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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 UTILITY
MONTHYEARML20058G2591990-11-0505 November 1990 Confirms 901106 Mgt Meeting in Region III Ofc to Discuss Violations Noted in Insp Rept 50-461/90-05 ML20058G1681990-11-0202 November 1990 Forwards Insp Rept 50-461/90-22 on 901015-19.Noncited Violation Noted ML20058D4331990-10-26026 October 1990 Informs That More than 60 Days Required to Complete Review of Util 900525 Submittal Incorporating Changes in QA Program Description ML20058D1791990-10-23023 October 1990 Forwards Safety Insp Rept 50-461/90-19 on 900822-1003.No Violations Noted ML20058A7471990-10-19019 October 1990 Forwards Safety Insp Rept 50-461/90-20 on 900924-28.No Violations Noted ML20058D5971990-10-18018 October 1990 Informs That Util 900925 Response to Generic Letter 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2 'Vendor Interface for Safety-Related Components,' Acceptable ML20059F8891990-09-10010 September 1990 Ack Receipt of W/Payment of Civil Penalty in Amount of $25,000 ML20059H0641990-08-24024 August 1990 Advises That 880729 & 890921 Responses to Generic Ltr 88-01, IGSCC in BWR Austenitic Stainless Steel Piping, Acceptable W/Some Exceptions.Review of Exceptions Requested ML20059C0981990-08-21021 August 1990 Forwards Details of Allegation RIII-90-A-0065.Encl Withheld (Ref 10CFR2.790) ML20056B4361990-08-0808 August 1990 Comments on Util 891229 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve (MOV) Testing & Surveillance. Addl Discussion of Plans for Periodic Verifications of Proper MOV Program Description Requested ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20056A7651990-08-0303 August 1990 Forwards Safety Insp Rept 50-461/90-15 on 900723-27.No Violations Noted.Exercise Weakness Identified & Will Require Corrective Action ML20055J3251990-07-25025 July 1990 Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Re 900411 Control Rod Event ML20055J1671990-07-25025 July 1990 Forwards Safety Insp Rept 50-461/90-11 on 900512-0703. Violations Noted.Nrc Wants to Encourage & Support Licensees Initiatives for self-identification & Correction of Problems,Therefore,Notice of Violation Will Not Be Issued ML20055J0001990-07-25025 July 1990 Forwards Corrected Forwarding Ltr for Requalification Exam Rept 50-461/OL-90-03,including Results of Addl Senior Reactor Operators W/Passing Grade in Exam ML20055J0031990-07-25025 July 1990 Corrected Forwarding Ltr for Requalification Exam Rept 50-461/OL-90-03,including Addl Senior Reactor W/Passing Grade in Exam ML20055G5991990-07-19019 July 1990 Advises That 900702 Rev 9D to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20055H3041990-07-19019 July 1990 Confirms Plans for Mgt Meeting on 900809 in Glen Ellyn,Il to Discuss Plant Performance & Other Issues ML20055E2461990-06-26026 June 1990 Advises That Scope,Objectives & Draft Scenario Manuals for Plant 900725 Emergency Preparedness Exercise Acceptable. NRC Will Provide Any Comments by 900713 ML20055D0181990-06-26026 June 1990 Discusses Review of s Documenting Oral Request for Waiver of Compliance Re Emergency Diesel Generator Operability Tech Specs ML20059M8591990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H0151989-10-0505 October 1989 Forwards Safety Insp Rept 50-461/89-28 on 890911-15 & Notice of Violation ML20248D5991989-10-0202 October 1989 Ack Receipt of & Payment of Civil Penalty in Amount of $75,000.In View of Corrective Actions Taken Re Electrical Junction Box,Partial Payment of Civil Penalty Acceptable ML20248H9911989-09-29029 September 1989 Forwards Amend 4 to Indemnity Agreement B-91 Reflecting Changes to Financial Protection Requirements & Indemnity Agreements ML20247H9591989-09-11011 September 1989 Confirms Plans for Operational Safety Team Insp on 890925- 30 to Review Nature of Problems During First Refueling Outage.List of Insp Team Members Encl ML20247C4731989-09-0707 September 1989 Advises That Written & Oral Operator & Senior Operator Licensing Exams Scheduled for Wk of 900115.Requirements & Procedures for Administration of Written Exams & Requirements for Facility Review of Written Exams Encl ML20247H9101989-09-0707 September 1989 Confirms 890913 Meeting in Region III Ofcs to Discuss Preliminary Results from Recent INPO Evaluation ML20246J3821989-08-21021 August 1989 Responds to Concerns Re NRC Position on Application of Plant Tech Spec for Inoperable Support Sys.Analysis Prepared by NRR Which Responds to Questions Raised Encl ML20246D9411989-08-18018 August 1989 Requests QA Audit Rept to Enable NRC to Review Security Screening Deficiencies Contained in LERs 89-S02-00 & 89-S02-01 ML20246D2691989-08-18018 August 1989 Forwards Safeguards Insp Rept 50-461/89-25 on 890717-0802 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR73.21(c)(2)) ML20246D2321989-08-18018 August 1989 Forwards Addendum 1 to NRC Forwarding Insp Rept 50-461/89-18,consisting of Viewgraphs from 890614 Enforcement Conference Re Actions Taken Against Lead Radiation Monitoring Sys Engineer ML20246B6131989-08-17017 August 1989 Forwards Amend 25 to License NPF-62 & Safety Evaluation. Amend Revises Tech Spec Table 3.3.2-1,providing Addl Info Re Channel Configuration for Main Steam Line Turbine Bldg Temp High Trip Channels ML20246C4271989-08-17017 August 1989 Forwards Safety Insp Rept 50-461/89-24 on 890801-04.No Violations Noted ML20246C4471989-08-17017 August 1989 Advises That Rev 9A to Physical Security Plan Transmitted by Consistent W/Provisions of 10CFR50.54(p) & Acceptable Except for Items Identified in Encl.Encl Withheld (Ref 10CFR73.21) ML20245F3401989-08-0404 August 1989 Forwards SER Accepting Util 841001,871118 & 880609 Responses to Generic Ltr 83-28,Item 2.1,Parts 1 & 2,re Evaluation of Reactor Trip Sys Equipment Classification & Vendor Interface,Respectively ML20245F0141989-08-0303 August 1989 Confirms 890823 Meeting W/Util Onsite to Discuss Plant Performance Since Last Mgt Meeting,Monthly Performance Monitoring Rept & Execution of Licensee Commitments to NRC ML20245E9231989-08-0303 August 1989 Forwards Synopsis of NRC Investigations Rept 3-84-012 Re Baldwin Assoc Document Reviewers Accepting Bogus Documents or Coercing Individuals to Accept Bogus Documents. Allegations Unsubstantiated.Issue Closed ML20245F3201989-08-0303 August 1989 Forwards Mailgram Containing Info Re Potential Violence at Plant for Evaluation.Increased State of Security Awareness Implemented at Facility to Respond to Potential Violence & Local Law Enforcement & FBI Agencies Advised of Violence ML20247N7181989-07-28028 July 1989 Forwards Safety Insp Rept 50-461/89-22 on 890619-0721.No Violations Noted ML20247N6781989-07-25025 July 1989 Forwards Safety Insp Rept 50-461/89-18 on 890512-0707 & Notice of Violation ML20247J7891989-07-24024 July 1989 Forwards Synopsis of Ofc of Investigations Rept 3-83-018 Re Possible Tampering W/Structural Steel Beam Connections. Although Region Agrees That Repts Falsified by Contractor,No Action Taken Since Inspector No Longer Employed at Plant ML20247N2761989-07-24024 July 1989 Forwards Safety Insp Rept 50-461/89-21 on 890601-23 & Notice of Violation.Insp Conducted in Response to 890601 Event Involving Loss of Reactor Recirculating Pump B Seals Which Resulted in RCS Leakage in Excess of 50 Gpm ML20247H4371989-07-21021 July 1989 Requests That Licensee Perform Analysis Re Potential Safety Implications of 12-wk Rolling Maint Schedule at Plant.Util Should Provide Results of Analysis & Any Actions Deemed Appropriate to Region III within 60 Days of Receipt of Ltr IR 05000461/19890061989-07-20020 July 1989 Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000 Resulting from Insps 50-461/89-06 & 50-461/89-14.Penalty Issued to Emphasize Importance of Adequate Planning & Procedures ML20246K7931989-07-12012 July 1989 Forwards Safety Insp Rept 50-461/89-20 on 890627-29.No Violations Noted.Nrc Expects That Util 1990 Emergency Preparedness Exercise Objectives Would Include Objectives Not Demonstrated Before 1989 Exercise Was Terminated ML20246C7981989-07-0606 July 1989 Forwards Ltr from Director,Ofc of Nrr,To Representative of Ecology Ctr of Southern California,Ack Receipt of Petition Filed by Ecology Ctr of Southern California & States Petition Being Treated Under 10CFR2.206 ML20246E4781989-07-0606 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-461/89-03.NRC Understands That Util to Provide Amended Response Addressing Listed Items by 890721,per 890629 & 30 Telcons ML20245J7511989-06-26026 June 1989 Informs That Credit Will Be Given for Fee Sent w/890612 Application for Amend to Tech Specs Re cycle-specific Parameter Limits ML20245H4411989-06-23023 June 1989 Forwards Safeguards Insp Rept 50-461/89-19 on 890206 & 0522-0607 & Notice of Violation ML20245H9591989-06-23023 June 1989 Forwards Enforcement Conference Rept 50-461/89-23 on 890614 Re Violations Noted in Insp Rept 50-461/89-14 1990-09-10
[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
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NUCLEAR REGULATORY COMMtsslON REGloN in
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-l CLEN ELLYN BLLINols 60137
- 1 IJUN 2 C 119o Docket tio.-50-461 lllinois Power Company ATTN: J. S. Perry Vice President Clinton Power Station Mail Code V-275 P. O. Box 678 Clinton, IL 61727 Gentlemen:
We have reviewed your letters (U-601696 and U-601698) dated June 22, 1990, documenting your oral request for a Waiver of Compliance regarding a requirement of ycur Te ' ical Specification that addresses emergency diesel generator (EDG) operabil.3y at the Clinton Power Station. Copies of your letters are enclosed.
Technicel Sp cification 3.8.1.1, Action b., stipulotes that with the IB EDG (Division 111 inopereble in operational conditions 1, 2, or 3 that the IB EDG must be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the IB EDG cannot be restored to en operable stdtus within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> the plant must be in at least hot shutdown within the-next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The IB EDG at the Clinton Power Station was removed from service at 2:45 a.m., (CDT) on June 22, 1990, after the discovery that a leak existed inside of one of the heat exchangers that cools the EDG.
~
The leak was suspected to have been caused by microbiologically induced corrosion (MIC) which had previously been found to be causing degradation of heat exchangers at Clinton. You requested an additional 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />s-before the unit would be required to commence shutdown to prevent an unnecessary transient on the plant, should you be able to repair the IB EDG and prove it operable within that time period. This period expires at 2:43~a.m., on-June 29, 1990.- If the problem with the IB EDG is not corrected and the EDG does not successfully pass its operational surveillance test by that time, action will be immediately taken to commence shutdown of the unit so as to alace it in hot shutdown by 2:43 p.m., of June 29, 1990, and cold shutdown
>y 2:43 p.m., on June 30, 1990.
I understand that during the period of time that this Waiver of Compliance is.
in- effect, Clinton Power Station will take the following compensatory actions
.to ensure th6t the unit is maintained in a safe and stable condition:
- a. fio testing that might cause a plant tronsient, other than normal required Technical Specification surveillance testing, will be performed, i OO bob): b ,
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- t Illinois Power Company 2 M N 2 0 1990
- b. No systems or equipment important to safety which are associated with Division I will be removed from service for electrical maintenance,
- c. If the test results for the reserve auxiliary transformer (RAT) oil samples (expected by June 25, 1990) are unsatisfactory, actions will be immediately taken to shut down the unit.
I agree that your request for a temporar Waiver of Compliance meets the elicibility criteria in 10 CFR SI.22(c)(y). 9 I also agree pursuant to 10 CFR 51.22(b), no environmental impact statement need be prepared.
Af ter consultation with Mr. E. G. Greenman, I granted the requested relief on June 22, 1990, based on the minimal increase in risk associated with keeping the unit in operation for an additional 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and thus avoiding a unnecessary transient in the plent. This approval is contingent on the compensatory measures described abuve.
Sincerely ,
> ui k .L%$ b A. Bert Davis '
Regional Administrator
Enclosures:
As stated
-See Attached Distribution:
l
1111nois Power Compeny 2 AN 2 61990
- b. No systems or equipment important to safety which are associated with Division I will be removed from service for electrical maintenance,
- c. If the test results for the reserve auxiliary transformer (RAT) oil samples (expected by June 25,1990) are unsatisfactory, actions will be immediately taken to shut down the unit.
I agree that your request for a temporar Waiver of Compliance meets the eligibility criteria in 10 CFR 51.22(c)(y). 9 I also agree pursuant to 10 CFR 51.22(b), no environmental impact statement need be prepared.
After consultation with Mr. E. G. Greenman, I granted the requested relief on June 22, 1990, besed on the minimal increase in risk associated with keepir.g the unit in operation for an additional 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and thus avoiding a unnecessary transient in the plent. This approval is contingent on the l compensatory measures described ebuve.
Sincerely,
,o hTM A A. Bert Davis !
Regional Administrator
Enclosures:
As stated j See Attached Distribution: ;
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Illinois Power Company 3 JUN 2 61990 Distribution:
cc w/ enclosure.
J. Cook; Manager, Clinton Power Station F. Spangenberg,-111, Maneger -
Licensing end Safety
-DCD/DCB,(RIDS)
Licensing. Fee Management Branch Resident inspector, Rill J. Hickman, NRR, PM J. McCof f rey, Chief, Public utilities Division H. Taylor, Quality Assurance Division, Sargent & Lundy Engineers Petricia 0'Brien, Governor's Office of Consumer Services S.-Zabel, Esquire, Schiff, Hardin,
& Weite L. Larson, Project Manager, General Electric. Company Chairman, DeWitt County Board Illinois Department of Nuclear Safety Robert Newmann, Office of Public Counsel, State of Illinois Center Perry SRI T. E.' Murley, NRR J. M. Taylor, EDO i
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' cLINTON AMsR sTA'nON. P.o. Dok ett, CWNToN H,LlWoD 017874078. TE1,3 PHONE ($17) 0664441 _
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i June 22, 1990 .
4 10CFR50.91(a) (5).
10CFR50.91 l
Docket No. 5'0-461 ,
, Nr. A. 3.-Davis _
l Regional-Administrator .
Region III U.S. Nuclear Regulatory-Commission [
1 799 Roosevelt Road '
Gian Ellyn, Illinois 40137 SUh7ECT! Followup to Request for Weiver of Compliance Regarding Teshnical, specification Limiting Condition for operation Related to Standby Emergency Diesel Generator 1B .
Dear Mr. Davis:
On June- 22, 1990, IP discussed with Nessrs. E.
l L Greenaan and R. Knopp of your staff the request-for a L waiver of compliance submitted via IP Letter U-601696 dated June 22, 1990. During this conversation and based on the information provided in Attachment 1 to this letter, Mr. Greenaan approved a waiver of compliance regarding the out-of-service time allowed for diesel generator (DG) it under the Technical specification Limiting condition for Operation (LCo). Under the granted waiver, the allowed-out-of-service time for DG15 ,
must not exceed seven days from'the time that DG1B was removed from service (entry into the LCo Action Statement). The waiver of compliance will therefore
. expire on or before 0243 on Frlday, June- 29, 1990, unless otherwise approved by the NRC.
It should be noted that Attachment 1 to this letter is a revision to Attachment 1 of the original request for waiver dated June 22, 1990 (U=601696) as it contains additional information. This letter and its attachments !
have been reviewed and approved by the CPS Facility Review Group.
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' IP appreciated your consideration and prompt response to this request..
' sincerely, fbQ l J. 8. Pe m Vice President TRE/rqpt Attachments ,
cci NRC Clinton Lise'nsing Project Manager -
NRC Resident Office I
L Illinois Department of Nuclear safety
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- - namerinalen af eendiaian/ mannan far Rasuant During normal shift rounds at approximately 0200 on June 22, 1990, an operater discovered (via the site glass) that the water level in the jacket oceling water .
o expansion tank on DG13 was overflowing. From earlier P
experi~ence, IP suspected that this-may be caused by service water leaking through-the diesel generator heat i
exchanger tubes and into the DG jacket cooling water within the associated heat exchangers. (A heat exchanger
- is provided for each of the two tendom engines (one 16-c/linder and one it-eylinder) associated with DG15.)
Although the condition described above would not prevent the DG from performing its safety function (since the '
diesel can function with direct service water flow into '
the cooling jacket), DG1B was removed from service et l
0243 hours0.00281 days <br />0.0675 hours <br />4.017857e-4 weeks <br />9.24615e-5 months <br /> for investigation and repair. '
! Microbiological 1y induced corrosion (MIc) was first identified in the DG heat exchangers at CP8 in 1989 as IP was developing and implementing its response to Generic ,
i Letter 89-13 and the associated suplement.* As an immediate corrective action, cleaning and closed loop chemical treatment of the De heat exchangers were l performed during planned outage 3 (70-3) IP (February, 1990) is currently to.tamporarily arrest the MIC problem.
working towards a long-term solution to the MIC problam, including:ebtaining an Illinois State discharge permit for ehemically treating service water on en open-loop (Retubing of basis and retubing the DG heat exchangers.
- the heat exchanger for DG1A was completed during Po-3.)
irements (during operational f Theoerabilityre!3).fortheemergencystandbydiesel condi ions 1,2, an L generators, including the actions to be taken it one (or more) is inoperable, are specified in CPS Technical-Specification 3.8.1.1. (see Attachment 2 of this )
submittal.) Action "bH ggquiggg ghgg gigh g{thgg diggel I generator LA or 1B inoperable, oper. ability of the required Ac offsite sources must be demonstrated, operability of the remaining operable diesel generators must be demonstrated (unless the DG became inoperable solely due to preplanned preventive maintenance or testing), and the inoperable DG aust be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the inoperable DG cannot be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the plant must be brought to a hot shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to a cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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- Reference IP Letter U-601574; dated January 29, 1990 i
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. to U-401698 .
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pago a of'8 By 1300 (on June 33, 1990), Ip completed a visual inspection of the tubes within the heat exchangerBased on the !
associated with the it-eylinder engine, j visual inepmotion performed and previous experience with l NIC in the Division I diesel generator heat exchanger, )
tube replacement is required for both heat exchangers (i.e., the heat' exchanger associated with the 12-cylinder ;
engine and the heat exchanger associated with the 16-This work will not-be able to be ;
oylinder engine). completed Itbeforeis surrently the 72= estimated hour time limit thatexpires at 0243 1 on Mondey, June 24, 1990, an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> will be needed to semplete the ,
retubing and to complete the testing required to reverify l operability of DGit. Regardless, IP does not expect and I will not permit the time required for retubing and testing to exceed a total of seven days from the time DG1B was removed from service.
Desa91stien/Saminnem of work to be Performed The work plan for retubing both heat exchangers is such that both heat exchangers for DG1B will be repaired in Because of the size limitation of the DGiB parallel. room, the 16-cylinder engine heat exchangerlinder must be removed from the skid for retubing. in pla.co.) The 16-engine heat exchanger will be ret.ubed(The 12-cy
- ylinder engine heat exchanger work will thus take almost another day more than the.repai't After .'tetubing work and for the la-cylinder reinstallation engine heat exchanger.
of the 16-cylinder engine heat exchanger, pressure testing and service water flow balancing will be required, followed by performance of a post-maintenance surveillance test. Ip currently estimates that all of the above will take, approximately, an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> beyond the allowed out-of service normally-required by-the' plant Technical specifications.
Justifiention for Drensand annuant The Illinois power electrieel system The design waiver of provides a compliance diversity of power supplies.
for the clinton power Station Technical specification (CPS-TS) Limiting Condition for operation (LCC) to extend the 72-hour allowed out-of-service time approximately 72 additional hours is justified partially on this diversity. The 128-XV offsite p wer system provides power to the station by one thrt,e= terminal transmission line. This line connects the s'sation to the Illinois Power company grid at the south Bloomington and Clinton
- Route 54 substations.
Electrical power een be fed to the station through the line from south Bloomington or north or both. The Decatur (via Clinton Route 54 .lubstation) line terminates directly (through a circuit switcher) at the Emergancy Reserve Auxiliary Transformer, which transforms the electrical power to 4160-volt auxiliary
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- power bus voltage. The 348-kV Offsite Power System provides power to the station through three separate transmission These lines connect the station to lines.Company
- the Illinois Power grid at the Brokew, Rising, and Latham substations. All three lines terminate at the station switchyard ring bus which feeds the Reserve Auxiliary Transformer, which in-turn transforms the electrical power to the 6900-volt and 4160-volt auxiliary power bus voltage. Only one 138-kV and one 345-kV feeders are required by CPS Technical specifications.
In the unlikely event that the power sources described there are two remaining onarahla above are unavailable,ite.
diesel generators on s Diesel Generator 1A (DGIA) supplies power to Division I electrical equipment and DG1C supplies power to Division III electriual equipment.
These operable diesel generator units are espable of sequentially starting and supplying the power Because of requiremente for safe shutdown of the plant.
the diversity of the power supplies described above, the increase in the allowable out of service time for DG18 is justified.
With respect to the current status of other systems at CPS important to safety, the following are currently but temporarily out of service. #LCo#e were entered for these systems strictly due to routine maintenance and not because of any discovered / determined condition of inoperability.' .
Syntam status 6/dammanta Standby Gas Treatment This LCC is expected to (1) clear during the current Subsysten B swing shift. Standby Gas Treatment subsystem A is operable.
(2) Wain Steamline Isolation This LCo is currently being Valve Leakage Control cleared. M8IVaLCS Systaa (N8IV-LCS)- Subsystem A is operable.
Subsyntam B Reactor Core Isolation This LCO is expected to (3) clear during the upcoming cooling (RCIC) system '
midnight shift. The MPCS system is operable.
Imminent restoration e' the above systems / subsystems and the operability of redundant systems provides added assurance that the proposed request is justified.
- As of 1800, June 22, 1990.
'803 4 of 8 1 There are two other plent/ equipment conditions of concern l
surrounding this event. IP is currently monitoring the ,
degradation of the inner aschanical seal on reactor reoirculation pump p as pressure across the inner seal has been observed to be increasing.
in good condition.) This conditionnot is(The outerto seal considered is be a sendition that warrants special consideration regarding the espability to shut down the plant and mitigate the consequences of an tecident. The most likely shallenge to the seal would be when shifting the reactor reciroubtion pump from slow to fast speed during a plant restart. _.
The second concern is the results of oil testing recently i
performed en the reserve auxiliary transformer (RAT) which provides power from the Cps switchyard to the Auxiliary power (Ap) System. The transformer is currently in servios and is one of two sources of power The tothesafat(-relatedportionoftheAPsystem.s transformer rated to carry more than four ti f total demand of the safety-related portion of the AP system.
Illinois power monitors the condition of transformer oil in the RAT by taking periodic oil semples and sending them to an independent laboratory for analysis. The results of oil samples taken in aid June of 1990 are ptovided.below. Two of the parameters were identified as being outside their recommended normal-ranges.
R&ngs .641A* A/.21* U.21**
Water content 15-34 ppm 31 ppm de ppm Dielectric Strength 24-31 kV 30 kV 14 kV 45 kV ,
The samples wore taken during extremely wet humid weather and are so divergent that they are questionable. All other parameters are normal and within their respective limits. In particular, the combustible gases are within their normal limits. (combustible gases are indicative of imminent failure and/or catastrophie damage due to internal arcing.)
The RAT has experienced no failures since IP received its I
ope.ating license in September 1986. The only outage of
! the off site power-from the 345 kV switchyard occurred in late itse due to a failure of a 345 kV switch. This outaite was of short duration (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />). .
- 0ffsite laboraton test results
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.. P0gO 5 of 9 IP believes requires the test closer resultsbut attention, indicate that it is not the R&T and inoperable is still espable of performing its intended function.
Nowever, IP has sent samples to two different
[ laboratories so thatTest the results recent are testexpected results can nextbeMonday further evaluated.
(June 88,1990) . If the test results for the RAT oil samples are unsatisfacton , IP will take appropriate action to shut down the plant.
Regarding the need for maintaining the plant on line, CPS is presently generating approximaf,ely 6b percent of the total electrical IP oustomer lead.
The current status of other 213.inois Power Generating Stations is as.follows: ,
Egnacted L
Re: urn-to-Service
=
gggggg Data ggig Baldwin 1 (540 MW) off-line 6/25/90 Baldwin 3 (540 NW) off-line 7/23/90 Havana 6.(410 MW) off-line 6/25/90 ,
and all of It is estimated that if CPS must be shut down,ll need to the available IP units are in operation, IP wi purchase at least 500 megawatts of m er.and must interrupt service to the interruptible customers on Monday -(June 25) . If Baldwin 1 and Havana 6 are not available, then IP will need to purchase at least 1200 megawatts (and discontinue service to the interruptible customers). Peaking Units (Gas Turbines) are not
' included in this forecast.
Additional Mitisatins conditisna in 2P contacted the National Weather Service (NW8)
Springfield, Illinois to consider the current and
- axpected weather conditions for the immediate service area. The NWS reported.that The NWS olear weather is forecast indicated that there is only a for the vaskend.
i slight chance of thur.04rstorms on Monday (June 25) and that the next possibility of thunderstorms is on Wednesday or Thursday (June 27 or 28) .
demeanantarv Actiona m
The remaining operable diesel generators are ready to perform their intended In function addition,in the no unlikely event testing will be that they are needed.
performed that might create a transient to normal plant conditions (other than the normal surveillance testing
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', Attachment 1 to U-soiset Pago 6 of 8
- required to satisfy Technical specification requirements) ,
during the extended time interval. Also, no systems or equipment important to safety which are associated with the redundant safety-related division (Div. I) will be removed from servios for electric maintenance during the extended time interval.
.safatv eieniffamnaa/ammia for Ma sianfficant Nazarda ,
eansideratian IP does not consider this request to be safety significant in view of the followingt . .
- 1) As noted previously, only the Division II DG is currently inoperable. As offsite power is also available, sufficient redundancy exists (assuming no concurrent failures) to provide emergency power to -
systems designed to mitigate the consequences of an aooident.
- 2) Generally, operation _under the provisions of an I action statement is permitted for limited periods of time as it is recognised that single-failure criteria may not be met during such operation. IP
- believes that operation with only DG1h out of service for a period of time longer than normally, allowed but within the noted limit constitutes no significant increase in risk regarding the safe operation of the facility..
- 3) In addition, IP does not believe that the present situation should require subjecting the plant to an unnecessary shutdown. Although there is a certain risk associated with the increased allowed out-of-service time, most challenges to plant systems occur during startup and shutdown events. Eliminating the '
risk associated with these events by preventing an unnecessary plant shutdown due to the current action time limit is viewed to have a positive effect on plant safety.
- 4) With respect to executing a safe shutdown of the
-plant if required, the plant design is such-that safe shutdown to a cold condition can be achieved with DGiB inoperable, particularly in view of the operability of all' redundant power sources and the operable status of systema important to safety.
1 According to 10CFR50.92, a proposed change to the license (Technical specifications) involves no significant hasards consideration if operation of the facility in accordance with the proposed change would not: (1) involve a significant increase in the probability or conseguences of an accident previously evaluated, or (2) create the possibility of a new or different kind of
' Attachmont 1
'l' to U-601694
- Page 8 of a The third option ie'to replace the heat exchanger tubes. ,
This can restore either or both heat exchangers to a like-new condition as IP pursues its long-tera solution-to the MIC problem. IP feels that this is the appropriate course of action. The proposed request would support oosplete replacement of the tubes in hate heat.
exchangere (for the it-eylinder and 16-cylinder engines),
thus precluding the possibility of having to again remove
- the De from service in order to plug more tubes, reassessing the impact of further plugging, Plant and and grid potentially reeddressing the MIC probles.
condit, ions are such that new is an appropriate time to
. request _a waiver of ocapliance in order to implement a complete and thorough (short-tera) fix to the MIc problem for 001B.
t e
a 1
l
A'ttachment 2 '
j ~. . - '
" . ' , 3/4.8 flECTRICAL.POWEA$YSTEMS ee U-601698 '
' . Pase.1 of 3 l i .
3/4.8,1 AC $00RCEI . .
i .
" AC 500R0t$ = OPERATING LIMITING CONDI" ION FOR OPERATION As a sinisua, the following AC electrical power sources shell be -
Sg ,
- a. sicaland indsendentci ,
Two netwo pgr ge ensgto. distributionsystas..and Class guits between the offsite transmission
- b. Three separata and independent dieset generators', each with:
- 1. A separats day fuel tank containine a, minimum of 345 gallons of fuel for diesel generators 1A and 18 and 240 gallons of fuel for diesel generator 1C. , .
- 2. A separate fuel storasp system containing a intaus of 48 000 gal-lens of fue' for diese, generator 1A and 45 fesel generator 10. l generator ill and 19,500 gallons of fuel for, 00 gallons for dies
- 3. - A separete fuel transfer pump. ,
Appl 1CABiltTY: OPERAf!OHAl CONDITIONS 1, 2, and 3.
t L
ACTION:
ired A0 electrica' power
- a. With one offsite circuit of the above r !!.!TY of the rosadning AC desenstrate the OPE
.sources sources by inoperable perfors {ng Surveillance Requ resent 4 4.1.1.1.a within one hour thd at Issst once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafttr. If eithat' dittel ganaratar demona 1A or 18 has not been successfu119 tasted within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,1.1.2.a.4 strate its CPLAABILITY by performing surveillance Requirements 4.8.
separately,within and'4.8.1.1.2.a.5 for each cuch diesel generator [I status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 24 hours. Restore the offsnte circuit to OPERAB or be in at least HOT SHUT 00WH within the next.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO l SHUf00WW'within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ,
- b. With either diesel gener4 tor 1A or 18 inoperable, demonstrate the OPERABIL-l ITY of the above required AC offsite sources by performing surveillance i Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at'least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If the diesel generator became inoperable due to any cause other t an preplanned prevective maintenance or testing, demonstrete the OPERA 81 ITY of the remaining QPERABLE diesel cenerators separately,by perform ng Surveillance Requirements 4.8.1.1.2.a.4 and d.8.1.1.2.a.5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />". Restore the inoperable diesel generator to OPERA 8tE
- This test is required to be conoleted regardless of when h,he inoperable diesel -
generator is restored to OPERAB.4 status. The provisions of $pecification 3.0.2 are not appitcable, ,
CLINTON - UNIT 1 3/481 Amendment No.13 e
-a-,,,~,-,,w>,a - - , , , - - , . . . - - , . .
v - - - , - -- --
___7 . .
t Attsoluentie 3 .
' ' ' to' tb 601698 ;
. , Pass 2 of 3 i '. x - .
(
1,h, .. . ,
i
' stactucat pansrivffixt '
ac souncts E tfNG . ,
...e .
LIMfMNG .C+3f710N FOR GGGiat18N f cantinuedi '
a l '
L 3.s.L1 ActiDN fiantinuesi autve heure endviein is COL 878 8W790W hewn witMner the sefs11in swing et ieus34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br />. =r *ewn0W *"- -
widia w4.t u- ,
s, , With one offsite ettsutt of the neeve=reevired At eseurtes sauress and diesel '
- senerster 1A er la of De 46 eve reevired At electe1441 AC seceses by-
- dennastrate the CPCAAR1M TV of.the remaint hour and at least
' Insparete,8vevet114nes Requirement 4.8.LLLa witMA
- l perferningease per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If.a diesel generster hasase isoperstle fMe any asuse suer uan pMalanned preventive maintenane's of testing seson=
strate tAe OptRAt!LffY of the remataing 0PERA8LE dieset sentratars,4 8 LLLa.4 and
- 4.parately, se s.LLLa.I witMa by performing 8 hoves*.Surye(11anseAastare at least Reevirtaansa one of De .insterials . AC secreas to CP8RA8LE status witMn the nant u nevre and in COW SWTDOW winin the fetiertAg to hours. within 12. Deves en he in. At least NOT Restem at least two offsite circuite and disset utneretare 1A ans 18 to CPERA8Lt status wisMn 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> fees time of fait' al less er te in et1*ast Hot .-
W folieving to hours.
$WTDOW j within ne next '
d.
With diesel generater 1C of the a6 eve requiMd AC elettrical power sovrees i inoperable, sesenstrate the OPERA 82WTY.ef the offsite AC secrees by pet
- forming svevet11ance Reevirement 4.8.LLLa vieta 1 hear and at lea ence per a heyrs tAereafter.a result of ag cause euer than preplanned preven '
.tssting, desenstrate the OPERAAIUTY of us remaining OptRASLE diesel ganar*
start, separately, ty.perfefsing 8vevet11ancs Aequirements 4.8.LL2.a.4 I
and 4.4.LLI.a.5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />". Rastem diasal generatar 1C to CPERA8LE stalvs witMn 71.hevn er u. declare the HPC1 bstes
. . ute . 4ct a ceund y ..eiftati.o a.8.1 ud e.
With diesel generator 1A er 18 of 2e deve retviced AC electrical power sources inoperatie, in sedition to taking ACT10M 4 er s, sunsyttaas, trafasu applicable, verify'within I hevn uat all nevired systans,ing CPtRASd diesel aesponents and devises that depend on the rossin Auervise, be fenerater a at least Hof asP.UT90W a seurtswiuin of emergency the nast it heves power and in 4M Cc alse OPERA 8LE wipin the fetteving 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- f. Vltti teth of' us ansva required offsite circulta inoperabfe,.desenstrate the OPERA 8!L!TY of three diesel geNreters, se$arsuly, ny perferming ,
Surve(11aue Requirements 4.8.L1.2.a,4 and 4.4.LL2.4.8 Restarewithin at itset 8 heves one unless us aissel generaters are alressy aparating. . .
l "This tes is resvired to be essoleted regardless of when the incoeraale eissel generasce is esstarts to CPtAABILITY. The previsions of Spectf.iastion 3.A .
ers not asplisaste. .
3/4 8 2 L CLINTON - UNIT 1 W
i
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f e go.jp ,,gg, g .
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Poea 3 et 3 tLECTRICAL POWER SYSTEMS AC 500RCIS - OPERATING
, LIMITING CCHDITION POR OPERATION (Centinued) 3.8.1.1' ACTION (Continued): ,
of the above* required offsite cirevits to CPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next u hours. With only one offsite circuit restored to CPERA8LE status, restore at least two offsite '
' aircuits to CPERABLE status within ?! hours free time of initial '1ess or '
be in at least NOT SWT00WN within the next M hours and in COLD $ NUT 00WN within the followint 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />. A suceessful teet(s) of diesel generator CPERASILITY per Siirveillance Requirements 4.8.1.1.2.a.4 and 4.6.1.1.2.a.5.. .
performed under this ACTION statement for the OPtRABLE diesel eenerators, estisfies the diesel genereter test requirements of ACT!0H staf,ement,s.
- g. With diesel generaters 1A and'1B of the above-required AC electrical power sources inoperable demonstrate the oftRASILITY ef the remaining AC sources by performInt Surveillance Requirement 4.8.1.1.1.s with' n I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter and Surveillance Require-ments 4.8.1.1.2.a.4 and 4.8.1.1.8 a 5 for diesel generator 1C within '
8 houes.* Restare at least one of the inoperable diasal generators 1A and 18 to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least NOT 8NUTDOWN within the nept 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the 'following 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />.
Resters both diesel generators 1A and 18 to OPERABLE status within it'heurs from time of initial lees er be in at least HOT 8HUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SWTDOWN Within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- h. With one offsite circuit of the above-required AC electrical power sources inoperable and diesel generator 1C inoperable, apply the requirements of . .
ACT!cN statements a and d specified above. ,
- 1. With either diesel generator LA or 18 inoperable and diesel generator 1C inoperable, apply the requirements of ACTION statements b, d and a specified above.
"This test is required to be completed regardless of when the inoperable diessi .
generater is restored to OPERABILITY. The previsions of Specifteation 3.0.2 .
are not applicable.
CLINTON - UNIT 1 3/4 6-3 ,
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Il&isets Power Seegany +
c1&aten power Statiza meste 84 - a Miles East Post office Des 478 cliates, Illissie s1737 l renee es ,.ine to. '/I]T.bflAhGl01)40L '
ritme U k b f1Arl0$L W telese,y machine me.: M/-N#7"dM) d4[OJ _
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. 1ees,1 a. ##mf/ mod Date seatt /b/Aff/6)0 Number of pagess / -
+ envar Operators. IlAlld . _ __
talaeany Mashiman Panafan MI=3000 Automaties (tif) 938-8294 Verificaties Numbert (317) 935=8881, estension 3597 E-ww @e y
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