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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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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INDIANA & MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHlO 43216 December 18, 1986 AEP:NRC:1009 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NRC REPORT NOS. 50-315/86029 and 50-316/86029 NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY Mr. James M. Taylor, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Taylor:
This letter responds to the NRC Region III letter dated November 18, 1986, which refers to the subject Inspection Report of the special safety inspection conducted by the Region III staff at the Donald C. Cook Nuclear Plant during the period July 14 through August 11, 1986. This inspection reviewed the circumstances associated with the inoperability of two of four power-range excore nuclear instruments during a Unit 2 reactor start-up. The Notice of Violation and Proposed Imposition of Civil Penalty transmitted by the Region III letter proposed a civil penalty of $25,000 collectively for Violations I.A.1, I.A.2 and I.B. The Notice indicates that the $25,000 represents reduction of the base civil penalty by one-half because of our unusually prompt and extensive corrective actions. Violation II was not assessed a civil penalty.
Our response to these violations is presented in the attachment to this letter. In addition, we have enclosed a check in the amount of $25,000 in full payment of the imposed civil penalty.
Very truly your ,
8612240264 861218 PDR ADOCK 05000315 O PDR . P. lexich Vice President 31 Attachment cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman J. G. Keppler - Region III 1\ /E: !Y l 1
Jamen M. Tcyler AEP:NRC:1009 STATE OF OHIO COUNTY OF FRANKLIN M. P. Alexich, being duly sworn, deposes and says that he is the Vice President of Licensee Indiana & Michigan Electric Company; that he has read the foregoing response to NRC Inspection Report 50-315/86029, 50-316/86029 and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
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Subscribed and sworn to before me this /# day of it/vrebt , 19 96.
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RUTH A. OHLINGER
- 01ARY PUBut SIAlt gF OHIO NCOMMISSION EAflRES.VM.1952~.
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Attachment to AEP:NRC:1009 NRC Inspection Report 50-315/86029; 50-316/86029 i
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AEP:NRC:1009 Attachm:nt Pags 1 NRC Violation No. I A. " Unit 2 Technical Specification 6.8.1 requires written procedures be implemented covering applicable procedures recommended in Appendix A of Regulatory Guide 1.33, November 1972, which includes administrative procedures cover - 3 procedural adherence.
Administrative Procedure PMI-20: 0, Plant Manager and Department Head Instructions, Procedures and Associated Indexes requires that instructions and procedures shall be adhered to by all plant personnel.
- 1. Administrative Procedure PMI-2140, Temporary Modifications, Revision 6 (in effect until July 1, 1986) required the use of Attachment 1, Lif ted Wire Form, unless wires were lifted one at a time and immediately relanded, as in troubleshooting.
Contrary to the above, on or about May 31, 1986, while performing Job Order No. 54516, two wires were lifted at the same time and crossed on power range nuclear instrument channel No. NI-41 without the use of the ' Lifted Wire Form.'
- 2. Administrative Procedure PMI-7030, Condition Reports and Plant Reporting, Paragraphs 5.2.b and 5.2.c, requires that a Condition Report must be submitted when print discrepancies are noted or when a suspected failure exists that could leave safety-related equipment inoperable or in a degraded mode.
Contrary to the above, on or about May 31, 1986, a Condition Report was not submitted when print discrepancies involving the wiring of power range nuclear instrument channels No. NI-41 and NI-42 w'ere noted. The discrepancies had the potential to render the equipment inoperable or degraded.
B. Unit 2 Technical Specification 2.2.1 requires that reactor trip system setpoints shall be consistent with the Trip Setpoint values of Table 2.2-1 when the respective instrumentation is required OPERABLE as shown in Table 3.3-1. Table 2.2-1 specifies two separate allowable power range neutron flux trip setpoints equal to or less than 26% and 110% of RATED THERMAL POWER. With a setpoint less conservative than that specified, the required ACTION is to declare the channel inoperable and apply the ACTION requirements of Technical Specification 3.3.1.1.
Technical Specification 3.3.1.1 requires that the reactor trip system instrumentation channels be OPERABLE as shown in Table 3.3-1.
For power range neutron flux instrumentation, Table 3.3-1 requires, while in MODES 1 or 2, or whenever the reactor trip system breakers are closed and the control rod drive system is capable of rod withdrawal, that with less than four channels OPERABLE, the inoperable channel must be placed in the tripped condition within one hour and the minimum channels OPERABLE requirement of three channels must be met.
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- - AEP:NRC:1007 Attachmant Psgs 2 1
Technical Specification 3.0.3 specifies that when a Limiting Condition-for Operation is not met, except as provided in the associated ACTION requirements, action shall be initiated within one hour to place the unit'in a Mode in which the specification does
.not apply.
-Contrary to the above, from 4:22 p.m. on July 6,1986, until 1:57 a.m. on July 7, 1986, and from 6:09 a.m. on July 7, 1986, until 4:14 a.m. on July 11, 1986, while in Modes 1 or 2 or with the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal, two of the four power range nuclear instrument channels, No. NI-41 and NI-42, were rendered inoperable and actions were not initiated within one hour to place the unit in a mode where the specification did not apply."
Resoonse to NRC Violation I
- Admission or Denial of the Alleged Violation Indiana & Michigan Electric Company admits to the violation. However, as described below, it should be noted that NI-42 was fulfilling its safety
- . function during the time it was connected to the reactivity computer.
i Reasons for the Violation During the period of May 20 through May 31, 1986, while Unit 2 was in Mode 5 (Cold Shutdown) following refueling, Instrumentation and Control (I&C) personnel were dressing cables (EIIS/CBL) and inspecting cable connections in the nuclear instrumentation (NI) cabinet drawers (EIIS/CHA). The I&C personnel first dressed the cables one at a time starting with the Channel I source range and intermediate range. At power range NI Channel I (N-41) all 3
the cables were first disconnected, to permit untangling. A cabinet wiring diagram (92018-14/NIS Protection Channel I CAB NIS I) was marked showing the
! "as-found" configuration cf the cables. The cables for N-41 were reconnected after untangling to what the technician thought was the "as-found"
! configuration. During the dressing / inspection, it was decided by I&C
[ personnel that some enhancements to labeling'were desirable. Plant l information tags (not permanent labels) were applied.
After completing Channel I NIS, I&C continued on to Channel II. Upon completing the Channel II source range drawer cables, they proceeded to the
- Channel II intermediate range drawer. After inspecting the intermediate range
- drawer, the involved I&C supervisory personnel decided that the best method of l straightening out the disarrayed cables would be to first disconnect all the
, intermediate and power range drawer cables and dress the cables from the ,
! bottom drawer (power range) up. As the cables were disconnected, a cabinet j wiring diagram (2-92019-17/NIS Protection Channel II CAB NIS II) was marked up i
designating the "as-found" configuration of the cables.
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AEP:NRC:1009 Attachment Pagt 3 Information tags were filled out for each of the cables designating their function (e.g., Detector A, high voltage, spare),. based on the cabinet wiring diagram, and placed on the cables. All the old labeling was then removed. It was at this time that the I&C personnel found that the old labels for " Detector A signal" and "high voltage" cables did not match'the cabinet wiring diagram /new information tags for power range Channel II (N-42), and there was a discrepancy between the cabinet wiring diagram and the wiring diagram 2-97005 (Reactor Nuclear Instrumentation System). To verify the correct cable configuration, the cables were physically verified at the containment penetration and at the channel drawer. Upon determining that the cabinet wiring diagram was in error, the I&C personnel filled out lifted lead tags explaining the situation (i.e., that the cables were not connected as shown on the cabinet wiring diagram) and the lifted lead tags were hung on the cables. The information tags, which incorrectly identified the cables, were not removed.
k Based on findings concerning N-42, the I&C personnel decided to recheck N-41 against design drawings. They found that the cables, which they thought had been landed to the "as-found" configuration, were also at variance with
, the drawings. To document this, they placed lifted lead tags as had been done on N-42. No cables were moved at this time; I&C personnel believed the cables were connected as they had been prior to the outage. The inspection and redressing of the nuclear instrumentation cables was completed on May 31.
On July 6 at 1532 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.82926e-4 months <br /> while ' Unit 2 was in Mode 3 (Hot Standby), N-42 was connected to the reactivity computer by I&C personnel to conduct low-power physics testing using **12 THP 6040. PER.355, Reactivity Computer Calibration and Setup. As required by procedure, the bistables (overpower Delta T and overtemperature Delta T reactor trips and runback) were tripped and the fuses (EIIS/FU) pulled, which placed N-42 in a tripped configuration. On July 7 at 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br /> Unit 2 entered Mode 2. N-41 remained inoperable at this time due to the wiring error noted above. N-43 and N-44 (Channels III and IV, respectively) were operable. In this configuration the Technical Specification-required protection redundancy existed.
On July 10 at 0402 hours0.00465 days <br />0.112 hours <br />6.646825e-4 weeks <br />1.52961e-4 months <br />, N-42 was disconnected from the reactivity j
computer using **12 THP 6040.PER.355. The I&C personnel restoring N-42 connected the " Detector A signal" and "high voltage" cables using the identification written on the information tags (incorrect) rather than the lifted lead tags (correct). The fuses for N-42 were replaced and the bistables restored to normal. N-42 was declared operable though in fact it was inoperable due to the " Detector A signal" and "high voltage" cables being incorrectly interchanged. The inoperability of both detectors was not noted at the time, since they were not providing an output signal due to the low reactor power level which existed at the time. Inoperability could only be determined at higher powers, when the differences between the inoperable and operable detectors could be noted.
I At 2311 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.793355e-4 months <br /> on July 10 permission was granted to enter Mode 1.
i During the power increase to Mode 1, it was noted by Operations personnel that N-41 and N-42 indication was lagging N-43 (Channel III) and N-44 (Channel IV) on the 0-120 percent full power meter. Based on past experience, this difference at low power levels was not deemed cause for concern as it was not 1
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AEP:NRC:1009 Attachm:nt Page 4 uncommon for the power range channels to require adjustment after refueling.
The channel currents are predicted quantities and are usually adjusted at higher power levels. Mode 1 was reached at 0038 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> on July 11.
Reactor power was increased to between 8 percent and 9 percent in preparation for turbine roll. At approximately 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> it was clearly evident to the control room operators that a situation requiring investigation existed in that N-41 and N-42 were not following the power increase. N-41 and N-42 were indicating approximately half the power indicated on N-43 and N-44, and the Delta-flux indication was slightly positive on the two meters that received input from N-41 and N-42. It was not noted at that time that the lower Detector "B" current for both channels was reading zero. From approximately 0110 to 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> the problem was discussed between control room, Operations staff, plant management, I&C Section and Nuclear Section personnel. Neither N-41 nor N-42 were declared inoperable, since the cause for the indicated deviation was not known at this time.
At 0208 hours0.00241 days <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br /> on July 11, I&C personnel began troubleshooting N-41 using
- 2 THP 6030 IMP.231, Power Range Nuclear Instrumentation Calibration.
Because Detector "B" current was indicating 0 amps (later determined to be a result of the interchanged cables for Detector A and high voltage), the I&C personnel checked and verified that the Detector "B" cables were properly connected for both N-41 and N-42. I&C contacted the Nuclear Section to determine if the channels were responding properly to the calculated / predicted quantities for the new core. The possibility of interchanged cables was discussed with Nuclear Section personnel; however, on checking the cable configuration on the N-41 drawer, the I6C personnel found the cables connected as identified on the lifted lead tags and believed the configuration was correct. At approximately 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />, while troubleshooting N-41, the I&C personnel decided to check the cable connections on N-42. The I&C person was the rame individual who had placed the lifted lead tags on the cables in May.
He immediately recognized that the N-42 " Detector A signal" and the "high voltage" cables were interchanged (reconnected following use for the reactivity computer as identified on the information tags rather than the lifted lead tags).
At this time, the two I&C personnel who had restored N-42, after disconnecting the reactivity computer, wera in the control room. When asked why they had connected it in reverse of the lifted lead tags, they stated they had used the information tags thinking that the lifted lead tags were attached because N-42 had been connected to the reactivity computer. The I&C personnel then stopped troubleshooting procedures on N-41 per **2 THP 6030 IMP.231. At 0407 hours0.00471 days <br />0.113 hours <br />6.729497e-4 weeks <br />1.548635e-4 months <br />, I6C personnel began troubleshooting N-42 (which were now suspected of having the " Detector A" and "high voltage" cables interchanged) per **2 THP 6030 IMP.231. N-42 was placed in a tripped configuration by pulling the instrument power fuses, and the cables were interchanged to the correct configuration. N-42 was restored to operable status at 0414 hours0.00479 days <br />0.115 hours <br />6.845238e-4 weeks <br />1.57527e-4 months <br />, and it was verified that N-42 was now indicating the same as N-43 and N-44.
Since symptoms for N-41 and N-42 had been the same, the I&C personnel correctly surmised that the N-41 cables were also interchanged and that the lifted lead tags were, in fact, wrong. N-41 was then placed in a tripped condition by removal of the instrument power fuses, and the cables were
4 AEP:NRC:1009 Attach::nt Page 5 reconnected in the correct configuration. It was then verified that N-41 indication was consistent with the other three channels. N-41 was restored to operable status at 0422 on July 11.
Neither N-42 nor N-41 were declared inoperable by the I&C personnel when
/ the cables were found interchanged. Upon being questioned by the Shift Technical Advisor (STA) as to whether the condition had been reported to plant management, the I6C person said he had reported the NI cabinet wiring drawing error in May via a Condition Report and did not feel an additional report was necessary. However, during the investigation, no documentation of the report could be found.
On July 12 at approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, the event was discussed with plant management and although no conclusion was reached on the operability /inoperability of the power range NIS, it was decided that a report to document the fact of the interchanged cables and initiate further investigation should be written. A report was written by an I&C technician at approximately 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, which reported the circumstances of the interchanged cables but made no determination on the operability of the channels in question. The report was received by the STA on shift at approximately 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />. The STA reviewed the report during the midnight shift on July 13.
Since the NIS had not been declared inoperable, it was not realized that the 4-hour reporting requirement per 10 CFR 50.72 applied. However, a follow-up review involving plant management revealed that the detectors should have been declared inoperable and thus a report was necessary.
The NRC resident inspector was informed, and at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on July 14, 1986 the Shift Supervisor made the required notification to NRC Operations Center via the Emergency Notification System phone.
Based on the above, it is our belief that the violation was the result of a personnel error by an I6C supervisor who failed to implement and follow procedures. This resulted in an impairment of administrative control systems designed to prevent occurrences of this nature, and the subsequent operation of the plant with two power range nuclear instrumentation channels inoperable.
Corrective Steps That Have Been Taken and the Results Achieved The incorrect wiring on the two power range NI channels was discovered on July 11, 1986. The wiring configuration was corrected and the two NI channels (N-41 and N-42) were declared operable on that same day. On July 14, 1986, following investigation of what had transpired, channel functional tests were performed on channels N 41 and N-42 to ensure that they were operating correctly.
On July 12, 1986, Condition Reports were written to document the wiring errors on NI-41 and NI-42 and the drawing error on NI-42.
Temporary Modification forms were initiated and approved for N-42 to document the configuration that did not conform to the approved drawings until the drawings were revised and issued. Information tags used to identify the NI cables were removed on July 21, 1986.
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AEP:NRC:1009 Attachaznt Pegs 6 Corrective Steos Taken to Avoid Further Violations
- 1. Operations Department power escalation procedures have been changed to alert operators in the control room to verify proper power range NI indication.
- 2. Information tags have been removed from the list of approved tags in the Plant Manager's Instruction.
- 3. A Plant Manager's Standing Order was written to control the temporary lifting and landing of leads and provide independent verification of proper system restoration.
4 Letters of Instruction were issued to the individuals directly involved in the incicent and to various sections and departments. The letters reviewed the circumstances of the event and reinforced the requirements for procedural adherence and individual responsibility.
In addition to the actions noted above, which were a direct result of the event, two other unrelated projects were finalized either during or shortly after the occurrence.
First, Revision 7 of PMI 2140 " Temporary Modifications" was issued and became effective on July 1,1986. This revision strengthens the control and review of Temporary Modifications, more clearly delineates what a Temporary Modification is and when it must be used, and clarifies the responsibilities of individuals in initiating a Temporary Modification.
Secondly, a concerted effort to review and oversee the work practices and overall performance of the I&C Section for improvement has resulted in the development of an I&C Production Control Group with responsibility for insuring that all work-related activities are properly pre-planned and technically reviewed. Also, as a result of a reorganization that took place on July 1,1986, we have taken steps to strengthen our on-site engineering support capability. This includes on-site participation by the American Electric Power Service Corporation I&C Section.
We feel that, although these two items were not a direct result of the occurrence, both provide additional positive controls to prevent a recurrence of this nature.
Date When Full Como11ance Will Be Achieved Full compliance was achieved on July 11, 1986, when the NI channels were declared operable.
NRC Violation No. II
" Unit 2 Technical Specification 6.8.1 requires written procedures be implemented covering applicable procedures recommended in Appendix A of Regulatory Guide No. 1.33, November 1972, which includes administrative procedures covering procedural adherence.
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AEP:NRC:1009 Attach: ant Page 7
- Administrative Proceiure PMI-2010, Plant Manager and Department Head Instructions, Procedures and Indexes, requires that instructions and procedures shall be adhered to by all plant personnel.
Administrative Procedure PMI-7030, Condition Reports and Plant Reporting, Paragraph 5.3, requires that the Shift Supervisor be immediately informed whenever any plant equipment is determined to be inoperable.
Contrary to the above, the Shift Supervisor was not notified on July 11, 1986 when power range nuclear instrument channels No. NI-41 and NI-42 were determined to be inoperable."
Resoonse to NRC Violation No. II Admission or Denial of the Alleged Violation Indiana & Michigan Electric Company admits to the violation.
Reasons for the Violation The violation was the result of the failure of personnel to recognize and
, declare the power range nuclear instrumentation channels inoperable when the symptoms and incorrect wiring were first discovered. (See response to Violation I.)
Once the inoperability of the channels was suspected, personnel failed to take prompt and aggressive action to make a final determination and initiate any reporting requirements.
Corrective Steps That Have Been Taken and the Results Achieved A report was written on July 12, 1986 documenting the fact that the NI cables had been interchanged. A follow-up review of the event by plant management on July 14, 1986 revealed that the NI detectors should have been declared inoperable. The NRC Resident Inspector was notified of the occurrence, and the Shift Supervisor notified the NRC Operations Center at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on July 14, 1986.
Corrective Action Which Will Be Taken to Avoid Further Violations See Response to NRC Violation I.
Date When Full Compliance Was Achieved Full compliance was achieved on July 14, 1986, when the event was determined reportable per 10 CFR 50.72 and the Shift Supervisor notified the NRC Operations Center.
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