ML17326B400
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| ML17326B400 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/22/1988 |
| From: | Copeland R SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RAC:048:88, RAC:48:88, NUDOCS 8808020374 | |
| Download: ML17326B400 (3) | |
Similar Documents at Cook | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999
[Table view]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Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted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 Category:INCOMING CORRESPONDENCE MONTHYEARML17335A5511999-10-0707 October 1999
[Table view]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 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) 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 |
Contents
Text
AC CE& RATED Dl- BUTI ON DE~~ 'lON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8808020374 DOC.DATE: 88/07/22 NOTARIZED: NO DOCKET FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION COPELAND,R.A. Advanced Nuclear Fuels Corp. (formerly Exxon Nuclear Co., I, RECIP-NAME RECIPIENT AFFILIATION Office of Nuclear Reactor Regulation, Director (Post 870411 R
SUBJECT:
Forwards listed topical repts,providing fuel storage thermal hydraulic & criticality analysis results. I'acility DISTRIBUTION CODE: T010D COPIES RECEIVED:LTR I ENCL C SIZE .D TITLE: Non-Proprietary Topical Report S
NOTES lf h
h P
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL h INTERNAL: ARM/DAF/LFMB ASLBP NRR'ARWOOD,C NRR NORBERG,J NRR/DEST/ADE 8H NRR/DEST/ADS 7E NRR/DLPQ/QAB 10 NUDOCS-ABSTRACT OGC 15-B-18 Et~M."3ZXb 01 RES R RGN2 RGN3 RGN4 RGN5 EXTERNAL: NRC PDR NSIC R
I D
D S
TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL
I li 'L l
ADVANCESNUCLEARFUELS CORPORATION 2101 HORN RAPIDS ROAD, PO BOX 130, RICHlAND, WA 993524130 FUEL ENGINEERING &
(509) 37&8100 TELEX: 15.2878 TECHNICAL SERVICES July 22, 1988 RAC:048:88 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Fli.nt North 11555 Rockville Pike Rockville, MD 20852
Dear Sirs:
Subject:
Transmittal of the Donald C. Cook Unit 2 Fuel Stol age Facility Thermal Hydraulic and Criticality Analysis Results Ref.: Donald C. Cook Nuclear Plant No. 2; Docket No. 50-316; License No.
DPR-74 (1) ANF-88-09, "Thermal-Hydraulic Analysis of the D.C. Cook Spent Fuel Pool" (2) ANF-88-112, "Criticality Safety Analysis D.C. Cook Spent Fuel Storage Racks with 15x15 and 17x17 Fuel Enrichments up to 5.0 Percent (3) ANF-88-057, "Final Report Criticality Safety Analysis D.C.
Cook New Fuel Storage Vault with 5.0% Enriched 17x17 Fuel" Enclosed are five (5) copies of each of the Advanced Nuclear Fuels Corporation (ANF) topical reports listed above. These topicals report the results from the criticality and thermal hydraulic analyses that support the storage of 17X17 and 15X15 fuel assemblies with burnups to 50.0 GWD/MT and initial enrichment levels up to 5.0% U-235 in the spent fuel storage facility at D.C.
Cook Unit 2 (ANF-88-09 and ANF-88-112). The third document (ANF-88-057) reports results from a criticality analysis that supports the storage of 17X17 fuel assemblies containing an enrichment level up to 5.0% U-235 in the new fuel storage vault at D.C. Cook Unit 2. At the request of American Electric Power Service Company (AEPSC), these reports are being transmitted directly by ANF.
If you have any questions regarding this transmittal, please contact Mr. Tom Georgantis of AEP at (614) 223-2059.
Sincerely, R.A. Copeland Manager, Reload Licensing gf cc: Mr. T. Georgantis (AEPSC)
Mr. John Stang (NRC) (w/Enclosures)
(J SSQSQ20374 PDR SS0722 pl<'~~
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ADOCK 050003ih PDC
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