Similar Documents at Cook |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17335A5691999-10-21021 October 1999 Forwards Insp Repts 50-315/99-25 & 50-316/99-25 on 990816- 20.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML17335A5681999-10-19019 October 1999 Confirms Plans to Conduct Meeting with American Electric Power & DC Cook Plant Mgt to Discuss Status of Case Specific Checklist Items,Rev to Restart Plan,Operations Dept Readiness for Restart & Performance Assurance Audit Status ML20217J4721999-10-15015 October 1999 Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21 IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20217D9241999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML17335A5541999-10-0101 October 1999 Submits Summary of 990712 Technical Meeting Re Containment Sump Issues Concerning Restart of Plant,Units 1 & 2.List of Attendees & Matl Used in Presentation Encl ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17335A5491999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix Encl ML17335A5391999-09-27027 September 1999 Forwards Copy of Preliminary Accident Sequence Precursor Analysis of Operational Condition Which Was Discovered at Plant,Units 1 & 2 on 980715,for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr ML17326A1601999-09-27027 September 1999 Forwards Insp Repts 50-315/99-16 & 50-316/99-16 on 990719-23 & 0802-06.Violations Re Failure to Maintain Exam Matl Security & Maintain Licensed Operator Biennial Medical Exams Identified & Being Treated as Noncited Violations NUREG-1706, Discusses Licensee & Suppl Which Responded to GL 98-01, Y2K Readiness of Computer Sys at Npps. Concluded That No Nuclear Plants with Y2K Issues Involving Safety Sys Identified1999-09-23023 September 1999 Discusses Licensee & Suppl Which Responded to GL 98-01, Y2K Readiness of Computer Sys at Npps. Concluded That No Nuclear Plants with Y2K Issues Involving Safety Sys Identified ML17326A1701999-09-23023 September 1999 Informs That Proposed Rev to Applicable Specifications to Containment Sys TS Bases 3/4.6.1.4 & 3/4.6.1.5,submitted in ,Withdrawn Per 990920 Telcon ML17326A1651999-09-22022 September 1999 Forwards Insp Repts 50-315/99-17 & 50-316/99-17 on 990717- 0825.One Violation Identified & of Concern Because Inspectors Identified Failure to Restore Compliance for Previously Identified Violation of NRC Requirements ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1551999-09-17017 September 1999 Transmits Updated Case Specific Checklist for DC Cook Nuclear Power Plant Which Identifies Specific Issues Requiring Resolution Prior to Restart of Cook Plant ML17326A1361999-09-16016 September 1999 Forwards Insp Repts 50-315/99-07 & 50-316/99-07 on 990712-30 & 0816.Seven Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1391999-09-15015 September 1999 Forwards Insp Repts 50-315/99-18 & 50-316/99-18 on 990726-30 & 0816 ML17326A1151999-09-0808 September 1999 Responds to W Nelson 990614 & 0726 Ltrs Re Schedule for Initial Licensing Exam for Operator License Application. Exam Scheduled for Wks of 010305 & 12 & 0423 & 30 ML17326A1031999-08-25025 August 1999 Forwards Notice of Consideration of Issuance of Amend to FOL Re Request for License Amend Dtd 980914.Amends Would Change Runout Limits for SI Pump to 675 Gallons Per Minute Not Exceeding 700 Gallons Per Minute for Both Units 1 & 2 ML17326A1021999-08-25025 August 1999 Informs That on 990819,NRC Held Public Meeting at Region III Ofc in Lisle,Il to Discuss Status of Facility Restart & NRC Manual Chapter 0350 Oversight Insp ML17326A0971999-08-25025 August 1999 Provides Summary of 990615 Public Meeting at DC Cook NPP in Berrien County,Michigan Re Technical Issues Concerning Restart of DC Cook Npp,Units 1 & 2.List of Meeting Attendees & Copy of Slides Used by Licensee Encl ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0831999-08-13013 August 1999 Forwards Insp Repts 50-315/99-15 & 50-316/99-15 on 990528-0716.No Violations Noted.Insp Consisted of Selective Examinations of Procedures & Representative Records, Interviews with Personnel & Observations of Activities ML17326A0881999-08-12012 August 1999 Forwards Draft Preliminary Results of Analysis of Risk Significance of Issues That Were Identified at DC Cook NPP, Units 1 & 2,between Aug 1997 & Jan 1999 ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, ML17326A0781999-08-0909 August 1999 Forwards SE Accepting 980403 Request for Approval Under Provisions of 10CFR50.55a(a)(3),to Use ASME B&PV Code, Section Ix,Code Cases 2142-1 & 2143-1 for Fabrication & Installation of Unit 1 Replacement SG Lower Assemblies ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca 05000315/LER-1998-029-01, Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed1999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46 ML17326A0701999-07-27027 July 1999 Summarizes 990715 Meeting Conducted in Bridgman,Mi Re Ongoing Transition from Discovery Phase of Restart Plan to Implementation Phase.List of Meeting Attendees Encl ML17326A0671999-07-26026 July 1999 Forwards Summary of 990616 Meeting at DC Cook Nuclear Plant in Berrien County,Mi Re Core Offload for Both Units.List of Attendees & Copy of Briefing Sheets Used by Licensee Also Encl ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE 05000315/LER-1998-014-03, Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed1999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0571999-07-16016 July 1999 Submits Summary of 990615 Public Meeting with Util in Berrien County,Mi Re Restart of Units at DC Cook,In Accordance with NRC Insp Manual Chapter 0350.List of Attendees & Slide Presentation Encl ML17326A0541999-07-15015 July 1999 Forwards Summary of 990324 Meeting with External 0350 Restart Panel to Discuss Status of Plant Restart Activities. List of Attendees & Slides Used by Licensee Encl ML17326A0551999-07-15015 July 1999 Fowards Summary of 990324 Technical Meeting Re Technical Issues Related to Restart of Plant,Units 1 & 2.List of Attendees & Slides Used by Licensee Encl ML17326A0561999-07-14014 July 1999 Forwards Summary of 990415 Meeting Re Status of Cook Nuclear Plant Restart Activities.List of Attendees & Matl Used in Presentation Enclosed ML17326A0441999-07-14014 July 1999 Ack Receipt of Withdrawing Request for Relief. Staff Actions for TAC M98339 Completed ML17326A0451999-07-12012 July 1999 Forwards Insp Repts 50-315/99-13 & 50-316/99-13 on 990517-0611.One Violation Noted & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy. Violation Re Failure to Perform Required Maint on Equipment ML17326A0371999-07-0606 July 1999 Discusses Meeting Conducted at Region III Senior Reactor Analysts at Plant Re Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee 05000315/LER-1999-004-01, Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed1999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML20196K5961999-06-30030 June 1999 Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021 ML17326A0271999-06-30030 June 1999 Confirms Plans to Conduct Meeting with Util & DC Cook Plant Management to Discuss Technical Issues at Plant on 990715 in Training Center at Plant ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl 1999-09-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML17335A5691999-10-21021 October 1999 Forwards Insp Repts 50-315/99-25 & 50-316/99-25 on 990816- 20.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML17335A5681999-10-19019 October 1999 Confirms Plans to Conduct Meeting with American Electric Power & DC Cook Plant Mgt to Discuss Status of Case Specific Checklist Items,Rev to Restart Plan,Operations Dept Readiness for Restart & Performance Assurance Audit Status ML20217J4721999-10-15015 October 1999 Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21 IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20217D9241999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML17335A5541999-10-0101 October 1999 Submits Summary of 990712 Technical Meeting Re Containment Sump Issues Concerning Restart of Plant,Units 1 & 2.List of Attendees & Matl Used in Presentation Encl ML17335A5491999-09-29029 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix Encl ML17326A1601999-09-27027 September 1999 Forwards Insp Repts 50-315/99-16 & 50-316/99-16 on 990719-23 & 0802-06.Violations Re Failure to Maintain Exam Matl Security & Maintain Licensed Operator Biennial Medical Exams Identified & Being Treated as Noncited Violations ML17335A5391999-09-27027 September 1999 Forwards Copy of Preliminary Accident Sequence Precursor Analysis of Operational Condition Which Was Discovered at Plant,Units 1 & 2 on 980715,for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr ML17326A1701999-09-23023 September 1999 Informs That Proposed Rev to Applicable Specifications to Containment Sys TS Bases 3/4.6.1.4 & 3/4.6.1.5,submitted in ,Withdrawn Per 990920 Telcon NUREG-1706, Discusses Licensee & Suppl Which Responded to GL 98-01, Y2K Readiness of Computer Sys at Npps. Concluded That No Nuclear Plants with Y2K Issues Involving Safety Sys Identified1999-09-23023 September 1999 Discusses Licensee & Suppl Which Responded to GL 98-01, Y2K Readiness of Computer Sys at Npps. Concluded That No Nuclear Plants with Y2K Issues Involving Safety Sys Identified ML17326A1651999-09-22022 September 1999 Forwards Insp Repts 50-315/99-17 & 50-316/99-17 on 990717- 0825.One Violation Identified & of Concern Because Inspectors Identified Failure to Restore Compliance for Previously Identified Violation of NRC Requirements ML17326A1551999-09-17017 September 1999 Transmits Updated Case Specific Checklist for DC Cook Nuclear Power Plant Which Identifies Specific Issues Requiring Resolution Prior to Restart of Cook Plant ML17326A1361999-09-16016 September 1999 Forwards Insp Repts 50-315/99-07 & 50-316/99-07 on 990712-30 & 0816.Seven Violations of NRC Requirements Occurred & Being Treated as Ncvs,Consistent with App C of Enforcement Policy ML17326A1391999-09-15015 September 1999 Forwards Insp Repts 50-315/99-18 & 50-316/99-18 on 990726-30 & 0816 ML17326A1151999-09-0808 September 1999 Responds to W Nelson 990614 & 0726 Ltrs Re Schedule for Initial Licensing Exam for Operator License Application. Exam Scheduled for Wks of 010305 & 12 & 0423 & 30 ML17326A1031999-08-25025 August 1999 Forwards Notice of Consideration of Issuance of Amend to FOL Re Request for License Amend Dtd 980914.Amends Would Change Runout Limits for SI Pump to 675 Gallons Per Minute Not Exceeding 700 Gallons Per Minute for Both Units 1 & 2 ML17326A1021999-08-25025 August 1999 Informs That on 990819,NRC Held Public Meeting at Region III Ofc in Lisle,Il to Discuss Status of Facility Restart & NRC Manual Chapter 0350 Oversight Insp ML17326A0971999-08-25025 August 1999 Provides Summary of 990615 Public Meeting at DC Cook NPP in Berrien County,Michigan Re Technical Issues Concerning Restart of DC Cook Npp,Units 1 & 2.List of Meeting Attendees & Copy of Slides Used by Licensee Encl ML17326A0831999-08-13013 August 1999 Forwards Insp Repts 50-315/99-15 & 50-316/99-15 on 990528-0716.No Violations Noted.Insp Consisted of Selective Examinations of Procedures & Representative Records, Interviews with Personnel & Observations of Activities ML17326A0881999-08-12012 August 1999 Forwards Draft Preliminary Results of Analysis of Risk Significance of Issues That Were Identified at DC Cook NPP, Units 1 & 2,between Aug 1997 & Jan 1999 ML17326A0781999-08-0909 August 1999 Forwards SE Accepting 980403 Request for Approval Under Provisions of 10CFR50.55a(a)(3),to Use ASME B&PV Code, Section Ix,Code Cases 2142-1 & 2143-1 for Fabrication & Installation of Unit 1 Replacement SG Lower Assemblies ML17326A0701999-07-27027 July 1999 Summarizes 990715 Meeting Conducted in Bridgman,Mi Re Ongoing Transition from Discovery Phase of Restart Plan to Implementation Phase.List of Meeting Attendees Encl ML17326A0671999-07-26026 July 1999 Forwards Summary of 990616 Meeting at DC Cook Nuclear Plant in Berrien County,Mi Re Core Offload for Both Units.List of Attendees & Copy of Briefing Sheets Used by Licensee Also Encl ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE ML17326A0571999-07-16016 July 1999 Submits Summary of 990615 Public Meeting with Util in Berrien County,Mi Re Restart of Units at DC Cook,In Accordance with NRC Insp Manual Chapter 0350.List of Attendees & Slide Presentation Encl ML17326A0551999-07-15015 July 1999 Fowards Summary of 990324 Technical Meeting Re Technical Issues Related to Restart of Plant,Units 1 & 2.List of Attendees & Slides Used by Licensee Encl ML17326A0541999-07-15015 July 1999 Forwards Summary of 990324 Meeting with External 0350 Restart Panel to Discuss Status of Plant Restart Activities. List of Attendees & Slides Used by Licensee Encl ML17326A0561999-07-14014 July 1999 Forwards Summary of 990415 Meeting Re Status of Cook Nuclear Plant Restart Activities.List of Attendees & Matl Used in Presentation Enclosed ML17326A0441999-07-14014 July 1999 Ack Receipt of Withdrawing Request for Relief. Staff Actions for TAC M98339 Completed ML17326A0451999-07-12012 July 1999 Forwards Insp Repts 50-315/99-13 & 50-316/99-13 on 990517-0611.One Violation Noted & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy. Violation Re Failure to Perform Required Maint on Equipment ML17326A0371999-07-0606 July 1999 Discusses Meeting Conducted at Region III Senior Reactor Analysts at Plant Re Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee ML17326A0271999-06-30030 June 1999 Confirms Plans to Conduct Meeting with Util & DC Cook Plant Management to Discuss Technical Issues at Plant on 990715 in Training Center at Plant ML20196K5961999-06-30030 June 1999 Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021 ML17326A0251999-06-23023 June 1999 Informs That on 990506,NRR Staff Held Public Meeting at NRC Headquarters in Rockville,Md to Discuss Hot Leg Nozzel Gap Issues in Conjunction with Restart of Plant.Viewgraphs Encl ML17326A0161999-06-18018 June 1999 Forwards Insp Repts 50-315/99-14 & 50-316/99-14 on 990517-0603.No Violations Were Identified.Insp Evaluated Control of Radiological Effluents & Offsite Dose Calculation Manual Implementation & Internal Exposure Control Program ML17326A0191999-06-18018 June 1999 Forwards Insp Repts 50-315/99-12 & 50-316/99-12 on 990503-21.No Violations Identified.Insp Was Exam of Activities Under License Re Implementation of Expanded Sys Readiness Review Program at DC Cook Units 1 & 2 ML17326A0141999-06-16016 June 1999 Forwards Request for Addl Documentation for Expanded Sys Readiness Review Validation Insp to Be Held During Week of 990621 ML17326A0081999-06-11011 June 1999 Forwards Insp Repts 50-315/99-10 & 50-316/99-10 on 990417-0527.No Violations Noted.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations ML17325B6501999-06-0808 June 1999 Informs That Nrc,Region III Will Be Conducting Expanded Sys Readiness Review Validation Insp at Facility,Starting 990712.Insp Will Be Performed IAW Various NRC Insp Procedures Including IP 93809,IP 37550 & IP 37700 ML17325B6371999-06-0303 June 1999 Forwards Insp Repts 50-315/99-06 & 50-316/99-06 on 990329- 0505.No Violations Noted.Insp Identified Number of Aspects of Overall Station Operation Where Programs & Processes Appeared to Have Weaknesses ML17325B6071999-05-26026 May 1999 Forwards Insp Repts 50-315/99-11 & 50-316/99-11 on 990426- 30.No Violations Noted.Circumstances Surrounding Two Electrical Faults Associated with Motor Control Centers 2-AM-B & 12-TSC-S Which Occurred on 990419 & 24 Reviewed ML17325B6021999-05-24024 May 1999 Submits Summary of 990520 Meeting Between NRC & Licensee in Lisle,Il Re Status of Resolution of Specific Technical Issues.List of Meeting Attendees & Handout Provided by Licensee,Encl ML17325B6141999-05-21021 May 1999 Forwards Insp Repts 50-315/99-09 & 50-316/99-09 on 990405-23.Violations Identified & Being Treated as non-cited Violations 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 ML17335A5311999-05-17017 May 1999 Ack Receipt of Licensee Which Provided Revised Expanded Sys Readiness Review Schedule.Nrc Has Rescheduled Appropriate Insp Activities to Ensure Timely Evaluation of Adequacy of Discovery Efforts ML17325B5921999-05-14014 May 1999 Forwards Insp Repts 50-315/99-04 & 50-316/99-04 on 990303-0416.Four Violations of NRC Requirements Occurred & Being Treated as non-cited Violations ML17325B5911999-05-13013 May 1999 Informs of NRR Reorganization,Effective 990328.Organization Chart Encl ML17335A5321999-05-12012 May 1999 Forwards Insp Repts 50-315/99-08 & 50-316/99-08 on 990412-16.Two Violations Identified & Being Treated as non-cited Violations.Observation of Activities Showed That Emergency Preparedness Program Was Adequately Implemented ML17325B5831999-05-0303 May 1999 Informs That Based on Results of April 1999 Senior Mgt Meeting & Revised SMM Process,Dc Cook Identified as agency-focus Plant.Nrc Commission Meeting,Open to Public Scheduled for 990506 in Rockville,Md 1999-09-08
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D,C. 2055&4001 June 23, 1999 Mr. Robert P. Powers Senior Vice President Nuclear Generation Group Indiana Michigian Power Company 500 Circle Drive Buchanan, Ml 491C7-1395
SUBJECT:
SUMMARY
OF THE MAY6, 1999, PUBLIC MEETING TO DISCUSS HOT LEG NOZZLE GAP ISSUES FOR THE RESTART OF THE DONALDC. COOK NUCLEAR PLANT
Dear Mr. Powers:
On May 6, 1999, staff of the Office of Nuclear Reactor Regulation held a public meeting at the U.S. Nuclear Regulatory Commission (NRC) headquarters in Rockville, Maryland, to discuss hot leg nozzle gap issues in conjunction with the restart of the Donald C. Cook Nuclear Plant, Units 1 and 2 (D. C. Cook). Formal presentations were made by the licensee.
A list of attendees for the meeting is provided as Enclosure 1. Enclosure 2 is a copy of the slides used by the licensee.
The public meeting with the licensee and NRC staff was designed to provide technical information to NRC staff members regarding the application of hot leg nozzle gap issues to the D. C. Cook loss-of-coolant accident (LOCA) analysis.
The licensee's presentation consisted of two parts. The first part outlined hot leg switchover subcriticality. The second part covered large break LOCA peak clad temperature (PCT) issues.
The discussion of hot leg switchover subcriticality detailed background information, problem statements, intended solutions, and an implementation strategy.
The discussion of large break LOCA PCT consisted of background information, problem statements, and solution. The two presentations were followed by an overall summary outlining the licensing strategy and expected submittal dates.
The licensee did not provide any expected dates for restart of either unit; however, the licensee did identify Unit 2 as being the lead unit for restart.
Following the conclusion of the presentation, the licensee answered questions presented by the NRC staff. NRC staff stated that the meeting was productive and well presented.
99070bOi09 990b23 PDR ADQCK 050003i5 P
PDR
R. Powers June 23, 1999 1
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC's Public Document Room.'incerely, Original signed by:
Docket Nos. 50-315, 50-316 License Nos.: DPR-58, DPR-74
Enclosures:
As stated John F. Stang, Sr. Project Manager, Section 1
Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation ccw/encls:
See next page DISTRIBUTION Hard Copy (w/ encls):
J. Stang Docket File K. Leigh PUBLIC OGC ACRS LPD31 RF E-mail:
S. Collins B. Sheron S. Black W. Lyon F. Orr G. Grant R. Zimmerman J. Zwolinski C. Craig E. Weiss T. Hiltz C. Sochor p/ S)
DOCUMENT NAME: G:>PDIII-1>DCCOOKFDc0506.wpd
- See previous concurrence OFFICE NAME DATE PGEB KLeigh*
6/23/99 LA LPD3 Q,
EBarnhill, 6/2)/99 PM:LPD3 JStang 6/2 /99 SC:LPD3 CcraigW 6//99 OFFICIALRECORD COPY 1
I li
R. Powers June 23, 1999 In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC's Public Document Room.
Sincerely, Original signed by:
Docket Nos. 50-315, 50-316 License Nos.: DPR-58, DPR-74
Enclosures:
As stated cc w/encls: See next page DISTRIBUTION John F. Stang, Sr. Project Manager, Section 1
Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Hard Copy (w/ encis):
J. Stang Docket File K. Leigh PUBLIC OGC ACRS LPD31 RF E-mall:
S. Collins B. Sheron S. Black W. Lyon F. Orr G. Grant R. Zimmerman J. Zwolinski C. Craig E. Weiss T. Hiltz C. Sochor DOCUMENT NAME: G:)PDIII-1EDCCOOK)Dc0506.wpd See previous concurrence OFFICE NAME DATE PGEB KLeigh*
6/23/99 LA:LPD3 Q,
PM:LPD3 JStang EBamhill 8<2)ice 6/z /99 OFFICIALRECORD COPY SC:LPD3 CCrai+~Q 6//99
R. Powers ln accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures willbe placed in the NRC's Public Document Room.
Sincerely, John F. Stang, Sr.
oject Manager, Section 1
Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315, 50-316 License Nos.: DPR-58, DPR-74
Enclosures:
As stated cc w/encls:
See next page
Robert P. Powers Indiana Michigan Power Company Donald C. Cook Nuclear Plant Units 1 and 2 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532%351 Attorney General Department ofAttorney General 525 West Ottawa Street Lansing, Ml 48913 Township Supervisor Lake Township Hall P.O. Box 818 Bridgman, MI 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Ml 49127 Jeremy J. Euto, Esquire Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 Mayor, City of Bridgman P.O. Box 366 Bridgman, Ml 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Ml 48909 Drinking Water and Radiological Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P.O. Box 30630 CPH Mailroom Lansing, Ml 48909-8130 David F. Kunsemiller Director, Regulatory Affairs Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495 A. Christopher Bakken, Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106 Michael W. Rencheck Vice President, Nuclear Engin'eering Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107
OFFICIALRECORD COPY Attendance Hot Leg Nozzle Gap Issues/American Electric Power (AEP)
May 6, 1999 9:00 a.m. -11:30 a.m.
- Name
- 1. Thomas Noonan
- 2. Mike Rencheck
- 3. Jeb Kingseed
- 4. Gordon Arent
- 5. Warren Lyon
- 6. Eric Weiss
- 7. Frank Orr
- 8. Michael Emery
- 9. David Kunsemiller
- 10. Daniel Garner
- 11. John Stang
- 12. Kim Leigh
- 13. Gregory Hill 14.
15.
Affiliation AEP AEP AEP AEP NRC NRC NRC Westinghouse AEP Westinghouse NRC NRC AEP Enclosure 1
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Technical Meeting May 6, 1999
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COOK NUClEARPlAM Hot Leg Nozzle Gap Issues Gregory J. Hi I Engineer Nuclear Safety 8 Analysis
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'MERICAN'LKCIIC POWER
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COOK NUQEAR PLANT r
HLNG Issues
- Introduction
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Introduce Participants
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Purpose of the Meeting Discuss Hot Leg Nozzle Gap Credit in the Cook LOCA Analyses Two Part Presentation
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Part 1: Hot Leg Switchover Subcriticality => ECCS-recirculation (cold leg injection -> hot leg injection)
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Part 2: Large Break LQGA PCT => ECCS-injection
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AM MICAH'LECTRIC POWER
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COOKNUQEAR PlANT HLNG Issues
- Participants M. W. Rencheck - Vice President of Nuclear Engineering T. P. Noonan - Fuels, Safety, and Analysis Director D. F. Kunsemiller - Regulatory Affairs Director J. B. Kingseed - Fuels, Safety, and Analysis Asst. Director G. P. Arent - Nuclear Licensing Engineer D. C. Garner - Westinghouse Fellow Engineer M. A. Emery - Westinghouse Senior LOCA Analyst G. J. Hill - Nuclear Safety 8 Analysis Engineer
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COOK NUClEARPlANT HLNG Issues
- Discussion r
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~ Analysis Benefits due to Hot Leg Nozzle Gap Part 1: ECCS-Recirculation => post-LOCA Subcriticality
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Sump dilution minimizes by borated coolant flow path
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Early analytical solution used HLNG benefit during cold leg recirc Part 2: ECCS-Injection => LOCA Peak Clad Temperature (PCT)
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Reflood phase benefit due to steam vent path
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HLNG benefit applied to past Cook Large Break LOCA analyses
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COOK NUCLEARPlANT Hof Leg Nozzle Gap Issues Part 1
Hot Leg Switchover Subcriticality
==> ECCS-recirculation
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COOK NUClEARPlANT HLSO Subcri ticali ty - Agenda
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Brief Background
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Problem Statement for Hot Leg Switchover Subcriticaliiy
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Early Solution
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New Problem
~ Solutions
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Implementation Strategy
~ Summary
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COOK NUQEAR PLANT HLSO Subcriticality - Background
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10 CFR 50.46 Requirement (b)(5) Long-term cooling. After any calculated successful initial operation of the ECCS, the calculated core temperature shall be maintained at an acceptably low value and decay heat shall be removed for the extended period of time required by the long-lived radioactivity remaining in the core.
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Licensing Commitment for LTCC in Original W LOCA Model ANMfCAN'LECTRIC POWER g
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COOK NUCLFARPlANT HLSO Subcriti cali ty - Background rqly ')i"'aI.
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ECCS-recirculation, cold-leg injection alignment Core Boron Concentrates Sump dilution
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ECCS-recirculation, hot leg injection alignment
'MKRICAN'LKCHtlC POWER
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COOK NUCLEARPLANT HLSO - Problem Statement
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Sub-regions of the containment sump
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Reduced active mixing volume
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Challenge to subcriticality
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'MERICAN'I.FCTRIC POWER 8
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COOK NUCLEARPlAM'LSO - Early Solufion
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Not an issue for Hot Leg Breaks
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Cold Leg Breaks credited Hot Leg Nozzle Gap
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COOK NUClEARRANT HLSO - New Problem
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HLSO Elimination Methodology Withdrawal
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New Solution Needed
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COOK NUCLEARPIANT HLSO - New Solutions
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Preferred Solution is Control Rod Insertion Credit Regulatory Documentation on Control Rod Insertion
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10 GFR 50 Appendix K, Section l.A.2. Fission Heat, "Rod Trip and Insertion may be assumed ifthey are calculated to occur."
Back-up Solution is Cycle-specific Analyses
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COOK NUCCEAR PlANT
'I HLSO-Control Rod Insertion Credit
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~ W Cook-specific Control Rod Insertability Analysis Definitions Current Methodologies Analysis Objectives and Methodology Rod Insertion Acceptance Criteria D. C. Cook Structural Margin Results Conclusions
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COOK NUClEARPlANT r
HLSO-Control Rod Insertion Credit
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Definitions Design Basis (Cold Leg} Breaks
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1.Q ft'eactor Vessel Inlet Nozzle (RVIN) break
~ Guillotine Reactor Coolant Pump (RCP) Outlet Nozzle break MULTIFLEX1.0 Code
~ W code use for LOCA forces analysis, NRC reviewed and approved MULTIFLEX3.0 Code
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Revised W code for LOCA forces analysis
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NRC accepted in SER on Baffle-Barrel-Bolt Program
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COOK NUClEARPlAM HLSO-Control Rod Insertion Credit
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~ Current Methodologies Westinghouse
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Large Break - "The effects of rod trip and insertion are conservatively neglected in analysis for large breaks."
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Long Term Cooling - "The ECCS water has enough boron concentration to maintain core shutdown."
Framatome Technologies (BBWl credits rod insertion
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COOK NUCtEARPlANT HLSO-Control Rod Insertion Credit Tf j7l
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~ Analysis Objective Demonstrate control rod insertion for post-LBLOCA reactivity calculations during long term cooling.
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'MERICAN'I.ECIIC POWER
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COOK NUClEARK4NT I
HLSO-Control Rod Insertion Credit
~ Analysis Methodology D. C. Cook -specific parameters 0
5 Step Analysis Process
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Fuel Data > Internals Data > LOCA & Seismic Forces > Core Plate Motion >
Grid Loads MULTIFLEX3.0 Design Basis Break Sizes
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COOK NUClFARPlAM HLSO-Control Rod Insertion Credit
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~ Acceptance Criteria Upper Internals Guide Tubes forces remain below the allowable insertion load limits
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COOK NUClEARPlANT HLSO-Control Rod Insertion Credit Structural Margin above Design Limits D. C. Cook Unit 1 Break Size I Location Structural Margin for LimitingGuide Tube Structural Margin for Limiting Fuel Assembly Grid 1.0 ft'VInlet Nozzle DEGL RCP Outlet Nozzle 101'/
24%
112%
120%
15x15 fuel matrix
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COOK NUCLEAR PLANT
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HLSO-Control Rod Insertion Credit
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Structural Margin above Design Limits-D. C. Cook Unit 2 Break Size/Location Structural Margin for Limiting Guide Tube Structural Margin for Limiting Fuel Assembly Grid 1.0 ft2 RV Inlet.Nozzle DEGL RCP Outlet Nozzle 146%
154%
141%
107%
17x17 fuel matrix
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AMERICAN'LEC1RIC POWER
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COOK NVCl&V3PIANT HLSO-Control Rod Insertion Credit ra
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Conclusions LOCA blowdown forces based upon Design Basis Break Sizes Seismic loads combined with LOCA blowdown loads Allowable Limits not exceeded for
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Upper Internals Guide Tubes
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Fuel Assembly Grids at Control Rod Locations Control rods will insert as demonstrated by the calculation
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COOK NUClEARRANT Hl SO-Control Rod Insertion Credit
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Implementation Strategy Tech Spec BASES change & USQ Submittal for NRC review and approval to be mar!e June 15, 1999
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COOK NUClEARPlANT HLSO-Cycle-specific Analysis I 44 i 'P' vv.v.
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Backup Solution
~ Current methods used with revised assumptions
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No credit for control rod insertion
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Requires extensive analysis effort each fuel cycle
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'MERICAN'I.KCFRlC POWER
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COOK NUClEARKANT HLSO-Cycle-specific Analysis II (
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Unit 1 Cycle 16 Uses existing burnup credit t
Refined Xenon calculation based on conservative power history Physical Plant Modifications to increase active sump volume Maximum HLSO time driven by available sump boron
~ Significant reduction in maximum HLSQ time (52 => 4.5 nours)
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COOK NUQEARPlAM'LSOSubcriticality Summary
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Preferred Solution => Control Rod Insertion Credit offers bounding analysis only solution for Unit 2 at this time lead unit for restart
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Backup Solution => Cycle-specific Analyses current methods / revised assumptions / no credit for RCCAs extensive analysis each fuel cycle HLSO window significantly reduced for operators success is not certain for fresh reload cores
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COOK NUQEAR PtANT
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HLSO Subcri ticali ty Summary O'0
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Both solution paths do NOT rely on credit associated with Hot Leg Nozzle Gap
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HLSO window for operators is less restrictive for control rod insertion credit approach
~ Submittal for NRC review and approval
- June 15, 1999
'MERICAN KI.KCIIC POWER
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COOK NUCtFAR PlANl Hot Leg Nozzle Gap Issues Part 2 Large Break LOCA Peak Clad Temperature
==> ECCS-injection
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COOK NUQEAR PlANT Large Break LOCA PCT - Agenda
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Background
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Problem Statement
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Solution
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COOK NUClEARAANl'BLOCAPCT - Background
~ Current analysis-of-record used PSSM methodology
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PSSM withdrawn / replaced with ESHAPE in 1995
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Hot Leg Nozzle Gap during ECCS-injection
~ Cook LBLOCAPCT credits HLNG during ECCS-injection
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COOK NUCtFAR PlANT LBLOCA PCT-Problej;> Statement C ~
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Hot Leg Nozzle Gap credit during ECCS-injection is currently under NRC review
~ Without HLNG credit Cook does not meet LBLOCA PCT limit
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COOK NUClFARPIANT LBLOCA PCT - Strategy
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New Analyses Unit 1 Cycle 16
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uses ESHAPE methodology
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no credit for HLNG Unit 2 Cycle 12 and beyond
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resubmit LBLOCAanalysis performed to support core uprating to 3600 Mwt
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uses ESHAPE methodology
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no credit for HLNG
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New analyses docketed via 10 CFR 50.46 submittal.
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COOKNN2&VIK4NT LBLOCA PCT-Summary
~ Current LBLOCAPCT Rack-ups credit HLNG
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New analyses do not rely upon Hot Leg Nozzle Gap credit NRC-approved ESHAPE methodology used
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COOK NUClEARPlANl 4
Hof Leg Nozzle Gap Issues-Overall Summary
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Part 1: HLSO Subcriticality Analysis Third-party review Licensing Strategy Submittal
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Part 2: Large Break LOCA PCT Licensing Strategy Submittal AMERICAN ELECTRIC POWER'
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