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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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
[Table view] |
Text
REGULATOR'l '4FORHATION DISTRIBUTION S,EM (BIDS)
ACCESSION NBR: 8<i 05220199 DOC. DATF: 84/05/17 NOTARI'C'ED; NO DOCKET ¹ FACIL:50-316 Donald BYNAME C ~ Cook Nuclear Power Planti Unit 2i Indiana 8 05000316 AUTH AUTHOR AFFILIATION ALEXICH<M.P. Indiana L Michigan Electric Co.
RECIP ~ NAME RECIPIENT AFFILIATION DENTONgH.Ro Office of Nuclear Reactor R'egulation~ Director
SUBJECT:
Forwards responses to questions raised by ANL at 840329 DISTRI.BUTION CODE+ A001S TITLE: OR COPIES RECK'IVEDeLTR Submittal: General Distribution
(,',~~+
meeting in support of Cycle 5 reload application.
KNCL l SIZEed K NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB1 BC 01 7 7 INTERNAL; ELD/HDS3 1 0 NRR/DE/MTEO NRR/DL DIR 1 1 NRR/DL/DRAB
~ I B 1 1 NRR/DSI/RA'B 04 1 1 RGN3 EXTERNAL: ACRS 09 6 6 LPDR 03
'
NRC PDR 02 1 NSIC 05 NTIS 1 1 L
TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 23
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INDIANA 8 MICHIGAN ELECTRIC COlttIPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 May 17, 1984 AEP:NRC:0860I Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 Cycle 5 Reload Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
We are t;ransmitting Attachments 1, 2, 3, 4 and 5 in response to a verbal question raised by your consultant, Argonne National Laborat;ory, during a meeting among the NRC st;aff, Argonne National Laboratory, Exxon Nuclear Company, and American Electric Power Service Corporation. The meeting was held on March 29, 1984 at your facility. This response is submitted in support of the Donald C. Cook Unit II Cycle 5 reload application.
This document has been prepared following corpor ate prooedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, ls4 M.P. Alexkah Ill I Vice President bus cc: John E. Dolan W.G. Smith, Jr. Bridgman R.C. Callen G. Charnoff E.R. Swanson, NRC Resident Inspector - Bridgman 8405220i99 840517 PDR ADOCK 050003th P . . . PDR
L I
Attachment 1 Question: How is the inadvertent boron dilution at shutdown while on RHR transient treated, and why is enough time to anticipate the consequences available2 Response: On July 14, 1980 a letter from F. Noon of the Westinghouse Electric Corporation to the Donald C. Cook Nuclear Plant, Plant Manager was received. The identifier for this letter is AEP-80-71. Zt is identical in content to Attachment 1 of the July 8, 1980 letter from T.M. Anderson of the Westinghouse Electric Corporation to Victor Stello of the NRC. The identifier of Mr. Anderson's letter is NS-TMA-2273. AEP-80-71 is included as Attachment 2.
The Donald C. Cook Nuclear Plant's response to the inadvertent boron dilution at shutdown while on RHR transient is based on AEP-80-71. When one of the Donald C. Cook units is in modes 4, 5 or 6 on RHR, the boron concentration is maintained so that the plant is in the region of "acceptable operation without bank withdrawal" of Figure A-1 of Appendix A to AEP-80-71. This is accomplished by increasing the required boron concentration required by the shutdown margin calculation near the beginning of cycle. The boron concentration required for N-1 rods, no xenon, Unit 2, Cycle 5 is displayed in Attachment 3. Zt is figure 4.5 of D C Coop ~U~t P ggt~Te ~gg~~t~Bggk. At boron concentr ations higher than 640 ppm, the boron concentration required for shutdown is increased above that required for Keff = 0.984. The 68 0 F curve, which is developed for use below 350 F, is calculated by the method described in Attachment 4.
The dilution rate is assumed to be 225 gpm, the value used for the Unit 1 dilution during refueling transient. See Section 14.1.5 of the FSAR. The calculation is done in a conservative manner so as to maximize the boron concentration and hence the time required to dilute to critical. lt is also conservative in that typically all rods are inserted in modes 4, 5 or 6 where as the Keff in Attachment 3 is calculated on the assumption that the most reactive rod is sticking out. This results in approximately 1$ of additional reactivity to dilute out prior to criticality which is not included in the calculation. Furthermore, the calculation is conservative in that a 100 ppm allowance is added to the shutdown margin curve. This 100 ppm must also be diluted prior to achieving critical.'t BOL (C approximately 1600 ppm) CZP, half loop when the plant is most vulnerable, 100 ppm amounts to approximately 1.2$ of additional reactivity.
A'ttachment 1 0 Page two The operator has the information available which was assumed in AEP-80-71. These are:
- 1. Source Range Neutron Flux with,
- a. High Flux at Shutdown Alarm set at half a decade above background.
- b. Use of the audible count rate indication to distinguish significant changes in flux, i..e., a doubling of the count rate.
- c. Periodic, i.e., frequent surveillance of the Source Range meters performed by the operator.
- 2. Status indication of the Chemical and Volume Control System and Reactor Makeup Water System with,
- a. Indication of boric acid and clean makeup flow rate,
- b. CVCS valve position status lights, and
- c. Reactor Makeup Water Pump "running" status light.
Procedural guidance for respond1ng to an inadvertent boron dilution incident is contained in the annunciator response for Source Range H1gh Flux at Shutdown and Emergency Boration procedures. These procedures deviate from the recommended Westinghouse response in that our preferred action for a reactivity increase is emergency boration. Use of the "refueling water sequence" is an alternate response. We believe this .is appropriate for several reasons:
- 1. 75 gpm of concentrated boric ac1d when mixed with 225 gpm of water has a boric acid concentrat1on greater than 2000 ppm.
- 2. In modes 5 and 6 the "refueling water sequence" may not be available as a boration path.
- 3. Our operators have repetitively and traditionally been tra1ned to emergency borate for any unexplained or uncontrolled reactivity increase.
To reduce the probability of this transient occurring, certain plant makeup water (PMW) valves are tagged shut prior to dra1ning the primary system to half loop. The valves 1n question supply the boric acid blender, 2-PW-263, the chemical mixing tank, 2-PW-256, and the PMW flush to the emergency boration line, 2-PW-265. These tags are lifted as part of the valve lineup for fill1ng and vent1ng the primary system. Attachment 5 1s a copy of 2-OHP 4021.002.005, "Draining the Reactor Coolant System".
Page three AEP-80<<71 indicates that operating the plant in the region of "acceptable operation without bank withdrawal" on Figure A-1 ensures that "the plant operator has fifteen minutes from the initiation of the dilution event to terminate the event before a return to critical occurs". As indicated above, we, have applied
'Figure A-1 with significant conservatism. Therefore, the transient will require 15 minutes or longer to reach criticality in the absence of operator intervention.
ATTACHMENT 2
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Westinghouse Water Reactor 00HAID t'- coop Electric Corporation Oivisions p;g;tt NsS- QI (c
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/~6 JU1y 9, 1980 AEP m<I Mr. 0. V. Shaller, Plant Manager O. C. Cook Nuclear Plan-Indiana and Michigan Power Company
"~CEtVZO P. O. 8ox 458 JULI 8 tgso Bridgman, Michigan 49106 Techrricat pept Oear Mr. Shal 1 er:
American E1ectric Power System
- 0. C. Cook Units 1 and 2 TNAOVERTENT 8GRGN OILUTION AT SHUTOOWN WHILE CN RHR On June 27, 1980, you were notified of cer.ain Westinghouse concerns and recommended ac:ions regarding the potential for an inadvertent boron diluticn event at cold or hot shutdown conditions while on the Residual Heat Removal System. This notificaticn was in accord with Westinghouse determination that these concerns constitr;te an Un-reviewed Safety question under 10CFR Part 50.59. The NRC Office of Inspection and Enforcement was also notified on June 27, 1980 that these concerns have generic applicability to Westinghouse-supplied nuclear power plants. Further clarification was made to the NRC Office of Inspection and Enforcement on June 30, 1980 that Westinghouse concerns are not applicable while the plant is greater han 5~ shutdown.
This letter is intended to formally document these concerns and to prov:de addi t onal relevant information. This letter also modifies the earlier recommended ac- ons oy a more detailed specification of applicaole plant operating conditions.
Inadver.ent boron dilution at shutdown has been generally regarded as an event which can be identified and terminated "y operator acticn.
prior to a return to cri.ical. Autcmatic protection has not been a standard feature for Westinghouse plants. Westinghouse has recently been conducting a general investigation of this potential event relat',ve to the licensin'g requirements imposed cn newe. plants not yet in operation. Tnis investigation is nct yet complete. However, it has been determined that under certain shutdown conditions and with certain ass"med dilut on rates, adequate ".'me for coeratcr action to prevent a return to critical may not be available.
~ ~
July 9, 1980 Page 2 The current westinghouse evaluations are based on plant conditions as noted below:
- 1. The Reac-or Coolant Svstam effec=ive volume is limi o he vessel and the active acrticns or the hot and cold leos <<hen on i.a. stem+ enera ar v ~
m 1 ~
Z. The plant is boratad o a shutdown margin gr a er than or equal ta I ak/k.
- 3. Uniform mixing o clean and baratad RCS water is not assumed, i.e., mixing cf:,".e clean, injec ed water and the arfacted loca is assumed but instantaneous, uni orm mixing wi h the vessel, hot legs, and cold leg volumes u"stream of the charging lines is not assumed. Tnus a "dilution front" moves hrough the cold legs, downc"mer, and lower plenum to he core volume as a single volume front. This results in subsequent decreases in shutdown margin due to dilution fronts moving thraugh the active care region with a, time constant equal ta the loop transit time <<hen an RMR (five to seven minutes).
If a return to cri ical occurs as a result of an inadvertent dilution, the following potential concerns have be n identiried:
- 1. A rapid, uncontrolled power excursion into the low and intermediate power ranges occurs, resulting in a power/flow mismatch due a the low flow (approximately 1 - 2 of nominal) provided by the RHR clumps.
- z. The'potential exists ror significant system averpressurizatian.
Pressure increases above the RHR cut of, head (approximately 500 psig) further accentuate the ef,ec:s of a power/flow mi'smatch when all RCS (RMR) flow is lost. An investigation of the adequacy of existing cold ever"ressuri at cn protec 'on systems is necessary in order ta assess the full impact oi this potential orablem.
r
- 3. The 'catential exists for limited f el damage. Tnis is not c r r ently a significant concern. ? rel iminary evai uati on 'indicates hat the potential or exceecing OHB limi>>s is law due ta the cold initial ooera.ing conditions. iurther investigation of this "raolem is uncerway.
The recamme..ced ;ntar.'m ac=.'ors :" "."event ar mitcata an inadver ant "aran d t':cn at shu-"cwn c nc';:i-ns =-",e detailed in Acpencix A.
nc =cc'<ed c"ntral raas are r equi rec, as spec ried in ; .'c re A-l, ne
July 9, 1980 Page. 3 plant operator has fif een minutes from the intiation of dilution event it to terminate the event oefore a return to critical oc"urs. is 'he Westinghouse cosition that a iftaen minute time interval from the initiation of the diRution to the time shutdown margin is lost is suf-ficient time for operator ac.ion..'f cocked control rods are reouired, the source ran e reac:"r tria QroviCes "osltsve 1nascat-on';or >mmeolata operator act;on to terminate ai utlon.
- t is expected that the operator has available the following information for determination that a dilution event, is in progress'.
Source Range Neutron Flux with,
- a. High Flux. at Shutdown Alarm set, at half a dec de above background.
- b. Use of the audible count rata indication to distinguish significant changes in flux i.a., a doubling of the count rate.
- c. Periodic, i. e., freouent surveillance of the Source Range meters performed by .he operator.
- 2. Status indication of the Chemical and Volume Can rol System and Reactor Makeup Mater System ~ith,
- a. indication of boric acid and blenced (total) flow ra a, or
- b. indication of boric acid and clean makeup flow rate,
- c. CVCS valve position status lights, and
- d. Reactor i4iakeup Mater P mo "". unning" status light.
The operator action necessary upon determinat'on that a dilution e'ient .
is in progress (by High Flux at Shutdown Alarm, Source Range Reac or Trip, "P-6 Avai lanle'naicztion, high indica:ad or audible count rates, or make uo flow deviation alarms) is:
- l. ammed-'ately "cen:"e c.".argirg/Si pump sue= on valves from the RMS7 (that open on receipt "I an "5" s;,"ra i ). (For 312 pl ants t"esa -"~ IrV-'=-~ 0 =or 412 piarts these are LCV-112-9, =.)
~ t ~
eg ~ g July 9, 1980 Page 4
- 2. Immediately clo e the charging/SI pump suction valves from the VCT (that close on receipt of'n'S" signal). (For 312 plants these are LCV-11S-C, E. For 412 plants these are LCV-112-8, C.)
- 3. For two-loop plants, immediately open the charging suction valves from the RWST. (For 212 plants these are LCV-113-8 and LCV-112"C.)
Also immediately close the charging suc-ion valves rom the VCT.
(For 212 plants these are LCV-113-A and LCV-112-B.)
Through the use of Appendix A ana the above noted operator action requirements, Westinghouse is at.empting to minimize the operational burden placed on the plant to prevent or mitigate an inadvertent dilu-tion event while mqintaining adequate safety margin. Our investigation of this event is continuing. A detailed analytical model of the system response o a dilution event at shutdown conditions is being developed and the potential for sys em overpressurization and fuel failure will subsequently be assessed, The Westinghouse investigation is expected to be completed by September 15, 1980. We will keep you informed as to the results of our efforts.
Very truly yours, Eastern Region WNI Support
'I SR4/B819/20 cc: R. W. Jurgensen J. E. Owyer W.
APP~HOIX A Figuro A-l, attached, provides -.he shut"cwn margin r quirem nw s a =unc:ion of Qeactor C"olant System boron c"ncentrat;cn ard maximum possible dilution flow rate. Prior to use o= this inure e Giant mus: determine .he maximum dilut Gn rlow rat4 of all charging pumps not rencaroa inooerable onc '.he :lant is placed on ~uq. 7o cover all modes, it should
'
'ssum d that the flew r'te is based on
" ng de'Ilcas n "'le system,'ol l cas, pump runout unless there are f'.cw I 1 p p-ing resistances, e c.).,lne Reactor Nakeup 'Qatar pump capacity may be limi ing in the determination of the maximum poss ibie dilution f',cw ra=a.
Flgur A-1 notes ar4as or accept4ble operation of thro e dif-,ar4nt -ilution rlcw rates as a function of RCS boron cconcactration and boratad shut"own mar,in (< --).
For a given dilution flow rate, i-'he RCS boron conc ntration and shutdown margin result in a point plac& to:he lert of the rlcw rate line, no contml rod bank wi".hdrawal is neca4ssarI. !f the r4sults place:he plant to the right the line, then either the snut"cwn margin must be incr4aSad such that the plant is moded to ".he a. ea 3 ac 49 4bie pera ion, Gt I, "k/k in control r ods withdrawn to crovide adcitionai shutdown mar".in. The =ripoing cr withdrawn rocs provides posit ve ope. a:-r lnolcatlon that a dilution event is;n progress and additional time =or operator ". rminat cn o= the event. In all cases, a shut"own margin of 5">> ak/k (< - ) < pig5) is considero> su-.=icient for contin-ued operation wf hout a requireAient =o-contrql rod bank withdr wal.
Figuro A-1 is based on bes- stimat calculations -or the "all rcds in" configu-ration. It is reccamended t",.at the 'Pest-ingnouse Nuclear pesign Repol ol Jour plant be used as a rererence in determining .he RCS borcn conc ntr tion wl tn le appropriat censer Iatism to e used in -he;igur4. ~.".e '<<estingnousa '(ucl ear Fuel pivision is available to provide ssis=nc in .;.e ti;.g -.e c"rstr in:s imcosad ."y the Figure A-1 requirements.
Ose of Figure A-1 fs applicable any "i-e tnere .'s beret on/dilution pability
- r -~e normal boric acid'blending sys=~i. Tne abo'Ia procedure
'= mboration and/or mak4up during cold =nd hct shu="'c<<n is per-,c...,ed ut.l i-ing is not r4qurr4d wa 4r fry the 3 AS7. i ni s r4qui r es =.".at =.'"e norma 1 "" 1 uti on/ c ration .:ath i s Sclatad from .he Chargina'pa:h. Twc meanS Or 1OCk"ut tc iSOla a the C:la ging path are available:
L."ck out Reac:or .'<akeup via ar '"ciy 7115 is ac PiQl l shed y 'Ia ve A ~
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- Lan&, nd va.ve =-'==;;l. -1 c,'.
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l.ocz out valves ".e-~e n ".".e d'or'c acid blencer nd -4e VC7.
7hese are;C'!-III3, C'I-IIQB, "339, 33="", and 8361 ".or 212 pIano;,=C'I-II4A, FC(-II".g, gage, 0<'I, and 8~3o;or 312 Planets; FC'l-IIIB,;C'/-IICB, 3'53, 8441, 8439 =or "12 plan~.
j 'q is reconmenda 7, i on pr c udes t e oc "r ence 0 i an inadver ~en ~ di I union ~ni e L
borax ng or ask-'ng up ~at r =rom i".e i'AST under -.geese conditions.
llW l(~E lu x lu lO Is INCII I x lo IIICIILu 46 1320
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2 FIGURE 4.5 D. C. Cook Unit 2 Cycle 5 Boron Concentration for N-1 Rods Inserted No Xenon Keff = 0.984 PREPARED BY ISSUE DATE~~ >~><
1600 b EXPIRATION DATE ~4 APPROVED APPROVEO FOR USE IN ~'~
DEPT. 5Y 1400 1200 8
C4 C4 o 1000 800 0
O o 600 68 F (CZP) 350 F 400 450 F
- NOTE: Includes 100 ppm allowance for 5470F (HZP) 200 conservatism 1 EFPH = 1.797 x 10 GWD/MT 6 8 10 12 16 17.9 Cycle Exposure (GWD/MT)
Attachment 4
~hdmm~~3m>~Mmo Since the boron concentration required to maintain a shutdown margin of 1600 pcm varies with core lifetime, the fuel vendor supplies curves of required boron as a function of core life and moderator temperature. The assumption is made that the most reactive rod is stuck out of the core. Also, 100 ppm in boron concentration is added for conservatism.
The curves supplied by the fuel vendor do not take into account the boron dilution accident. Therefore, the curves are modified as specified in AEP-80-71, Attachment 2, before incorporating the curve in the Plant Technical Data Book. Figure A-1 in AEP-80-71 gives the required Keff, hence the shutdown margin for a given boron concentration. The following procedure is used to recalculate the required shutdown boron.
Step 1- Interpolate Figure A-1 in Attachment 2 for dilution flow r ate of 225 GPM for "all banks in" case.
Note: maximum dilution rate possible is 225 GPM.
Step 2- Obtain boron concentration SB1 from the interpolated line (Step 1) for a Keff of 0.984.
Note: Keff of 0.984 corresponds to a shutdown margin of 1600 pcm.
Step 3- From the vendor supplied shutdown boron curve for moderator temp of 68 F find the burnup (B1MWD/T) corresponding to S 1.
Correction to the shutdown boron concentration is nolf necessary for concentrations less than SB1.
Step 4- Obtain the shutdown boron SB2 / for 0 MWD/T from the vendor supplied, curve for moderator temperature of 68 0 F.
Step 5- If SB2> /
SB1'hen SB2/ needs correction.
Step 6- Obtain Keff2 corresponding to a boron concentration / from, SB2 Figure A-1 and calculate dp'ef4 - 0'f8't Kefh.
/
Step 7- Increase dP by an arbitrary factor of 1.4 Ap = s9 xdp Note: A factor of 1.4 is conservative for the iterative solution required.
Page two Step 8 - Obtain the required shutdown boron concentration where 88/SC is the boron worth. To conservatively calculate SB>, the boron worth is chosen to be lowest value in the boron concentration and temperature range for which SB> is being calculated.
Step 9 - Draw a straight line between point (SB , 0 MWD/T) and point (SB1, B1 MWD/T). For burnups higher tkan B1 MWD/T, the line specified in the vendor supplied shutdown boron curve is applicable.
5'8a Sea S8L M%ID/7 B1 Step 10 Verify that the straight line approximation is conservative.