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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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 IIt MICHIGAN ELECTRIC COMPANY P.O.BOX 18 BOWLINO GREEN STATION NEW YORK, H.Y.10004 January 18, 1982 AEP:NRC:0055E Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 ENVIRONMENTAL TECHNICAL SPECIFICATIONS Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 g)C RECEÃ<O JAN3 51982~g muc mapr~ICIER N4+++%C
Dear Mr.Denton:
This letter responds to a request for information from your Staff to provide additional justification for the deletion of the requirement to perform Erosion and Scour Bed studies from the proposed revision to the Donald C..Cook Nuclear Plant Environmental Technical Specifications, submitted in our letter No.AEP:NRC:0055C, dated November 4, 1981.Attachment 1 to this letter provides the basis for our request to delete these requirements.
Attachment 2 identifies information pertinent to the reports that contain studies performed as part of our current surveillance program and is submitted as an annotated bibliography for reference purposes.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, R.F.Hering Vice President RFH/sg cc: Attached 8201260381 820118 PDR ADOCK 05000315 p PDR
!r cc: John E.Dolan R.S.Hunter W.G.Smith-Bridgman R.C.Callen G.Charnoff Joe Williams, Jr.NRC Region III Resident Inspector-Bridgman ATTACR1ENT 1 to AEP:NRC:0055E Erosion and Scour Studies in Lake (1ichigan Near the Donald C.Cook Nuclear Plant The Appendix B, Environmental Technical Specifications, Sections 4.1.1.3, Erosion and 4.1.1.4, Scour Studies have been part of the annual studies by the University of Michigan for 12 years.A brief summary of the studies is presented below to demonstrate that the Objectives have been achieved and that the Bases for the studies have been satisfied.
The erosion study objective was to determine the effect of the Plant's circulating water, rip-rap scour bed, and shore pi lings on the erosional and depositional processes affecting the stability of beaches in the vicinity of the site.The basis of the beach erosion monitoring program was to verify the contention that ice building mechanisms operate to repair any ice melt caused by the thermal plume.Studies were conducted by photographing the beach area from the air and from the ground.Pictures were taken during seasons when ice was present and when the ice was absent.Photographs taken from the air during non-ice conditions were compared from year-to-year to determine if the beaches north and south of the plant were stable, in other words, that sand erosion and accumulation rates were equal and unaltered by the construction and operation of Cook Nuclear Plant.Photographs of the ice accumulation and destruction were taken and studied over the.fall and winter ice season.Each season the photographs were studied to determine whether or not the thermal plume had melted the beach ice ridge, allowing the waves to'erode sand from the unprotected beach..The scour studies were to verify that there are no scour problems resulting from the Plant's high velocity discharge and to verify the short-term and long-term integrity of the scour bed placed around the cooling water discharge structures.-
Monitoring of the scour bed performance has been completed in accordance with the environmental technical specifications.
Our studies revealed that modifications to the Unit 1 scour bedwere required and subsequently completed.
Modifications to the Unit 2 scour bed were also made and completed.
Information concerning the modifications made to the areas surrounding the discharge structure were submitted to the NRC in our letters AEP:NRC:0170 and AEP:NRC:0243, dated April 6, 1979 and September 13, 1979, respectively.
Monitoring continued on the performance of these modifications for one year after completion of the work.
Results of the studies have been reported in scientific journals in the Great Lakes Research Division of'he University of Michigan Special Reports and in the Environmental Operating Reports to the NRC.The conclusions of all the reports clearly demonstrate that the construction and operation of the Cook Nuclear Plant has not caused a significant change in the beach configuration near the Plant, the thermal plume does not cause significant shore ice melting and subsequent beach erosion, and the high velocity jet discharges do not cause scouring of the Lake bottom.'uture modifications to the scour beds resulting from any future studies performed by the licensee ot requested by the appropriate federal or state agency will be, submitted for approval to said agencies having jurisdiction over this work.The appropriate federal agency is the United States Corps of Engineers under Section 10, Rivers and Harbors (RSH)Act, 1899, and Section 404, Federal Mater.Pollution Control Act (FMPCA), 1972.The appropriate state agency is the State of Michigan, Department of Natural Resources under Act 346, P.A.1972, and Act 247, P.A.1955.
Attachment 2 to AEP:NRC:0055E NRC Submittal Source Document List Annotated Bibliography'non.
1975.Environmental Operating Report.October 25 through December 31, 1974.Donald C.Cook Nuclear Plant Unit 1.Indiana 8 Michigan Po>ver Company.15 pp.+appendices.
Aerial surveys were made monthly of ten miles of beach, north and south of the plant.All erosion observed was due to natural processes.
Three one-foot interval contour maps of the Lake Michigan shoreline were made during 1974 and none of these maps showed any unusual erosion patterns.Lake bottom profiles by sounding were made during 1974 on a grid 3,000 ft.x 13,000 ft.The bottom profile showed no scour due to p'lant operation.
Semiannual soundings of the intake and discharge areas, which covered an area 1,400 ft.x 2.400 ft., also showed no signs of scour.Anon.1975.Environmental Operating Report, January 1 through June 30, 1975, Donald C.Cook Nuclear Plant Unit 1.Indiana 5 Michigan Power Company.27 pp.plus appendices.
Aerial photographs from one mile north of the plant to one mile south of the plant were taken monthly and the analyses of the photographs from September 1974 through March 1975 showed no appreciable changes in beach profile during this time.A map was prepared from the March 1975 photographs and compared with earlier maps.An area 2,000 ft.to 2,500 ft.1 south of the plant no longer showed the various mounds and channel-like depressions which remained after the safe harbor was removed in 1973.
Two bottom profiles were made by sounding a 3,000 ft.x 13,000 ft.grid, during April and May.These soundings indicated only minor lake bottom movement and s'tight deviations from the August'1974 soundings.
'There appeared to be normal seasonal shifting of sand bar position.Semiannual soundings of the intake and discharge scour beds showed no significant changes.'I Anon.1976.Environmental Operating Report, July 1 through December 31,'1975, Donald C.Cook Nuclear Plant, Unit 1.Indiana, 8 Michigan-Power Company.pp.+appendices.
Aerial photographic surveys of the beach north (one mile)and south (five miles)of the plant indicate that no appreciable change in the beach front since the March, 1975 survey.The lake bottom profiles determined by sounding in the 3,000 ft.x 13,000 ft.area showed some minor shifting of the bottom,'ut the overall trend was toward stabil.ization.
The more detailed sounding of the 1,400 ft.P x 2,400 ft.grid over the intake and discharge also showed only minor changes in the lake bottom.SCUBA diver observation of the scour beds near the intake and discharge structures found the rip-rap was covering the two scour-beds and the three intake pipes.Anon.1976.Environmental Operation Report, January 1, 1976 through June 30, 1976, Donald C.Cook Nuclear Plant, Unit 1.Indiana 8 Michigan Power Company.24 pp.+appendices.
The shoreline since the September reported in Special Research Division.aerial photographic survey also showed no changes 1975 survey.Shore ice studies of Hinter 1973-74 were Report No.55 of the University of Michigan, Great Lakes All studies showed there were no significant
'changes to the shoreline profile or lake bottom profile due to the construction and operation of the plant.Monthly soundings beginning in April, 1976, of the 3,000 x 13,000 ft.grid adjacent to the plant showed Very little change had occurred in the bottom profile since October 1975.Similar results were obtained from soundings taken on the 1,400 ft,.x 2,400 ft.grid encompassing the intake and discharge structures.
Anon.1977.Environmental Operating Report, July 1, 1976 through December 31, 1976, Donald C.Cook Nuclear Plant, Unit 1;Indiana 5 Nichigan Power Company.25 pp.+appendices.
Aerial photographs of the shoreline indicated the beaches were stable and not eroding.Bottom profile studies within the'3,000 ft.x 13,000 ft.grid were conducted monthly from April through October, however, weather conditions did not allow soundings after August.No soundings were taken within the 1,400 ft.x 2,400 ft.study area.The data showed the bottom profiles to continue to stabili"e.
Anon.1978.Annual Environmental Operating Report, January 1 through December 31, 1977, Donald C.Cook Nuclear Plant, Unit l.Indiana 8 Michigan Power Company.29 pp.+appendices.
Ice studies during 1976-77 showed that the ice melt hole caused by the thermal plume.had no effect on the most lakeward ice ridge.Therefore, the beach was protected the entire winter from the erosion by open waters caused by the plant.During 1977 depth profile data were collected using electronic digital depth sounding equipment wired to a microprocessor which recorded the 4
real-time depth readings from the depth sounder and boat position supplied ,by an electronic ranging system.Data collection cruises were made on July 29, and September 22, 1977.Bathymetric maps of L'ake Michigan adjacent to the plant were prepared and presented in the annual report 1 I ,(pages 8 and 9).Comparisons of'he maps produced by the two surveys show very little change occurred between the two'surveys.
Anon.1979.Annual Environmental Operating Report, January 1 through December 31, 1978, Donald C.Cook.Nuclear Plant Units 1&2.Indiana&Michigan Power Company.'42 pp.+appendices.
Shore ice photographs taken from the ground and from the air during Winter 1977-78 were examined for the effects of the thermal plume.Unlike.the previous winter, the pl'ume did melt the third ice'ridge during Winter 1977-78.The ridge was reformed shortly after the melt and on"no occasion did the-plume melt the ice completely shoreward.
Therefore, no beach erosion occurred due to plant operation.
1 Lake bottom profiles were determined from data collected on June 20 and October 20, 1978.Depth data, boat location, and data recording were all accomplished with the same electronic depth sounding, ranging system,.and microprocessor and recorder used in the 1977 surveys.Bathymetric., maps were prepared and presented in the" report.Comparisons of the two maps show litt'le difference between the June and October surveys and no significant changes from the 1977 maps.Anon.1980..Annual Environmental Operating Report, January 1 through December 31, 1979, Donal.d C.Cook Nuclear Plant Units 1&2.Indiana&Michigan Electric Company.30 pp.+appendices.
Beach erosion was studied by photographing the ice melt caused by the f~i'if plant thermal discharge.
Aerial and ground level photographs were taken and analyzed to determine thermal plume impacts.Ice was melted from the shoreline out to the hole melted by the thermal plume.The melting.was limited to a narrow strip-immediately in front of the plant above the discharge tunnels and at no time exceeded the width of the plant property.This melting of ice was due primarily to water'leaks in the discharge tunnels and not due to two-unit operation.
The shore ice melting may have been enhanced by sa'lt used to melt ice and snow from plant parking lots which runs off the lots into the lake.Except for the area in front of the plant, the me1ted first lagoon and bared beach were protected from erosion by,ice ridges.Scour studies required by'he Technical Specifications had been'completed'n 1978, therefore, no scour studies were conducted in 1979.Anon.1981.Annual Environmental Operating Report, January I through December 31, 1980, Donald C.Cook Nuclear Plant Units I&2.Indiana 5 Michigan Electric Company.33'pp.+appendices.
Shore ice studies continued the same as previous years.Ice formation occurred in late January 1980, somewhat later than previous years.Once formed, the shore ice complex effectively protected the beach from erosion I for many miles north and south of the plant.The melting due to leaks in the discharge tunnels was not clearly demonstrated by ice melt patterns,'ut ice melting in the first ice lagoon in front of the plant was more extensive than areas north and south of the plant indicating some leakage may have occurred.Scour studies were continued in 1980.Placement of concrete scour bed pads around the Unit 1 and Unit-2 discharge structure was considered a major repair implementing the Technical Specification requirement that P 0
one full year of surveys conducted at six month intervals be completed.
The first of the two surveys was completed November 7, 1980 with the ,second one planned for April 1981.A bathymetric map was prepared and presented on page 9 of the Annual EOR.Comparisons of this map with maps from earlier surveys, July 1977, September 1977, April 1978, and October 1978, showed that there has been very little change in the bottom profiles.Ayers, J.C;, N.W.O'ara, and W.L.Yocum.1971.Benton Harbor Power Plant Limnological Studies: Part VIII.Winter Operations 1970-1971.
Special Report'No.44.Great Lakes Research Division, University of Michigan, Ann Arbor, MI.37 pp.This report is a summary of the analysis of the 1970-1971 ice study at the Cook Nuclear Plant site.Ice formation, ice accumulation, ice destruction,.and the effects of weather on these processes are extensively discussed in this report.Data during this winter were collected to compare with ice formation and destruction during the winters after Cook Nuclear Plant began operation.
A ers, J.C.and W.L.Yocum.1972.Benton Harbor Power Plant Limnological Studies: Part XI.Winter Operations 1971-1972.
Special Report No.44, Great Lakes'esearch Division, University of Michigan, Ann Arbor, MI.22 pp.This report describes the sequence of ice formation and ice destruction at Cook Nuclear Plant during the ice season of Winter 1971-1972.
Cook Nuclear Plant was not operational during the winter.These data will be useful for comparing with data collected during plant, operation.
Ice began forming in early January and lasted until early April'
Ayers, J.C., W.L.Yocum, and F.Seibe'l.1973.Benton Harbor Power Plant Limnological Studies: Part XIV.Minter Operations,1972-1973..Sp'ecial'eport No.44, Great Lakes Research Division, University.of Michigan, Ann Arbor, MI.22-pp.This report describes the.sequence of ice formation and destruction during, the ilinter of 1972-1973 near the Donald C.Cook Nuclear Plant.Ice first began to form in mid-December 1972 and disappeared in early March 1973.During January 1973 a pronounced thaw occurred.The high water levels caused severe erosion of the beach before the ice season began.Cook Nuclear Plant was, not operating during Hinter 1972-1973.
O'ara, N.H.and J.C.Ayers.1972.Stages of Shore Ice-Development.
Proc.15th Conf.Great Lakes Research Internat.Assoc.Great Lakes Res.521-535'.'ield observations and aerial and ground level photographic surveys were conducted throughout the winters of 1969-70 and 1970-71 to determine the sequence of events and processes involved in the development of the shore ice complex in fresh water.The study was carried out along the eastern Lake Michigan shoreline with the major effort concentrated on the beaches adjacent to the Donald C.Cook Nuclear Power Plant south of Benton Harbor, Michigan.The shore ice complex first produces an icefoot composed of two ridges of onshore ice, followed by the formation of a frozen lagoon of brash ice and an outer barr ier of ice.A second frozen lagoon and outer barrier-develop during the coldest part of winter.Finally a field of floe ice may fo'rm for a limited time reaching offshore to a distance of at least 17 km.The developmental stages of ice ridge and lagoon formation and destruction ar'e dynamic and changing.The'exterior ice field, second 0
outer ice barrier and lagoon are transient and apt to be carried away as the result, of wave flexing, wind and current movements.
Ice ridges and lagoons can be broken and breached by stream and wave action and reduced in height by sand-melting.
However, as 1ong as the weather and water remain sufficiently cold, the rejuvenating processes will restore ridge and lagoon continuity when exposed to the open lake.Seibel, E., C.T.Carlson, and J.M.Mareca, Jr.1975.Lake and Shore-Ice Conditions on Southeastern Lake Michigan in the Vicinity of the Donald C.Cook Nuclear Plant: Winter 1973'-74.Special Report No.55, Great Lakes Research Division, University of Michigan, Ann Arbor, MI.62 pp.This study reported on the shore ice studies near the Cook Nuclear Plant during 1973-1974.
Cook Nuclear Plant was not operating during this winter.Considerable analyses were completed on the ice study data since this was the fifth consecutive winter of the shore ice study.Some of the conclusions of this study were: 1.The stages of ice development are not controlled by any single climatic variable but instead there exists a complex inter-relationship between the two.2.E'asterly winds coupled with rising air temperatures appear to consistently produce significant deterioration of the ice complex.3.Onshore northwesterly winds coupled with increase in wind speed and a drop in air temperature initiate accretive sequences.
4.Large quantities of sediment are incorporated in the nearshore ice complex during accretionary stages and are transported landward, lakeward or alongshore at the time of breakup.5.Since the ice ridges are grounded, as the data indicate, they may serve to modify the nearshore topography in the proximity
of the offshore bars sufficiently to influence the wave regime capable of reaching and acting on the shoreline and bluff line.The exact influence of this modification of the shoreline and bluff line is not yet established.
Seibel, E., C.T.Carlson, and J.W.Hareca, Jr.1976.Ece Ridge Formation:
Probable Control by Hearshore Bars.J.Great Lakes Res.Enternat;Assoc.Great Lakes Res.2(2): 384-392.Ouring the 1973-1974 winter season a time-lapse photographic system was'used to provide a nearly continuous record of ice conditions along a, segment of the southeastern Lake Michigan shoreline.
By analysis of the photographs, a typical sequence of nearshore ice formation through break-up was identified.
From the record of nearshore ice formation, a three-element mechanism for the development of the nearshore ice<idges in the vicinity of the study site was formulated.
Observations reveal that large quantities of sediment are incorporated into the nearshore ice and that the nearshore ice ridges are grounded.on the nearshore bottom in the proximity of'the'offshore bars.We believe that the grounded nearshore ice ridges simultaneously modify the nearshore topography and protect the shoreline and bluffline from erosion by winter storms.The degree to which the nearshore is protected or modified has not yet been established.
S<<~tse7 Cocket File DOCKET NO(S)~: 9MGP16 Q.S.~~altHltal KotectlcA~Ac/Bagicn V QEiae mm.m axxdm:~230 Bath Dm9xxn 8xeet Chicago/Illirxds KGX
SUBJECT:
D C~~~~t/~ta y~2-~na~I~~g~c gxpmy 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 Q Notice of Consider'ation of Issuance of Facility Operating License, or Amendment to Faci1 i ty Operating Li cense, dated Q Bi-Weekly Notice;Applications and Amendments to Operating Licenses Involving No Significant Hazards Considerations, dated[see pagel's)]Exemption, dated Construction Permit No.CPPR-, Amendment No.dated Facility Operating License No., Amendment No.dated Order Extending Construction Completion Date, dated QM tlyap i Rp f~i dt 1 d d~Annual/Semi-Annual Report-transmitted by letter dated
Enclosures:
As stated Office of Nuclear Reactor Regulation See rext pry OFFICE/SURNAME/DATE P 02/>/87~~~~~~~~~~~~~~~~~~~~~~0~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~I~~~~~~~NRC FORM 318110/80)
NRCM 0240 OFFICIAL RECORD COPY I~A 4 I k~
j;~4 I'r (~;r'pril 7, 1986'I, II l',.-~'""~;;Dr's TRrsu Tr ON:, D'ocket.File 50-.316 Pl(Rb4 Rdg hDuncan D~ligginton DOCKET NO(S).50-316 U.S.Environmental Protection Agency Region V Office ATTN: EIS Coordinator 230 South
Dearborn Street Chicago,
Illinois 60604
SUBJECT:
Donald C.Cook Nuclear Plant, Unit 2-Indiana and Hichigan Electric Company The following documents concerning our review of the subject facility are transmitted for your information.
D Notice of Receipt of Application, dated D Draft/Final Environmental Statment, dated D Notice of Availability of Draft/Final Environmental Statement, dated D Safety Evaluation Report, or Supplement No., dated D Notice of Hearing on Application for Construction Permit, dated D Notice of Consideration of Issuance of Facility Operating License, dated D Monthly Notice;Applications and Amendments to Operating Licenses Involving no Significant Hazards Considerations, dated D Application and Safety Analysis Report, Volume D Amendment No.to Application/SAR dated D Construction Permit No.CPPR-D Facility Operating License No., Amendment No., Amendment No.dated , dated D Order Extending Construction Completion Date, dated ling Other (Specify)e n Re ort for December 1985
Enclosures:
As stated Office of Nuclear Reactor Regulation See next page oar rem~SURNAME%DATE%.QB/.7../06..
NRC FORM 3'r8{1i84)NRCM 0240 A" ca~~
\pir l J>>)~k I4 I~4~+g~'I II l
,',...',, Dbcket-Ji'Ve.50-316~";~p'., RWR44~R(fgŽ~
Hie 2 2]986 NDuncan DWi ggi nton CA DOCKET NO(S)50-316 U.S.Environmental Protection Agency Region Y Office ATTN: EIS Coordinator 230 Beati
Dearborn Street Chicago,
Illinois 60604
SUBJECT:
Donald C.Cook Nuclear Plant, Unit 2-Indiana and Michigan Electric Company The following documents concerning our review of the subject facility are transmitted for your information.
D Notice of Receipt of Application, dated D Draft/Final Environmental Statment, dated D Notice of Availability of Draft/Final Environmental Statement, dated D Safety Evaluation Report, or Supplement No., dated D Notice of Hearing on Application for Construction Permit, dated D Notice of Consideration of Issuance of Facility Operating License, dated D Monthly Notice;Applications and Amendments to Operating Licenses Involving no Significant Hazards Considerations, dated D Application and Safety Analysis Report, Volume D Amendment No.to Application/SAR dated D Construction Permit No.CPPR-, Amendment No.D Facility Operating License No., Amendment No.D Order Extending Construction Completion Date, dated H Other(SpeclfyJ Monthly Operating'Repol t for October 19S5 dated , dated
Enclosures:
As stated Office of Nuclear Reactor Regulation cc: See next page PNRP4 PWR HB n oa/mo (gl 3I(A OFS ICS)SURNAMS+DATE+NRC FORM 318 (1/84)NRCM 0240~~~~~
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