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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 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 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 ML20055J3251990-07-25025 July 1990 Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 Re 900411 Control Rod Event 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 ML20055D0181990-06-26026 June 1990 Discusses Review of s Documenting Oral Request for Waiver of Compliance Re Emergency Diesel Generator Operability Tech Specs 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 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 ML20247H9101989-09-0707 September 1989 Confirms 890913 Meeting in Region III Ofcs to Discuss Preliminary Results from Recent INPO Evaluation 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 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 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)) 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 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 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) 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 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 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 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 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 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 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 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 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 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
[Table view] |
See also: IR 05000461/1985039
Text
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DEC 2 0 1985
Docket No. 50-461
Illinois Power Company
ATTN: Mr. W. C. Gerstner
Executive Vice President
500 South 27th Street
Decatur, IL 62525
Gentlemen:
SUBJECT: EMERGENCY PREPAREDNESS IMPLEMENTATION APPRAISAL
To verify that applicants have attained an adequate state of onsite emergency
preparedness as required by 10 CFR 50.47(a)(1), the NRC conducts special
preoperational appraisals of their emergency preparedness program. The
objectives of the appraisal are to evaluate the overall adequacy and
effectiveness of emergency preparedness and to identify areas of weakness
that need to be strengthened.
During the period November 12-21, 1985, the NRC conducted a special appraisal
of the state of onsite emergency preparedness at the Clinton Nuclear Power
Station, Unit 1, authorized by NRC Construction Permit No. CPPR-137. Areas
examined during this appraisal are described in the enclosed report
(50-461/85039). Within these areas, the appraisal team reviewed selected
procedures and representative records, inspected emergency facilities and
equipment, observed work practices, and interviewed personnel.
No significant deficiencies, deviations, or violations were identified as a
result of this appraisal.
The findings of this appraisal indicated that a number of areas of your
emergency preparedness program were not complete at the time of this appraisal.
These areas included, among others, installation and calibration of certain
equipment, related procedural development and training, procedure updates, and
demonstration of shift augmentation and assembly / accountability. These items
are identified as Open Items and are listed in the enclosed Appendix A.
The findings also indicate that there are several items in your emergency
preparedness program which need improvement, and these items are listed in the
enclosed Appendix B. These improvements are areas which we believe, based on
professional judgement, should be corrected.
You are requested to submit a written statement within thirty days of the date
of this letter, describing your planned actions for completing each of the
items identified in Appendix A and the results of your consideration of each
of the items in Appendix B. All of the Open Items must be completed prior to
licensing.
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Illinois Power Company 2 l
.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of !
this letter, the enclosures, and your responses to this letter will be placed I
in the NRC Public Document Room. [
t
The responses directed by this letter are not subject to the clearance !
procedures of the Office of Management and Budget as required by the l
Paperwork Reduction Act of 1980, PL 96-511. L
We will gladly discuss any questions you have concerning this appraisal, f
i
Sincerely, l
!
" Original tir d by U.D. C.dar" l
W. D. Shafer, Chief
Emergency Preparedness and :
Radiological Protection Branch (
Enclosures: !
1. Appendix A, Appraisal !
Open Items l
2. Appendix B, Appraisal
Improvement Items
3. Inspection Report
No. 50-461/85039(DRSS)
cc w/ enclosures: f
DCS/R$B (RIOS) !
Resident Inspector, RIII i
Richard Hubbard !
Gary N. Wright, Manager (
Nuclear Facility Safety i
Jean Foy, Prairie Alliance [
Allen Samelson, Assistant -
Attorney General, ;
Environmental Control Division !
H. S. Taylor, Quality Assurance ;
Division i
D. Matthews, OIE, EPB l
W. Weaver, FEMA, RV j
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Appendix A -
Open Items
The following is a list of Open Items identified in the area of emergency-
preparedness which must be completed prior to fuel load.
1. An actual drill demonstrating the capability to implement staff
augmentation in accordance with the CPS Emergency Plan must be performed
prior to fuel load. (Section 2.2) (461/85039-01)
2. All primary and alternate personnel must be trained in their emergency
functions prior to fuel load. (Section 2.2) (461/85039-02)
3. The Emergency Plan and/or EPIPs must address relocating the TSC and OSC
if they become uninhabitable. This must be completed prior to fuel
load. (Sections 4.1.1.2 and 4.1.1.3) (461/85039-03)
4. Installation of the telephones planned for the TSC's NRC Consultation
Room must be completed prior to fuel load. (Section 4.1.1.2)
(461/85039-04)
5. Develop and maintain an official controlled inventory list for the supply
cabinet in the TSC containing administrative and support material;
including a provision for periodic inwmterics. This must be completed
prior to fuel load. (Section 4.1.1.2) (461/85039-05)
6. The Area Radiation Monitoring / Process Radiation Monitoring (ARM /PRM)
system and the Performance Monitoring System / Display (PMS/ DES) system
(data acquisition *ystems) must be operable in the TSC and EOF, and
operators trained in its use prior to fuel load. (Sections 4.1.1.2 and
4.1.1.4) (461/85039-06)
7. Revise EPIP FE-02, Operations Support Center Operations, to reflect the
correct location of the OSC prior to fuel-load. (Section 4.1.1.3)
(461/85039-07)
8. Establish and maintain operability of telephone systems in the OSC prior
to fuel load. (Section 4.1.1.3) (461/85039-08)
9. Develop and maintain an official controlled inventory list for the EOF
cabinet containing administrative and miscellaneous supplies, including a
provision for periodic inventories, prior to fuel load. (Section 4.1.1.4)
(461/85039-09)
10. Equipment (sample containers, shielding, handling, and transport equipment)
needed to enable sampling at existing grab sample ports for the HVAC vent
and SGTF offgas system must be developed and tested prior to fuel load.
(Section 4.1.1.7) (461/85039-10)
11. Accessibility to and from the HVAC vent and SGTF offgas system sample
ports, while using all necessary equipment, must be verified prior to
fuel load. (Section 4.1.1.7) (461/85039-11)
12. Procedure CPS 1890.36 must be completed and approved prior to fuel load.
(Section4.1.1.7) (461/85039-12)
_ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ -
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Appendix A 2
13. Complete the installation of the Germanium Detector and make necessary
repairs to the Phoswich System located in the. EOF Environmental Sample
Analysis Laboratory. This equipment must be operational prior to fuel
load. (Section 4.1.1.8) (461/85039-13)
14. Training lesson plans, for both Emergency Response and nonessential
personnel, must be change to reflect actual assembly and reassembly
areas and evacuation routes r.c. all plant personnel retrained. This
must be completed prior te iuet load. (Section 4.1.2.1) (461/85039-14)
15. The assembly and reassembly areau and evacuation routes must be identified
and quipped with appropriate communication and protective equipment,
including provisions for decontamination. This must be completed prior
to fuel load. (Section 4.1.2.1) (461/85039-15)
16. Provide extremity dosimetry for the OSC and hospital kits prior to fuel
load. (Section 4.2.1.1) (461/85039-16)
17. Confirm that the operational meteorological measurements programs meet
the system accuracy specifications stated in ANSI /ANS 2.5-1984 and
Regulatory Guide 1.97 for wind speed, wind direction and vertical
temperature difference. This must be completed prior to fuel load.
'
(Section 4.2.1.4) (461/85039-17)
. 18. Confirm that meteorological data availability goals can be achieved during
. plant operation prior to fuel load. (Section 4.2.1.4) (461/85039-18)
19. Demonstrate that meteorological data from the NWS station at Springfield
adequately represents the Clinton site in real-time for use as backup
information. (Installation of onsite backup or redundant sensors at the
10-meter level would be an adequate alternative to the use of Springfield
j, data). This must be completed prior to fuel load. (Section 4.2.1.4)
- (461/85039-19)
i
20. Incorporate the specific methodology and responsibility for acquisition
j of NWS forecast inforr.ation and integration of this information into
protective action recommendations and dose assessment prior to fuel load.
.! (Section 4.2.1.4) (461/85039-20)
I
i 21. Correct inaccurate and incomplete references to meteorological information
i
(i.e., determination of atmospheric stability) from EPIP RA-01, Manual
,
Dose Assessment, and identify averaging periods that are to be used in
i the calculations. This must be completed prior to fuel load.
i (Section 4.2.1.4) (461/85039-21)
i
l 22. Protectivc clothing supplies now stored in the Unit II Crossover Room
i must be placed in designated areas of the plant in accordance with
! Emergency Plan, Chapter 3.2.10.1 and Table 3-8 prior to fuel load.
j (Section 4.2.2) (461/85039-22)
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Appendix A 3
23. The public address system must be completely installed and operational
prior to fuel load. (Section 4.2.3) (461/85039-23)
24. All emergency alarms must be completely installed and operational prior
to fuel load. (Section 4.2.3) (461/85039-24)
25. Complete the stocking, organization and inventories of damage
control / corrective action equipment and supplies prior to fuel load.
(Section 4.2.4) (461/85039-25)
26. Where appropriate, Systen/ Plant Operating Procedures (3000 Series),
Off-Normal Procedures (4000 Series) and Annunciator Procedures
(5000 Series) must be completed and appropriately reference and implement
EPIP EC-02, Emergency Classifications. This must be completed prior to
fuel load. (Section 5.2) (461/85039-26)
27. Ensure to the maximum extent possible that EALs are quantified and that
criteria constituting EALs shall be as-read or as observed, minimizing
computations or calculation to determine if the EAL is exceeded. This
must be completed prior to fuel load. (Section 5.3) (461/85039-27)
28. Revise EPIP EC-07, Emergency Plan Notification, prior to fuel load to be
consistent with the methodologies actually employed. (Section 5.4.1)
(461/85039-28)
29. Revise the Emergency Plan and EPIPs prior to fuel load to conform with
the requirements of 10 CFR 50.72(a)(3) concerning notification time limits.
(Section 5.4.1) (461/85039-29)
30. Procedure CPS 1890.34 for use of the PASS must be completed and approved
prior to fuel load. (Section 5.4.2.3) (461/85039-30)
31. Revise the EPIPs to correctly reflect the actual location of the assembly
areas prior to fuel load. (Section 5.4.3.1) (461/85039-31)
32. Develop and implement a means for verifying that personnel outside the
protected area but inside the CPS exclusion area have actually received
the notification of the emergency condition and have followed the
instructions provided prior to fuel load. (Section 5.4.3.1) (461/85039-32)
33. Revise the Emergency Team Data Sheet to provide for individual
authorization signatures for each person who is authorized to exceed
10 CFR 20 limits. The data sheet should also provide for an acknowledge-
ment signature by each authorized worker to signify his understanding of
the assignment, the potential risks, and his willingness to accept those
risks. This must be completed prior to fuel load. (Section 5.4.4)
(461/85039-33)
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Appendix A 4
34. Revise the procedures to identify media organizations, media locations,
and specific methods for contacting the media in the event of an
emergency. This must be completed prior to fuel load. (Section 5.4.6)
(461/85039-34)
35. The procedures should be revised to prescribe the means for coordinating
i.nformation among spokespersons of various organizations and groups prior
to the activation of the JPIC. This must be completed prior te fuel
load. (Section 5.4.6) (461/85039-35)
36. Procedure EPIP FE-05, Emergency Kits, must be modified prior to fuel load
to assign responsibility for inventory and maintenance of emergency
equipment in the Control Room, TSC, OSC, E0F, and BE0F, (Section 5.5.1)
(461/85039-36)
37.' Procedure EPIP AP-09, Emergency Communications Surveillances, must be
modified prior to fuel load to specify the testing frequencies of
emergency communications equipment. (Section.5.5.1) (461/85039-37)
38. All Letters of agreement must be obtained and/or updated prior to fuel
load. (Section 6.1.7) (461/85039-38)
39. The public information brochure must be oisseminated to the public prior
to fuel load. (Section 6.2) (461/85039-39)
40. Emergency information must be made available to the transient population
prior to fuel load. (Section 6.2) (461/85039-40)
41. The operability of the final siren system must be ' demonstrated prior to
fuel load. (Section 6.2) (461/85039-41)
42. The news media must be informed of the applicant's program for media
familiarity with emergency plans, points of contact for release of public
information, space allocated for the media's use, information about
radiation, normal plant operation versus accident operation and accident
sequences. This must be completed prior to fuel load. (Section 6.3)
(461/85039-42)
43. Control Room personnel must be provided with additional training regarding
emergency classifications, especially related to the relationship between
emergency classifications and fission product barrier status. This must
be corrected prior to fuel load. (Section 7.2.2) (461/85039-43)-
44. Conduct additional practical training prior to fuel load for Control Room
personnel concerning notifications, message preparation, and communications
to ensure uniform and timely accomplishment of notification requirements.
(Section 7.2.3) (461/05039-44)
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- Appendix A 5
45. Conduct training for appropriate personnel on the use of SAARS Emergency
Dose Calculation Package and the utilization of computed data from SAARS
prior to fuel load. (Section 7.2.4) (461/85039-45)
46. Revise RA-02, Protective Action Recommendations, to ensure functionality
and compliance with regulatory requirements and guidance, prior to fuel
load. (Section 7.2.5) (461/85039-46)
47. Conduct practical training for emergency response organization personnel
in formulating protective action recommendations based on varying plant
conditions and status, dose assessment / projection, and environmental
conditions prior to fuel load. (Section 7.2.5) (461/85039-47)
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Appendix B -
Improvement Items
+ ?
Based on the results of the NRC's apprdtisal of the Clinton Nuclear Power
Station emergency preparedness program conducted November 12-21, 1985, the
,
following items should be considered for improvement:
1. A formal program for training should be developed and implemented for
individuals who are assigned Emergency Planning responsibilities, which
will enable them tLattain and maintain a state-of-the-art knowledge in
the field of emergency planning and preparedness. (Section 1.3)
2. Section 5.4.3 of the Emergency Plan should be amended to provide that no
one will be assigned a position in the Emergency Response Organization
prior to satisfactorily completing all required training. (Section 3.1)
1y ~
3. The Training Department should be represented on the Safety Evaluation
,
. Review Board _when proposed changes to the EPIPs are considered.
(Section 3.1)'
!
4. Section 5.4.3.2 of the Emergency Plan should be revised so that it clearly
indicates that fire brigade members will receive all required refresher
training at least biannually. (Section 3.1)
5. The discrepancy between Section 5.4.2 of the Emergency Plan which
indicates that lesson plan concurrence is a responsibility of the
Supervisor - Emergency Planning and the CPS position description which
assigns that responsibility to Supervisor - Emergency Response, should
be reconciled. (Section 3.1)
6. A set of selected models and/or color photographs and layouts of key
areas within the' plant should be prepared and maintained for use in job
planning / training for re-entry under accident and/or accident recovery
conditions. (Section 4.1.1.4)
/
7. A routine quality control check, either manual or automated, should be
implemented for, meteorological data. (Section 4.2.1.4)
8. The return-to-service times for replacement of inoperable meteorological
equipment should be reduced. (Section 4.2.1.4)
9. Procedures for obtaining and using backup or offsite meteorological data
should be clarified and simplified, and reflect the uncertainties in
these data sources in the dose assessment and protective action
+decisionmaking process. (Section 4.2.1.4)
10. The plume-segment atmospheric dispersion model used for dose assessment
should be documented and veriff,ed. (Section 4.2.1.4)
11. The following should be considered for inclusion in damage control /
maintenance kits: fire suits; acid suits; steam suits; respiratory
equipment (including ancillary support equipment); protective clothing;
portable lighting; portable radiation monitors; Polaroid cameras and
film; rubber nats; and, Wiggins voltage testers. (Section 4.2.4)
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Appendix B 2
12. Procedure indexes should be provided, where appropriate, to relieve
operator memory tasks. (Section 5.2)
13. References to deleted procedures should be deleted in the operating
procedures. (Section 5.2)
14. Emergency procedures should be prepared for loss of DC power and
Combustible Gas Control. (Section 5.2)
15. Temporary changes should be entered into the body of emergency procedures
to reduce operator workload. (Section 5.D
16. . Emergency Action Levels (EALs) (defined in 10 CFR 50, Appendix E, IV.B)
and emergency cl. asses (Appendix E, IV.C) should be differentiated and
made in accordance with the regulations throughout the Emergency Plan and
EPIPs. (Section 5.3)
17. The Emergency Classification scheme (and supporting EALs) should be
structured in a manner that' establishes the following equivalencies of
fission product barrier integrity and classifications: (a) Unusual Event -
all barriers intact; (b) Alert - one barrier challenged or failed;
(c) Site Area Emergency - two barriers challenged, failed, or combination
thereof; and (d) General Emergency - all three barriers challenged, failed,
or combination thereof. (Section 5.3)
18. Iniiernal references and requirements in the EPIPs and the Emergency Plan
should be consistent. (Section 5.3)
19. . Assumption of duties in various disciplines should be provided by the
first responder to.the facilities. (Section 5.3)
' 20. An authentication scheme should be provided in event of NARS failure.
(Section 5.4.1)
21. The Emergency Plan should specify that a certain percentage of the-drills
will be conducted on the backshifts. (Section 5.5.2)
22. The specific requirements for the annual Emergency Preparedness Program
Audit.should be defined in an expanded version of Section 5.2 of the plan
or in the EPIPs and these requirements should be cited as a reference in
the annual audit order. (Section 5.5.4)
23. The team conducting the annual. audit of the Emergency. Preparedness
Program should observe an emergency drill.other than as controllers or
evaluators. (Section 5.5.4)
24. The applicant should consult and coordinate with'the ambulance service
to improve enroute communications. '(Section 6.1.2)
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Appendix B 3
25. The Sheriff Department's training should be improved to include
information on siren activation, purpose of siren system modifications,
and notification sources. (Section 6.1.5)
26. A sufficient amount of respiratory equipment should be provided *n fully
equip properly manned fire trucks. (Section 6.1.6)
27. Training should be sufficient to distinguish between security requirements
and health physics practices. (Section 6.1.6)
28. IPC Corporate Nuclear Procedure 4-03, Revision 2 should be revised to
accurately reflect who has responsibility for coordination of publication
of the public information brochure. (Section 6.2)
29. A rumor control number should be listed in the public informatico
brochure's next update; in the interim, the rumor control number should
be placed in the monthly newsletter after fuel load. (Section 6.2)
30. Additional practical training for MCR personnel should be conducted to
ensure adequate capability to implement plant emergency procedures.
(Sections 7.2.1)
31. Additional training should be conducted for watch organizations to assure
personnel assignments in the emergency organization make the most efficient
use of the expertise of the various individuals to meet the needs of the
existing situation. (Section 7.2.3)
32. Additional practical training should be conducted for appropriate personnel
in performing EPIP RA-01, Manual Radiological Dose Assessment, and
evaluation of computed data. (Section 7.2.4)
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CONTENTS
PAGE
1.0 ADMINISTRATION OF THE EMERGENCY PREPAREDNESS PROGRAM................ 2
1.1 Responsibility and Authority Assigned.......................... 2-
1. 2 Planning Coordination.......................................... 3
1.3 Selection and Qualification.................................... 3
2.0 EMERGENCY ORGANIZATION.............................................. 3
2.1 Onsite Emergency Organization.................................. 3
2. 2 Augmentation of the Emergency Organization. . . . . . . . . . . . . . . . . . . . . 4
3.0 TRAINING AND RETRAINING.............................................. 5
3.1 Program Establishment.......................................... 5
3.2 Program Implementation......................................... 7
4.0 EMERGENCY FACILITIES AND EQUIPMENT.................................. 8
4.1 Emergency Facilities........................................... 8
4.1.1 Assessment Facilities..................... ............. 8
4.1.1.1 Control Room................................... 8
4.1.1.2 Technical Support Center (TSC)................. 8
4.1.1.3 Operational Support Center (05C)............... 10
4.1.1.4 Emergency Operations Facility (E0F)............ 11
4.1.1.5 Post-Accident Coolant Sampling and
Analysis..................................... 14
4.1.1.6 Post-Accident Containment Air
Sampling and Analysis........................ 14
4.1.1.-7 Post-Accident Gas, Particulate, and
Radiciodine Effluent Sampling and
Analysis..................................... 15
4.1.1.8 Offsite Laboratory Facilities.................. 16
4.1.2 Protective Facilities................................... 16
4.1.2.1 Assembly / Reassembly Areas...................... 16
4.1.2.2' Medical Treatment Facilities................... 17
4.1.3 Expanded Support Facilities............................. 18
4.1.4 Joint Public Information Center (JPIC).................. 18
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4.2 Emergency Equipment............................................ 19
4.2.1 Assessment Equipment.................................... 19
4.2.1.1 Emergency Kits and Emergency Survey
Instrumentation.............................. 19
4.2.1.2 Area and Process Radiation Monitors............ 20
4.2.1.3- Non-Radiation Process Monitors................. 20
4.2.1.4 Meteorological Instrumentation................. 21
4.2.2 Protective Clothing..................................... 23
4.2.3 Emergency Communications Equipment...................... 24
4.2.4 Damage Control / Corrective Action and
Maintenance Equipment and Supplies.................... 25
4.2.5 Reserve Emergency Supplies and Equipment................ 26
4.2.6 Transportation.......................................... 27
5.0 EMERGENCY PLAN AND IMPLEMENTING PROCEDURES.......................... 27
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5.1 General Content and Format..................................... 27
5?2 Emergency,_ Alarm, and Abnormal Occurrence Procedures........... 27
5.3 Implementing' Instructions...................................... 30
5.4 Implementing Procedures........................................ 32
5.4.1 Notifications........................................... 32
5.4.2 Assessment Actions...................................... 33
5.4.2.1' Offsite and Onsite Radiological Surveys. . . . . . . . 36
5.4.2.2 Inplant Radiological Surveys................... 36
5.4.2.3 Primary Coolant Sampling and Analysis.......... 37
5.4.2.4- Fire Assessment and Classification............. 37
5.4.3 Protective Actions...................................... 38
5.4.3.1 Evacuation of Owner Controlled Areas........... 38
5.4.3.2 Personnel Accountability....................... 39
5.4.3.3 Onsite irst Aid and' Rescue.................... 39
5.4.4' Repair and Corrective Actions........................... 39
5.4.5 Recovery................................................ 40
5.4.6 Public Information...................................... 41
5.5 Suppl ementa ry Procedu re s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i41
5.5.1 . Inventory, Operational Check, and Calibration of
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-Emergency Equipment, Facilities, and Supplies.........
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5.5.2 ' Drills and Exercises.................................... 42
5.5.3 Review, Revision and Distribution....................... 43-
5.5.4 Audits.................................................. 43
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6.0 COORDINATION WITH OFFSITE GR0UPS.................................... 44
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6.1 Offsite Agencies............................................... 44
6.1.1 DeWitt County Board..................................... 44
6.1.2 Clinton Ambulance Service................. ............. 45
6.1.3 Illinois and DeWitt County /Clinton Emergency
Services and Disaster Agency (ESDA)................... 45
6.1.4 Medical Services Arrangements........................... 45
6.1.5- DeWitt County Sheriff................................... 46
6.1. 6 Clinton Fire District................................... 46
6.1.7 Letters of Agreement.................................... 47
6.2 General Public and Transient Population........................ 47
6.3 News Media..................................................... 49
- 7.0 DRILLS, EXERCISES AND WALKTHROUGHS.................................. 49
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7.1 Drills and Exercises........................................... 49
7.2 Main Control Room Wal kthrough Observations. . . . . . . . . . . . . . . . . . . . . 49
7.2.1 Emergency Detection..................................... 49
7.2.2 Emergency Classificaticn................................ 50
- 7.2.3 Notifications........................................... 50
7.2.4 Dose Calculations....................................... 51
- 7.2.5 Protective' Action Decisionmaking........................ 52
7.3 Emergency Response Organization Walkthrough Observations....... 53
8.0 PERSONS C0NTACTED................................................... 53
8.1 - Illinois Power Personnel....................................... 53
8.2 Non-Illinois Power Personne1................................... 55
9.0 EXIT INTERVIEW...................................................... 55
Attachment: -Emergency Response Organization
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