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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
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JUN 18 586 DISTRIBUTION JUocreT7TTes DVassallo,F0B Docket No. 50-461 PD#4 Rdg.~~ RBernero NRC PDR RGoddard,0 ELD LPDR WButler BSiegel Mr. Frank A. Spangencerg M0'Brien Manager-Licensing and Safety EJordan Clinton Power Station BGrimes P.O. Box 678 JPartlow Mail Code V920 ACRS(10)
Clinton, Illinois 61727 NThompson
Dear Mr. Spangenberg:
SUBJECT:
DRAFT LOW POWER LICENSE Re: Clinton Power Station, Unit No. 1 As you are aware, the staff is preparing a low power license (NPF-55) for the Clinton Power Station. Enclosed is a draft copy of this license but without attachment I and appendices. It is provided for your review and comment to ensure that it accurately reflects the commitments required of you as described 4
in the FSAR, SER and other documents. We request that you review this draft low power license and provide any comments in writing within 10 working days of receipt of this document.
If you have any questions regarding this draft low power license, contact the staff's Project Manager for your application, Byron Siegel, at (301) 492-9474.
l Sincerely, original signed by Walter R. Butler, Director BWR Project Directorate No. 4 i
Division of BWR Licensing
Enclosure:
As stated cc: w/ enclosure See next page
! PD#1) PD#4/?M k PD#4/D M0 ' B r, BSiegel:f6 WButler -
86 06/tW86 06/ly/86 06/[
8606270078 860618 PDR ADOCK 05000461 A PDR
Mr. Frank A. Spangenberg Clinton Power Station Illinois Power Ccmpany Unit 1 cc:
Mark Jason Richard B. Hubbard Assistant Attorney General Vice President Public Utilities Division Technical Associates Office of the Attorney General 1723 Hamilton Avenue - Suite K State of Illinois Center San Jose, California 95125 100 West Randolph Street - 12th Floor Chicago, Illinois 60601 Chairman of DeWitt County c/o County Clerk's Office Mr. D. P. Hall DeWitt County Courthouse Vice President Clinton, Illinois 61727 Clinton Power Station P. O. Box 678 Director, Criteria & Standards (ANR-460)
- Clinton, Illinois, 61727 Office of Radiation Programs V. S. Environmental Protection Agency Mr. D. C. Shelton Washington, DC 20460 Manager-Nuclear Station Engineering Dpt.
Clinton Power Station EIS Review Coordinator P. O. Box 678 .
Environmental Protection Agency 4.
Clinton, Illinois 61727 Region V 230 S. Dearborn Street Sheldon Zabel, Esquire Chicago, Illinois 60604 Schiff, Hardin & Waite 7200 Sears Tower Illinois Department of Public Health 4 233 Wacker Drive ATTN: Chief, Division of Nuclear Safety Chicago, Illinois 60606 535 West Jefferson Springfield, Illinois 62761 Resident Inspector U. S. Nuclear Regulatory Commission Director, Eastern Environmental RR 3, Box 229 A Radiation Facility Clinton, Illinois 61727 U. S. Environmental Protection Agency i P. O. Box 3009 i Mr. R. C. Heider Montgomery, Alabama 36193 Project Manager Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Mr. L. Larson Project Manager General Electric Company 175 Curtner Avenue, N/C 395 San Jose, California 95125 Regional Administrator, Region III 799 Roosevelt Road )
Glen Ellyn, Illinois 60137 l
l l
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) % UNITED STATES
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5
- p NUCLEAR REGULATORY COMMISSION W ASHINGTON. D. C. 20555
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ILLIN0IS POWER COMPANY S0YLAND POWER COOPERATIVE, INC.
WESTERN ILLINOIS POWER COOPERATIVE, INC.
DOCKET NO. 50-461 ,,
CLINTON POWER STATION, UNIT'NO. 1 FACILITY OPERATING LICENSE 1.icense No. NPF-55
- 1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A. The application for license filed by Illinois Power Company * (IP),
acting on behalf of itself and as agent for Soyland Power Cooperative, Inc. and Western Illinois Power Cooperative, Inc. (licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in
~~
- h. - --40.CFR Chapter If and all required notifications to other agencies or bodies have been duly made; B. Construction of the Clinton Power Station, Unit No. 1 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-137 and the application, as amended, the provisions of the Act and the regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.0.
below);
D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D.
below);
E. Illinois Power Company is technically qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F. The licensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," '
of the Comission's regulations;
- Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and Western Illinois Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
- e. .
G. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and c'ontidering available alternatives, the issuance of Facility . ~- .
Operating License No. NPF-55, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.
- 2. Based on the foregoing findings, Facility Operating License NPF-55 is hereby issued to Illinois Power Company, Soyland Power Cooperative, Inc.
and Western Illinois Power Cooperative, Inc. (the licensees), to read as follows: , ,
A. This license applies to the Clinton Pcwer Station, Unit No. 1, a boiling water nuclear reactor and associated equipment (the facility), owned by Illinois Power Company, Soyland Pcwer Cooperative, Inc. and Western Illinois Power Cooperative, Inc. The facility is located in Harp Town-ship, DeWitt County, approximately six miles east of the city of Clinton in east-central Illinois ar.d is described in the licensees' Final Safety Analysis Report, as supplemented and amended, and in the licensees' Environmental Report-0perating License Stage, as supplemented and amended.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Illinois Power Company (IP), pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in Harp Township, DeWitt County, Illinois, in accordance with the procedures and limitations set forth in this license; (2) Soyland Power Cooperative, Inc. and Western Illinois Power Cooper-ative, Inc. pursuant to Section 103 of the Act and 10 CFR 50, to possess the facility at the above designated location in accord-ance with the procedures and limitations set forth in this license; (3) IP, pursuant to the Act and 10 CFR Part 70, to receive, possess and to use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;
(4) IP, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radi-ation monitoring equipment calibration, and as fission detectors
- in amounts as required; - -
(5) IP, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) IP, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the condi-tions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all. applicable provisionstof the..A. t agg ,
- -to the rules, regulations and orders of the Commission now ors (he m 4 after in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level IP is authorized to operate the facility at reactor core power levels not in excess of 2894 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
Pending Commission approval this license is restricted to power levels not to exceed five percent of rated power (144.7 megawatts thermal). The items identified in Attachment I to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. IP shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions IP shall comply with the antitrust conditions in Appendix C
- attached hereto, which is hereby incorporated into this license.
i W. 1
(4) Inservice Inspection Program (Section and 6.6, SER, SSER 1 and SSER 5)*
.IP shall submit the initial inservice inspection program required by 10 CFR 50.55(a) for NRC staff review and approval
. . - = within six (6) months after exceeding five percent of rated powert -
(5) New Fuel Storage (Section 9.1.1, SER and SSER 6)
IP shall store new fuel assemblies in accordance with the requirements specified in Attachment 2. Attachment 2 is hereby incorporated into this license.
(6) Fire Protection (Section 9.5.1, SER, SSER 1, SSER 3, SSER 5 and SSER 6)
IP shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report as amended, for the Clinton Power Station, Unit No. 1, and as approved in the Safety Evaluation Report (NUREG-0853) i dated February 1982 and Supplement Nos. I thru 6 thereto subject '
to the following provision: -
IP may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(7) Post-Fuel Loading Initial Test Program (Section 14, SER and SSER 5)
Any changes to the initial test program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change. 1 (8) Partial Feedwater Heating (Section 15.1, SER, SSER 5, and SSER 6)
The facility shall not be operated with partial feedwater heating for the purpose of extending the normal fuel cycle.
After the first operating cycle, steady state operation with reduced feedwater temperature during the normal fuel cycle l
t
! *The parenthetical notation following the title of many license conditions l denotes the section of the Safety Evaluation Report and/or its supplements ,
wherein the license condition is discussed. I
shall be prohibited until plant specific analyses justifying such operation are provided by IP and approved by the staff.
(9.) Emergency Response Capabilities (Generic Letter 82-33, Supplement 1 to NUREG-0737, Section 7.5.3.1, SSER 5, .
~ " Section 7.5.3.2, SSER 6 and Section 18, SER and 55ER 5) *" '
- a. IP shall install and have operational separate Class IE power sources on the fuel zone level channels and inform the staff that the fuel zone level instrument item has been environmentally qualified in accordance with the requirements of 10 CFR 50.49 prior to startup following the first refueling outage.
- b. IP shall submit a detailed control room design supplemental summary report within six (6) months of receipt of a low-power license that addresses all the items identified in Section 18.3 of Supplement 5 to the SER.
- c. The SPDS modifications related to the display of the con-tainment isolation valve group status in the main control.
room and the incorporation of the 51 additional valves and the isolation valves currently statused on the SPDS into 13 valve groups, instead of 11 shall be completed on the schedule contained in IP's June 11, 1986 letter.
(10) Emergency Planning (Section 13.3, SSER 6)
In the event the NRC staff finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive' problem exists in achieving or maintaining 1 an adequate state'of emergency preparedness, the provisions of '
10 CFR Section 50.54(s)(2) will apply.
(11) Salem ATWS Event, Generic Letter 83-28 (Section 15.2.2, SSER 5 and SSER 6)
IP shall implement the requirements of Generic Letter 83-28, for those items not already completed, on a schedule which is consistent with that given in IP's letter dated October 1, 1984, 1
1 w- .
The facility requires exemptions from certain requirements of 10 CFR D.
Part 50 and 10 CFR Part 70. An exemption from the criticality alarm requirements of 10 CFR 70.24 was granted in an Amendment to the Special Nuclear Material License No. SNM-1886 dated November 27, 1985.
This exemption is described in Section 9.1.1 of Supplement No. 6 fo'the SER. This previously granted exemption is continued in this -'-
operating license. Exemptions from certain requirements of Appendix A to 10 CFR Part 50 are described in Supplement No. 6 to the SER. These include: (a) A schedular exemption from the requirements of General Design Criterion (GDC) 29, permitting deferral of completion of pre-operational acceptance testing of the Turbine Electrohydraulic Control System until prior to reactor heatup (Appendix to SSER 6); (b) A schedular exemption from the requirements of GDC 13, permitting deferral of completion of preoperational testing of the Traversing Incore Probe System until prior to reactor heatup (Appendix to S3ER 6); (c) A schedular exemption from the requirements of GDC 60, permitting deferral of preoperational testing related to the Off-Gas System until prior to reactor pressure vessel headset before heatup (Appendix TOSSER 6);
(d) A schedular exemption from the requirements of GDC 41 and 64, permitting deferral of preoperational testing related to portions of the Containment (Appendix to SSERMonitoring) Systemexemption 6); (e A schedular until priorfrom to initial criticality the requirements of GDC 30 and 64, permitting deferral of preoperational testing of the Leakage Detection System until prior to initial criticality (Appendix to SSER 6); (f) A schedular exemption from the requirements of GDC 61, permitting deferral of completion of preoperational testing of a portion of the Fuel Pool Cooling and Cleanup System until prior to exceeding five percent of rated reactor power or before removal of the reactor pressure vessel head after initial criticality (Appendix TOSSER 6);
(g) A schedular exemption from the requirements of GDC 61, permitting deferral of completion of preoperational testing of a portion of the Fuel Handling System until prior to exceeding five percent of rated reactor power or before removal of the reactor pressure vessel head after initial criticality (Appendix to SSER 6); (h) A schedular exemption from the requirements of GDC 19 permitting deferral of completion of preoperational testing of the In-Place Filters on the Control Room Heating Ventilating and Air Conditioning System until prior to initial criticality (Appendix to SSER 6); and (1) A sched-ular exemption from the requirements of GDC 41, 57, 60, 61, 63 and 64 permitting deferral of various tests of the Heating, Ventilation and Air Conditioning Systems until prior to reactor heatup or before removal of the reactor pressure vessel head after initial criticality (Appendix to SSER 6). Additional exemptions from two requirements of Appendix J to 10 CFR Part 50 are described in Supplement No. 6 to the SER. These are: a)AnexemptionfromtherequirementofParagraphIII.D.2(b)(ii) l l
6
of Appendix J, substituting the seal leakage test at Pa of paragraph III.D.2(b)(iii) for the entire airlock test at Pa of paragraph III.D.2(b)(ii) of Appendix J when no maintenance has been performed in the airlock that could affect its sealing capability (Section 6.2.6 of SSER 6); and (b) An exemption from the requirement of
- - Pa5 graph III.C.3 of Appendix J, exempting the measured leakage rates +L from the main steam isolation valves from inclusion in the combined leak rate for the local leak rate tests (Section 6.2.6 of SSER 6).
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the comon defense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E. IP shall fully implement and maintain in effect all provisions of the physical security, guard training and qualifications, and safe-l guards contingency plans previously approved by the Commission and all amendments and revisions to such plans made pursuant to,the authority under 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain safeguards information protected under 10 CFR 73.21, are entitled: "Clinton Power Station Physical Security Plan," with revisions submitted through January 17, 1936, "Clinton Power Station Guard Quali-fication and Training Plan," with revisions submitted through September 19, 1985; and "Clinton Power Station Safeguards Contingency Plan,"
with revisions submitted through September 20, 1985.
F. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, IP shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73 (b), (c), and (e).
G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accord-ance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
H. This license is effective as of the date of issuance and shall expire at midnight on 2026 FOR THE NUCLEAR REGULATORY COMMISSION
~~ = -
cG4. . s Harold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1. Attachments 1 and 2
- 2. Appendix A - Technical Specifications (NUREG-1203)
- 3. Appendix B - Environmental Protection Plan
- 4. Appendix C - Antitrust Conditions Date of Issuance:
m 1
e i
4
,r
H. This license is effective as of the date of issuance and shall expire at midnight on 2026 FOR THE NUCLEAR REGULATORY COMMISSION
~ .
,, ; ':n;. ' ' 2.*
Harold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1. Attachments 1 and 2
- 2. Appendix A - Technical Specifications (NUREG-1203)
- 3. Appendix B - Environmental Protection Plan
- 4. Appendix C - Antitrust Conditions Date of Issuance:
PD#4/LA PD#4/PM SAB/DE SP SP OELD OELD M0'Brien BSiegel:1b WLamb IDinitz JSaltzman RGoddard EReis
/ /86 / /86 / /86 / /86 / /86 / /86 / /86 OELD PD#4/D DD/ DBL D/BDL DD/NRR D/NRR JScinto WButler RHouston RBernero DEisenhut HDenton
/ /86 / /86 / /86 / /86 / /86 / /86
O 4
ATTACHMENT I DETAILS TO BE PROVIDED AS APPROPRIATE BY REGION III
.. , e
^
I ATTACHMENT 2 TO NPF-55 NEW TUEL STORAGE IP shall store new fuel assemblies in accordance with the following requirements.
- a. No more than three. fuel assemblies shall be outside their shipping containers and storage racks at any one time. . ..
- b. The minimum edge-to-edge distance between the group of three fuel assemblies and all other fuel assemblies shall be 12 inches,
- c. Fuel assemblies for the initial core, when stored dry in the Contain-i ment Fuel Storage Pool, shall be stored such that: no more than 12 rows of fuel assemblies shall remain uncovered during the loading or unloading of fuel assemblies; fire retardant covers shall cover all other rows containing fuel assemblies during loading and unloading of fuel assemblies; when loading or unloading of fuel assemblies is not in progress, fire retardant covers shall cover all rows of fuel assemblies; increased surveillance of the Containment Fuel Storage Pool vicinity will be maintained to assure that the area is kept free of extraneous combustible material; the fire protection hose stations servicing the Containment Fuel Storage Pool area will be equipped-with solid stream nozzles prior to the dry storage of fresh fuel assemblies in the Containment Fuel Storage Pool; and the containment spray system will be tagged out prior to the dry storage of fresh fuel as'semblies in the Containment Fuel Storage Pool in a status that will prevent initiation of a spray or mist.
- d. Fuel assemblies, when stored in the New Fuel Storage Vault, shall be stored such that: no more than 12 rows of fuel assemblies shall remain uncovered during the loading or unloading of fuel assemblies; metal covers shall cover all other rows containing fuel assemblies during loading and unloading of fuel assemblies; and when loading or unloading of fuel assemblies is not in progress, metal covers shall cover all rows of fuel assemblies.
- e. Fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of flooding and sub-sequent draining of the fuel storage area.
l f. Fresh fuel assemblies after the initial core loading shall be stored in the containment fuel storage pool only under water.
- g. No fuel assemblies shall be stored in the control rod racks.
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