ML17324A773
ML17324A773 | |
Person / Time | |
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Site: | Cook ![]() |
Issue date: | 04/17/1986 |
From: | Ward G SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
To: | Harold Denton Office of Nuclear Reactor Regulation |
Shared Package | |
ML17324A774 | List: |
References | |
GNW:055:86, GNW:55:86, NUDOCS 8604220217 | |
Download: ML17324A773 (4) | |
Similar Documents at Cook | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17335A5691999-10-21021 October 1999
[Table view]Forwards Insp Repts 50-315/99-25 & 50-316/99-25 on 990816- 20.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML17335A5681999-10-19019 October 1999 Confirms Plans to Conduct Meeting with American Electric Power & DC Cook Plant Mgt to Discuss Status of Case Specific Checklist Items,Rev to Restart Plan,Operations Dept Readiness for Restart & Performance Assurance Audit Status ML20217J4721999-10-15015 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 ML17335A5541999-10-0101 October 1999 Submits Summary of 990712 Technical Meeting Re Containment Sump Issues Concerning Restart of Plant,Units 1 & 2.List of Attendees & Matl Used in Presentation Encl 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 ML17335A5491999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix Encl ML17335A5391999-09-27027 September 1999 Forwards Copy of Preliminary Accident Sequence Precursor Analysis of Operational Condition Which Was Discovered at Plant,Units 1 & 2 on 980715,for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr ML17326A1601999-09-27027 September 1999 Forwards Insp Repts 50-315/99-16 & 50-316/99-16 on 990719-23 & 0802-06.Violations Re Failure to Maintain Exam Matl Security & Maintain Licensed Operator Biennial Medical Exams Identified & Being Treated as Noncited Violations NUREG-1706, Discusses Licensee & Suppl Which Responded to GL 98-01, Y2K Readiness of Computer Sys at Npps. Concluded That No Nuclear Plants with Y2K Issues Involving Safety Sys Identified1999-09-23023 September 1999 Discusses Licensee & Suppl Which Responded to GL 98-01, Y2K Readiness of Computer Sys at Npps. Concluded That No Nuclear Plants with Y2K Issues Involving Safety Sys Identified ML17326A1701999-09-23023 September 1999 Informs That Proposed Rev to Applicable Specifications to Containment Sys TS Bases 3/4.6.1.4 & 3/4.6.1.5,submitted in ,Withdrawn Per 990920 Telcon ML17326A1651999-09-22022 September 1999 Forwards Insp Repts 50-315/99-17 & 50-316/99-17 on 990717- 0825.One Violation Identified & of Concern Because Inspectors Identified Failure to Restore Compliance for Previously Identified Violation of NRC Requirements 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 ML17326A1551999-09-17017 September 1999 Transmits Updated Case Specific Checklist for DC Cook Nuclear Power Plant Which Identifies Specific Issues Requiring Resolution Prior to Restart of Cook Plant ML17326A1361999-09-16016 September 1999 Forwards Insp Repts 50-315/99-07 & 50-316/99-07 on 990712-30 & 0816.Seven Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy 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 ML17326A1391999-09-15015 September 1999 Forwards Insp Repts 50-315/99-18 & 50-316/99-18 on 990726-30 & 0816 ML17326A1151999-09-0808 September 1999 Responds to W Nelson 990614 & 0726 Ltrs Re Schedule for Initial Licensing Exam for Operator License Application. Exam Scheduled for Wks of 010305 & 12 & 0423 & 30 ML17326A1031999-08-25025 August 1999 Forwards Notice of Consideration of Issuance of Amend to FOL Re Request for License Amend Dtd 980914.Amends Would Change Runout Limits for SI Pump to 675 Gallons Per Minute Not Exceeding 700 Gallons Per Minute for Both Units 1 & 2 ML17326A1021999-08-25025 August 1999 Informs That on 990819,NRC Held Public Meeting at Region III Ofc in Lisle,Il to Discuss Status of Facility Restart & NRC Manual Chapter 0350 Oversight Insp ML17326A0971999-08-25025 August 1999 Provides Summary of 990615 Public Meeting at DC Cook NPP in Berrien County,Michigan Re Technical Issues Concerning Restart of DC Cook Npp,Units 1 & 2.List of Meeting Attendees & Copy of Slides Used by Licensee Encl 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) ML17326A0831999-08-13013 August 1999 Forwards Insp Repts 50-315/99-15 & 50-316/99-15 on 990528-0716.No Violations Noted.Insp Consisted of Selective Examinations of Procedures & Representative Records, Interviews with Personnel & Observations of Activities ML17326A0881999-08-12012 August 1999 Forwards Draft Preliminary Results of Analysis of Risk Significance of Issues That Were Identified at DC Cook NPP, Units 1 & 2,between Aug 1997 & Jan 1999 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, ML17326A0781999-08-0909 August 1999 Forwards SE Accepting 980403 Request for Approval Under Provisions of 10CFR50.55a(a)(3),to Use ASME B&PV Code, Section Ix,Code Cases 2142-1 & 2143-1 for Fabrication & Installation of Unit 1 Replacement SG Lower Assemblies 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 05000315/LER-1998-029-01, 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 Listed1999-08-0404 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 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 ML17326A0701999-07-27027 July 1999 Summarizes 990715 Meeting Conducted in Bridgman,Mi Re Ongoing Transition from Discovery Phase of Restart Plan to Implementation Phase.List of Meeting Attendees Encl ML17326A0671999-07-26026 July 1999 Forwards Summary of 990616 Meeting at DC Cook Nuclear Plant in Berrien County,Mi Re Core Offload for Both Units.List of Attendees & Copy of Briefing Sheets Used by Licensee Also Encl ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE 05000315/LER-1998-014-03, 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,Listed1999-07-22022 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 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 ML17326A0571999-07-16016 July 1999 Submits Summary of 990615 Public Meeting with Util in Berrien County,Mi Re Restart of Units at DC Cook,In Accordance with NRC Insp Manual Chapter 0350.List of Attendees & Slide Presentation Encl ML17326A0541999-07-15015 July 1999 Forwards Summary of 990324 Meeting with External 0350 Restart Panel to Discuss Status of Plant Restart Activities. List of Attendees & Slides Used by Licensee Encl ML17326A0551999-07-15015 July 1999 Fowards Summary of 990324 Technical Meeting Re Technical Issues Related to Restart of Plant,Units 1 & 2.List of Attendees & Slides Used by Licensee Encl ML17326A0561999-07-14014 July 1999 Forwards Summary of 990415 Meeting Re Status of Cook Nuclear Plant Restart Activities.List of Attendees & Matl Used in Presentation Enclosed ML17326A0441999-07-14014 July 1999 Ack Receipt of Withdrawing Request for Relief. Staff Actions for TAC M98339 Completed ML17326A0451999-07-12012 July 1999 Forwards Insp Repts 50-315/99-13 & 50-316/99-13 on 990517-0611.One Violation Noted & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy. Violation Re Failure to Perform Required Maint on Equipment ML17326A0371999-07-0606 July 1999 Discusses Meeting Conducted at Region III Senior Reactor Analysts at Plant Re Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee 05000315/LER-1999-004-01, Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed1999-07-0101 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 ML17326A0271999-06-30030 June 1999 Confirms Plans to Conduct Meeting with Util & DC Cook Plant Management to Discuss Technical Issues at Plant on 990715 in Training Center at Plant 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 1999-09-08 Category:INCOMING CORRESPONDENCE MONTHYEARML20217D9361999-09-30030 September 1999
[Table view]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 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 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) 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, 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 05000315/LER-1998-029-01, 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 Listed1999-08-0404 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 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 05000315/LER-1998-014-03, 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,Listed1999-07-22022 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 05000315/LER-1999-004-01, Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed1999-07-0101 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 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 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 05000315/LER-1998-037-01, Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal1999-05-24024 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 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 05000316/LER-1999-002, Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed1999-05-10010 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 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 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, & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects 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) 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 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 ML17325B4651999-03-12012 March 1999 Forwards Rev 5 to Cook Nuclear Plant Restart Plan, Which Supercedes Previous Revs in All Aspects.Licensee Will Continue to Advise NRC of Progress Toward Restart & Provide Addl Info During Monthly 0350 Restart Panel Public Meetings ML17325B4601999-03-11011 March 1999 Forwards Copy of Util 981102 Cover Ltr Sent to Mi Dept of Environ Quality Which Transmitted Storm Water Pollution Prevention Plan Rev Sheet. Util Failed to Send Copy to NRC within 30-day Period,Per Ets,Due to Internal Oversignt ML17325B4541999-02-28028 February 1999 Informs NRC Staff That Jr Sampson Will Assume Position of State President,Aep Impco,Effective 990301.Block Diagram of Interim Organizational Chart Attached ML17325B4521999-02-20020 February 1999 Discusses Delay in Implementation of License Amend 227 Until Issues Fully Evaluated ML17325B4531999-02-19019 February 1999 Forwards for Files,Copy of DC Cook Nuclear Plant Ltr AEP:NRC:90358B,dtd 981218 ML17325B4491999-02-18018 February 1999 Forwards Rev 1 to Licensee Ltr Sent to DOT Re Exemption Request to Support Disposal of DC Cook,Unit 2 Generators Removed in 1988.Rev 1 to ER-98-009, Premliminary Waste Characterization of DC Cook SG Lower Assemblies, Encl ML17335A5001999-01-30030 January 1999 Submits Response to GL 96-01, Testing of Safety Related Logic Circuits. Surveillance Revalidation Program Has Been Initiated by Operations Dept to Compare Associated Procedures with TS ML17335A4931999-01-22022 January 1999 Requests Extension of Response to NRC NOVs 50-315/97-201, 50-316/97-201,50-315/97-17,50-316/97-17,50-315/98-04, 50-316/98-04,50-315/98-05,50-316/98-05,50-315/98-09 & 50-316/98-09,until 990305 ML17335A4851999-01-18018 January 1999 Submits Overview of Updated Plant Restart Plan & Schedule 05000315/LER-1998-052-01, Forwards LER 98-052-01,re Potential Failure Mode for Air Operated Components Not Considered in Original Design. Interim LER Has Been Updated to Include Two Addl Instances of Same Failure Mode1999-01-18018 January 1999 Forwards LER 98-052-01,re Potential Failure Mode for Air Operated Components Not Considered in Original Design. Interim LER Has Been Updated to Include Two Addl Instances of Same Failure Mode ML17335A4941998-12-18018 December 1998 Informs NRC of Desire to Defer Number of Insps NRC Currently Has Scheduled for Dec 1998 & Jan 1999.Requests That Insps for Listed Items Be Postponed ML17335A4191998-12-18018 December 1998 Informs That Based on Stated Items,Nrc Review & Approval of License Amend Request Is No Longer Considered Necessary Prior to Restart of Unit 1 ML17335A4051998-12-16016 December 1998 Forwards Rev 4 to Cook Nuclear Plant Restart Plan, IAW Previous Commitments to Provide Copies of Restart Plan for Info ML17335A4091998-12-16016 December 1998 Withdraws All Previous Requests for Relief from Code Requirments for Containment Spray Pumps.Util Installing Mod to CSS That Will Enable Util to Perform Pump Tests IAW Code Requirements Prior to Restart ML17335A4101998-12-15015 December 1998 Informs That Licensee Would Be Pleased to Be Included as Reference Plant in GSI - 191 Evaluations,In Response to JW Craig Request 05000315/LER-1998-031-01, Forwards LER 98-031-01,re Potential Common Mode Failure of RHR Pumps Due to Use of Inaccurate Values.Commitment Made by Util,Listed1998-12-11011 December 1998 Forwards LER 98-031-01,re Potential Common Mode Failure of RHR Pumps Due to Use of Inaccurate Values.Commitment Made by Util,Listed ML17335A3891998-12-10010 December 1998 Informs That Util Is Extending Severe Accident Mgt Guidelines Until 991231 Due to re-assigned Engineering Resources 1999-09-30 Category:VENDOR/MANUFACTURER TO NRC MONTHYEARML17328A3091990-06-20020 June 1990
[Table view]Requests That Proprietary WCAP-12623 & Rev 4-P to CEN-313-P, Steam Generator Sleeving Rept & Steam Generator Tube Repair Using Leak Tight Sleeves, Respectively,Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20043C0771990-05-14014 May 1990 Requests That Proprietary WCAP-12576, Westinghouse Revised Thermal Design Procedure Instrument Uncertainty Methodology for American Electric Power DC Cook Unit 2 Nuclear Power Station, Be Withheld (Ref 10CFR2.790) ML17326B4001988-07-22022 July 1988 Forwards Listed Topical Repts,Providing Fuel Storage Facility Thermal Hydraulic & Criticality Analysis Results. W/O Stated Encls ML17334B1281987-08-25025 August 1987 Forwards Proprietary Version of Rev 1 to ANF-87-91(P), DC Cook 2 Debris-Resistant Lower Tie Plate Pressure Drop Test Rept, Supporting Operation of Facility.Rept Withheld (Ref 10CFR2.790(b)) ML17325A1271987-05-29029 May 1987 Forwards Proprietary XN-NF-87-31(P), Steamline Break Analysis for DC Cook Unit 2, Addressing Asymmetric Thermal Hydraulic & Neutronic Core Characteristics Resulting from Event.Rept Withheld (Ref 10CFR2.790) ML20215D4081987-05-15015 May 1987 FOIA Request for Reactor Vessel Surveillance Capsule Repts for Turkey Point 4,Zion 2 & DC Cook 1 NRC-86-3160, Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P1986-09-0808 September 1986 Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P ML17324A7991986-04-24024 April 1986 Forwards Rev 1 to Proprietary XN-NF-85-68(P), DC Cook Unit 2 Limiting Break Loca/Eccs Analysis,10% Steam Generator Tube Plugging & K(Z) Curve. Rev Reflects Changes to Reflood Correlation Per NRC Concerns ML17324A7731986-04-17017 April 1986 Forwards Proprietary Responses to NRC Questions 4 & 5 Re Rev 1 to XN-NF-85-64(P) Plant Transient Analysis for DC Cook Unit 2 w/10% Steam Generator Tube Plugging. Responses Withheld (Ref 10CFR2.790) ML17326B2241986-04-14014 April 1986 Forwards Response to 860108 Question 10 Re XN-NF-85-28, DC Cook Unit 2 Sar. Info Provided Re Calculated Coolant Pressure Rise & DNBR During Rod Ejection Accident ML17326B2111986-03-21021 March 1986 Forwards Proprietary Suppl 1 to Rev 1 to XN-NF-85-64(P), Plant Transient Analysis for DC Cook,Unit 2 W/10% Steam Generator Tube Plugging, Providing Revised Boron Dilution Analysis.Suppl Withheld (Ref 10CFR2.790(b)) ML17324A7201986-03-14014 March 1986 Forwards Proprietary Responses to NRC 860108 Questions 6,8 & 10 Re XN-NF-85-64(P) & Rev 1 to XN-NF-85-64(P), Plant Transient Analysis for DC Cook Unit 2 W/10% Steam Generator Tube.... Encls Withheld (Ref 10CFR2.790(b)) ML17324A6721986-03-0505 March 1986 Forwards Proprietary Responses to NRC Questions 1-4,7 & 11 Re XN-NF-85-64(P), Plant Transient...Steam Generator Tube Plugging. Addl Responses Expected by 860314.Proprietary XN-NF-84-69 Also Encl.Encls Withheld (Ref 10CFR2.790) ML17324A7511986-02-20020 February 1986 Requests That Proprietary WCAP-11080, DC Cook Unit 2 Rdf Resistance Temp Detector Installation Safety Evaluation, Be Withheld from Public Disclosure,Per 10CFR2.790.Affidavit Encl ML17321A9561985-11-15015 November 1985 Forwards Proprietary XN-NF-85-64(P), Plant Transient Analysis for DC Cook Unit 2 W/10% Steam Generator Tube Plugging. Rept Withheld (Ref 10CFR2.790(h)) ML17326B0081985-10-15015 October 1985 Forwards XN-NF-85-28, DC Cook Unit 2,Cycle 6 SAR & Proprietary Suppl 1 to XN-NF-85-28(P), DC Cook Unit 2, Cycle 6 Sar:Disposition of Srp.... Proprietary Suppl Withheld (Ref 10CFR2.790(b)) ML17326B0011985-10-0303 October 1985 Forwards Proprietary XN-NF-85-68(P), DC Cook Unit 2 Limiting Break Loca/Eccs Analysis,10% Steam Generator Tube Plugging & K(Z) Curve. Affidavit Encl.Rept Withheld (Ref 10CFR2.790) ML17321A9001985-09-30030 September 1985 Notifies of Error in 10CFR50.46 LOCA Analyses Performed for Facilities.Input Error in TOODEE2 Code Used to Calculate Fuel Rod Heatup Resulted in Rod Decay Heat Power Too Low & Subsequent Underpredicted Cladding Temp.Part 21 Related ML17321A7851985-08-0909 August 1985 Requests That Proprietary Safety Evaluation for Resistance Temp Detector Operability & Cross Calibr Be Withheld (Ref 10CFR2.790) ML17321A7861985-08-0606 August 1985 Requests That Proprietary Safety Evaluation for Increased Rdf Resistance Temp Detector Uncertainty Installation Be Withheld (Ref 10CFR2.790) ML20134P6651985-07-22022 July 1985 FOIA Request for Nonproprietary Version of Exxon Nuclear Co, Inc Rept XN-NF-739 Re Seismic Evaluation of Nuclear Fuel ML17321A6711985-06-10010 June 1985 Forwards Proprietary Slides Entitled, Cycle 6 Safety Analysis Status Review, Presented at 850530 Meeting W/Nrc & Util.Rb Stout Affidavit Also Encl.Slides Withheld (Ref 10CFR2.790) ML17321A5191985-04-0303 April 1985 Forwards Proprietary Draft DC Cook Unit 2 Cycle 5 5% Steam Generator Tube Plugging Limiting Break LOCA-ECCS Analysis:K(Z) Curve. Rept Withheld ML17321A5141985-04-0303 April 1985 Forwards Proprietary XN-NF-85-20(P), Mod of Exem/Pwr Flecht Based Reflood Quench & Heat Transfer Correlations for DC Cook Unit 2. Affidavit Encl.Rept Withheld (Ref 10CFR2.790) ML17321A4991985-03-21021 March 1985 Discusses 850315 Telcon Re Incorrect Expression for Multiplier on Heat Transfer Coefficient Used in TOODEE2, Which Affected LOCA-ECCS Analyses for Several Pwrs.Analyses Redone ML17334A8181984-08-22022 August 1984 Forwards Nonproprietary XN-NF-84-25(NP), Mechanical Design Rept Suppl for DC Cook Unit 1 Extended Burnup Fuel Assemblies ML17334A8121984-08-21021 August 1984 Forwards XN-NF-83-61, DC Cook Unit 1 LOCA-ECCS Analysis for Extended Exposure & Proprietary XN-NF-84-25(P), Mechanical Design Rept Suppl for DC Cook Unit 1 Extended Burnup Fuel Assemblies. Proprietary Rept Withheld ML17326B1311984-08-0707 August 1984 Forwards Nonproprietary Version of Rev 2 to XN-NF-84-21, DC Cook,Unit 2,Cycle 5,5% Steam Generator Tube Plugging Limiting Break Loca/Eccs Analysis, Per American Electric Power Svc Co Request ML17326B1241984-07-27027 July 1984 Forwards Proprietary Rev 2 to XN-NF-84-21 (P), DC Cook Unit 2,Cycle 5 5% Steam Generator Tube Plugging Limiting Break Loca/Eccs Analysis, Per American Electric Power Svc Co Request.Rept Withheld (Ref 10CFR2.790) ML17334A8061984-07-18018 July 1984 Forwards XN-NF-82-25(NP)(A), Generic Mechanical Design Rept,Exxon 17x17 Fuel Assembly, Per 830111 Request ML17320B0701984-05-22022 May 1984 Forwards Nonproprietary & Proprietary Rev 1 to DC Cook Unit 2 Cycle 5 5% Steam Generator Tube Plugging Limiting Break Loca/Eccs Analysis. Proprietary Rept Withheld (Ref 10CFR2.790) ML17320B0671984-05-21021 May 1984 Forwards Nonproprietary Info Re Cycle 5 LOCA ECCS Analysis, Per & Proprietary Page 1 of Response 4, Inadvertently Omitted from Ref Ltr Submittal.Proprietary Info Withheld (Ref 10CFR2.790) ML17320B0311984-05-0707 May 1984 Forwards Proprietary Addl Info Re DC Cook Unit 2 Cycle 5 LOCA ECCS Analysis,Per .Info Withheld (Ref 10CFR2.790) ML17320A9631984-03-16016 March 1984 Forwards Rev 1 to XN-NF-83-85,Suppl 1, DC Cook Unit 2, Cycle 5 Sar ML20081C9821984-03-13013 March 1984 Forwards Nonproprietary Version of XN-NF-82-90(NP),Suppl 1, Potential Radiological Consequences of Incidents Involving High Exposure Fuel, Which Supports Application for Tech Spec Changes for Cycle 5 Reload ML17334A5161984-03-0202 March 1984 Forwards Proprietary & Nonproprietary Info Supporting Application for Tech Spec Changes for Cycle 5 Reload. Proprietary Repts Withheld ML17334A4871983-11-0404 November 1983 Forwards XN-NF-621(NP)(A) Rev 1 Exxon Nuclear DNB Correlation for PWR Fuel Designs ML17320A8441983-10-11011 October 1983 Forwards Affidavit AW-78-23 & RB Stout 831011 Affidavit Requesting Withholding XN-NF-739(P), Seismic Evaluation of Exxon Nuclear 17x17 Assemblies in Westinghouse Pwrs ML17320A6921983-09-16016 September 1983 Requests Expedited Review of Creep Collapse Criteria Presented in XN-NF-82-06(P) Qualification of Exxon Nuclear Fuel for Extended Burnup. to Support Cycle 5 Operation, Approval of Creep Collapse by 831231 Requested ML17320A6751983-08-24024 August 1983 Authorizes Use of Encl Affidavit AW-78-23 Re Request for Withholding Proprietary Info Concerning Optimized Fuel Assemblies Transition Reload Review ML17320A3581983-02-0303 February 1983 Requests Generic Review of PTS-PWR2 Plant Transient Simulator Code Be Reactivated,Due to Difficulty Encountered in DC Cook Unit 2 Cycle 4 Review ML17320A2831983-01-0404 January 1983 Forwards Proprietary Responses to Issues Raised by NRC at 821202 Meeting W/American Electric Power Re Cycle 4 Operation.Affidavit Supporting Withholding from Public Disclosure Encl.Responses Withheld (Ref 10CFR2.790) ML17320A2621982-12-20020 December 1982 Forwards Table 1 Providing Reactivity Parameters for Unit 2, Consistent W/Parameters Used in FSAR Issued in Jul 1982 ML20070C7631982-12-10010 December 1982 Part 21 Rept Re Problem W/Brown Boveri Electric,Inc Low Voltage Circuit Breakers W/Solid State Trip Devices.Units from San Onofre 2 & 3 Failed Due to long-term Degradation of Filter Capacitor C205.Suspect Trip Units Should Be Tested ML17320A2331982-12-0909 December 1982 Responds to Question Re Basis for Full ECCS Flow Used in LOCA-ECCS Analysis in XN-NF-82-35,Suppl 1,per 821208 Telcon ML17334A4501982-11-24024 November 1982 Forwards Suppl 1 to XN-NF-82-35, DC Cook Unit 2 Cycle 4 Limiting Break LOCA-ECCS Analysis Using Exem/Pwr ML17319B6681982-11-24024 November 1982 Forwards DC Cook Unit 2 Potential Radiological Consequences of Incidents Involving High Exposure Fuel. Util Will Be Referencing Rept in Future Correspondence Re Cycle 4 Operation ML17319B5731982-10-0808 October 1982 Forwards Proprietary Users Manual for PTSPWR2-FORTRAN Program for Simulation of PWR Plant Transients & Suppl 1 to Manual.Affidavit Supporting Proprietary Classification of Documents Encl.Manuals Withheld (Ref 10CFR2.790) ML17319B5761982-10-0808 October 1982 Forwards Revision 1 to XN-NF-82-32(P), Plant Transient Analysis for DC Cook Unit 2 Reactor at 3,425 Mwt, Including DNB Analysis Method Changes to Support Cycle 4 Operation. Revision Withheld (Ref 10CFR2.790) ML17319B5671982-09-29029 September 1982 Forwards Proprietary Suppl 1 to XN-NF-82-37(P), DC Cook Unit 2,Cycle 4 SAR,Thermal-Hydraulic Analysis, Providing Addl Analysis of steady-state Thermal Margins During Cycle 4 Operation.Rept Withheld (Ref 10CFR2.790) 1990-06-20 |
Text
REGULA TOR INFORNATION DISTRIBUTION b TEN (R IDS)
ACCESSION NBR: 8604220217 DOC. DATE: 86/04/17 NOTARIZED:, NO DOC/(ET FAC IL: 50-316 Donald C.
Cook Nuclear Power Plant'ni t 2.
Ind iana 0
05000316 AUTH. NANE AUTHOR AFFlLIATION 4lARD> 0. N.
Exxon Nuclear Co. i Inc.
(subs.
of Exxon Cor p. )
RECIP. NANE RECIPIENT AFFILIATION DENTONi H. R.
Office of Nuclear Reactor Regulation.
Direc tor (post 851125 BUHJECT:
Forwards proprietary responses to NRC Guestions 4
8( 5 re Rev 1 to XN-NF-85-64(P) "Plant Transient Analysis for DC Cook Unit 2 w/10/ Steam Generator Tube Plugging
Response
withheld (ref 10CFR2. 790).
DISTRIBUTION CODE:
PAOID COPIEB RECEIVED: LTR Q ENCL J BITE:
TITLE: Proprietary Review Distribution-Operating Reactor NOTES:
RECIPIENT ID CODE/MANE PLJR-A PD4 PD 05 COP IEB RECIPIENT LTTR ENCL jD CODE/NANE 5
5 4'3 5
COP IEB LTTR ENCL INTERNAL ELD/HDB3 R('N3 EXTERNAL: 24X NRC PDR 0
1 0
LPDR 1
0 REQ FILE 1
02 1 I 1
Q TOTAL NUNBER OF COPIEB REGUIRED:
LTTR 11 ENCL 7
b
I
E@QN NUCLEAR COMPANY, INC.
2101 HORN RAPIDS ROAD. PO BOX 130, RLCHlAND,IMA99352 (509) 375.8100 TElEX: 15.2878 April 17, 1986 GNW:055:86 Donald C.
Cook Nuclear Plant No.
2 Docket No. 50-316 License No.
DPR-74 TRANSMITTAL OF RESPONSES TO NRC QUESTIONS IN SUPPORT OF UNIT 2 OPERATION Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
SUBJECT:
Transmittal of Responses to NRC guestions Ref.:
(1)
XN-NF-85-64(P),
Rev.
1, "Plant Transient Analysis for D.C.
Cook Unit 2 with 10% Steam Generator Tube Plugging,"
Exxon Nuclear
- Company, March 1986 (2)
- Letter, R.A. Copeland (ENC) to H.R.
Denton (NRC),
dated November 15, 1985; RAC:070:85 Enclosed are five copies of responses to Numbers 4
and 5
of the NRC questions transmitted April 3, 1986 to American Electric Power Service Corporation (AEPSC) concerning the Reference 1 topical report.
This topical report provides support for Cycle 6 operation of the D.C.
Cook Unit 2 nuclear power plant.
These questions were previously discussed in an April 10, 1986 telephone conversation with
- AEPSC, NRC and ENC personnel.
NRC personnel indicated that the verbal responses to the remaining April 3 questions were acceptable.
At the request of AEPSC, these responses are being transmitted directly to the NRC by Exxon Nuclear.
Information contained in the responses is proprietary to Exxon Nuclear Company.
The Affidavit provided with the Reference 2
letter provides the necessary information to allow the withholding of the responses from public disclosure as required by 10 CFR 2.790(b).
8b04220217 Sb0417 PDR ADOCK 050 P
ANAFFIUATEOF EXXONCORPORATION yl
If you have any questions regarding this transmittal, please contact Hr. James B. Feinstein of AEPSC at (614) 233-2040.
gf Enclosure cc:
Hr.
D. L. Wigginton (NRC)(w/enc.)
Hr.
W. Jensen (NRC)(w/enc.)
Hr. H.
P. Alexich (AEPSC)
G.
N. Ward, Hanager Reload Licensing