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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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ILLINDIS POWER COMPANY 73 3 z 99_g5 y _7 ffy 500 SOUTH 27TH STREET, DECATUR, ILLINOIS 62525 September 25 , 1981 s
@ QP rT 9 t'
Mr. Darrell G. Eisenhut, Director f ~, 8&p Division of Licensing (4 At g8 --
Office of Nuclear Reactor Regulation <4 "4e /ggIh6 United States Nuclear Regulatory Commission {}g .Qy Washington, D.C. 20555 ,
o
Dear Mr. Eisenhut:
References:
- 1. D. G. Eisenhut letter, dated December 22, 1980, regarding " Control of Heavy Loads"
- 2. G. E. Wuller (IP) letter to D. G. Eisenhut, U-0249, dated June 22, 1981 Clinton Power Station Units 1 and 2 Docket Nos. 50-461 and 50-462 Illinois Power has completed the last phase of the
" Control of Heavy Loads" study. The attachment represents IP's response to section 2.2 and 2.3 of enclosure 3 to re-ference 1 above. The result of the study is that IP currently complies or will comply with the requirements of NUREG 0612.
As in our previous response the requests of sections 2.2 and 2.3 will each be restated, followed by IP's response. This letter satisfies the response requirements of reference 1. If there are any questions regarding this submittal, please do not hesitate to contact Steve Swartz at (217)424-6983.
Sincerely,
~
G. E. Wuller Supervisor-Licensing Nuclear Station Engineering SWS/lt Attachments cc: J. H. Filliams , NRC Clinton Proj ect Manager jgyd H. H. Livermore, NRC Resident Inspector '
fs JI l 8109290486 810925 1 PDR ADOCK 050004611 A pop) . . - - -
-Attachment-The following is Illinois Power's (IP's) response to Sections 2.2 and 2.3 of Enclosure 3 of Mr. Eisenhut's December 22, 1980 letter regarding IP's compliance to NUREG 0612, " Control of Heavy Loads at Nuclear Power Plants".
2.2 Specific Requirements for Overhead Handling Systems Operating in the Reactor Building Section 2.2-1 Request and Answer (R) Identify by name, type, capacity, and equipment designator, any cranes physically capable (i.e.,
ignoring interlocks, moveable mechanical stops, or operating procedures) of carrying leads over spent fuel in the storage pool or in the reactor vessel.
(A) The term " reactor building" as used in NUREG 0612, shall be construed to include the fuel building and the containment building for the Clinton Mark III '
plant. The following table includes all cranes in the fuel and containment buildings capable of carrying loads over or near spent fuel pools.
i i
l i
1 I
I i
Crane Equip. L.os at ion havie6L hat e huutdown Lquip bed Equip Floor Column Piece Crane . Equip. Load Below (0) or Near By During Cr~ne Served Elev. Bldg. Row Lifted Type Ident. Capacity (P) Operation Polar RPV Head 828' 3" Contain- 105-121 Drywell Head Circular 1HC01G Main Hook Reactor Vessel (0) Yes "n
- AH-K 65T Rail Tram 100T Fuel Assembly (0)
Crina Drywell Head ment Insulation T/R E1. (90T IncludesBeam, Aux. Hook Vessel Internals (0)
STEAM Separator 856'0" Strongback (Single-Failure 10T Regen. Hx El 803'(0)
STEAM Dryer 41 rad Block) Proof) Fuel Storage Rack (0)
Spent Fuel Gates Auxiliary Platform D. Refuel Fuel Bundles, 828'3" Contain. 110-114 Fuel CE Platform F11-E014 Fuel Hoist Reactor vessel (0) No Pittform Reactor Ocepor.ents ment AE-AC Bundle (Single Fall. 1000 lbs. Fuel Storage Rack (0)
Control Rod 51Me Guides T/R El. 625 lba. Proof) (Electric)
Control Rods 828'3" Auxi. doist Neutron Instr ments 1000 lbs.
(Electric)
C
- Aux 11ary Control Rods 828'3" contain- 110-114 Control GE Platform F15-E005 " load Celled" Reactor Vessel (0) No P11tform Stm. Line Plups ment AE-AC 218 lbs 500 lb.
Jet Pumps T/R El. Electric Vessel Inspection 828'3" Holst d.alb (2) ruel Bundles 828 3" Contain- liO-tis ment AH-AE ri i enei.
625 lbs.
alb GE Equip 1000s ruei Transfer (0)
Pool (0)
Yes (New Fusi)
' Spent Fuel rool (P) e , Fuel Fuel Bundles 7!5'C" Fuel 112 J i-121 Fuel GE Plat- F11-E017 Fuel Moist 6 Tes n:.ndling (New Fuel & AH-AL Bundle form (Single 1000 lb (HaveSo[on?lates)
Plttfore Spent Fuel) T/R El. 625 lbs Failure Proof) (Electric) 755'0" Aux. Hoist 1000 lb.
(Electric)
[. Futi -Fuel Cask 755'0" Fuel 102-114 Fuel Recti- 1HC07G 125T Main New Fuel Storage Yes Bldg -Spent Fuel AH-AM Cask linear 10T Aux. (on F1. E1. 707'0") (0)
Crane -Pool Cates T/R El. (Not yet (Single Fuel Transfer Pool (0)
-New Fuel 781'0" Selected) Failure 50-75T Proof, Except (3 Ton Load Hook)
Block)
Note: Frane Cannot travel over Spent luel Pool cr J18 -Work Table 755'0" Fuel 121-124 Fuel Bundle J1B GE Equip. 1000 lb. Spent Fuel Fool (0) Yes O* Cranes -Fuel Prep. Mach. AH-AL 625 lbs.
(2)
Notet 3 post holes - only 2 JIBS
- h. ala ruei 755'0" ruel 112.1-116 Shield Trolier: as 10T Spent ruei Pool (P) Yes Crone Transfer A-H Plates Mat.ual (contract Tube Holst: ident.)
Shield Plate Motorized i
2-
1 Please note that item h is a crane which is not operated over the spent fuel pool in the fuel building. This is a new crane whose mounting detail has not yet been determined. Once identified, the crane will either be deleted from this list, or additional drawings and hazard elimination criteria will be supplied to the NRC.
Section 2.2-2 Request & Answer (R) Justify the exclusion of any cranes in this area from the above category by verifying that they are incapable of carrying heavy loads or are permanently.
- prevented from movement of heavy loads over stored fuel or into any location where, following any failure, such load may drop into the reactor vessel or spent fuel storage pool.
(A) Item c, the auxilary platform, is limited to a 500 pound lifting capacity and therefore, is excluded.
Item f, the fuel building crane, is permanently prevented from travel over the spent fuel pool and also is eliminated. It is anticipated that item h will also be included in this category.
Section 2.2-3 Request & Answer (R) Identify any cranes listed in 2,2-1, above, which .
you have evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads-to be. carried and the basis for this evaluation (i.e., complete compliance with NUr"" 9612, Section 5.1.6 or partial compliance supplemented by suitable al - ,
ternative or additional design features). For
- each crane so evaluated, provide the load-handling-system (i.e., crane-load-combination) information specified in Attachment 1.
(A) Item a of Section 2.2-1, the polar crane, is de-signed and built to the requirements of NUREG 0554.
The crane, with the exception of the ten (10) ton:
auxilary hook, is single-failure proof. Administra-Live controls will be required, when using the auxilary hook, to prevent the carrying of loads over the fuel transfer pool and the reactor during re-fueling operations. The following is a step by step response to the requirements of Attachment 1.
e
. , . . - - . . - - , - . = --- -. - -..-. - - , -. -
Single-Failure-Proof Handling System-Attachment (1)
ITEM (R) Provide the name of the manufacturer and the design-1 of 5 rated load (DRL). If the maximum critical load (MCL),
as defined in NUREG 0554, is not the same as the DRL,
- provide this capacity.
(A) The polar crane is manufactured by P&H Harnischfeger.
The design-rated load is 100 tons. The MCL is 88 tons. The MCL consists of the RPV head and the carousel stongback, 63 and 25 tons respectively.
ITEM Provide a detailed evaluation of the overhead handling 2 of 5(R) system with respect to the features of design, fabrication, inspection, testing, and operation as delineated in NUREG 0554 and supplemented by the identified alternatives specified in NUREG 0612,.
Appendix C. This evaluation must include a point-by-point comparison for each rection of'NUREG 0554.
If the alternatives of NUREG 0612, Appendix C, are used for certain applications in lieu of complying with the recommendation of NUREG 0554, this should be explicitly stated. If an alternative to any of those contained in NUREG 0554 or NUREG 0612, Appendix C, is proposed, details must be provided on the proposed alternative to demonstrate its t equivalency.
(A) The following is a point-by-point comparison of the polar crane design, fabrication, etc. to the re-quirements of NUREG 0554.
NUREG 0554 Requirements Met By the Polar Crane The polar crane will be employed during the construction phase. The maximum load allowed during this period will be 85 tons. No separate performance specifications for the construction period are considered necessary. The crane will be thoroughly examined and tested at the end of the construc-tion period, prior to turn-over to the operations staff. Of particular concern will be the possible damage caused by use of the crane in a dirty environment (i.e., dust, grinding wheel residue, etc.). A temporary tent was constructed over the main drum to protect the wire rope from abrasives. At the-end of the construction phase the wire rope will be examined to determine if replacement is necessary.
An operating environment of -0.5 inches H2O to 2 psig, 65 F to 104 F, and 100% relative humidity was specified for the polar crane. The crane box girders are vented to prevent collapse during containment pressurization. Since the crane was to be used for a short period of time before the contain-ment dome was installed, it was designed to include drainage ,
holes to eliminate standing water and drip proof electric motors, drip covers for brakes, and waterproof enclosures for all electrical controls, limit switches, etc., to protect against possible moisture related failures. Coating of crane surfaces is in accordance with ANSI N101.4.
l
__ _ _ _ _ _ _ _ - - _ - - _ - _ _ l
l- .
I Materials used for stru tural members essential co structural integrity were impact tested, unless exempted by the provisions of paragraph'AM-218 of ASME Code,Section VIII, Division 2. The " minimum design temperature" was defined as 60 F below the minimum operating temperature of 65 F. Minimum Charpy V-notch impact test requirements were those given in Table AM 211.1 of the ASME Code,Section VIII, Division 2.
All complete penetration groove welds were 100% radio-graphed in accordance with acceptance standards stated in Section 6, AWS Dl.l. Welds impractical to radiograph were examined 100% by both Ultrasonic and either Magnetic Particle or Liquid Penetrant methods.
Fillet welds were 100% examined by Magnetic Particle or Liquid Pentrant methods. This examination conforms to all applicable requirements of AWS Dl.1, Section 6. Welds meeting the acceptance standards indicated in AWS Dl.1 were considered acceptable.
Thc polar crane is designed to raise, lower, hold in position,.and transport test loads of 125% of the DRL with-out damage or excessive deflection of any crane part. This design feature, plus additional margin applied, and the redundancy aspects of the crane appear to adequately cover the aspect that the effect of cyclic loading on this crane would be minimal. Over the 40 year life of the crane, in-cluding the construction period, the small number of critical lifts made would appear also to have minimal' cyclic effect.
The main hoist load block assembly, rope reeving system, and lifting devices are of redundant. design (dual load attach-ing points) such that each attaching point and lifting device is_ capable of supporting a static load of three times the rated load without permanent deformation. Main hoist rope reeving syrtems are of redundant design such that each system is capable of providing separately the load balance on the head and load blocks through'the rope and equalizer. The auxilary 10 ton hoist is not used to make critical lifts, either by itself or in conjunction with the main hoist.
The load hoisting drum is provided with structural and mechanical safety devices to prevent the drum from dropping, disengaging from its holding brake system or rotating in the event of a drum, shaft,or bearing failure.
Two automatic electric release (magnetic), spring set, shoe type hoist brakes, each with a 125% motor torque rating, are provided. One brake is provided on the motor shaft and one brake is provided on the motor shaft extension on the opposite side of the gear case. Provisions are made for manual operation of the above-mentioned holding brakec. Manual brake operation during emergency lowering includes features to limit the lowering speed to less than 3.5 fpm. One eddy current electrical load brake is provided for precise speed regulation in handling the load.
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Controls are provided to stop the_ hoisting movement within a maximum of 3 inches of vertical load block travel through the use of electrical power. controls, mechanical braking systems and torque controls when rope failure, overspeed, or an overl.onding condition occurs.
The maximum fleet angle from the main hoist drum to the lead sheave in the load block does not exceed 3 degrees during.
hoisting and does not have more than one 180 degree reverse
-bend for'each rope leaving the drum and reversing on the first, or lead sheave, of the load block. Fleet angles between individual sheaves to not exceed 3k degrees. Pitch diameter of the lead sheave is greater than or equal to 30 times the rope diameter for reverse bend, 26 times rope diameter for running.
sheaves and the drum, and 13 times.the rope diameter for equalizers. The portions of the vertical hoisting system components of the main hoist of the containment building crane, which includes the head block, rope reeving system, load
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block, and dual load-attaching device are each designed to support a static load of 200% of.the design rated load. With the hook in the lowest position,-two full wraps of cable remain on the drum. A cold proof test of the cable was performed.
The crane hook is a forged stainless steel (AISI 4820H),
sandwich design, sister hook. In other words, a hook within a hook. Each hook is designed to support a load, both static and dynamic, of 3 times the DRL. Each portion of the hook was statically. load tested to 200% of the DRL. After testing, the hook underwent PT and UT examination.
The mechanical and structural components of the hoisting system are designed and_ fabricated to have the required strength to resist failure if the hoist block should come inta contact with the bead block assembly or if the load is hung up.
The main hoist is provided with limit switches to stop the hook in its highest and~1owest safe positions. Each limit switch !s wired so that the drive motor can be energized-in the reverse direction after its limit switch ~has opened.
Two limit switches are used to limit the upward travel of the hoist hook. A block type switch is used on the cable and a screw type-on the drum. These switches are ' adjusted so that if the screw type switch fails, the block switch will shut
' off the current.
To further protect the wire rope no side loads are allowed on the polar. crane. This requirement is posted on the side of the main load block.
-4(B)-~
No travel rail stops are necessary for the polar crane, since it operates on circular rails. It does have an electrical interlock feature en prevent cab travel in the 350*
to 360* azimuth region of the containment building. This is to prevent contact of the crane cab with the refueling plat-form when the platform is in the stored position. The inter-lock can be bypassed from the cab however when an interference does not exist.
Radio control is provided for all functions of the crane.
Radjo control transmitters and receivers are compatible with the stepless control system provided for the crane. As a backup to the radio control, a bridge mounted pendant push-button station is provided which vill extend to four feet above the main floor for the crane. Each pendant control station is designed to operate contactors on the control panel by means of pilot currents through transformers pro-vided with the equipment, thus eliminating danger of the crane operator coming in contact with high voltages.
A " dead-man" type of control system is used on the crane.
A control lever or pushbutton must be engaged and held in place prior to and during any crane operation. The release of the control lever or pushbutton will result in an immediate cessation of the crane operation with the load locked in place.
The main and auxiliary hoist controls are provided with step-less ac control to provide variable speed for lowering and raising. Inching provisions are also provided for lowering and raising each hook. The bridge and trolley controls have a stepless ac control to provide variable speed for each crane motion. Inching provisions are also provided for each crane ruotion.
A plugging circuit is provided on the crane and is designed to decelerate, stop, and accelerate the bridge, trolley, or load in a controlled, safe manner.
I The polar crane was installed and thoroughly tested be-fore turn-over to the construction organization. Periodic maintenance is performed or the crane as recommended by the
' manufacturer. Prior to turn over to the operations staff, at the end of the construction period, the crane will again be tested and, if necessary, degraded components replaced.
i The crane was statically tested to, at the least, 125%
of MCL with the girders and trolley in a position to generate the maximum strain on the bridge and trolley structures. A performance test using 100% MCL was performed for all speeds and motions the crane is capable of.
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A load limit control prevents crane lifts when a specific load size is exceeded. This device was tested using the 122 ton load of the static load test. With two upper limit switches and the load limit control available, it does not appear advantageous to submit a crane to the possible damage a two-block test could present.
The polar crane was manufactured under a quality assurance program by P&H. The program was audited pericdically by the purchaser. Periodic surveillance was also performed at P&H to determine that the requirements of NUREG 0554, as written into the purchase contract, were met.
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Single-Failure-Proof Handling Systems Attachment 1
-continued-ITEM (R With respect to the seismic analysis employed 3 of 5 ) to demonstrate that the overhead handling system can retain the load during a seismic event equal to a safe shutdown earthquake, provide a description of the method of analysis, the assumptions used, and the mathematical model evaluated in the analysis.
The description of assumptions should include the basis for selection of trolley and load position.
(A) Due to soil modulus calculations having changeu the seismic response spectra for the Clinton plant, reanalysis of the polar crane seismic design must be done. When completed, the above requested infor-mation will be supplied.
IT2M (R) Provide an evaluation of the lif ting devices for each 4 of 5 single-failure-proof handling system with respect to the guidelines of NUREG 0612, Section 5.1.6.
(A) Two lifting devices are currently anticipated to be used to accomplish lifts with the polar crane over the refueling floor. Both are supplied by General Electric. They are the Steam Separator / Dryer Strongback and the RPV Head Carousel Strongback.
Each strongback is provided with four (4) lift points to the load. General Electric states that two (2) of the four (4) attachments are capable of supporting the load. A single failure is considered as the loss of one lift point only.
The strongbacks are attached to the polar crane redundant sister hook through the use of a hook box on top of the strongbacks and through two (2) six (6) inch diameter link pins. General Electric terms the strongbacks " single-failure proof."
The operations and maintenance staff has not yet procurred lifting devices, such as slings, for use with the polar crane. It is anticipated that slings will be required for such items as shield plugs, auxilary platform installation on the vessel flange, and miscellaneous uses. When sling selection is required,the staff will consider the selection guidelines of ANSI B30.9-1971. Dual slings for use with the sister hook will be employed when the application permits.
ITEM Provide an evaluation of the interfacing lift 5 of (5R) points with respect to the guidelines of NUREG 0612, Section 5.1.6.
(A) Fuel casks are not intended to be used in the containment, only in the fuel building.
Four lifting lugs are useo on the RPV head. After failing two lugs, each of the remaining lugs would have to support 63,100 pounds. (These two (2) remaining lugs are assumed to be opposed on the head so that the head would remain level.) Based on a tensile strength of 80,000 psi and a cross sectional analysis on the lug only-(18 in2), the remaining 2 lugs in cross section have a design margin of approximately
- 22. The cross sectional area above also applies to the steam separator and steam dryer lugs.
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- Section 2.2-4 Request and Answer i < (R) For cranes identified in 2.2-1, above, not categorized l . according-to 2.2-3, demonstrate.that the criteria of NUREG 0612, Section 5.1, are satisfied. Com-2 pliance with Criterion IV will be demonstrated in response to Section 2.4 of this requent. With respect i to criteria I through III, provide a discussion of your evaluarion of crane operation in the Reactor 1
Building and your determination of compliance. This response should include the following information :
- for each crane
1
- a. Where' reliance is placed on the installation and j
use of electrical interlocks or mechanical stops, indicate the circumstances under which these i
protective devices can be removed or bypassed i- and the administrative procedures invoked to ensure proper authorization of such action.
, Discuss any related or proposed technical specifi-
! cations concerning the bypass of such interlocks.
- b. Where reliance is places on the operation of the Standby Gas Treatment System, discuss present
, and/or proposed technical specifications and
.! administrative or physical controls provided to
- ensure that these assumptions remain valid.
i
- c. Where reliance is placed on other site-specific considerations (e.g., refueling sequencing).
provide present or proposed technical specifi-
! . cations , and discuss administrative or physical
- controls provided to ensure the validity of such considerations.
r d. Analyses performed to demonstrate compliance l vith Criteria I through III~should conform to l C e guidelines of NUREG 0612, Appendix A. .
( Justify any exception taken to these guidelines, l and. provide the specific information requested l
in Attachment 2, 3, or 4, as appropriate, for each analysis performed. i (A) Based upon the requests of the previous sections, i
it would appear that the author intended to eliminate L from. discussion here the cranes categorized in 2.2-2, as well as the cranes categorized in 2.2-3.
basis, the remaining cranes to be addressed h: Chi ere-that would be items b, d, e, g and h from the Section 2.2-23 response.
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,1 It should be noted that NUREG 0612 (sect. 1.1) defines a heavy load as one "whose weight is greater than the combined weight of a single spent fuel assembly and its handling tool". Depending upon the handling tool used, the combined weight could exceed 1000 pounds. This would, in effect, eliminate items b, d, e and g from the study, since "the handling of a single spent fuel assembly has been reviewed in the original licensing review or in the Generic Issue " Fuel Handling Accident Inside Containment". Items b, d, e and g all have 1,000 capacities. The 1,000 pound capacity is pro-vided for these cranes due to the sizing practices of the crane hoist industry (i.e., hoists are not generally produced in the 700 - 1000# range). These cranes do not handle weights greater than those of fuel bundles.
The one remaining crane is item h, the fuel transfer tube shield plate jib crane, which is to have a 10 ton capacity. As previously stated, this crane's location from the spent fuel pool in the fuel building, and its means of operation have not been determined.
Once engineering design is completed, the required information will be supplied.
2.3 Specific Requirements for Overhead Handling Systems Operating in Plant Areas Containing Equipment Required for Reactor Shutdown, Decay Heat Removal, or Spent Fuel Pool Cooling Section 2.3-1 Request and Answer (R) Identify any cranes listed in 2.1-1, above, which you have evaluated as having sufficient design features to make the likelihood of'a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features).
For each crane so evaluated, provide the load-handling-system (i.e., crane-load-combination) information specified in Attachment 1.
(A) The intent of the response to 2.1-1 was to separate all.the cranes,which exist in the Clinton plant,into three (3) categories. One category (Table 1, supplied with the section 2.1 response) includes cranes that are not near safe shutdown equipment, spent fuel, or the reactor vessel. The other two categories (Load / Impact Area Matrix, supplied with the section 2.1 response) include cranes near spent fuel or the reactor and cranes near safe shutdown equipment. The cranes
listed in Table 1 will not be covered again here.
Nor will the cranes which were analyzed in Section 2.2 above, be discussed again. Therefore, it is understood, that only cranes in the Load /
Impact Area Matrix which are near safe shutdown eautruient need be discussed here.
The cranes included in Load / Impact Area Matrix, not discussed in Section 2.2, are listed below:
- 1. Recirculation Pump / Motor Removal Monorai.1 -
- 2. MSIV Monorail
- 3. Containment Equipment Hatch Hoist Beam 35
- 4. MSIV Steam Tunnel Bridge Crane
- 5. Fuel Pool Waste Filters and Filter Demineralizers Beam 33
- 6. RHR Pumps Removal Beams 38, 39, 40
- 7. HPCS Pump Removal Beam 69
- 8. LPCS Pump Removal Beam 42
- 9. RCIC Puup Removal Beams 41, 13 None of the above cranes are single-failt re-proof, as defined by NUREG 0554.
Section 2.3-2 Request and Answer !
(R) For any cranes identified in 2.1-1 not designated as single failure-proof in 2.3-1, a comprehensive hazard evaluation should be provided which includes
. the following information:
- a. The presentation in a matrix format of all heavy loads and potential imp ~act areas where damage might occur to safety-related equipment. Heavy loads identification should include designation and weight or cross-reference to information pro-vided in 2.1-3-c. Impact areas should be identi-fied by construction zones and elevations or by some other method such that the impact area can be located on the plant general arrangement drawings. Figure 1 provides a typical matrix.
(A) Cranes 1-9 of Section 2.3-1 are .11 included in the l Load / Impact Area Matrix suppliea in response to Section 2.1-3-6.
(R) b. For each interaction identified, indica *.e which
! of the load and impact area combin&tions can be l eliminated because of separation and redundancy of safety-related equipment, mechanical stops and/or electrical interlocks, or other site-l specific considerations. Elimination on the basis
! of the aforementioned consideration should be l supplemented by the following specific information:
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(R) 2.3-2 (Continued)
- 1. For load / target combinations eliminated because of separation and redundancy of safety-related equipment, discuss the basis for determining that load drops will not affect continued system opera-tion (i.e., the ability of the system to perform its safety-related function).
(A) The cranes 1-9 of Section 2.3-1 appear to be divided into two groups. Those which could Le used during operation of the plant and those which could not be used. Some of the cranes are in areas which are highly irradiated and used to repair systems of which no work could be performed while the plant is operational. Those cranes which could be used during plant operation fit into the category described by Section 2.3-2-b-(1).
Cranes 5-9 could be used to repair equipment while the plant is operational. Cranes 6-9, besides having back-up cooling systems which can perform their functions, are each separated from the other, with each one having its own crane. In the event that a system would require repair, that system's operation would not be affected by a load drop, since it would be shut down in order for the repair to be done.
Crete 5 services the fuel pool waste filters and filter demineralizes periodically during plant operations. A load drop in this area would not affect the cooling capability of the fuel pool cooling system due to isolation valves on either side of the filters and the filters being in a separate loop from the cooling loop. However, if fuel pool cooling would become unavailable, the RHR system is available as a backup cooling system.
l (R) 2. Where mechanical stops or electrical inter-
! locks are to be provided, present details showing the arear where crane travel will be prohibited. Additionally, provide a discussion concerning the procedures that are to be used for authorizing the bypassing of interlocks or removable stops, for verifying that interlocks are functirnal prior to crane use, and for verifying thac interlocks are restored to operability after operations which require bypassing have been completed.
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(A) Of the cranes 1-9, described in Section 2.3-1, none rely upon mechanical stops or electrical interlocks to limit their travel or use.
(R) 3. Where load / target combinations are elim-inated on the basis of other, site-spec-ific considerations (e.g., maintenance sequencing), provide present and/or pro-posed technical specifications and dis-cuss administrative procedures or physi-cal constraints invoked to ensure the validity of such considerations.
(A) Cranes 1-4 of Section 2.3-1 are eliminated as possible hazardous load contributors under the
" site-specific considerations". Simply stated, a crane cannot do Camagi to an operating system if it is not used during that operation. Cranes 1-4 are in high radiation areas and intended for use on systems which can only be repaired when the plant is non-operational.
(R) c. For interactions not eliminated by the analysis of 2.3-2-b, above, identify any handling systems for specific loads which you have evaluated as having sufficient design features to make the likelihood of a load drop extremely small and the basis for this evaluation (i.e., complete compliance with NUREG 0612, Section 5.1.6, or partial compliance supplemented by suitable alternative or additional design features).
For each so evaluated, provide the load-handling-system (i.e., crane-load-combination) information specified in Attachment.
(A) No cranes remain.
(R) d. For interactions not eliminated in 2.3-2-b or 2.3-2-c, above, demonstrate using appropriate analysis that damage would not preclude operation of sufficient equipment to allow the system to perform its safety function following a load drop (NUREG 0612, Section 5.1, Criterion IV). For each analysis so conducted, the following infor-mation should be provided:
- 1. An indication of whether or not, for the specific load being investigated, the overhead crane-handling system is designed and constructed such that the hoisting system will retain its load in the event of seismic accelerations equivalent to those of a safe shutdown earthquake (SSE).
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- 2. The basis for any exceptions taken to the analytical guidelines of NUREG 0612, Appendix A.
(R) 2.3-2 (Continued)
- 3. The information requested in Attachment 4.
(A) No cranes remain.
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