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MONTHYEARML20140C3371997-03-27027 March 1997 Forwards Staff Evaluation for Licensee IPE Submittal for Internal Events & Internal Flooding & Contractor TERs Project stage: Other 1997-03-27
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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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p%% &W y t UNITED STATES g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30066 4 001 o% ...../ .
March 27, 1997 Mr. Paul J. Telthorst Director - Licensing Clinton Power Station i P. O. Box 678 i Mail Code V920 i Clinton, IL 61727 !
SUBJECT:
STAFF EVALUATION OF CLINTON POWER STATION INDIVIDUAL PLANT j EXAMINATION - INTERNAL EVENTS (TAC NO. M74396)
Dear Mr. Telthorst:
j Enclosed is the staff's evaluation for the Clinton Power Station individual
~
plant examinati6n (IPE) submittal for iriternal events and. internal flooding.
~~
The contractor's technical evaluation reports (TER_s) are included with the evaluation. i The staif performed a " Step 1" review during which it examined the IPE results 4 for their " reasonableness," taking into consideration the design and operation of Clinton Power Station. Science & Engineering Associates, Inc., Concord Associates, and Scientech, Inc reviewed the front-end analysis, human reliability analysis, and back-end analysis, respectively, of the IPE submittal. Thair TERs are enclosed as Appendices A, B, and C. respectively, to the staff's evaluation. These TERs were reviewed by the IPE Senior Review Board (SRB) as part of the Office of Nuclear Regulatory Research (RES) quality assurance process. The SRB consists of RES staff and consultants at Sandia ,
and Brochten National Laboratories with probabilistic risk assessment (PRA) l expertise.
In the IPE, you estimated a total core damage frequen~cy (CDF) of about 3E-5/ reactor-year, including a contribution from internal flooding of about 2E-6/ reactor-year. Transients contribute 52 percent, station blackout 37 i percent, internal flooding 6 percent, loss-of-coolant accidents 4 percent, and anticipated transient without scram 1 percent.
To identify vulnerabilities, you addressed the following questions: (1) Are there new or unusual means by which core damage or containment failure could occur compared to those identified in other PRAs: (2) Do the results suggest /
that the plant CDF would not be able to meet the NRC's subsidiary safety goal for core damage (IE-04/ reactor-year); and (3) Are there any systems,
/)
components, or operator actions that control the core damage result (i.e., J greater than 90 ercent)? Your examination did not lead to the identification ks--D/
of any vulnerabi ities. Several plant improvements, however, were identified l and implemented.
NHC m g6H 2 CUPY 970403o150 970327 PDR ADOCK 0500o461 P PDR
i l
,- 1 i
P. Telthorst-
~
l . i-t On the basis of the " Step 1" review, we conclude'that you have met the intent of Generic Letter 88-20.--The staff does not recommend that a more detailed.
- " Step 2" review be conducted. We note, however, that identified weaknesses in
- the IPE may limit its use for'any other regulatory purposes.
If you have any questions regarding the enclosed evaluation, please feel free 1
to contact me at (301) 415-1364.
i : Sincerely,1 Original signed by:
Douglas V. Pickett, Senior Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosures:
As stated cc: See next page l
DISTRIBUTION: W/ encl i Docket File OGC PUBLIC RHernan PD3-3 R/F JRoe ,
ACRS EAdensam (EGA1)
JCaldwell, RIII GMarcus MHodges, RES i
DOCUMENT NAME: G:\CLINTON\CLI74396.LTR To receive a copy of this document, indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy 0FFICE LA:PD3-3, E PM:PD3-3 .c c: ;
NAME CBoylell) DPickettF' l DATE 03/a?/97 03tL3/97
- 0FFICIAL RECORD COPY
._ m P. Telthorst ,
On the basis of the " Step 1" review, we conclude that you have met the intent of Generic Letter 88-20. The staff does not recommend that a more detailed.
" Step 2" review be conducted. We note, however, that identified weaknesses in the IPE may limit its use for any other regulatory purposes.
If you have any questions regarding the enclosed evaluation, please feel free to contact me at (301) 415-1364. .
Sincerely.
Original signed by:
Douglas V. Pickett. Senior Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosures:
As stated cc: See next page DISTRIBUTION- w/ encl Docket File OGC PUBLIC RHernan PD3-3 R/F JRoe ACRS EAdensam (EGA1)
JCaldwell. RIII GMarcus MHodges. RES DOCUMENT NAME: G:\CLINTON\CLI74396.LTR Ta receive a copy of this document, Indicate in the box: "C" = Copy wthout enclosures "E" = Copy wth enclosures "N" = No copy 0FFICE LA:PD3_3, lE PM:PD3-3 .c c:
NAME CBoyle/ k) DPickett F DATE 03/2?/97 03tL3/97 0FtlCIAL RECORD COPY
. . . _ _ _ . - . _ _ _ _ - _ . _ _ _ _ . ~ _ . _ _ _ . _ _ _ _ . _ . . . _ . _.- _. . _ . _ _ . _ _ _ . . _ _
P. Telthorst '
On the basis of the " Step 1" review, we conclude that you have met the intent !
( of Generic Letter 88-20. The staff does not recommend that a more detailed, s l
" Step 2" review be conducted. We note, however, that identified weaknesses in the IPE may limit its use for any other regulatory purposes.
l If you have any questions regarding the enclosed evaluation, please feel free to contact me at (301) 415-1364.
Sincerely.
l w =h V f i l Douglas V. Pickett. Senior Project Manager Project Directorate III-3 t
Division of Reactor Projects III/IV l Office of Nuclear Reactor Regulation -
Docket No. 50-461 i
Enclosures:
As stated cc: See next page t
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l Mr. Paul J. Telthorst Clinton Power Station Illinois Power Company Unit No. 1 cc:
Mr. Wilfred Connell Vice President Illinois Department Clinton Power Station of Nuclear Safety Post Office Box 678 Office of Nuclear Facility Safety Clinton, Illinois 61727 1035 Outer Park Drive Mr. Daniel P. Thompson Manager Nuclear Station Engineering Department Clinton Power Station Post Office Bdx 678
! Clinton, Illinois 61727 Resident Inspector )
l U.S. Nuclear Regulatory Commission i RR#3, Box 229 A <
l Clinton Illinois 61727 l l Mr. R. T. Hill l Licensing Services Manager j General Electric Company 175 Curtner Avenue, M/C 481 San Jose, California 95125 Regional Administrator Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road l Lisle Illinois 60532-4351 l Chairman of DeWitt County c/o County Clerk's Office DeWitt County Courthouse Clinton, Illinois 61727 Mr. J. W. Blattner Project Manager Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603
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CLINTON NUCLEAR POWER PLANT INDIVIDUAL PLANT EXAMINATION STAFF EVALUATION REPORT l
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l ENCLOSURE
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- 1. INTRODUCTION On September 23, 1932, Illinois Power (licensee) submitted tne Q11nton Nuclear
, Power Plant individual plant examination (IPE) in response to Generic Letter
. (GL) 88-20 and associated supplements. On July 21, 1995, the staff sent a request for additional information to the licensee. The licensee responded in a letter dated November 22, 1995.
The staff performed a " Step 1" review of the Clinton IPE submittal. As part of this review, Science & Engineering Associates, Inc., Scientech, Inc., and Concord Associates reviewed the front-end a'nalysis, back-end' analysis, and the human reliability analysis (HRA), respectively. The Step 1 review focused on whether the licensee's method was capable of identifying vulnerabilities.
Therefore, the review considered (1) the completeness of the information and
' (2) the reasonableness of the results given the Clinton design, operation, and history. A more detailed review, a " Step 2" review, was not performed as part of this IPE submittal. Details of the con' tractors' findings are given in the technical evaluation reports (Appendices A, B, and C) attached to this staff
. evaluation report (SER).
i In accordance with GL 88-20,'the licensee proposed to resolve Unresolved Safety Issue (USI) A-45, " Shutdown Decay Heat Removal Requirements." No other USIs or generic safety issues were proposed for resolution as part of the Clinton IPE.
II. EVALUATION Clinton Nuclear Power Station is a boiling water reactor (BWR) 6 with a Mark III containment. The licensee estimated a core damage frequency (CDF) of about 3E-5/ reactor-year from internally initiated events, including a contribution from internal flooding of about 2E-6/ reactor year. The Clinton CDF compares reasonably with that of other BWR 6 plants. Transients i ' contribute 52 percent, station blackout -37 percent, internal flooding 6 -
percent, loss-of-coolant accidents 4 percent, and anticipated transient without scram 1 percent.
" On the basis of the licensee's Fussell-Vesely importance analysis, the most-important contributors to the estimated CDF sequences are associated with loss
- of offsite power, failure of the high pressure core spray (HPCS) system, failure of the reactor core isolation coolant (RCIC)* system, transients l without isolation, transients with isolation, failure of the fire protection system, and failure of t.he automatic depessurization system (ADS).
The licensee performed an HRA to document and quantify potential failures in human-system interactions and to quantify human-initiated recovery-of-failure events. The licensee identified the following operator actions as important in the estimate of the CDF: failure to recover offsite power in 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, failure to recover HPCS, failure to recover RCIC, failure to manually initiate ADS, failure to recover Division 2 within the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and failure to manually initiate service water.
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The licensee's Level 1 analysis appears to have examined the significant initiating events and dominant accident sequences. However, it does not appear that the licensee incorporated plant-specific experience in the calculation of equipment failure rates and initiating event frequencies.
Responding to staff's'RAI, the licensee stated that very limited plant-specific data exists because Clinton'is a relatively new plant. The licensee cited examples showing that plant-specific failure data are comparable to or better than the generic data used. However, plant-specific data could have been used to update the generic data by means of a Bayesian process.
Insufficient incorporation of plant experience may not have a significant !
', impact on the total CDF but it may have a significant impact on' the relative contributions of the various sequences and failure events and, therefore, it may limit the ability-to identify plant-specific insights and improvements. ;
Also, the Clinton IPE credited local repair of various equipment components and systems (including diesel generators, pumps, valves, and instrumenfation) and has taken credit for up-to-two component / system repair activities. The licensee stated that the repair activities credited in the Clinton IPE were based on actual emergency exercises; however, the quantification of these repair activities is based on a generic Electric Power Research Institute database. ,
The licensee, as part of its response to staff's RAI, performed a sensitivity analysis that involved removal of all credited equipment repair recoveries, except thos.e involving offsite power, direct current power, and operator actions performed from the control room. The result was~a'n insignificant increase of the CDF from about 3E-05/ reactor-year to about 4E-05/ reactor-year, a factor of 1.5. The relative contributions of individua,1 accident sequences also were not significantly altered. In no instances were increases in individual accident sequence frequencies greater than a factor of 2.4.
Although two new sequences.were introduced, their frequencies were less than IE-08/ reactor-year. .
l The success of equipm'ent repair depends on many important plant-specific factors such as the type of failure, time needed for diagnosis, time needed i for repair'(which may range'from a very few hours to several days), crew competing tasks under different accident conditions, and crew availability (especially when multiple-repairs are credited). These factors do not appear to have been taken into consideration in the Clinton IPE in modeling and estimating equipment repair probabilities under accident conditions.
Therefore, although the staff concludes that the credit.taken for repair of equipment did not have a significant effect on the IPE's results, the staff believes that insufficient examination of important aspects of human performance under severe accident conditions may have limited the ability to identify factors critical to the accomplishment of the actions modeled.
The Clinton IPE results are in line with those for similar BWR 6 plants in
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both the most dominant initiators and the most dominant accident sequences.
Therefore, the staff believes it is unlikely that the limitations identified have impacted the licensee's overall conclusions from the IPE and its capability to identify vulnerabilities. However, they may have limited its ability to gain insights and identify improvements.
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0n the basis of the licensee's IPE process used.to search for decay' heat removal (DHR) vulnerabilities, and review of Clinton plant-specific features,
' the staff finds the licensee's DHR evaluation consistent with the intent of the resolution of USI A-45 " Shutdown Decay Heat Removal Requirements."
The licensee evaluated and quantified the results of the severe accident progression. The back-end analysis results are as follows: early containment
, failure (including isolation failure) will occur about 3 percent of the time, late containment failures will occur about 2 percent of the time, and bypass will occur less than 1 percent of the time. The containment. remains intact 95 percent of the time.
The staff has also identified a weakness in the Clinton IPE back-end analysis.
The licensee, responding to staff's request for additional information, did not provide a justification for the very small probability of containment failure from hydrogen ignition after power recovery under station blackout conditions, or for no containment failure from excessive fuel-coolant interaction. Although, as stated in the IPE, Clinton has "the largest free air volume and suppression pool Volume to rated thermal power of any domestic Mark III," it is not clear whether the result that the containment remains intact 95 percent of the time is skewed because of the licensee's optimistic '
approach to the examination of hydrogen combustion and ex-vessel steam explosion phenomena. It is noted, however', that although certain phenomena may have been~ treated optimistically, the licensee has considered all relevant phenomena. ' The licensee developed containment event trees to characterize containment response to severe accidents and examined several severe accident l phenomena in detail for their applicability to Clinton. Also, the licensee '
used the Modular Analysis Accident Program to ' analyze representative sequences and addressed phenomenological uncertainties of accident progression through sensitivity studies. These findings coupled with the fact that the Clinton containment is substantially stronger than any other Mark III containment -
leads the s.taff to conclude that the licensee did not miss a vulnerability -
with respect Clinton's containment. ;
The licensee's r.esponse to' containment performance improvement program ;
recommendations is consistent with the intent of GL 88-20 and.its '
Supplement 3. ,
Some insights and uni'que plant safety features identified by the licensee are the following:
- 1. four-hour battery lifetime
- 2. motor-driven feedwater pump
- 3. three safety-related divisions of core cooling, each of which has its I own emergency diesel generator and cooling water
- 4. ability of the emergency core cooling system pumps to operate when,the suppression pool is saturated !
- 5. ability to cr,oss-connect the fire protection system for core injection l
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- 6. a cont'ainment with the largest free air volume and suppression pool volume with respect to rated thermal power of any domestic Mark III.
To identify vulnerabilities the licensee addressed the following questions:. )
(1) Are-there new or unusual means by which core damage or containment failure could occur. compared to those identified in other PRAs? (2)-Do the results suggest that the plant CDF would not be able to meet the'NRC's subsidiary safety goal for core damage (IE-04/ reactor-year)? (3) Are there any systems, components, or operator actions that control the core damage result (i.e., greater.than 90 percent). The licensee's examination did not lead to the' identification of any vulnerabilities. Several plant improvements, however, were identified. The following improvements have been implemented: I
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- l. operator training to emphasize the importance of maintaining offsite l power- !
- 2. operator training to emphasize the importance of manual ADS initiation
- 3. modification of the HPCS surveil, lance procedure to test the suppression pool suction path
- 4. installation of a bypass line to allow easier use of the fi.re protection system for vessel makeup
- 5. operator training to emphasize the importance of maintaining offsite power.to prevent offsite releases
- 6. operator training to emphasize the importance of alternate current power recovery .
- 7. operator training to emphasize the importance of manually isolating the containment bypass path into the fuel pool cooling / cleanup line during station blackout
- 8. operator training to emphasize the significance of scram system hardware failures as related to release frequencies III. CONCLUSION Based on the above findings, the staff notes thati (1) the licensee's IPE is complete with regard to the information requested by Generic Letter 88-20 (and associated guidance in NUREG-1335), and (2) the IPE results are reasonable given the Clinton Nuclear Power Station. design, operation, and history. As a '
result, the staff concludes that the licensee's IPE process is capable of identifying the most likely severe accidents and severe accident .
. vulnerabilities, and therefore, that the Clinton Nuclear Power Plant IPE has met the intent of Generic Letter 88-20. However, the staff noted limitations in the. licensee's IPE associated with (1) the extensive use of generic data, (2) the' credit taken for equipment' repair, (3) the credit taken for containment performance under hydrogen combustion upon power recovery
-(negligible failure probability), and (4) the credit taken for containment j 4
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' 8 performance under ex-vessel steam-explosion conditions (no containment failure). These limitations may limit the IPE's usefulness for other regulatory , applications.
It should be noted that the staff's review primarily focused on the licensee's ability to examine Clinton Nuclear Power Station for severe accident -
vulnerabilities. Although certain aspects of the IPE were explored in more detail than others, the review is not intended to validate the accuracy'of the licensee's detailed findings (or quantification e timates) that stemmed,from the examination. Therefore, this SER does.not constitute NRC approval or endorsement of any IPE material. for purposes other than those associated with meeting the intent of GL 88-20.
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l l i APPENDIX A FRONT-END TECHNICAL EVALUATION REPORT S
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