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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:NRC TO STATE/LOCAL GOVERNMENT
MONTHYEARML20137B4071986-01-10010 January 1986 Informs That,Based on Review of Issues Raised in Request for Reevaluation of Updated OL Antitrust Review,Updated No Significant Change Finding Will Not Be Amended.Fr Notice & Reevaluation Encl ML20132E3631985-09-26026 September 1985 Ack Positions in 850827 & 0912 Ltrs Re Pending Overinsp Program Termination Requests & Proposed Suspension of Program Activities.Responses to Comments Encl.Approval of Termination Requests Discussed ML20135D1561985-09-10010 September 1985 Forwards Fr Notice of Updated Finding of No Significant Antitrust Changes & Time for Filing Requests for Reevaluation & Staff Analysis ML20134K3691985-08-14014 August 1985 Responds to 850710 Request Re Status of Implementation & Review Schedules.Util Conforms to or Has Provided Acceptable Justification for Deviations from Reg Guide 1.97 W/Exception of Fuel Zone Level Instrumentation.Dcrdr & SPDS Discussed ML20132D9071985-07-15015 July 1985 Responds to 850603 Comments on FA Spangenberg 850524 Request for Approval of Alternate Method of Meeting Intent of Certain Portions of Rev 1 to Reg Guide 1.108.Agrees That Periodic Start & Load Tests Can Be Combined ML20127D3831985-06-17017 June 1985 Forwards Synopsis of 850509 Meeting W/State of Il Re Util Overinsp Program ML20127A7601985-06-14014 June 1985 Forwards NRC Responses to State of Il Questions Re Util Proposed Changes to Overinsp Program & Procedures & Util Responses to State of Il Questions 1986-01-10
[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] |
Text
O y b September 26, 1985 t--
Docket No. 50-461 Allen Samelson, Esq.
Assistant Attorney General, Environmental Control Division, State of Illinois 500 South 2nd Street Springfield,.!L 62706
References:
- 1. Letter, A. Samelson to J. Keppler dated 8/27/85
- 2. Letter, A. Samelson to J. Keppler dated 9/12/85
- 3. Letter, D. Hall to J. Keppler, U-600197, dated 7/26/85
- 4. Letter, D. Hall to J. Keppler, U-600211, dated 8/6/85
- 5. Letter, D. Hall to J. Keppler, U-600215, dated 8/12/85
- 6. Letter, D. Hall to J. Keppler, U-600244, dated 9/6/85
- 7. Letter, J. Keppler to D. Hall dated 9/13/85
Dear Mr. Samelson:
This letter acknowledges the positions stated in your letters dated August 27 and September 12, 1985 (references 1 and 2) concerning Illinois Power (IP)
Company's pending Overinspection Program temination requests and their proposed suspension of Overinspection Program activities. Your positions have been and are being carefully considered during Region III review of IP's requests.
As you know, IP requested temination of the Overinspection Program for electrical hangers; HVAC duct and duct supports; and cable tray, conduit, cable, and cable terminations based on 1984 Overinspection Program results (references 3-5,respectively). We initially denied this request.
Subsequently, IP proposed suspension of Overinspection Program activities in the requested corrmodities, at its risk, pending completion of Region III's review of IP's temination requests (reference 6). We have concluded that IP may suspend Overinspection Program activities, at its risk, pending receipt-and review of requested 1985 data (reference 7). This conclusion was based on infomation reviewed by Region III to date which supports the~ basis provided by IP for its termination requests. It is noted that new information based on NRC inspections was received and evaluated between the time of the initial denial and the acceptance of the proposal to suspend o/erinspection activities. It should also be noted that suspension is not equivalent to termination. Should Region III review of 1985 data reveal some significant anomaly not present in the 1984 Overinspection Program data, then Region III will require IP to continue Overinspection Program activities within the anomalous corrmodity.
8510010060 850926 D3 ADOCK O Q1 h h.\
Allen Samelson, Esq. September 26, 1985 t
Your September 12, 1985 letter requested a written response and a response to your letter of August 27, 1985 as well (references 1 and 2). -The requested s responses are provided in the enclosure to this letter. I believe that this information is responsive to your concerns.
If you have any additional questions or comments, or if you require additional infonnation concerning the enclosure, please feel free to contact.
Mr. R. F. Warnick of my staff at (312) 790-5575. As Mr. Warnick previously stated, we would be pleased to meet with you to discuss this mattcr in greater detail if you desire.
- Sincerely, 1riginal . sf rned by ey
- s G. Kc;pler James G. Keppler l'egional Administrator
Enclosure:
Reply to Illinois Attorney General letters dated August 27 and September 12, 1985 i
cc w/ enclosure:
W. C. Gerstner, Executive Vice President, Illinois Power Company i
DMB/ Document Control Desk (RIDS)
Resident Inspector, RIII Richard Hubbard Gary N. Wright, Manager Nuclear Facility Safety Jean Foy, Prairie Alliance l
H. S. Taylor, Quality Assurance bec: J. Taylor, IE H. Denton, NRR R. Goddard, ELD lit.<
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Enclosure
$N REGION III RESPONSES TO ILLIN0IS ATTORNEY GENERAL (IAG) COMENTS A. Responses to IAG letter Samelson to Keppler dated August 27, 1985
- 1. IAG Comment Firstly, in the referenced letters IPC has provided Overinspection Program results only as of December 31, 1984. Data for 1985 should be provided in order to confirm that the 1984 data is still representative of current program results. In our opinion, it would be imprudent to allow deletion of comodities from the Overinspection Program in the absence of current data.
Region III Response 4
Region III has requested certain 1985 overinspection results be provided for the commodities subject to Illinois Power's (IP) requests. The request, as defined in our letter to IP dated September 13, 1985, included all data that Region III deemed essential to complete our review. The requested data will be reviewed by Region III to determine whether the 1984 data is still representative of current program results. This is consistent with your request.
I 2. IAG Comments Secondly, we urge NRC to independently determine the " safety significance" of the nonconformances identified by the Overinspection Program before concurring with the removal of comodities from the program. At a minimum, NRC should conduct a detailed review of the documents relied upon by IPC in reaching the conclusion that none of the identified nonconformances are "hafety significant". We would expect the NRC's assessment to be documented and available for our review.
In this regard, the IAG believes that special attention should be given to the categorization of nonconformances by IPC. Two examples will illustrate the basis for this concern. In many cases, IPC relies upon the exis'tence of future testing programs.in order to conclude that a group of nonconformances are not safety significant.
, Such reliance may be misplaced as was demonstrated during the CAT i
inspection by the failure of the electrical separation walkdowns to detect discrepant conditions. Also noteworthy in this regard is the CAT inspection finding.that work performed by IPC staff on systems and components after turnover from construction has been ineffectively controlled. Another example is the IPC conclusion that wood debris left in cable trays presents no safety-significant i
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condition. Yet it appears that IPC failed to consider the fire hazard that such debris might pose. Thus, we believe NRC should conduct a detailed review of the nonconfomance categorizations in order to independently determine whether all implications of the nonconforming attributes have been adequately identified and addressed by IPC.
Region III Response Region III has reviewed a sample of the documents relied upon by IP in their engineering evaluations of the safety significance of overinspection program identified nonconfomances. The results of the review have been documented in Inspection Report 50-461/85044.
In addition, Region III has asked that IP provide the results of some safety significance evaluations perfomed for nonconformances identified in 1985-within the comodities for which termination was requesuu. This information will be used by Region III in reaching a decision concerning IP's termination requests.
The matter of reliance on future activities to disposition and evaluate the significance of Overinspection Program identified deficiencies was the subject of questions and answers between IP and Region III (refer to letter J. Keppler to D. Hall dated April 11, 1985 and each IP termination request, enclosure 2, IP RESPONSE TO ENCLOSURE 2 NRC Ouestion C.1, respectively). In addition, Region III reviews of engineering evaluations to date, as ' documented in Inspection Reports 50-461/85027 and 85044, have not revealed any instance in which IP has improperly categorized nonconformances or misplaced reliance on future test activities. Region III specifically included a review of evaluations taking credit for future testing activities in the first Inspection Report (50-461/85027). That inspection revealed that "no instances of improper reliance on future actions to disposition the NCRs were discovered."
- 3. IAG Comment Thirdly, we remain concerned that thousands of nonconformances were undetected by the normal QA/QC program. It is significant that for a number of commodities, approximately 50% of the items inspected required the issuance of an NCR documenting at least one nonconforming attribute. The IAG believes that IPC should (1) conduct analyses to identify the root cause(s) which allowed nonconformances to remain undetected by the normal QA/QC program and (2) initiate appropriate corrective actions to address the root causes. The root cause analyses and corrective action program should be provided to NRC and the IAG.
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Region III Response This coment is essentially identical to earlier IAG questions and coments to which Region III has already responded (please refer to letter Keppler to Samelson dated June 14, 1985, enclosure 1,.page 9 Region III response to IAG Question 14). While the occurrence of .
high nonconformance rates is undesirable, the more important consideration is the safety significance of the nonconformances.
Since the time of Region III's . earlier response, Region III and the Construction Appraisal Team have conducted extensive reviews of the as-built condition of the commodities subject to IP's current termination requests.and of the significance of deficiencies identified during conduct of the Overinspection Program.
The requirements of 10CFR50, Appendix B, Criterion XVI apply to IP's activities and are being enforced by Region III. Should significant conditions adverse to quality be identified during Region III's review, the cause of the condition will have to be determined by IP if not already determined and corrective action taken to preclude repetition.
- 4. IAG Comment Finally, the IAG believes, based upon findings of the recent CAT-inspection, that the Overinspection Program should include systems "important-to-safety" but not " safety-related". As you are aware, the CAT inspection confirmed that there are more hardware and QA/QC program deficiencies in areas not covered by the Overinspection Program. Consequently, we believe that commodities installed in important reactor control systems that are not presently addressed by the Overinspection Program, such as the feedwater control system, should be . included in the Program, especially if other commodities are removed from Overinspection.
Region III Response This coment is essent'ially identical to earlier 1. 3 questions and coments to which Region III has already responded (please refer to letter Keppler to Samelson dated June 14, 1985, enclosure 1, page 7 Region III response to IAG Question 12). In addition, this matter was specifically discussed in the meeting held between Region III and the IAG on May 9,1985. in the Region III Office (please refer to letter Keppler to Samelson dated June 17, 1985, enclosure, page 2).
The NRC Construction Appraisal Team (CAT) Report Executive Summary (Inspection Report 50-461/85030) stated in part that "An effort was madebytheNRCCATtoassesstheIPOverinspection(IP01) Program.
The NRC CAT found fewer program or hardware deficiencies in areas 3
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. covered by the IP01 Program than in areas not covered by the IP0I Program." Based on the scope and results documented by the NRC CAT, it is clear that the CAT Report Executive Sumary was referring to findings related to vendor supplied safety related components which were not subject to IP0I (e.g., vendor supplied tanks and heat exchangers with deficient weldments; vendor supplied panels with wiring deficiencies; and vendor supplied, skid mounted equipment with incorrect or' unidentified fasteners) rather than referring to findings related to plant structures, systems, and components (SSC's) classified as "important to safety" but not " safety related".
Region III has carefully reviewed the IAG's suggestion that important reactor control systems, such as the feedwater control. system (FWCS),
be included in the Overinspection Program. The Clinton Power Station (CPS) Final Safety Analysis Report (FSAR) states the following
, concerning the classification of the FWCS: "This system is a power generation system and is not related to safety". The failure of FWCS components has been analyzed (as documented in chapter 15 of the CPS FSAR) and included in the design basis for CPS safety systems. The failure of the FWCS does not impact plant safety; however, FWCS failures have a direct impact on power generation reliability. Increasing the quality-of FWCS construction and the reliability of FWCS operation is a commercial consideration.
The Overinspection Program scope, which includes systems "important to safety" (fire protection and radwaste) was established by IP and concurred in by Region III in late 1982 and early 1983. Region III does not believe there is either a regulatory basis or sufficient technical justification to require a change to the program scope at this late date; however, Region III has discussed with IP how we can be more responsive to IAG connents. Deficiencies in systems "important to safety" have been and are being identified, dispositioned, and corrected by IP's Quality Assurance Program.
B. Responses To IAG letter Samelson to Keppler dated September 12, 1985
- 1. IAG Coment Firstly, it is our understanding that NRC concurrence is required before termination of any commodities from the Overinspection Program. Given the history and continuance of QA/QC problems at Clinton, the reasons for this requirement are obvious. Although it appears this procedure has been adhered to thus far, the September 6,1985 IPC proposal would, if accepted by NRC, be a departure from this established procedure. Either the data and engineering evaluations thereof warrant termination for a specific commodity or they do not. Unless the fonner is true and NRC is able and willing to document its confidence in that conclusion, concurrence for removal of a comodity from the Overinspection Program should not be given, in our opinion.
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Region III Response
)~ NRC concurrence is required before termination of any comodity from ,
the Overinspection Program. IP requested termination of i Overinspection for specific commodities in their letters of July 26, l August 6, and August 12, 1985. Region III was unable to concur in IP's requests for the reasons documented in our August 30, 1985 and ,
September 13, 1985 letters to IP.
- IP strongly believes that there is sufficient basis for termination j of the requested commodities, as expressed in their letter to Region i
III(U-600244) dated September 6, 1985. Based on its strong belief,
! IP proposed suspension of Overinspection-activities in the requested comodities pending submittal of additional information and
- completion of Region III's review.
Suspension of Overinspection activities and termination of the Overir.spection Program by comodity are not equivalent. Suspension 4
of activities was undertaken by IP as a cost saving measure at its i own risk. IP remains committed to performing Overinspection for the suspended commodities unless and until released from their comitment
! by Region III. Overinspection Program termination by comodity .
i represents a release from previous comitments and requires Region III concurrence.
In this instance, Region III allowed IP to assume the risk of suspending Overinspection activities in the requested comodities on j the following basis:
. a. Region III's confidence in the quality of the hardware involved l based on direct NRC inspection results.
- b. Region III's confidence-in the adequacy of engineering
- evaluations performed by Sargent and Lundy of the safety significance of deficiencies identified by the Overinspection Program in 1984.
1 c. Region III's confidence in the adequacy of implementation of l the Overinspection Program based on direct Region III inspection results.
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- d. IP's acknowledgement that it might have to resume overinspection of the suspended comodities.
- This basis was documented in Region III's September 13, 1985 letter to IP.
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i Region III's review of IP's termination requests will continue upon j receipt of requested 1985 Overinspection Program results for the -
requested comodities. Our conclusion on termination will be
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documented following our review and evaluation of the data.
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k hangers have been inspected under the Overinspection program. This information, when combined with the large body of information already available to Region III, should provide a fim and conservative basis for decision on IP's pending termination requests.
The subject of evaluation of nonconformances, considering the -
cumulative effects of nonconforming attributes, was addressed by IP for each comodity for which tennination was requested. Please refer to IP's response to NRC questions A.3, B.3, and B.4 in enclosure 2 to each of IP's termination requests (IP letters U-600197, U-600211, and U-600215 dated July 26, August 6, and August 12, 1985, respectively).
Region III has inspected nonconformances, dispositions, engineering evaluations, and the as built condition of commodities subject to the pending tennination requests. The results of these inspections have been documented in inspection reports. Our engineering specialist inspector, Mr. Muffett, has recently completed two inspections relative to the pending termination requests for electrical hangers, conduit, cable tray, HVAC duct, and HVAC duct supports. The results of his inspections, which have been documented in Inspection Reports 50-461/85044 and 85049, revealed that the procedures dealing with the disposition of discrepancies were properly
, implemented; that engineering evaluations demonstrated that FSAR commitments were met as they pertain to engineering design and analysis; and that the as-built condition of components inspected was found to be acceptable.
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- 2. IAG Comment Secondly, there appears to be a substantial dispute regarding the safety significance of nonconfonnances identified by the Overinspection Program. Specifically, NRC has stated its concern regarding the high rate of nonconformances per item,' while IPC believes the rate of nonconformances ge_r attribute is .the appropriate basis for engineering evaluation and, on this basis, contends no safety significant nonconformances have been shown. In our August 27, 1985 letter to you, the IAG raised questions as to both the number and categorizatior, of nonconformances. These questions remain unanswered. Because plant structures and systems perform in an integrated manner and are subject to cumulative effects, evaluation of nonconformances solely by discrete
" attribute" is inappropriate, in our view.
In this regard, we understand that Jim Muffett has inspected the Sargent & Lundy engineering evaluations and has found no significant deficiencies therein. We would hope that the safety significance issue has been thoroughly examined by NRC. In any event, we believe an appropriate resolution of this issue should be achieved and documented prior to NRC concurrence with the IPC proposal.
Region III Response The matter of presenting Overinspection Program results in terms of items versus attributes does not relate to a " substantial dispute regarding the safety significance of nonconformances identified by the Overinspection Program"; the matter in dispute relates to the sufficiency of docketed infonnation supporting IP's conclusion that Overinspection Program findings have no significance to plant safety. Region III agrees with IP's contention that the rate of nonconforming items, unto itself, is not an appropriate basis for engineering evaluation. The key question is the confidence that can be achieved based on the sample size and the significance of identified deficiencies with respect to plant operational safety.
Region III has initiated actions on its own [ inspections] and has requested actions by IP to obtain additional docketed infonnation.
The information is needed by Region III in order to achieve a thorough understanding of the significance of Overinspection Program findings; to verify that no new trends or types of discrepancies have been discovered; to verify the sufficiency of the sample to support a conclusion of high confidence that the results of reinspections are representative of overall quality for each comodity; to verify that IP's conclusions.concerning the significance of Overinspection Program findings remain valid in light of the total body of data accumulated for each applicable commodity; and to enable Region III to determine that a sufficient sample of both conduit and cable tray 6