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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 ML20212G6751999-09-22022 September 1999 Forwards Comment Submitted to NRC by Environ Law & Policy Ctr Re Proposed License Transfer for Clinton Power Station 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 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 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 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 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 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 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 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 ML20207D1261999-05-28028 May 1999 Forwards Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206P0641999-05-12012 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Aj Mendiola Will Be Section Chief for Clinton Power Station.Organization Chart Encl ML20206K4351999-05-0707 May 1999 Discusses NRC OI Investigation Rept 3-99-002 Re 981018 Personnel Error Which Resulted in Loss of Offsite Power Which Caused Loss of Only Operating Shutdown Cooling Subsystem ('A' RHR Pump) ML20206J7461999-05-0505 May 1999 Forwards Insp Rept 50-461/99-04 on 990301-0407.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206L5191999-05-0303 May 1999 Informs That on 990420-21 NRC Senior Managers Met to Evaluate Nuclear Safety Performance of Operating Reactors, Fuel Cycle Facilities & Other Matl Licenses ML20206G9691999-04-30030 April 1999 Forwards Insp Rept 50-461/99-11 on 990408-21 & NOV Re Failure to Correctly Translate Design Basis for Hydrogen Mixing Compressors Into EDG Load Calculation ML20206G6671999-04-30030 April 1999 Discusses Insp Rept 50-461/99-01 on 990208-0325.Number of Weaknesses Were Identified in C/A Program Re Approval Process for Issuing Condition Repts,Program Effectiveness Reviews & Issue Resolution.Six non-cited Violations Noted ML20206F2111999-04-27027 April 1999 Informs That NRC Considers Util Actions Associated with demand-for-info Pursuant to 10CFR50.54(f) Re C/A Program Performance at Clinton Power Station,Satisfactory & Therefore DFI Closed ML20206F2141999-04-27027 April 1999 Documents Completion of NRC Review of Specific Corrective Actions Util Committed to Complete Prior to Restarting Clinton Power Station & Forwards NRC Manual Chapter 0350 Restart Action Plan ML20206F1741999-04-27027 April 1999 Informs of Completion of Review of Actions Taken by Illinois Power as Specified in NRC CAL-III-97-09 Issued on 970806. Considers Actions Taken to Be Satisfactory & CAL Re 970805 W Circuit Breaker Failure at CPS Closed ML20205S6921999-04-21021 April 1999 Forwards Insp Rept 50-461/99-06 on 990217-0407.Four Violations Noted Re Professional Atmosphere of Main Control Room & Being Treated as Non-Cited Violations ML20205T5711999-04-21021 April 1999 Forwards Insp Rept 50-461/99-03 on 990208-0318.Eight Violations Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls ML20205P3921999-04-0909 April 1999 Forwards Emergency Preparedness Exercise Insp Rept 50-461/99-08 on 990309-12.No Violations Identified.Exercise Weakness Re Maintenance of Status of Repair Teams Identified During Insp ML20205H3001999-04-0101 April 1999 Confirms Plans to Have Meeting on 990416 at Clinton Power Station to Discuss Results of Plant Performance Review Process & Discuss Progress in Addressing Remaining Open Items in NRC Specific Checklist Which Need Resolution ML20205G2141999-04-0101 April 1999 Ack Receipt of ,Which Transmitted Changes Identified as Rev 26 to CPS Security Plan,Per 10CFR50.54(p) ML20205G5471999-03-26026 March 1999 Advises of Completion of Plant Performance Review on 990202 to Develop Integrated Understanding of Safety Performance. Three Areas of Concern Are Operator Performance,Cap Implementation & Resolution of Engineering Design Issues ML20205C5181999-03-26026 March 1999 Ack Receipt of Revising 2 Previously Communicated Corrective Action Commitments Contained in . Corrections Reviewed & NRC Have No Questions at Present Time ML20204J5071999-03-24024 March 1999 Forwards Insp Rept 50-461/98-29 on 981214-990217.No Violations Noted.Insp Conducted to Review Circumstances Surrounding Unsatisfactory Licensed Operator Performance That Staff Identified During Sept 1998 Operator Exam ML20204F4281999-03-18018 March 1999 Forwards Insp Rept 50-461/99-02 on 990107-0216.Violations Noted.Violation Re Engineering & Work Mgt Personnel Failure to Ensure Overdue Preventive Maint Items Were Completed ML20204E6311999-03-10010 March 1999 Forwards Insp Rept 50-461/99-05 on 990208-12 & Notice of Violation Re Inadequate Radiological Surveys Were Performed in Residual Heat Removal Heat Exchanger Room ML20207K2841999-03-0909 March 1999 Confirms Discussion Between Members of Staffs to Have Meeting on 990325 at Illinois Power Energy & Environ Ctr. Purpose of Meeting to Discuss Performance Improvement Initiatives ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20202J8541999-02-0505 February 1999 Forwards Notice of Proposed No Significant Hazards Consideration & Opportunity for Hearing ML20202H9941999-02-0303 February 1999 Forwards SE Accepting Changes in Quality Assurance Program Continuing to Meet Requirements of App B to 10CFR50 ML20202G4951999-02-0101 February 1999 Forwards Insp Rept 50-461/98-28 on 981214-18.No Violations Noted.Inspector Concluded That Risk Assessment Process for Evaluating on-line & Outage Maint Activities Has Been Developed ML20202H6851999-01-26026 January 1999 Forwards Request for Addl Info Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20202D7871999-01-22022 January 1999 Confirms Discussion Between Members of Staff to Have Meeting on 990205 at NRC Office in Lisle,Il to Discuss Performance Improvement Initiatives.Meeting Will Be Open to Public ML20203A0501999-01-22022 January 1999 Requests Expedited Publication of Encl Notice of Consideration of Issuance of Amend to Facility Operating License,Proposed NSHC Determination & Opportunity for Hearing on 990129 ML20206S0931999-01-22022 January 1999 Forwards Insp Rept 50-461/98-20 on 981118-0106 & Notice of Enforcement Discretion.Inspectors Identified That Operations Personnel Did Not Initiate Condition Repts for Several Nonconforming Conditions Documented in Main Control Room ML20199E1431999-01-12012 January 1999 Refers to Info Provided on 981229 That Was Requested by NRC in .Informs That Info Has Been Reviewed & Forwards List of Mods & Other Engineering Work Products Which Will Be Reviewed During Ssei ML20198S8221999-01-0505 January 1999 Confirms Discussion Between Members of Staff to Have Meeting on 990114 in Clinton,Il to Discuss Licensee Performance Improvement Initiatives 1999-09-08
[Table view] |
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_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _
e e UNITED STATES
- p5 %g~ o, NUCLEAR REGULATORY COMMISSION 8 n REGION 111
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2 801 WARRENVILLE ROAD LISLE, ILLINOIS 60532-4351 July 14, 1998 k ..... f 1
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Mr. Walter G. MacFarland IV Senior Vice President Clinton Power Station Illinois Power Company Mail Code V-275 P. O. Box 678 Clinton,IL 61727
Dear Mr. MacFarland:
On March 13,1997, NRC forwarded a Restart Action Plan to Illinois Power (IP), which was developed in accordance with NRC Inspection Manual Chapter (MC) 0350, " Staff Guidelines for Restart Approval," and included a list of specific items that were to be reviewed prior to restart of Clinton Power Station. The results of our review of those items was documented in a letter and inspection report that was forwarded to IP on July 15,1997. Since then, several activities have transpired which necessitated a revision to the NRC's oversight process and Restart Action Plan.
Included in these activities was the docketing by IP of a simmary of the Clinton Plan For Excellence on February 19,1997, which included new co.;mitments that will be completed prior to plant startup.
This letter forwards our revised Restart Action Plan. The Action Plan includes a summary of the major activities that have taken place since July 1997, the cu6 rent membership of our Site Performance improvement and Restart Oversight Panel, and a Case Specific Checklist specifying the items that the NRC considers as necessary to be addressed prior to plant restart.
The items listed in the Case Specific Checklist will be reviewed prior to plant restart during our scheduled inspections as described to you in our May 28,1998, letter conceming the latest Plant Performance Review of CPS.
The routine, public Restart Oversight Panel Meetings between NRC and IP will be focussed on the progress made by IP to address the specific restart commitments listed in the summary for the Plan For Excellence as well as the items in the Case Specific Checklist. Similar to our July 15,1997, letter, we will forward a letter to IP to close out the revised Restart Action Plan once the items listed in the Case Specific Checklist have been adequately resolved. Our Case Specific Checklist may be modified as necessary if other items requiring resolution prior to plant restart are identified or if a change to IP's commitments is requested.
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- W. MacFarland IV In accordance with 10 CFR 2.7g0 of the NRC's " Rules of Practice," a copy of this letter and its enclosure will be placed in the NRC Public Document Room.
Sincerely,
/
hn A. Grobe, Director Division of Reactor Safety Docket No.: 50-461 License No.: NPF-62 '
Enclosure:
Startup Readiness Action Plan
- .c w/ encl: G. Hunger, Station Manager R. Phares, Manager, Nuclear Safety and Performance improvement J. Sipek, Director- Licensing N. Schloss, Economist Offics of the Attomey General G. Stramback, Regulatory Licensing Services Project Manager .
General Electric Company Chairman, DeWitt County Board State Liaison Officer Chairman, lilinois Commerce Commission i
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- W. MacFarland IV In accordance with 10 CFR 2.790 of the NRC's
- Rules of Practice," a copy of this letter and its enclosure will be placed in the NRC Public Document Room.
Sincerely, f
/s/ John A. Grobe John A. Grobe, Director Division of Reactor Safety Docket No.: 50-461 License No.: NPF-62
Enclosure:
Startup Readiness Action Plan cc w/ encl: G. Hunger, Station Manager R. Phares, Manager, Nuclear Safety -
and Performance Improvement J. Sipek, Director- Licensing N. Schloss, Economist Office of the Attomey General G. Stramback, Regulatory Licensing Services Project Manager General Electric Company Chairman, DeWitt County Board State Liaison Officer Chtirman, Illinois Commerce Commission i
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l DATE 06/Ji/98 09/11/98 R&1lA**r 07//4g8 l
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W. MacFarland IV r Distribution:
Project Mgr., NRR w/ encl C. Paperiello, Rlli w/enci J. Caldwell, R!ll w/enci .
B. Clayton, Rill w/enci SRI Clinton w/enci DRP w/enci TSS w/enci DRS (2) w/ encl Rill PRR w/enci PUBUCJE-Otw/enci Docket File w/enci
[6b GREENS LEO (E-Mail)
DOCDESK (E-Mail) l
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1 Enclosure Startup Readiness Action Plan for Clinton Power Station A. PURPOSE To establish guidelines for approving restart of Clinton Power Station which has been shutdown since September 1996.
B. BACKGROUND NRC Inspection Report 50-461/97012, "Clinton Startup Readiness Action Plan Close-out," dated July 15,1997, documented the completion of the original startup readines.= action plan with the exception of recirculation pump seal performance, feedwater check valve performance, and monitoring of control room activities during restart of the facility. Since then, several activities have transpired which necessitated a revision to the NRC's oversight process.
On August 4,1997, the NRC closed Confirmatory Action Letters (CALs) 50-461/ Rill-96013, 97001, and 97006. CAL Rill-96013 concemed the September 5,1996, event, CAL Rlll-97001 concerned the Clinton Startup Readiness Action Plan, and CAL Rill-97006 involved degraded containment coatings. Additionalissues regarding degraded voltage, breaker reliability, and temperature qualification of emergency diesel generator components remained open pending resolution prior to startup of the facility.
Between August 5 and 15,1997, the NRC performed an Augmented Inspection Team review of a July 22 and August 5,1997, failure of two 4.16 KV circuit breakers. The results of the inspection were documented in NRC Inspection Report 50-461/97018, dated November 24,1997. The NRC determined that the circuit breaker failures were caused by inadequate and ; appropriate maintenance activities, and deficiencies in the corrective action program. The circuit breaker deficiencies resulted in a potential common mode failure being introduced into at least all 4.16KV j Westinghouse Corporation circuit breakers.
On August 6,1997, the NRC issued CAL 50-461/ Rill-97009. The actions that were agreed to be taken in the letter included the preservation of the August 5 failed circuit breaker, the formation of an independent review team to establish the breaker failure mechanism, and the documentation j in a letter to the NRC that reasonable assurance existed that all safety-related circuit breakers 1 will function when called upon. A meeting to discuss the circuit breaker determinations with the NRC is required prior to restart of the facility.
Between August and October 1997, a licensee initiated integrated Safety Assessment (ISA) team identified significant weaknesses in operations, engineering, maintenance, and plant support.
Identified weaknesses included the overall conduct of operations, management and supervision of operations, performance of system engineers, control and understanding of the design basis, maintenance work scheduling, work processes, and radiation protection performance. In addition, the ISA identified weaknesses in barriers to prevent safety problems that were not typical of facilities with a strong nuclear safety culture. These weak barriers were identified at all levels of management associated with CPS and were dispersed throughout CPS' processes.
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On September 26,1997, the NRC issued a Demand For Information (DFI) regarding inadequacies in the corrective actic,n program. The DFl required that, prior to restart, information be provided regarding improvements in the corrective action program and the basis for why I safety-related structures, systems, and components will function as designed if called upon.
Following submittal of the DFI, and prior to the NRC mt2 king a decision on CPS' readiness to restart, NRC intends to meet with Illinois Power management to discuss the response and the basis for confidence that the corrective action pogram is effective. q On January 2,1998, the NRC documented the results of an NRC Special Evaluation Team (SET) which evaluated activities at CPS and validated the findings of the ISA. The SET determined that the ISA conducted an effective diagnostic assessment of the station's performance and reached substantive conclusions. The SET determined, based on an assessment of CPS performance from June 1995 through October 1997, that the following were the root causes of the licensee's problems conceming management and leadership; programs, processes, and procedures; and human performance: (1) management generally did not establish and implement effective performance standards; (2) CPS programs, processes, and procedures did not consistently provide defense in depth to assure plant activities were conducted in a safe manner; (3) problem identification was inconsistent and evaluation and corrective actions were generally ineffective; and (4) management did not ensure that the infrastructure was suitable to support major changes.
On January 15,1998, a letter was forwarded to Illinois Power which documented that NRC senior managers had placed Clinton on the NRC Watch List as a Category 2 plant and that increased NRC attention was warranted until a period of demonstrated improved performance was obtained. NRC letter dated January 21,1998, documented that the NRC Site Performance improvement Oversight Panel activities had been re-initiated.
On February 3,1998, CPS announced several management changes following the January 5, 1998, announcement that PECO Energy Company would provide management services at CPS.
On February 19,1998, CPS docketed a summary of the Plan For Excellence (PFE) including restart commitments. The PFE summary identified actions to achieve broad goals, including strategies for management oversight, personnel development, communications, safety culture, training of personnel, conduct of operations, corrective action program, work management program, procedures, preventive maintenance, plant equipment performance, system engineer effectiveness, backlogs of maintenance and surveillance tests, hardware / design readiness, organization readiness, and program readiness.
Meetings were held between the NRC and CPS on September 26 and November 14,1997, and January 18, February 5, March 17, and May 5,1998, to discuss activities involving circuit breakers, the corrective action program, preventive maintenance, work control, quality assurance, design reviews, plant material condition, the conduct of operations, and the development and implementation of the PFE.
C. SITE PERFORMANCE IMPRO$ MENT AND RESTART OVERSIGHT PANEL MEMBERSHIP An NRC Site Performance Improvement And Restart Oversight Panel has been established and is composed of the members listed below. The panel has the responsibility for developing and l maintaining this Action Plan and reviewing all available information related to CPS' current 2
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I performance and emerging issues, the actions taken by the licensee to address performance weaknesses, and the effectiveness of the licensee's corrective actions. Once the panel has completed the actions listed in the Case Specific Checklist (CSC) below and has determined that the licensee has effectively completed the activities committed to prior to plant restart, the panel will provide a written recommendation for approval of plant restart to the Region ill Regional Administrator. Once licensee performance has improved to a level where this additional NRC attention is no longer necessary, the panel will provide a written recommendation to the Region til Regional Administrator for approval to close this plan.
John A. Grobe, Chairman CPS Oversight Panel Ronald R. Bellamy, Vice Chairman, CPS Oversight Panel Thomas J. Kozak, Chief, Reactor Projects Branch 4 Jon B. Hopkins, Project Manager Troy W. Pruett, Senior Resident inspector Karia K. Stoedter, Resident inspector Carey E. Brown, Resident inspector D. CASE SPECIFIC CHECKLIST The Case Specific Checklist for CPS specifies the items that the NRC considers as necessary to be addressed prior plant restart. These items were derived from the NRC's review of inspection activities including the ISA and SET inspections, other NRC inspections, the PFE, CALs, the DFI, and Licensee Event Reports. The corrective actior:s for these items will be reviewed during the planned inspection activities. The results of the inspections will be evaluated by the NRC's Oversight Panel. The checklist will periodically be revised to reflect changes in plant performance noted by the NRC's Oversight Panel.
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CASE SPECIFIC CHECKLIST REM NUMBER SOURCE DOCUMENT STATUS I Management and Supervision 1.1 Estabhsh and Implement Root cause from the NRC Safety Evaluaton Open Management Expectations Team (SET) Report. CPS Plan For Excellence (PFE) Summary Secton 2.1.
Il Conduct of Operations
- 11. 1 Estabhsh and implement NRC Inspection Reports 97022,97025, and Open Continuing Operator Training 98003 PFE Summary Sections 2.2 and 2.4.
Emphasizing TS Adherence / Knowledge and Recognition of Degraded Conditions
- 11. 2 Estabhsh and implement an NRC Inspection Report 97019. Open Effectrve Equipment Clearance Program 11 3 Review and Revise Abnormal NRC Letter dated June 9,1997," imposition of Open Operations Sections of CMI Penalty." NRC Inspecton Report 98003.
Operatons Procedures PFE Summary Secton 2.2.
11 4 Estabhsh and implement an NRC Inspecton Report 97022. PFE Summary Open Effective Risk Assessment Sectons 2.2 and 2.4.
Program lli Corrective Actions 111. 1 Estabhsh and implement Demand For Informaton (DFI) ttem 1. SET Open Actons to Achieve and Report. PFE Summary 2.3.
Sustain improvement in the Correctve Acton Program til 2 Establish and Implement DFlitem 1. SET Report. PFE Summary 2.3. Open Performance Measures To q Assess Performance IV Structures, Systems, and Components (SSCs) Operational Readiness IV.1 Estabbsh Program to Reduce Confirmatory Acton Letter Rill-97-001. NRC Open and Maintain Main Control Inspecton Report 98003. PFE Summary Room Deficiencies. Secton 2.4.
IV.2 Provide Reasonable DFlitem 2. PFE Summary Secton 2.3. Open Assurance that Deficiencies Affectng Safety Related SSCs Have Been Identified and Cortacted.
IV.3 Resolve issues Associated Confirmatory Acton Letter Rill-97-009. PFE Open With Circuit Breaker Failures. Summary Secton 2.4.
N.4 Resolve Degraded Voltage NRC inspecton Report 97012. PFE Summary Open and Electncal Distributor Secton 2.4.
Concems.
IV.5 Resolve Fire Protecton Safe SET Report. PFE Summary Section 2.4. Open Shutdown Concems i
ITEM NUMBER SOURCE DOCUMENT STATUS IV.6 Complete Root Cause PFE Section 2.4. NRC inspection Report 97012. Open Analysis of Recirculation Pump Seal Failures and Develop Field Performance Measures IV.7 Resolve EDG Concerns SET Report. Open V Maintenance V.1 Develop Process to Review SET Report. PFE Summary Section 2.4. Open Deferrais of Preventive Maintenance items.
V.2 Provide Reasonable LERs 98001 and 98004, NRC inspection Report Open Assurance that Quairfied 97020.
Materials and Parts are Installed in Plant Systems V.3 Establish Maintenance Rule PFE Summary Section 2.4. Open Program VI Design and Configuration Control VL1 Provide Reasonable SET Report. PFE Summary Section 2.4. Open Assurance That Safety System Design and Functional Validation Related SSCs Will Perform (SDFV) Program.
Their Intended Safety Functions as Described in the Design and Licensing Basis.
VI.2 Validate the Adequacy and SET Report. SDFV Program. Open Control of Calculations VI.3 Validate the Adequacy and SET Report. SDFV Program. Open Control of the Setpoint Program.
Vil Emergency Preparedness Program Vll.1 Develop and Implement EP NRC inspection Report 98003,97022 Open improvement initiatives Vill Licensing Actions Vill.1 Develop a List and Schedule General Open for Anticipated Licensing Action Submittals Affecting Plant Restart 1
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