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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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] |
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REGULATO INFORMATION DISTRIBUTION . TEM (RIDS)
ACCESSION NBR: 87122'70389 DOC. DATE: 87/12/23 NOTARIZED: NO DOCKET 0 FACIL: 50-316 Donald AUTH. NAME C. Cook Nuclear Power P I
AUTHOR AFF IL ATION lant'nit 2i Indiana 5 05000316 ALEX ICHOR M. P. American Electric Power Service Corp.
REC IP. NAME REC IP IENT AFFILIATION MURLEYs T. E. NRC No Detailed Affiliation Given
SUBJECT:
Forwards addi info on emergency diesel generator surveillance interval extensions for Cycle 6> per NRC 871218 tee lan request.
DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
REC IP IENT COPIES REC IP IENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 0 PD3-3 PD 5 5 WIGGINGTONi D 1 INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEBT/ADS 1 1 NRR/DEST/CEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/RSB 1 1 NRR/DOEA/TSB 1 1 NR S/ILR9 1 1 OGC/HDS1 0 01 1 RES/DE/EIB 1 EXTERNAL LPDR 1 NRC PDR 1 1 NSIC 1 1 TOTAL NUMBER OF COP 1 ES REQUIRED: LTTR 20 ENCL 17
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1 Cy
'll V
American Electric Power Service Corporation 1 Riverside Plaza Columbus, OH 43215 614 223 1000 8
AEP:NRC:0916AG Donald C. Cook Nuclear Plant Unit 2 Docket No. 50-316 License No. DPR-74 ADDITIONAL INFORMATION ON SURVEILLANCE INTERVAL EXTENSIONS FOR UNIT 2 CYCLE 6 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley December 23, 1987
Dear Dr. Murley:
This letter responds to requests for additional information made by your staff during a telephone conversation on December 18, 1987.
Specifically, we were asked to provide supplemental information regarding the diesel generator surveillance interval extensions that we requested in our letter AEP:NRC:0916AE, dated October 28, 1987. The information requested is contained in the attachment to this letter.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M. . Al xich Vice President cm Attachments cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman A. B. Davis - Region III 87i2290389 87>~3ib PDR ADocx 0 PDR p
'l Attachment to AEP:NRC:0916AG Supplemental Information Regarding Diesel Generator Surveillance Interval Extensions
Answers to NRC Questions of 12/18/87 Regarding Cook Nuclear Plant Emergency Diesel Generator Surveillance Extensions Problem Areas from Past Ins ections 4
Completed packages of Maintenance Procedure MHP 4030STP.046 (Emergency Diesel Generator System 18-month Inspection) were reviewed for identified equipment deficiencies by the Plant Maintenance Department on 12/18 and 12/21/87. Packages from the previous 5 inspections for the Unit 1 diesels, and from the previous 4 inspections for the Unit 2 diesels, were reviewed.
The vast majority of these deficiencies were in the category of minor gasket leaks. These leaks are judged to have had no effect on the operability or reliability of the affected diesel generator. The other categories were:
- 1. Broken intake or exhaust valve springs (5 occurrences)
- 2. Failed valve lifters (6 occurrences)
- 3. Re-torquing of a cylinder head bolt and a foundation bolt (1 occurrence each)
- 4. Crankshaft deflection out of specification (4 occurrences all in 1984 or earlier)
- 5. Missing nut or lockwire (1 occurrence each)
- 6. Injector failure or popping pressure out of specification (3 occurrences)
- 7. Main bearing found worn upon inspection (1 occurrence)
These items would maintenance.
all fit in the category of routine Emer enc Diesel Generator Manufacturer's Recommendation on Surveillance Interval Extension The Cook EDGs were manufactured by Worthington Compressor Co. of Buffalo, NY. The company was merged with Dresser-Rand of Painted Post, NY in 1987.
Dresser-Rand technical personnel were contacted by AEPSC on 12/21/87. They stated that extending the interval of the
Page 2 surveillance inspections until June 1, 1988 should cause no problems. They also stated that no additional inspections were recommended for the interim period from January 1 to June 1, 1988.
As a point of reference, the manufacturer's standard recommendation calls for an inspection of similar scope every 4000 hours0.0463 days <br />1.111 hours <br />0.00661 weeks <br />0.00152 months <br /> of operation. This recommendation applies to diesels in continuous operation and is therefore not directly applicable to the Cook EDGs. For comparison, the Cook Unit 2 EDGs have each incurred approximately 1500 total hours of operation.
Emer enc Diesel Generator Reliabilit Reliability for the last 100 starts is 100% for 2AB diesel and 99% for 2CD diesel.
Effect on Blackout Tests Extension of the surveillance inspection interval should not affect the ability of the EDGs to successfully perform the blackout tests specified in the Technical Specifications.
The main problem area of past blackout tests has been in the area of load rejections. During a full load (3500 kw) rejection, approximately 80% of the Technical Specification overspeed margin (7.5%) had been used. The amount of overspeed margin used in subsequent tests has been reduced to approximately 55% by tuning and adjustment of the governor, and of fuel rack linkages. We believe this problem to be corrected, however, it is not considered relevant to the extension of the surveillance interval since these components are not subjected to substantial wear or degradation.
Results of Last lns ection The most recent 2AB EDG inspection was completed on 5/3/86.
No major problems were found. One main bearing that was inspected was found to be worn on the lower half. The bearing was replaced.
The most recent 2CD EDG inspection was completed on 6/3/86.
No major problems were found during the inspection.
Following the inspection, during a post-maintenance test run, a main bearing failure occurred. This failure caused damage to the crankshaft and b=se. The engine was rebuilt with new parts and tested successfully.
~- Page 3 Desi n and 0 erational Chan es to Enhance Main Bearin Reliabilit Two main bearing failures have occurred on the Cook EDGs since initial criticality of Unit 1 in 1975. The failures have never been attributed to a specific cause or'causes.
Several improvements in the areas of design and operation have been or will be implemented:
- 1. Improved method of checking crankshaft web deflection. (Completed)
- 2. Reducing oil sump temperature from 165F to 145F.
(Completed on Unit 1)
- 3. Installation of a main bearing metal temperature indication/high temperature trip system.
(Completed on Unit 1)
- 4. Elimination of Tech Spec requirement to run EDG at 3850 kw (104 overload) for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during the post-maintenance 24-hour run prior to blackout testing.
(Completed on Unit 1) 5 ~ Change in the maintenance procedure to ensure that the bottom half, as well as the top half, is inspected any time a main bearing assembly is opened for inspection. (Completed)
- 6. Change to Tech Spec to allow "slow" starts for most surveillance starts, consistent with manufacturer's recommendations and Generic Letter 84-15.
- 7. Installation of an improved-design center main bearing. This design will improve the load-carrying capability of the bearing and improve the oil supply to the predominantly-loaded area of the bearing.
G. D. Hines 12/22/87
SURVEILLANCE TEST DUE DATES
- 1. Maintenance Inspection (T/S 4.8.1.1.2.c.l)
Due Date Approximate length Diesel Last Test Date includin 25% race of Extension 2AB 05/03/86 03/18/88 3-1/2 months 2CD 06/03/86 04/18/88 2-1/2 months
- 2. Blackout Testing (T/Ss 4.8.1.1.2.cd 2 through 4.8.l.l.c.12)
Due Date Approximate Length Diesel Last Test Date includin 25$ race of Extension 2AB 07/01/86 05/16/88 l-l/2 months 2CD 07/01/86 05/16/88 1-1/2 months
~Assumes that the fuel is unloaded from the core on July 1, 1988.
1 SPECIFIC DIESEL GENERATOR RELATED TECHNICAL SPECIFICATION EXTENSIONS The diesel-generator related Technical Specifications which we are requesting extensions for are listed below:
Test 4.8.3..1.2.C.1 Diesel generator inspection per manufacturer's recommendations.
4.8.1.1.2.C.2 - 4.8.1.1.2.C.12 Diesel generator "blackout": testing 4.8.1.2 Node 5 and 6 reference to Technical Specification 4.8.1.1.2.
4.4.11.3 PORV and block valve emergency power supply.
4.7.4.1.b ESW automa=ic valve actuation.
The relevant Technical Specification pages, with the specific extension Technical Specifications circled, are attached for the reviewer's convenience.
3/4.8 ELECTRICAL nOWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDII.ON:OR OPERATLON 3,8.1.1 As a minimum, tne following A.C. electrical power sources shall be OPERABLE:
a, Two physically independent circuits between the offsite trans-mission network and the onsite Class lE distribution system, and
- b. Two separate and independent diesel generators each with:
- l. A day fuel tank containing a minimum volume of 70 gallons of fuel,
- 2. A separate fuel storage system containing a minimum volume of 42,000 gallons of fuel, and
- 3. A separate fuel transfer oumo.
APPLICABILITY: MODES.1, 2, 3 and 4, ACTION:
- a. With either an offsite circuit or diesel generator of the above requi red A.C. el ectri ca power sources inoperabl e, demons trate 1
the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.l.l.a and 4;8.1.1.2.a.4 within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A C. sources by performing
~
Surveillance Requirements 4.8.l.l.l.a and 4.8.1.1.2.a.4 within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least one of the inoperable sources to OPERABLE status within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> s or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours.
D. C. COOK - UNIT 2 3/4 8-1
ELECTRZCAL POWER SYSTEMS ACTZON {Continued) c, With two of the above reauired of site A.C. circuits inoperable, demonstrate the OPEPiBZLZTY of two d'esel cenezators by performing Surveillance Recuireme..t 4 8 1 1 2 a.4 within one hour and at least
~ ~ ~ ~
once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> the eafter, unless the diesel generatozs are alzeady operating; zestore a" least one of the inoperable offsite sources to OPERABLE status w thin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hcurs. with only one of site source restozedp restore at least two offs'=e c>> 'uits to OP PEBBLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss cr be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDCWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- d. with two of the above recuired diesel generators inoperable, demonstzate the OPERABZLZTY of two offsite A.C. circuits by pezforming Surveillance Requirement 4. 8. l. 1. l. a within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> the eafter; restore at least one of the inoperable diesel generators to CPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> oz be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hcurs. Restore at least two diesel generators to OPERABLE status'within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the fol'owing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURV ZLLAÃCE zvQU B-.v-.y S 4.8.1.1.1 Each of the above required irdepe..den= =ircuits between the offsite t ansmission network a..d the cnsite Class 'E d's='= bution system shall be:*
- a. Determined OPERABLE>> at least once per 7 days by verifying correct breake alignments, indicated power availability, and
- b. Demonstrated OPERABLE at least once per 18 months by transferring the uni" oower souzce automatically from the ..ormal auxiliary source to the pre;erred rese ve source and by transfe 'ng manually to the alternate reserve source, 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:'.
Zn accordance w'th the frequency specified in Table 4.8-1 on a STAGGERED T:"S. BASZS bv:
- 1. Vez'fying =he fuel level in the day fuel tank.
- 2. Verifying =he "uel level in the fuel storage tank.
.he provisions of Spec'f'cat'on 4.0.6 are applicable.
D. C. COCK - LNZT 2 3/4 8<<2 Amendment No. 78
ELECTRICAL POME" ""ST= !S SUR!lEIL! ANCE RE"!g:R-".'!E;3"S ",'"ontinued)
- 3. 'ler ;y nc :he fuel iransfer pump can be started and tr ns-.e. s -..ei ;rom the storage system to the aay tank.
- 4. 'ler ;yina the diesel starts from ambient condition and acc ie. a-.es to at least 514 rpm in < 10 seconds.
- 5. Ver ifying the generator is loaded to > 1750 kw, and operates -.or. > 60 minutes and verifying that the generator output breaker to the emergency bus is OPERABLE.
- 6. Verifying the diesel generator is aligned to provide stana"y power io the associated emergency busses.
At least onc per 92 days by verifying that a sample of diesel fuel free the fuel storage tank obtained in accordance with AST>'l-"273-65 's uithin the ac eptable limits specified in
!able 1 o= AS!'1-0975-74 when check="'or viscosity, water and sediment.
c, At least once per 18 months during shutdown by:
Subjec:ing the diesel to an ';"spection in accordance with proceaures prepared in conjunction with i: s manufacturer's recommendations 'or this class of standby service.
Ver;;ying that ihe automatic sequence timing relays are OPER"BLE with each load sequence =ime within + 5.'"o of i;s required value and that each load is sequencea on within ihe design allowable time limit.
'leri,ying the generator capabi!ity to reject a load of >
600 ku uhile maintaining voltage at 4160 + 420 volts and req ency at 60 + 1.2 Hz.
"leri;ying the generator capaoili iy to reject a load of 3500 '<w without exceeding 75:l of the difference between ncminal soeed and the overspeed trip setpoint.
mulating a loss of offsite pcwer by I
itself, and:
Verifying de-energization of the emergency busses and load sheading from the emergency busses.
- 0. C. COOK - Ui'ii 3/4 8-3
~ ~
h.LECTRICAL Vv'~cR SY
'URVKiLLAllC"=R"-"UiR-.M-..(TS (Continue>
b) Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency busses with "er.-..anently connec"ted loads, energizes the auto-connected shutd"wn loads through the load sequencer and ."pera:es fcr ' minu:es while its generator :s loaded wi:h :he shu"down loads.
Veri fying .'.hat cn an .S.= ac.uaticn 'est signal (without
'loss of offsite -ower ) the d':esel generator starts on the auto-star. s~gnal and operates on standby '.or '
minutes.
Q7. Verifying .hat "n ~ simulated loss of the diesel gener-ator (with orfsite vower not available), the loads are shed from .he emergency busses and hat subsequent loading o; :he diesel generator is in accordance with design requirements.
r
- 8. Simulating a loss of f offsite f power in conjunction with t an ESF actuation
~ '.t e st signal, g and a) Veri,ving de-energization of the emergency busses and load shed".',"." from the emergercy busses.
b) Veri;yinc << e diesel starts f."m ambient condition
~
on the auto-start signa 1, ener: :es the emergency busses with pe..<<anently connec:e". loads, energizes the auto-connected emergency ,=:ident) loads '.hrouch the load sequencer and operates 'or . 5 minutes while its generator is loaded with :.-.e emergency loads.
c) Veri,ying that on diesel generator tr ip, the loads are shed from the emergency buses and the diesel re-starts on the auto-s <<art s; gnal fc lowing manual 1 resetting of the diesel trip lockout relay, '.he emergency buses are energized w;".h permanen:ly connected loads the auto-conne . d mer-ency loads are energized through the load sequencer and the diesel opera es -,or >5 minutes while i: s generator is loaded with emergency loads.
d) Veri fving tha t a I ) diesel gener a tcr '.ries, except engine overspeed and generator di fferential , are au'tcma << i ca y bvpa s s ed upcn os s 1 1 1 o.'ol ta ge on the emer"ency bus and/or safety injection ac:ua << Ion signal.
Verifying the diesel generator opera t~s for a 1 ast 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Our,'ng the '.Irst 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of thl s tes t, he diesel generator shall be leaded to 3 0 kw and during t(ie rema inirg 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, ". e diesel genera Qr shall be loaded to .'500 xw. 'Jithin 5 minutes af (.~r corn pleting this 2>>'cur test, repeat Sp ecification '.8.1.1.2.c.S.
- 0. C. CCQK - U'llT 2 3/v 8-3a hi <<;noh'>out t(o. 22, ~in L
ELECTRICAL POWER SYST=PIS SURVEILLANCE RE UIRE.'1E.'ITS (Continued 10 f i that :he auto-connected Yerifying t loads o each diesel generator do c rot exceed e the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 3850 kw.
11 f Yerifying "iesel genera or's caoability to:
.'.",e d a) Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power.
b} Transfer i.s loads to the of. site power source.
c.} Proce d through its shutdown sequence.
- 12. Verifying tnat with the diesel generator operating in a
~
test mode, a simulated safety injection signal overrides tne test mode by (1} returning the diesel generator to
~
stancby oceraticn and (2} automatically energizing the emergency loads with cffsite pcwer.
- d. At least ence per 10 years or after any ;..c=.'rications which could affect diesel generator interdepence",ce by starting. both diesel generators simultaneously, during s.'"utdown, and verifying that both diesel generators accelerate tc -. least 514 rpm in
( 10 seconds.
.8.1.1.3 Recorts - All diesel generator failures, valid or non-valid, hall be reportea to the Conmission pursuant to Specification 6.9.1, If he number of failures in he last 100 valid tests (on a per nuclear nit basis) is ) 7, the report, shall be supplementec to include the dditional informaticn r cormended i'n Regulatory Position C.3.b of egulatory Guide 1.108, Revision 1, Augus- 1977.
- 0. C. COOK - U!LIT 2 3/4 8-4
iAHL:. 4 8-1
..'.:.":-L G=N:RA "R .5 iC:.""DUL"-
Number of;ai I~res Las- 1 "0 'la" s:= i st Freo~uenc At least once per 31 days At least once per 14 days At least once per 7 days At least once per 3 days Cri eria -.". "eterminirg number of fai'.res and number of valid
- ests shall be in accordance wi h Regu'..--..ry position C.2.e of Regul a tory "=vide . 108, Revi s ion 1, Au=..:: 1977, where the last 1
100 tests are determined on a per nucle= Jnit basis.
- 0. C. COOK - U'l " > 3/4 8--'a
0 t TT hf OP 3.4.11 Three power operated elief valves (PORVs) and their associated block valves shall ba OP~L"-.
KXLQE:
a ~ PORVs inoperab': *
- 1. With o,. PCB.V nope able, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> e cher restore che PORV to OPB.%LE status or close the assoc'aced block valve and remove paver from the b'ock valve; otherwise be in ac lease HOT STANDBY vichin che next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHtJTDOlVi vichin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- 2. j 7 th rvo PORVs inoperable, within 'our eithe restore ae least one PORV to OP~L"= stat s or close the associated block valves and re ove power from che olock valves; restore ac least one PORV to OP~LZ sea~ vithin the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY vichin che ne:..= 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOl if vithin the Following'30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- 3. arith ~"~e PORVs inoperable, vithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either reseore a" 'ease one of the PORVs co OPDA3L". sea~ or close their associated block valves and remove powe" rom che b'ock va'ves and be in HOT STAÃ)BY vithin eha nexe 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD Si'.UTDO~N vithin the following 30 hou s .
- b. Block valves inoperable:*
- l. Pith ~ block valve inoparaole, within 'our eiehar (1) reseora che block valve eo OP~LZ scaeus, or (2) close the block valve and rcmove power from the block valve, or (3) close the associated PORV and remove power from the assoc'aced solenoid valve; otherwise, be in ae least HOT STAR)BY vi&in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SciVii04H within the folloving 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- PORVss isolated co 1~it RCS leakage th ough their saaes and the block sh<<eot isolate this 'eakage are valvess shut noe considered inoperable.
C. CQQg - ggZT 2 3/4 4-32 A?~DIGHT HO. 82
s MI Th) Q QQ T'QR Q<<c'J 'TTQg (Co <<~<<used) 2, With -~o ot -,...-e block va ves inope able, within 1 hou" e'ther {1) restore a "otal of at 'east two b'ock valves to OP-""~LE status, or (2) close the block valves and e .ove power rom the block valves, or (3) close "he associated PORVs and x'emove power from their assoc'ared scl nnid valves; and apply the poxtion" of ACTION a.2 or a.3 above for inoperable PORVs, re'ting to OP&A..ONAL .'LODE, as appropr'ate.
Wj.th >OV7s and b ock va>v~ ..ot in che same line inoperable,
- within 1 hou" e ther (1) restore the valves to OP%ABLE status or (2) close and de-energize the othe. valve in each line.
Apply the port'ons of ACTION a.2 or a. 3 above, relating to OP~TIONAL .'fCDE, as appropr'ate for two or three ~> ~~e unavailable .
- d. The provisions o Spec ication 3.0.4 are not applicable.
S RV"I < Rr U R"-u~~
.5 4.4.11.1 Each of the three PCRVs shall be demons-". "ed OPERABLE:
a At least once per 31 days by perfox~nce -.= a CK<4~rL HRiCTIONAL TEST, excluding valve operation, and b, At least once per 18 months by performance of a CHA'GAEL CALIBRATION.
4.4.11.2 Each of the three block valves shall be demonstrated OPE~LE at.
least once pex'2 days by operating the valve through one complete cycle of full travel. The block valve(s) do not have to be tested when ACTION 3.4.11.a or 3.4.ll.c is applied.
4.4.11.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE a" least once pex'& months by operating the valves through a complete cycle of full travel while the emergency buses axe energized by the onsite d'esel generators and onsite plant batte i.es. This testing can be performed in con]unction with the requirements of Specifications 4.8.1.1.2 ' a"..d 4.8 '.3.2.d.
- PORVs i.solated to limit RCS leakage through their seats and the block valves shut to isolate thi.s leakage ax'e not considered inoperable.
- 9. C. COOK - UNIT 2 3/4 4-33 ~mme No. 82
PLANT SYST",'iS
/4 7 4
"-"""g . <r>"'r- HAT-2 SYST 1 LIMNI "ING CONOIT:ON ."-."R ')P=.";~.:"N 3.7.4.1 At leas-.':wo ','nde.encent essent al service water looos shal'i be OPERABLc,.
APPLICABIL!:Y: MODES 1, 2, 3 and 4.
ACiIOII:
c I>lith Only One ServiCe water 1OOp OPLRABLE, reStOre'at leaSt tWO lOOOS to OP RABLe. status within 72 hours or be in. at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and n COLD SHUT~0'AN within tne following 30 nours.
SURVE ILL~"iC"- R='"U! R"=~'.5'ITS
.7.4.1 At least two essential service wate" '".ops shall be demonstrated BL"=
At least once per 31 days by verify no that each valve (manual, power operated or automatic) servic'ng safe y related equip-ment that is no" locked, sealed, or :therwise secured in position, is in its correct position.
At least once'er 18 months dur nc snutdown, 5y veri,ying that each automatic valve servicing sa=e:y related equi" ment actuates to its correct pos',t'on on 'afety In',ec:ion tes:
signal,
- 0. C. COCK - "NI; 2 3/4 7-13