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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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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I REQULATORY XFQRNATIQN DISTRIBUTION BY El'l'R IDB>
ACCESSION NBR: 8705050166 DQC. DATE.: 87/04/30 NOTARIZED: NO DOCKET 0 FACIL: 50-315 Donald C. Cool Nuclear Pouer Plant> Unit 1> Indiana 5 05000315 AUTH. NANE AUTHOR AFFILIATI QN ALEXICH l'l. P. Indiana Cc Nichigan Electric Co.
RECIP. NAl'lE RECIPIENT AFFILIATION Document Control Branch (Document Control'Desk)
SUBJECT:
Responds to 870420 telcon U/D Wigginton C Tinkler re 8c util 870210 request for ice condenser surveillance'interval extension for abaci)itg Cycle DISTRIBUTION CODE: AOOID TITLE: QR COPIES RECEIVED: LTR Submittal: General Distribution i ENCL / SIIE: /5 NOTES:
RECIPIENT CQPIEB RECIPIENT COPIES ID CODE/NANE LTTR ENCL ID CODE/NAl'1E LTTR ENCL PD3-3 LA 0 PD3-3 PD 5 5 llIQQINQTQN D 1 INTERNAL: ARN/DAF/LFNB 1 0 NRR/DEBT/ADE 1 NRR/DEBT/ADB 1 NRR/DOEA/TSB 1
/ILRB 1 OGC/HDS1 0 REQ FILE 01 1 EXTERNAL: EQM BRUBKEp S 1 LPDR NRC PDR 1 1 NBIC TOTAL NUl'lBER OF COPIEB REQUIRED: LTTR 18 ENCL 15
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INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. 80X 16631 COLUM8US, OHIO 43216 April 30, 1987 AEP:NRC:0967I Donald C. Cook Nuclear Plant Unit No. 1 Docket No. 50-315 License No. DPR-58 ICE CONDENSER SURVEILLANCE INTERVAL EXTENSION FOR UNIT 1 CYCLE 9 U.S. Nuclear Regulatory Commissi'on Attn: Document Control Desk Washington, D.C. 20555 Attn: H. R. Denton
Dear Mr. Denton:
This letter responds to the April 20, 1987 telephone conversation with Messrs. David Wigginton and Charles Tinkler of your staff. Mr. Tinkler asked a number of questions regarding our February 10, 1987 request (AEP:NRC:0967H) for an ice condenser surveillance interval extension for Unit 1 Cycle 9. The responses to those questions are given below.
Question 1. Were the ice weight calculations extrapolated to July 1, 1987, or July 31, 1987?
Response: The ice weight calculations were extrapolated to July 31, 1987.
Question 2. What is the date to which the surveillance interval extension is needed'?
Response: We request an extension to July 31, 1987.
Question 3. How does the most recent weighing compare with the five most recent weighings?
Response: We have compared the most recent weight losses with the four previous weight losses and also with the average of the five most recent weight losses. Twenty-five percent of the bays and seventeen percent of the row groups had ice loss significantly greater in the most recent interval than in the previous intervals, at the 958 confidence level. These larger ice losses would not be expected in the present operating cycle, since few air-handling units have been out of operation recently. This is discussed further in the response to Question 4.
8705050i66 870430 PDR ADOCK QQQ0031g PDR
AEP:NRC:0967I Question 4. What maintenance has been performed over previous weighing intervals'E Response: Although no major maintenance has been done in recent cycles, we have checked the number of air-handling units that were turned off and out of service during the most recent periods of plant operation. There are 60 air-handling units available by design. These units are frequently referred to as 30 pairs of 2 units, though each unit is independent with its own air intake, motor, and glycol chiller. The average number of units that were turned off during a particular month of operation is tabulated below.
Avg No. of Air Handling 0 eratin Period Month ear Units Turned Off 6/86 - 4/87 4/87 3 3/87 2 2/87 3 1/87 4 12/86 5 11/86 3 10/86 5 9/86 4 8/86 4 7/86 3 6/86 8 12/85 - 6/86 6/86 13 5/86 8 4/86 7 3/86 4 2/86 1 1/86 3 12/85 3 9/85 - 12/85 12/85 6 11/85 2 10/85 4 9/85 7 6/85 - 9/85 9/85 7 8/85 5 7/85 5 6/85 10 8/84 - 4/85 4/85 2 3/85 1 2/85 unavailable 1/85 1 12/84 1 11/84 1 10/84 2 9/84 3 8/84 3 8/83 - 8/84 8/84 5 7/84 5 6/84 3 5/84 3
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AEP:NRC:09671 e 4/84 4 3/84 3 2/84 1/84 3 12/83 6 11/83 4 10/83 6 9/83 3 There is some overlap in the operating periods, which results in different averages in the same month. Except for a few cases with a large number of units off, there seems to be no overt trend of fewer units off in recent cycles. The present operating cycle (6/86-4/87) seems to have fewer units off than did the previous cycle (12/85-6/86)--4 compared to 5.6. Other units that were operating may have had varying amounts of ice buildup on the air intake that reduces efficiency.
Quantification of the ice buildup or reduced efficiency was not available.
The dates of the six most recent weighings are 06/02/86 to 06/05/86 12/03/85 to 12/06/85 09/03/85 to 09/04/85 04/15/85 to 07/19/85 07/25/84 to 08/27/84 07/18/83 to 09/12/83 The dates of the refueling outages are 06/27/87 - (Scheduled)
None in 1986 04/06/85 - 11/17/85 None in 1984 07/16/83 - 10/24/83 Question 5. Has there been any maintenance or ice replenishment since the last weighing2 Response: There has been 1,
no'ajor maintenance and no ice replenishment since the last weighing. Air-handling units were discussed in response to Question 4. Ice was replenished during the refueling outages of April 6, 1985 to November 17, 1985 and July 16, 1983 to October 24,,1983. Ice is not added during ordinary surveillances, only during refueling outages.
Question 6. During the recent 'shutdown did plant personnel check to determine whether the Row 1 and Row 9 baskets were -frozen in place'P Response: During the recent shutdown (April 8, 1987 to April 20, 1987) we did not check to determine whether Row 1 and Row 9 baskets were frozen in place. Due to the short outage period it not possible to prepare to perform a T/S ice weighing without
'was unnecessarily delaying our return to power.
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Question 7. Why is it appropriate to use the average ice weight and subtract from it the upper limit of the 95% confidence interval of the average weight loss per yearV What would be the effect of using the lower 95% confidence limit of the ice weight and subtract from that the average weight loss per yearV Response: To support our request for the surveillance extension we needed to determine the expected or average ice weight loss per year at a 95% confidence level. The weight loss then is the statistical var'iable determined from "as-left" and "as-found" weighings. The weight loss is the difference between the as-left and as-found weights, normalized to a weight loss/yr. These as-left and as-found weighings were treated as paired observations for each bay. The average ice weights were treated as data. This method of paired observations is discussed in R. E. Walpole's text, Introduction to Statistics, 2nd edition, and is quite appropriate for this analysis.
We did not believe there was reason to consider any additional statistical methods such as the lower 95% confidence level of ice weight and average weight loss. Responding to the staff's request, however, we have repeated the analysis using this technique and found that the projected ice weights for each bay and row-group are greater than the T/S limit of 1220 pounds. This technique is not as conservative as the method we used originally because the standard deviation of the ice weights is much less than the standard deviation of the ice weight losses.
We have also subtracted the most, recent weight loss from the average ice weights. All ice weights projected to July 31, 1987 remained above the 1220 pound T/S limit.
Furthermore, when the most recent ice weight losses were subtracted from the lower 95% confidence limit of ice weights there were two bays and one row group below the 1220 T/S limit, but none below the 1098 weight allowed by the T/S Bases. The projected ice condenser weight is greater than the minimum required for safe operation. The total ice weight extrapolated to July 31, 1987 was always greater than 2,590,000 pounds regardless of averaging technique. This is far greater than the 2,371,450 pound minimum required by T/Ss.
The results of all these new calculations are in Attachment 1.
Question 8: Have there been any events at the plant since June 1986 such as the inadvertent opening of the lower inlet doors that would lead us to believe that the next surveillance will be different from any past surveillance or average of past surveillancesV Response: Our April 29, 1987 telephone conversation with D. C. Cook Plant ice condenser personnel indicated there have been no significant events such as door openings or defrosting that would affect melting or ice weights on the next surveillance.
Air-handling units were discussed in response to Question 3.
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AEP:NRC:0967I Based on numerous ice weight samples and calculations, we are convinced that the Unit 1 ice condenser will have more than sufficient ice mass, with proper distribution, to completely mitigate the consequences of the design-basis accident.
The calculations used to support our previous submittal (AEP:NRC:0967H) treated any ice weight gains as zero ice weight losses instead of negative weight losses. This zero weight loss keeps the average weight loss higher, and we believed, would provide a more conservative prediction of ice weight for July 31, 1987. However, the zero weight loss approach results in a small standard deviation associated with the average weight loss, and for this reason gives a less conservative prediction of ice basket weight. The standard deviation associated with treating weight gains as negative weight losses is larger and results in the more conservative calculation, though the average weight loss is smaller.
We have repeated the ice weight predictions based on the average ice basket weight and the upper 95% confidence limit average weight loss, treating the weight gains as negative weight losses. The results are tabulated in Attachment 2. Table 1 lists the June 1986 as-left average ice basket weights and the expected weights on July 31, 1987 for each bay.
All bays except Nos. 1, 7, 8, 10, and 24 are expected to have average basket weights above 1220 pounds at the lower 95% confidence level. Bays 1, 7, 8, 10, and 24 are expected to have average basket weights above 1098 pounds at the lower 95% confidence level.
Table 2 lists the June 1986 as-left average ice basket weights for each row-group required to be weighed by T/S 4.6.5.l.b.2 and the expected weights on July 31, 1987. All row-groups except Nos. 1-1, 1-2, 2-2, 4-1, 4-2, 4-3, and 9-3 are expected to have average basket weights above 1220 pounds at the lower 95% confidence level. These anticipated lower ice weights are a result of a statistical anomaly due to some relatively large weight gains in one other surveillance period. Two of the row-groups are below 1098 pounds at the lower 95% confidence level. They are Nos. 1-2 (1048 pounds) and Nos. 4-3 (1061 pounds). We believe these weights, although conservative, would not adversely affect public health and safety since the current FSAR analysis is based on a total ice mass of 2,000,000 pounds, which corresponds to an average ice basket weight of 1029 pounds.
Table 3 lists the total ice weight expected on July 31, 1987. The ice condenser is expected to have at least 2,400,000 pounds of ice at the lower 95% confidence level on July 31, 1987. This is well above the 2,371,450 pound limit of T/S 4.6.5.1.b.2 and 2,000,000 pound limit of the FSAR analysis. The total ice weights were calculated using the predicted average bay basket weights and the predicted average row-group basket weights at the lower 958 confidence level. The weights for Rows 3, 5, and 7 were estimated as the average of the two adjacent row-groups.
It was not necessary to repeat calculations which used the most recent ice weight losses, since using a zero weight loss instead of a negative weight loss (gain) is conservative. There is no standard deviation associated with the most recent weight loss, since single observation.
it is treated as a
AEP:NRC:0967I This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M. . Alexi h Vice President cm Attachment cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman A. B. Davis - Region III Administrator to AEP:NRC:0967I Ice Weight Tables
Attachment 1 to AE .. C:0967I Page 1 I
TABLE 1 Projected Ice Weights per Basket by Bay Based on Lower 95% Confidence Level on Basket Weight
~Ba P 1 1361 46.0 1311 2 1436 21, 1434 3 1439 3.6 1435
- 4. 1413 28.5 1382 5 1346 41.5 1301 6 1345 28.8 1314 7 1332 67.6 1259 8 1380 51.3 1324 9 1382 54.9 1322 10 1345 44.5 1297 11 1410 16.1 1392 12 1363 37.5 1322 13 1391 35.5 1352 14 1389 33.0 1353 15 1398 21.9 1375 16 1388 49.2 1334 17 1422 43.9 1375 18 1420 23.1 1395 19 1408 8.0 1400 20 1377 26.3 1348 21 1387 42.6 1340 22 1410 36.5 1371 23 1435 32.9 1400 24 1388 116.2 1263 Projected Total Ice Weight 2,624,300 A - Average ice weight per basket (lbs) at the lower 95% confidence level.
As-left June 1986.
d Average ice weight loss per basket per year (lbs/yr) over the last 5 surveillances.
P Projected ice weight per basket (lbs) on July 31, 1987.
P A-d(13/12).
Attachment 1 to AE . RC: 09 67 I TABLE 2 Projected Ice Weights Per Basket by Row- Group Based on Lower 9 5 % Confidence Level on Basket Weights
~Row - G o o u l-l 1309 63.4 1241 1-2 1384 81.3 1295 1-3 1501 36.2 1461 2-1 1342 30.4 1310 2-2 1410 41.6 1365 2-3 1447 37.0 1407 4-1 1340 52.0 1284 4-2 1332 41.6 1287 4-3 1367 69.7 1292 6-1 1459 20.4 1437 6-2 1480 13.5 1466 6-3 1418 30.2 1386 8-1 1426 51.4 1371 8-2 1405 49.0 1352 8-3 1417 59.6 1352 9-1 1393 35.0 1356 9-2 1454 74.4 1374 9-3 1417 106.4 1301 Projected Total Ice Weight 2,631,800*
A Average ice weight per basket (lbs) at the lower 95% confidence level.
As-left June 1986.
d Average ice weight loss per basket per year (lbs/yr) over the last 5 surveillances.
P - Projected ice weight per basket (lbs) on July 31, 1987.
P A-d(13/12).
+Averaged Row-Groups 3, 5 and 7 by 2+4, 4+6 and 8+6, respectively.
Attachment 1 to AEP: RC:0967I ~,
TABLE 3 Pr'ojected Ice Weights Per Basket by Bay Based on Most Recent Ice Weight Loss
~Ba d5 Pl P2 1 1387 1361 226 1142* 1117*
2 1480 1436 0 1480 1436 3 1483 1439 0 1483 1439 4 1471 1413 10 1461 1403 5 1407 1346 146 1248 1187*
6 1391 1345 52 1334 1288 7 1380 1332 78 1295 1247 8 1434 1380 0 1434 1380 9 1436 1382 0 1436 1382 10 1410 1345 88 1314 1249 11 1472 1410 22 1449 1387 12 1423 1363 114 1299 1239 13 1433 1391 122 1300 1258 14 1435 1389 82 1347 1301 15 1452 1398 36 1413 1359 16 1440 1388 88 1344 1292 17 1451 1422 28 1420 1389 18 1469 1420 2 1466 1417 19 1456 1408 28 1425 1377 20 1491 1377 0 1491 1377 21 1432 1387 66 1360 1315 22 1454 1410 62 1386 1342 23 1482 1435 0 1482 1435 24 1430 1388 2 1428 1386 Projected Total Ice Weight 2,692,200 2,592,200 Y Average ice weight per basket (lbs) as-left June 1986.
A - Average ice weight per basket (lbs) at the lower 95% confidence level.
As-left June 1986.
d5 - Most recent ice weight loss per basket per year (lbs/yr).
Pl Projected ice weight per basket on July 31, 1987 based on Y, Pl-Y-d5(13/12).
P2 Projected ice weight per basket on July 31, 1987 based on A, P2 A-d5(13/12).
- Below 1220 lbs. but above 1098 lbs.
to AE C:0967I TABLE 4 Projected Ice Weights Per Basket by Row-Group Based on Most Recent Ice Weight Loss
~Row - G woo d5 Pl P2 l-l 1397 1309 110 1277 1189*
1-2 1437 1384 14 1421 1368 1-3 1578 1501 0 1578 1501 2-1 1392 1342 86 1298 1248 2-2 1439 1410 50 1384 1355 2-3 1467 1447 0 1467 1447 4-] 1356 1340 22 1332 1316 4-2 1352 1332 98 1245 1225 4-3 1391 1367 0 1391 1367 6-1 1469 1459 48 1417 1407 6-2 1502 1480 30 1469 1447 6-3 1445 1418 36 1406 1379 8-1 1451 1426 60 1386 1361 8-2 1430 1405 112 1308 1283 8-3 1441 1417 34 1404 1380 9-1 1447 1393 96 1343 1289 9-2 1484 1454 50 1429 1399 9-3 1450 1417 16 1532 1399 2,690,700 2,630,700 Projected Total Ice Weight Y - Average ice weight per basket (lbs) as-left June 1986.
A Average ice weight per basket (lbs) at the lower 95% confidence level.
As-left June 1986.
d5 Most recent ice weight loss per basket per year (lbs/yr).'l Projected ice weight per basket on July 31, 1987 based on Y, Pl Y-(j5(13/12).
P2 Projected ice weight per basket on July 31, 1987 based on A, P2 A-d5(13/12).
~Below 1220 lbs. but above 1098 lbs.
~~Averaged Row-Groups 3, 5 and 7 by 2+4, 4+6 and 8+6, respectively.
Attachment 2 to AEP:NRC:0967I Ice Weight Tables Weight Gains Treated as Negative Losses to AEP: RC:0967I Page 1 TABLE 1 Average Ice Weights per Basket by Bay Expected Average Ice Weight/
Ice Weight/ Expected Basket at Basket Ice Weight/ Lower 95%
As Left Basket Conf. Level June 1986 July 1987 July 1987
~Bs No . ~lbs. ~lbs . ~lbs .
1 1387 1435 1170 2 1480 1529 1477 3 1483 1531 1440 4 1471 1521 1332 5 1407 1437 1244 6 1391 1400 1267 7 1380 1372 1108 8 1434 1462 1185 9 1436 1441 1232 10 1410 1457 ll 12 1472 1490 1159 1415 1423 1451 1273 13 1433 1457 1280 14 1435 1453 1284 15 1452 1491 1303 16 1440 1431 1267 17 1451 1460 1259 18 1469 1515 1293 19 1456 1480 1398 20 1491 1541 1355 21 1432 1434 1283 22 1454 1460 1317 23 1482 1522 1221 24 1430" 1313 1129
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Attachment 2 to AEP: RC:0967I Page 2 TABLE 2 Expected Average Ice Weights per Basket by Row-Group Average Ice Weight/
Ice Weight/ Expected Basket at Basket Ice Weight/ Lower 95%
As Left Basket Conf. Level Row No. June 1986 July 1987 July 1987
~Gs su Ns . ~lbs . ~lb s ~lbs .
1-1 1397 1419 1148 1-2 1437 1474 1048 1-3 1578 1666 1357 2-1 1392 1426 1272 2-2 1439 1517 1178 2-3 1467 1501 1271 4-1 1356 1385 1102 4-2 1353 1399 1183 4-3 1391 1426 1061 6-1 1469 1479 1374 6-2 1502 1517 1448 6-3 1446 1427 1358 8-1 1451 1440 1288 8-2 1430 1396 1284 8-3 1441 1389 1259 9-1 1447 1431 1341 9-2 1484 1450 1255 9-3 1450 1339 1161
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Attachment 2 to AE : RC:09671 Page 3 TABLE 3 Total Ice Weight Expected on July 31, 1987 Based on Average Ice Basket Weights Based on Average at the Lower 95%
Ice Basket Wei hts ConEidence Level
~B~Ba ~B~Ba B Row-Grou 2,841,800 2,811,500 2,480,100 2,422,900
DISTRIBUTION:
+Docket- Files PKreutzer
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DWigginton April 29, 1987 PDIII-3 r/f DOCKET NO(S). 50-315/316 Mr. John Dolan, Vice President Indiana. and Michigan Electric Company c/o American Electric Power Service Corporation 1 Riverside Plaza Columbus, OH 43216
SUBJECT:
DONALD C. COOK NUCLEAR PLANTS The following documents concerning our review of the subject facility are transmitted for your information.
Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No. dated Environmental Assessment and Finding of No Significant Impact, dated Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License, dated Q Bi-Weekly Notice; Applications and Amendments to Operating Licenses Involving No Significant Hazards Considerations, dated Apr 22~8~ [see page(s) 3 Exemption, dated Construction Permit No. CPPR- , Amendment No. dated Facility Operating License No. , Amendment No. dated Order Extending Construction Completion Date, dated Monthly Operating Report for transmitted by letter dated
+ Annual/Semi-Annual Report-transmitted by letter dated Office of Nuclear Reactor Regulation Encl osures:
As stated cc: See Next Page OFFICE)
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,SURNAME/
DATE P 4/g.g/87-
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NRC FORM 3I8 IIO/80)NRCM 0240 OFFICiAL RECORD COPY
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Mr. John Dolan Donald C. Cook Nuclear Plant Indiana and Michigan Electric Company CC:
Mr. M. P. Alexich The Honorable John E. Grotberg Vice President United States House of Representatives Nuclear Operations Washington, DC 20515 American Electric Power Service Corporation 1 Riverside Plaza Columbus, Ohio Regional Administrator, Region III 43215 U.S. Nuclear Regulatory Commission 799 Roosevelt Road Attorney General Glen Ellyn, Illinois 60137 Department of Attorney General 525 West Ottawa Street J. Feinstein Lansing, Michigan 48913 American Electric Power Service Corporation Township Supervisor 1 Riverside Plaza Lake Township Hall Columbus, Ohio 43216 Post Office Box 818 Bridgeman, Michigan 49106 W. G. Smith, Jr., Plant Manager Donald C. Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charno ff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mayor, City of Bridgeman Post Office Box 366 Bridgeman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan .48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909