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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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:VENDOR/MANUFACTURER TO NRC
MONTHYEARML17328A3091990-06-20020 June 1990 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) 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) 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 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 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) ML17320B0671984-05-21021 May 1984 Forwards Nonproprietary Info Re Cycle 5 LOCA ECCS Analysis, Per 840507 Ltr & 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 840302 Ltr.Info Withheld (Ref 10CFR2.790) 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 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) ML17319B4091982-06-30030 June 1982 Forwards XN-NF-82-37, DC Cook Unit 2,Cycle 4 SAR, XN-NF-82-35, DC Cook Unit 2 LOCA ECCS Analysis Using Exem/ PWR Large Break Results, & XN-NF-82-32(P), Plant Transient Analysis... XN-NF-82-32(P) Withheld (Ref 10CFR2.790) ML20038C0241981-10-29029 October 1981 Requests Withholding of Proprietary Version of Clasix Computer Program for Analysis of Reactor Plant Containment Response to Hydrogen Release & Deflagration, (Ref 10CFR2.790) ML17331A8011981-07-23023 July 1981 Forwards Affidavit for Withholding Proprietary Facility Conceptual Design Description for Technical Support Ctr & Emergency Operations Facilities. Affidavit Corrects CAW-80-75 Submitted 800613 ML19340C1081980-11-0404 November 1980 Forwards Corrections to XN-NF-77-57,Suppl 1,Exxon Nuclear Power Distribution Control for Pwrs:Phase 2, June 1979. Revisions Do Not Change Intent of Related PDC-2 Procedure But Clarify Requirements ML17317B5371979-09-11011 September 1979 Forwards Proprietary & Nonproprietary Versions of XN-NS-TP-009, Fuel Storage Racks Corrosion Program, Boral-Stainless Steel. Proprietary Version Withheld (Ref 10CFR2.790) ML17317B3001979-06-26026 June 1979 Advises That Westdyn Computer Code Analysis of Benchmark Problems Will Be Completed by 790731 1990-06-20
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ATTACH(TNT 2
.Q Westinghouse Water Reactor Huctear Technology Olvlslon Electric Corporation Divisions Box 355 Pittsburgh Pennsylvania 15230 October 11, 1983 CAW-83-87 Mr. Harold Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC 'ISCLOSURE
Reference:
Indiana and Michigan Electric Company letter to U.S. NRC, Alexich to Denton, dated October, 1983 The proprietary material transmitted by the reference letter for which with-holding is being requested by Indiana and Michigan Electric Company ( I and ME) is of the same type as the proprietary material previously submitted in
'connection with NRC Staff reviews of WCAP-9401/9402 and WCAP-9500. A pre-vious Application for Withholding, AW-78-23, was accompanied by a non-proprietary Affidavit signed by the owner of the proprietary information, Westinghouse Electric Corporation. The proprietary material is being submitted in support of transition reload analysis associated with the I and ME Donald C. Cook Nuclear Plant Unit No. 2.
Accordingly, this letter authorizes the use of the previously furnished affidavit, a copy of which is attached.
Correspondence with respect tol:the proprietary aspects of this application for withholding or the Westinghouse a'ffidavit should reference CAW-83-87 and should be addressed to the undersigned.
Very truly yours, bert A. Wiesemann, Manager Regulatory 8 Legislative Affairs MMS:pj Attachment cc: E. C. Shomaker, Esq.
Office of the Executive Legal Director, NRC 83iii80268 050003ih PDR ADOCK 83iiii P PDR
AM-78-23 AFFIDAVIT COHNONMEALTH OF PENNSYLYANIA:
COUNTY OF ALLEGHENY:
Before me, the undersigned authority, per sonally appeared Robert A. Miesemann, who, being by;e duly sworn according to law,:
deposes and says that he is authorized to execute this Affidavit on behalf of Mestinghouse E1ectric Corporation ("Mestinghouse") and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
Robert A. Miesemann, Hanager Licensing Programs Sworn to and subscribed before,me this. - " day iJ
) of //c4~w 1 g78.
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Notary Public
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N-78-23 (1) I am Manager, Licensing Programs, in the Pressurized Mater Reactor Systems Division, of Aestinghouse Electric Corporation and as such,'
have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure fn connection with nuclear power plant. licensing or rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Mater Reactor Divisions.
(2) I am making this affidavit in conformance with the provisions of 10 CFR Section 2.'790 of the Commission s regulations and in con-
)unction with the Westinghouse application for withholding accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Mestinghouse Nuclear Energy Systems in designating information as a trade secret, privileged or a's confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Conmission's rogulations, the following is furnished for consideration by the Commission in. determining whether the information sought to be withheld from public disclosure should be withhe1d.
(i) The information sought to be withheld from public disclosure
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is owned and has been held in confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public.
Westingt ouse has a rational basis for determining the types of information customarily he1d in confidence by it and, in that connection, utilizes a system to determine when and
N-78-23 whether to hold certain types of information in confidence.
The application of that system and the substance of that system constitutes Mestinghouse policy and provides the rational basis required.
Criteria and Standards Utilized In determining whether information in a document or report is proprietary, the following criteria and standards are util ized by Mestinghouse. Information is'roprietary if any one of the
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following are met:
(a) The information reveals the distinguishing aspects of .
a process (or component, structure, tool, method, etc.)
where prevention of its use by any. of Mestinghouse's competitors without license from Mestinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, too<,
method, etc .), the application of which data secures a
'I competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, mar ufacture, shipment, installation, assurance of quality, or licensing of a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or comnercial strategies of Mestinghouse, its customers or suppliers.
4-(e) It reveals aspects of past, present, or future Mesting-house or customer funded development plans and programs of potential coamercial value to Mestinghouse.
(f) It contains patentable ideas, for which patent protection Nay be desirable.
(g) It is not the property of Westinghouse, but must be treated .as proprietary by Westinghouse according to agreements with the owner.
(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.
(iv) The information is not avai1able in public sources to the best
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of our knowledge and belief.
(v) The proprietary information sought to be withheld in this submittal are the copies 'of slides uti1ized by Westinghouse in its presentation to the NRC. at the March 21, 1978 meeting concerning the Westinghouse optimized fuel assembly. The letter and the copies of slides are being submitted in pre-1iminary form .to the Cormission for revie~ and comment on the Westinghouse optimized fuel assenbly in advance of a formal suhnittal for NRC approval.
Public disclosure of this information is likely to cause substantial harm to the competitive position of Westinghouse as it would reveal the description of the approved design, the comparison of the improved design with the standard design, the nature of the test conducted, the test conditions, the test results and the conclusions of the tes ing program,
0-78-23 all of which is recognized by the Staff to be of competitive value and because of the large amount of effort and money expended by Mestinghouse over a period of several years in carrying out this particular development program. Further, it would enable competitors to use the information for comnercial purposes and also to meet, NRC req'uirements for licensing documentation, each without purchasing the right from Mesting-house to use the. information.
Information regarding its development programs is valuable to Mestinghouse because:
(a) Information resulting from its development programs gives Mestinghouse a competitive advantage over its competitors.
It is, therefore, withheld from disclosure to protect the Mestinghouse competi tive position.
l1 (b) It is information which is marketable in many ways. The extent to which such information is available to compet-itors diminishes the Mestinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Mestinghouse at a com-petitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If com-petitors acquire components of proprietary information, any one component may be the kev to t'Oe qntirp p': z4e thereby depriving Mestinghouse of a competitive advantage.
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~ AM-78-23 (e) The Mestinghouse capacity to invest corporate assets in
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research and development depends upon the success in obtaining and maintaining a competitive advantage.
Being an innovative concept; this information might not be discovered by the competitors of Mestinghouse independently. 'o duplicate this infor-mation, competitors would first have to be similarly inspired and would then have to expend an effort similar to that of Mestinghouse to develop the design.
Further the deponent sayeth not.
r 'ACHHENT 3 AFF IDAV IT STATE OF Washington )
ss.
COUNTY OF Benton )
I, Richard B. Stout, being duly sworn. hereby say and de-pose:
- 1. I am Manager, Licensing and Safety Engineering, for Exxon Nuclear Company, Inc. ("ENC"). and as such I am authorized to execute this Affidavit.
- 2. I am familiar with ENC's detailed document control system and policies which govern the protection and control of information.
- 3. I am familiar with the document XN-NF-739(P) entitled "Seismic Evaluation of Exxon Nuclear 17x17 Assemblies in Westinghouse PWR's", referred to as "Document". Information contained in this Document has been classified by ENC as proprietary in accordance with the control system and policies established by ENC for the control and protection of information.
- 4. The Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by ENC and not made available to the public. Based on my experience, I am aware that other. companies regard information of the kind contained in the Document.
- 5. The Document has been made available to American Electric Power Service Corporation in confidence, with the request that the information contained in the Document not be disclosed or divulged.
- 6. The Document contains information which is vital to a com-petitive advantage of ENC and would be helpful to competitors of ENC when competing with ENC.
- 7. The information contained in the Document is considered to be proprietary by ENC because it reveals certain distinguishing aspects of PWR seismic analysis methods which secure competitive economic advantage to ENC for fuel design optimization and improved marketability, and includes information utilized by ENC in its business which affords ENC an opportunity to obtain a competitive advantage over its competitors who do not or may not know or use the information contained in the Document.
- 8. The disclosure of the proprietary information contained in the Document to a competitor would permit the competitor to reduce its expenditure of money and manpower and to improve its competitive position by giving it extremely valuable insights into PWR seismic analysis methods, and would result in substantial harm to the competitive position of ENC.
- 9. The Document contains proprietary information which is held in confidence by ENC and is not available in public sources.
- 10. In accordance with ENC's policies governing the protection and control of information, proprietary information contained in the Document has been made available, on a limited basis, to others outside ENC only as required and under suitable agreement providing for non-disclosure and limited use of the information.
- 11. ENC policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 12. This Document provides information which reveals PWR seismic analysis methods developed by ENC over the past several years. ENC has invested millions of dollars and many man-years of effort in developing the analysis methods revealed in the Document. Assuming a competitor had available the same background data and incentives as ENC, the competitor might, at a minimum, develop the information for the same expenditure of manpower and money as ENC.
- 13. Based on my experience in the industry, I do not believe that the background data and incentives of ENC's competitors are suf-ficiently similar to the corresponding background data and incentives of ENC to reasonably expect such competitors would be in a position to duplicate ENC's proprietary information contined in the Documents.
THAT the statements made hereinabove are, to the best of my knowledge, information, and belief, truthful and complete.
FURTHER AFFIANT SAYETH NOT ~
SWORN TO AND SUBSCRIBED before me this /j day of
, 19+
NOTARY PUBLIC
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