Similar Documents at Cook |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999 Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21 IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20217D9241999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML20196K5961999-06-30030 June 1999 Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021 ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML20207A9201999-05-21021 May 1999 Ack Receipt of 990319 Response to Notice of Violation & Proposed Imposition of Civil Penalty .On 981124, Licensee Remitted Check for Payment of Civil Penalties. Licensee Requests for Extension for Response,Granted ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML20205P0591999-04-14014 April 1999 Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed ML17325B5141999-03-30030 March 1999 Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML17325B5191999-03-29029 March 1999 Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed ML20204F6401999-03-19019 March 1999 Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage ML17325B4751999-03-18018 March 1999 Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed ML17325B4721999-03-18018 March 1999 Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal ML17325B4641999-03-17017 March 1999 Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML17328A4481990-09-21021 September 1990 Requests Withdrawal of Mode 6 Proposed Tech Spec Change Since Issue Currently Being Addressed by New STSs ML17328A4331990-08-27027 August 1990 Informs of Preliminary Assessment of 900713 Electrical Contact Accident at Facility.Investigation Concludes That No Safety Rules Violated ML17328A4001990-08-24024 August 1990 Responds to 900725 Ltr Re Commitments Made in Response to Generic Ltr 88-14 on Instrument Air Supply Problems Affecting safety-related Equipment.Simulator Training to Be Provided as Stated ML17334B3781990-08-24024 August 1990 Forwards Info to Certify Plant Simulator Facility.Results of Evaluation of Dual Unit Simulation Facilities Demonstrate That Plant Simulator Performance Compares Favorably W/Units ML17328A4231990-08-21021 August 1990 Forwards Under Separate Cover,Semiannual Radioactive Effluent Release Rept for Jan-June 1990 ML17328A3901990-08-17017 August 1990 Responds to NRC 900720 Ltr Re Violations Noted in Onsite Audit of Spds.Corrective Actions:Apparent Disparity in Selection of Reactor Trip & Sys Capacity or Anticipatory Values Rectified ML17328A3891990-08-15015 August 1990 Forwards Performance Data Sheets for Plant fitness-for-duty Program for Period Jan-June 1990,per 10CFR26.Encl Includes Statistics on Various Categories of Testing,Substances Tested for & cut-off Levels Used ML17328A3571990-08-0202 August 1990 Responds to Open Items in Safety Evaluation of Util Response to Unresolved Issues on post-fire Safe Shutdown Methodology. Open Items 1 & 21 Will Be Closed by Implementing Plant Procedures Providing Equivalent Degree of Protection ML17328A3431990-07-23023 July 1990 Requests Withdrawal of 890830 Proposed Tech Spec Changes Re Sections 3.0 & 4.0.Util Will Resubmit Generic Ltr 87-09 Recommended Improvement Items on Case by Case Basis ML17328A3421990-07-23023 July 1990 Provides Results of Offsite Dose Calculation for Reactor Coolant Pump Locked Rotor Event for Facility Cycle 8.Util Identified Previously Issued SERs Addressing Short Term Containment Analysis & LOCA Containment Integrity ML20055G7551990-07-18018 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-315/90-10 & 50-316/90-10.Corrective Actions:Required Review Performed & Updated Procedure 12 Mhp 5021.019.001 Revised & Issued ML17328A3191990-07-12012 July 1990 Responds to NRC 900601 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Electrical Testing Techniques Improved & Surveillance Procedures for Feedwater Pumps Will Be Rewritten ML17328A3181990-07-0909 July 1990 Responds to Generic Ltr 90-03,Suppl 1, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' Licensee Will Contact safety-related Vendors on Annual Basis ML17328A3111990-07-0303 July 1990 Provides Certification of Funding Plan for Decommissioning of Plant,Per 10CFR50.33 & 50.75 ML17328A2961990-06-25025 June 1990 Forwards Response to Generic Ltr 90-04 Re Closeout of Generic Safety Issues.Util Supports Concern & Desire to Close long-standing Generic Safety Issues ML17328A2921990-06-22022 June 1990 Forwards WCAP-12483, Analysis of Capsule U from American Electric Power Co DC Cook Unit 1 Reactor Vessel Radiation Surveillance Program. ML20044A3521990-06-22022 June 1990 Submits Info Re Sensitivity Study Performed on Number of Fuel Axial Intervals,Per Topical Rept, American Electric Power Reactor Core Thermal-Hydraulic Analysis Using Cobra III-C/MIT-2 Computer Code. ML17328A2821990-06-15015 June 1990 Submits Ltr Re Proposed Control Room Habitability Tech Spec Changes & Supporting Analyses,Per 900521 Discussion.Revised Calculations of Control Room Thyroid Doses Will Be Submitted within 60 Days of Receipt of Proposed Generic Ltr ML17328A2741990-06-12012 June 1990 Submits Followup,Per 900205 & 0308 Ltrs & Provides Update Re Inoperable Fire Barrier.Fire Seal Repaired & Restored to Operability on 900419 ML17328A2551990-06-0505 June 1990 Forwards Addl Info Re Util 900126 Revised Response to NRC Bulletin 88-002,per NRC 900509 Request ML17328A7361990-06-0101 June 1990 Forwards Addl Info Re 890825 & 1212 Applications for Amends to Licenses DPR-58 & DPR-74,per Request.Amends Make Changes to Administrative Controls ML17328A7331990-05-29029 May 1990 Forwards Nonproprietary WCAP-12577 & Proprietary WCAP-12576, Westinghouse Revised Thermal Design Procedure Instrument... Methodology for American Electric Power DC Cook Unit 2 Nuclear Power Station, Per 900419 Commitment ML17328A7321990-05-24024 May 1990 Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Model 1153 Series B or D or Model 1154 Transmitters Installed at Facility.Transmitters Purchased as commercial-grade Units ML17328A6991990-05-0909 May 1990 Provides Suppl to 900103 Response,Certifying That Fitness for Duty Program Implemented at Plant.Change Also Clarifies When More Stringent cut-off Levels Adopted at Plant Program Apply ML17328A7001990-05-0909 May 1990 Responds to NRC 900406 Ltr Re Inadequacies of Spds,Per Audit on 900221-22.Corrective Actions:Software Mod Will Prevent User from Accessing Displays Other than Iconic Displays from SPDS Dedicated Terminal ML17328A7071990-05-0707 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept Mar 1990 for Donald C Cook Nuclear Plant Unit 1 ML17328A7031990-05-0707 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for DC Cook Nuclear Plant Unit 2 ML17328A6951990-04-30030 April 1990 Certifies That Training Programs for Initial Licensing & Requalification Training of Operators & Senior Operators at Plant Accredited by Inpo,Per Generic Ltr 87-07 ML17328A6861990-04-30030 April 1990 Forwards Annual Environ Operating Rept,Jan-Dec 1989, & DC Cook Nuclear Plant Units 1 & 2 Operational Radiological Environ Monitoring Program 1989 Rept Jan-Dec 1989. ML17328A6801990-04-23023 April 1990 Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Study Planned to Evaluate Alternative Actions to Be Taken for Protecting RHR Pumps ML17328A6771990-04-23023 April 1990 Forwards DC Cook Nuclear Plant 1990 Annual Emergency Preparedness Exercise. Exercise Scope & Objectives & Detailed Scenario Documentation Encl ML17334B3641990-04-11011 April 1990 Responds to NRC 900301 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Reliability Centered Maint Program Initiated ML17328A6601990-04-11011 April 1990 Forwards Updated QA Program Description for Cook Nuclear Plant, Incorporating Editorial,Organizational & Position Title Changes ML17328A6551990-04-0909 April 1990 Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-316/90-08.Corrective Actions:Procedure for Steam Generator Stop Valve Operability Test Revised to Require That MSIV Be Declared Inoperable After Failing Stroke Test ML17334B3601990-04-0606 April 1990 Forwards Revised Figures for Loss of Load Event Previously Submitted in Attachment 4,App B of Vantage 5 Reload Transition Safety Rept Supplied by Westinghouse in Jan 1990. Update Is Editorial in Nature ML17334B3621990-04-0606 April 1990 Forwards 1989 Annual Rept & Projected Cash Flow ML17328A6341990-03-30030 March 1990 Forwards Application for Renewal of Plant NPDES Permit,For Info,Per Section 3.2 of App B to Plant Tech Specs.W/O Encl ML17328A6331990-03-30030 March 1990 Responds to NUMARC 900104 Request for Addl Info Re Station Blackout Submittals.Target Reliability for Emergency Diesel Generator of 0.0975 Established for 4 H ac-independent Coping Category Will Be Maintained ML17328A6321990-03-30030 March 1990 Forwards Response to Generic Ltr 90-01, NRC Regulatory Impact Survey. Util Ack Recommendation by NUMARC ML17328A6221990-03-27027 March 1990 Responds to 900226 Ltr Transmitting Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000. Corrective Actions:Flow Retention Circuitry Setpoints Set to Compensate for Missized Process Flow Orifice ML17328A6191990-03-27027 March 1990 Forwards Payment in Amount of $75,000 for Civil Penalty Imposed Through Notice of Violation Issued in Insp Rept 50-316/89-02 on 891016-20,24-26 & 1204.Response to Violation & Corrective Actions Provided in Separate Submittal ML17328A6161990-03-20020 March 1990 Responds to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs (USI A-47).Both Units Have Steam Overfill Protection Sys That Would Automatically Prevent Water Carryover Into Steam Lines If Control Sys Failed ML17328A6121990-03-13013 March 1990 Forwards Monthly Performance Monitoring Rept,Jan 1990. ML17325B3901990-03-0606 March 1990 Forwards Annual Rept to NRC Per 10CFR50.54(W)(2) Re Nuclear Property Insurance ML17325B3921990-03-0606 March 1990 Modifies Application for Amend to License DPR-74 Re Cycle 8, Per 900228 Telcon ML17325B3781990-02-28028 February 1990 Forwards Response to NRC Info Notice 89-056 Re Questionable Certification of Matl Supplied to Dod by Nuclear Suppliers. Matl Capable of Performing Design Function & Acceptable for Continued Use ML17328A5971990-02-27027 February 1990 Withdraws 890203 Application for Amend to License DPR-74, Modifying Tech Spec Table 3.2-1 Re DNB Parameters to Express RCS Flow Rate on Volumetric Rather than Mass Basis ML17334B3511990-02-22022 February 1990 Submits Annual Rept of Changes to or Errors in Acceptable LOCA Evaluation Models or Application of Models for Plants. Wflash Analyses Will Be Superceded by Notrump Analyses for Unit 2,Cycle 8 Reload ML17328A5881990-02-21021 February 1990 Responds to NRC 890914 Request for Addl Info Re Safe Shutdown Methodology.App R Fire Barriers Being Maintained & Surveilled Under 3/4.7.10 for Units 1 & 2 ML17328A5861990-02-16016 February 1990 Provides Revised Comments in Response to NRR Comments During 891213 Telcon Re Allowable Stresses for Piping & Piping Supports 1990-09-21
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AC CELE RATED DlKBl'TJ ON DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8905260403 DOC.DATE: 89/05/16 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION NXLLIAMS,D.H. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECXP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards response to NRC Bulletin 88-010, "Nonconforming Molded-Case Circuit Breakers."
DISTRIBUTION CODE: IE21D TITLE: Bulletin Response COPIES RECEIVED:LTR L ENCL 88-10 Nonconforming Molded Case
( SIZE:
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indiana Michigan Power Company P.O, Box 16631 Columbus, OH 43216 INDIANA NICHIGAN POWER AEP:NRC:1083A Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NRC BULLETIN NO. 88-10: REPORT ON ACTION ITEM STATUS U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley May l6, l989
Dear Dr. Murley:
The purpose of this letter is to provide a response to NRC Bulletin No. 88-10, "Nonconforming Molded-Case Circuit Breakers." Reporting requirement 1 of the bulletin required all holders of operating licenses to provide a written report by April 1, 1989, that:
- 1) Confirms that only molded-case circuit breakers that meet the criteria of Item 7 of the actions requested are being maintained as stored spares for future use in safety-related applications,
- 2) Provides information on those circuit breakers that could not be traced to the circuit breaker manufacturer in Items 1 and 4 of the actions requested, and
- 3) Confirms that Items 1 through 7 of the actions requested hav been completed or will be implemented as requested.
A previous submittal, AEP:NRC:1083, "Request for Extension on NRC Bulletin No. 88-10 Action Items and Reporting Requirements,"
requested extension of our response to May 16, 1989. The attachments to this letter fulfillour commitment to respond to the bulletin.
p9p52 gpzp3 e9p5~~ pg,ppps f 6 pDR ADO pDC 9
Dr. T. E. Murley AEP'NRC:1083A This letter is being submitted under oath pursuant to the provisions of Section 182a, At'omic Energy Act of 1954, as amended.
As such, an oath is attached.
Sincerely, David H. Wi liams, Jr.
Vice President ldp Attachments cc: M. P. Alexich W. G. Smi.th, Jr. - Bridgman R. C. Callen G. Charnoff A. B. Davis NRC Resident Inspector - Bridgman G. Bruchmann
STATE OF OHIO COUNTY OF FRANKLIN David H. Williams, Jr., being duly sworn, dep'oses and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing Response to Bulletin No. 88-10: Nonconforming Molded Case Circuit Breakers and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
Subscribed and sworn to before me this day of 198~.
NOTARY PUBLIC DlANE P. POWELL NOTARY PUBLIC-STATE OF, HIP MY COMMISSION EXPIRES .....6 j&%.$ 3.
ATTACHMENT 1 TO AEP:NRC'1083A RESPONSE TO NRC BULLETIN NO. 88-10 to AEP:NRC:1083A Page 1, Reporting Requirements:
--1) All holders of operating licenses are required to provide a written report by April 1, 1989, that:
a) Confirms that only molded-case circuit breakers that meet the criteria of Item 7 of the actions requested are being maintained as stored spares for future use in safety-related applications.
~Res onse Steps have been initiated to ensure that only molded-case circuit breakers that meet the criteria of Item 7 of the acti.ons requested are being maintained as stored spares for future use in safety-related applications.
b) Summarizes the total number, manufacturer, model number, and to the extent possible the procurement chain of those circuit breakers that could not be traced to the circuit breaker manufacturer in Items 1 and 4 of the actions requested. For installed circuit breakers, also identify each system in which they are/were installed. If Item 4 of the actions requested has not been completed by April 1, 1989, due to the schedule for tests in Item 3 of the actions requested, this information should be updated within 30 days of the completion of Item 4 to address those additional circuit breakers that could not be traced to the circuit breaker manufacturer.
~Res onse The total number, manufacturer, model number, and, to the extent possible, the procurement chain of those circuit breakers that could not be traced to the circuit breaker manufacturer in Item 1 of the actions requested are summarized in Attachment 2.
Since these circuit breakers were initially being maintained as stored spares, the system in which they are/were installed is not applicable.
The total number, manufacturer, model number, procurement chain to the extent possible, and each system in which they are/were installed for those circuit breakers that could not be, traced to the circuit breaker manufacturer in Item 4 of the actions requested are summarized in Attachment 3 for to AEP:NRC:1083A Page 2 Unit 1 only. Item 4 of the actions requested has been completed for Unit 1 (presently in a refueling outage) with the exception of the five models of General Electric (GE) circuit breakers identified in Attachment 3. The traceability of these circuit breakers has not yet been verified. We plan to take the following actions regarding these circuit breakers:
GE THED(60 amp), GE TED(80 amp) and GE TFK(125 amp): These circuit breakers were purchased as part of a qualified system (control room instrumentation dis tribution inver ters) from Solidstate Controls. While indications exist that these circuit breakers were manufactured by General Electric, Plainville, CT, for Solidstate Controls via GESCO, Columbus, OH, a complete documentat'ion trail has not yet been established. We are continuing attempts to establish traceability for these circuit breakers. If traceability cannot be established, an analysis justifying continued operation will be prepared prior to startup of Unit 1 and the untraceable circuit breakers will be replaced at the next refueling outage.
GE TEB (20 amp) and GE TEB (50 amp): These circuit breakers were purchased as panel components from Farwell & Hendricks and are installed in the auxiliary feedwater and auxiliary emergency local shutdown control distribution panels. Only two of the 20 amp circuit breakers are presently supplying loads in Unit 1 with the remainder of the 20 amp circuit breakers and all of the 50 amp circuit breakers serving as spares. A modification is under investigation to relocate the two loads from the 20 amp circuit breakers to alternate power sources. If traceability cannot be established for these circuit breakers, an analysis )ustifying continued operation will be prepared prior to startup of Unit l.
Item 4 of the actions requested is pro)ected to be completed for Unit 2 by June 30, 1989. We will update Attachment 3 with Unit 2 information by July 28, 1989.
The procurement information presented in Attachments 2 and 3 provides the source(s) for each model number to AEP:NRC:1083A Page 3 of molded-case circuit breaker. A specific model number may have been procured from more than one source. Since the circuit breakers are.not tracked by serial number, the source of a given circuit breaker cannot be identified. However, the source of a given circuit breaker is limited to those sources listed for that model number. All sources, even those that provide traceability, are listed for each model number. The source(s) for which traceability could not be verified are marked with an asterisk (*). The sources were identified by reviewing stores issue and receipt inspection records at Cook- Nuclear Plant.
c) Confirms that Items 1, 2, 3, 4, 5, 6 and 7 of the actions requested have been completed or will be implemented as requested.
R~es onse Per action Item l.a, we identified all molded-case circuit breakers purchased prior td August 1, 1988, that were being maintained as stored spares for safety-related (Class 1E) applications, No commercial grade circuit breakers were being maintained as stored spares for future dedication and use in safety-related applications, More than 50 stored spare circuit breakers were identified per Item 1 of the actions requested. Therefore, it was not necessary to randomly select installed circuit breakers to form a minimum sample of 50 circuit breakers.
Action Item l.b reque'sts that the traceability of the sample identified above be verified.
"Circuit breaker manufacturer" and "verifiable traceability" are defined in Attachment 2 of NRC Bulletin No. 88-10. Per these definitions, documented evidence from the manufacturing facility that actually produced the circuit breaker is required to establish traceability.
If the documented evidence is provided by any party other than the circuit breaker manufacturer, the bulletin required that the validity of the evidence be verified through an audit or other appropriate means.
In evaluating the traceability of molded-case ci'rcuit breakers at Cook Nuclear Plant, to AEP:NRC:1083A Page 4 traceability to distribution centers or divisions other than supply companies was accepted. For example, in the case of molded-case circuit breakers manufactured by Westinghouse Electric Corporation at their facility in Beaver, PA., traceability to distribution centers in Duncan, SC., or St. Louis, MO., was accepted. Traceability to Westinghouse divisions such as Westinghouse Nuclear Services in Monroeville, PA., or Westinghouse Power Systems in Pittsburgh, PA.,
was also accepted. On the other hand, traceability to any regional office of Westinghouse Electric Supply Company (WESCO) was not accepted. This methodology was used for evaluating the traceability of stored spares per Action Item 1 and installed circuit breakers per Action Item 4.
Action Item l.c requests that the number, manufacturer, model number, and, to the extent possible, the procurement chain for all those circuit breakers identified in action Item l.a be identified. This information has been identified and is submitted in Attachment 2 of this letter.
- 2) Action Item 2 requests that all holders of operating licenses who identify installed circuit breakers per action Item 1 or 4 that cannot be traced to a circuit breaker manufacturer prepare, within 30 days of the completion of each item, an analysis )ustifying continued operation until action Items 1 through 5 have been completed.
No installed circuit breakers were examined per the requirements of action Item 1. Therefore, action Item 2 is not applicable to those circuit breakers identified during our evaluation of stored spares.
Per action Item 4, installed circuit breakers that could not be traced to the circuit breaker manufacturers were identified in Unit 1, which is presently in a refueling outage. As stated previously,'n analysis
)ustifying continued operation of Unit 1 will be prepared prior to startup -if the traceability of any installed circuit breakers to AEP:NRC:1083A Page 5 cannot be established. At least 50$ of the circuit breakers identified by Attachment. 3 will be replaced prior to Unit 1 startup.
As stated previously, action Item 4 is projected to be completed for Unit 2 by June 30, 1989. If this evaluation identifies installed circuit breakers that cannot be traced to the circuit breaker manufacturer, then we will prepare an analysis justifying continued operation of Unit 2 within 30 days of the completion of action Item 4.
- 3) Action Item 3 requests all addresses who identify 80 percent or more circuit breakers traceable to the circuit breaker manufacturer per action Item 1 to test the circuit breakers that are not traceable to the circuit breaker manufacturer in accordance with the test program described in Attachment 1 of NRC Bulletin No. 88-10. For Cook >>Nuclear Plant, less than 80 percent of the circuit breakers identified in action Item 1 were traced to the circuit breaker manufacturer. Therefore, action Item 3 is not applicable to Cook Nuclear Plant.
- 4) Action Item 4 requests all addressees who identify less than SO percent of the circuit breakers traceable to the circuit breaker manufacturer per action Item 1 to identify all molded-case circuit breakers purchased between August 1, 1983, and August 1, 19SS, and installed in safety-related applications. The traceability of the circuit breakers identified under this action item is requested to be verified.
A review of design change documentation, stores issue records, and job orders was performed in order to identify molded-case circuit breakers installed in Unit 1 after August 1, 1983.
Information regarding those circuit breakers that could not be traced to the circuit breaker manufacturer is submitted in Attachment 3 of this letter. We are still trying to verify the traceability of the GE circuit breakers identified by Attachment 3.
to AEP:NRC:1083A Page 6 A review of the above documentation is in progress for Unit 2. This review is projected
'o be completed by June 30, 1989. We will update Attachment 3 with Unit 2 information and submit this update by July 28, 1989.
- 5) Action Item 5 specifies the requirements for replacing installed safety-related circuit breakers that cannot be traced'o the circuit breaker manufacturer, This action item allows replacement with circuit breakers that meet the criteria of action Item 7 or circuit breakers that pass all tests in accordance with the test program described in Attachment 1 of NRC Bulletin No. 88-10. Action Item 5 further requests holders of operating licenses to replace at least one-half, or all if the total number is less than 75, of these installed circuit breakers before startup from the first refueling outage beginning after March 1, 1989.
Unit 1 is presently in a refueling outage that began after March 1, 1989. We will replace at least one-half of the safety-related circuit breakers installed in Unit 1 that could not be traced to the circuit breaker manufacturer before Unit 1 startup. A total of 100 installed circuit breakers that have not been traced to the circuit breaker manufacturer were identified in Unit 1. We will replace at least 50 of these prior to Unit 1 startup. An analysis justifying continued operation, will be prepared for the remaining installed circuit breakers prior to Unit 1 startup. Of the remaining, circuit breakers, we will replace all units for which we have not verified traceability at the next refueling outage.
We have not completed identification of safety-related circuit breakers installed in Unit 2 for which traceability cannot be verified. Action Item 5 will be implemented as requested for Unit 2.
- 6) Action Item 6 requires that information generated while performing action Items 1 through 5 be documented and maintained for a period of 5 years after all action items have been completed. We will implement action Item 6 as requested.
to AEP:NRC:1083A Page 7
- 7) Action Item 7 specifies procurement requirements for molded-case circuit breakers installed in safety-related applications after August 1, 1988. Several molded-case circuit breakers that do not meet the criteria of action Item 7 (i,e., could not be traced to the circuit breaker manufacturer) were installed at Cook Nuclear Plant after August 1, 1988. The time delay between August 1, 1988, and receipt of NRC Bulletin No. 88-10 and the time required for us to complete action Item 1 of the bulletin created the situation where circuit breakers without verifiable traceability wer'e installed in safety-related applications after August 1, 1988.
The molded-case circuit breakers installed in Unit 1 safety-related applications after August 1, 1988, that could not be traced to the circuit breaker manufacturer were identified during the evaluation performed under action Item 4. These circuit breakers will be replaced before- Unit 1 startup.
Any molded-case circuit breakers installed in Unit 2 safety-related applications after August 1, 1988, that cannot be traced to the circuit breaker manufacturer will be identified
'uring the action Item 4 evaluation for Unit 2 ~
Action Items 2, 5 and 6 will be applied to these circuit breakers as outlined in the above responses.
Except for those cases described above, steps have been initiated to ensure that the criteria of action Item 7 will be met for future installations of molded-case circuit breakers in safety-related applications.
- 2) All holders of operating licenses are required to submit a report that summarizes available results of tests conducted in accordance with Items 3 and 5 of the acti'ons requested within 30 days after startup from the first and second refueling outages beginning after March 1, 1989.
For circuit breakers that pass these tests, the only information required is the number, manufacturer, model number, and to the extent .possible the procurement chain of circuit breakers tested {summary report format is acceptable). For circuit breakers that fail these test(s), these reports should indicate the test(s) and the values of test parameter(s) at which the failure(s)
~ <<w\ikssek.. ~
~ to AEP:NRC:1083A Page 8 occurred, as well as the corresponding manufacturer, model number, and to the extent possible, the procurement chain.
~Res ense We do not plan to perform tests conducted in accordance with Items 3 and 5 of the actions requested. These circuit breakers will not be installed at Cook Nuclear Plant.
ATTACHMENT 2 TO AEP:NRC:1083A - Information on stored, spare, molded-case circuit breakers that Page 1 could not be traced to the circuit breaker manufacturer in Item 1 of the actions requested.
Manufacturer Model Number Number Procurement Source s F83015 *Construction Store Room Westinghouse Elec. Corp., Beaver, PA;
+WESCO, Ft. Wayne, IN Westinghouse Elec. Corp., St. Louis, MO FB3020 *Contruction Store Room FB3030 *Construction Store Room Westinghouse Elec. Corp., Beaver, PA FB3050 14 *Construction Store Room Westinghouse Elec. Corp., Duncan, SC;
- WESCO, Monroeville, PA FB3070 19 *Construction Store Room
+WESCO, Columbus, OH
+WESCO, Monroeville, PA FB3090 10 *Construction Store Room
- WESCO, Hammand, IN; Westinghouse Elec. Corp., Duncan, SC 0
'B3100>
Westinghouse Elec. Corp., Duncan, SC;
+WESCO, Ft. Wayne, IN FB3125 *Construction Store Room
+WESCO, Monroeville, PA GE TEB(20 amp) 50 **Fazwell 6 Hendricks, Milford, OH e
Page 2 Manufacturer Model Number Number Procurement Source s GE TEB(50 amp) **Farwell 6 Hendricks, Milford, OH GE THED(60 amp) Solidstate Controls, Columbus, OH
- GESCO, Columbus, OH GE TED(80 amp) Same as above GE TFK(125 amp) Same as above ITE P1515 Comsip, Inc., Whittier, CA
- Nunn-Royal Elec., Carson, CA ITE FJ3B225 *Exide Industrial Battery, Richmond, KY ITE JL2F400 *Exide Industrial Battery, Richmond, KY Square D FAL240501021 Power Conversion Products Inc., Crystal Lake, IL
- Interstate Electric, Crystal Lake, IL Square D QOU325 Same as above TOTAL 159
- Verifiable traceability was not obtained.
- Verifiable traceability is still being pursued.
ATTACHMENT 3 TO AEP:NRC:1083A - Information on molded-case circuit breakers that could not be traced to the circuit breaker Page 1 manufacturer in Item 4 of the actions requested.
Total Manufacturer Model Number Number Procurement Source s ~uantit ~ga tea BA1020 2., *Construction Store Room; Heat trace-train A (boric acid)
- WESCO: Ft. Wayne, IN; Heat trace-train B (boric acid)
Monroeville, PA; Columbus, OH FB3015 26 Same as above Spare Heater (AB diesel generator lube oil filter)
Shutoff valve (pressurizer relief valve)
Starter (control rod hoist)
Shutoff valve-(boron injection)
Shutoff valve-(west containment spray pump)
Suction valve (refueling water storage tank pump)
~
Outlet valve (volume control tank)'hutoff valve (boron injeciton tank outlet)
I Valve (charging pumps to regenerative heat exchanger)
Page 2 Total e Manufacturer Model Number Number Procurement Source s guuant it ~Sstem Suction valve (refueling water storage tank)
Valve (essential service water to containment spray heat exchanger)
Valve (essential service water from containment spray heat exchanger)
Valve (essential service water to component cooling heat exchanger)
Valve (essential service water from component cooling heat exchanger)
Valve (motor driven auxiliary feedwater to steam generator Cl)
Valve (motor driven auxiliary feedwater to steam generator ¹4)
Valve (component cooling to hydrogen skimmer vent) ~
(component cooling
'alve skimmer vent) from'ydrogen Heater (containment quad 4 instrument room ventilation unit)
Air handler (ice condenser ventilation)
FB3030 Same as above Auxiliary charcoal filter (lower containment ventilation)
Page 3 Total Manufacturer Model Number Number Procurement Source s uantit ~Sstem Oil lift pump (C3 reactor coolant pump thrust bearing)
Spare FB3040 Same as above 'entilation unit (containment quad 3 instrument room)
Crane (containment ice condenser)
Ventilation unit (upper containment quad 4)
FB3050 Same as above Distribution panel (boric acid heat trace)
Transfer pump (south primary water)
Supply unit (auxiliary building ventilation)
Inverter (channel IV control room instrumentation)
FB3070 Same as above Exhaust fan (control rod drive mechanism ventilation)
Heater (upper containment quad 3 ventilation)
Exhaust fane(lower containment quad 1 ventilation)
Exhaust fan (lower containment quad- 2 ventilation)
Page 4 Total Manufacturer . Model Number Number Procurement Source s ~uentit ~Secern Exhaust fan B (lower containment quad 4 ventilation)
Exhaust fan A (lower containment quad 4 ventilation)
FB3100 Same as above Distribution panel (local shutdown) 600 volt ac motor control center (technical support center)
FB3125 Same as above Exhaust fan (auxiliary building ventilation)
FB3150 Same as above Pressurizer heaters (¹43, ¹73,
¹74)
Ventilation fan (containment hydrogen skimmer)
GE THED(60 amp) Solidstate Controls, Inverters (control room Worthington, OH instrumentation distribution)
~GESCO, Columbus, OH GE TED(80 amp) Same as above Same as above GE TFK(125 amp) Same as above Same as above GE TEB(20 amp) 30 **Farwell & Hendricks, Recorders refueling water storage Milford, OH tank level (and reactor coolant temperature and pressure)
Recorder (reactor coolant system wide range temperature) 28 Spares
Page 5 Total Manufacturer Model Number Number Procurement Source s guuantit r ~Sstem 'E TEB(50 amp) **Farwell & Hendricks, 6 Spares Milford, OH TOTAL 100
+Verifiable traceability was not obtained
~Verifiable traceability is still being pursued.