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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217J4331999-10-15015 October 1999 Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station ML20217A9881999-10-0101 October 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A7361999-10-0101 October 1999 Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs ML20217J1251999-09-30030 September 1999 Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC ML20217J1421999-09-30030 September 1999 Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC ML20212G6751999-09-22022 September 1999 Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability ML20217H3421999-09-17017 September 1999 Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed ML20211Q2671999-09-0808 September 1999 Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000 U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 ML20211D2201999-08-23023 August 1999 Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired ML20211A8931999-08-19019 August 1999 Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 ML20210U3771999-08-12012 August 1999 Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210A4401999-07-16016 July 1999 Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations ML20209G7671999-07-12012 July 1999 Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed ML20209D5691999-07-0707 July 1999 Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20196J9651999-07-0202 July 1999 Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements ML20196J7131999-06-30030 June 1999 Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1 U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology ML20196A3471999-06-16016 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology 05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed 05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors ML20209G7731999-05-27027 May 1999 Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999 Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999 Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5 U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999 Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999 Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999 Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999 Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999 Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999 Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999 Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f) U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999 Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3) 05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999 Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999 Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999 Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired 1999-09-22
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L6571990-09-19019 September 1990 Advises That Dp Hall No Longer Associated W/Facility Since Dec 1989.Mail Should Be Addressed to Js Perry JSP-739-90, Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump1990-09-12012 September 1990 Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump U-601729, Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn1990-08-27027 August 1990 Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn JSP-676-90, Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event1990-08-23023 August 1990 Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event U-601723, Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.711990-08-16016 August 1990 Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.71 U-601722, Forwards Reissued NPDES Permit IL00369191990-08-10010 August 1990 Forwards Reissued NPDES Permit IL0036919 U-601721, Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators1990-08-0808 August 1990 Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators U-601716, Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))1990-08-0303 August 1990 Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2)) U-601715, Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly1990-08-0202 August 1990 Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly U-601708, Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 19891990-07-19019 July 1990 Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 1989 U-601702, Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990 Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20044A3001990-06-22022 June 1990 Forwards Update to 890817 Response to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Unisolable Piping Connected to RCS Identified & Evaluated to Determine Which Piping Could Be Subj to Stratified Flow Phenomena ML20044A4601990-06-22022 June 1990 Provides Followup to 900622 Request for Waiver of Compliance Re Tech Spec Limiting Condition for Operation Concerning Standby Emergency Diesel Generator 1B.Rev to Attachment 1 of Original Request for Waiver Encl ML20043H5021990-06-19019 June 1990 Requests Changes to License NPF-62,correcting Typos, Refs to Fsar,Testing to Be Done During Initial Plant Startup & Incorporating Revised Operating Power/Flow Map for Two Reactor Recirculation Loop Operation ML20043G8221990-06-0707 June 1990 Provides Update to Util Response to Item 1 of Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. ML20043F0591990-06-0606 June 1990 Forwards Endorsements 44-50 to Nelia Policy NF-261 & 25-31 to Maelu Policy MF-121 & 10 & 11 to Maelu Policy N-85 & M-85,respectively ML20043D0531990-05-31031 May 1990 Forwards 1989 Annual Rept for Illinois Power Co & Soyland Power Cooperative,Inc ML20043C7501990-05-25025 May 1990 Forwards Rev 20 to Illinois Power Nuclear Program QA Manual. Rev Evaluated by Util as Not Reducing Quality Program Commitments ML20043B4891990-05-21021 May 1990 Informs NRC of Plant Initiatives for 1990 to Improve Corrective Action Program Effectiveness,In Response to SALP Rept & Violations Noted in Insp Rept 50-461/89-32. Centralized Commitment Tracking Sys Upgraded ML20043B1141990-05-17017 May 1990 Suppls 900330 Response to Station Blackout Rule.Calculation of Heatup of Main Control Room Due to Loss of Ventilation Following Station Blackout Revised to Properly Account for Heat Sinks & Credit Existing Masonry Walls ML20043D9901990-05-14014 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Rept 50-461/90-02.Corrective Actions:Safety Evaluation Prepared & Reviewed for Level Instrumentation & Annunciators Identified in Updated SAR ML20043A9811990-05-14014 May 1990 Notifies That Wc Metzner Resigned from Position of Licensed Operator W/Util,Effective 900430 ML20042E6181990-04-13013 April 1990 Updates 890406 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Condition Rept Initiated to Address Issue to Drain Instrument Air Filter Regulators ML20012E8991990-03-27027 March 1990 Forwards Rev 9C to Physical Security Plan.Rev Does Not Decrease Effectiveness of Plan.Rev Withheld (Ref 10CFR73.21) ML20012D9451990-03-20020 March 1990 Informs of Current Activities Re Restoration of Shutdown Svc Water (SX) Sys to Operability Following Cleaning of Div I HX Per Generic Ltr 89-13.SX Sys to Be Restored by Returning Sys Flows to Design Values ML20012D9641990-03-19019 March 1990 Lists Present Levels of Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w)(2) ML20012D9901990-03-19019 March 1990 Responds to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-461/89-38.Corrective Actions:Maint Supervision Added Critical Points to Existing Maint Work Requests & Preventive Maint Activities & Training Program Updated ML20012D4321990-03-16016 March 1990 Responds to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Detailed Analytical Review & Proposed Schedule for Implementing Required Actions Scheduled to Be Completed by 900625 ML20012A2771990-02-28028 February 1990 Forwards Final Response to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded Case Circuit Breakers. Actions Taken by Util Have Established That All safety-related Circuits Remaining in Stock Can Be Verifiably Traced to Mfg ML20012C2511990-02-23023 February 1990 Responds to Ninth SALP Rept 50-461/89-01 for Sept 1988 - Oct 1989.Rept Concluded That Overall Performance Satisfactory & Identified Strengths in Areas of Emergency Preparedness U-601611, Notifies That Gd Setser Resigned Position W/Util,Effective 9002131990-02-20020 February 1990 Notifies That Gd Setser Resigned Position W/Util,Effective 900213 ML20011F6501990-02-12012 February 1990 Responds to NRC 900112 Ltr Re Violations Noted in Insp Rept 50-461/89-37.Corrective Actions:Radiation Protection Technicians Provided W/Method for Identifying Radiation Work Permits Which Change Radiological Conditions ML20006C6721990-02-0505 February 1990 Responds to NRC 891207 Ltr Re Violations Noted in Insp Rept 50-461/89-35.Corrective Actions:Emergency Planning Bulletin Issued to All Emergency Response Organization Members Emphasizing Importance of Attending Required Training ML20006D1951990-01-30030 January 1990 Responds to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Util Intends to Discontinue Sending Ack Upon Receipt of Vendor Manual Matls ML20006A8291990-01-23023 January 1990 Forwards Rev 3 to Inservice Exam Plan. Changes to Text Described.Approval of Changes by 900601 to Allow Time to Plan Refueling Outage Activities Re Inservice Exam Program Requested ML20005H2711990-01-12012 January 1990 Advises That Licensee Will Remove Terminal Blocks for Control Circuits within 100% Relative Humidity Harsh Environ at Plant by End of Second Refueling Outage Currently Scheduled to Begin in Sept 1990 ML20006A7121990-01-10010 January 1990 Forwards Revised Pages to 1987 Radiological Environ Monitoring Rept ML20005F0001990-01-0505 January 1990 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Util Revised Plant Operating Procedures for Hpcs,Lpcs & RHR Pumps & Vibration Monitoring Program Expanded to Include ECCS Pumps at Plant ML20006A7921989-12-29029 December 1989 Responds to 891129 Ltr Which Forwarded Insp Rept 50-461/89-31,requesting Identification of Actions Underway to Ensure That Falsification of Interim Security Screening Records Would Be Detected in Timely Manner in Future U-601573, Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently1989-12-29029 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently ML20005E0891989-12-27027 December 1989 Advises That Revised Fitness for Duty Program Will Meet 10CFR26 Requirements,Effective 900103.Util Intends to Test for Substances Listed at Indicated cut-off Levels ML20006C2961989-12-21021 December 1989 Responds to NRC 891121 Ltr Re Violations Noted in Insp Rept 50-461/89-32.Corrective Actions:Review Performed to Identify Surveillances Which Require Lifting of Leads in Main Control Room ML20005D9521989-12-15015 December 1989 Forwards Monthly Operating Rept for Nov 1989 for Clinton Power Station Unit 1 & Corrections to Oct 1989 Rept ML20005E7781989-12-12012 December 1989 Advises That False Alarm Criteria Will Be Implemented by 900131,per Insp Rept 50-461/89-31.Util Established New Criterion of 100 False Alarms for Security Sys in 24 H Period ML20011D1741989-12-0707 December 1989 Informs of Changes Made to Util Fitness for Duty Program Procedure.Change Specifies That Supervisor - Medical Programs,Assistant Director - Labor Relations or Manager - Nuclear Planning & Support Will Generate Computer List ML19332F0071989-11-30030 November 1989 Responds to Violations Noted in Insp Rept 50-461/89-29. Corrective Actions:Preventive Maint for Ph Monitor & Liquid & Gaseous Gamma Monitors Added to Appropriate Tracking Programs ML19332E9431989-11-29029 November 1989 Forwards Executed Amends 4 & 5 to Indemnity Agreement B-91, Reflecting Change in Ownership of License,Effective 890327 ML19332D5031989-11-27027 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Results of Util Review & Reporting of Status of Implementation of USIs Encl ML19332D0291989-11-22022 November 1989 Informs That Effective 891201,JS Perry Will Assume Responsibility for Mgt of Nuclear Program at Util ML19332D0431989-11-22022 November 1989 Informs NRC of Change in Schedule for Providing Info Re Environ Qualification Testing of Terminal Blocks for Control Circuits of Conax Electrical Penetrations.Wyle Labs Test Results & Util Review of Results Will Be Sent by 900112 1990-09-19
[Table view] |
Text
,-
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> U 600848 n
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'lLLJN018' POWER COMPANY
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,, CLfNTON POntR STATION, P.O. BOX 678. CLINTON. fLLINOIS 61727
- MAR 31987
- ' Docket No. 50-461
-Mr. Harold R. Denton,' Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.. 20555
Subject:
Clinton Power Station Technical Specifi' cations for Full Power Operating License Dear Mr. Denton n This letter supplements Illinois Power Company's (IP) letters dated January 8, 1987 (U-600785) and February 4, 1987 (U-600817) and provides additional changes that IP requests be included in the Technical Specifications (CPS-TS) which will accompany the full-power operating license for the Clinton Power, Station. These changes represent clarification and sahancements to the CPS-TS and in'part, have been discussed with your Mr. B. L. Siegel, Clinton NRC Project Manager. The justifications and the proposed marked-up phges are attached. None of these changes affect IP s ability to safely operate the Clinton
. -Power Station under its current license. Therefore, no amendment to the present low-p'ower license (NPF-55) is being rs' quested. ,
These changes to the CPS-TS'have been reviewed and are consistent in all material aspects with the FSAR as amended,
.the Safety Evaluation Report and its Supplements Nos. 1-7 and the as-built plant. An affidavit relating to this certification accompanies this letter.
If you have any questions or require additional information, please contact me.
Sinc e ours,
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D. P. all Vice President RPF/ckc Attachment 80*'
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STATE OF ILLINOIS COUNTY OF DEWITT DONALD P. HALL, Being first duly sworn, deposes and says: That he is Vice President of Illinois Power Company; that the information provided in letter U-600848 to certify that the Clinton Power Station (CPS) Technical Specifications are consistent with the CPS - Final Safety Analysis Report, the NRC Safety Evaluation Report and the as-built facility, has been prepared under his supervision and direction; that he knows the contents thereof; and that to the best of his knowledge and belief said request and the facts contained therein are true and correct.
DATED: Thisd day of J4a 1p Signed: ('DonaT&T . Hall Subscribed and sworn to before me this M day of March, 1987.
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Attcchment U-600848 Page 1 of 23 Description of Change Table 1.2, page 1-11 Change Table 1.2 Notations *** to delete the word "recoupled" and insert the word " moved".
Justification The purpose of this note is to allow for testing to determine operability in accordance with Specifications 3/4.1.3.2 and 3/4.1.3.4 In addition, this change is consistent with changes made to other BWR Technical Specifications (LaSalle, River Bend, Perry, and Hope Creek).
The above change request was presented for consideration in letter U-600817 dated February 4, 1987. At the request of Mr. B. Siegel and D.
Katze, the following additional information is provided.
Movement of control rod under the controls of the one-rod-out interlock is considered as part of the design basis of operation of the reactor.
The design basis for the one-rod-out interlock is such that the single, highest worth control rod can be removed from the reactor core at any time while still preserving the required shutdown margin. Shutdown margin is demonstrated in Specification 3/4.1.1. A sufficient shutdown margin ensures that the reactor can be made suberitical from all operating conditions, the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
a i
Attechmtnt U-600848
~Page 2 of 23 TABL'E 1.2 r,3
~
MODE SWITCH CONDITION AVERAGE REACTOR POSITION COOLANT TEMPERATURE
- 1. POWER OPERATION Run Any temperature
- 2. STARTUP Startup/ Hot Standby Any temperature
- 3. HOT SHUTDOWN Shutdown #'*** > 200*F
- 4. COLD SHUTDOWN Shutdown #'##'*** 1 200*F
- 5. REFUELING
- Shutdown or Refue1**'# $ 140*F M , TABLE NOTATIONS l
- The reactor mode switch may be placed in.the Run or Startup/ Hot Standby position to test the switch interlock functions, provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
- The reactor mode switch may.be placed in the Refuel. position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.
- Fuel in the reactor fully tensioned vessel or with with the the head vessel head closure bolts less than removed.
- See Special Test Exceptions 3.10.1 and 3.10.3.
j y *** The reactor mode switch may be placed in the Refuel position while a single control rod is being(r;;;;;?:C OPERABLE.
ed provided that the one-rod-out interloc l
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4 CLINTON - UNIT 1 1-11 l
, ,. Attachment
'. U-600848 Page 3 of 23 Description of Change Table 3.3.2-2, Item 4.1, page 3/4 3-23.- !
Change the inequality sign from 1 to f . ,
1 Justification Typographical Error.
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TABLE 3.3.2-2 (Continued)
P E CRVICS INSTRUMENTATION SETPOINTS 3
z TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE E
I Z 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued) i e. RCIC Equipment Room Ambient .
l Temp. - High 1 222.5'F 1 233.1*F
- f. RCIC Equipment Room a Temp. - High 1 34.5'F i 40*F l g. Main Steam Line Tunnel Ambient j Temp. - High i 165'F i 176*F i
- h. Main Steam Line Tunnel t
w a Temp. - High < 54.5*F
_ < 60*F s
b
- w i. Main Steam Line Tunnel e
, 4 w
Temp. Timer -d5 min. 1 28 min. l i
! j. Drywell Pressure - High i 1.68 psig i 1.88 psig l k. Manual Initiation NA NA j
j 1. RHR/RCIC Steam Line Flow - High 1 179.5 in. H20** 1 188 in. H20**
- m. RHR Heat Exchanger A, B Ambient Temperature - High 1 138.5*F i 149.6*F
- n. RHR Heat Exchanger A, B a Temp. - High 5 74.2*F 1 79.6*F , , y c: g oo e n
- 5. RHR SYSTEM ISOLATION -
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! a. RHR Heat Exchanger Rooms A, B *$"
Ambient Temperature - High 1 138.5*F i 149.6 F g
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- b. RHR Heat Exchanger Rooms A, B a Temperature - High 1 4.2*F 7 i 79.6*F
-s Attcchm:nt U-600848 Page 5 of 23 Description of Change Table 3.3 3-2. Item A.1.c, page 3/4 3-39 and Item B.1.c, page 3/4 3-40 Change the trip setpoint to 472 psig and allowable value range to 1 452 psig,S. 478 psig.
Justification The Instrument Setpoint Methodology Program (ISM) sponsored by the BWR Owners Group authorized General Electrical Company to perform validation calculations of the Technical Specification operating limits and instrument setpoints. The ISM calculation, for the LPCS/LPCI injection valve interlock, has determined that the instrument (Rosemount 1153B pressure transmitter) loop accuracy is significantly affected by a high environmental radiation dose equivalent to that in a LOCA. To remedy this concern, the Rosemount 1153B pressure transmitters are being replaced with Rosemount 1154R pressure transmitters. These new pressure transmitters have higher radiation tolerances and low inaccuracies due to radiation effects. The replacement of the 1 transmitters and revisions to the CPS-TS bring the CPS-TS into compliance with the ISM requirements.
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TABLE 3.3.3-2 ,
b EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS 5
E
, ALLOWABLE e TRIP FUNCTION TRIP SETPOINT VALUE A. DIVISION I TRIP SYSTEM
[
- 1. RHR-A (LPCI MODE) AND LPCS SYSTEM -
- a. Reactor Vessel Water Level - Low Low Low, > -145.5 in.* 2 -147.7 in.
Level I
- b. Drywell Pressure - High $ 1.68 psig $ 1.88 psig
- c. Reactor Vessel Pressure-Low (LPCS and LPCI 452 9 78 Injection Valve Permissive) y72M psig > M sig, < ig
- d. LPCI Pump A Start Time Delay Lggic Card 5 sec. 5 i 0.5 sec.-
- e. LPCS Pump Discharge Flow - Low 2 875 gpm 2 750 gpm w f. LPCI Pump (A) Discharge Flow - Low,, 3 1100 gpm 3 900 gpm
) g. Manual Initiation NA NA
[ 2. AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "1"
- a. Reactor Vessel Water Level - Low Low Low, -> -145.5 in.* -> -147.7 in.
Level 1
- b. Drywell Pressure - High $ 1.68 psig $ 1.88 psig
- c. ADS Timer < 105 sec. < 117 sec.
- d. Reactor Vessel Water Level-Low, level 3 I 8.9 in.* I 8.3 in.
- e. LPCS Pump Discharge Pressure-High [145psig [125psig
- f. LPCI Pump A Discharge Pressure-High 2 125 psig 2 115 psig
- g. ADS Drywell Pressure Bypass Timer < 6.0 min. < 6.5 min.
- h. Manual Inhibit ADS Switch NA NA
- 1. Manual Initiation NA NA . , ycg
. $$E
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TABLE 3.3.3-2 (Continued) ..
n C EMERGENCY CORE COOLING SYSTEM ACTUATION INS 1RUMENTATION SETPOINTS 5
E ALLOWABLE
. TRIP FUNCTION TRIP SETPOINT VALUE e
5 B. DIVISION II TRIP SYSTEM H
- 1. RHR 8 AND C (LPCI MODE)
- a. Reactor Vessel Water Level - Low Low Low, > -145.5 in.*
> -147.7 in.
Level I
- b. Drywell Pressure - High 1.68 psig i 1.88 psig
- c. Reactor Vessel Pressure-Low (LPCI Injection 4 72. 452 478 Valve Permissive) M sig > 469# psig, 5 d psig
- d. LPCIPump(B)StartTimeDelayLogjgCard 5 sec. 5 2 0.5 sec.
- e. LPCI Pump (B) Discharge Flow - Lowg > 1100 gpa > 900 gpm
- f. LPCI Pump (C) Discharge Flow - Low > 1100 gpm > 900 gpm w g. Manual Initiation NA NA k
w 2. AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "2" 1 ADS LOGIC "B" AND "F" o
- a. Reactor Vessel Water Level - Low Low Low, -> -145.5 in.* ~> -147.7 in.
Level 1
- b. Drywell Pressure - High 5 1.68 psig 5 1.88 psig
- c. ADS Timer < 105 sec. < 117 sec.
- d. Reactor Vessel Water Level-Low, Level 3 5 8.9 in.* I 8.3 in.
- e. LPCI Pump (B and C) Discharge Pressure-High [125psig. [115psig
- f. ADS Drywell Pressure Bypass Timer s 6.0 min. i 6.5 min.
- g. Manual Inhibit ADS Switch NA NA
- i. Manual Initiation NA NA 2?R
- %8; 89-P,, E f a
,. t. Att:chment U-600848 Page 8 of 23 Description of Change Specification 3/4.3.7.12, Table 3.3.7.12-1, pages 3/4 3-102, 3/4 3-103, and 3/4 3-104.
Add (#) to the Minimum Channels Operable column of Table 3.3.7.12-1, pages 3/4 3-102 and 3/4 3-103. Add note i to the Table Notations on page 3/4 3-104 as follows:
"A channel may be placed in an inoperable status for up to I hour for the purpose of performing surveillances of Specification 3/4.11.2.1 and this Specification."
Justification Sampling system down time and resultant associated monitoring system instrumentation inoperability, due to unavoidable perturbations to the system configuration, is acceptable for small periods of time. The NRC recognizes that performing sampling requirements of CPS-TS 3/4.11.2.1 will affect the system operability requirements of CPS-TS 3/4.3.7.12.
Performance of surveillances of this Specification (4.3.7.12) in accordance with the requirements of Table 4.3.7.12-1 will also result in instrumentation inoperability for small periods of time. Since performance of surveillances is the normal method of determining
" operability" there should be no penalty (i.e., entry into ACTION statement) for their performance. A one hour provision for surveillance performance is well within the ACTION limitations for appropriate systems and Specifications 3.0.3 and 3.0.4 are not applicable as referenced in this Specification.
. This change has been discussed with the NRC Messrs. J. Lee and B.
Siegel.
4
TABLE 3.3.7.12-1 .
b RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 5
INSTRUMENT MINIMUM CHANNELS OPERABLE d APPLICABILITY ACTION e
5
- 1. Station HVAC Exhaust PRM
]
- a. High-Range Noble Gas Activity 1 121 Monitor
- b. Low-Range Noble Gas Activity 1 121 Monitor
- c. Iodine Sampler 1 l d. Particulate Sampler 1 122 i
$ e. Sample Flow-Rate Measuring 1
- 2 f. Effluent System Flow Rate 1 123
, Measuring Device ,
- 2. Standby Gas Treatment System I txhaust PRM
- a. Medium-Range Noble Gas 1 Activity Monitor l
- b. Low-Range Noble Gas 1 l
- Activity Monitor
??R
- c. Deleted - $$E
.84 Sk e
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TABLE 3.3.7.12-1 (Continued) ..
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION z
e MINIMUM g INSTRUMENT CHANNELS OPERABL APPLICABILITY ACTION
- 2. Standby Gas Treatment System Exhaust PRM (Continued) .
Low-Range Iodine Sampler ** 122
- d. 1
- e. Particulate Sampler 1 Sample Flow-Rate Measuring 1 ** 123 f.
Device .
Effluent System Flow-Rate **
- g. 1 123 Measuring Device
{
T 3. Main Condenser Off gas 5
Treatment System Explosive Gas Monitoring System Hydrogen Monitor *** 124
- a. 1
??%
. % 8 ET E
an 0
)
Attschment
., U-600848 Paga 11 of 23 TABLE 3.3.7.12-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATIONS
=ff ACTION ACTION 121 - With the number of channels OPERABLE.less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed for gross noble gas activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 122 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the channel has been declared inoperable, samples are contin-uously collected with auxiliary sampling equipment as required in Table 4.11.2-1.
ACTION 123 - With the number of channels OPERABLE less than required by the 5 Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 124 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser off gas treatment system may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 125 - Deleted ACTION 126 - With the number of channels OPERABLE less than required by the
! Minimum Channels OPERABLE requirement, suspend release of radio-l activity effluents via this pathway.
l cfanaeI may b< Place d 51 d'l I0'Y" 5 lclu5 (c, af k illour f" S /"@S '
of ,auf,w),19 sarveillGtKC5 d f S3eCY54bb'l j 3/ q. it. 2. / a ad His Sp ci Aca (n i .
. CLINTON - UNIT 1 3/4 3-104 I
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. Attcchment U-600848 Page 12 of 23 Description of Change Specification 4.4.3.2.1.a. page 3/4 4-11.
Delete surveillance requirement.
Justification Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," states that the source of reactor coolant leakage should be identifiable to the extent practical. Leakage detection and collection systems should be selected and designed according to Position C.5, such that leakage to the containment building from unidentified sources should be collected, and the flow monitored with an accuracy of I gallon per minute in one hour (gpm/hr.), or better.
In Section 5.2.5.10 of the CPS FSAR, " Regulatory Guide 1.45 Compliance,"
IP commits to comply with Regulatory Guide 1.45 and describes the details of that compliance. In the Clinton Safety Evaluation Report (SER), Section 5.2.5, the NRC finds the Clinton compliance to Regulatory Guide 1.45 acceptable and Item (5) of the SER states, "The sensitivity and response time of the systems . . . for the detection of unidentified leakage are adequate to detect a leakage rate of 1 gpm in less that I hour." The Lenk Detection System will comply with Regulatory Guide 1.45 as currently specified in the FSAR except that the drywell atmospheric particulate and gaseous radioactivity monitoring systems are not capable of measuring a leakage rate of 1 gpm within an hour as required by Position C.5 of Regulatory Guide 1.45. Therefore, the airborne radioactivity monitoring systems will be considered as a secondary detection method, along with the monitoring of pressure and temperature, to detect gross unidentified leakage.
On January 12, 1987 (U-600809), and February 16, 1987 (U-600840), IP submitted letters describing revisions to the Clinton Power Station Final Safety Analysis Report (FSAR). This change and the FSAR revisions have been discussed with the NRC's Messrs. J. Ridgely and B. Siegel.
Attcchment
. U-600848 Pegs 13 of 23 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE.
- b. 5 gpm UNIDENTIFIED LEAKAGE.
- c. 25 gpm IDENTIFIED LEAKAGE (averaged over any 24-hour period).
] d. 0.5 gpm leakage per nominal inch of valve size up to a maximum of 5 gpm
- from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1, at rated reactor pressure.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
a ACTION:
- a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two other closed manual or deactivated automatic valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ,
SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by: i Deleted.
i Monitoring-the-drywell-atmospheric-particulate and gaseous-radle d
- a. 3 activity-et-least-once-per-12 hours;- *'
j
- b. Monitoring the drywell floor and equipment drain sump level and sump flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
- c. Monitoring the drywell air coolers condensate flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and CLINTON - UNIT 1 3/4 4-11
. Attachment U-600848 Page 14 of 23 Description of Change Specification 4.6.1.4.c.2, page 3/4 6-7.
Change the surveillance commensurate to the markup.
i Justification Experience gained in the testing and startup programs indicate that the present Technical Specification is burdensome to manage and implement as written. As an operational enhancement. IP proposes to change this i specification to accommodate the as-built configuration of the system.
The control logic of the outboard blowers is such that both blowers i operate at the same time. Testing the blowers on an individual basis requires that the non-testing blower be physically removed from its
- foundation and a blind flange installed in place of the removed blower i- each time this surveillance test is performed. The proposed change l' allows both blowers to be tested simultaneously and as configured by the system logic and construction. This change is typical of other BWR's and the Standard Technical Specifications (NUREG-0123).
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Attcchment
. U-600848 CONTAINMENT SiSTEMS Page 15 of 23 MSIV LEAVAGE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.4 Two independent MSIV leakage control system (LCS) subsystems shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With one MSIV leakage control system subsystem inoperable, restore the inoper-able subsystem to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.4 Each MSIV leakage control system subsystem shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying:
- 1. Blower OPERABILITY by starting the blowers from the control room and operating the blowers for at least 15 minutes.
- 2. Heater OPERABILITY by demonstrating electrical continuity of the heating element circuitry.
- b. During each COLD SHUTDOWN, if not perforined within the previous 92 days, by cycling each remote, manual and automatic motor operated valve through at least one complete cycle of full travel,
- c. At least once per 18 months by:
- 1. Performance of a functional test which includes simulated actuation of the subsystem throughout its operating sequence, and verifying that each automatic valve actuates to its correct position, the blower (s) start.
- 2. Verifying that Nbloweridevelops at least the required vacuum at l
the rated capacity and each heater unit draws 7.4 to 9.2 amperes per phase.
a) Inboard system, 15" H 2O vacuum at > 100 scfm.
b) Outboard system, 15" 2H O vacuum at > 100'scfm for-each-blo d 2co l CLINTON - UNIT 1 3/4 6-7
k
.. Attrchment
- D-600848
. Page 16 of 23 Description of Change Specification 4.6.2.2, page 3/4'6-15.
. Add the words "or during each refueling outage" as indicated in the markup.
i Justification This change will bring the CPS-TS into agreement with the NRC position 1
as described in SSER-5, page 6-1, paragraph 6.2.1.7. This change has
! been discussed with the NRC's B. Siegel, NRC Clinton Licensing Project Manager. _This change amends the change presented in letter U-600817 1 dated February-4, 1987.
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Attachment U-600848 CONTAINMENT SYSTEMS Page 17 of 23 DRYWELL BYPASS LEAKAGE ,
LIMITING CONDITION FOR OPERATION 3.6.2.2 Orywell bypass leakage shall be less than or equal to 10% of the minimum acceptable A/4 design value of 1.18 ft2 ,
~
APPLICABILITY: When ORYWELL INTEGRITY is required per Specification 3.6.2.1.
1- ACTION:
With the drywell bypass leakage greater than 10% of the minimum acceptable A/4 design value of 1.18 ft ,2restore the drywell bypass leakage to within the limit prior to increasing raactor coolant system temperature above 200'F.
, j SURVEILLANCE REQUIREMENTS 4.6.2.2 The drywell bypass leakage rate test shall be conducted at least once
> I per 18 months e at an initial differential pressure of 3.0 psi and the A/4 shall g i tFe calculated from the measured leakage. One drywell airlock door shall remain open during the drywell leakage test such that each drywell door is leak tested j during at least every other leakage rate test) i U CIf any drywell bypass leakage test fails to meet the specified limit, the schedule for subsequent tests shall be reviewed and approved by the Com-mission. If two consecutive tests fail to meet the limit, a test shall be performed at least every 9 months until two consecutive tests meet the
< limit, at which time the 18 month test schedule may be resumed. .
! m n. _- ..,.1--- .,
- f3;;;;;; 4,0,; ; ; ,;; ;ppli;;ti;,
- m m ,,, m a m g y i .
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l CLINTON - UNIT 1 3/4 6-15 l
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. Attcchment U-600848 Page 18 of 23 Description of Change Specification 3/4.9.12, page 3/4.9-19 Add the information per the markup.
Justification Illinois Power Company letter U-600785 dated January 8, 1987, submitted a change to this Specification. After NRC's review, and in accordance with discussions held with the NRC's Messrs. B. Siegel and J. Ridgely,
, additional changes to Specification 4.9.12.1 are proposed to ensure sufficient precautions are taken to prevent personnel from entering into areas adjacent to where irradiated fuel is being handled with the Inclined Fuel' Transfer System (IFTS). This action is considered
- necessary because, unlike similar BWR's, Clinton does not have visible warning lights which would warn individuals of IFTS operation.
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Attcchment
.. U-600848 REFUELING 0PERATIONS Page 19 of 23 3/4.9.12 INCLINED FUEL TRANSFER SYSTEM LIMITING CONDITION FOR OPERATION -
3.9.12 The inclined fuel transfer system (IFTS) may be in operation provided that:
- a. The access doors
- of all rooms through which the transfer system penetrates are closed and locked.
b.
All access doorfinterlocks are OPERABLE. l
- c. The blocking valve located in the fuel building IFTS hydraulic power unit is 0PERA8LE.**
- d. At least one IFTS carriage position indicator is OPERA 8LE at each carriage position and at least one liquid level sensor is OPERA 8LE.**
- e. Any keylock switch that provides IFTS access control-transfer system lock-out is 0PERABLE.
, APPLICA8ILITY: When the IFTS containment blank flange is removed.
ACTION:
With the requirements of the above specification not satisfied, suspend IFTS operation with the IFTS at either termTnal point. The provisions of Specifi-cation 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS @d d/ /td5/ one per/2 hours t .
4.9.12.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to the startup he F hat no personnel are in areas immediately adjacent to the IFTS and that all access doors to rooms through which the IFTS penetrates are closed and locked.
4.9.12.2 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the operation of IFTS and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify that; a.
AllaccessdoorfinterlocksareOPERA8LE. l
- b. The blockin OPERA 8LE.**g valve in the Fuel Building IFTS hydraulic power unit is
- c. At least one IFTS carriage position indicator is 0PERA8LE at each carriage position and at least one liquid level indicator is OPERA 8LE.**
" Includes removtble shields.
- The blocking vdive in the fuel building IFTS hydraulic power unit and the liquid level indicator are not required to be OPERA 8LE for the purposes of these specifications until after fuel loading, but before exceeding 5% of RATED THERMAL POWER or before removal of the reactor pressure vessel head after the initial criticality.
CLINTON - UNIT 1 3/4 9 19
U-bc0 7FD Att:chment U-600848 -
Page 20 of 23 REFUELING OPERATICKS , ;-;
3/4.9.12 INCLINED FUEL TRANSFER SYSTEM . .
- {
.5 LIMITING CONDITION FOR 0PERATICN. t l .
3.9.12 The inclined fuel transfer system (IFTS) may be in operation pr: viced that: .-
- a. The access doors
- of all rooms through which the transf.er system penetrates are closed and locked. .
- b. All access door interlocks are OPERABLE. -
- c. The biceking valve loc'ated in the fuel building IFTS hydraulic pcwer unit is 0PEMBLE.'"
- d. At least one IFTS carriage position indicator is OPEMELE at each carriage position and at least ene liquid level sens' ro is CPEMBLE.'"
- e. Any keylock switch.that provides IFTS access control-transfer system lock-
-, out is OPE MBLE.
. APPLICABILITY: When the IFT5 containe.ent blank flange is removed.
i ACTION:
With the requirements of the above specification not satisfied, sus;end IFT5 operation with the IFT5 at either termTnal point. The provisions of Specifi-cation 3.0.3 are not applicable.
SURVEILLANCE REOUIREu!NTS ,
4.9.12.1 Within I hour prior to the startup of the IFTS, verify that no personnel are in areas ircediately adjacent to the IFi$ and that all access s doors to rooms through which the IFTS penetrates are closed and locked.
4.9.12.2 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the operation of IFT5 and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter, verify thatf* '79 3
~~~?g,i'
- a. All access d;or interlocks are OPEMBLE. t~
- b. The blocking valve in the Fuel Building IFT3 hydraulic c:wer unit is
_ O P E RAB LE. "" -
( ---
.sr*' t least one IFT5 carriage p:sition indicat:r is CP!RAEL! at en:n car-iage j' position and at least one liquic level incicator is OE!!AILI."
"Incluces remova01e shields.
'"The blocking valve in the fuel b.silding lFis nycrawlic =cwer unit anc the liquid level incicator are not recuirec to be CP!PABL! s f r tne cur;:ses of
.these s:eciff cations until after fuel leading, but sf:re ex:eecing M of RATED TFIRwAL MwER or tef:re re eval of the rea::ce ;ressee sessel neac after tne initial criticality.
CL:NTON = UN:7 1 3/4 9 *.9
M-kco785 Attcchment -
U-600848 Page 21 of 23 .
REFUELING CPERATIONS . . .
.' 3 i
- INCLINED FUEL TRANSFER SYSTEM . .
5 '*
5URVEILLANCE REQUIREMENTS [ Continued) ,
s 4.9.12.2 (Continued) ,% y w
'.-C
. v -
, hi-dThe keylock switches which provide' IFTS access or control-transfer system W
lockout are OPERABLE.
I " ~
h ,9,12.'5 um h 4 hows Pd oc 4o 4ke cMea W of s o
g -CFT5 and cd lea.si ence Pec 7 dap -K ercaf4<r, vtci G3 Mat p 3//1-20 +'.' 9. o. 2 o-, b N s 7A .
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- . Att:chment U-600848 Page 22 of 23 Description of Change BASES 3/4.4.3, page B 3/4 4-3 Revise paragraph 3/4.3.1 as shown in the markup.
Justification The purpose of this revision is to update the BASES in accordance with the described revision to the FSAR as contained in letter U-600840 from F. A. Spangenberg to Dr. W. R. Butler (NRC) dated February 16, 1987.
This change has been discussed with the NRC's Messrs. J. Ridgely and B. I Siegel and is consistent with BASES of other operating BWR's. Please l see the change and justification to page 3/4 4-11 (page 12 of 23 of this ;
Attachment) for additional details.
l
.- , Attcchment U-600848 page 23 of 23 REac7OR C00LaNT SYSTEM LASES .
3/.1.4.1 RECIRCULATION SYSTEM (Continued) the recirculation flow control failures on increasing and decreasing flow are ,
j presented in Sections 15.3 and 15.4 of the FSAR respectively.
The required surveillance interval is adequate to ensure that the flow control I valves remain OPERABLE and not so frequent as to cause excessive wear on the i system components.
i 3/4.4.2 SAFETY / RELIEF VALVES 4
The safety valve function of the safety / relief valves (SRV) operate to prevent the reactor coolant system from bein<1 pressurized above the Safety Limit of 1375 psig in accordance with the ASMB Code. A total of 11 OPERABLE safety- ,
relief valves is required to limit reactor pressure to within ASME III allowable l values for the worst case upset transient. Any combination of 5 SRVs operating 1 l
i in the relief mode and 6 SRVs operating in the safety mode is acceptable.
1 i
, Demonstration of the safety relief valve lift settings will occur only during <
shutdown and will be performed in accordance with the provisions of Specifica-l tion 4.0.5.
[ I The,10w low set system ensures that safety /reifef valve discharges are minimized I for a second opening of these valves, following any overpressure transient.
i' l This is achieved by automatically lowering the closing setpoint of 5 valvesInand lowering the opening setpoint of 2 valves following the initial opening.
) this way, the frequency and magnitude of the containment blowdown duty cycle is T substantially reduced. Sufficient redundancy is provided for the low-low set system such that failure of any one valve to open or close at its reduced set-point does not violate the design basis, f l .
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3/4.4.3 REACTOR COOL ANT SYSTEM LEAGGE Med M* Ioldd l 3/4.4.3.1 LEA UGE DETECf!ON SYSTE f I J
The RCS leakage detecti n systems required by this specification are provided These
' to monitor and det et ea age from the reactor coolant pressure boundary.
..... ..,. ....~ . ~ .,
Jof Regulatory Guide detection systems - -. m...,.
i 45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May ,
i 2 nece*wirfort-w wA*-renmeer du%ww-* F-h u s 2-m r e s % ?
- , e #*/*^4# 8M*/**/-AW'-3**'dary 488V 3/4.4.3.2 OPERATIONAL LEAUGJ Desube9N482 e r I The allowable leakage rates from the reactor coolant system have beenThe based on f
i the predicted and experimentally observed behavior o i capability of the instrumentation for determining system
! sidered.
i what greater than that specified for UNIDENTIFIED l 8 3/4 4-3
]
CLIN 7CN