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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217J4331999-10-15015 October 1999 Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station ML20217A9881999-10-0101 October 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A7361999-10-0101 October 1999 Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs ML20217J1251999-09-30030 September 1999 Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC ML20217J1421999-09-30030 September 1999 Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC ML20212G6751999-09-22022 September 1999 Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability ML20217H3421999-09-17017 September 1999 Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed ML20211Q2671999-09-0808 September 1999 Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000 U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 ML20211D2201999-08-23023 August 1999 Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired ML20211A8931999-08-19019 August 1999 Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 ML20210U3771999-08-12012 August 1999 Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210A4401999-07-16016 July 1999 Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations ML20209G7671999-07-12012 July 1999 Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed ML20209D5691999-07-0707 July 1999 Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20196J9651999-07-0202 July 1999 Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements ML20196J7131999-06-30030 June 1999 Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1 U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology ML20196A3471999-06-16016 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology 05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed 05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors ML20209G7731999-05-27027 May 1999 Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999 Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999 Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5 U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999 Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999 Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999 Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999 Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999 Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999 Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999 Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f) U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999 Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3) 05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999 Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999 Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999 Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired 1999-09-22
[Table view] |
Text
. .. .
U 602025 L47-92(08-17)LP
. BE.100a tuos Power Ccmpany Clinton Power Sta%n
, P.O Ib 678 C1mton, il t I 72 ?
TtA 217 935-SPB1 POWER August 17, 1992 10CFR50.90 Docket No. 50 461 Document Control Desk Nuclear Regulatory Commission -
Washington, D.C. 20555
Subject:
Clinton Power Station Revision to Previously Submitted Proposed Amendment of Facility Opert tint License No. NPF-62
Dear Sir:
By letter dated September 20, 1991 (reference U-601871), Illinois Power (IP) applied for amendment of Facility Operating License No. NPF- ,
62, Appendix A - Tecnnical Specifications, for Clinton Power Station (CPS). That reqtest consisted of proposed changes to the CPS Technical Specifications to incorporate reliability-based improvements to instrumentation Action Statements and surveillance test intervals based on Topical Rep cts which were previously submitted to the NRC by the Bolling Wat_r Peactor Owners' Croup (B'JROC) . However, as a result of questions / comments received from the NRC during their review of IP's request, additional clarifications /revicior.s have become necessary.
Attachment 1 to this letter contains the additional clarifications as well as a description and justification for the additional proposed changes. Attachment 2 to this letter cortains replacement pages for the af fected marked-up pages f or Technical Specification 3/4.3. 7.1,
" Radiation Monitoring Instrumentation," and 3/4.3.9, " Plant Systems Actuation Instrumantation," contained in IP's September 20, 1991 request (i.e., pages 33, 34, and 35 through 39 of Attachment 3 to U-601871).
IP has reviewed the Bases for No Significant Hazards considerations contained in IP's September 20, 1991 amendment request and has concluded that the additional changes contained in this revision do not alter the bases or conclusions provided in those assessments.
Additionally, the changes contained in]this revision do not alter IP's l
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i af determination that:the proposed' changes meet the criteria given la 10CFR50.22(c)(9) for a categorical exclusion.from the requirement for an LEnvironmental Impact Statement, Sincerely yours
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F. A, pange erg, 11 Manager - Licensing &~ Safety
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. Attachments cc: Regional Administrator, Region III, USNRC NRC. Clinton Licensing Project Manager NRC Resident Office,-V-690
'IllinoisLDepartment of Nuclear Safety 4
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ce So Attachment 1-to U 602025-LS 88-042- l 1 Page 1 of 7
.3.
As a result of' questions / comments - received from the NRC during their review of IllinoisLPower's (IP's)-September 20, 1991 amendment request (reference U 601871):regarding reliability-based improvements to instrumentation JAction Statements and surveillance test intervals ,- additional clarifications / revisions have become necessary. These clarifications / revisions are related to the requirements for the followin5 '
instrumentation: (1) the Reactor Core Isolation Cooling (RCIC) system ,
actuation instrumentation, (2) the control rod block instrumentation, (3) radiation monitoring instrumentation, and (4 plant systems actuation
' instrumentation. Each-of these groups of requirements are discussed separately'below.
In addition, the NRC reviewer requested that IP confirm that the analysis documented in NEDC 30851P, " Technical Specification Improvement Analyses jfor BWR Reactor Protection System," for-the BWR/6 solid-state design
-supports relaxing-the Channel Functional Test frequency from monthly to .,
quarterly'for'the Manual Scram Functional Unit. IP confirmed with Genertl Electric that the Channel Functional Test frequency for the Manual Scram Functional Unit was assumed to be quarterly'in the model used for the analysis documented in.NEDC-30851P.
- 1. Technical Snecification 3/4.3.5. " Reactor Core Isolation Coolinn o System Actuation Instrumentation" TheJustification for IP') proposed changes to.the RCIC system
' actuation instrumentation requirements was provided in Part V of E Attachment 2 to IP's September 20, 1991 amendment request (reference page 28 uf 33). -IP's amendment request stated that the proposed
[
H changes were included in the Boiling Water Reactor Owners' Group
.(BWROG)fanalysis'of emergency. core cooling system (ECCS). actuation -
instrumentation-contained in NEDC-30936P, "BVR Owners' GroupL LTechnicals Specification Improvement Methodology (with Demonstration L for BWR ECCS. Actuation Instrumentation) Part-2." Howeier, model Technical Specification changes _ forL the RCIC actuation
-instrumentation.were not opecifically included in NEDC-30936P (Part
~
-2) . ?IP's-September 20, 1991- amendment request noted that model Technical Specification _ changes for the RGIC actuation h
H tinstrumentation were subsequently-provided_by the BWROG.in GENE-770-
~0 6-1, " Bases - for Changes to = Surveillance Test Intervals and Allowed
_ _0ut-of-Service Times for Selected Ins trumentation Technical Specifications." IP referenced the analyses provided in NEDC 30936P (Pait 2)L and -GENE-770-06-1 as the basis for the proposed changes to
-the RCIC:autuation instrumentation requirements.
JAdditional analyses and model: Technical Specification changes for the RCIC actuationiinstrumentation~were provided by:the BVROG in CENE-770-06-2, " Addendum to Bases for. Changes . to Surveillance Test
> Intervals .and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifica~!ons." IP has reviewed the-
. analyses presentedLin CENE-770.-06-2 and concluded that these tesults-are also directly applicable to CPS. The model Technical
, _ Specifications fur the BWR/6 solid-state plant (which were provided
- .. _. . - - - - _ - _ - - - - _ = _ ,
. . . ._- - . - . - . _. . . - - - . ~ . - - - ~ _ - --~---
Attachment 1
, to U-602025 LS-88-042 lage 2 of 7 in Appendix C of GENE 770-06-2) are identical to the proposed changes provided in IP's. September 20, 1991 amendment request. As a result.
-IP has determined that GENE-770 06-2 also providas justification for the changes to Technical Specification 3/4.3.5 proposed in IP's September 20, 1991 amendment request.
- 2. Technical Speci fication 3/4.3.6. "
Control Rod Block Instrumentation" The changes to Technical Specification 3/4.3.6 proposed in IP's September 20, 1991 amendment request are discussed in two separate locations in that request, Part III (reference page 12 of Attcchment
- 2) and Part V (reference page 29 of Attachment 2). Attachment 2, Part III, Item 1 of IP's September 30, 1991 amendment request discusses proposed changes to the allowable out-of-service time ( A0T)-
for performing surveillances. IP's amendment request stated that-this proposed change was included in the BWROG analysis docamented in t -NEDC-30851P, Supplement 1, " Technical Speciftcation Improvement l Analysis for BVR Control Rod Block Instrumentation." However, proposed changes to the surveillance A0T were actually included in GE';P-770-06-1. Thus, this proposed change should have been discussed under Part V of IP's amendment request. [The proposed change to the surveillance A0T was specifically addressed in GENE-770-06-1 by the addition of footnote "*" to Surveillauce Requirement 4.3,6 (reference GENE 770 06 1 pages 19 s Td A-40) . ]
In addition, the justification for the proposed changes to the ,
control rod block instrumentation requirements discussed in Part V of IP's September ~20,=1991 amendment request (reference page 29 of -
p Attachment 2) also contains an error in the BWROG report reference, i:
IP'sfamendment-request stated that the changes proposed in Part V Lwere bounded by the bases provided.in NEDC-30851P, Supplement 2.
However, this reference should have been NEDC-30851P, Supplement 1 sint Supplement 1- supports proposed changes to control rod block instrumentation requirements. (Supplement 2 addresses proposed changes to containment isolation instrumentation requirements.)
-3. Technical Specification 3/4.3.7.1. " Radiation Monitorinr.
Instrumentation" Proposed. changes to Technical Specification 3/4.3.7.1, which are j _ based onLGENE-770-06-1, were described in Part V of Attachment 2 to l _ IP's September _20,fl991 amendment request (reference pages 25 and 29). GENE-770-06-01 provided the justification for changing the Channel Functional Test Frequency for the main control room air intake' radiation monitors from monthly-(M) to quarterly (Q) based on the analyses documented in NEDC-31677P, " Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation."
NEDC-31677P also supported changes to the repair A0T for containment L isolation instruments" from one hour to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. However, CENE-770-06-01 did not specifically identify that the repair A0T for the main control room air intake radiation monitors could be increased.
- Notwithstanding, based on the main control room air intake radiation .
monitoring instrumentation arrangement being similar to the containment and reactor vessel isolation control system (CRVICS)
~
radiation monitoring instrumentation, IP concluded that the analysis .
,-er
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F Attachment.1
, to U 602025 LS-88-042 Page 3 of 7 of the isolation actuation instrumentation provided in NEDC-31677P supports similar surveillance test interval (STI) and A0T changes to the Technical Specifications for the main control room air intake radiation monitors.
During subsequent conversations with the NRC, it was determined that, as no specific change to the repair A0T was identified for the main control room air intake radiation monitors and the referenced Technical Specification in GENE-770-06 1 was "BWR 6 Improved Technical Specification (ITS), Control Room Fresh Air Instrumentation" (reference GENE 770-06-1 page 18), the NRC would only agree to the repair AOT provided in the BWR 6 Improved Technical Specifications. -
IP continues to believe that the analysis of the isolation actuation
-instrumentation provided in NEDC-31677P supports similar STI and A0T changes to the Technical Specifications for the main control room air intake radiation monitors. How3ver, IP now proposes that the repair A0T for these radiation monitors be increased from one hour to six
' hours (rather than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) to be consistent with the latest draft of.the BWR 6 Improved Technical Specifications (NUREG-1434).
Therefore, IP requests that the marked up pages from Technical Specification 3/4.3 7.1 contained in.IP's September 20, 1991 amendment request-(Attachment 3 pages 33 and 34) be superseded by the marked up pages 1 and 2 of Attachment 2 of this letter.
1-
- 4. Technical Specification 3/4.3.9. " Plant Systems Actuation Instrumentation" Proposed changes to Technical Specification 3/4.3.9, which are based on GENE 770-06-1, were described in Part V of Attachment 2 to IP's September 20, 1991 amendment request (reference pages 25 and 30). _
CENE-770-06 1 provides justification for increasing the repair A0T
~
for these instruments "if takinn out the channel does not cause loss of the trip function." During their review of IP's amendment request, the NRC ncted that the proposed changes to the repair A0Ts for the containment spray system and the suppression pool makeup system actuation instrumentation of Technical Specification 3/4.3.9 are not consistent with this limitation of GENE-770-06-1. As a-
-result, IP has re-evaluated the proposed changes to the repair A0Ts -
for Technical ~ Specification 3/4.3.9 and determined that the marked-up pages-from Technical Specification 3/4.3.9 contained in IP's September 20, 1991 amendment request (Attachment 3 pages 35 through
- 39) should-be superseded by the marked-up pages 3 through ? of
-Attachment 2 to this letter. [The additioaal changes proposed by
-this revision are identified by double change bars.] Justification for each-of these proposed changes is discussed below.
Containment Spray System
_The containment spray system is an operating mode of the residual heat removal (RHR) system and is a containment heat removal system.
The containment spray system is described in CPS Updated Safety Analysis Report (USAR) Section 6.2.2. As described in the USAR, during containment spray system operation, water is drawn from'the
]
Attachment 1 to U-602025 LS-88 042 Page 4 of 7 i
suppression pool, pumpec through one or both RHR heat exchangers (which removes heat to the emergency service water system), and is 3 delivered to the containment spray headers. Most of the water discharged from the containment spray headers will return to the suppression pool, where it is recirculated through the spray headers.
The purpose of this mode oi RHR is to cool non-condensible gases and condense steam which may be present in the containment following a loss-of-coolant accider- (LOCA) in order to reduce containment pressure and prevent atainment from exceeding its design limits.
The actuation logic for the containment spray system at CPS is described in USAR Section 7.3.1.1.4.4. As described in the USAR, the _
containment spray system can be actuated either automatically or manually. The system is automatically actuated approximately 10 minutes af ter receiving a LOCA signal (which is provided by two high drywell pressure and two low reactor water level, level 1 signals combined in a one-out-of-two-twice logic configuration) provided a high drywell pressure condition (two signals combined in a one-out-of-two logic arrangement) and a high containment pressure condition (two signals combined in a one-out-of-two logic arrangement) exist concurrently. In addition, the Division 11 system includes an additional 90-second time delay to ensure that both containment spray loops do not initiate simultaneousif. The system can be manually actuated by arming and depressing a single manual pushbutton coincident with the above high drywell pressu o condition (or.e-out-of-two).
The analog trip modules (ATMs) (or channels) used to provide the LOCA signal for automatic actuation of the containment spray system are the same ATMs (or channels) used to automatically initiate operation .
of the low pressure emergency core cooling systems (ECCS). In addition, the current Action Statements under Technical Specification 3/4.3.9 are based on the number of containment spray loops affected by inoperability of the instrument channels rather than the effect on the automatic actuation capability for the associated loop. In contrast, the Action Statements under Technical Specification 3/4.3.3 for the ECCS actuation function of these instruments are based on whether automatic trip capability has been affected for the associated ECCS loop. In order to maintain consistency with the proposed ECCS actuation function Action Statements (i.e., those contained in IP's September 20, 1991 amendment request) and to satisfy the preciously noted limitation of CENE-770-06-1 (regarding potential loss of function), IP now proposes to revise the Action Statements for the containment spray loops by deleting Action Statement "b" a d creating new Action Statements 52 and 53 for Table 3.3.9-1, " Plant Systems Actuation Instrumentation."
The proposed Action 52 is based on the number of channels that are affected (rather than the number of containment spray loops affected) so that the impact on automatic actuation capability for the associated containment spray loop is properly considered. Proposed Action 52 is consistent with the corresponding Action Statement for the i r/well Pressure-High and Reactor Vessel Water Level - Low Low Low, Level 1 instruments under Technical Specification 3/4.3.3. (See
, - . - - . - . - . - - - .- . . - - _ _ ~ . - . , - - - .
Attachment l
, to U-602025 LS-88-042 Page 5 of 7 Action 30.)- As the containment pressure signals for the containment
-spray system are arranged in a one out-of-two logic configuration, ,
inoperability of one containmene pressure instrument will not alone cause loss of the automatic actuation capability for the associated containment spray' loop. Therefore, proposed Action 52 has 4.n
. addition to-the Drywell Pressure - High and Reactor Vessel Water
. Level - Low Low Low, Level 1 Trip Functions) also been apolied to the Containment-Pressure - High Trip Function.
Proposed-Action 53 applies to those Trip Functions with od v one channel per containment spray loop. In the event that one o ~ these channels become inoperable, actuation of the associated contaiinent r spray loop could be prevented [ automatically (as in the case of timers) or manually (as in the case.of manual initiation pushbuttons)]-, As a result, it is appropriate to declare the associated containment spray loop inoperable and follow the appropriate Action Statement under Technical Specification 3/4.6.3.2,
" Containment Spray." Proposed Action 53 has accordingly been applied ,
to the Timers and Manual Initiation Trip Functions.
Proposed Actions 52 and 53 for the containment spray er.tuatior
-instrumentation are bounded by.the model Technical Specifications and analyses ptesented in GENE-770-06-1 (reference pages 15 and A-32) and appropriately implement the allowable repair A0T extension to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in only those instances where taking out the channel does not cause loss of the trip function.
Suppression Pool Makeup System The suppression pool mskeup system (SPMS) is described in CPS USAR Section 6.2.7. As stated in the USAR, the SPMS provides makeup water from the upper containment pool to the suppression pool by gravity
' flow following a LOCA. The quantity of water provided is sufficient l
to account for all conceivablo post-LOCA entrapment volumes to ensure that long-term drywell vent coverage is maintained. -The SPMS consists of two-independent lines, either of which is capable of providing the required water volume. Each of these lines contains g two normally-closed, motor-operated valves. .As these valves are I
arranged in series, opening of both valves is required to provide-
- -makeup water to the suppression pool via the associated dump line.
The-logic _for the SPMS is described in UShR Section 7.3.1.1.10.4 As.
described in the USAR, the SPMS can be actuated either: automatically or manually, provided the SPMS mode switch is in the " enable" position. {The SPMr rode switches are provided on a divisional basis to prevent.actuatim s abtomatically o. mar.ually) of that SPMS division (i.e.,-dwsr line). As described in USAR Section y 7.3.1.1.10.6, the SPMS is disabled during tuel handling activities to
- prevent overexposure of refueling personnel as a result of an inadvertent SPMS actuation during--fuel handling activities.] With respect to automatic actuation of the SPMS, mach trip system-will automatically _open both. valves in the associatedadump line. Each trip system is-actuated with a LOCA signal (which is provided by two high drywell pressure and two low reactor water level, level 1 signals which are combined in a ane-out-of-two-twice logic-
Attachment 1 to U-602025 LS-88-042 Page 6 of 7 configuration) coincident with a low suppression pool level condition (two signals combined in a one-out-of-two logic arrangement).
Alternctely, the SPMS will automatically actuate approximately 30 minutes af ter a LOCA signal in the absence of a low suppression pool level condition. Further, each SPMS dwnp valve is equipped with a manual control switch. Manually opening both dump salves in a SPMS line will thus tesult in manual accustion of the associated $FM9 division.
Similar to the logic for the RHR containment spray system discussed above, the ATMs (or chsnnels) used to provide the LOCA signal for the SPMS are the same ATMs (or channels) used to initiate operation of the low pressure ECCS and RHR containment spray systems. The current _
Action Statement for these SPMS instruments (Action 50) is based on the number of trip systems affected by the inoperability rather than the impact on the automatic trip capability of that trip system.
Therefore, IP rroposes to revise Action 50 to address the number of channels that are affected (rather than the number of trip systems).
This proposed change will make Action 50 consistent with Action 52 for the RUR cantainment spray system and Activa 30 for the low pressure ECCS.
In addition, Action 50 currently allows placing the inoperable channel (s) and/or trip system in the tripped condition to satisfy the Action requirement. However, placing a trip syster in the tripped condition would result in actuation of the associated SPMS. As a result, IP proposes to delete this option from Actica 50. Further, as the low suppression pool water level signals are arranged in a one-out-of-two logic configuration (for each logic subsystem), .
inoperability of one suppression pool water level instrument will not al ane cause loss of automatic initiation capability for the associated SPMS line. Therefore, IP proposes that Action 50 also be _
applicable to the Suppression Pool Water Level-Low Low Trip Function.
The proposed chaages to Action 50 for the suppression pool makeup system actuatien instrumentation are bounded by the model Technical Specifications and analyses presented a GENE-770-06-1 (reference pages 16 and A-32-) and appro .iatelj implement the allowable repair AUT extension to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on;y in those instances where takir; out the channel does not cause loss of the trip function. t Editorial / Format Channes In order to facilitate the use of a consistent format for the Action Statements for each of the plant systems actuation instruments, the current Action Statement "c" addressing the feedwater/ main-turbine trip system has been relocated to Table 3.3.9 1 as new Action 54. As there are no changes to these requirements, this change is purely edit rial.
Current Action Statement "d" addresses inoperability of SPMS actuation instrumentation and directs action to be taken as required by Table 3.3.9-1. As the action requirements for all instruments within the scope of this Technical Specification are now dictated by Tabic 3,3.9-1, Action Statement "d" has been replaced by new Action
_ , . .. .- - - -- - - . . ~ . . . - - -. . - -- . - . ,
/
Attachment--1
- to U-602025 9;
LS-88 042-
. Page-7 of 7 Statement;"b" which generically. addresses inoperable plant systems actuation instrumentation. As the proposed Action "b" directs-action to be taken-as required by Table 3.3.9 1 for any inoperable-plant systems-actuation instrumentation and the applicable Action Statements are addressed above, this change does not resule in any technical changes. Therefore, this change is'also editorial.
' Footnote "*" to Table 3.3.9-1 currently states, in part that a ,
channel may be placed in-an inoperable status for required surveillans without placing the trip system in the tripped condition. Hosever, as stated above, placing a trip system in the
~ tripped condition will result-in-an automatic ectuation of the '
associated system (s). -In addition, each of the Action Statements (as proposed) only addresses placing a chu.nel in the tripped condition.
Therefore, IP-proposes to revise footnote "*" to state "...without placing the channel in the tripped condition...". As this more accurately-reflects _the proposed Action Statements, this propoaed
' change is also editorial.
-, . Finally, the word." action" has been replaced with the defined term-
'" ACTION" in the. proposed Action Statements to denote that-the associated Action Statement is being referenced. -Thcre is no change in intent, and.therefore, this change is also editorial.
- Summary In summary, this submittalLprovides: (1) an additional reference for IP's
- proposed changes to-the RUIC actuation instrnmentation requirements as provided in I/*s September 20, 1991 amendment request, (2) makes editorial
- corrections to references for IP's proposed changes to the_ control rod block instrumentation:-requirements as provided in-IP's September 20, 1991
- amandment reque.t,.(3) provides a revision to the proposed rcpair AOT for
' the s in control room airLintake radiation'nenitors,'and (4)-provides
. reviatons = to othe Action Stacements (including format) and surveillance A0T
- footnote for-thefplant systems;ectuation' instrumentation. IP,has-reviewed-the(Bases for No-Significant Hazards Considerations provided IP's September-20,11991 amendment regunst and.has.cor.cluded that'the additional-changes contained in this revision do net. alter. the bases or conclusions provided
. in those assessments.
+_
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