Similar Documents at Cook |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999 Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21 IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20217D9241999-10-0808 October 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML20196K5961999-06-30030 June 1999 Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021 ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML20207A9201999-05-21021 May 1999 Ack Receipt of 990319 Response to Notice of Violation & Proposed Imposition of Civil Penalty .On 981124, Licensee Remitted Check for Payment of Civil Penalties. Licensee Requests for Extension for Response,Granted ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML20205P0591999-04-14014 April 1999 Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999 Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed ML20217D9361999-09-30030 September 1999 FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2 ML17326A1541999-09-20020 September 1999 Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn ML17326A1261999-09-17017 September 1999 Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal ML17326A1441999-09-17017 September 1999 Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted ML17326A1531999-09-16016 September 1999 Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl ML17326A1101999-08-27027 August 1999 Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided ML17326A0991999-08-26026 August 1999 Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed ML17326A1221999-08-23023 August 1999 Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I ML17326A0981999-08-23023 August 1999 Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d) ML17326A0891999-08-16016 August 1999 Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed ML17326A0811999-08-10010 August 1999 Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623 ML17326A0821999-08-0606 August 1999 Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation ML17326A1451999-08-0404 August 1999 Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca. ML17326A0751999-08-0404 August 1999 Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed ML17326A0721999-07-29029 July 1999 Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER ML17326A0711999-07-27027 July 1999 Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46. ML17326A0601999-07-22022 July 1999 Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR ML17326A0631999-07-22022 July 1999 Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed ML17326A0311999-07-0101 July 1999 Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed ML17326A0281999-06-28028 June 1999 Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl ML17326A0241999-06-23023 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl ML17326A0121999-06-18018 June 1999 Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed ML17326A0111999-06-11011 June 1999 Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. ML17325B6401999-06-0101 June 1999 Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal ML17325B6281999-06-0101 June 1999 Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed ML17325B6331999-05-28028 May 1999 Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed ML17265A8201999-05-24024 May 1999 Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal ML17325B6111999-05-21021 May 1999 Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17325B6031999-05-21021 May 1999 Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. ML17325B5971999-05-20020 May 1999 Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed ML17335A5281999-05-12012 May 1999 Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept ML17335A5271999-05-11011 May 1999 Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight ML17325B5841999-05-10010 May 1999 Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed ML17325B5871999-05-0707 May 1999 Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates ML17325B5821999-05-0404 May 1999 Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan ML17325B5791999-05-0404 May 1999 Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed ML17325B5741999-05-0303 May 1999 Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal ML17325B5631999-04-22022 April 1999 Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227 ML17325B5561999-04-16016 April 1999 Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed ML17325B5451999-04-12012 April 1999 Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed ML17325B5301999-04-0707 April 1999 Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed ML17325B5241999-04-0505 April 1999 Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects ML17325B5121999-04-0101 April 1999 Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed ML17325B5141999-03-30030 March 1999 Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML17325B5191999-03-29029 March 1999 Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed ML20204F6401999-03-19019 March 1999 Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage ML17325B4751999-03-18018 March 1999 Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed ML17325B4721999-03-18018 March 1999 Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal ML17325B4641999-03-17017 March 1999 Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation 1999-09-30
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jF'R.jt:C3R.L JL V 1 ACCELERATED RIDS PROCESSING)
~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9407120131 DOC.DATE: 94/07/05 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION P SMITH,W.'G. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MARTIN,J.B. Region 3 (Post 820201) R
SUBJECT:
Informs that util submittinq encl scope 6 objectives for I 941004 emerqency plan exercise to J McCormick-Barger.Subj exercise utz.l only exercise. Complete exercise scenario package will be submitted 60 day's in advance of exercise.
DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR ENCL SIZE: R TITLE: OR Submittal: Emergency Preparedness Plans, Implement'g Procedures, C NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 PD 1 1 HICKMAN,J 1 1 INTERNAL'EOD/DOA/IRB 1 1 NRR/DRSS/PEPB 1 1.
NUDOCS-ABSTRACT 1 1 RE FI 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D
0 C
U NOTE TO ALL"RIDS'ECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAME FROM DISTRIBUTIONLISTS I:OR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 8 ENCL 8
~ I ~
American Electric P~
Service Corporation~
1 Riverside Plaza Columbus, OH 43215 614 223 1000 AEP:NRC:0965AF 10 CFR 50 App. E Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 1994 EMERGENCY PLAN EXERCISE SCOPE AND OBJECTIVES U.S. Nuclear Regulatory Commission, Region III 801 Warrenville Road Lisle, Illinois 60532-4351 Attn: J. B. Martin July 5, 1994
Dear Mr. Martin:
This letter is to inform you that we are submitting the scope and objectives for the October 4, 1994, Donald C. Cook Nuclear Plant Emergency Plan Exercise to Mr. James McCormick-Barger of your Radiological Programs Section. This action is in accordance with A. B. Davis'RC-Region III March 16, 1987, letter and FEMA Guidance Memorandum EX-3, "Managing Pre-exercise Activities and Post-exercise Meetings."
The October 4, 1994 exercise will be an utility only exercise.
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 back-up for the exercise in the event of simulator equipment problems.
Also, in accordance with FEMA Guidance Memorandum EX-3, 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, 60 days in advance of the exercise.
Sincerely, W. G. Smith, Jr.
Chief Operations Manager
~ J' 9407120131 940705 PDR ADOCK 05000315 F . , PDR
J. B. Martin 2 AEP:NRC:0965AF bib Attachment c; A. A. Blind - w/o att.
G. Charnoff E. E. Fitzpatrick - w/o att.
J. McCormick-Barger - Region III - w/attachment NFEM Section Chief - w/o att.
NRC Resident Inspector - Bridgman J. R. Padgett W. T. Russell F/Lt. J. M. Tyler - Lansing, MI
COOK NUCLEAR PLANT 1994 EMERGENCY PLAN EVALUATED EXERCISE SCOPE AND OBJECTIVES
PURPOSE The purpose of this emergency preparedness exercise is to meet the conditions of 10CFR50, Appendix E,(IV)(F)(2) which requires a licensee to annually exercise its Emergency Plan.
SCOPE This exercise will take place between the hours of 0800 and 1600 on October 4, 1994.
It will include actions taken by the Cook Plant, the American Electric Power Service Corporation, and Indiana Michigan Power Company personnel. State of Michigan and the County of Berrien will participate at the initial notification stages and Plant personnel will be stationed in the State and County EOCs to maintain continuous communications with the EOF.
The Cook Plant Unit 2 simulator will be utilized to drive scenario events and all emergency response facilities will be activated. They include the Operations Staging Area (OSA),
Simulated Technical Support Center (TSC), Emergency Operations Facility (EOF) and the Joint Public Information Center (JPIC).
Simulated events at the plant will begin with a Reactor Coolant System (RCS) leak of just sufficient magnitude to force a Technical Specification shutdown and subsequent Unusual
'vent declaration. As the Control Room operators are determining the size and source of the leak, a mild earthquake occurs. An Alert is declared as a result of the earthquake and as damage assessments continue, a strong aftershock is felt causing the RCS leak to increase significantly. A reactor trip results along with safety injection. A Refueling Water Storage Tank level indication malfunction, high turbine vibrations and a high pressure differential across the travelling screens is also noted. High containment pressure causes containment spray to actuate and a phase B isolation to occur. A Site Area Emergency is declared. A second aftershock occurs creating electrical malfunctions and the spill of a barrel of hazardous water treatment chemicals. A short release of radioactive material via the plant vent occurs because of a 20 gpm leak in an RHR pump. This leak is soon isolated, terminating the release. At about that same time a medical emergency occurs in the TSC. The exercise will terminate with the RHR leak isolated, electrical and chemical problems neutralized and the plant on its way to safe shutdown.
A EXERCISE OB JECTIVES 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, the Indiana Michigan Power Company Emergency Plan Response Manual and the AEPSC Emergency Response Manual.
- 2. Demonstrate the ability to establish emergency management command and control, and maintain continuity of this function for the duration of the postulated event.
- 3. Demonstrate the ability to establish communications and information flow between DCCNP emergency response facilities and participating offsite agencies.
- 4. Demonstrate the ability to designate subsequent shifts of the emergency response organization.
B. ONTR L ROOM BJE TIVE Demonstrate the ability to recognize symptoms and parameters indicative of degrading plant conditions and to classify degraded conditions as emergencies.
- 2. Demonstrate the ability to initiate notification of offsite authorities and plant personnel.
- 3. Demonstrate communications and information flow to and from the Technical Support Center.
- 4. Demonstrate the ability to transfer emergency authorities and responsibilities from the on-shift emergency organization to the DCCNP emergency response organization.
- 5. 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.
- 3. Demonstrate the ability,to coordinate onsite activities in response to the emergency.
4 Demonstrate the ability to establish and maintain hard copy communications with the EOF and verbal communications with the EOF, OSA, IAG, and JPIC.
- 5. Demonstrate the ability to provide analytical radiological assistance to the OSA and Control Room.
- 6. Demonstrate the ability to obtain data from the OTSC/PSSD System and Plant Process Computer.
- 7. Demonstrate the ability to request emergency response teams from the OSA.
- 8. Demonstrate the ability to evaluate the results of TSC/OSA habitability surveys and assess the need to evacuate these facilities.
- 9. 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. OPERATION STAGING AREA BJECTIVES
- 1. Demonstrate the ability to activate the facility within one hour of declaration of an emergency requiring facility activation.
- 2. 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. On-site Radiation Monitoring
- d. Off-site Radiation Monitoring
- 3. Demonstrate the ability to designate a second shift for OSA operation.
4 Each emergency response team assembled and dispatched shall demonstrate the following actions as applicable to the team type and mission:
- a. Assembly of tools/equipment;
- b. Pre-operation checks of equipment and communications devices; C. Performance of appropriate radiological precautions; d, Performance or simulation of team mission
- e. Post-mission debriefing and radiological controls;
- 5. Demonstrate the ability to provide emergency radiological support. As a minimum, the following activities should be demonstrated:
- a. Establishment of emergency dosimetry and exposure tracking system;
- b. Determination and establishment (if necessary) of emergency control points; C. Performance of habitability surveys prescribed by procedure;
- d. Analysis of radiological conditions to be encountered by emergency response teams;
- e. Specification of radiological controls and precautions for emergency response teams; i
- 6. Demonstrate the ability to perform offsite radiological monitoring. As a
I minimum, two teams should be dispatched and direct radiation monitoring as well as airborne radioactivity analysis should be demonstrated.
- 7. Demonstrate the ability to implement damage control activities in accordance with applicable Emergency Plan Procedures.
- 8. 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.
- 9. - 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, RCS Loop
- b. Containment Sump E. EMERGEN Y OPERATIONS FA ILITY BJE TIVES 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.
- 3. ii to establish and maintain effective" emergency Demonstratet thee aability communications with each of the following agencies an and facilities:
a
'O State of Michigan
- b. Berrien County C. NRC
- d. Technical Support Center
- e. Joint Public Information Center
- f. Initial Assessment Group
- 4. Demonstrate the ability to establish and maintain hard copy data transmission and reception with each of the following facilities:
Technical Center a.
- b. 'oint PublicSupport Information Center or Emergency News Center
- c. State of Michigan EOC
- 5. Demonstrate the ability to direct Offsite Radiation Monitoring Teams in order to determine the geographical location and radiological magnitude of the postulated plume.
- 6. Demonstrate the ability to update the State of Michigan on the status of the emergency at 15 minute intervals.
- 7. Demonstrate the ability to respond to inquiries from the TSC, JPIC, IAG and State of Michigan in a timely manner.
- 8. Demonstrate the ability to project the magnitude of offsite dose using the Dose Assessment Program.
- 9. Demonstrate corporate augmentation of the EOF staff.
10, Demonstrate recovery planning associated with the emergency termination.
- 11. Demonstrate the ability to designate a second shift for EOF operations.
F. PUBLIC AFFAIRS OBJECTIVES
- 1. Demonstrate activation of the Joint Public Information Center.
- 2. Demonstrate the ability to conduct media briefings.
- 3. Demonstrate the ability to respond to actual or simulated inquiries from media representatives.
4 Demonstrate the ability of 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.
- 6. Demonstrate coordination of news announcement content with State and County authorities.
INITIALCONDITIONS
1 ~
Unit 1 Mode 6 Core Off-loaded CVCS Crosstie - Out of Service for flow orifice replacement.
1AB Diesel and Train "B" Equipment - Out of Service for related work.
Unit 2 100 % Power, End of Life Control Air Compressor - Out of Service for oil change and preventive maintenance.
RWST level indicator ILS-951, Failed as is.
TIMELINf The times listed for the events below are times which have been estimated based on trial simulator runs of the scenario. They are nominal only and may vary depending on minor simulator changes or techniques the exercise control room crew may have that are different than the test crew'.
TIME EVENT CONDITION 0800 Exercise begins 0815 A RCS (Reactor Coolant System) leak of 15 gpm occurs.
0820 The Operators recognize a RCS leak is occurring and begin actions to identify source of leakage and attempts to isolate it in accordance with the RCS Excessive Leakage procedure, Symptoms occurring are: decreasing pressurizer level and pressure along with increasing containment pressure and humidity.
0845 The Operators recognize the RCS leak cannot be isolated. Plant conditions are stabilized and the decision is made to perform a Unit shutdown.
0900 Unit shutdown is initiated. Unusual Event is declared based on ECC-14. Initial notifications are made to plant management and off-site agencies.
0930 During Unit shutdown, the site experiences an Earthquake (No. 1),
which can be readily felt in each Control Room.
0935 Plant Seismic Instrumentation confirms an Earthquake has occurred.
An Alert is declared based on ECC-3. Initial notifications are made to plant management and off-site agencies.
Plant tours/inspections are begun to assess plant damage and determine if a site area emergency is necessary. Plant shutdown continues.
1015 TSC and OSA are operational ~
1020 Plant tours/inspections reveal no plant damage has occurred.
1030 EOF is operational.
1045 Earthquake ¹2 is readily felt in each Control Room causing the pre-existing RCS leak to increase, causing a Reactor Trip and Sl (Safety Injection) to occur. Plant symptoms occurring include: RWST Level Indicator malfunction, turbine high vibration, circulating water travelling screen High ~P.
1050 High containment pressure causes a containment spray and containment isolation Phase B to occur. Site Area Emergency is declared based on either ECC-3 or ECC-14. Initial notifications are made to plant management and off-site agencies.
1115 PACHMS is placed in service.
1120 Plant accountability is completed.
1130 Earthquake ¹3 is readily felt in each Control Room. Plant symptoms occurring include: loss of 600 Volt AC electrical buss 2-AM-D, a barrel of hazardous water treatment chemicals falls and is punctured, resulting in a hazardous chemical spill.
1145 ECCS suction source is switched from the RWST to the recirculation sump.
1200 A 20 gpm leak occurs on the "East" RHR Pump. This results in a small off-site release via the plant vent, 1215 A medical emergency occurs in the TSC.
1230 "East" RHR Pump leak is isolated, termination of the off-site release.
I245 Hazardous chemical spill is neutralized/contained.
1400 Drill terminates with approval from the Recovery and Control Manager.