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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H6231999-10-18018 October 1999
Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs
ML20217J4331999-10-15015 October 1999
Forwards Insp Rept 50-461/99-19 on 990913-17.One Violation Re Individual Failure to Follow Radiation Protection Procedures When Accessing High Radiation Area Noted & Being Treated as Noncited Violation
U-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999
Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)
ML20217C0871999-10-11011 October 1999
Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld
U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999
Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included
U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999
Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld
U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999
Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station
ML20217A9881999-10-0101 October 1999
Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities
ML20217A7361999-10-0101 October 1999
Forwards Insp Repts 50-461/99-14 & 50-461/98-12 on 990729-0908.Two Violations Identified,One Re Failure to Place Control Switch in Proper Position to Identify Piece of out-of-svc Equipment & Being Treated as NCVs
ML20217J1251999-09-30030 September 1999
Refers to Investigation 3-1997-040 Conducted from 971028- 980921 & Forwards Nov.Investigations Determined That During Jan 1997,supervisor Qv Dept Discriminated Against Qv Inspector in Retaliation for Inspector Contacts with NRC
ML20217J1421999-09-30030 September 1999
Refers to Investigation 3-97-040 Conducted from 971028- 980921 & Forwards Nov.Investigation Concluded That Recipient Engaged in Deliberate Misconduct in That Recipient Discriminated Againt Qv Inspector for Having Contacted NRC
ML20212G6751999-09-22022 September 1999
Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station
U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999
Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl
U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999
Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl
ML20212G6981999-09-20020 September 1999
Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability
ML20217H3421999-09-17017 September 1999
Forwards Request for Addl Info Re Licensee 990723 Application for License Transfer & Conforming Administrative License Amend.Response Requested within 20 Days of Receipt of Ltr
05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999
Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events
05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999
Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments
U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999
Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed
ML20211Q2671999-09-0808 September 1999
Informs That NRC Tentatively re-scheduled Initial Licensing Exams for License Operator License Applicants During Weeks of June 5 & 12,2000.Validation of Exams Will Occur at Station During Weeks of May 15,2000
U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999
Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl
U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999
Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7
ML20211D2201999-08-23023 August 1999
Confirms 990817 Telcon with J Neuschwanger & D Mcneil Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Plant
U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999
Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage
ML20211B0871999-08-20020 August 1999
Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723
U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999
Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired
ML20211A8931999-08-19019 August 1999
Forwards Insp Rept 50-461/99-13 on 990611-0728.Two Violations Noted & Being Treated as Ncvs.Violation Re Three Examples Where Licensee Procedural Requirements for Minor Maint Work Were Not Followed
U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999
Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813
ML20210U3771999-08-12012 August 1999
Forwards Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amend & Opportunity for Hearing Re Amend Request for Approval of Clinton Power Station License NPF-62 Transfer to Amergen
U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999
Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729
U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999
Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809
ML20210N2961999-08-0909 August 1999
Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend
U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999
Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55
U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999
Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS
ML20210J0541999-07-30030 July 1999
Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files
U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999
Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS
U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999
Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131
U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999
Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71
U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999
Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790
ML20210A4401999-07-16016 July 1999
Forwards Insp Rept 50-461/99-10 on 990422-0610.Four Violations Being Treated as Noncited Violations
ML20209G7671999-07-12012 July 1999
Ack Receipt of Encl FEMA Correspondence ,which Transmitted FEMA Evaluation Rept for 981118 Biennial EP Exercise at Clinton Power Station.No Deficiencies Were Observed
ML20209D5691999-07-0707 July 1999
Forwards Insp Rept 50-461/99-12 on 990607-11.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Observations of Work in Progress & Interviews with Personnel
U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999
Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date
U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999
Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events
ML20196J9651999-07-0202 July 1999
Confirms Discussion Between Members of Staffs to Conduct Meeting on 990714 at Clinton Power Station to Discuss Results of Restart Insp & Licensee Progress in Addressing Remaining Long Term C/A Actions to Sustain Improvements
ML20196J7131999-06-30030 June 1999
Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1
U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999
Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant
U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999
Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys
U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999
Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology
ML20196A3471999-06-16016 June 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/99-11 Issued on 990430.Corrective Actions Will Be Examined During Future Inspections
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARU-603280, Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)1999-10-12012 October 1999
Forwards Rev 27 to Clinton Power Station Physical Security Plan,Iaw 10CFR50.54(p).Encl Withheld from Public Disclosure, Per 10CFR50.54(p)
ML20217C0871999-10-11011 October 1999
Forwards Proprietary Attachment Inadvertently Omitted from Encl 2 to Submitting Responses to NRC RAI Re License Transfer Application for Plant.Proprietary Encl Withheld
U-603276, Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included1999-10-0808 October 1999
Forwards Rev 8 to CPS USAR, Which Includes Changes from 970701 Through 990630 & Available Changes Approved After 990630 That Reduce Overall Burden of Submittal Changes for Forthcoming Reporting period.10CFR50.59 Rept Included
U-603279, Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld1999-10-0707 October 1999
Forwards non-proprietary & Proprietary Responses to NRC RAI Re License Transfer Application for Plant.Attached Responses Also Respond to Comments of Environ Law & Policy Center Dtd 990920.Proprietary Encl Withheld
U-603275, Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station1999-10-0707 October 1999
Provides Updated Illinois Power Rept on Status of Decommissioning Funding for Clinton Power Station
U-603272, Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl1999-09-22022 September 1999
Provides Update to Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. 3-D Monicore & Station Security Sys remediated.Y2K Readiness Disclosure for Cps,Encl
U-603225, Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl1999-09-20020 September 1999
Provides Closure of Util Commitments Re Ci Cv Noted in Previous Ltr to Nrc.Basis for Expecting Valves to Remain in leak-tight Condition Throughout Operating Cycle & Basis That Justifies Not Performing mid-cycle Leak Testing,Encl
ML20212G6981999-09-20020 September 1999
Requests That NRC Reject Proposed License Transfer for Clinton Power Station & That NRC State That Public Interest in Safe Nuclear Power Industry Will Not Be Subordinated to Interest in Maximizing Profit by Limiting Liability
05000461/LER-1996-010, Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events1999-09-13013 September 1999
Forwards LER 96-010-01, Plant Shutdown Due to Unidentified RCS Leakage from Degraded Reactor Recirculation Pump Seal Greater than TS Limit. Revised Rept Includes Cause of Event,Corrective Actions & Discussion of Similar Events
U-603269, Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed1999-09-10010 September 1999
Certifies That DB Livingston,License OP-31136,successfully Completed Facility Licensees Requirements to Be Licensed as Ro,Per 10CFR55 & Has Need for RO License to Perform Assigned Duties.Five Significant Control Manipulations,Listed
05000461/LER-1999-011, Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments1999-09-10010 September 1999
Forwards LER 99-011-00 Re Improper Restoration of a APRM Which Caused Monitor to Not Meet Seismic Qualification Requirements.Rept Contains Listed Commitments
U-603229, Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl1999-08-25025 August 1999
Provides Response to NRC RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Dtd 990528.Rev 0 to Calculation IP-M-0556 & Rev 0 to Calculation IP-M-0570,encl
U-603243, Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.71999-08-23023 August 1999
Forwards Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Util Performing Testing of ESF Ventilation Sys Charcoal Samples Using ASTM D3803- 1989 Methodology as Required by TS 5.5.7
U-603258, Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage1999-08-23023 August 1999
Forwards ISI Summary Rept, IAW ASME Section Xi,Article IWA-6000.Summary Rept Addresses ISI Activities Performed at Plant from 950429-990527,including Extended Sixth Refueling Outage
ML20211B0871999-08-20020 August 1999
Responds to J Hopkins Inquiry Re Application for Order Consenting to License Transfer & Approving Conforming Administrative License Amend Filed by Ilpr & Amergen Energy Co on 990723
U-603259, Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired1999-08-19019 August 1999
Provides Notification That Cl Kreidler Has Resigned Position with Util,Effective 990818.License Status Should Be Changed to Expired
U-603253, Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 9908131999-08-16016 August 1999
Notifies NRC That Je Smith,License SOP-30819-1,has Resigned from Position with Ilpr Effective 990813.Status of License Should Be Changed to Expired,Effective 990813
U-603250, Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 9907291999-08-10010 August 1999
Notifies NRC That Ma Freihofer (License SOP-31296-1) Has Resigned from Position with Illinois Power Effective 990729 & License Status Should Be Changed to Expired Effective 990729
U-603249, Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 9908091999-08-10010 August 1999
Notifies NRC That He Bouska (License SOP-3055-1) Has Resigned from Position with Illnois Power Effective 990809. & License Status Should Be Changed to Expired Effective 990809
ML20210N2961999-08-0909 August 1999
Forwards Form of Nuclear Decommissioning Master Trust Agreement,Per CPS Application for License Transfer & Conforming Administrative License Amend
U-603248, Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR551999-08-0606 August 1999
Requests Unrestricted License for Kc Scott,License SOP-31532.Scott Has Successfully Completed Facility Licensee Requirements to Be Licensed as Operator/Senior Operator Per 10CFR55
U-603236, Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS1999-08-0202 August 1999
Forwards Revised Data Point Ref File Sheets for Clinton Power Station Computer Points That Input to ERDS
ML20210J0541999-07-30030 July 1999
Forwards Three Original Signature Pages of Gr Rainey for Application for License Transfer & Conforming Administrative License Amend, for NRC Files
U-603178, Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS1999-07-29029 July 1999
Forwards Four ASME Section XI Relief Requests Re Performance of non-destructive Exams for First 120-month Inservice Insp for CPS
U-603237, Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 0001311999-07-28028 July 1999
Informs That Util Will Provide Response to fire-related Questions One & Two of NRC RAI Re CPS Ipeee,By 000131
U-603240, Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.711999-07-27027 July 1999
Forwards Clinton Power Station semi-annual Fitness for Duty Rept for Period Ending 990630,IAW 10CFR26.71
U-603235, Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.7901999-07-23023 July 1999
Forwards Application for License Transfer & Conforming Administrative License Amend for OL NPF-62.Proprietary & Nonproprietary Asset Purchase Agreement Encl.Proprietary Info Withheld,Per 10CFR2.790
U-603231, Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date1999-07-0707 July 1999
Forwards Summary of Status of Plan for Excellence (Pee) Initiatives & Clinton Power Station (CPS) 1999 Business Plan.Encl Documents Provide Status & Disposition for Actions Not Completed to Date
U-603214, Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events1999-07-0606 July 1999
Forwards Results of Analysis Performed on Recently Completed Vendor Contracts,Per GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events
U-603218, Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant1999-06-28028 June 1999
Provides Final Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Attachment Provides Y2K Readiness Disclosure for Plant
U-603212, Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys1999-06-24024 June 1999
Forwards Response to NRC 990315 Telcon Re Proposed Amend of License NPF-62,implementing Feedwater Leakage Control Sys Mode of RHR Sys
U-603227, Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology1999-06-24024 June 1999
Provides Updated Rept on Status of Decommissioning Funding for Plant.Updated Rept Provides Min Decommissioning Fund Estimate,Per 10CFR50.75(b) & (C) Utilizing NUREG-1307,Rev 8 Methodology
05000461/LER-1999-007, Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed1999-06-12012 June 1999
Forwards LER 99-007-00,re Design Error Causing Main Steam Isolation Valve Leakage Control Sys to Be Outside Design Basis.Commitment Made by Util,Listed
05000461/LER-1999-008, Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed1999-06-12012 June 1999
Forwards LER 99-008-00,re Failure of Motor Driven Reactor FW Pump Regulating Valve.Commitment Made by Util,Listed
U-603213, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors1999-05-28028 May 1999
Responds to NRC Ltr Re Violations Noted in Insp Rept 50-461/99-01.Corrective Actions:Calculation 19-AK-05, Calculation for DG Load Monitoring, Was Revised Using Correct Horsepower for Hydrogen Mixing Compressors
ML20209G7731999-05-27027 May 1999
Forwards Copy of Final Rept for 981118,Biennial Radiological Emergency Preparedness Exercise for Clinton Nuclear Power Station.No Deficiencies Were Noted
U-603207, Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs1999-05-13013 May 1999
Provides Util Rept Confirming Completion of Actions Required by NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs
U-603201, Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.51999-05-0505 May 1999
Forwards 4-yr Updated Certification Rept for Plant Training Simulator.Nrc Form 474, Simulation Facility Certification Also Encl Which Was Developed in Accordance with Reg Guide 1.149 & Ansi/Ans Std Ansi/Ans 3.5
U-603196, Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in1999-04-27027 April 1999
Provides Notification That Util Has Completed Thermo-Lag 330-1 Fire Barrier Corrective Actions as Described in 970619 & s in Addition to Repair of Butt Joint Described in
U-603205, Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl1999-04-27027 April 1999
Forwards Annual Radioactive Effluent Release Rept for Clinton Power Station for Period Jan-Dec 1998. Rev 17 to ODCM for Clinton Power Station, Also Encl
U-603197, Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases1999-04-24024 April 1999
Provides Details of Other Activities Being Taken as Part of CPS Plan for Excellence Re Ensureing That CPS Physical Plant & Functional Characteristics Are Consistent with & Are Being Maintained IAW CPS Design Bases
U-603194, Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired1999-04-15015 April 1999
Provides Notification That Ta Staber,License SOP-31298,has Resigned Position,Effective 990401.License Status Should Be Changed to Expired
U-603189, Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License1999-04-0505 April 1999
Requests That Status of License SOP-31187-1,for Le Anderson, Be Changed to Expired,Per 10CFR50.74.Util Determined That Individual No Longer Has Need for SRO License
U-603190, Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response1999-04-0202 April 1999
Provides Update for Certain 10CFR50.74(f) Info Addressed in Licensee 980619 Submittal,But Not Included in Final Response
U-603185, Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program1999-03-30030 March 1999
Forwards Response to NRC RAI Re CPS GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs, Program
U-603186, Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)1999-03-29029 March 1999
Forwards Rept on Status of Clinton Power Station Decommissioning Funding,Iaw 10CFR50.75(f)
U-603184, Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)1999-03-26026 March 1999
Submits Info Re Current Levels of Property Insurance & Sources of Insurance for CPS as Listed,Per 10CFR50.54(w)(3)
05000461/LER-1999-005, Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed1999-03-15015 March 1999
Forwards LER 99-005-00,re Inoperability of Standby Gas Treatment Sys Train a Caused by Inadequate Design of Control Circuit.Commitments Listed
U-603165, Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation1999-03-12012 March 1999
Forwards Revised Data Point Ref File Sheet for Clinton Power Station Computer Point That Inputs to Erds.Change Necessary to Support Plant Mods to Drywell Floor Drain Instrumentation
U-603179, Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired1999-03-10010 March 1999
Provides Notification That RG Giuliani & R Zacholski,No Longer Have Need for Operating License.License Status Is Therefore Requested to Be Changed to Expired
1999-09-22
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059L6571990-09-19019 September 1990
Advises That Dp Hall No Longer Associated W/Facility Since Dec 1989.Mail Should Be Addressed to Js Perry
JSP-739-90, Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump1990-09-12012 September 1990
Requests Expedited Review & Approval of Proposed Change to Emergency Tech Specs Re Div III Nuclear Sys Protection Sys Inverter Concerning Inoperability of Emergency Shutdown Svc Water Sys Pump
U-601729, Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn1990-08-27027 August 1990
Notifies That Bn Chambers Permanently Reassigned to Position Not Requiring Operator License.Certification of Chambers Need to Hold License Previously Provided by Dp Hall Withdrawn
JSP-676-90, Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event1990-08-23023 August 1990
Responds to 900725 Notice of Violation & Proposed Imposition of Civil Penalty Documented in Insp Rept 50-461/90-09. Corrective Action:Critique Initiated to Identify Precise Causes & Contributing Factors Leading to Event
U-601723, Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.711990-08-16016 August 1990
Forwards Results of fitness-for-duty Program for 900103-0630,per 10CFR26.71
U-601722, Forwards Reissued NPDES Permit IL00369191990-08-10010 August 1990
Forwards Reissued NPDES Permit IL0036919
U-601721, Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators1990-08-0808 August 1990
Provides Response to Re Process for Requalification Exam Security Agreements.Security Agreement Forms Revised to Direct Individuals Not to Participate in Any Instruction Involving Operators or Senior Operators
U-601716, Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))1990-08-0303 August 1990
Forwards Response to Violations Noted in Insp Rept 50-461/90-10.Response Withheld (Ref 10CFR73.21(c)(2))
U-601715, Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly1990-08-0202 August 1990
Provides Addl Info Re Proposed Amend to Plant Tech Spec 3/4.8.1.1, AC Sources - Operating, Per .Amend Will Allow Testing Frequency of Diesel Generator to Be Returned to Monthly
U-601708, Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 19891990-07-19019 July 1990
Forwards Revised Pages to Semiannual Radioactive Effluent Release Repts for Jul-Dec 1988,Jan-June 1989 & Jul-Dec 1989
U-601702, Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)1990-07-0202 July 1990
Forwards Rev 9D to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20044A3001990-06-22022 June 1990
Forwards Update to 890817 Response to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Unisolable Piping Connected to RCS Identified & Evaluated to Determine Which Piping Could Be Subj to Stratified Flow Phenomena
ML20044A4601990-06-22022 June 1990
Provides Followup to 900622 Request for Waiver of Compliance Re Tech Spec Limiting Condition for Operation Concerning Standby Emergency Diesel Generator 1B.Rev to Attachment 1 of Original Request for Waiver Encl
ML20043H5021990-06-19019 June 1990
Requests Changes to License NPF-62,correcting Typos, Refs to Fsar,Testing to Be Done During Initial Plant Startup & Incorporating Revised Operating Power/Flow Map for Two Reactor Recirculation Loop Operation
ML20043G8221990-06-0707 June 1990
Provides Update to Util Response to Item 1 of Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping.
ML20043F0591990-06-0606 June 1990
Forwards Endorsements 44-50 to Nelia Policy NF-261 & 25-31 to Maelu Policy MF-121 & 10 & 11 to Maelu Policy N-85 & M-85,respectively
ML20043D0531990-05-31031 May 1990
Forwards 1989 Annual Rept for Illinois Power Co & Soyland Power Cooperative,Inc
ML20043C7501990-05-25025 May 1990
Forwards Rev 20 to Illinois Power Nuclear Program QA Manual. Rev Evaluated by Util as Not Reducing Quality Program Commitments
ML20043B4891990-05-21021 May 1990
Informs NRC of Plant Initiatives for 1990 to Improve Corrective Action Program Effectiveness,In Response to SALP Rept & Violations Noted in Insp Rept 50-461/89-32. Centralized Commitment Tracking Sys Upgraded
ML20043B1141990-05-17017 May 1990
Suppls 900330 Response to Station Blackout Rule.Calculation of Heatup of Main Control Room Due to Loss of Ventilation Following Station Blackout Revised to Properly Account for Heat Sinks & Credit Existing Masonry Walls
ML20043D9901990-05-14014 May 1990
Responds to NRC 900413 Ltr Re Violations Noted in Insp Rept 50-461/90-02.Corrective Actions:Safety Evaluation Prepared & Reviewed for Level Instrumentation & Annunciators Identified in Updated SAR
ML20043A9811990-05-14014 May 1990
Notifies That Wc Metzner Resigned from Position of Licensed Operator W/Util,Effective 900430
ML20042E6181990-04-13013 April 1990
Updates 890406 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Condition Rept Initiated to Address Issue to Drain Instrument Air Filter Regulators
ML20012E8991990-03-27027 March 1990
Forwards Rev 9C to Physical Security Plan.Rev Does Not Decrease Effectiveness of Plan.Rev Withheld (Ref 10CFR73.21)
ML20012D9451990-03-20020 March 1990
Informs of Current Activities Re Restoration of Shutdown Svc Water (SX) Sys to Operability Following Cleaning of Div I HX Per Generic Ltr 89-13.SX Sys to Be Restored by Returning Sys Flows to Design Values
ML20012D9641990-03-19019 March 1990
Lists Present Levels of Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w)(2)
ML20012D9901990-03-19019 March 1990
Responds to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-461/89-38.Corrective Actions:Maint Supervision Added Critical Points to Existing Maint Work Requests & Preventive Maint Activities & Training Program Updated
ML20012D4321990-03-16016 March 1990
Responds to Bulletin 88-008,Suppl 3, Thermal Stresses in Piping Connected to Rcs. Detailed Analytical Review & Proposed Schedule for Implementing Required Actions Scheduled to Be Completed by 900625
ML20012A2771990-02-28028 February 1990
Forwards Final Response to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded Case Circuit Breakers. Actions Taken by Util Have Established That All safety-related Circuits Remaining in Stock Can Be Verifiably Traced to Mfg
ML20012C2511990-02-23023 February 1990
Responds to Ninth SALP Rept 50-461/89-01 for Sept 1988 - Oct 1989.Rept Concluded That Overall Performance Satisfactory & Identified Strengths in Areas of Emergency Preparedness
U-601611, Notifies That Gd Setser Resigned Position W/Util,Effective 9002131990-02-20020 February 1990
Notifies That Gd Setser Resigned Position W/Util,Effective 900213
ML20011F6501990-02-12012 February 1990
Responds to NRC 900112 Ltr Re Violations Noted in Insp Rept 50-461/89-37.Corrective Actions:Radiation Protection Technicians Provided W/Method for Identifying Radiation Work Permits Which Change Radiological Conditions
ML20006C6721990-02-0505 February 1990
Responds to NRC 891207 Ltr Re Violations Noted in Insp Rept 50-461/89-35.Corrective Actions:Emergency Planning Bulletin Issued to All Emergency Response Organization Members Emphasizing Importance of Attending Required Training
ML20006D1951990-01-30030 January 1990
Responds to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events. Util Intends to Discontinue Sending Ack Upon Receipt of Vendor Manual Matls
ML20006A8291990-01-23023 January 1990
Forwards Rev 3 to Inservice Exam Plan. Changes to Text Described.Approval of Changes by 900601 to Allow Time to Plan Refueling Outage Activities Re Inservice Exam Program Requested
ML20005H2711990-01-12012 January 1990
Advises That Licensee Will Remove Terminal Blocks for Control Circuits within 100% Relative Humidity Harsh Environ at Plant by End of Second Refueling Outage Currently Scheduled to Begin in Sept 1990
ML20006A7121990-01-10010 January 1990
Forwards Revised Pages to 1987 Radiological Environ Monitoring Rept
ML20005F0001990-01-0505 January 1990
Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Util Revised Plant Operating Procedures for Hpcs,Lpcs & RHR Pumps & Vibration Monitoring Program Expanded to Include ECCS Pumps at Plant
ML20006A7921989-12-29029 December 1989
Responds to 891129 Ltr Which Forwarded Insp Rept 50-461/89-31,requesting Identification of Actions Underway to Ensure That Falsification of Interim Security Screening Records Would Be Detected in Timely Manner in Future
U-601573, Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently1989-12-29029 December 1989
Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Detailed Procedures Controlling Actuator Adjustments,Repair,Preventive Maint & Other Activities Used & Updated Frequently
ML20005E0891989-12-27027 December 1989
Advises That Revised Fitness for Duty Program Will Meet 10CFR26 Requirements,Effective 900103.Util Intends to Test for Substances Listed at Indicated cut-off Levels
ML20006C2961989-12-21021 December 1989
Responds to NRC 891121 Ltr Re Violations Noted in Insp Rept 50-461/89-32.Corrective Actions:Review Performed to Identify Surveillances Which Require Lifting of Leads in Main Control Room
ML20005D9521989-12-15015 December 1989
Forwards Monthly Operating Rept for Nov 1989 for Clinton Power Station Unit 1 & Corrections to Oct 1989 Rept
ML20005E7781989-12-12012 December 1989
Advises That False Alarm Criteria Will Be Implemented by 900131,per Insp Rept 50-461/89-31.Util Established New Criterion of 100 False Alarms for Security Sys in 24 H Period
ML20011D1741989-12-0707 December 1989
Informs of Changes Made to Util Fitness for Duty Program Procedure.Change Specifies That Supervisor - Medical Programs,Assistant Director - Labor Relations or Manager - Nuclear Planning & Support Will Generate Computer List
ML19332F0071989-11-30030 November 1989
Responds to Violations Noted in Insp Rept 50-461/89-29. Corrective Actions:Preventive Maint for Ph Monitor & Liquid & Gaseous Gamma Monitors Added to Appropriate Tracking Programs
ML19332E9431989-11-29029 November 1989
Forwards Executed Amends 4 & 5 to Indemnity Agreement B-91, Reflecting Change in Ownership of License,Effective 890327
ML19332D5031989-11-27027 November 1989
Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Results of Util Review & Reporting of Status of Implementation of USIs Encl
ML19332D0291989-11-22022 November 1989
Informs That Effective 891201,JS Perry Will Assume Responsibility for Mgt of Nuclear Program at Util
ML19332D0431989-11-22022 November 1989
Informs NRC of Change in Schedule for Providing Info Re Environ Qualification Testing of Terminal Blocks for Control Circuits of Conax Electrical Penetrations.Wyle Labs Test Results & Util Review of Results Will Be Sent by 900112
1990-09-19
[Table view] |
Text
-
i U- 600968 L30-87(06-30).
1A.120 ILLINDIS POWER 00MPANY CLINTON POWER STATION. P.O. BOX 678. CLINTON. ILLINOIS 61727 June 30, 1987 Docket No. 50-461 Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Clinton Power Station Inservice Testing Program l
i 1
Dear Sir:
l l
i Attached are responses to Dr. Walter R. Butler's February 6, 1987, letter to Mr. Frank A. 3pangenberg on the Inservice Testing Program (IST). Also, a revised Pump and Valve Testing Program, relief request matrix which cross references the previous and current relief requests,-
revised relief requests, and a listing of additional changes made to the program plan which were not discussed in the responses to the NRC items are attached. Illinois Power will now implement this revised IST Program.
If you have any que-tions on this material, please contact me.
Sincerely yours, ;
.cb
- h. 7 F. A. Sjjbnge erg, II Manager - Licensing and Safety DW/krm Attachmer,ts j cc: B. L. Siegel, NRC Clinton Licensing Project Manager l NRC Resident Office l Regional Administrator, Region III, USNRC !
Illinois Department of Nuclear Safety !
00 8707070414 870630 gg PDR ADOCK0500g1 P
i f i l- . _ _ _ J
ATTACHMENT 1 RESPONSE TO NRC ITEMS NRC ITEM IST PROGRAM REFERENCE / RESPONSE
- 1. VALVE TESTING PROGRAM A.1 Previous response is adequate. No Inservice Testing (IST)
Program changes.
A.2 All valves that are Appendix J, Type C, leak rate tested are listed in Clinton Power Station (CPS) Technical Specification Table 3.6.4-1. These valves (except vent valves, drain valves, manual isolation valves, etc. which are exempt per Section XI, Paragraph IWV-1200) have been listed as Category A or A/C in the IST Program. The leak rate was added as a required test for these valves.
A.3 Containment isolation valves that are Appendix J, Type B or Type C, and within the reactor coolant boundary are individually leak rate tested in accordance with the Code.
Containment isolation valves that are Appendix J, Type B or Type C, but are not within the reactor coolant boundary and can be individually tested, are tested in accordance with 10CFR50 Appendix J.
Containment isolation valves which cannot be individually tested (except Excess Flow Check Valves), are tested by utilizing the maximum permissible leakage rate for a specific containment penetration (inboard and outboard valves combined) instead of a leakage rate for individual valves as required by IWV-3426, Analysis of Leakage Rates.
See Relief Request 2011 (previously 056) for justification.
Excess flow check valves are not required to be leak rate tested (Type B or Type C) per CPS Technical Specification.
Ilowever , excess flow check valves are included within the Integrated Leak Rate Test (ILRT) boundaries. No separate test either by individual valve or by penetration will be performed on these valves. See Relief Request 2011 (previously 056). j Relief Request 2011 also provides justification for relief from the requirements of IWV-3423, Differential Test Pressure, for all containment isolation valves except those which serve as reactor coolant boundary valves.
All containment isolation valves comply with the staff position except those identified in Relief Request 2011.
l l
A.4 The response to this item is provided in the response to Item A.2.
i Response to NRC/ISI Page 1 of 21 t-_____---_-----------_-___________-.--______________ _ _ _ _ _ _ _ _ _ _ _ _ _ __
____________j
NRC ITEM- .IST PROGRAM REFERENCE / RESPONSE-A5 Previous response is adequate. tk) IST Program changes.
i l
)
A.6 Previous response is adequate. Relief Request 2016 provides the guidelines for valve testing during cold shutdowns. The justification for the cold shutdown testing frequency is provided in the individual item responses.
A.7 The IST Program format has been clarified by'specifying the frequency of each' test. '
1 A.8 Previous response is adequate. No IST Program changes.
A.9 The IST Program has been revised to verify all remote position. indicators every 2 years. l A.10 When a check valve is exercised by use of fluid flow through the valve, the flow rate value specified in the CPS Technical Specification and/or the CPS FSAR.is utilized to verify the valve's operability. When the flow rate value is not specified in the CPS Technical Specification and/or the CPS FSAR, the valve is exercised by proving that the disk moves promptly away from the seat.
A.11 Previous response is adequate. No IST Program changes.
A.12 Valves 1DG007A-D/G/H/J/K have been removed from the system.
Valves 1DG007E/F and 1DG008A-H/J/K have been deleted from the IST Program (see response to Items I.1 and I.3 for the detailed justification).
Valves 1D0001A/B/C, 1SX006C and 1SX063A/B were included in l the IST Program in Revision 1 and are tested quarterly. j A.13 These check valves (lFC018A/B, 020A/B, 022A/B, 073, 077 and 096) perform a safety function in the open direction and have been added to the IST Program for quarterly testing.
A.14 In addition to the previous rbsponse, the only valves that are partial exercised quarterly are 1B21-F022 A/B/C/D and ;
IB21-F028 A/B/C/D which are addressed in the response to )
Item B.l.
Response to NRC/ISI Page 2 of 21 A- __ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ - _ . _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ . .
i
NRC ITEM IST PROGRAM REFERENCE / RESPONSE For valves identified for testing during cold shutdowns, l testing.will be performed both during cold shutdowns and 4 refueling outages. However, when valves are identified for testing during refueling outages, testing will be performed f j
during refueling outages only.
B.1 Full-stroke exercising the Main Steam Isolation Valves (lB21-F022A/B/C/D and 1B21-F028A/B/C/D) during normal operation would increase the possibility of main steam-line isolation due to high flow in the other lines and could cause a plant shutdown. In addition, closing these valves with full steam flow would degrade the valve seats by throttling the steam flow, create thermal transients on the main steam lines, and increase the challenges to the Reactor l Protection System.
The MSIVs are designed for partial exercising with full steam flow during plant operation. This partial exercising will verify the operability of the valve and operator.
l These valves will be partial-stroke exercised quarterly and full-stroke exercised during cold shutdowns and refueling outages.
The IST Program has been revised to add the quarterly partial exercise test and to change the test frequency of the stroke time, exercise, and loss of power test from refueling to cold shutdown.
Relief Request 053 has been deleted.
B.2 Previous response is adequate. No IST Program changes.
B.3 In addition to the previous response, Relief Requests 015 and 016 have been deleted.
B.4 These Air Accumulator Supply Check Valves (lB21-F024A/B/C/D, 1B21-F029A/B/C/D, 1B21-F036A/F/G/J/L/M/N/P/R, l 1B21-F039B/C/D/E/H/K/S, 1B21-F433A/B and lIA042A/B) prevent i depressurization of the air accumulators on'a loss of 1 Instrument Air. Exercising these check valves would require isolating the air supply to the accumulators. This could prevent the Safety Relief Valves and Main Steam. Isolation Valves from performing their design function. Failure of these check valves during exercising could depressurize the accumulators and lead to opening the SRVs and/or closing the MSIVs resulting in a plant shutdown. ]
Response to NRC/ISI Page 3 of 21 l
g ..
NRC ITEM- IST PROGRAM REFERENCE / RESPONSE These valves will be exercised during cold shutdowns and refueling outages.
The IST Program has been revised to change the testing frequency from refueling to cold shutdown for these' valves.
Relief Request 042 has been deleted.
B.5' Repeatable arid representative stroke times can be measured (Action Item) for the ADS valves (lB21-F041B/C/D/F, 1B21-F047A/C and l 1B21-F051G). The IST Program has been revised to change l
them from Category C to B/C valves and to identify their required tests as exercise, stroke time, and loss of power during refueling outages. Relief Request 2012 (previously 057) describes the alternate testing to be utilized and provides the technical justification.
1 B.6 Valves 1B21-F098A/B/C/D perform no safety function. These valves have been deleted from the IST Program and Relief Request 005 has been deleted.
B.7 Previous response is adequate. No IST Program changes.
B.8 Valves 1B21-F010A/B and F032A/B cannot be exercised closed (Action Item) during cold shutdowns. The technical justification for only testing these valves during refueling outages is provided in Relief Request 2001 (previously 001).
B.9 Valves 1B21-F001 and F002 are Reactor Pressure Vessel (RPV) vent valves. These valves are Category A passive valves since they are not required to change position in order to perform a safety function and have been identified as such in the IST Program. They are the only passive valves in the IST Program.
B.10 These vacuum relief valves (IB21-F037A-H/J-N/P/R/S, (Action Item) 1B21-F040, 1B21-F078A-H/J-N/P/R/S, and 1B21-F379A-H/J-N/P/Q/R) prevent drawing a vacuum in the Safety Relief Valve discharge and vent lines following relief valve operation. These valves are located inside the drywell and are inaccessible during normal plant operations.
These vacuum breakers are normally closed during plant operation. Exercising these valves during power operation would have adverse personnel safety implications and would present ALARA concerns.
Response to NRC/ISI Page 4 of 21 L____-__-___-___-____________-_-__ _ _ - ____ __ _ _ _ _ __
4 NRC ITEM IST PROGRAM REFERENCE / RESPONSE These valves will be exercised during cold shutdowns and refueling outages.
The IST Program has been revised to change their testing frequency to cold shutdown from refueling.
Relief Request 003 has been deleted.
i B.ll These Feedwater RPV Inlet Isolation Valves (lB21-F065A/B)
(Action Item) isolate the feedwater flow to the Reactor Pressure Vessel (RPV). Exercising these valves during plant operation would interrupt the flow of feedwater to the RPV. Isolation of one line of feedwater flow during normal operation would introduce undesirable operational transients and could result in a reactor trip. Partial stroke testing cannot be performed since these valves stroke fully on initiation.
These valves will be exercised and stroke timed during cold i shutdowns and refueling outages.
The IST Program has been revised to change the testing frequency to cold shutdown from refueling.
Relief Request 004 has been deleted. ,
1 l
C.1 Previous response is adequate. No IST Program changes.
C.2 Previous response is adequate. No IST Program changes.
D.1 Previous response is adequate. Valves ICC188A/B have been deleted from the IST Program.
l D2 Previous response is adequate. Valves 1CC065, 067, 068 and 070 have been deleted from the IST Program.
i D.3 These component cooling valves (1CC049, 050, 053, 054, 057, (Action Item) 060, 127 and 128) isolate the Component Cooling System supply to containment and return from containment. These valves are normally open during plant operation. Exercising these valves would eliminate cooling water to the Reactor.
Recirculation Pumps and the Non-regenerative Heat !
Exchangers. Elimination of cooling water to these components during plant operation would result in premature i failure of the Reactor Recirculation Pump seals and undesired thermal shocks to the Non-regenerative Heat-Exchangers. Partial stroke testing cannot be performed since these valves stroke fully on initiation.
Response tc NRC/ISI Page 5 of 21 L
NRC ITEM IST PROGRAM REFERENCE / RESPONSE These valves will'be exercised and stroke timed during cold shutdowns and refueling outages.
The IST Program has been revised to change the. testing frequency of these valves to cold shutdown from refueling.
Relief Request 019 has been deleted.
D.4 Previous response is adequate. These valves (1CC065, 067, 068, 070 and 188A/B) have been-deleted from the IST Program and Relief Request 036 has been deleted.
D.5 Previous response is adequate. No IST Program changes.
E.1 Previous response is adequate. See Relief-Request 2006 (previously 037).
E.2 The IST Program was revised to change valves ICM0ll, 012, 022, 023, 025, 026, 047 and 048 from Category B to A .
(containment isolation valves). The.IST Program has been l revised to identify the tests required.as stroke time, loss of power, and exercise at a frequency of quarterly for all valves that were in Relief Request 032 and Relief Request j 032 has been deleted. Relief Request 2013 (previously 058) has been initiated to eliminate the trending requirements for these rapid acting solenoid valves.
E.3 Valves 1CM066 and 067 can be and are tested quarterly. The IST Program has been revised to indicate this and they have been deleted from Relief Request 037.
F.1 Previous response is adequate. No IST Program changes.
l G.1 The hydraulic control unit air operated valves 126, 127 and .
(0 pen Item) 139 and check valves 114, 115 and 138 (145 of each valve) ;
perform a safety function. These valves are not ASME Class-
~
1, 2, or 3 valves and therefore do not fall within the scope of this program.
However, these valves are tested as follows:
Response to NRC/ISI Page 6 of 21 1
L__ _ _ _ _ _ - - _ _ _ _ - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - -
'NRC ITEM IST PROGRAM REFERENCE / RESPONSE l All valves except 115 CPS Technical Specification 4.1.3.2 requires performance of scram insertion time testing and single control rod scram time testing with the reactor coolant pressure greater than i or equal to 950 psig with the Control Rod Drive Pumps l isolated from the accumulators as follows: i
)
- 1) For all control rods, prior to thermal power exceeding )
40% of rated thermal power following core alterations j or after'the reactor has been shutdown for more than '
120 days.
- 2) For at least 10% of the control rods, on a rotating basis, at least once per 120 days of power operation.
Valve 115 CPS FSAR requires that check valve 115 be periodically tested to ensure the operability. Testing of this. valve will be performed during refueling outages by securing the Control Rod Drive Pumps and verifying that these valves are closed by monitoring the accumulators' low pressure alarm.
Relief Request 059 has been deleted.
G2 Previous response is adequate. No IST Program changes.
G.3 Previous response is adequate. No IST Program changes.
G.4 Valve 1C11-F083 (Action Item)
Control Rod Drive (CRD) Pump Discharge Isolation Valve (1C11-F083) is a containment isolation valve. Failure of this valve in the closed position during exercising would i result in a loss of drive water to the Control Rods and seal l' flow to the Reactor Recirculation Pumps. .This would inhibit normal operation of the Control Rods and could result in a reactor shutdown. Isolating the cooling water could also i result in damage to the Reactor Recirculation Pump seals. j This valve strokes fully on initiation and cannot be i partial-stroke tested.
This valve will be exercised and stroke timed during cold' shutdowns and refueling outages.
The IST Program has been revised to change this valve from j Category B to A and to change its testing frequency to cold ]
shutdown from refueling. 1 Relief Request 008 has been deleted.
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4 NRC ITEM IST PROGRAM REFERENCE / RESPONSE Valve 1C11-F122 (Action Item)
This CRD Water Header check valve (1Cll-F122) cannot be tested.during normal operation or cold shutdown. See Relief l Request 2002 (previously 010) for the detailed justification. This valve was changed from Category C to -
A/C in the IST Program.
H.1 Previous response is adequate. See Relief Request 2003 (previously 011).
l H.2 Previous response is adequate. No IST Program. changes.
H.3 Previous response is adequate. No IST Program changes.
H.4 Previous response is adequate. No IST Program changes.
i 1.1 Valves 1DG007A-D/G/H/J/K have been removed from the system and deleted from the IST Program.
Valves 1DG007E/F perform an active safety function.
However, they are not ASME Class'1, 2, or 3 valves and.do j not fall within the scope of this program. Their j operability is assured by the monthly diesel generator surveillance test required by CPS Technical Specification 4.8.1.1.2(a). These valves have been deleted from the IST Program and Relief Request 038.
1 I
I.2 These valves (1DG168, 169, 170, 171, 172 and 173) perform 1 (Action Item) an active safety function. However, they are not ASME Class 1, 2, or 3 valves and do not fall within the scope of this program.
The operability of these valves is assured by the monthly diesel generator surveillance test, required by CPS Technical Specification 4.8.1.1.2(a).
No IST Program changes are required.
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NRC ITEM IST PROGRAM REFERENCE / RESPONSE I.'3 CPS has not received written direction from'the NRC (Action Item) concerning inclusion of emergency diesel generator subsystems in the IST Program. These Diesel Start Valves (1DG008 A-H/J/K) perform an active safety function.
However, they are not ASME Class 1, 2, or 3 valves and do not fall within the scope of this program. The operability of these valves is assured by the monthly diesel generator surveillance test, required by CPS Technical Specification 4.8.1.1.2(a).
These valves have been deleted from the IST Program and Relief Request 038 has been deleted since valves 1DG007E/F were deleted per Item I.l.
J.1 Previous response is adequate. No IST Program changes.
1 J.2 Previous response is adequate. No IST Program changes.
l J.3 Valves lE12-F026 A/B, F051 A/B, F052 A/B, F065 A/B and F087 A/B are in the flow path of the steam condensing mode of the RHR System. The steam condensing mode of operation is not required for the safe shutdown of the plant. However, all of these valves except lE12-F051 A/B and F065 A/B are required to close to allow Low Pressure Core Injection systems operation which is a safety function.
All of these valves are included in the IST Program as Category B valves except lE12-F051 A/B and F065 A/B. Valves lE12-F051 A/B and F065 A/B are pressure regulating valves which are exempt from testing per IWV-1200(a) and have been deleted from the IST Program.
J.4 This valve (1E12-F095) is addressed in Relief Request 2007 ,
(previously 045) which requests relief from the stroke time l test. Valves lE12-F060A/B and lE12-F075A/B have been j deleted from Relief Request 2007 (previously 045). Also, i valve lE12-F095 was changed from Class 2 to 3 in the IST j Program.
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Response to NRC/ISI Page 9 of 21 L
NRC ITEM IST PROGRAM REFERENCE / RESPONSE J.5 This Residual Heat Removal (RHR) to RPV Head Spray Check Valve (lE12-F019) prevents backflow from the. Reactor Pressure Vessel into the RHR System. This valve is designed to be exposed to the Reactor Pressure Vessel pressure.
During normal reactor operation, the RHR mode of operation which provides cooling water to the RPV through Reactor Core Isolation Cooling (RCIC) head spray is in standby.
Exercising this valve with a mechanical exerciser during normal reactor operation with a differential pressure equivalent to the reactor pressure across the disk would result in damage to the valve. Therefore, this valve cannot be exercised quarterly. This valve can be exercised during cold shutdowns since the reactor pressure will be less than the RHR system pressure.
This valve will be exercised during cold shutdowns and refueling outages. The IST Program was revised to change the testing frequency from quarterly to cold shutdowns. .
Relief Request 066 has been deleted. >
J6 The air operators on valves lE12-F041A/B/C do not fully (Action Item) stroke these check valves. CPS will disconnect the air operators during the first refueling outage so that the valves can be full-stroke exercised by utilizing a j mechanical exerciser.
Relief Request 2014 (previously 060) has been initiated to request relief from fully stroking these valves in the interim period until the air operators are disconnected.
These valves are pressure isolation valves. There are two pressure isolation valves in each piping line between the high pressure Reactor Coolant System and the low pressure RHR system. Testing any of these valves during normal operation would result in a loss of one isolation barrier.
This could cause an inter-system Loss of Coolant Accident (LOCA) and damage low pressure system piping with the potential for release of reactor coolant outside the primary containment.
Therefore, these valves will be partially exercised during cold shutdowns and refueling outages until the air operators are disconnected. After the air operators are disconnected, full-stroke exercising of these valves will be performed by utilizing a mechanical exerciser during cold shutdowns and refueling outages.
The IST Program has been revised to change from exercising during refueling outages to partial exercising during cold shutdowns.
Response to NRC/ISI Page 10 of 21 C__________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _. _ _ _ _ _ _ _ _ _ _
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NRC ITEM IST PROGRAM REFERENCE / RESPONSE J.7- Valves lE12-F046A/B/C are check valves installed in minimum flow lines. These valves are tested by ensuring that they open to the point necessary to provide design minimum flow.
J.8 Valves 1E12-F084A/B/C and lE12-F085A/B/C-perform safety (Open Item) functions in both the open and the closed positions. The open position is verified quarterly by observation that the low discharge pressure alarm on Panel lH13-P601 is cleared. . i Since the Waterleg Pump discharge check valves.are check and I stop check valves in series, an alternate testing method is required to test their closure individually. See Relief Request 2015 (previously 061) for the testing method and frequency for individually verifying closure of these valves.
J.9 Previous response is adequate. No IST Program changes, i
l J.10 Previous response is adequate. No IST Program changes.
J.ll The valves in Relief Request 054 are pressure isolation (Action Item) valves between the high pressure Reactor Coolant System and various low pressure systems (e.g. RHR, LPCS, HPCS and RCIC).
Valves lE12-F008, F009, F023, F041A/B/C, F042A/B/C, F053A/B; lE21-F005, F006; lE22-F004, F005 lE51-F013, F066: l There are two pressure isolation valves in each piping line between the high pressure Reactor Coolant System and low pressure systems (ECCS and RCIC). Testing any of these valves during normal operation would result in a loss of one isolation barrier. This could cause an inter-system Loss of Coolant Accident (LOCA) and damage low pressure system piping with the potential for release of reactor coolant outside the primary containment. Therefore, these valves cannot be tested during normal operation. These valves can be tested during cold shutdowns since reactor pressure will be less than RHR aystem pressure.
These valves will be exercised and stroke timed during cold shutdowns and refaeling outages. The IST Program was revised to change the frequency of these tests to cold shutdowns from refueling outages.
These valves were deleted from Relief Request 054.
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t NRC ITEM IST PROGRAM REFERENCE / RESPONSE-Valves lE12-F050A/B .
These valves cannot be tested' during normal operation cnf cold shutdowns and are addressed in Relief Request 2010 .j (previously 054) which provides the detailed justification for not testing these valves during normal operation or cold shutdowns. ;
J.12 Valves 1512-F037A/B are containment isolation valves and have been included in the IST Program as Category A valves.
Exercise and stroke time tests will be performed on these valves quarterly.
J.13 The IST Program has been revised to identify the tests required as stroke time, loss of power and exercise-at a frequency of quarterly for valves lE12-F060 A/B and F075 A/B
- and they have been deleted from Relief Request 045.
l lE12-F095 is now the only valve in Relief Request 2007 (previously 045) which requests relief from the stroke time test.
1 1 Valves 1E12-F060 A/B and F075 A/B are included in Relief Request 2013 (previously 058) which eliminates the trending requirements for these rapid acting valves.
K.1 See response.to Item J.6. This valve (1E21-F006) is also l (Action Item) included in Relief Request 2014 (previously 060) which describes the testing method and frequency for this check valve.
K.2 This valve (1E21-F005) is included in the response to Item J.11. This valve will be full-stroke exercised and stroke timed during cold shutdowns and refueling outages. It'has been deleted from Relief Request 054.
K.3 See response to Item J.8. These valves (lE21-F033 and F034)
(open Item) are also included in Relief Request 2015 (previously.061) which describes the testing method and frequency for i individually verifying closure of these valves.
K.4 Previous response is adequate. No IST Program changes.
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Response to NRC/ISI Page 12 of 21 L- - - - - - -
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NRC ITEM IST PROGRAM REFERENCE / RESPONSE K.5 Valve 1E21-F306 supplies the flushing water to the Low Pressure Core Spray system from the Cycled Condensate system !
which is not a safety function. Therefore, this valve has been deleted from the IST Program..
Relief Request 041 has also been deleted. j L.1 See response to Item J 6. This valve (1E22-F005) is also (Action Item) included in Relief Request 2014 (previously 060) which describes the testing method and frequency for this check valve.
L.2 See response to Item J.8. These valves (1E22-F006 and F007)
(0 pen Item) are also included in Relief Request 2015 (previously 061) which describes the testing method and frequency for individually verifying closure of these valves.
L.3 Previous response is adequate. Valve 1E22-F332 is now included in Relief Request 2006 (previously 037). The IST Program was revised to change its testing frequency from j quarterly to refueling outages.
L.4 Previous response is adequate. No IST Program changes.
M1 Previous response is adequate. These valves (1E31-F016 and F019) have been deleted from the IST Program.
Relief Request 040 has also been deleted.
M.2 The IST Program has been revised to identify the tests required as stroke time, loss of power, and exercise at a frequency of quarterly for valves lE31-F014, 015, 017 and 018. Relief Request 033 has been deleted.
Relief Request 2013 (previously 058) has been initiated to eliminate the stroke time trending requirements for these rapid acting valves.
Response to NRC/ISI Page 13 of 21 L.-- __
NRC ITEM IST PROGRAM REFERENCE / RESPONSE N.1 These valves (lE32-F010, F0ll and F315A/B/C/D) perform a safety function in both the closed and open positions.
These valves are closed to allow the MSIV leakage control blowers to obtain the required negative pressure on the MSIV headers. These valves will be verified to close during the system operability. test performed during cold shutdowns.
Testing these valves quarterly would require disassembly of portions of downstream piping components since these valves do not have any actuators or hand levers. Therefore, these valves will be tested during cold shutdowns and refueling outages.
0.1 Valves lE51-F061 and F062 perform a safety function in the open direction to allow the Waterleg Pump to fill the RCIC piping. There is no safety function in the closed direction to protect low pressure piping since the Waterleg Pump discharges to the suction piping of the RCIC Pump.
Valve lE51-F062 has been added to the IST Program as a Category C valve.
For valve lE51-F061, the closed test position has been deleted.
0.2 Valve lE51-F066 (Action Item) See response to Item J.6. Until the air operator is disconnected, this valve will be partially exercised during cold shutdowns using the air operator.
However, after the air operator is disconnected, valve lE51-F066 cannot be exercised utilizing a mechanical exerciser during cold shutdowns since it is located inside the drywell which is inaccessible during cold shutdowns.
Therefore, valve lE51-F066 will be full-stroke exercised utilizing a mechanical exerciser during refueling outages after the air operator is disconnected.
Relief Request 2020 has been initiated to request relief from fully stroking this valve in the interim period until the air operator is disconnected and for the refueling outage test frequency after the air operator is disconnected.
Valve lE51-F065 This RCIC injection line check valve prevents backflow from the Reactor Pressure Vessel. This valve is designed to be exposed to the Reactor Pressure Vessel pressure. During normal reactor operation the RCIC system is in standby mode.
This valve is located within the pressure isolation boundary. Exercising this valve with flow would require one of the pressure isolation valves to be opened which could Response to NRC/ISI Page 14 of 21 t___________________._______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
l NRC ITEM IST PROGRAM REFERENCE / RESPONSE result in an inter-system Loss of Coolant Accident (LOCA).
Exercising this valve with the mechanical exerciser during normal operation with a differential pressure equivalent to the Reactor Pressure Vessel across the disk would result in damage to the valve. Therefore, this. valve cannot be exercised quarterly. This valve can be exercised during cold shutdowns and refueling outages. The IST program was revised to change the testing frequency from quarterly to.
l cold shutdowns and Relief Request 062 was deleted.
1 0.3 Previous response is adequate. No IST Program changes.
0.4 Previous response is adequate. No IST Program changes.
0.5 Valve lE51-F015 is a pressure control valve which is exempt from testing per IWV-1200(a) and has been deleted from the IST Program. Also, Relief Request 046 has been deleted.
0.6 Valves lE51-F004 and F005 have been' reclassified as active (Action Item) valves. These valves have been added to the IST Program with required tests being exercise, stroke time, and loss of power at a frequency of quarterly.
Valve lE51-F047 performs only a passive safety function.
Since this valve is not a Category A valve, no testing is required by the ASME Code and it has been deleted from the IST Program.
P.1 Previous response is adequate. These valves (1FC018A/B, 020 A/B, 022A/B, 073, 077 and 096) have been added to the IST program and will be exercised quarterly.
P.2 Previous response is adequate. No IST Program changes.
i P.3 Previous response is adequate. These valves were already included in the IST Program. No IST Program changes.
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9 NRC 1 TEM IST. PROGRAM REFERENCE / RESPONSE Q.1 Valves 1G33-F051 and F052A/B perform a safety function in (Action Item) the closed position to prevent backflow from the Feedwater System and Residual Heat Removal (RHR) System to the Reactor Water Cleanup System and the other train of the RHR system.
The IST program has been revised to exercise these valves i during refueling outages. See Relief Request 2008 q (previously 047) for justification.
R.1 These Instrument Air System and Containment Isolation Valves (llA005, 006, 007 and 008) are within the normal flow path between the Instrument Air System and various valves located inside the drywell. Exercising these isolation valves during normal operation would isolate the air supply to 4 various instrumentation and sensing lines and could cause 1, the reactor to scram. Exercising these valves would also isolate the air supply to various safety-related valves and reduce the operational readiness of.those systems. Partial stroke testing cannot be performed since these valves stroke h fully on initiation.
.i These valves will be exercised and stroke timed during cold I shutdowns and refueling outages.
The IST Program has been revised to change their testing frequency from quarterly to cold shutdown and Relief Request 063 has been deleted.
- R.2 Previous response is adequate. The IST Program has been revised to change the testing frequency of these valves (lIA012A/B and llA013A/B) to quarterly from refueling. c I
Relief Requests 028 and 029 have been deleted, j i
R.3 Valves lIA042A/B perform a safety function in the closed j position and are included in the response to Item B.4. The )
IST Program has been revised to change valves lIA042A/B from Category C to A/C and to change their test frequency from ;
refueling to cold shutdown.
Relief Request 042 has been deleted.
Valves lIA076A/B do not perform a safety function.
R.4 Previous response is adequate. IST Program changes regarding valves lIA012A/B, 013A/B and 042A/B were addressed in the responses to Items R.2 and R.3. Valves lIA043A/B do Response to NRC/ISI Page 16 of 21 L
6 NRC ITEM IST PROGRAM REFERENCE / RESPONSE not exist and reference to-them in the IST Program has'been deleted.
R.5 Previous response is adequate. These valves (lIA044A/B) q have been deleted from the IST Program and Relief Request 044.
. S.1 The IST Program was revised to change valves IPS004, 005, 009, 010, 016, 017, 022, 023, 031,_032, 034, 035, 037, 038, l
047, 048, 055, 056, 069 and 070 from Category B to A j (containment isolation valves). The IST Program has been i revised to identify the tests required as stroke time, loss-of power, and exercise at a frequency of quarterly for all of the valves that were in Relief Request 043'and Relief Request 043 has been deleted. i Relief Request 2013 (previously 058) has been initiated to eliminate the stroke time trending requirements for these rapid acting valves.
4 S.2 Previous response is adequate. No IST Program changes. ]
T.1 Relief Request 2005 (previously 027) seeks relief from the i trending requirements for these rapid acting valves (0RA026, j 027, 028 and 029). !
The IST Program was revised to change valves _0RA026 and 027 from Category B to A (containment isolation valves). ;
U.1 1RA017A/B are pressure regulating control valves and are exempt from testing per IWV-1200. These valves have been i deleted from the IST Program.
Relief Request 044 has been deleted since valves lIA044A/B were deleted from the IST Program per Item'R.5.
V.1 Previous response is adequate. Valves 1SM008 and 011 have been included in Relief Request 2006 (previously 037) and their testing frequency was changed from quarterly to refueling in the IST Program.
Page 17 of 21 Response to NRC/ISI e - - - - - - - . - - - - - _ _ - - - - - - - - - _ _ - - . - - - - _ - _ - - _ - - _ - - _
. l NRC ITEM IST PROGRAM REFERENCE / RESPONSE ,
J W.1 Previous response is adequate. Valves 1SX025A/B/C are control valves which are exempt from testing per IWV-1200 and have been deleted from'the IST Program. The IST: Program has been revised to add the stroke time test for the other valves in Relief Request 048'and Relief Request 048 has been deleted.
1 W.2 Previous response is adequate. No IST Program changes.
l W.3 Valves lSX012A/B, 1SX062A/B (Action Item) These Fuel Fool Cooling and Cleanup (FPCC) Heat Exchanger Backup Cooling Water Isolation Valves isolate the FPCC Heat Exchangers from the backup cooling water supplied ~from the lake. Testing of these valves will allow lake water into .,
the FPCC heat exchangers. After_the valves are stroked, the' '
heat exchangers must be flushed and sampled to ensure-the normal cooling water does not become contaminated by the lake water. Therefore, these valves cannot be tested during normal operation.
These valves will be exercised and stroke timed during cold shutdowns and refueling outages. ,
The IST Program has been revised to change the testing I frequency of these valves from refueling to cold shutdown.
Relief Request 030 has been deleted.
Valves ISX016A/B These valves cannot be tested quarterly or during cold !
shutdowns. Relief Request 2004 (previously 017) provides.
the detailed justification. for testing' these valves during refueling outages only. ,
W.4 Valves 1SX083 A/B provide flushing water to the RHR System Heat Exchangers which is not a safety function. These valves have been deleted from the IST Program.
l W.5 Previous response is adequate._ Valves 1SX025A/B/C are hydromoter control valves which are exempt from testing-per IWV-1200 and have been deleted from the IST Program. Relief Request 064 has been deleted.
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NRC ITEM IST PROGRAM REFERENCE / RESPONSE W6 The IST Program has been revised to identify the required tests for 1SX071A/B, 072A/B, 073A/B, 074A/B, 075A/B, 076A/B, 105A/B, 106A/B and 107A/B as stroke timing and exercising during refueling outages. See Relief Request 2009
-(previously 050) for the detailed justification.
W.7 Valves ISX013D/E/F perform no active safety function.
(Action Item) Passive valves do not require testing per Subsection IWV so these valves have been deleted from the IST Program.
Relief Request 049 has been deleted.
1 W.8 Previous response is adequate. Valves 2SX017A/B, 073A/B, 076A/B and 107A/B have been deleted from the IST Program and Relief Request 051 has been deleted.
X.1 Previous response is adequate. No IST Program changes.
X.2 The IST Program has been revised to include valves OVC010A/B and 022A/B as Category B valves and identify the quarterly tests required.
X.3 The IST Program has been revised to include valves OVC020A/B, and 032A/B as Category C valves and identify the quarterly tests required.
X.4 The IST Program has been revised to include valves OVC001A/B i and 002A/B and identify the quarterly tests required. These are solenoid operated valves (rapid acting) and are' included i in Relief Request 2013 (previously 058). J Also, valves OVC017A/B and 025A/B have been added to the~IST i Program since they perform a safety function.
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X.5 Valves OVC056A/B, 057A/B, 058A/B and 059A/B are normally l closed solenoid operated drain valves and are interlocked j with Shutdown Service Water System deluge valves (ISX107A/B and 1SX074A/B). These valves are not active valves as Response to NRC/ISI Page 19 of 21 s
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4 NRC ITEM IST PROGRAM REFERENCE / RESPONSE defined in the ASME Section XI. The IST Program has been revised to delete these valves and Relief Request 055 has been deleted.
Y.1 Previous response is adequate. No IST Program changes.
Y.2 Previous response is adequate. No IST Program changes.
Y.3 Valves 1VR035, 036, 040 and 041 are containment isolation ,
valves which are solenoid operated (rapid acting). The IST Program has been revised as follows:
- 1) The category of all of these valves has been changed ;
from B to A (containment isolation valves).
- 2) The stroke time test has been identified as a required test for all of these valves every three months. {
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- 3) Relief Request 035 has been deleted. 3 l
- 4) Relief Request 2013 (previously 058) identifies the testing frequency and method for all of these valves, l Z.1 Previous response is adequate. No IST Program changes.
Z.2 Previous response is adequate. No IST Program changes. ,
Z.3 Valves 1W0001A/B, 002A/B (Relief Request 021)
These chilled water supply / return valves isolate the chilled water system from the steam tunnel area coolers, Reactor Water Cleanup System regenerative and non-regenerative heat exchanger air handling units, and the containment building ;
air handling units. Testing these valves would isolate !
chilled water to certain air handling units that are ;
important while the plant is operating. Isolating chilled water to.these components could cause a high temperature .
o initiated containment isolation and result in a reactor j scram. i The IST Program has been revised to change these valves from i Category B to A and to change the testing frequency from refueling to cold shutdown.
Relief Request 021 has been deleted. !
I Response to NRC/ISI- Page 20 of 21 ;
NRC. ITEM IST PROGRAM. REFERENCE / RESPONSE Valves 1WO551A/B and'552A/B (Relief Request 052)
These Drywell Cooling Chilled Water DrywellLIsolation Valves provide chilled water to the Drywell Cooling System Coil Cabinets. Exercising these valves.during normal operation would require.the Drywell Chilled Water System Coil. Cabinets to be inoperable. These coil cabinets are required for.
drywell' cooling during reactor-operation.
The IST Program has been revised to change the testing frequency from refueling to cold-shutdown. e l
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2.' Pump Testing Program 2.1 Previous response is adequate. Relief Request 3001 (previously 001) has been revised to provide a more detailed justification for not measuring pump bearing temperatures annually.
2.2 Relief Request 3004 (previously 004) provides the justification for not utilizing lake level to calculate pump inlet pressure.
Response to NRC/ISI Page 21 of 21
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