Similar Documents at Cook |
---|
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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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
[Table view] |
Text
Nuclear Technology Olvision Westinghouse Water Reactor Electric Corporation Divisions Box 355 Pittsburgh Pennsylvania15230 August 9, 1985 CAW-85-053 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comnd.ssion Washington, D.C. 20555
Subject:
Westin@ouse Safety Evaluation for RTD Operability and Cross Calibration
Dear Mr. Denton:
The proprietary material for which withholding is being requested in the reference letter by the American Electric Power Service Corporation for the D.
C. Cook Plant Unit 1 is further identified in an affidavit signed by the caner of the proprietary information, Westinghouse Electric Corporation. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Coranission and addresses with specificity the considerations listed in paragraph (b)(4) of 10CFR Section 2.790 of the Comtission's regulations.
The proprietary material for which withholding is being requested is of the same technical type as that proprietary material previously sutmitted with Application for Withholding AW-76-60.
Accordingly, this letter authorizes the utilization of the accompanying affidavit by American Electric Power Service Corporation.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westin@ouse affidavit should reference this letter, CAW-85-053, and should be addressed to the mdersigned.
Very truly yours, Ro ra A. Nieaemann, Nanaaer LVT/lsv egulatory & Legislative Affairs Enclosure(s) e cc: E. C. Shcmaker, Esq.
Office of the Executive Legal Director, NRC i BanBAaomrs seo8i'm P, .:.;ADocx
'. o5ooosq pDR s
0 PROPRIETARY INFORMATION NOTICE TRANSYETTED HEREWITH ARE PROPRIETARY AND/OR NON-PROPRIETARY VERSIONS OF DOCUMENTS FURNISHED TO THE NRC XN CONNECTION WITH KQUESTS FOR GEhERZC AND/OR KANT SPECIFIC REVIM AND APPROVAL.
IN ORDER TO CONFORM TO THE REQVZRBKNTS OF 10CFR2.790 OF THE COSQSSION'S REGULATIONS CONCERNING THE PROTECTION OF PROPRIETARY INFORMATION SO SUBY~~ED TO THE NRCq %E ZNFORNTZON WHICH ZS PROPRIETARY IN %E PROPRIETARY VERSIONS ZS COHTAZHED WITHIN BRACKETS AND WHERE THE PROPRIETARY INFOiPATZON HAS BEEN DELETED XN THE NON-PROPRIETARY VERSIONS M.Y THE BRACKETS REMAIN~ %E
~imNTZOH THAT WAS CONTAINED WITHIN %E BRACKETS IN &E PROPRIETARY VEPSZONS HAVING BEEN DELETED. THE JUSTIFICATION FOR Q.AIMING RiE XNFORYdlTZON SO DESIGNATED AS PROPRIETARY XS INDICATED ZH BOIH VERSIONS BY MEANS OF LCMER CASE LEiiERS (a) THROUGH (g) CONTAINED WITHIN PARENTHESES LOCATED AS A SUPERSCRIPT IS ~
DZATELY FOLL%'ZNG THE BRACKETS EHQ.OSZNG EACH XTEM OF XNFOtuATZON BEING ZDEHTZFIED AS PROPRIETARY OR IN THE e,RGZN OPPOSITE SUCH INFORMATION. THESE LCVER CASE LETTERS REFER TO %E TYPES OF ZNFOiu'ATION WESTINGHOUSE CUSKi'DRILY HOLDS IN CONFIDENCE IDENTIFIED ZN SECTIONS (¹)(if)(a) through (¹)(ii)(E) OF THE AFFZDNZT ACCOMPANYING THIS TRANSYZIYAL PURSUANT K 10CFR2.790(b)(1) ~
..e AW-76-60 AFFIDAVIT ~
CON~i0l>WEALTH OF PENNSYLVANIA:
COUNTY OF ALLEGHENY's Before me, the undersigned authority, personally appeared Robert A. Miesemann, who, being by me duly sworn according to law, de-poses and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation ("Westinghouse" ) and that the aver-ments of fact set forth in this Affidavit are true and correct to the best of his I;nowledge, information, and belief Robert A. Miesemann, flanager Licensing Programs Sworn to and subscribe3 before me this ~ 'ay of d~'ink'& 1976.
gg fi,86' lNrWe~
Notary Public
~ ~
AM-76-60 (1) 1 am Manager, Ucensing Programs, in the Pressurized Mater" Reactor Systems Division, of hestinghouse Electric Corporation and as such, 1 have been specifically delegated the function of reviewing the proprietary information sought to b withheld from public dis-closure in connection with nuclear power plant licensing or rule-inaking proceedings, and am authorized to apply for its withholding on behalf of the Mestinghouse Mater Reactor Divisions.
(2) ? 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 Mestinghouse application for withholdirig ac-companying this Affidavit.
(3) I have persona'i tnoxledga of the criteria and procedures utilized by 1'estinghouse Nuclear Energy Systems in designating information
~
as a trade secret, privileged or as confiden ial comaercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the in-formation sought to be withheld from public disclosure should be
. withheld.
(i) The information sought to be withheld from public disclosure is. owned and has been held in confidence by Mestinghouse.
(ii) The information is of a type customarily held in confidence by Restinghouse and not customarily disclosed to the public.
Mestinghouse has a rational basis for determining the types o, information customarily held in confidence by it and, in that
. connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The ap-plication of that system and the substance of that system constitutes k'estinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types', the release of which might result in the loss of an existing or potential com-petitive advantag , as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.)
where prevention of its u:e by any of lestinghouse'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, tool, method, etc.), the application of which data secures a 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, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price in,ormation, production cap-acities, budget levels. or commercial trategies of Mestinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future hest-inghouse or customer funded development plans and pro-grams of potential commercial value to Hestinghouse.
{ f) It contains pe tentabl e ideas, for which patent pro-tection may be desirable.
(g) It is not the property of Mestinghouse, but must be treated as proprietary by stinghouse according to 1
agreements with the owner.
There are sound policy reasons behind the h'estinghouse system which include the following:
(a) The use of such information by llestinghouse gives Mestinghouse a competitive advantage over its com-petitors. It is, therefore, withheld from disclosure to protect the I/estinghouse competitive position.
e AM-76"60 (b) It is information which is marketable in many ways.
The extent to 'which such information is available to competitors 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 competitive 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 competitors acquire components of proprietary infor-mation, any one component may be the key to the entire puzzle, thereby depriving Mestinghouse of a competitive advantage.
(e)
'f Unrestricted disclosure would jeopardize the position prominence of Mestinghouse in the world market, and thereby give a market advantage to the competition in those countries.
(f) The Mestinghouse capacity to invest corporate assets in research and development depends upon the success
- - in obtaining and maintaining a competitive advantage.
(iii) The information is being transmitted to the Conmission in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Comission.
(iv) The information is not available in public sources to the best of our knowledge and belief.
(v) The proprietary information sought to be withheld in this sub-mittal is that which is appropriately marked in the attach-ment to Westinghouse letter number NS-CE-1296, Eicheldinger to Stolz, dated December 1, 1976, concerning information relating-to HRC review of MChP-G567-P and MCAP-856S entitled, "Improved Thermal Design Procedure," definirg the sensitivity of DhB ratio to various core parameters. The letter and attachment are being submitted in response to the HRC request at the October 29, 1976 NRC/Westinghouse meeting.
This information enables Westinghouse to:
(a) Justify the Westinghouse design.
(b) Assist its customers to obtain licenses.
(c) Neet warranties.
(d) Provide greater operational flexibility to customers assuring them of safe and reliable operation.
(e) Justify increased power capability or operating margin for plants while assuring safe and reliable operation.
~ .
&7M AM-76-60 (f) Optim'ize reactor design and performance while maintaining a high level of fuel integrity.
Further, the information gained fro. the improved thermal design procedure is of significant commercial value as follows:
(a) Mestinghouse uses the information to perform and justify analyses which are sold to customers.
(b) Westinghouse sells analysis services based upon the experience gained and the methods developed..
Public disclosure of this information concerning design pro-cedures is likely to cause substantial harm to the competitive position of )Jestinghouse because competitors could utilize this information to assess and justify their own designs without commensurate expense.
The parametric analyses p rformed and their evaluation represent
~
a considerable amount of highly qualified development effort.
This work was contingent upon a design method development pro-gram which has been underway during the past two years.
Altogether, a substantial amount of money and effort has been expended by lJestinghouse which could only be duplicated by a competitor if he were to invest similar sums of money and pro-vided he had the appropriate talent available.
Further the deponent sayeth not.