|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999
Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs
ML20217J4331999-10-15015 October 1999
Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation
U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999
Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)
ML20217C0871999-10-11011 October 1999
Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld
U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999
Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included
U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999
Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld
U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999
Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station
ML20217A9881999-10-0101 October 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities
ML20217A7361999-10-0101 October 1999
Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs
ML20217J1251999-09-30030 September 1999
Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC
ML20217J1421999-09-30030 September 1999
Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC
ML20212G6751999-09-22022 September 1999
Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station
U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999
Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl
U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999
Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl
ML20212G6981999-09-20020 September 1999
Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability
ML20217H3421999-09-17017 September 1999
Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr
05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999
Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events
05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999
Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments
U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999
Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed
ML20211Q2671999-09-0808 September 1999
Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000
U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999
Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl
U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999
Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7
ML20211D2201999-08-23023 August 1999
Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant
U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999
Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage
ML20211B0871999-08-20020 August 1999
Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723
U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999
Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired
ML20211A8931999-08-19019 August 1999
Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed
U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999
Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813
ML20210U3771999-08-12012 August 1999
Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen
U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999
Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729
U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999
Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809
ML20210N2961999-08-0909 August 1999
Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend
U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999
Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55
U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999
Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS
ML20210J0541999-07-30030 July 1999
Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files
U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999
Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS
U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999
Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131
U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999
Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71
U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999
Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790
ML20210A4401999-07-16016 July 1999
Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations
ML20209G7671999-07-12012 July 1999
Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed
ML20209D5691999-07-0707 July 1999
Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel
U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999
Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date
U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999
Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events
ML20196J9651999-07-0202 July 1999
Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements
ML20196J7131999-06-30030 June 1999
Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1
U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999
Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant
U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999
Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys
U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999
Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology
ML20196A3471999-06-16016 June 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999
Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)
ML20217C0871999-10-11011 October 1999
Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld
U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999
Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included
U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999
Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld
U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999
Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station
U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999
Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl
U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999
Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl
ML20212G6981999-09-20020 September 1999
Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability
05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999
Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events
U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999
Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed
05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999
Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments
U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999
Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl
U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999
Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7
U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999
Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage
ML20211B0871999-08-20020 August 1999
Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723
U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999
Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired
U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999
Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813
U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999
Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729
U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999
Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809
ML20210N2961999-08-0909 August 1999
Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend
U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999
Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55
U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999
Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS
ML20210J0541999-07-30030 July 1999
Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files
U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999
Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS
U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999
Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131
U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999
Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71
U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999
Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790
U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999
Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date
U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999
Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events
U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999
Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant
U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999
Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys
U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999
Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology
05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999
Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed
05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999
Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed
U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999
Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors
ML20209G7731999-05-27027 May 1999
Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted
U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999
Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs
U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999
Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5
U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999
Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in
U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999
Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl
U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999
Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases
U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999
Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired
U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999
Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License
U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999
Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response
U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999
Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program
U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999
Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)
U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999
Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)
05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999
Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed
U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999
Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation
U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999
Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired
1999-09-22
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059L6571990-09-19019 September 1990
Advises That Dp Hall No Longer Associated W/Facility Since Dec 1989.Mail Should Be Addressed to Js Perry
JSP-739-90, Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump1990-09-12012 September 1990
Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump
U-601729, Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn1990-08-27027 August 1990
Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn
JSP-676-90, Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event1990-08-23023 August 1990
Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event
U-601723, Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.711990-08-16016 August 1990
Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.71
U-601722, Forwards Reissued NPDES Permit IL00369191990-08-10010 August 1990
Forwards Reissued NPDES Permit IL0036919
U-601721, Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators1990-08-0808 August 1990
Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators
U-601716, Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))1990-08-0303 August 1990
Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))
U-601715, Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly1990-08-0202 August 1990
Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly
U-601708, Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 19891990-07-19019 July 1990
Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 1989
U-601702, Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990
Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20044A3001990-06-22022 June 1990
Forwards Update to 890817 Response to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Unisolable Piping Connected to RCS Identified & Evaluated to Determine Which Piping Could Be Subj to Stratified Flow Phenomena
ML20044A4601990-06-22022 June 1990
Provides Followup to 900622 Request for Waiver of Compliance Re Tech Spec Limiting Condition for Operation Concerning Standby Emergency Diesel Generator 1B.Rev to Attachment 1 of Original Request for Waiver Encl
ML20043H5021990-06-19019 June 1990
Requests Changes to License NPF-62,correcting Typos, Refs to Fsar,Testing to Be Done During Initial Plant Startup & Incorporating Revised Operating Power/Flow Map for Two Reactor Recirculation Loop Operation
ML20043G8221990-06-0707 June 1990
Provides Update to Util Response to Item 1 of Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.
ML20043F0591990-06-0606 June 1990
Forwards Endorsements 44-50 to Nelia Policy NF-261 & 25-31 to Maelu Policy MF-121 & 10 & 11 to Maelu Policy N-85 & M-85,respectively
ML20043D0531990-05-31031 May 1990
Forwards 1989 Annual Rept for Illinois Power Co & Soyland Power Cooperative,Inc
ML20043C7501990-05-25025 May 1990
Forwards Rev 20 to Illinois Power Nuclear Program QA Manual. Rev Evaluated by Util as Not Reducing Quality Program Commitments
ML20043B4891990-05-21021 May 1990
Informs NRC of Plant Initiatives for 1990 to Improve Corrective Action Program Effectiveness,In Response to SALP Rept & Violations Noted in Insp Rept 50-461/89-32. Centralized Commitment Tracking Sys Upgraded
ML20043B1141990-05-17017 May 1990
Suppls 900330 Response to Station Blackout Rule.Calculation of Heatup of Main Control Room Due to Loss of Ventilation Following Station Blackout Revised to Properly Account for Heat Sinks & Credit Existing Masonry Walls
ML20043D9901990-05-14014 May 1990
Responds to NRC 900413 Ltr Re Violations Noted in Insp Rept 50-461/90-02.Corrective Actions:Safety Evaluation Prepared & Reviewed for Level Instrumentation & Annunciators Identified in Updated SAR
ML20043A9811990-05-14014 May 1990
Notifies That Wc Metzner Resigned from Position of Licensed Operator W/Util,Effective 900430
ML20042E6181990-04-13013 April 1990
Updates 890406 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Condition Rept Initiated to Address Issue to Drain Instrument Air Filter Regulators
ML20012E8991990-03-27027 March 1990
Forwards Rev 9C to Physical Security Plan.Rev Does Not Decrease Effectiveness of Plan.Rev Withheld (Ref 10CFR73.21)
ML20012D9451990-03-20020 March 1990
Informs of Current Activities Re Restoration of Shutdown Svc Water (SX) Sys to Operability Following Cleaning of Div I HX Per Generic Ltr 89-13.SX Sys to Be Restored by Returning Sys Flows to Design Values
ML20012D9641990-03-19019 March 1990
Lists Present Levels of Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w)(2)
ML20012D9901990-03-19019 March 1990
Responds to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-461/89-38.Corrective Actions:Maint Supervision Added Critical Points to Existing Maint Work Requests & Preventive Maint Activities & Training Program Updated
ML20012D4321990-03-16016 March 1990
Responds to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Detailed Analytical Review & Proposed Schedule for Implementing Required Actions Scheduled to Be Completed by 900625
ML20012A2771990-02-28028 February 1990
Forwards Final Response to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded Case Circuit Breakers. Actions Taken by Util Have Established That All safety-related Circuits Remaining in Stock Can Be Verifiably Traced to Mfg
ML20012C2511990-02-23023 February 1990
Responds to Ninth SALP Rept 50-461/89-01 for Sept 1988 - Oct 1989.Rept Concluded That Overall Performance Satisfactory & Identified Strengths in Areas of Emergency Preparedness
U-601611, Notifies That Gd Setser Resigned Position W/Util,Effective 9002131990-02-20020 February 1990
Notifies That Gd Setser Resigned Position W/Util,Effective 900213
ML20011F6501990-02-12012 February 1990
Responds to NRC 900112 Ltr Re Violations Noted in Insp Rept 50-461/89-37.Corrective Actions:Radiation Protection Technicians Provided W/Method for Identifying Radiation Work Permits Which Change Radiological Conditions
ML20006C6721990-02-0505 February 1990
Responds to NRC 891207 Ltr Re Violations Noted in Insp Rept 50-461/89-35.Corrective Actions:Emergency Planning Bulletin Issued to All Emergency Response Organization Members Emphasizing Importance of Attending Required Training
ML20006D1951990-01-30030 January 1990
Responds to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Util Intends to Discontinue Sending Ack Upon Receipt of Vendor Manual Matls
ML20006A8291990-01-23023 January 1990
Forwards Rev 3 to Inservice Exam Plan. Changes to Text Described.Approval of Changes by 900601 to Allow Time to Plan Refueling Outage Activities Re Inservice Exam Program Requested
ML20005H2711990-01-12012 January 1990
Advises That Licensee Will Remove Terminal Blocks for Control Circuits within 100% Relative Humidity Harsh Environ at Plant by End of Second Refueling Outage Currently Scheduled to Begin in Sept 1990
ML20006A7121990-01-10010 January 1990
Forwards Revised Pages to 1987 Radiological Environ Monitoring Rept
ML20005F0001990-01-0505 January 1990
Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Util Revised Plant Operating Procedures for Hpcs,Lpcs & RHR Pumps & Vibration Monitoring Program Expanded to Include ECCS Pumps at Plant
ML20006A7921989-12-29029 December 1989
Responds to 891129 Ltr Which Forwarded Insp Rept 50-461/89-31,requesting Identification of Actions Underway to Ensure That Falsification of Interim Security Screening Records Would Be Detected in Timely Manner in Future
U-601573, Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently1989-12-29029 December 1989
Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently
ML20005E0891989-12-27027 December 1989
Advises That Revised Fitness for Duty Program Will Meet 10CFR26 Requirements,Effective 900103.Util Intends to Test for Substances Listed at Indicated cut-off Levels
ML20006C2961989-12-21021 December 1989
Responds to NRC 891121 Ltr Re Violations Noted in Insp Rept 50-461/89-32.Corrective Actions:Review Performed to Identify Surveillances Which Require Lifting of Leads in Main Control Room
ML20005D9521989-12-15015 December 1989
Forwards Monthly Operating Rept for Nov 1989 for Clinton Power Station Unit 1 & Corrections to Oct 1989 Rept
ML20005E7781989-12-12012 December 1989
Advises That False Alarm Criteria Will Be Implemented by 900131,per Insp Rept 50-461/89-31.Util Established New Criterion of 100 False Alarms for Security Sys in 24 H Period
ML20011D1741989-12-0707 December 1989
Informs of Changes Made to Util Fitness for Duty Program Procedure.Change Specifies That Supervisor - Medical Programs,Assistant Director - Labor Relations or Manager - Nuclear Planning & Support Will Generate Computer List
ML19332F0071989-11-30030 November 1989
Responds to Violations Noted in Insp Rept 50-461/89-29. Corrective Actions:Preventive Maint for Ph Monitor & Liquid & Gaseous Gamma Monitors Added to Appropriate Tracking Programs
ML19332E9431989-11-29029 November 1989
Forwards Executed Amends 4 & 5 to Indemnity Agreement B-91, Reflecting Change in Ownership of License,Effective 890327
ML19332D5031989-11-27027 November 1989
Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Results of Util Review & Reporting of Status of Implementation of USIs Encl
ML19332D0291989-11-22022 November 1989
Informs That Effective 891201,JS Perry Will Assume Responsibility for Mgt of Nuclear Program at Util
ML19332D0431989-11-22022 November 1989
Informs NRC of Change in Schedule for Providing Info Re Environ Qualification Testing of Terminal Blocks for Control Circuits of Conax Electrical Penetrations.Wyle Labs Test Results & Util Review of Results Will Be Sent by 900112
1990-09-19
[Table view] |
Text
, - -
e U-600253 L30- (10-08) 1A.120
/LLINDIS POWER COMPANY -
October 8, 1985 Docket No. 50-461 Director of Nuclear Reactor Regulation Attn: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Clinton Power Station Unit 1 Preservice Inspection Program Relief Requests License Condition No. 12 Confirmatory Issue No. 67 The Clinton Power Station (CPS) Safety Evaluation Report (SER)
Section 5.2.4 including Supplements #1 and #2, identified requiremen;;s to identify all requests for relief from impractical ASME Code requirements with supporting justification. This letter submits those relief requests and supplements the Preservice Inspection Program originally sent to you by our Letter U-0422 dated February 23, 1982, and as amended March 4, 1985.
The attached relief requests constitute conditions that were found during performance of Preservice Inspection which require requests for relief. These conditions are as follows: (1) eleven welds located below the surface of the suppression pool, (2) two welds located within wall penetrations, and (3) one weld located underneath component supports. The relief requests specifically identify the welds involved and provide justification for deviating f rom the specific requirements of the ASME Code. Please contact us should you have any questions on this matter.
Sincerely yours, s .
I F. A. S;. nge erg Manager - Licensing and Safety JLP/kaf Attachment ec: B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC [
Illinois Department of Nuclear Safety 0510100045 051000 PDR ADOCK 05000461 E PDR
,.s._._.______ .
PRESERVICE INSPECTION ,
~ NONDESTRUCTIVE EXAMINATION OF PIPING WELDS l- RELIEF REQUEST ,
i I. Weld (s) Identification:
A.; System: Residuni Heat Renval (RH) l B. Wald Number: 1RH-22-6-2 and 1RI-22-6-4 and associated longitudinal seam f
! C. Piping Line Numbers, .1mI3n l
D. ASME.Section III Code Class: 2 E. Line Size: 12 inches ;
F. Materials: Staininss steel SA-358 Gr. 304 G. Piping. Nominal Wall Thickness: 0.625 inch R. Function: lhislinedirectsdisclurgefromRHIkeatexchangerinlet relief valve to the suppression pool. *1his line is the last section of piping prior to suppression pool discharge and is open ended.
II. Relief from: -
A. ASME Code Requirements: Er-2100 #nFsrRvTm msnmrinn s B. Reason for Relief 'this lino is an oom onded ninina and thane welds are located below the surface of the sonoression oool. Any leaknoa f'mn the wlds wuld not be detrimmtal to systm operation in maintaining the plant in a cold shutdown or mitigating the consequences of an accident.
C. Alternate Preservice Inspection: None -
f Sketch frce M05-1075 P&lD -
lief Valve f ( ( . Containment Wall ,
1 I Inlet .
? rn .
I k .RH Heat Exchanger A suppression " Line IRH30CA l Pool y 9
-a.- - - _ - ._ - _... .. - . - - - - -
t PRESERVICE INSPECTION NONDESTRUCTIVE EXAMINATION OF PIPING WELDS RELIEF REQUEST I.. Weld (s) Identification:
A.! System: Residual Heat Romnval (Rm B. Weld Number: 1RH-22-6-3 and associated longitudinal seam C. Piping Line Number: 1 RIG 0CA
_ D. ASME Section III Code Class: 2 E. Line Size: 12 inches Carbon Steel - SA 106 Gr. B F. Material: Dissimilar m,terial stainioss sennl - m 1sa cr. 104 CS - 0.500 inch G. Piping Nominal Wall Thickness: SS - 0.625 inch H. Function: This line directs discharge from RH heat exchancer inlet relief valve to the suppression pool. This line is the last section of i
pipirq prior to suppression pool discharge and is open ended.
II. Relief from: -
A. ASME Code Requirements: IWC-2100 PRESERVICE INSPECTION B. Reason for Relief: This line is an open ended piping and this weld is located below the surface of the suppression pool. Any leakage from this weld would not be detrimental to system operation in maintaining the plant in a cold shutdown condition.or mitigating the consequences of an accident.
, C. Alternate Preservice Inspection: Ennn Sketch from M05-1075 P51D Relief Valve
( ( Containment. wall Inlet
'r3 . .
Rllllcat Exchanger A suppression
. . Pool y Line IRIG0CA
-- w, y- . - - ,ee am s omee+ - ~ + .m.e+. ,,-mme-PRESERVICE INSPECTION NONDESTRUCTIVE EXAMINATION OF PIPING WELDS RELIEF REQUEST
- 1. Weld (s) Identification:
A.l System: Residual Heat Rcmoval 0 01)
B. Weld Number: 1RH-28-6 and issocinted longitudinal seam C.* Piping Line Number: 1RH30CB D. ASME Section III Code Class: 2 E. Line Size: 12 inches Carbon Steel - SA 106 Gr. B F. Material: Dissimilnr m,enrini - Stainless Steel - SA 358 Gr. 304 CS - 0.500 inch G. Piping Nominal Wall Thickness: ss --0.625 inch H. Function: This line directs discharge frcm RH heat exchanger inlet relief valve to the suppressica pool. This line is the last section of pipir(prior to suppression pool discharge and is open ended. See sketch below.
II. Relief from: ,
A. ASME Code Requirements: IWC-2100 PRESERVICE TNSPECPTON B. Reanon for Relief: 'Ihis line is an open ended pining nnd this weld is located below the surface of the suppression pool. Any leaknge from this weld would not be detrimental to systan operation in maintaining the plant in a cold shutdown condition or mitigating the consequences of an accident.
C. Alternate Preservice Inspection: None Sketch Fmn M05-1075 P&ID Relief Valve
( ( -Containment wall Inlet Ril IIcat Exchanger B Suppression
'. Pool y y Line 1RIl30CB
a g
PRESERVICE INSPECTION NONDESTRUCTIVE EXAMINATION OF PIPING WELDS RELIEF REQUEST I. Weld (s) Identification:
A .', S y s t e m : Residual Heat Rcmoval (RH)
B. Weld Number: 1RH-28-6-3 and 1RH-28-6-4 and associated longitudinal seam.
C. Piping Line Number: 11000CB
- D. ASME Section III Code Class: 2 E. Line Size: 12 inches F. Material: Stainless Steel SA-358 Gr.304 G. Piping Nominal Wall Thickness: 0.625 inch H. Function: This line directs discharge from RH heat exchanger inlet relief valve to the suppression pool. This line is the last section of piping prior to suppression pool discharge and is open ended. See sketch below. .
II. Relief from: -
A. ASME Code Requirements: IWC-2100 PRESERVICE INSPECTION B. Reason for Relief: This line is an open ended piping and these welds are located below the surface of the suppression pool. Any leakage from these welds muid not be detrimental to system operation in tinin-taining the plant in a cold shutdown or mitigating the consequences of an accidcut.
C. Alternate Preservice Inspection: None Sketch frcm M05-1075 P&ID Relief Valve Containment Wall x (
V Inlet.
n .
Ril llent Exchanger B Suppression i > ' Pool y Line 1 RIG 0CB
u ., . u. .a_ .a ;.un - -
1 d 1- - l -- -
t' -
PRESERVICE INSPECTION .
{L . N ii
- r. NONDESTRUCTIVE EXAMINATION OF PIPING WELDS ,
[ -RELIEF REQUEST \s I.. Weld (s) Identification:
(
A.-System: Residual Hent Removal (RH)
B. Weld Number: 1RH-25-9-3 -
CE Piping _Line! Number:. 1RH02AB \
u DI ASME -Section III Code Class : 2 W X$
x El Line Size: 14 inches- ,'
, , ,q_ J F.1 Material:-' Carbon Steel SA-106 Gr.B L;- 9 sy G.'i. Piping Nominal Wall Thickness: 0.438 inch '
(
,p.,
.1 . <
.H. Function: his is a discharce line of RH pump -B
.j. h,
- '4- 'a -
. j. t -
. .t
- 1
.y ,
l-s II.' Relief'from:
A. ASME Code Requirements: IWC-2100 Preservi'ce Inspection B. Reason for Relief: his weld is located inside the Auxil'iary '
Building wall penetration sleeve number 1AB0011 and is inaccessible to
?; perform any nondestructive examination. .
[ t
?
4:.
' (
- C. ' Alternate .Preservice Inspection:- None '
- t. ) N
n j: . - g ;. -
II '. ,
,s e -
- .~.. .
_t_.- . . _ _ .
s- u . =:; - - -
=======--- -
= -
+. ,. 2 -
w e ,, .
e .
f& ng
(
l
[ [+
,.4
^ .
y r H>
- PRESERVICE INSPECTION Oy
- NONDESTRUCTIVE EXAMItATION OF PIPING WELDS
- . j$'. g "~
p K" 'i gh,g %g .
RELIEFREQ(UEST. m.J I. Weld (s)2 Identification:
A.(System: NeactorCoreIsolationCooling-(RI)
. x, .
~
B. Weld. Numbed:- 1RI-4-6-2 n.!!.w. ., .
'^ .
!C. Eiping Line Number:
1RIO80 =
m.
r D.lASMEiSection III Code. Class: 2 E.~Line Size: 12 inches' .
i 3
,. , , F. Material: Carbon Steel SA-106 Gr. B w
e i ~%s..
v 4,
{ G..P,iping Nominal Wall' Thickness: 0.500 inch H.' Function: This line prouides an exhaust for RI turbine and diacharnes into the suppr'ession pool.
A II. Relief from:
A. ASME Code Requirements: IWC-2100 Preservice Inspection
+ -
Q c.
(g[1, [,B.ReasonforRelief: This line is an open ended piping and this weld pb -
is located below the-surface of the suppression pool. Any leakage from
. 1,.
this wid would not be detrinental to systen operation. Iater Edition Y of ASFE Fiction XI exonot this wcld from Inservice Insaection (ISI).
I~
Re ~1980 Edition Winter 81 Addenda Subsection IWC-1zzJ (b).
C. Alternate :Preservice Inspections- Nona u
m, le i l'
i I
g.
$I q t .7 ' .
fr 3
'~ ,9 n
, .L . . , . . . - , , , . - , . - - - - . . . , . . _ . . . . .-.,.,,,,-,._,,_n.,.a,..-_,, .,--.,----.,--..,,,n_,._,,.,,.._,,
. = _ - -~ ___ . _ ._ _ __ -
]
PRESERVICE INSPECTION NONDESTRUCTIVE EXAMINATION OF PIPING WELDS RELIEF REQUEST I. Weld (s) Identification:
A. System: Reactor Core Isolation Cooling (RI)
B. Weld Number: 1RI-4-7-2 C. Piping Line Number: 1RIO8C D. ASME Section III Code Class: 2 E. Line Size: 12 inches F. Material: Stainless Steel SA-358 Gr. 304 G. Piping Nominal Wall Thickness: 0.625 inch H. Function: his line provides an exhaust for RI turbine and dis-charges into the suppression pool.
II. Relief from:
A. ASME Code Requirements: IWC-2100 Preservice Inspection B. Reason for Relief: This line is an open ended piping and this weld is located below the surface of the svapression pool. Any leakage from this weld ux:1d not be detrimental to systcm operation. Iater Edition of AfBE Section XI exanne thia weld from Inservice Inspection (ISI) .
Re: 1980 Edition Winter 81 Addenda Subsection IWC-1220(b).
C. Alternate Preservice Inspection: None i:
e D
.~ -
_ . . _ . , u _. . _ -. - .-
p -
l-. _
c b -
lPRESERVICE' INSPECTION L
1 NONDESTRUCTIVE EXAMINATION OF PIPING WELDS
_ ' RELIEF REQUEST.
-I. - Weld (s); Identification:
A.iSystem: Suppression Pool Cleanup and Transfer (SF)
B. Weld Number: ISF-1-1-2 C. Piping Line Number:- ISF02A
- D. ASME Section III Code Class:
4 2
. . E.LineiSide:- 12 inches
} : F. Material':T Stainless Steel SA 358 Gr. 304 C1. 1
' G. Piping Nominal ~ Wall ~ Thickness:
.. 0.375 inch e
H. Function:g7his line provides a suction from the' suppression pool-j _
for'the SF System.
'II. Relief from:
- [ A. ASME Code Requirements: IWC-2100 Preservice Inspection.
B~. Reason for-Relief: This line is an open ended piping and this weld is located below the surface of the suppression pool. Any leakage from this weld would not be detrimental to systen operation. Later Edition of ASE Section XI exannt this ueld from Inservice Inspection (ISI)
Re: 1980 Edition Winter 81 Addenda Subsection IWC-1220 (b)
- C. Alternate Preservice Inspection:- None .
g.
.r-4 0
..F.:a = =
t.. .
i PRESERVICE INSPECTION v-NONDESTRUCTIVE EXAMINATION OF PIPING WELDS RELIEF REQUEST
-1. Weld (s) Identification:
A} System: Sucoression Pool and Transfer (SF)
B. Weld. Number: -TSF-3-4-4 C. Piping Line Number: ISF01G D. ASME Section III Code Class: 2 E. Line Size: 12 inches-Carbon Steel - SA 106 Gr. B F. Material: Dissimilar material - Stainless Steel - SA 312 Gr. TP304
-CS-0.375 inch G. Piping Nominal Wall Thickness: SS -0.375 inch.
H. Function: This line provides a discharge form the SF system into the suooression nool.
II. Relief from:
A. ASME Code Requirements: 11C-2100 Preservice Inspection
- B. Reason for Relief: . This line is an open ended piping and this L weld is located below the surface of the suppression pool. Any leak-i i- age from this weld would not be detrimental to system operation. Later i
f j Edition of ASME Section XI exmpt this weld from Inservice Inspection (ISI).
Re. 1980 Edition Winter 81 Addenda Subsection IWC-1220(b) j c.* Alternate Preservice Inspection: None <
}-
1 f
O ,
- - n_ _
.- a e _ __ . _ _. _
+
PRESERVICE INSPECTION NONDESTRUCTIVE EXAMINATION OF PIPING WELDS RELIEF REQUEST I. Weld (s) Identification:
A. System:- Suppression Pool Cleanup and Transfer (SF)
~
7 B. Weld Number: ISF-3-5-A01 C. Piping Line Number: ISF01G D. ASME Section III Code Class: 2 E. Line Size: 12 inches F. Material: Stainless Steel SA-312 Gr. TP 304 G. Piping Nominal Wall Thickness: 0.375
- 11. Function: This line provides a discharge from the SF Systen into the sunpressim nool.
6 II. Relief from:
A. ASME Code Requirements: IW,-2100 Preservice Inspection B. Reason for Relief: This line is an open ended piping and this weld
, in inenend boirw the surface of the suppression pool. Any leakage from this weld would not be detrimental to system operation. Later Edition of ASME Secrim XI prormt this weld from Inservice Inspection (ISI) .
RE: 1980 Edition Winter 81 Addenda Subparagraph IWC-1220 (bT.
C. Alternate Preservice Inspection: None 4
+
4 I
y7 m.
A.; System: Drywell Cooling J,
B. Ueld Number: 1VP-6-1-5 C. Piping Line Number: 1VP02BB D. ASME Section III Code Class: 2 E. Line Size: 10 inches F. Material: Carbon Steel SA-106 Gr. B G. Piping Nominal Wall Thickness: 0.365 inch H. Function: This line provides chilled water to the drvwell coolers.
II. Relief from:
A. ASME Code Requirements: IWC-2100 Preservice Inspection B. Reason for Relief: _'Ihis weld is located inside the containment
- penetration sleeve number IW107. Later Edition of ASME Section XI ~
- code excmpt this weld from Inservice Inspection (ISI). Re
- 1980 Edition Winter 81 Addenda Subsection IWC-1220(b)
, C. Alternate Preservice Inspection: None
7m. ,_ . _ _ _ . .
PRESERVICE INSPECTION NONDESTRUCTIVE EXAMINATION OF PIPING WELDS RELIEF REQUEST I. Weld (s) Identification:
A.; System: Reactor Core Isolation Cocling (RI)
B. Weld Number: 1RI-13-8AQ1 C. Piping Line Number: 1RIO3C D. ASME Section III Code Class: 1 E. Line Size: 4 inches F. Material: Carbon Steel SA-333 Cr. 6 i
G. Piping Nominal Wall Thickness: 0.438 inch H. Functions. This ifne provides the cooling water to the reactor pressure vessel.
II. Relief from:
A. ASME Code Requirements: IWC-2100 Preservice Inspection B. Reason for Relief: This weld is located underneath of a ccxuponent support and is inaccessible because support is welded and its design does 1
not allow for disassmbly. The rcmoval and reinstallation of this support wuld require grinding and rewelding instead of disassably as found with other supports.
C. Alternate Preservice Inspection: None f
4
7:
[,;.'._,t M Performed under Section III ASME SECTION III ASME SECTION.III WELD NUMBERS
1RH-28-6-2 RT RT 1RH-28-6-3 RT RT & UT Thickness only 1RH-28-6-4 RT RT & UT Thickness only 1RH-25-9-3 RT RT 1RI-4-6-2 RT RT & UT Thickness only 1RI-4-7-2 RT s RT ISF-1-1-2 RT RT t
ISF-3-4-4 RT RT ISF-3-5AQ1 RT RT IVP-6-1-5 RT RT 1RI-13-8AQ1 RT & MT/PT RT, PT & UT Thickness only
- The weld numbers listed correspond to the weld numbers identified in the relief requests.
NDE - Non Destructive Examination RT - Radiographic Testing UT - ' Ultrasonic Testing PT - Dye penetrar.t Testing i
