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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] |
Text
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' llhnois Power Company Chnton Power Stakin
- P O Dos 670 Chnton. IL 61727 Tel 217 935 6??6 J. Stephen Perry Wce Pre!. cent U-602099 POWER U47 93(02-17 )-LP 8E.100a JSP-071-93 February 17, 1993 10CFR50.90 Docket No. 50 461 Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Clinton Power Station Supplement to Proposed Amendment of Facility Operatipt License No. NPF 62
Dear Sir:
By letter d.ated October 16, 1992, Illinois Power (IP) applied for amendment of the Clinton Power Station (CPS) Technical Specifications to support CPS compliance with the new requirements of Title 10 Code of Federal Regulations Part 20. The proposed changes are necessary to reflect implementation of the CPS Radiation Protection Program in accordance with 10CFR20.1101.
Subsequent to IP's application for amendment, the NRC provided IP with additional guidance on necessary revisions to the Technical Specifications to support implementation of the new 10CFR20 requirements. IP is therefore providing a supplement to its October 16, 1992 Technical Specification amendment request to address the additional guidance on liquid and gaseous release rate limits, high radiation areas and annual report requirements.
A description of the proposed changes and the associated justifications (including a Basis for No Significant Hazards Consideration) are provided in Attachment 2. A marked-up copy of the affected pages from the current Technical Specifications are provi6ed in Attachment 3. For convenience, the attached Technical Specification pages include the changes which were originally requested and thus replace in their entirety the marked-up pages provided in IP's October 16, 1992 amendment request. In addition, an affidavit supporting the facts set forth in this letter and its attachments is provided in Attachment 1.
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Page 2 of 2
- to U 602099 The supporting environmental impact analysis is also provided in Attachment 2. Based upon the evaluation provided, IP has determined that pursuant to 10CFR51.22(c)(9), the proposed license amendment can be categorically excluded from the requirement for an environmental impact statement.
As stated in its October 16, 1992 amendment request, IP is currently scheduled to fully implement the requirements of the revised 10CFR20 on April 1, 1993. Therefore, IP requests that the license amendment, including the attached supplement, be approved prior to April 1, 1993, but not be required to be implemented until that date.
Sincerely yours,
. S. Perry nior Vice sident TAB /msh Attachments cc: NRC Clinton Licensing Project Manager NRC Resident Office, V 690 Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety
1 i
. Attachtsnt 1 to U.602099 4
STATE OF ILLINOIS COUNTY OF DEWITT J. Stephen Perry, being first duly sworn,- deposes and says: .That he is Senior Vice President of Illinois Power Company; - that the c.pplication for amendment of Facility Operating Licens'e NPF 62.has been prepared under his supervision and direction; that he knows the contents thereof; and that to the best of his knowledge and belief said application and the facts contained therein are true and correct.
DATED: This I "7 day-'of February 1993 Signed; b As Q
() T-Subscribed and sworn to before me this /fMday of February 1993.
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9 . Linda S. Frencli - ,
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Attachment 2' to U 602099 i _Page 1 of 6
! LLS-92-001 3'
l Background and Description or Propor.ed Chane.es 4
On May 21, 1991, the Nuclear Regulatory Commission (NRC) issued a j revision to its standards for protection against ionizing radiation, j j 10CFR Part 20. Revised Part 20 became effective on June 20, 1991 and '
j requires implementation on or before January 1,1994 Illinois Power j (IP) plans to implement the new 10CFR20 requirements on April 1 1993 4
and in support of this implementation schedule IP submitted proposed j changes to the CPS Technical Specifications in a letter (U-602052)-dated October 16, 1992.
Subsequent to IP's application for amendment, If participated in l discussions with the NRC on the content of generic guidance currently j being developed to support licensees ~in the implementation of 10CFR20 1 and 10CFR50.36a as recent'.y amended. Based on the recommendations of the NRC, IP is supplementing its October 16, 1992 amendment request to' incorporate some of the generic guidance which was not included in the
- original submittal, i In accordance with 10CFR50.90, the followingichanges to the CPS
, Technical.Spacifications are being proposed in addition to those identified in the previously submitted amenument request:
J
. 1. Technical Specification 6.8.4.f.2 is being revised to read as
- follows
{ "2. Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED 1
AREAS conforming to ten times the concentration values
} in 10CFR Part'20.1001 - 20.2401, Appendix B, table 2, i
column 2;"
i
- 2. Technical Specification 6.8.4.f.7 is being revised to read as
- follows
. "7, Limitations on the dose rate resulting from radioactive material released in gaseous effluents i from the site to areas at or beyond the SITE BOUNDARY i
shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrem /yr to the total body.and less than or equal to 3000 mrem /yr.to the skin, and-
- b. . For Iodine -
131, for Iodine - 133, for tritium,-
and for all radionuclides in particulate _ form-with half-lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ;"
1- 3. Technical Specification 6.9.1.5.a is being' revised ~to11ndicate
- that the annual tabulation of individuals receiving; greater than 100 mrem /yr. includes only those individuals for whom monitoring-was required.
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, Attachment 2 to U-602099 Page_2 of 6
-LS-92 001
- 4. Technical Specifications 6.12.2 and 6.12.3 are being revised to delete " equivalent" (which was added in the previous IP amendment request) from_the term " dose equivalent"'and to identify the maximum dose associated with a high radiation area.
- 5. Note "**" of Technical Specifications 6.12.2 and 6.12.3 is being revised to read as follows:
"** Measurements made at 30 cm (12 inches) from sources of rad'.oactivity."
(The footnote "*" in Technical Specification 6.12.3 is being replaced with footnote "**" as described in a separate amendment request '
submitted in a letter dated Octobar 16, 1992. This change is included in this letter to provide clarification.)
Justification For Proposed Chances The basic requirements for Technical Specifications concerning effluents from nuclear power reactors are_ stated in 10CFR50.36a. These requirements indicate that compliance with effluent Technical Specifications will keep average annual releases of radioactive material in effluents to small percentages of the limits specified in the old 10CFR20.106 (new 10CFR20.1302). These requirements further indicate that operational flexibility is allowed, compatible with considerations '
of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10CFR20.106, 10CFR20.106 in turn refers to Appendix B. Table II, which-provides concentration limits for airborne and liquid effluents. The specified concentration limits are. specific values which ralate to an annual dose of 500 mrem. In addition, 10CFR50.36a states that when using operational flexibility, best efforts shall be exerted -
to keep levels of radioactive materials in effluents asilow as is reasonably achievable (ALARA) as set forth in 10CFR50, Appendix I.
Liould Effluents - (Technical Specification 6.8.4.f.2).
As stated in the. Introduction to Appendix B of;the_new 10CFR20, the liquid effluent concentration _ limits given in Appendix B, Table 2, Column 2, are based on an annual dose ~of 50 mrem. Since a release-
- concentration corresponding' to a- limiting dose rate of 500 mrem / year has been acceptable as.a Technical Specification limit for liquid effluents under the old Part 20 it should not be necessary to reduce this limit by a factor of ten.
Operational history at CPS has demonstrated that the use of the-concentration values associated with the old 10CFR20.106 as Technical Specification limits has resulted in calculated maximum individual' doses to a member of the public that are small percentages of the limits of .
10CFR50, Appendix 1. Therefore, the use of concentration values which correspond to an annual 1 dose of 500 mrem (ten times the concentration values stated in the new 10CFR20, Appendix B, Table 2, Column 2) should-
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1 Attachment 2 1 ..
) '
not have a negative impact on the ability to continue to operate within the limits of 10CFR50, Appendix I and 40CFR190.
As discussed above, the concentrations stated in the new 10CFR20,
! Appendix B. Table 2, Column 2, relate to a dose of 50 mrem in a year.
f When applied on an instantaneous basis, this corresponds to a dose rate i of 50 mrem / year. It is impractical to base effluent monitor setpoint 4 calculations for many liquid effluent release situations on this low
- value when monitor background, sensitivity, and performance must be
- taken into account. Therefore, to accommodate operational flexibility j needed for effluent releases, the limits associated with the liquid -
release rate are being revised to indicate ten times the concentrations -
stated in the new 10CFR20, Appendix B Table 2, Column 2. The j multiplier of ten is proposed because the annual dose of 500 mrem, upon f which the concentrations in the old 10CFR20, Appendix B. Table II, 3 Column 2 are based, is a factor of 10 higher than the' annual dose of 50 mrem, upon which the concentrations in the new 10CFR20, Appendix B, Table 2, Column 2 are based. The proposed change will retain operational flexibility consistent with 10CFR50 Appendix I, concurrent with the implementation of the revised 10CFR Part 20.
) Gaseous-Effluents - (Technical Specification 6.8.4 f.7)
Technical Specification 6.8.4.f.7 provides for a program which ensures 4 the dose from gaseous effluents a t anytime, at and beyond the site boundary, will be within the annual dose limits for unrestricted areas 1
as specified by 10CFR20. The current annual dose limits are the doses associated with the concentrations in 10CFR20, Appendix B, Table II, Column 1 (10CFR20.106). These limits provided reasonable assurance that radioactive material discharged in gaseous effluents would not result in the exposure of a member of the public in an unrestricted area, either l within or outside of the site boundary, to annual average concentrations
- exceeding the limits specified in Appendix B, Table 11 of 10CFR20 (10CFR20.106(b)). The CPS Offsite Dose Calculation Manual'(ODCM) currently specifies release rate limits which restrict', at all times, i the corresponding gamma and beta-dost rates above background' to a member of the public, at or beyond the-site boundary, to less than or-equal to 500 mrem / year to the whole body or to less than or-equal to 3000 mrem / year to the skin. These release rate limits also-restrict, at all
} times, the correspor. ding thyroid dost rate above background to a child -
i via the inhalation pathway to less than or equal te 1500 mrem / year.
, The basis for the instantaneous release rate limits for gaseous releases-4 did not change with the revised 10CFR20. The instantaneous limits are based on a whole body dose limit of 500 mrem / year and a thyroid dose limit of 1500 mrem / year for gaseous releases and are imposed on
, licensees as a control to ensure that' licensees meet 10CFR50 Appendix I requirements. Appendix I of 10CFR50 and 10CFR50.36a were not revised as part of the 10CFR20 revision. .Therefore, for purposes of. maintaining effluent releases ALARA pursuant to 10CFR50.36a and 10CFR50., Appendix I, power reactor licensees-are restricted to instantaneous. limits as currently defined.
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. to U-602099 1
Page 4 of 6 LS 92 001:-
- i. The proposed Technical Specification change does not revise the dose rate limits as identified in the Technical Specifications and implemented by the CPS ODCM. Based on the recommendation of the NRC, the proposed change deletes the reference to 10CFR20 Appendix B, Table 2 and instead explicitly identifies the instantaneous dose rates. This
- change vill help ensure CPS compliance with 10CFR50.36a and 10CFR50 Appendix 1. The proposed change to the Technical Specification is consistent with the CPS ODCM.
i High Radiation Area -(Technical Specification 6.12)
The revised 10CFR20 provides a new definition of a high radiation area j which is based on a radiation level measurement made at 30 cm.
- Therefore, the measurement distance identified in Technical
- Specification 6.12 footnote "**" is bein5 changed from 18_ inches to 30 cm (which is equivalent to 12 inches) to be consistent with
. 10CFR20.1601(a)(1). This represents a conservative change _ since 30 cm 4
is a shorter distance than 18 inches. Implementing this change will j therefore-result in higher dose measurements and more conservative i identification of high radiation areas.
} The revised 10CFR20 also requires that additional controls be in place to prevent unauthorized or inadvertent access to very high radiation areas. Very high radiation areas are those areas where radiation levels could be 500 rads or more in one hour at one meter from a radiation
- source. Therefore, the Technical Specifications identifying controls on access to high radiation-areas are being revised to acknowledge the new upper limit (500 rads) on the determination of a high radiation area.
This will ensure that the measures which are adequate for controlling access to high radiation areas are not used for very high radiation
~
areas which require much more stringent control. This-change will ensure individuals are not exposed to potentially lethal doses as a-result of insufficient controls on access to a very high radiation area.
This change will ensure that the CPS programs for controlling access to
- high radiation areas recognize the requirements for very high radiation
[ areas.
{ Annual Report - (Technical Specification 6.9.1.5) l- Technical Specification 6.9.1.5 requires a report to be submitted
, annually which includes a tabulation of individuals receiving exposures
! _ greater than-100 mrem /yr and their associated man-rem-exposure according to work and job functions. ' Since the revised 10CFR20 only requires.
monitoring for certain individuals as defined in 10CFR20.1502, Technical Specification 6.9,1.5.a is being revised to clearly identify the individuals who are tabulated in the annual report. - This is jul administrative change which provides clarification and-consistency i
between all reporting requirementa. This change will not alter any of
- _ IP's requirements or responsibilities-for protection of the public and ;
, employees against radiation hazards. I 1
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j . Attachment 2-to U 602099 Page 5 of 6 t
? -
LS92-001 Basis for No Sinnificant Hazards Consideration
- In accordance with 10CFR50.92, a proposed change to the Operating
- License (Technical Specifications) involves no significant hazards considerations if operation of the-facility in accordance with the proposed change would not
- (1) involve a significant increase in the probability or consequences of any accident previously evaluated, or (2)
, create the possibility of a new or different kind of accident from any
. accident previously evaluated, or (3) involve a significant reduction in a margin of safety. The propos0d change is evaluated against each of
- these criteria below
I (1) The proposed revisions to the liquid and gaseous release rate limits will not result in a change in the types or amounts of effluents released nor will there be an increase in individual or cumulative radiation exposures. In addition, these changes do not impact the operation or design of any plant structures, systems or
- components. These changes ensure compliance with 10CFR50.36a and 10CFR50 Appendix I and result in levels of radioactive materials in effluents being maintained ALARA, The revision tc the high radiation area controls and dose measurement distance will ensure araas are conservatively posted as high radiation area in j compliance with 10CFR20.1601(a)(1) and provide controls to ensure individuals are not overexposed. This change will not result in a i change to plant design or operation. Therefore, it can be "
concluded that the proposed changes do not involve an increase in
! the probability or consequences of an accident previously
- evaluated.
(2) The proposed changes do noc affect the plant design or operation nor do they result in a change to the configuration of any equipment. There will be no change-in types or increase in the amount of effluents released off-site. As a result, this proposed change cannot create the possibility of a new or'different kind of j accident from any previously evaluated.
I j (3) The proposed revisions do not involve any change in the types or increase in the amount of effluents released off-site. The proposed changes do not involve any actual change in the methodology used in the control of-radioactive wastes'or radiological environmental monitoring. The methodology that-will i
i be used in the control of radioactive effluents and calculation of
. effluent monitor setpoints 'will result 'in the same effluent-release rate as the current methodology now being used. The operational flexibility needed for effluent releases allows the
, use of limits as proposed. In addition, the changes-in measurement distances for determination of high radiation areas
.will not result in an increase in individual or cumulative occupational radiation exposures since it will result'in a more conservative ide tification of high radiation areas. Compliance with the limits oC the new 10CFR20.1301 will be demonstrated by operating within the limits of 10CFR50 Appendix I and 40CFR190.
Therefore, these. changes cannot reduce a margin of safety.
l
t Attachment 2
. to U 602099 Page 6 of 6 LS 92-001:
- Based upon the foregoing, IP concludes that these proposed changes do-not involve a significant hazards consideration. j Environmental Impact Analysis
. The proposed changes to CPS Technical Specifications have been reviewed i against the criteria of 10CFR51.22 for environmental considerations.
l The proposed char.ges do not involve a significant hazards consideration;
, increase the types and amounts of effluents that may be released
- offsite; nor increase the individual or cumulative occupational radiation exposures. The proposed effluent concentration limits requested will allow the liquid and gaseous effluent release rates to l correspond to the current annual dose limits. Compliance with the d
annual dose limits of the new 10CFR20.1301 will be demonstrated by s operating within the limits of 10CFR50 Appendix I and 40CFR190.
l Therefore, the proposed Technical-Specification changes meet the
. criteria given in 10CFRSI.22(c)(9) for a categorical exclusion from the
! requirement far an Environmental Impact Statement.
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