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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217J4331999-10-15015 October 1999 Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station ML20217A9881999-10-0101 October 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20217A7361999-10-0101 October 1999 Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs ML20217J1251999-09-30030 September 1999 Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC ML20217J1421999-09-30030 September 1999 Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC ML20212G6751999-09-22022 September 1999 Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability ML20217H3421999-09-17017 September 1999 Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed ML20211Q2671999-09-0808 September 1999 Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000 U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 ML20211D2201999-08-23023 August 1999 Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired ML20211A8931999-08-19019 August 1999 Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 ML20210U3771999-08-12012 August 1999 Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 ML20210A4401999-07-16016 July 1999 Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations ML20209G7671999-07-12012 July 1999 Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed ML20209D5691999-07-0707 July 1999 Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20196J9651999-07-0202 July 1999 Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements ML20196J7131999-06-30030 June 1999 Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1 U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology ML20196A3471999-06-16016 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999 Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p) ML20217C0871999-10-11011 October 1999 Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999 Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999 Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999 Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999 Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999 Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl ML20212G6981999-09-20020 September 1999 Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability 05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999 Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999 Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed 05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999 Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999 Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7 U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999 Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage ML20211B0871999-08-20020 August 1999 Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723 U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999 Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999 Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813 U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999 Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729 U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999 Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809 ML20210N2961999-08-0909 August 1999 Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999 Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55 U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999 Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS ML20210J0541999-07-30030 July 1999 Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999 Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999 Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131 U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999 Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71 U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999 Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790 U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999 Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999 Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999 Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999 Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999 Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology 05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed 05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999 Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors ML20209G7731999-05-27027 May 1999 Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999 Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999 Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5 U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999 Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999 Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999 Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999 Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999 Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999 Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999 Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999 Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f) U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999 Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3) 05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999 Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999 Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999 Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired 1999-09-22
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L6571990-09-19019 September 1990 Advises That Dp Hall No Longer Associated W/Facility Since Dec 1989.Mail Should Be Addressed to Js Perry JSP-739-90, Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump1990-09-12012 September 1990 Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump U-601729, Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn1990-08-27027 August 1990 Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn JSP-676-90, Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event1990-08-23023 August 1990 Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event U-601723, Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.711990-08-16016 August 1990 Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.71 U-601722, Forwards Reissued NPDES Permit IL00369191990-08-10010 August 1990 Forwards Reissued NPDES Permit IL0036919 U-601721, Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators1990-08-0808 August 1990 Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators U-601716, Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))1990-08-0303 August 1990 Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2)) U-601715, Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly1990-08-0202 August 1990 Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly U-601708, Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 19891990-07-19019 July 1990 Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 1989 U-601702, Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990 Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20044A3001990-06-22022 June 1990 Forwards Update to 890817 Response to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Unisolable Piping Connected to RCS Identified & Evaluated to Determine Which Piping Could Be Subj to Stratified Flow Phenomena ML20044A4601990-06-22022 June 1990 Provides Followup to 900622 Request for Waiver of Compliance Re Tech Spec Limiting Condition for Operation Concerning Standby Emergency Diesel Generator 1B.Rev to Attachment 1 of Original Request for Waiver Encl ML20043H5021990-06-19019 June 1990 Requests Changes to License NPF-62,correcting Typos, Refs to Fsar,Testing to Be Done During Initial Plant Startup & Incorporating Revised Operating Power/Flow Map for Two Reactor Recirculation Loop Operation ML20043G8221990-06-0707 June 1990 Provides Update to Util Response to Item 1 of Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. ML20043F0591990-06-0606 June 1990 Forwards Endorsements 44-50 to Nelia Policy NF-261 & 25-31 to Maelu Policy MF-121 & 10 & 11 to Maelu Policy N-85 & M-85,respectively ML20043D0531990-05-31031 May 1990 Forwards 1989 Annual Rept for Illinois Power Co & Soyland Power Cooperative,Inc ML20043C7501990-05-25025 May 1990 Forwards Rev 20 to Illinois Power Nuclear Program QA Manual. Rev Evaluated by Util as Not Reducing Quality Program Commitments ML20043B4891990-05-21021 May 1990 Informs NRC of Plant Initiatives for 1990 to Improve Corrective Action Program Effectiveness,In Response to SALP Rept & Violations Noted in Insp Rept 50-461/89-32. Centralized Commitment Tracking Sys Upgraded ML20043B1141990-05-17017 May 1990 Suppls 900330 Response to Station Blackout Rule.Calculation of Heatup of Main Control Room Due to Loss of Ventilation Following Station Blackout Revised to Properly Account for Heat Sinks & Credit Existing Masonry Walls ML20043D9901990-05-14014 May 1990 Responds to NRC 900413 Ltr Re Violations Noted in Insp Rept 50-461/90-02.Corrective Actions:Safety Evaluation Prepared & Reviewed for Level Instrumentation & Annunciators Identified in Updated SAR ML20043A9811990-05-14014 May 1990 Notifies That Wc Metzner Resigned from Position of Licensed Operator W/Util,Effective 900430 ML20042E6181990-04-13013 April 1990 Updates 890406 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Condition Rept Initiated to Address Issue to Drain Instrument Air Filter Regulators ML20012E8991990-03-27027 March 1990 Forwards Rev 9C to Physical Security Plan.Rev Does Not Decrease Effectiveness of Plan.Rev Withheld (Ref 10CFR73.21) ML20012D9451990-03-20020 March 1990 Informs of Current Activities Re Restoration of Shutdown Svc Water (SX) Sys to Operability Following Cleaning of Div I HX Per Generic Ltr 89-13.SX Sys to Be Restored by Returning Sys Flows to Design Values ML20012D9641990-03-19019 March 1990 Lists Present Levels of Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w)(2) ML20012D9901990-03-19019 March 1990 Responds to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-461/89-38.Corrective Actions:Maint Supervision Added Critical Points to Existing Maint Work Requests & Preventive Maint Activities & Training Program Updated ML20012D4321990-03-16016 March 1990 Responds to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Detailed Analytical Review & Proposed Schedule for Implementing Required Actions Scheduled to Be Completed by 900625 ML20012A2771990-02-28028 February 1990 Forwards Final Response to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded Case Circuit Breakers. Actions Taken by Util Have Established That All safety-related Circuits Remaining in Stock Can Be Verifiably Traced to Mfg ML20012C2511990-02-23023 February 1990 Responds to Ninth SALP Rept 50-461/89-01 for Sept 1988 - Oct 1989.Rept Concluded That Overall Performance Satisfactory & Identified Strengths in Areas of Emergency Preparedness U-601611, Notifies That Gd Setser Resigned Position W/Util,Effective 9002131990-02-20020 February 1990 Notifies That Gd Setser Resigned Position W/Util,Effective 900213 ML20011F6501990-02-12012 February 1990 Responds to NRC 900112 Ltr Re Violations Noted in Insp Rept 50-461/89-37.Corrective Actions:Radiation Protection Technicians Provided W/Method for Identifying Radiation Work Permits Which Change Radiological Conditions ML20006C6721990-02-0505 February 1990 Responds to NRC 891207 Ltr Re Violations Noted in Insp Rept 50-461/89-35.Corrective Actions:Emergency Planning Bulletin Issued to All Emergency Response Organization Members Emphasizing Importance of Attending Required Training ML20006D1951990-01-30030 January 1990 Responds to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Util Intends to Discontinue Sending Ack Upon Receipt of Vendor Manual Matls ML20006A8291990-01-23023 January 1990 Forwards Rev 3 to Inservice Exam Plan. Changes to Text Described.Approval of Changes by 900601 to Allow Time to Plan Refueling Outage Activities Re Inservice Exam Program Requested ML20005H2711990-01-12012 January 1990 Advises That Licensee Will Remove Terminal Blocks for Control Circuits within 100% Relative Humidity Harsh Environ at Plant by End of Second Refueling Outage Currently Scheduled to Begin in Sept 1990 ML20006A7121990-01-10010 January 1990 Forwards Revised Pages to 1987 Radiological Environ Monitoring Rept ML20005F0001990-01-0505 January 1990 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Util Revised Plant Operating Procedures for Hpcs,Lpcs & RHR Pumps & Vibration Monitoring Program Expanded to Include ECCS Pumps at Plant ML20006A7921989-12-29029 December 1989 Responds to 891129 Ltr Which Forwarded Insp Rept 50-461/89-31,requesting Identification of Actions Underway to Ensure That Falsification of Interim Security Screening Records Would Be Detected in Timely Manner in Future U-601573, Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently1989-12-29029 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently ML20005E0891989-12-27027 December 1989 Advises That Revised Fitness for Duty Program Will Meet 10CFR26 Requirements,Effective 900103.Util Intends to Test for Substances Listed at Indicated cut-off Levels ML20006C2961989-12-21021 December 1989 Responds to NRC 891121 Ltr Re Violations Noted in Insp Rept 50-461/89-32.Corrective Actions:Review Performed to Identify Surveillances Which Require Lifting of Leads in Main Control Room ML20005D9521989-12-15015 December 1989 Forwards Monthly Operating Rept for Nov 1989 for Clinton Power Station Unit 1 & Corrections to Oct 1989 Rept ML20005E7781989-12-12012 December 1989 Advises That False Alarm Criteria Will Be Implemented by 900131,per Insp Rept 50-461/89-31.Util Established New Criterion of 100 False Alarms for Security Sys in 24 H Period ML20011D1741989-12-0707 December 1989 Informs of Changes Made to Util Fitness for Duty Program Procedure.Change Specifies That Supervisor - Medical Programs,Assistant Director - Labor Relations or Manager - Nuclear Planning & Support Will Generate Computer List ML19332F0071989-11-30030 November 1989 Responds to Violations Noted in Insp Rept 50-461/89-29. Corrective Actions:Preventive Maint for Ph Monitor & Liquid & Gaseous Gamma Monitors Added to Appropriate Tracking Programs ML19332E9431989-11-29029 November 1989 Forwards Executed Amends 4 & 5 to Indemnity Agreement B-91, Reflecting Change in Ownership of License,Effective 890327 ML19332D5031989-11-27027 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Results of Util Review & Reporting of Status of Implementation of USIs Encl ML19332D0291989-11-22022 November 1989 Informs That Effective 891201,JS Perry Will Assume Responsibility for Mgt of Nuclear Program at Util ML19332D0431989-11-22022 November 1989 Informs NRC of Change in Schedule for Providing Info Re Environ Qualification Testing of Terminal Blocks for Control Circuits of Conax Electrical Penetrations.Wyle Labs Test Results & Util Review of Results Will Be Sent by 900112 1990-09-19
[Table view] |
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E t '; U-0832 r #, L30-65 (04-16)-L 1A.120 ILLIN018 POWER COMPANY IP . CLINToN PonEP STATION. P.o. BOX 678. CLINToN. ILLINOIS 61727 tApril 16, 1985 Docket No. 50-461 h .Direc'ort of Nuclear Reactor Regulation Attention: Mr..A. Schwencer, Chief
-Licensing Branch No. 2
' Division of Licensing-US Nuclear Regulatory Commission
- Washington, DC 20555.'
$ i
Subject:
.Clinton Power Station Unit I l
- ' Elimination of Arbitrary Intermediate Pipe Breaks t
Dear .Mr. Schwencer:
The purpose of this letter is to request exemption from current Nuclear Regulatory Commission ~(NRC) piping design criteria with respect
.to' arbitrary intermediate pipe breaks. These'are breaks which, based on
. stress. analysis,-are below the stress limits and/or the cumulative usage factors specified in_the curren'd NRC criteria, but are. selected to provide'a minimum of two breaks between terminal ends.- Elimination of arbitrary-intermediate pipe breaks at Clinton Power Station (CPS) results in design and construction benefits due to the potential elimination of the' associated pipe whip restraints. Also, operational benefits arise from the decreased number of pipe whip restraints to be inspected and maintained for 40 years.
Attached is a detailed explanation and justification for the elimination of arbitrary intermediate _ pipe breaks at CPS. The following information is presented in it:
-1)- Current Break Selection Criteria
- 2) Industry Experience
- 3) Benefits.
4)- Al' ternate Pipe Break' Criteria
- 5) . Listing lof the Eliminated Pipe, Breaks s
6)' l Additional Technical: justification
.Since the design'and-construction of-pipe whip restraints Jassociated with arbitrary intermediate pipe breaks is nearly. complete,
- Illinois Power Company,(IPC):does not. anticipate removing any of the installed restraints at this time. IPC is requesting the approval of' alternative. pipe. break criteria to provide.the flexibility to remove or not to-shim-: restraints in the future, if deemed necessary.
J 8504100416 850416 > d T:
{DR ADOCK 05000461 PDR ii - , 800l u
L. ]
. C . . . .* .,. U-0832' L30-85(04-16)-L 1A.120 IPC requests NRC approval for the application of alternative pipe
. break criteria as stated in section Sil and 5.2 of the attachment which would; eliminate the need to postulate' arbitrary intermediate pipe.
. breaks. Application'of the alternative pipe break criteria vill not falter IPC's ccamitment to quality in the design of safety related
' structures, systems, and components. The quality assurance program will i continue.to-ensure that safety related attuctures, systems and LcomponentsJare designed, fabricated, erected and tested to the quality.
standards appropriate with the safety. function to be performed.
i Dae~to'the mid-May' scheduling of hot op'erational testing at CPS,
-immediate attention by the NRC-'is requested so\that IPC can realize maximum benefits afforded by this proposed change to the pipe break criteria. A favorable response is requested by May 9,.1985.
Sincerely yours,
/
y, no e N F. A. Sf angefterg Director - Nuclear L.Lcensing and configuration 4 Nuclear. Station Engineering 4
Attachment
{ JDT/ lab I' cc: B. L. Siegel,' ERC Clinton Licensing Project Manager NRC Resident Office
' Illinois Departmentaof Nuclear Safety
~ Regional Administrator, Region III, USNRC s
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.CLINTON POWER STATION UNIT 1 ARBITRARY INTERMEDIATE PIPE BREAKS 1.0 Introduction
.The Fuclear[ Regulatory Commission (NRC) staff and industry discussions with the Advisory Committee on Reactor Safeguards
'(ACRS) have indicated general agreement with the elimination of the arbitrary _ intermediate breaks. Additionally, the NUREG-1061, LVolumo'3,' published in November 1984 recommends that the current NRC criteria be revised to eliminate the requirements for
. mechanical pipe rupture-protection against arbitrary intermediate breaks.: Elimination of arbitrary intermediate. breaks results in l_ design benef'.ts due to the potential elimination of.the associated
. pipe whip;rs.straints and related provisions currently incorporated
,i Ein the plart design to mitigate 'the effects of 'such pipe breaks.
- In addition,. operational-advantages also ensue from the decreased' g . numbers of' pipe whip restraints to be inspected.and maintained for i
- f40 years.;
-2.0. Break Selection Criteria
[ The break'aelection criteria-currently employed by Illinois Power
! - Company (I?C) for the- Clinton Power Station Unit 1 (CPS) is based f upon NRC Branch Technical Position MEB 3-1 as presented in the
- " Standards Review Plan, Section 3.6.2. This position, requires-that n'
pipe breaks.be postulated at anchored' terminal ends and at.
intermediate locations where, depending on the pipe class, stresses or. cumulative usage factors-exceed specified limits. If two intermediate locations cannot be determined based'on the above
.because the stresses and cumulative usage factors are below the ,
-specified limits, the two highest' stress locations are selected.
3.0 Industry-Experience
- l. . IPC c'oncurs with other nuclear utilities in the belief that current
[
l'
' knowledge and experience' supports the conclusion that designing for arbitrary intermediate breaks uis not justified.and that this ,
y _ requirement should be deleted. iThie conclusion:is supported by. ,
! , extensive operating-experiencecin over 80 operating U.S. plants and-j ca' number of similar plants overseas in which no_ piping failures
. have been known - to occur: that 'would suggest :the need ' to design l Lprotective features to mitigate the dynamic effects of arbitrary j~ -intermediate breaks. Arbitrary' intermediate breaks are~often.
t- :. postulated'atLlocations where maximum pipe _ stresses are well'below
- .the ASME Codetallowables.and'within a few-percent of theistress-levels at' other points 1La th'e same piping s' y stem. Mitigating the
~
1 effects =fram such breaks with pipe _ whip restraints results'in fcomplicated protective ~ features being provided atfarbitrary b'reak'
-locations but.does lictie to enhance overall plant safety..
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4.0 Benefits-Elimination of the arbitrary intermediate break locations results in the potential elimination of the associated pipe whip restraints e.nd other structural provisions to mitigate the consequences of these bre'aks. Significant operational benefits are also realized F over the 40-year life of each plant. As identified in NUREG/'
4 CR-2136,:these benefits accrue in the areas of plant reliability and reduce. exposure of plant personnel to radiation during in-service inspection which is complicated by the presence of pipe
-whip restraints.
4.1 Access Access during plant operation for maintenance and inservice inspection is: improved due.to decreased congestion from these '
restraints.and their supporting structural steel. Also, fewer r restraints must be removed to gain access for weld inspec-
' tions. In addition to the decrease in maintenance effort, a corresponding reduction in man-rem exposure can be realized from fewer manhours spent in radiation areas, per ALARA.
- 4.2 Decrease in Heat Loss i By design, whip restraints fit closely around the high energy
. piping with gaps typicully being on'the order of an inch. t These restraints and their. supporting steel increase the heat loss to the surrounding environment significantly. Also, because thermal movement of the piping system during start-up and shutdown could deform the piping insulation against the fixed whip restraint, che insulation must be cut back in these areas, creating convection gaps. adjacent to the restraint, which, also increased heat loss to the environment'. This is a contributor to the tendency of many containments to operate at
-temperatures near technical specification limits. The ,
. elimination of whip reatraints associated with arbitrary :
intermediate breaks would' reduce heat loss to the containment and reduce containment temperature during power = operation.
4.3 Unanticipated Thermal Expansion Stress Pipe rupture protection devices are designed not to restrict pipe-free-thermal ~ expansion _however should these_ devices come into contact with the pipe.itself, unanticipated stresses due to restraint'of thermal expansion can be introduced into the piping system. As brought:out in ACRS hearings,sthe. potential
~
for'this happening is greaterfthan:the potential for mechanistic failure at an arbitrary break point.- This results
~
-in'a decrease in the;overall reliability.of the pipe system.
'To prevent this, an additional as-built verification step'is .s involved inLthe design process for each installed pipe whip restraint that requires complex measurements both in the cold and hot position of the pipe. _ The elimination of arbitrary Dintermediate breaks would significantly reduce the effort 2
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-_ involved in protecting the piping from the effects of unanticipated thermal expansion stresses at the associated whip restraints.
h 5.0 ' Alternative Pipe Break Criteria IPC proposes the following alternative pipe break criteria.
5.1- ASMZ Section III Piping Inside Containment ,
Piping systems shall be designed to accommodate pipe breaks at anchored terminal ends and locations where the
~
stress or usage factor criteria of MEB 3-1 are exceeded.
. -No arbitrary-intermediate pipe breaks wil1~be postulated where the stress.and/or usage factor criteria are not exceeded.
I
- For: breaks that must-be taken, the design will accommodate pipe whip, . jet impingement, -and compartment pressurization resulting from mechanistic treatment of the break. Current acceptable methods for limiting break opening, moderate and low energy exclusions, limited
. duration operation, etc. may still be applied..
l For plant flooding evaluations,' environmental qualification of equipment, and structural design of
- equipment in' areas traversed by high energy piping i systems,~ pipe breaks will continue to be postulated ~1n accordance with the 'present project criteria,- i.e. , in
~
each area traversed by the high energy piping system,
, non-mechanistic breaks _are postulated at the location
[~ that results in the-most severe environmental con' sequences. .Therefore. elimination of.the' arbitrary intermediate pipa breaks does not impact environmental
- .qualifiqation of equipment nor' plant structural design.
- 5.2 ASME Section III and Seismically Designed Non-Section III~
' Piping Outside Containment Piping systems shall'be designed to accommodate pipe breaks at anchored terminal ends and locations where the
~
stress criteria of MEB-3-1 is r.xceeded. No arbitrary intermediate pipe' breaks will be- postulated when the ~
stress criterion is not exceaded.
!~
For breaks thatimust be taken, the_ design will-accommodate pipe whip and jet impingement effects
- resulting from mechanistic treatment of.the break.
- -Compartment pressurization and flooding effects from breaks postulated.in accordante with MEB 3-1 will be
,' . accommodated in~the design.. Current acceptable methods I for limiting break' opening,Lmoderate and low energy exclusions,-limited duration operation, etc.'may still be
. _ applied.
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For plant flooding evaluations, environmental ,
qualification of equipment, and structural design of
- - equipment.in. areas traversed by high energy piping i' systems, pipe-breaks-will continue to be postulated in
. accordance with the present project criteria, i.e., in E . each area-traversed by the high energy piping system,-
non-mechanistic breaks are postulated-at the location
, that results-in the most severe environmental
- consequences. Therefore, elimination of the arbitrary intermediate pipe breaks does not impact the
' environmental qualification of equipment nor plant structural: design.
-6.0. Eliminated Pipe Breaks
' Appendix A. lists by subsystem Class 1 large bore intermediate pipe-
- 1breaks which may be eliminated from the design because the stress and usage factor limits have not been exceeded. ;After approval of this submittal by th9 NRC, the FS_AR will be revised to show which pipe whip restraines are not-required. A4 total of approximately 33
. breaks-sre to be eliminated.
. Appendix B lists the ASME Class 1, 2, and 3 small bore piping
' intermediate break locations that are to be eliminated. A total of approximately 12 breaks are~to be. eliminated.
j' The application of the proposed alternative pipe break criteria will result.in the deletion of approximately 45 break' locations and the potential deletion of 37 pipe whip. restraints. However, it should be noted that piping and system design is an iterative i process and that postulated break locations could potentially move
- .as the system design and analysis of structures and piping develops over the course
- of the design and construction. process.f Owing to j tha iterative nature of!the design process and its:potentialifor affecting postulated break-locations, changes affecting high' energy L , systems are continuously monitored and' evaluated to determine'the impact on. break location. ,IPC proposes to apply'these alternative criteria'to any potential break locations in the systems identified ~
.herein,'provided the stresses at those' locations areLbelow'the break selection threshold, and the operational concerns'in
~
~
l Attachments D through'F are adequately' addressed. .This flexibility-is necessary to minimize future requests for break' elimination as '
the location' of the intermediate break points change during the ,
evolution'of the plant' design.
q 6.1 Elimination of Breaks Not Yet Identified' 1 4
iThe existing guidelines in MEB 3-1 of'the SRP (NUREG-0800) I
- Revision 1 will be metifor1 hose t piping systems, or' portions l thereof, which'are not included
- in this submittel. -If.other ;
- piping subsystems included in the systems: identified in Table- '
- -D-1, but not specifically1 identified in this submittal, subse-quently qualify for the conditions described herein, the ,
I implementation of the proposed elimination of the arbitrary l L
1
~ 4l
,at
'i n'tet-ediate break criteria may be used. If this criteria is to be applied to additional. systems not included in Table D-1, those systems will be appropriately identified to the staff. ,
7.0 Additional Technical Justification
- The following appendices provide additional technical information to justify this request. Specific NRC concerns are addressed in 10 Appendices C through G as follows:-
- 1. Technical justification for elimination Appendix C of arbitrary intermediate pipe breaks
_ 2. Provisions for minimizing intergranular Appendix D stress corrosion cracking in high energy lines
- 13. Provisions for minimizing the. effects Appendix E of thermal and vibration induced .
. piping fatigue
- 4. Provisions for minimizing water / steam Appendix-F hammer effects 5.- - Provisions for minimizing local stresses Appendix G from welded attachments 8.0 Conclusion IPC has reviewed the basis for the postulation of intermediato pipe breaks on designated high energy lines and has compared the design stresses and usage factors with the SRP MEB 3-1 Guidelines. On the
' basis'of ASME Code calculations, there is no technical' justification for the postulation of arbitrary intermediate pipe breaks. The probability of pipe rupture at the values of stress and usage factors assignable to these intermediate pipe' breaks is extremely remote, subsequently this' relief should..be' granted.
Since the design.and. construction of pipe whip restraints associated with arbitrary intermediate pipe breaks is nearly
- complete,; Illinois Power-Company _(IPC)'does not anticipate removing any of the installed restraints at this time. 'IPC is requesting
.the approval-of alternative. pipe break criteria to provide the ~
. flexibility: to remove or not to' shim restraints in the future, if
' deemed necessary.
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APPENDIX A
- j- Summary of Class l'Large Bore Piping Intermediate. Break and Pipe Whip Restraint Reductions ,
Potential
' Pipe Whip Breaks /- Restraints /.
4 Intermediate Break ID Restraint'ID System Subsystem Break Locations Eliminated Eliminated
-Reactor RR Loop A - Discharge piping branch' 8/RD6 8/R356B R357B' c Recirculation RR Loop B connection points to RD7 the ring-header. RD8 R358B RD9 R359B (Loop A (Loop A numbers similar to identical) Loop B)
Main' Steam MS-Line A - Elbow butt welds on 3/MS-C57 4/MS-R24 50' elbows prior to MS-C58 'MS-R25 containment MS-C68 MS-R26 Elbow butt weld at top MS-R27 of riser from RPV.
MS-Line B .- Isolation valve guide 2/MS-Cl 4/MS-R2 locations. MS-C19 MS-R4
- ' Elbow butt weld at top MS-R5 of riser from RPV. MS-R6 i
~
.MS-Line C - Isolation valve guide 2/MS-C35 4/MS-R16 locations. MS-C55 MS-R18 Elbow butt welds at top MS-R19 of riser from RPV . MS-R20
+
.,i A-1
I.
9' APPENDIX A -
a_ ,
- Summary of Class 1 Large Bore Piping Intermediate Break and Pipe.-Whip Restraint Reductions- *
(continued)
' Potential ~-
Pipe Whip- ,
Breaks / Restraints /. '
Intermediate Break ID: Restraint ID~
' System Subsystem Break' Locations . Eliminated- ' Eliminated Main Steam MS-Line D Isolation valve' guide 2/MS-C21 4/MS-R10
- . locations. MS-C33 MS-R11
, - Elbow butt veld at top MS-R12 of riser from RPV. MS-R13
.High Pressure HP-01 -
Butt veld at check valve 2/HP-C6' 3/HP-R3 -
Core Spray prior to drywell wall. HP-C8- HP-R4 elbow butt weld at bottom of riser from RPV. HP-R4A
. - Elbow tutt weld at top of' riser from RPV.
Low Pressure LP-01 -. Butt welds at check valve 2/LP-CIA 4/LP-R1 core Spray and gate valve prior to LP-C8 LP-R2A-drywell wall. LP-R3
, Elbow butt welds at LP-R4A -i l
bottom.and-top of riser
, from RPV.
t Residual Heat RH-01 - Butt weld at check valve 3/RH-C1 2/RH-R2 '
l Removal prior to drywell. wall. RH-C8 RH-R3 Butt weld at gate valve RH-C9 '
prior to drywell wall.
- Elbow butt. welds at top ;
of riser from RPV.
]
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- 7. _ _ . - . ..
~7/!
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' - r-'~1 APPENDIX JL .
Summary of Class 1 Large Bore" Piping"
. ~. Intermediate Break andL. Pipe: Whip Restraint-Reductions (continued)-
Potential Pipe Whip .
1 Breaks / . Restraints /-
Intermediate ' Break ID. Restraint ID System- : Subsystem ~ Break Locations Eliminated Eliminated eResidual Heat ~ RH-O'3 -
Butt weld at check' valve 3/RH-C20 2/RH-R9- it Removal prior to drywell~ wall. RH-C21. 'RH-RIO
--Elbow butt welds at RH-C25 bottom-of riser from RPV.
. Elbow-butt weld-at' top. I of riser from RPV.
~
, RH-05 - Lutt' weld at check valve 2/RH-C15 -
prior to drywell wall. .RH-C17
- Butt weld at gate valve .r prior.to drywell wall.
- Elbow butt weld at top of risersfrom RPV.
'RH-34 - Butt. welds at first-~and 1/RH-C32 -
second gate valves from '
the 20" Recire. header.
Reactor' Core RI-01: - ElbowLbutt welds at 3/RH-C5 2/RI-R4
-Isolation bottom ofl: riser f rom 24" RI-C6. RI-R5 Cooling- MSz header. RI-C5A :
- Butt veld at 45* elbow prior to drywell wall. ,
TOTALS 33 37 ;
i A-3
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r- -- - - - - - - - - - - - - = - - - - - - - - ~ ~ ~
APPENDIX B- '
~. ,
Summary of Class 1, 2, and13-Small Bore. Piping-Intermediate Break-Reductions ,
Potential No..of -Pipe. Whip
' Intermediate Breaks Restraints System Subsystem Break Locations ID EliminatedJ Eliminat'ed.
' Standby. Liquid SC-07 SC-C4- -3 0
' Control. .SC-C5 SC-C6 Reactor. Water RT-02 :RT-C341A '2 0 Cleanup RT-C261 RT-05 RT-C173A 2 0 RT-C187A Nuclear NB-01 NB-CSA 2 0 Boiler NB-CIO Piping Main Steam MS-05 MS-C74 1 0 Drain
- Isolation IS-03 IS-C5 2 0 Valve Seal IS-C8 TOTALS 12 0 t
b B-1
]
. . ~l7 : :._ l APPENDIX C TECHNICAL JUSTIFICATION FOR ELIMINATION OF ARBITRARY INTERMEDIATP. BREAKS ,
The following items provide generic. technical justification for the
- elimination of: arbitrary intermediate pipe breaks and their associated
- ' pipe whip restraints.
- 1. _ Operating-procedures and pipe and system designs minimize the
- possiblity of intergranular stress corrosioa cracking, thermal and vibration induced
- fatique, and water / steam hammer in these. lines in which arbitrary pipe. breaks are currently poaculated. Detailed design provisions for these phenomena are provided in Appendices D, E, and _ F,: respectively.-
- 2. The' remaining postulated pipe breaks and whip restraints _ provide an adequate level'of protection in areas containing high energy lines.
Potential environmental effects are still considered in the design.
- 3. Pipe breaks ~are postulated to occur at locations whers, depending on.the pipe class, stresses are only 80% of Code allowable or where
'the cumulative usage factor is only 10% of the allowable 1.0. 1he
-arbitrary breaks'to be eliminated all exhibit stresses and usage factors below these conservative thresholds. r
- 4. Pipe rupture is recognized in Branch Technical-Posicion NEB 3-1 as l being a:" rare event which may only occur under unanticipated conditions".
- 5. Arbitrary intermediate breaks are only postulated'to. provide t
' additional conservatism in the design. - There is no technical
-justification for. postulating these _ breaks.
6.- Elimination of pipe whip restraints associated-with the arbitrary
~ breaks will facilitate'in-service inspection, reduce heat losses i
from the restrained piping, and reduce the potential-for-restraining pipe due to unanticipated' thermal' growth and' seismic motion.
- 7. . Pipe break-related' equipment qualification-(EQ) requirementsTare not.affected by-the. elimination of the' arbitrary. breaks. Breaks
-are' postulated non-sechanistically for EQ purposes.-
It is' concluded that the elimination of arbitrary intermediate breaks is I t'echnically ~ justified. basedion the proceding reasons.
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APPENDIX D PROVISIONS FOR MINIMIZING STRESS CORROSION CRACKING IN HIGH ENERGY LINES Industry' experience has shown~(NUREG-0691).that the potential for inter-
. granular' stress corrosion cracking (IGSCC) is less likely if the !
- following conditions are controlled: high residual tensile stresses, i
susceptible piping material', and a corrosive environment.-
4 With_the' exception of the reactor recirculation piping, all austenitic stainless steel in contact with the reactor coolant is 316 L stainless Esteel and, therefore, has less than 0.03% carbon content.- The likelihood of IGSCC in stainless steel increases with carbon content.
The following additional process controls were applied in addition to 4 material l selection; j i:
3-
- All'austenitic stainless steel was purchased in the solution
- heat treated condition in accordance with applicable ASME and
-ASTM specifications.
~
Welding heat input was restricted and interpass temperature l
wasilimited to 350*F. High heat welding processes such as
' block welding and electroslag welding were not permitted. All ,
. weld filler metal and castings were required by specification ,
i j to hwe a minimum of 5% ferrite. ,
- Inside diameter grinding of pipe welds was prohibited unless
! the pipe weld was subsequently solution-annealed.
g
- Bending of small diameter.(2 inch and smaller) piping or tubing were eliminated by using fittings in the solution /
annealed condition. Pipes cold bent to.cause greater than 2h%
[ strain or to a radius less-than 20D'("D" being the' pipe or j: tubing diameter) were solution annealed.
Pickling of welds not subsequently solution-annealed were prohibited.
r ..
D These controls were used to avoid severe sensitization and to comply
'with the intent of Regulatory Guide 1.44, " Control of the Use of
[ Sensitized Stainless Steel."
The reactor recirculation piping is fabricated primarily of 304 j' stainless steel.- Certain portions'have been changed to " nuclear grade" type"316-L which conts. ins less than 0.03% carbon. The remainder has had
!' corrosion-resistant clad" applied in the vicinity of the field ' welds 'so tihat no heat-affected type 304 will be'in contact with the coolant. The
- piping assemblies were all solution annealed after all shop ~ welding and application of the cladding.
4 1
' EFurthervare, NUREG-1061, Volume 3 (November 1984) indicates that thermal fatigue and stress corrosion cracking ~cannot be absolutely excluded from piping' operation and that it may never be possible to either precisely D-1 l
. _ .- _ _ . - . . _ - _ , . . J, __ __ , ~ . - _ - , . _ , - , _ . _ . - . _ . . , . _ . _ , -,. _.. ,_._.
-_. , - ~ . - . - . - _
, .- 1. .:- ..-
-specify acceptable levels for them or assure' analytically that the specific. levels would not be exceeded. However, NURFG-1061 indicates that should these unanticipated severe conditions occur, the break would 1 most likely be located at the ' terminal ends, at connections to
-components .and at other locations which introduce higher stress concentration or that exceed the stated threshold limits of'SRP 3.6.2.
Based on these factors, the NUREG-1061, Volume 3, concluded that .
relaxing the arbitrary intermediate break requirements would not
-introduce adverse effects.
. Table D-1 summarizes the systems in which currently postulated arbitrary
' intermediate-breaks are to be eliminated.
L e
- D-21
. ,, ,$ lg s ,,n. .-w4,,--rw
. . . _ . ., . . , _ . - . , _ . _ . _ ...._,,_ ~ -. . . _ . _ .
- " APPENDIX D. M I TABLE D-1. y ,
, ;3 Elimination of Arbitrary: Breaks: ^
-. Systems Summary-
' Numb'e r' o f 1 B reaks /1.
~~
Pipe. Operating: ! Whip. Restraints-Temp'. -(,F).
Piping = System -Material Deleted
-Main'~ Steam CS 550- ^11/16: -
. Reactor Recire SS 534 -8/8 550" 2/3 High. Pressure Core CS Spray LowiPressure Core CS 550 2/4 o
Residual Heat.' Removal CS/SS 550 9/4
- Reactor Core. Isolation' CS- 550 3/2 Reactor. Water. Clean-up CS 534-544/,437/ 4/0 t 233/120 .
Main. Steam Isolation ~ CS. 550 2/0 .
. Valve-Leakage rControl .)
CS/SS 549 2/0 NucleariBoiler: Piping Standby.. Liquid: Control CS/SS 135/80 2/0 45/37
- SS'.- Stainless Steel CS - Carbon Steel- <
a-7 D-3 .
^^ ?
.i . ,. ._
n ry ~ ~. .._ -. - - .-- ~ .
.y
~
nG '*
APPENDIX E PROVISIONS TO MINIMIZE THE EFFECTS OF-THERMAL AND VIBRATION INDUCED PIPING FATIGUE I.. GENERAL FATIGUE DESIGN CONSIDERATIONS For Class 1 lines, fatigue considerations are addressed by the cumulative usage factor (CUF). To' ensure that piping does not fail due-to fatigue, the ASME Code has established the CUF limit at 1.0.
By definition, all arbitrary intermediate break locations have CUFs below 0.1.
For Class 2 and 3 lines, fatigue.is. considered in the allowable stress range check for thermal expansion stresses. This stress is included in the total stress.value.used to determine postulated break locations. All arbitrary break locations exhibit stresses less than 80% of-the code allowables. If the number of thermal cycles is' expected _to be greater than 7,000, then the' allowable
. stresses are-further reduced by an amount dependent on the number of cycles.
II. THERMAL DESIGN CONSIDERATIONS For Class 1 lines anticipated flow conditions that could result in piping thermal transient stresses are defined. Piping thermal
~
transient stresses are included in cumulative usage factors and documented in stress reports for the piping.
III. VIBRATION DESIGN CONSIDERATIONS
- Piping at CPS is designed and supported to minimize transient and steady state vibrations. Preoperational and start-up testing will be performed to ensure that vibration of the piping systems are within allowable limits. The purpose of the program is to ensure that operations piping vibration does not result in exceedances of allowable stress amplitudes nor result in undesirable system
. responses. ~The freedom from restraint or snubber lock-up will also be observed; and a-cold / hot walkdown will be included.
Plant personnel will be trainedsto recognize excessive piping vibration so that' potential problems can be. resolved. In addition, a formal' test' program, as outlined-in the FSAR will be completed to
- verify the acceptability of the piping steady-state vibration.
6
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H
, , 1* -? ,
APPENDlX F
-PROVISION FOR MINIMIZING STEAM / WATER HAMMER EFFECTS 1 1. . Wr.ter' hammer is prevented in the ECCS discharge lines by maintaining the lines in a full condition. The lines are kept
. full up to the injection isolation valves by water leg pumps.
Bayond the discharge valve the line is not drained when the system is on standby, so the discharge lines will remain full.
"The HPCS is a motor-operated system and has no steam supply line. l The steam supply line to the RCIC turbine is maintained at an elevated temperature down to the shutoff valve directly upstream of
.the turbine by means of a condensing pot arrangement. The steam supply line is sloped downward to allow any moisture in the line to )
l drain off to the condensing pot. The condensing pot drains to the main condenser during normal plant operation and is automatically isolated when the RCIC system is initiated.
The. isolation valves on the steam supply line to the RCIC turbine are normally open, and automatically close upon receipt of any one of the following signals; a) A high pressure drop across a flow device in the Steam supply line equivalent to 300 percent of the steady state steam flow at 1192 psia.
b) A high area temperature, utilizing temperature switches in the leak detection system.
c)' A low reactor pressure of 50 psig minimum.
d) A high pressure between the turbine exhaust rupture diaphragas.
These valves may also be remote manually closed. A one-inch bypass with a motor operated-shutoff valve is supplied'around the inboard steam line isolation valve. This bypass.line will be used for
- pressurizing,' draining, and pre-warming the. steam line prioroto opening the inboard steam'line' isolation
- valve.
J In order to prevent damage from water hammer, neither steam isolation valve is opened automatically by an initiation'aignal.
Should either or both'of these valves be closed, they must be reopened by first closing both valves completely. With both' valves
. closed, the outboard-isolation valve can be: reopened to allow any.
imoisture in the line to drain.- Then moisture ahead of the inboard isolation valve is equalized and the downstream'line is warmed by slowly opening the inboard isolation valve bypass valve. Finally,
.the: inboard isolation valve may be reopened without. water hammer occuring.
-y_1-t: a
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- 2. The main. steam and feedwater systems'are expected to experience steam and. water hammer loadings, respectively. Analyses are p
'erformed for these loadings and the main steam and feedwater systems are. designed to accommodate and minimize effects of these
>1oadings.- Main-steam piping is analyzed and designed for the
, effects of isolation valves closures, turbine stop valve closures, and safety relief valve openings. The feedwater piping is analyzed and designed for the effects of check valve closure caused by flow reversa1'from the RPV after a feedwater pump trip. The main steam
- and feedwater: stress reports include the stresses and usage factors calculated from.the analyses of these events.
~
F-2
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APPENDIX G ,
PROVISION FOR MINIMIZING LOCAL STRESSES FROM WELDED ATTACHMENTS IPC has reviewed >all arbitrary l intermediate break locations to be
. eliminated and has determined that.in most cases no welded attachments are placed in close proximity to postulated break. locations. In four cases.'where welded attachments are in proximity to the postulated arbitrary. breaks, the local bending stresses induced by the attachment will not affect the stresses at the postulated break point. To ensure that this is the case, the~1ocal stresses have been determined and added
.to the primary stress in the stress report.
l 5
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i j j' G.