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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:INCOMING CORRESPONDENCE
MONTHYEARML20217D9361999-09-30030 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 ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca 05000315/LER-1998-029-01, Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed1999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46 ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR 05000315/LER-1998-014-03, Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed1999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed 05000315/LER-1999-004-01, Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed1999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed 05000315/LER-1998-037-01, Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal1999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight 05000316/LER-1999-002, Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed1999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current ESRR Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5141999-03-30030 March 1999 Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20204F6401999-03-19019 March 1999 Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage ML17325B4641999-03-17017 March 1999 Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation ML17325B4651999-03-12012 March 1999 Forwards Rev 5 to Cook Nuclear Plant Restart Plan, Which Supercedes Previous Revs in All Aspects.Licensee Will Continue to Advise NRC of Progress Toward Restart & Provide Addl Info During Monthly 0350 Restart Panel Public Meetings ML17325B4601999-03-11011 March 1999 Forwards Copy of Util 981102 Cover Ltr Sent to Mi Dept of Environ Quality Which Transmitted Storm Water Pollution Prevention Plan Rev Sheet. Util Failed to Send Copy to NRC within 30-day Period,Per Ets,Due to Internal Oversignt ML17325B4541999-02-28028 February 1999 Informs NRC Staff That Jr Sampson Will Assume Position of State President,Aep Impco,Effective 990301.Block Diagram of Interim Organizational Chart Attached ML17325B4521999-02-20020 February 1999 Discusses Delay in Implementation of License Amend 227 Until Issues Fully Evaluated ML17325B4531999-02-19019 February 1999 Forwards for Files,Copy of DC Cook Nuclear Plant Ltr AEP:NRC:90358B,dtd 981218 ML17325B4491999-02-18018 February 1999 Forwards Rev 1 to Licensee Ltr Sent to DOT Re Exemption Request to Support Disposal of DC Cook,Unit 2 Generators Removed in 1988.Rev 1 to ER-98-009, Premliminary Waste Characterization of DC Cook SG Lower Assemblies, Encl ML17335A5001999-01-30030 January 1999 Submits Response to GL 96-01, Testing of Safety Related Logic Circuits. Surveillance Revalidation Program Has Been Initiated by Operations Dept to Compare Associated Procedures with TS ML17335A4931999-01-22022 January 1999 Requests Extension of Response to NRC NOVs 50-315/97-201, 50-316/97-201,50-315/97-17,50-316/97-17,50-315/98-04, 50-316/98-04,50-315/98-05,50-316/98-05,50-315/98-09 & 50-316/98-09,until 990305 ML17335A4851999-01-18018 January 1999 Submits Overview of Updated Plant Restart Plan & Schedule 05000315/LER-1998-052-01, Forwards LER 98-052-01,re Potential Failure Mode for Air Operated Components Not Considered in Original Design. Interim LER Has Been Updated to Include Two Addl Instances of Same Failure Mode1999-01-18018 January 1999 Forwards LER 98-052-01,re Potential Failure Mode for Air Operated Components Not Considered in Original Design. Interim LER Has Been Updated to Include Two Addl Instances of Same Failure Mode ML17335A4941998-12-18018 December 1998 Informs NRC of Desire to Defer Number of Insps NRC Currently Has Scheduled for Dec 1998 & Jan 1999.Requests That Insps for Listed Items Be Postponed ML17335A4191998-12-18018 December 1998 Informs That Based on Stated Items,Nrc Review & Approval of License Amend Request Is No Longer Considered Necessary Prior to Restart of Unit 1 ML17335A4051998-12-16016 December 1998 Forwards Rev 4 to Cook Nuclear Plant Restart Plan, IAW Previous Commitments to Provide Copies of Restart Plan for Info ML17335A4091998-12-16016 December 1998 Withdraws All Previous Requests for Relief from Code Requirments for Containment Spray Pumps.Util Installing Mod to CSS That Will Enable Util to Perform Pump Tests IAW Code Requirements Prior to Restart ML17335A4101998-12-15015 December 1998 Informs That Licensee Would Be Pleased to Be Included as Reference Plant in GSI - 191 Evaluations,In Response to JW Craig Request 05000315/LER-1998-031-01, Forwards LER 98-031-01,re Potential Common Mode Failure of RHR Pumps Due to Use of Inaccurate Values.Commitment Made by Util,Listed1998-12-11011 December 1998 Forwards LER 98-031-01,re Potential Common Mode Failure of RHR Pumps Due to Use of Inaccurate Values.Commitment Made by Util,Listed ML17335A3891998-12-10010 December 1998 Informs That Util Is Extending Severe Accident Mgt Guidelines Until 991231 Due to re-assigned Engineering Resources 1999-09-30
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Text
REGULA RY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9908180095 DOC.DATE: 99/08/06 NOTARIZED: NO DOCKET I FXCIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 50-,31'onald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION POWERS,R.P.
Indiana Michigan Power Co.
RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
SUBJECT:
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.
DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
Emergency Preparedness
- Plans, Implement'g Pro edures, NOTES:
A, C E, G,
RECIPIENT ID CODE/NAME S
INTERN: FILE CENTER 0
HP EXTERNAL: NOAC COPIES LTTR ENCL 1
1 2
2 1
1 1
1 RECIPIENT ID CODE/NAME IRO/HAGAN,D.
NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 0
R Y'
r I
itFtt DE NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 8
ENCL 8
I l%
One CxkRar Bxkpan, M46!06 61 6 465 5901 S
SNlMBNA RMCNIGQN PQWM August 6, 1999 C0799-10 Docket Nos.:
50-315 50-316 U.
S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Stop 0-Pl-17 Washington, D.C.
20555-0001 Donald C.
Cook Nuclear Plant Units 1 and 2
1999 EMERGENCY PLAN EXERCISE SCOPE AND OBJECTiVES This letter is to inform you that we are submitting the scope and objectives for the October 26,
- 1999, Cook Nuclear Plant emergency plan exercise to Mr.
Gary Shear of your Plant Support Branch.
This action is in accordance with A.
B. Davis'RC-Region III March 16, 1987, letter and FEMA-REP-14, "Radiological Emergency Preparedness Exercise Manual".
The October 26,
- 1999, exercise will include full state and county participation.
The exercise will be conducted using the unit 2 simulator and the simulated technical support center in the Cook Nuclear Plant training center.
Controller information and simulation data are also being developed to provide backup for the exercise in the event of simulator equipment problems.
Also, in accordance with FEMA-REP-14, sixty days in advance of the exercise we will submit the complete exercise scenario package with all controller information and simulation
- data, including plant
- data, radiation level
- data, and release rate data.
Sincerely, R.
P.
Powers Senior Vice President
/dms Attachment 9908i80095'90806.
PDR ADQCK 050003%5 F
PDR AEI':~>Iaerica's k'Ireful Parlaer"
U.
S. Nuclear Regulatory Commission gage 2,
C0799-10 A. C.
Bakken, III, w/attachment J.
E. Dyer, w/attachment Gary Shear, Chief Plant Support
- Branch, Region III HDEQ-DW
& RPD NRC Resident Inspector
'L
'l l
Attachment 1 to C0799-10 Page 1
DONALD C.
COOK NUCLEAR PLANT 1999 EMERGENCY RESPONSE EXERCISE SCOPE In the interest of verifying that the health and safety of Plant staff, Plant visitors and the general public are protected in the event of an accident at the Cook Nuclear Plant, American Electric Power conducts an annual plant emergency response exercise.
In accordance with the schedule prescribed by the Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA), the 1999 emergency exercise will be conducted as a day shift exercise.
Exercise events will begin in the plant's UNIT 2
simulator at approximately 0830 on October 26, 1999 initiating the mobilization of Cook Nuclear
- Plant, Berrien
- County, and State of Michigan emergency response= personnel.
The plant site simulated Technical Support Center (TSC) and Operations Staging Area (OSA);
Emergency Operations Facility (EOF) at the Buchanan Office; and the Joint Public Information Center (JPIC) at Lake Michigan College will all be activated in response to the simulated emergency events.
A full State and County response will also result from these simulated events.
Exercise termination is expected to take place at approximately 1400 on October 26, 1999.
The intent of the exercise is to demonstrate that these various emergency response organizations (EROs) are adequately trained to implement their corresponding emergency plans and procedures from their respective emergency response facilities (ERFs).
It will also serve to demonstrate their ability to effectively communicate with each other and coordinate their activities.
The scenario has been designed to provide ample opportunity for all participating organizations to meet their objectives.
It progresses through the appropriate emergency classifications in such a
way that sufficient time is spent at each classification to allow objective-related decision making and actions to take place.
- However, scenario events have been created and paced to challenge the responders'bility to make timely and accurate emergency declarations; damage assessments and protective action recommendations and orders.
EOF and onsite exercise activities will be observed and evaluated by American Electric Power Nuclear Generation and NRC personnel.
Offsite activities will be observed and evaluated by Federal Emergency Management Agency (FEMA) personnel the State of Michigan and the County of Berrien.
ERE-99 1-1
1 t
P I
Attachment 2 to C0799-10 Page 1
SECTION II EXERCISE OBJECTIVES ERE-99
Attachment 2 to C0799-10 Page 2
DONALD C.
COOK NUCLEAR PLANT 1999 EMERGENCY RESPONSE EXERCISE II.
EXERCISE OBJECTIVES The exercise objectives dictate the scope of the scenario.
The objectives for this exercise were developed based upon the Donald C.
Cook Nuclear Plant (DCCNP)
Emergency Plan Administrative Manual.
Situations will be presented in the scenario to prompt the desired player response for each objective.
Where appropriate, specific objectives and criteria for adequate demonstration will be included in the exercise messages for Controller/Observer use.
A.
OVERALL LICENSEE OBJECTIVES Demonstrate the ability of the emergency response organization to implement DCCNP Emergency Plan Procedures, and the AEP Emergency
Response
Manual.
Demonstrate the ability to establish emergency management command and
- control, and maintain continuity of this function for the duration of the postulated event.
Demonstrate the ability to establish communications and information flow between DCCNP emergency response facilities and participating offsite agencies.
Demonstrate the ability to designate subsequent shifts of the emergency response organization.
Demonstrate the ability to provide adequate control of the exercise to maintain scenario continuity; 'rovide accurate and timely information; and appro'priate instructions to exercise participants.i B.
CONTROL ROOM OBJECTIVES Demonstrate the ability to recognize
'symptoms and parameters indicative of degrading plant conditions and to classify degraded conditions as emergencies.
(
Demonstrate the ability to initiate notification of offsite authorities and plant personnel.
Demonstrate communications and information. flow to and from the Technical Support Center.
'bjectives added to close out Inspection Follow-up Item (IFI 50-315-03; 316/97013-03)
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Demonstrate the ability to transfer emergency authorities
.and responsibilities from the on-shift emergency organization to the DCCNP emergency response organization.
Demonstrate the duties of the Control Room Emergency Organization as described in procedure OHI-2080.
C.
TECHNICAL SUPPORT CENTER OBJECTIVES Demonstrate the ability to activate the facility within one hour of declaration of an emergency requiring facility activation.
Demonstrate the ability to provide analytical assistance and operational guidance to the Control Room.
Demonstrate the ability to coordinate onsite activities in response to the emergency.
Demonstrate the ability to establish and maintain hard copy communications with the EOF and verbal communications with the
- EOF, OSA, and JPIC.
Demonstrate the ability to provide analytical radiological assistance to the OSA and Control Room.
6.
Demonstrate the ability to obtain data from the Plant Process Computer.
Demonstrate the ability to request emergency response teams from the OSA.
Demonstrate the ability to evaluate the results of TSC/OSA habitability surveys and assess the need to evacuate these facilities.
Demonstrate the ability to recognize degrading plant conditions and classify plant conditions as an emergency.
10.
Demonstrate the ability to direct the implementation of site assembly, accountability and evacuation.
11.
Demonstrate the ability to evaluate site evacuation routes and determine an appropriate route based on indicated radiological and meteorological conditions.
12.
Demonstrate the actions required to be taken in the TSC if the emergency involves a
breach of the reactor coolant system.
D.
OPERATIONS STAGING AREA OBJECTIVES Demonstrate the ability to activate the facility within one hour of declaration of an emergency requiring facility activation.
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Demonstrate the ability to
- assemble, brief, and
- dispatch, within an average time of 20 minutes or less after being requested, the following emergency response teams:
a.
Damage Control b.
Chemistry Sampling c.'n-site Radiation Monitoring d.
Off-site Radiation Monitoring I
Demonstrate the ability to designate a second shift for OSA operation.
Each emergency response team assembled and dispatched shall demonstrate the following actions as applicable to the team type and mission:
a
~
b.
c ~
d.
e.
Assembly of tools/equipment; Pre-operation checks of equipment and communications devices; Performance of appropriate radiological precautions; Performance or simulation of team mission; Post-mission debriefing and radiological controls.
5.
Demonstrate the ability to provide emergency radiological support.
As a minimum, the following activities should be demonstrated:
Establishment of emergency dosimetry and exposure tracking system; Determination and establishment (if necessary) of emergency control points; Performance of habitability surveys prescribed by procedure; Analysis of radiological conditions to be encountered by emergency response teams; Specification of radiological controls and precautions for emergency response teams.
Demonstrate the ability to perform offsite radiological monitoring.
As a
- minimum, two teams should be dispatched and direct radiation monitoring as well as airborne radioactivity analysis should be demonstrated.
Demonstrate the ability to implement damage control activities in accordance with applicable Emergency Plan Procedures.
Demonstrate the ability to perform onsite radiological monitoring in accordance with applicable Emergency Plan Procedures.
This monitoring should include direct radiation surveys and analysis of airborne radioactivity samples.
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Attachment 2 to C0799-10 Page 5
8.
.~Demonstrate the ability to obtain post accident samples from one of the following mediums and complete appropriate chemical and isotopic analysis within three hours of the sample request.
a
~
b.
RCS Loop Containment Sump 10.
Demonstrate proper Controller's actions in the OSA during the exercise.'MERGENCY OPERATIONS FACILITY OBJECTIVES Demonstrate the ability to activate the facility within one hour of declaration of an emergency requiring facility activation.
Demonstrate the ability to establish overall command and control of the DCCNP emergency response within one hour of declaration of a
site area emergency or higher classification, as applicable.
Demonstrate the ability to establish and maintain effective emergency communications with each of the following agencies and facilities:
a
~
b.
C.
d.
e.
State of Michigan Berrien County (Simulated)
NRC (Simulated)
Technical Support Center Joint Public Information Center Demonstrate the ability to establish and maintain hard copy data transmission and reception with each of the following facilities:
a.
Technical Support Center b.
Joint Public Information Center c.
State of Michigan EOC 5.
Demonstrate the ability to direct Offsite Radiation Monitoring Teams in order to determine the geographical location and radio1ogical magnitude of the postulated plume.
1 Demonstrate the ability to update the State of Michigan on the status of the emergency at 15 minute intervals.
Demonstrate the ability to respond to inquiries from the
- TSC, JPIC, and State of Michigan in a timely manner.
Demonstrate the ability to project the magnitude of offsite dose using the Dose Assessment Program.
Objectives added to close out Inspection Follow-up Item (IFI 50-315-03; 316/97013-03)
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~9.
..Demonstrate recovery planning associated with the emergency termination.
10.
Demonstrate the ability to designate a second shift for EOF operations.
F.
PUBLIC AFFAIRS OBJECTIVES Demonstrate activation of the Joint Public Information Center.
Demonstrate the ability to conduct media briefings.
3.
Demonstrate the ability to respond to actual or simulated inquiries from media representatives.
,4.- j Demonstrate the ability'f rumor control personnel to respond to simulated inquiries from the general public.
5.
Demonstrate the ability to monitor media transmissions and respond to inaccurate information being transmitted by the media.
Demonstrate coordination of news announcement content with
- State, County'and Federal authorities.
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