the station by one throo-terminal transmission line. This lino connects the station to the IP grid at the south Bloomington and Clinton Route 54 Substations. Electrical power can be
Attachmont 1 ;
to U-501879 Pago 3 of 7 !
fed to the station tnrough the lino from south l Bloomington or north Decatur (via Clinton Routo 54 ;
Substation) or both. The lino terminaten directly ;
r (through a circuit owitcher) at the Emergency Recorvo Auxiliary Trannformer, which transforma the oloctrical f power to 4160-volt auxiliary power bun voltago. Tho 345- !
kV offaito Power Syntom providen power to the station j through throo separato transminuion lines. Thoco linen ,
connect the station to tho Illinois Power Company grid at !
the Drokaw, Rising, and Latham substations. All throo !
lines terminato at the station switchyard ring bus which foods the Reservo Auxiliary Transformer (RAT), which in turn transforms the electrical power to tho 6900-volt and l 4160-volt auxiliary power bua voltago. Only one 138-kV !
foodor and ono 345-kV foodor are required by the CPS t Technical Specifications. l The RAT has experienced no failuron sinco IP roccived ito :
operatina licenso in September 1986. The only outage of l the off-sito power from the 345-kV uwitchyard occurred in ;
lato 1900 due to a failuro of a 345-kV diaconnect nWitch, j This outage was of s1. ort duration (24 houro). [
In the unlikely event that the power courcos doacribed abovo become unavailable, there are two remaining }
operahlg dional generators on site. Diosol Generator 1A [
(DG1A) supplios power to Division I electrical equipment and DG1C supplios poWor to Division III olectrical +
equipment. Those operable diosci c') orator ut,ita aro
- capable of noquentially startine ; supplying the power !
requirements for cafo shutdowr .he plant, because of ;
the divoralty of the power r os described above, the !
increano in the allowablo ( -sorvice timo for DG1B is r justified. i I
With respect to the current statun of other ayatema at CPS important to safety, the following are currently out i of cervice, j EY.nica Statuo*/ comments j
-(1) Position indication The limit switch for !
for Main Steamlino the position indication in !
Isolation Valvo achedulod to bo repaired j 1821-F022D-(Post- during the next plant ;
accident Monitoring shutdown. !
Instrumentation) j (2) Drywoll atmosphere Parts to repair filter !
particulato radio- paper drivo mechanism aro l activity monitoring expected to be rocoived on t system (Loak' September 6, 1991. Monitor Detection System) is expected to be restored shortly thereafter.
- As of September 6, 1991. [
I h
, _ _ _ _.____._.n_ . - _ __~ _ _. .__..____.___.________! _
T Attachmont 1 to U-601879 [
Page 4 of 7 Imminent restoration of the drywoll atmosphoro i particulato radioactivity monitor and the operability of l rodundant syntoms provido added anuurance that adoquato !
safety will bo maintained during the timo parlod that the i roquanted waivor of complianco would be in offect. ;
Regarding the nood for maintaining the picnt on-lino, CPS i la procontly generating approximately 30 porcent of the h total olectrical Ip customer load. It is octimated, however, that if CPS must nhut down, IP will continuo to I have c.doquato generating capacity. ;
Mdit;10Bal Hitiaatina conditionn 1P contacted the National Weather Servico in Springfloid, I Illinois and hao evaluated the current and expected :
weather conditions for the immediato service aroa, clear i weather with light and variable windo la forecast for the .
wookond. However, the forecast calls for a chango of
- scattered showers and thundorotorma Monday and Tuonday.
Tempqraturco for tho wookond are predicted to be moderato ;
with higha in the mid-to-high eighties with lown in tho ;
mid-cixtion. ,
Camnennatory Actionn }
The romaining operablo diocol generatoro aro ready to !
perform their intended function in the unlikely ovant that they are nooded. In addition, no testing will bo !
performod that might croato a transient to normal plant ;
conditions during the extended timo interval. Also, no !
nyatomo or equipment important to safoty which aro !
associated with the redundant safety-related division !
(Division I) will be removed from service for planned ;
maintenanco or tonting during tho extended timo interval. l Further, both replacoment heat exchangora arc oncito and i IP is working on a continuous baolo to completo ;
inctallation and rostoro DG1B to operablo utatuo.
I It should be noted that Action "b" of cps Technical ;
Specification 2.8.1.1 alao requires that operability _of ;
the remaining operablo diocol generatora be demonstrated ,
separately by performing surveillanco tests for starting i and loading thoso diocol generators if the diocol l generator which cauced entry into Action "b" becamo !
f inoperable due to any cause other than proplanned proventivo maintenanco or testing. However, an discussed l previously, leakage through the heat exchangor tuben accociated with a particular dionol generator does not i rondor the diocol generator inoperable cinco the diesel ;
can function with direct corvico water flow into the !
l engincor water jacket. Entry into the Action statomont ,
! to replace the DG1D heat exchangers was dono on a !
I voluntary bacia and is regarded as proplanned proventivo !
l t
maintenance. Thorofore, no additional tonting (i.e.,
l
Attachment 1 to U-601879 !
Pago 5 of 7 !
L starting and loading) to verify operability of the r Division I and III diesel generators (DG1A and DG1C) was j required or performed. ,
Safety Significangp/ Basis f or_ No _ Slanificau.t._llManlil ,
CgnsideratioD j IP does not consider this request to be safety significant in view of the following :,
- 1) With rocpoet to AC power, only the Division II DG is h currently inoperablo. As offsito power is available, sufficient redundancy existo (assuming no concurrent failuros) to provido omorgency power to ,
systems designed to mitigate the consequences of an i accident. [
- 2) Generally, operation under the provisions of an h Action Statomont is permittod for limited periods of !
time. It is recognized that singlo-failuro critorin !
may not bo not during such operation. IP believes that oporation with DGlu out of service for a period [
of tino longer than normally allowed but within the j noted limit constitutes no significant increano in !
risk regarding the saf) opcration of the facility.
- 3) In addition, IP does not believe that the present !
situation should require subjecting &ho plant to an l unnecessary shutdown. Although there is a cortain risk associated with tho increased allowed out-of- }
servico_timo, most challongos to plant systems occur 1 during startup and shutdown evolutions. Eliminating the risk associated with thoso events by proventing ;
an unnecessary plant shutdown due to the current i action timo limit, is viewed to be a positivo i increase in plant safety.
- 4) With respect to executing a safe shutdown of the i plant if required, the plant design is such that ;
safo shutdown to a cold condition can be achieved I with DG1B inoperable, particularly in view of the operability of all rodundant power sources and tho :
operable status of systems important to safety. [
i According to 10CFR50.92, a proposed chango to the licenso (Tochnical Specifications) involves no significant L
hazards consideration if operation of tho facility in :
L accordance with the proposed change would nots (1) involve a significant increase in the probability or i consequences of an accident previously evaluated, or_(2) !
croato the possibility of a new or different kind of '
c accident from any accident previously evaluated, or (3) 7 involvo a significant reduction in a margin of safoty. >
This request is ovaluated against each of those critoria l below.- f 1
I
^
Attachment 1 to U-601879
. Page 6 of 7
- 1) As noted above, the proposed one-tino request would permit DG1D to be out of servico for a longer period of tino than normally allowed oy the Technical specifications. However, in view of the oporability of all other required on-sito sources and all required off-sito sourcos, Ip believes that the proposed request does not constituto a significant increase in risk with respect to the capability of safety systems to mitigato the consequences of an accident. Additionally, the proposed request would i permit a reasonable amount of timo to rostore the DG1B heat exchangers to a liko-now condition whilo avoiding an unnecessary plant shutdown and potential cha11ongos to safety systems. Thoroforo, the proposed request does not involvo a significant increase in the probability or consequences of any accident previously evaluated.
- 2) The propocod requent does not involv: any changes to the design or operation of the plant. Sinco no now failure modos aro introduced by the proposed request,fthe proposed request does not create the possibility of a now or difforont kind of accident '
from any accident previously evaluated.
- 3) Under the proposod request, the al. lowed out-of-service time for DGlB (although longer than normally allowed) would still be limited to a reasonable period of time. With DG1A and DGlc operable, the proposed chango does not involvo a significant reduction in the margin of safety normally onsured by the Technical Specifications with respect to the availability of omergency onsite Ac sourcoss Dased on the foregoing, IP has concluded that this request does not involvo a significant hazards consideration.
ggneludino Remarks It should be noted that the current MIC problem of DG1B l could be resolved through a number of options. As noted previously, the diosol generator is not rendered inoperable by the MIC condition since the DG could K perform its intended function with flow directly from the service water' system into the jacket water system. One possible (but unrealistic) option would be to simply continuo operation with the heat exchangers "as-is."
Another option would bo to plug the leaking tubes in lieu of 'oplacing_them. Neither of those options, however, would be offective in mitigating the MIC condition or proventing a potential near-term future nood to again address degradation of the DGlB heat exchanger tubos duo to MIC.
Attachmont I t to U-601879
'- Pago 7 of 7 I The third option in to replaco the heat oxchangers. Thio ;
will rostore the heat oxchangers to a liko-new condition an IP roaddronnou its long-term solution to the MIC t problem. IP fools that thin in the appropriato courso of action. The proposed request would support comploto l replacuent of lath heat exchangora (for the 12-cy11nder l nnd 16-cylindor enginos), thus precluding the !
possibility, in the near term, of having to again romovo the DG from servico in order to perform additional l ropaira duo to MIC. ;
Plant and grid conditions are auch that now la an appropriate tino to request a waivor of compliance in ,
ordor to implomont a thorough (short-term) fix to the MIC [
problem for DG1D.
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