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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
.
ILLINDIS POWER COMPANY y g{g L3 (3,_3gy_5 500 SOUTH 27TH STREET, DECATUR, ILLINOIS 62525 December 14, 1981 Mr. James R. Miller, Chief QfS N
Standardization & Special Projects Branch Division of Licensing 4 ,
G' -
Office of Nuclear Reactor Regulation h .'; i, ~
'~
U.S. Nuclear Regulatory Commission Il-- g Washington, D.C. 205S5 Q gg,@o Se,
$ i-3' n
Dear Mr. Miller:
A/-< ," vr -
/)-
Clinton Power Station Unit 1 3 7;--p Docket No. 50-461 Ns Attached are details related to the Clinton fire detection system which were discussed with John Stang, Chemical Engineering Branch during a meeting on December 10, 1981. This item is considered by the NRC and IP to be confirmatory for CPS Licensing purposes.
Attachment s_
Clinton Fire Detection System PGCC Fire Detection (Verbal Question)
Sincerely, bLbM J. D. Geier Manager Nuclear Station Engineering ALR/lt cc: J. H. Williams , liRC Clinton Proj ect Manager H. H. Livermore, NRC Resident Inspector og J. Stang, NRC CEB $Os 1(
8112230483 DR ADOCK 811214 05000
[
CLINTON FIRE DETECTION SYSTEM ,
. I. General Fire Protection Panel lH13-P840 serves as the central alarm panel for Sprinkler, CO , Halon, Ionization, Water Flow, DieselFirePump,andTarbineBuildingSmokeventportions of the Clinton Fire Detection System. This panel is located -
in the Main Control Room.
Devices located on this panel are a3 follows:
- a. Fire Protection Annunciator Windows
- b. Supplementary Initiation Pushbuttons for Pre-Action, Deluge, CO , and Halon Suppression Systems
- c. Control Sw$tches and Indicating Lights.for Turbine Building Smoke Vents
- d. Remote Start Pushbuttons for Diesel Fire Pumps
- e. Supplementary Fire Indicating Lights for Individual Ionization Detector Zones The primary power source for the annunciator is the station non-Class lE 125V de system which has a four-hour battery backup following loss of offsite power as the secondary source. Dedicated circuits will be provided for manual connection to a Class lE power source within four-hours of loss of site power. This load is within the design limits of the Class lE power system.
The annunciator at this panel was not originally designed to monitor the integrity of incoming conductors. However, since the purpose of the fire protection program is to pro-tect safety-related systems and components against the hazards of fire,'it will be modified to monitor the intecrity of'the primary incoming fire alarm circuits from systems located in buildings containing safety-related equipment as follows:
- a. Ionization Detection Panel (lPA09J) Common Fire Alarm
- b. Division 1 - Cable Spreading Room Autc Pre-action System c.- Division 2 - Cable Spreading Room Auto Pre-action System
- d. Division 1 - Diesel Generator Oil Storage Tank Room Wet Pipe System
- e. Division 2 - Diesel Generator Oil Storage Tank Room Wet Pipe System
- f. Division 3 - Diesel Generator Oil Storage Tank Room Wet Pipe System
- g. Division 1 - Diesel Generator Day Tank Room Wet Pipe System
- h. Division 2 - Diesel Generator Day Tank Room Wet Pipe System
- 1. Divinion 3 - Diesel Generator Day Tank Room Wet Pipe System
- j. Fuel Building Railroad Bay Auto Pre-Action System i
l The performance requirements of Style 1 of Table 3-10.1 ,
oof NFPA-72D (1979) will be mat for those circuits monitored. E Interconnections of those systems to the annunciator are !
shown on Figure 1.
A description of the elements of the Fire Detection / Protection system follows:
II. Ionization Detection System
-The ionization detection system consists of. detection zones throughout the plant as indicated in the fire hazards anal-ysis. Detectors are Pyrotronics Model DIS-5B with the excep-tion of the detectors in the Reactor Recirculation Pump-area which are thermal detectors. The power supply / alarm panel (lPA09J) for these detectors is located on Elevation 781'-0" in the Control Building. 120V power to this panel is provided by the Station Uninterruptible Power Supply (UPS) located in the same room. The primary power source.
for the UPS is the station.non-Class lE 480V ac power system, with a four-hour battery backup following loss of offsite power, as the secondary source. A dedicated circuit will be provided for manually connecting a Class lE source to this panel within four-hours of a loss of-offsite power.
This load is within the design limits of the Class lE power system.
The detector circuits are monitored for open or short cir-
-cuits as well as loss of power or undervoltage. Fire and trouble alarms for each dete-tor circuit are indicated at 1
IPA 09J; system fire and trouole alarms are indicated at lH13-P840. Supplementary fire indicating lights are pro-vided at lH13-P840 for identification of which fire zone is in the alarm state. System Fire and Trouble alarms will be arranged to provide redundant fire alarm receipt capa-
~
bility as shown in Figure 2.
III. Water Spray Fire Protection Systems Each water spray fire protection system zone (deluge, pre-action, or wet pipe) has an individual local supervisory control panel. Thermal detectors, flow switches, manual pull stations, low-air pressure switches, gate valve position switches as applicable to each type cf system are connected to the local supervisory panels. Local fire bell alarms are provided for each panel. Circuit integrity for detectors, local pull stations and flow switches connected to the local
. supervisory panels is monitored (Class B, per NFPA 72D-1975).
Fire and trouble (combined for wet pipe systems) for each
, local supervisory panel are alarmed-at lH13-P840.. Fire and Trouble alarms for each system identified in I will be arranged to provide redundant fire alarm' receipt capa-bility as shown in Figure 2.
The primary power source for the local supervisory panels is the station non-Class 1E 125V de system,.which has a four-hour battery backup following loss of offsite power, as the secondary source. Dedicated circuits will be provided for manually connecting a class lE source to panels located in buildings which contain safety-related equipment within four hours of a loss of offsite power. This load is within the design limits of the Class lE power system.
IV. Diesel Fire Pumps Each of the diesel fire pumps is provided with a local con-trol panel (OFP0lPA and OFP0lPB) . A remote start pushbutton
~
is provided at panel lH13-P840. The following alarms appear on both the local control panels and panel lH13-P840:
- 1) Failure to Start
- 2) Low Fuel Level
- 3) Auto Start / Engine Running The following alarms appear individually at each of the-local panels and are combined into a common " Trouble" alarm for each panel at Panel lH13-P840:
- 1) Engine Overspeed
- 2) Low Oil Pressure
- 3) High Water Temperature
- 4) Engine Failure
- 5) AC Failure
- 6) Battery 1 Failare
- 7) Battery 2 Failure
- 8) Control Switch in OFF Position The diesel fi;e pumps and controller panels are installed in accordance with.NFPA 20. The power supply to the con-troller is from the station non-Class lE 120V ac power system.
The diesel starting batteries provide in excess of a 24-hour capability for manual or automatic starting of the diesel fire pumps.
V. CO, Fire Protection Systems CO; fire protection is provided for each of the three sta-tion diesel generator rooms as well as for the main generator exciter bearing enclosure. A local control panel 1 COO 4J is provided for the exciter bearing enclosure. A common local control panel (lCOO5J) is provided for the three diesel generator room CO2 systems.
Fire and Trouble alarms, as well as a pushbutton for remote initiation for each of these systems are provided at Panel lH13-P840. Fire and Trouble alarms for the diesel generator rooms will be arranged to provide redundant fire alarm re-ceipt capatility as shown in Figure 2.
The following Trouble Alarms at the local control panel are combined into a Trouble Alarm at-lH13-P840:
i
- 1) Loss of Power
- 2) Alarm Supervisory
, 3) Solenoid Supervisory
- 4) Detector Supervisory
- 5) Lockout Valve Closed-
- 6) Manual Release Circuit Supervisory Local detection circuits are monitored for integrity (Class A per NFPA 72D 1975). The primary power source for the panels is the station non-Class lE 125V de system, which' has a four-hour battery backup following loss of offsite power as the secondary source. A dedicated circuit will be provided for manually connecting a Class 17 source to the control panel (lCOO 5J) for the diesel generator room CO 3 system. This load is within the design limits of the Class lE power system.
~
VI. Standpipe Flow Switches Flow switches are provided in each of the standpipes as well as in the piping connections between the plant service '
water system and the fire protection system. Each of these switches is individually alarmed at lH13-P840.
VII. Turbine Building Smoke Vents Thirty-two smoke vents are provided in the roof-of the.tur-bine building. Each vent-has a fusible link trip as well as a solenoid release for manual opening. An alarm is pro-vided at lH13-P840 which indicates that one or more of the smoke vents is open. A supplementary indicating light is provided for each of six groups of smoke vents which indicates that one or more of the smoke vents in that group is open..
A control switch is also provided on 1H13-P840 to open.each group of smoke vents. The power supply is from the station.
non-Class lE 120V ac power system.
VIII. Halon Suppression System Halon suppression systems are provided in the QA Record Vault and the Telephone Equipment Room, both of which are located in- the service building.
Local control, monitoring of detector,. pull station and release solenoid circuit integrity (Class B per NFPA 72D-1975) is provided by a Pyrotronics " System 3" control panel.
Detectors are Pyrotronics Model DI-4A. Alarms will be pro-vided at lH13-P840 for-fire and trouble for there systems.
The power supply for these systems is from the station non-Class lE 120V ac system. A 24-hour battery backup is pro-vided for the QA Records Vault System.
^~
e
, . .. s FICURC 1 CLINTON POWER STATION - 11 NIT 1 ,
. CIRCUlf ARRA"GEMF.NT FOR ,
DETECTION AND SUPPRESSION SYSTEMS TCATED IN BUIIANGS CONTAININT SAFETY-RELATED EQUIPMENT , I To Diesel Generator 5 d From C0 7
Roome Storage Tank 120 py (1) - Style 1 Signaling Line Circuit
,o r p l (A) - Class A Electrical Supervision :
Manual Connection to (B) - Class B Electrical Supervision 125 V de supply Class IE Source 4 Hour Battery Jackup }-
knual Connection to f, y Class 1E Source 4 Manuel Pushbuttoe 1.ocal lonization Local C0 Stations Detector Zone Controlhanel ( IN . I Control Panel
- Thermal Detectors Ionization 7 (B) Electro-k nual '
Detsctors s
' ~ ~/ Pilot Cabinet l U-* (-(A) 1PA69J 1C005J '
5 3 .
B B
, Fire,Ala_rm/ Trouble _Circui,t,,(1) ,,,j l
! bME.*" 1 dI
- S*'"l.3Dd".cpu,it {11,,_), Fire Protection Panel e in MCR
__Sys_t e.m. _Re_du_n.t_an_t _Fi_re_A_la_rm_C_ir_cu_it__ . ] ,
4.RedundantFireAlarmCircuit i
p - -Fire . .Alarm
. . . /_Ci.rcuit_(1)__
Trouble
-)
g _ .F.i.r.e A_la.rm._/Tr.o.u.b.le
(
.C.i.rcuit. - - .1.)_ , _ _ - 3 3 l peu vu eum.csu a-_ -._.._ y <_.w. net u w.n.ae_mca_ _ _. _
l l l l 1H13-P840 l l g ,g y,, pgp, Local Fre-Actian Sprinkler Panet Sprinkler Panel -g 125 V DC Supply 4 Hour Battery Backup
( .
knual Connection To Class 1E Source
> f j
Tae - 1 Detectors ?_)._)
h 'h I (9) -f f g l Manual Pull l l(B) e (g) [
f(B) .s (B) Station j(g) s 3 1 g***"' '
]
~TJ - - - "I Flow Switch ~ ,
Watir Supply Isolation Alara
) To Sprinklers To Sprinklerm {
Air Pressure Switch Deluge Isolation
$ Water Supply i Valve Cate Valve Cate Valve Check Valve n.
x -.. .. . - , . - _ __ _ _. ,
_ - . . . ~ .. ,
.. . i FIGURE 2-CLINTON POWER STATION UNIT 1 ,
TYPICAL FIRE AND TROUBLE ALARM INDICATION FOR SUPPRESSION SYSTEMS LOCATED IN EUILDINGS CONTAINING SAFETY-RELATED EQUIPMENT l
Fire / Trouble Fire l l
Annunciator Window Annunciator Window i
g-_.--- ; r----- l 1 e l
i i i l l
' ' Control Room i *
- L- - - --- J ' - - --
O ire Alarm danel l ,
1H13-P840_ j
- l. __ _ _ __ __ _ _ _ _ _ _- _ _
F = Fire Alarm Contact T = Trouble Contact R = End of Line Resistor a f " Circuit 2 Circuit 1 *
- - y- - _ - - _ . . - _ - _
\^
e--_ ,
- -! ocal L Panel I ' 7 ,I I
! l t l
i l
Tf I l
1 F I I R L__ _
% ll __ _ _J Circuit 1 operation provides separate visual ~ indication of fire or trouble. Circuit 2 provides fire alarm receipt l-capability should there be an open circuit on Circuit 1.
L
o .
NRC Concern What indication is provided to the operator for a fire detected by the PGCC fire protection system.
Response
A fire bell, trouble horn, and indicating lights are provided ac each fire protection panel.
