ML20237B686
| ML20237B686 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/24/1998 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20237B681 | List: |
| References | |
| NUDOCS 9808190150 | |
| Download: ML20237B686 (350) | |
Text
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yonfidM** COOPER NUCLEAR STATION 1998 BIENNIAL EXERCISE
***ConfidentiF*
WARNING: Do NOT review this information without approval of the Emergency Preparedness Unit
*** Confidential * * * -
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Drill Section 1.0
w 1998 Cooper Nuclear Station Emergency Exercise JUNE 9,1998 EXERCISE MANUAL AEullISC1 PUBLIC Puller DIS 11U('I
TABLE OF CONTENTS VOLUME 1 GENERALINFORMATION
- 1. INTRODUCTION
- 2. SCOPE AND OBJECTIVES 2.1 Scope 2.2 Objectives
- 3. GENERAL EXERCISEINFORMATION 3.1 Facilities Activated 3.2 Exercise Organization 3.3 Conduct of the Exercise 3.4 Precautions and Lhnitations 3.5 Abbreviations 3.6 Definitions 3.7 References 4.
CONTROLLER /EVALUATORINFORMATION 4.1 Controller / Evaluator Organization 4.2 Generallnformation 4.3 ControllerInstmctions 4.4 EvaluatorInstmetions 4.5 SimulatorInstmetions
- 5. PARTICIPANTINFORMATION 5.1 GeneralInformation 5.2 Participant Guidelines
- 6. SCHEDULE OF EVENTS 6.1 Times and Places 6.2 TravelInfonnation Table of Contents for Sections 7-15 are contained in Volume 11 of this Exercise Manual.
DrillSectwn 1.0 -i. l'olume 1. doc l I
l l TABLE OF CONTENTS I l VOLUME 2 CONFIDENTIAL ' SCENARIO SPECIFIC INFORMATION 7. SCENARIO OVERVIEW / OPERATIONS INFORMATION 7.1 Scoping Document j 7.2 Simulator Guide (SIMGUIDE) 7.3 Narrative Summary 7.4 Master Scenario Events List 7.5 Exercise Critique Notes
- 8. ON-SITE RADIOLOGICAL DATA 8.1 Radiological Sumnwy 8.2 Release Source Terms 8.3 Reactor Water Activity / PASS data 8.4 Area Radiological Maps (Direct radiation) and Airborne concentrations
- 9. OFF-SITE RADIOLOGICAL DATA Off-site Radiological Survey Team Controller Data Sheets 9.1 Off-site Release (initial phase) 9.2 Off-site Release (second phase) 9.3 Off-site Release (final phase)
- 10. OSC MISSION PACKAGES
- 11. BACKUP DATA (IfSimulator fails) 11.1 PMIS-04 Ops Data 11.2 PMIS-05 ARM Rad Data
- 12. EXERCISE MESSAGE CARDS (including Initial Conditions) -
- 13. METEOROLOGICAL DATA
- 14. JOINT INFORMATION CENTER DATA
- 15. SCENARIO BACKGROUND INFORMATION Table of Contents for Sections 16 are contained in Volume I of this Exercise Manual.
I DrillSection 7.0 1- Volume 2. doc l l _
- 1. INTRODUCTION i
Cooper Nuclear Station (CNS), owned and operated by the Nebraska Public Power District (NPPD) annually conducts an Emergency Preparedness Exercise. The purpose is to demonstrate that the NPPD emergency response organization can effectively meet its responsibilities in protecting the heal and safety of the residents of the Plume Exposure Pathway Emergency Planning Zone in the event of a radiologicalincident at the plant. The NPPD response organization and facilities developed to respond to such an emergency are described in the CNS Emergency Plan. The Plan also describes support available from Federal, St and local govemment agencies, and private organizations. The Plan describes a program ofcontinuous preparedness, one element of which is the conduct and evaluation of this exercise. The purpose of this exer :ise is to evaluate the NPPD emergency response organization in accordance with the CNS Emergency Plan and implementing procedures. The exercise will be conducted and evaluated by NPPD personnel. Upon termination of the exercise, the NPPD Evaluators will critique the response of the participants, assess the effectiveness oftheir response, and compile a Critique Repon to ensure appropriate actions are taken to resolve any w .aknesses identified. This Exercise Manual consists of two volumes; Volume I (Sections I through 6) provides information ofgeneral interest, instmetions to participants, a schedule of associated events, a general description and overview of the exercise, including administrative and logistical information helpful to all participants. Volume II (Sections 7 through 15), which is subject to a limited, controlled distribution provides the scenado-specific information and supporting data for the sequence of events to Controllers, Evaluators and authorized observers. Exercise " Participants" will not have prior access to or knowledge of any of the scenado developed for this exercise. Dri!! Section 1.0 Volume 1 doc
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- 6. 7.
9. 1 1 8 I 1 0. 2 1 2 2 2 3 2 4 N 2 *
- 3. GENERAL EXERCISE INFORMATION 3.1 - Facilities Activated 3.1.1 The Nebraska Public Power District a.
Control Room (Simulator)
- b. Technical Support Center (TSC)
- c. Operations Support Center (OSC)
- d. Emergency Operations Facility (EOF)
- e. Off-site radiation monitoring teams
- f. Joint Information Center .
3.1.2 Off-site Agencies 1 1998 is a biennial exercise year. The States of Nebraska and Missouri and plume exposure counties will participate in this exercise, and will be evaluated by FEMA. Some elements / locations may be evaluated out-of-sequence from the exercise.
- a. Nebraska Emergency Operations Center, Lincoln, NE
- b. Missouri Emergency Operations Center, Jefferson City, MO
- c. Nemaha County Emergency Operations Center, Auburn, NE
- d. Atchison County Emergency Operations Center, Rock Pon, MO
- e. Richardson County Emergency Operations Center, Falls City, NE 3.2 Exercise Organization The Organization participating in the exercise consists of the Exercise Director, Exercise Coordinator, Facility Lead Controllers, Controllers, Evaluators, Observers, and Participants as follows:
l 3.2.1 Exercise Director (Emergency Preparedness Manager) The Exercise Director is responsible for the post-exercise Controller debriefing, the CNS exercise critique, and NRC critique and exit meeting. Subsequent to the exercise, he will direct the preparation of a consolidated evaluation package and preparation cf an itemized list of recommended corrective actions. 3.2.2 Exercise Coordinator The Exercise Coordinator is responsible for the conduct of a successful exercise and will coordinate exercise preparations including the development of the scenario package. The Exercise Coordinator will ensure the safe conduct of the exercise and ensure that the conduct of the exercise does not adversely impact the DrillSection 3.0 1- Volume 1. doc
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operation of the station. He is responsible for resolution of any scenario related questions, The Exercise Coordinator will assist with the preparation of the consolidated evaluation package. 3.2.3 Controllers s Controllers are qualified personne! selected to perform functions as follows: A Le d Controller is assigned to each emergency response facility. The Lead Controller is responsible for all Controller, Evaluator, and Observer activities in a given facility and, as appropriate, its associated teams. Controllers for teams or sub-areas of a facility report to the Lead Controller of that facility. Controllers will deliver Exercise Messages or Data to designated Participants at specified times and places during the exercise, inject or deliver contingency messages as required, and keep the exercise actions moving according to the scenario, observe the exercise at other assigned locations, and prepare an evaluation. Controllers will submit written observations to the Lead Facility Controller who will summarize all comments for submittal to the Exercise Coordinator. Controllers are provided with the instructions contained in Section 4.0 of this manual. 3.2.4 Evaluators Evaluators are personnel assigned to evaluate the effectiveness of personnel, organizations, and activities in response to the scenario. They will evaluate performance on the basis of standards or requirements contained in the Emergency Plan, implementing Procedures, exercise messages, or as described herein. Some Controllers will also function to evaluate the facility or function to which they are assigned. They will document their fmdings on evaluation forms. 3.2.5 Observers A limited number of Observers may be allowed to watch the Exercise. They are prohibited from interaction with the Participants. The purpose of their attendance is generally personal education.
- 3. 2. c Inspectors Inspectors are members of the NRC evaluation team and may have prior knowledge of the exercise scenario At their asdgned locations they will observe the exercise and prepare an evaluation to be presentd at the exit meeting and critique.
Dn!!Sectwn 3 0 l'ulu.e Ldoc
3.2.7 Participants Participants include station and other utility personnel assigned to perform emergency functions as described in the Emergency Plan and Implementing Procedures. Personnel from off-site organizations and agencies (County, State, and private industry) are also participants in the exercise. 3.3 Conduct of the Exercise The exercise will simulate a radiological incident at the Cooper Nuclear Station in order to allow demonstration of the erectiveness of NPPD Emergency Plan for CNS, emergency response personnel, facilities, and equipment. It will be initiated by abnormal events requiring the Shia Supervisor to implement the Emergency Plan. All notifications to NPPD, State and local responders will be made in accordance with applicable procedures and policies, to the actual agencies, or to a Control Cell (for those agencies not participating). The exercise will include the tise of a " live" simulator. The CNS Simulator will duplicate plant response to actions taken by the on-shia crew of operators. Indications and annunciators which are modeled by the software will be available to indicate to the crew the status of systems and equipment, as the operators respond to the scenario.
"Real time" data from the Simulator will also be fed to other emergency response facilities (TSC and EOF) using terminals connected to the Simulator. The terminals will provide Participants in these facilities similar information normally available through the Plant Management Information System (PMIS).
The Simulator will be the central point for dissemination of plant data and is the key to ensuring that the exercise progresses on schedule. In the event of a failure of the Simulator computer, the Exercise Coordinator will determine the course of action. An attempt may be made to " reset" the Simulator and ;, tart over, or at a designated place. If this is unsuccessful, the Exercise Coordinator may direct that plant indications, parameters and annunciators be provided to the Control Room operators (and others) using message forms and plant data sheets. Plant information is provided on these data sheets similar in format to what the Simulator would provide. This is so that at no time will the messages
" prompt" the Participants or provide undue assistance in recognition of events. To more closely approximate the data that would be available in an actual emergency situation, information available on PMIS will also be provided in the TSC and the EOF where output consoles are located.
DnliSecticno 3.0 l'olume 1. doc l
i t Contingency messages are to be delivered only when conditions described in the Controller notes have been met. Receipt of a contingency message by a Participant is NOT necessarily indicative of an error, and should not be construed as such. Some data on these messages, for example, is provided only when specific actions have been taken to access the information o'r when a particular extent of play activity is required to demonstrate a exercise objective or to keep the Scenario on its timeline. Radiological and meteorological data, presented in this manual and any information included in the supplemental scenarios will be disseminated by Controllers only when Participants demonstrate the capability to obtain the information from appropriate sources. At no time, unless noted specifically as an exception, will information be provided at a point where it would Nt be available in a real emergency. Controllers shall deliver all information and mc sages in the time and manner described on the message form or as directed at the Controller briefing. Controllers may inject other information or change a message to ensure that the exercise progresses as planned only with the concurrence of the Exercise Coordinator. Participants are expected to " play" the scenario to the extent permitted by their Controller. That is, response to each situation should be as realistic as possible, without simulation, consistent with the maintenance of personal and plant safety. Notifications of, and contact with supervisors, plant management, and off-site agencies will be made in accordance with applicable procedures and instructions (unless a Controller issues instructions to the contrary). Only those simulations identified by a Controller or specifically identified in briefings are permissible. Non-participating organizations may be simulated through the use of the Control Cell. 3.4 Precautions and Limitations This section provides information for all exercise participants regarding guidelines to be followed throughout the conduct of this exercise Prior to initiation of the exercise, pre-exercise briefings will be held to review the exercise process and expectations with , exercise participants.
- 3. /.1 ActualEmergencies it will be the responsibility of any Exercise Controller, Observer, Evaluator, or Participant who becomes aware of an actual emergency to stop exercise response in his/her immediate area and immediately contact 1) the real Control Room and then 2) the Exercise Coordinator. The exercise will be suspended until the real emergency has been appropriately evaluated. The Exercise Coordinator or Exercise Director will make a determination whether to continue, terminate or re-schedule the exercise.
DntiSecnon 30 4 l'olme I, doc
j 3.4.2 Unsafe Conditions At no time during the course of the conduct of this exercise shall any Controller, Evaluator, Observer, Participant, or Inspector undertake any action which would place either an individual or component in an unsafe condition. All personnel are responsible for intervening in such a case and terminating the unsafe activity immediately. No action will be taken which reduces the margin of safety in the olant. 3.4.3 Operating Equipment All (simulated) repair activities associated with the scenario will be simulated with extreme caution around operating equipment. There are to be ng manipulations of any plant operating systems, valves, breakers, or controls in response to this exercise. These are to be simulated, coordinating with your Controller. No pressurization of fire hoses, discharging of fire extinguishers, or initiation of any fire suppression systems are allowed without Controller approval. No such actions will be allowed within plant buildings. 3.4.4 Public Announcements All telephone communications, radio transmissions, and public address j announcements related to the exercise must begin and end with the statement, l "This is a drill" Should a Controller witness an exercise participant not obsemng j this practice, it is the Controller's responsibility to remind the individual of the need to follow this procedure. ! Care must be taken to assure that any non-participating individuals who may observe exercise activities or overhear exercise communications are not misled into believing that an actual emergency exists. Any Controller who bev.:nes aware of an individual or group who may have become alarmed or confused about the situation, should explain the nature and intent of the exercise. 3.4.5 Motor l'ehicle Response All motor vehicle response to this exercise, whether it be ambulance, fire fighting equipment, police / security vehicles or field monitoring teams, shall follow normal l motor vehicle laws, including posted spe:d limits, stop lights / signs, one way l streets, etc. Red lights and/or sirens wih yd be operated on emergency vehicles l for the purposes of the exercise. DnllSection 3 0 5- Volm e1. doc i l
, 3.5 Abbreviations AC Auxiliary Condensate ACB Air Circuit Breaker 1
ACAD Atmosphere Containment Atmosphere Dilution ! ACD Auxiliary Condensate Drains l ACRS Advison Committee on Reactor Safeguards ADS Automatic Depressurization System ALARA As Low As Reasonably Achievable ) ALRW Augmented Liquid Radwaste ANN Annunciator AOG Augmented Off Gas i AOV Air Operated Valve l APRM Average Power Range Monitor ! AR Air Removal { ARM Area Radiation Monitor AS Auxiliary Steam ASB Auxiliary Steam Boilers ATS Alarm Trip Setting i ATWS Anticipated Transient Without Scram l BF Booster Fan BLDG Building BOP Balance *of Plant BPV Bypass Valve BUCLE Backup Core Limits Evaluation BWR Boiling Water Reactor t CD- Condensate Drain CDP Computer Data Processing CF/CFD Condensate Filter Demineralized CHF Critical Heat Flux CI Chemistry Instrumentation CIC Component Identification Code CM Condensate Makeup CMFLPD Core Maximum Fraction of Limiting Power Density CNS Cooper Nuclear Station CNSNO CNS Number (Used for part numbers only) CP Process Computer CPP Control Power Panel CRDM Control Rod Drive Mechanism CR Control Room CRS Control Room Supervisor j CS Core Spray i CSCS Core Standby Cooling System i CSP Core Spray Pump i DrillSection 30 Iblume Ldoc f
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CST Condensate Storage Tank CW Circulating Water CWP Circulating Water Pump l j DBA Design Basis Accident l DEH Digital Electro-Hydraulic System DG Diesel Generator.
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DPM Disintegrations Per Minute DV Drain Valve or Dump Valve DW Demineralized Water ECCS Emergency Core Cooling Systems ECST Emergency Condensate Storage Tank EDF Equipment Data File EE Electrical Equipment EF Exhaust Fan EOF Emergency Operations Facility EOP Emergency Operating Procedure EPIP Emergency Plan Implementing Procedure EPRI Electric Power Research Institute EQ Equipment Qualification ERP Elevated Release Point ES Extraction Steam ESS Engineered Safeguard System FEMA Federal Emergency Management Agency FO Fuel Oil FP Fire Protection . FPC Fuel Pool Cooling and Cleanup O.E. General Electric or General Emergency GM Geiger-Mueller HAD Heat Actuating Device HCU Hydraulic Control Unit HEPA High Efficiency Particulate Absorber HP Health Physics or High Pressure HPCI High Pressure Coolant Injection HVAC Heating, Ventilating, and Air Conditioning HX Heat Exchanger IA Instrument Air I&C Instrumentation and Controls
- ILRT Integrated Leak Rate Test INPO Institute ofNuclear Power Operations INTK Intake Structure IRM Intermediate Range Monitor JIC Joint Information Center DrillSectwn 30 l'olume 1. doc
LCO Limiting Condition for Operation LER Licensee Event Report LLRT Local Leak Rate Test LOCA Loss ofCoolant Accident LPAP Low Power Alarm Point LPCI Low Pressure Coolant Injection LPSP Low Power Setpoint LPRM Local Power Range Monitor LSA Low Specific Activity MC Main Condensate MCC Motor Control Center MCPR Minimum Critical Power Ratio MOV Motor Operated Valve MPC Maximum Permissible Concentration MS Main Steam MSIV Main Steam Line Isolation Valve MSL Main Steam Line MWR Maintenance Work Request NPPD Nebraska Public Power District NPSH Net Positive Suction Head NRC Nuclear Regulatory Commission NRHX Non-Regenerative Heat Exchanger NSSS Nuclear Steam Supply System OBE Operating Basis Earthquake OG OffGas OPL Operating Plant Limits OSC Operations Support Center PASS Post-Accident Sampling System PC Primary Containment PCIS Primary Containment isolation System P&ID Piping and Instrumentation Drawing PM Preventative Maintenance PMIS Plant Management Information System Q.A. Quality Assurance Q.C. Quality Control REM Rod Block Monitor RCIC Reactor Core Isolation Cooling REC Reactor Equipment Cooling i RF Reactor Feedwater or Recire Fan RFP Reactor Feed Pump RFPT Reactor Feed Pump Turbine ; RHR Residual Heat Removal l RMA Radiation Monitoring - Area 1 RMCS Reactor Manual Control System DnliSection 3 0 -A. l'olume I. doc
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RMP Radiation Monitoring - Process - i j RMV Radiation Monitoring - Valve ' RO Reactor Operator RPIS Rod Position Information System RPS Reactor Protection System l RPV Reactor Pressure Vessel RRP Reactor Recirculation Pump RRMG Reactor Recirculation MG Set RSCS Rod Sequence Control System RTD Resistible Temperature Detector RTS Reactor Trip System RWCU Reactor Water Cleanup RWM Rod Worth Minimizer SA Service Air SDC Shutdown Cooling SDV Scram Discharge Volume SDM Shutdown Margin SGT or SBGT Standby Gas Treatment SJAE Steam Jet Air Ejector SLC Standby Liquid Control SORC Station Operations Review Committee SPDS Safety Parameter Display System SRAB Safety Review and Audit Board SRM Source Range Monitor SRO Senior Reactor Operator SRV Safety /ReliefValve SS Shift Supervisor SSE Safe Shutdown Eanhquake STA Shift Technical Advisor SW Service Water TAF Top Active Fuel (352.56" Above Vessel Bottom) TB Turbine Building TEC Turbine Equipment Cooling TG Turbine Generator TIP Traversing In-Core Probe TLD Thermoluminescent Dosimeter TSC Technical Suppon Center USAR Updated Safety Analysis Report WT Water Treatment l Dnt!Section 3.0 9- l'olume i. doc
j 3.6 Definitions i ALERT: The level of emergency classification which indicates that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS): Failure of the reactor control rods to insert into the core upon a scram signal from the Reactor Protection System or the failure of said system to initiate a SCRAM when Reactor Protection System trip limits have been exceeded. ASSESSMENT ACTIONS: Those actions taken during or after an accident to obtain and process information that is necessary to make decisions to implement specific emergency measures. CONTROL ROOM (CR): The principle on-site location from which the reactor is controlled and from which emergency control is initially exercised. CONTROLLER: A member of the Exercise control group, assigned to one or more activities or functions for the purpose of keeping the action going according to a scenario, resolving scenario discrepancies, and supervising the actions of the participants. CORRECTIVE ACTIONS: Those emergency measures taken to improve or terminate an emergency situation. DECONTAMINATION: The process by which the body or an object is relieved of radioactive substances (contamination). D0%E ASSESSMENT: The process of estimating the amount of radiation a person will potentially receive as a result of exposure to a radiological release. PRILL: A supervised event aimed at evaluating, developing, and maintaining skills in a particular operation. EMERGENCY ACTION LEVELS (EALs): Radiological dose rates; specific contamination levels or airborne, waterborne, or surface-deposited concentrations of radioactivity; or specific plant conditions that may be used as thresholds for initiating specific emergency measures. i DnliSection 30 - 1o . I blume i. doc l
1 EMERGENCY OPERATIONS CENTER (EOC): An emergency response facility from which government officials exercise direction and control. The EOCs are located as follows: State ofNebraska: 1300 Military Road Lincoln, NE State ofMissouri: 1717 Industrial Drive Jefferson City, MO Nemaha County: Auburn County Building Hwy 75 Nonh, Auburn, NE ! Richardson County: County Courthouse (Basement) { Falls City, NE Atchison County: 101 Highway 136 East Rock Port, MO l
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EMERGENCY OPERATIONS FACILITY (EOFh The NPPD emergency response facility from which overall direction and control are exercised for emergencies at CNS. The facility also provides a central point of contact for communications and external (non-NPPD) organizations, and is fully activated fcr emergencies classified as an Alert or higher. l EMERGENCY PLANNING ZONES (EPZsh The land areas encompassed within j approximately 10 and 50 mile radii of CNS, in which protective actions may be necessary to ' protect the public in the event of a nuclear plant accident. The 10 mile zone is referred to as the Plume Exposure EPZ; the 50 mile zone is termed the Ingestion Exposure EPZ. 1 EMERGENCY RESPONSE FACILITY: Any of several on-site and off-site centers which are activated to coordinate emergency actions. Included in this category are the Control Room, Technical Support Center, Operations Support Center, Emergency Operations Facility, Joint Information Center, and State and local Emergency Operations Centers. EVALUATOR: A member of the exercise evaluation group, assigned to one or more activities or functions for the purpose of evaluating and making recommendations for improvement. An evaluator may serve in a dual capacity as both a Controller and Evaluator. EXCLUSION AREA: The area surrounding the CNS in which the NPPD has the authority to determine all activities including exclus:on or removal of persons and property from ! the area during accident conditions.
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EXERCISE: An event which tests the overall functions and capabilities of organizations l involved in responding to an emergency situation An exercise will usually simulate an emergency i that results in off-site radiological releases which require response by off-site authorities. DrillSection 3.0 - 1I . l'olume 1. doc I i
j 1 QENERAL EMERGENCY: The most severe level of emergency classification which indicates that events are in progress or have occurred which involve actual or imminent substantial core degradation or rnelting with potential for loss of containment integrity. Release of radioactive material can be reasonable expected to exceed PAG exposure levels off-site. INGESTION PATHWAY: The exposure mode for which the zone of concern encompasses an area of approximately 50 mile radius from ingestion of contaminated water or foods; such as milk or fresh vegetables. The period of potential exposure could range in length from hours to months. JOINT INFORMATION CENTER DIC): An emergency response facility, staffed by NPPD, local, State, NRC and FEMA officials. The JIC provides a forum and point of contact for a coordinated release of news and information to the news media, general public, district employees and special interest groups. OBSERVER: An individual authorized to observe the Exercise, but is not authorized to interact with the participants. OFF-SITE: All areas outside the Protected Area (the area outside the fence. May also be used to refer to areas over which NPPD has no jurisdiction or control over persons' actions. For example, when referring to a release 'off-site' OFF-SITE would be synonymous with OWNER-CONTROLLED AREA (OCA), below. ON-SITE: All areas within the Protected Area (the area inside the fence) surrounding CNS. OFF-SITE DOWNWIND SURVEY TEAMS (also called Downwind Survey teams): Two-person teams responsible for monitoring radiation levels in the environment and collecting soil, air, vegetation, snow, and water samples for laboratory analysis OPERATIONS SUPPORT CENTER (OSC): An on-site emergency response facility which provides a location where emergency response teams can be assembled and coordinated during an emergency. OWNER-CONTROLLED AREA: The area around the CNS that is owned /and to which the access controlled, by NPPD. PARTICIPANT: Any individual (CNS, NPPD personnel, or individual from off-site organization and agency) who is assigned to perform functions of the emergency response organization, as described in the appropriate Emergency Plan and Emergency Plan implementing Procedures. DntiSectwn 3.0 12 Volume 1. doc u-_----_------------_------------- - - - . - - - - - - - -
PLUME EXPOSURE PATHWAY: The exposure mode for which the zone of concern encompasses an area of approximately a 10 ml:e radius around CNS. The principle exposure i sources in this area: 1) whole body external exposure to gamma radiation from the plume and l deposited material, and 2) inhalation exposure from the passing radioactive plume. The period of potential exposure could range from hours to days. POPULATION AT RISK: Those persons for whom protective actions would be taken. PROTECTED AREA: The area within the Site Boundary encompassed by physical barriers and to which access is controlled for security purposes. PROTECTIVE ACTION: Those emergency measures taken after an accident or an l uncontrolled release of radioactive materials has occurred, for the purpose of preventing or minimizing radiological exposures to personnel that would otherwise occur. PROTECTIVE ACTION RECOMMENDATION (PAR): Those emergency measures recommended by NPPD to off-site governmental authorities after an accident or an uncontrolled release of radioactive materials has occurred, for the purpose of preventing or minimizing radiological exposures to personnel that would otherwise occur. ! PROTECTIVE ACTION GUIDES (PAGs): Projected radiological doses to individuals in the general population which warrant protective action following a release of radioactive material. SITE AREA EMERGENCY: The level of emergency classification which indicates that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases of radioactive material are not expected to exceed Protection Action Guide (PAG) exposure levels, except within the Site Boundary. TECHNICAL SUPPORT CENTER (TSC): An on-site emergency response facility for use by technical and management personnelin support of the command and control functions executed in the Control Room. UNUSUAL EVENT: The lowest level of emergency classification, which indicates that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. I Dn'llSecnon 30 - 13 I'olume I. doc l l
3.7 References 3.7.1 CNS Emergency Plan - Nebraska Public Power District 3.7.2 CNS Emergency Plan Implementing Procedures 3.7.3 CNS Technical Specifications 3.7.4 CNS Updated Safety Analysis Report 3.7.510 CFR 50.47,50.54 and Appendix E 3.7.6 NUREG-0654/ FEMA-REP-1, Rev.1 3.7.7 CNS Piping and Instrumentation Drawings l [ t DrillSection 3 0 . ]4 L'olsome 1. doc
I
- 4. CONTROLLER / EVALUATOR INFORMATION 4.1 Controller / Evaluator Organization >
j
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l Controller / Evaluator organization assignments are listed in Table 4.1-1 !' 4.2 GeneralInformation I Each Controller / Evaluator should be fami!!ar with the following: { l i 4.2.1 The objectives of the Exercise (Section 2.0). 1 4.2.2 Applicable precautions and limitations (Section 3.0). 4.2.3 The exercise scenario, including the initial conditions and the expected course of action to be taken (Section 7.0). 4.2.4 The various plant locations to be involved in the scenario and specific items to be observed at those locations. 4.2.5 The evaluation checklists. I 4.3 Controlier Instructions l 4.3.1 Controllers will position themselves at their assigned locations 30 minutes prior to the activation of the facility or team for which they have responsibility. 4.3.2 Communications will be tested prior to exercise commencement. All facility clocks are to be synchronized with the Simulator clock.' 4.3.3 All Controllers will comply with instructions from their Lead Facility Controller and Exercise Coordinator. 4.3.4 No messages shall be delivered out of seauence or other than as written unless authorized by the Exercise Coordinator. 4.3.5 Controllers will nel provide information to the Participants regarding scenario progression or resolution of problems encountered in the course of the simulated emergency. The exercise participants are expected to obtain information through their own organizations and exercise their own judgment in determmmg response actions and resolving problems. Eiriu Section 4.0 l'olume 1. doc I
J' CONTROLLER / EVALUATOR ORGANIZATION TABLE 4.1-1 Drill Director,,,,,, ,, , ,,, , , , , , , , , , , ,, , ,, Terry Brown Drill Coordinator., ,, , , , , , , , , , , , , , , , , , , , , , , Bryant Pergerson CONTROL CELL: Lead Control Cell Coordinator,,,,,,,,, ,, , , , , , , ,,, , , Bryant Pergerson Simulator Control Cell ,,,,, ,, , , , , , , , , , , , , , , , , , , , Dave Werner Simulator Control Cell ,,,, , ,,,, ,,,,, , , , ,, , , , , , , , , , ,, ,, Don Olson Simulator Control Cell ,, ,,,,,,, ,,,,,, ,, ,,, ,,,, , , , , , , ,, , Mark Kaul SIMULATOR: Lead Controller... , , , , ,,, , , , ,, , , Ed Jackson ( i Lead Evaluator ,, '
. . . , , , , , , , , , , , , , , , , , , , ,, , Dave Vanderkamp Communications CE , ,,, , , , , , , , , .. Wayne Wicks l
TSC: Lead Controller, , ,, ,,, , ,,, ,,, , , ,, ,,, , , Kent Sutton Lead Evaluator , , , , , , , , , , , , , , ,,,, ,, , , ,, , . Mike Krumland Engineering Team CE , , , , , , , , , . , , , , , , ,, John Lindinger Security C/E,,, ,, ,,, ,,,, , ,,, , , ,, , , , , , , , ,, Ron Koepel Security C/E., ,,,, ,,,, ,, ,, , , , , , , , , , , , , Pat Carlock OSC: , Lead Controller, , , , , , , , , , , . ,,, ,,, ,, Chris Sunderman
' Lead Evaluator,, , , , , , , , , , , Mark Ward Ops C/E ., ,, , , , , ,, , , ,, ,, , , , Kris Peterson l
Ops C/E ... ,, , , , , , ,,,, ., ,, ,, ,,, John Shrader Ops C/E ... ,,,,,, , Chris Volk
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RP C/E,,,,,,,,,, ,,,, ,,, ,, , , , , , , , , , , , , , ,,,, , , , ,,, , Bill Williams RP C/E,,,,, , ,, , , , , , , , , , , , , ,, .. John Fall.s RP C/E,, ,, , , , , , , ,,, ,, , , , , , . Bill Chapin RP C/E., ,, , , , ,, , , , Joe Dixon PASS / Chemistry Controller,. .. Mark Uhri I&C Maint CE , , ,
. Jim Rassmussen I&C Maint C/E . Ed Stuckenholtz Elect Maint CE , .Doyle Oaks Elect Maint CE , Bernie Handley Mech Maint CE . , , Corky Reimers Mech Maint C/E , ,
. Rod Pebley Fire Brigade CE , ,
. John Shrader l EOF:
Lead Controller, ( . Glen Seeman DrillSection 4.0 3 I'olume 1. doc _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ .
Lead Evaluator........ . , , , , , , ,, ,, , , . . Terry Brown Dose Assessment CE.., .. ,, ,,,,,,, , , . , , . . . . .. ,,,, Joe Bednar Communications CE...... .. ,,,, .. . ,,, , ... , , , , ,,, ,, , ,, Wayne Wicks CNS Downwind Survey Team 1 CE , , . . . , , , , , , , Gerald Grotrian CNS Downwind Survey Team 2 CE.. .. ,, . , , . . . . . Jack Frary Nebraska Downwind Survey Team 1 CE,. ,,, , ,, , , ,,Duane Pavel Nebraska Downwind Survey Team 2 C/E., , ,, , , ,, .. Sterling Bray Missouri Downwind Survey Team 1 CE., ,,
... Kurt Kent Missouri Downwind Survey Team 2 CE., , , ,To be determined JIC:
1 Lead Controller................ , . . , , , , . . . ,,,, ,, , .To be determined
' Lead Evaluator... . . . . . . . . . , , , , , , , , . , , , , , , , ., , , , ,, , , Larry Linder Rumor Control CE ., ,,, . .. ... , , , .., ,,, , ,
.To be determined Mock Media Lead Controller. , ,, , , ,
.To be d ,termined Mock Media....... , .. , , , , ,
.To be de: ermined Mock Media... , , , , ,, , , , , , , , ,, . To be determined Mock Media... , ,, . ,, ,, , , , , .,, , ..To be determined Mock Media,, , , ,, ,, , , , , ,, , , , ,To be determined Mock Media..., , ,, , , , .To be determined OTHER:
NOTE: Some personnel may be reassigned to meet exercise needs. { i i 1 l DrillSection 4.0 -4 I'olume 1. doc I l l
4.3.6 In the event a Participant insists that certain parts of the scenario are unrealistic, Controllers have authority to remind Participants that the purpose of the exercise is to demonstrate the effectiveness of the Emergency Plan if an emergency occurred. The Controller may clarify any questicu regarding scenario content. 4.4 Evaluator Instructions Each Evaluator will take detailed notes regarding the orogress of the exercise and resoonse of the exercise canicioants at their assigned locati.p_nui. r Each Evaluator should note arrival and departure times of participants, times when major activities or milestones occur, and problem areas encountered. Evaluators' comments will be used to reconstruct the exercise chronology and prepare a written evaluation of the exercise. Evaluation criteria are provided to the Controller / Evaluator organization. These are to be completed and provided to the Exercise Coordinator at the conclusion of the exercise. 4.5 Simulator Instructions The simulator will be relied on primarily for data generation and plant response interactions with the Control Room crew. Should it malfunction or go off-line (e.g., a loss of power to the Training Center), the Exercise Coordinator has several options to choose from. They include: stopping the exercise and conducting it the following day (provided Simulator repairs can be performed); completing the exercise using the data sheets provided in the Exercise Manual; or ending the exercise if most of the objectives have been demonstrated. (Unmet objectives would be re-scheduled for a later date.) DrillSection 4.0 -2 Mume Ldoc
l l l l l
- 5. PARTICIPANT INFORMATION i
5.1 GeneralInformation This section provides guidelines for all exercise Participants, which should be followed throughout the conduct of the exercise. A pre-exercise briefing will be held for Participants to review the exercise process, including " Precaution and Limitations" in Section 3.4, and the following information. The success of the exercise is largely dependent upon Participant reaction, Participant i knowledge of their appropriate Emergency Plan and Implementing Procedures, and an understanding of the purpose of the exercise. Initial conditions which will affect Participant action or reaction will be provided to the Participants at the time the exercise begins. However, most of the elements of the exercise play will be introduced through the use of controlled casualties on the " live" simulator. Participants, therefore, are responsible for initiating actions during the exercise in accordance with instructions for their particular function. Each Participant will advise his/her Controller prior to performing required emergency actions during the simulated activities to ensure that the Participant is credited for his/her actions. t Participants are reminded not to bc excessively critical with the mechanics or cause of the exercise scenario. This exercise is desianed to evaluate the Emergency Plan. Implementing Procedures. and the Emercency Response Organization. Additionally, the exercise is a training vehicle for NPPD personnel to practice coordination with outside organizations in a simulated emergency environment. Participants should note any needed improvements which come to their attention during the exercise and submit them to the appropriate Controller at the conclusion of the exercise. i 1 5.2 Participant Guidelines 5.2.1 Maintain a serious, professional attitude throughout the exercise. 5.2.2 Teamwork is essentiall Do yourjob and be conscious of the needs of others 5.2.3 Think "outside the box" and look for all possible solutions or consequences of events. Maintain the " big picture" of what is happening. 5.2.4 Identify yourself by name and function to the Controller b. your area. 5.2.5 If you are entering normal nuclear station radiation areas, observe all rules and procedures. No one (including Controllers)is exempt from normal station radiological oractices and procedures. NOTE: DO NOT ENTER ACTUAL lilGil RADIATION AREAS IN Tile PLANTt FOLLOW ALARA PRINCIPLES. I Drill Section 5 0 1 i Volume i Doc j i i
I I i l 5.2.6 Observe all normal security orocedures. All normal security procedures are in i effect without exception. If a security condition arises, obey immediately the directions of Security Guards.
$.2.7 Initiate actions in accordance with instructions and responsibilities.
5.2.8 Communications should be concise and formal with use of abbreviations minimized. Always include "This is a drill" 5.2.9 i Use and demonstrate knowledge of the Emergency Plan and Implementing Procedures. 5.2.10 No action will be taken which reduces the margin of safety in the plant. No other actions will be simulated without Controller approval. 5.2.11 Keep a list ofitems you believe will improve the Emergency Plan and/or procedures. Provide this to your Controller / Evaluator at the end of the exercise. 5.2.12 Remember, one of the main purposes of a exercise is for you to assure yourself that you are adequately prepared. Areas for improvement or lessons learned, when identified, will improve your overall emergency preparedness. l l l I l l l I ( Drill Section 5.0 -2 Vohime i Doc
- 6. SCHEDULE OF EVENTS 6.1 Times and Places Event Elacs Time p_gjs Exercise Controller / Auditorium 10:00-12:00 June 8 EvaluatorInitial Walkthrough NRC Entrance EOF TBA June 8 and Facility walkthrough Exercise Participant Auditorium 15:00-16:00 June 8 Briefing
' Conduct ofExercise Various All Day June 9 Participant Critiques ERFs (immediately after exercise)
FaciF:y Evaluator Critique Each ERF, (immediately after Participant Critique) sessions Lead Evaluator Critique TBA 09.00 June 10 FEMA Exit with Auditorium TBA June 10 States / Counties Exercise Critique TBD 08:00-09:00 JuneJl Presentation to NRC Exercise Critique TBD 09:00-10:00 June 1I by NRC and exit FEMA Public meeting Auditorium 12:30 June 11 Participant De-brief Auditorium 13:00 June 16 DnilSection 6.0 I-l'olume 1. doc
6.2 TravelInformation/ Permission to Observe For prior arrangements, questions, or permission to observe, contact: Bryant Pergerson Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 (402) 825-5573 Airoorts
- 1. Omaha, NE - Approximately 75 miles. From airport, take Route 75 South
(~2 mi), Route 6 East (~1 mi), Interstate 29 South (~65 mi), Route 136 West to Brownville (~5 mi), follow signs to Cooper Nuclear Station (~2 mi).
- 2. Kansas City, MO - Approximately 90 miles. From airport, go East, take Interstate 29 North (~80 mi), Route 136 West to Brownville (~5 mi),
follow signs to Cooper Nuclear Station (~2 mi). Motels Name Phone # Distance to Plant
- 1. Arbor Manor (402) 274-3663 10 minutes I Auburn, NE
- 2. Auburn Inn (402) 274-3143 10 minutes Auburn, NE
- 3. Palmer House (402)274-319; 15 minutes Auburn, NE
- 4. Oak Grove Inn (816) 744-5357 15 minutes Rock Port, MO
- 5. Rock Pon Inn (816) 744-6282 15 minutes !
I Rock Port, MO l l Food: A contract food service provides hot breakfast and lunch, weekdays only. There I are also a number of vending machines on-site and in the Training building (off-site). In 1 addition there are numerous small restaurants in nearby communities. DnliSection 6.0 2 yoj,,, ygo, !
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i June 9,1998 !
TABLE OF CONTENTS VOLUhfE2 CONFIDENTIAL ! SCENARIO SPECIFIC INFORMATION l 7. SCENARIO OVERVIEW / OPERATIONS INFORMATION 7.1 Scoping Document 7.2 Simulator Guide (SIMGUIDE) 7.3 Narrative Summary l 7.4 Master Scenario Events List 7.5 Exercise Critique Notes
- 8. ON-SITE RADIOLOGICAL DATA 8.1 Radiological Summary 8.2 Release Source Terms 8.3 Reactcc Water Activity / PASS data 8.4 Area Radiological Maps (Direct radiation) and Airborne concentrations
- 9. OFF-SITE RADIOLOGICAL DATA 05 site Radiological Survey Team Controller Data Sheets 9.1 0$ site Release (initial phase) 9.2 05 site Release (second phase) 9.3 05 site Release (final phase)
- 10. OSC MISSION PACKAGES
- 11. BACKUP DATA (IfSimulator fails) 11.1 PMIS-04 Ops Data i
11.2 PMIS-05 ARM Rad Data {
- 12. EXERCISE MESSAGE CARDS (including Initial Conditions)
- 13. METEOROLOGICAL DATA
)
- 14. JOINT INFORMATION CENTER DATA
- 15. SCENARIO BACKGROUND INFORMATION Tab.!e of Contents for Sections 1-6 are contained in Volume 1 of this Exercise Manual.
)
I 1 1 I \ oriit secison 7.o 1- votume 2. soc k l
SCENARIO OVERVIEW / OPERATIONS INFORMATION l 7.1 Scoping Document Extent of Play / Scoping document The following checklist should be completed to establish the extent of play for each drill / exercise i The completed checklist will be used by the scenario development team as the design critexia f the development of the drill / exercise. Exercise
Title:
CNS020-98-03 Drill / Exercise Date: June 9,1998 Check each function to be demonstrated: Annotate as needed. NPPD Facilities / Functional Areas to be activated: [X] Simulator [] Control Room TSC [X] [X] OSC [X] EOF [X] In-plant repair teams i [X] On-site monitoring teams [X] Downwind field monitoring teams [X] Joint Information Center (JIC) l [X] Public Affairs Duty Officer (PADO) [] Load Dispatcher (ifrequired by scenario) [X] CAS (needed for assembly and accountability) [] Other: State / Local Governments: [X] State ofNebraska Full [X] State ofMissouri Full [] State oflowa [] State ofKansas [X1 Nemaha County . Full [X] Atchison County Full [X] Richardson County Full [- ] Otoe County [] Other: i DrillSection 7,1 Volume 2. doc
O Federal Government: [X] NRC (Headquarters) [ ] Calls'only [X] NRC (Region) [X] NRC (Resident) [X] NRC (Site Response Team) [X] FEMA [] Other: Medical Response: [] On-site: [] Off-site: [] Nemaha County Hospital [] University of Nebraska Medical Center [] Other: [] Transportation: [] Contaminated Personnel: How many? Emergency Notification Systems: [X] Emergency Alarm (via Gaitronics) [] Siren System [X] Simulated [X] Emergency Alert System (EAS) [ ] Simulated - [] Pagers [ ] Simulated [] Automated Notification System [] Other: Computer Systems: [X] Simulator- [X] PMIS [X] CNS DOSE [] Other: Simulator Communications: ) PBX telephones { [ ] Simulator booth [X] Cross-tied to Live Line
- GAITRONICS .
[ ] Simulator booth [X] Crost. tied to Live Line ENS (FTS) telephone [ ] Simulator booth [X] Cross-tied to Live Line Call-back phone [ ] Simulator booth [X] Cross-tied to Live Line Radio console [ ] Simulator booth [X] Cross-tied to Live Line State Notification phone [ ] Simulator booth [X] Cross-tied to Live Line i DrillSection 7.1 -3 i Volume 2. doc l
l Degree ofSimulation: [] Anti-Cs: [X) first entry, each person [ ] all entries l [X] Respirators / SCBA (scenario dependent) [X] one respirator per team, including communications, for one bottle. [ ] other: [X] Assembly & Accountability: [] Site Evacuation: [X] Simulated [] KI(simulated) but must include possession or demonstration ofdistribution and approval [X) Tools to worksite [X) Parts to worksite (time constraint for mini-drill) [ ] use process, but do not issue parts Operations Data Requirements: (OPS SDC representative) [X) Prepare work packages for work-in-progress [X) Previous Shift information (Shift Turnover log) [X) Initial Conditions [X] Backup Data and Exercise Messages [X] Hardcopy data (PMIS Screens) [] Graphs of affected parameters Radiological Data Requirements: (RAD SDC representative) [X] Prepare previous chemistry data for initial conditions [X) PASS sample data [] Other Chemistry data [X] In-plant radiation monitors [X] In-plant survey data: , [X] dose rate l [X) airborne sampling data [ ] smear data [X] CAMS [X) On-site out-of-plant data [X] dose rate [X) airbome sampling data [ ] smear data l DrillSection 7.1 4-Volume 2 doc \ l
[X] Off-site monitoring data [X] dose rate l [X] airborne sampling data t- [ ] smear data j [] soil [ ] water [ ] vegetation [ ] liquid [] Ingestion Pathway data l [] Special Off-site dose requirements: (to meet FEMA State objectives) [X] None Special Meteorological Data Requirements: [X] None Wind Direction (from): deg. Wind shift?: [X] Yes [ ] No Predominant Stability Class: [ ]A [ ]B [ ]C [X]D [ ]E [ ]F [ ]G [X] NWS Information [X] Drill / exercise findings will be presented to Management Review Board [] List NRC open items to be closed: [] List FEMA open items to be closed: Other Drill / Exercise Requirements: [X] QA will evaluate drill l [X] Off site observers l Drill Section 7.1 -S- Volume 2. doc
l
*** CONFIDENTIAL **
- 1998 CNS Biennial Exercise Simulator
. . . . . . . . . . . . . . . . . . . . . . . . . . . .......................... . . . . . . . . . . . .G u i d e Note: The exercise will be conducted with the Cooper Plant Simulator in the interactive mode. Times given are for planning purposes only. Actual times may vary due to dynamic response of the operators on the Simulator.
SIMULATOR SETUP Modify constant (cukadm9)from 0.837599 to 4for RWCU leak rateflow JC-184 IC-18 (Basic setup) Batch File EPIP/98-01 Tag HPCI out anddose and deenergize HPCI-MO-15 & 16 M' CRDpump in service 0745 The drill begins with the plant at 100% power. The Operations shin will take the watch at approximately 0745. Initial Plant Conditions: The plant is at 100% (2381 MWt) on day 325 of a continuous run. The plant is preparing to shutdown for refueling outage in 14 days. Equioment Out of Service: HPCI is tagged out in day 3 of a 5 day Outage. The turbine is uncoupled. Meteorological Information: Forecast: - Weather is clear Wind Direction from 320 350 degrees Wind Speed 10-20 mph Temperature High 75 Low 55 A cold front is expected to pass through the area around noontime. Winds may vary generally from the west Conditions at time of release: Wind Direction from 330 degrees Wind speed 13 mph Temperature 70 degrees Stability class D A wind shin will occur at approximately 1230 with wind direction from 260 Drill Section 7.2 1 Rev 0
9283 Unusual Event The Control Room receives a report of a fire located at lunch trailer within the Protected Area. The fire lasts longer than 10 minutes. The Shift Supervisor should declare an Unusual Event based on a fire lasting longer than 10 minutes within the Protected Area per EAL 5.1.1. 98G Alert insert Trg! 1 to activate malfunction HV02b at 100% severity A seismic alarm will be received. The Controller will report to the operator that the i seismic monitor reading is .12g (moderate tremor). The ED should declare an Alert based on greater than .lg on seismic instrumentation per EAL 7.2.1. This will require a controlled plant shutdown per procedure 2.1.4. L The System Dispatcher will call and request Cooper shutdown slowly as grid conditions are serious due to several plants tripping off-line due to the seismic event. The 9ispatcher will request current power level maintained for 30 minutes fellowed by a powreduction ( of 50 MWe every 30 minutes. Plant Management has received a request from the Governor's Office to keep Cooper on-line as long as possible without violating federal regulations. When Civil Engineers or1& C come in to replace seismic tape, delete malfunction HV02b. t Continnenev Over the next 15 to 45 minutes, the Operations crew should reduce power by taking the { Recirculation pumps back to minimum. When reactor power reaches approximately 80%, ' with Recirculation pumps at minimum, the annunciators on 9-5-1 and 9-5-2 will begin to flash. The annunciator failures will be a result of the earthquake and caused by trash in multiple relays causing the relays to continuously flash. The operators should stop all plant i transient activities until the annunciators can be repaired. This will become an additional 1 classification after 15 minutes. The annunciators may.be a success mission for the OSC. At ! i approximately 1005, the cards will be reinstalled / replaced and annunciators will be ' restored to normal operation. 850 Nitrogen Leak At 0850, a mock Security guard calls to report a nitrogen leak a valve on the Nitrogen Tank is leaking downstream ofH283C. ! 0925 Security Challenge to Protected Area l At 0915, a disgruntled former Security Guard will call making threats to the plant. He L then arrives at the plant at approximately 0925 and crashes through the Protected Area Fence into the On-site Warehouse. Security should respond and take protective actions including subduing the aggressor. Drill Section 7.2 2 Rev0 L
1912 Site Are? Emergency Insert Trgt 2 to activate malfunctions XV02a at 20% severity and CUO9 at 75% severity after a 60 second time delay. A second seismic event occurs (after shock) with a magnitude of.08g. The Reactor Water Clean Up system (RWCU) will suffer a small line break into secondary containment on the 93 l' elevation inside of the Heat Exchanger room. An RP will call the Control Room and report steam on the 931' in the area of the South West 931'. Since power level should be near 80%, radiation data will be available ifRP responds to investigate the steam leak. Radiation levels will be minimal since there has been no fuel failure and the readings are based on normal coolant activity. When Civil Engineers or I& C come in to replace seismic upe, delete malfunction HV02a. When Operators attempt to isolate the steam leak using RWCU-MO-15 (Inboard valve) and RWCU-MO-18 (Outboard valve), both valves remain open creating a loss of2 of 3 Fission Product Barriers. The ED in the EOF should declare a Site Area Emergency per EAL 2.3.3. The Operations crew should also initiate a manual reactor scram. When the scram occurs there will be a spurious Group 1 Isolation (closure of MSIVs). When the Operations crew attempts to operate Safety Relief Valves (SRVs) to reduce reactor pressure, all SRVs will fail to operate due to loss of Control Power caused by tripping of supply breakers in the DC Distribution Panels from faults on SRV Logic bus. SRV failure to operate will prevent reactor pressure from being reduced. SRVs will still lift on over-pressure causing a slow loss ofinventory.
" Alpha" Control Rod Drive (CRD) pump fails. The " Bravo" pump may be started manually. " Alpha" Standby Liquid Control (SLC) pump relief valve lifts causing the pump to run but not inject.
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'100%.
Approximately 1 hour and 15 minutes after the RWCU leak, the Reactor Core Isolation Cooling (RCIC) fails due to Governor Control problems. If an Operator is dispatched, he will fmd the Governor leaking oil and RCIC will have tripped. 1100-1130 NRC Initial Site Team is expected to arrive on plant site. 1100-1130 FEMA Evaluators FEMA Evaluators should suggest a shift change during this time for agencies needing to demonstrate this objective. l Drill Section 7.2 3 Rev0
l lig[ General Emergency ( Insert Trg/15 to activate malfunctions CV03 at 100% Rm03dd Rm0!ee i Upon reaching Top of Active Fuel (TAF), a fuel failure will result, as the core is uncovered. By procedure, the Control Room Operators are required to Alternate Emergency Depressurize (AEDP) per ESP-5.8.2, the reactor to the Turbine Condenser (in l the Turbine Building) by opening the Bypass Valves to reduce reactor pressure allowing water injection using low pressure systems. Low pressure water systems will function as designed to cover the core. When one MSL is unisolatedInsert Trg! 7 to activate MSIO at 10% A Turbine Condenser leak will occur (due to the seismic event). The Control Room w be unable to draw a vacuum on the Condenser. Due to no vacuum, the Turbine Rupture diaphragms will rupture causing a release into the Turbine building. Condensate pumps and Condensate booster pumps may be tripped to minimize cooling of the steam into the condenser. Trip Condensatepumps and Condensate boosterpumps as necessary. 1210 Off-site Release This vent path will create a monitored and unfiltered release from the Turbine Building through the Turbine Building Ventilation system. Fuel failure may not be evident on Control Room instrumentation until the reactor is depressurized due to the failed fuel being contained within the vessel. When MSIVs and bypass valves are opened per AEDP, the Main Steam Line rad monitors will rise and Drywell High Range Radiation monitors will exceed 2500 R/hr under LOCA conditions. This will indicate that the last Fission Product Barrier has been breached. The ED shou declare a General Emergency based on EAL 2.4.1. The ED may also declare the General Emergency when TAF is reached, before the AEDP is completed, based on a loss of 2 of 3 Fission Product Barriers with the potential for the loss of the third (EAL 2.4.1). i 1230 Wind Shift Wind direction will be from 330 degrees at 13 mph. This will cause the plume to move in the general direction toward Indian Cave State Park. At 1230, a wind shift will occur causing the wind to come from 260 toward Rock Port, Missouri. 1400 Termination The exercise will be terminated at approximately 1400. If all objectives have been demonstrated, the exercise may be terminated prior to this time at the discretion of the Drill Coordinator. 1410 Participant Critique Drill Section 7.2 4 Rev0
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*** CONFIDENTIAL * *
- 1998 CNS Biennial Exercise Narrative Summ
...........................................ary ......................
Note: This exercise is a full participation exercise with the States of Nebraska and Missouri, the Counties ofNemaha and Richardson in Nebraska, and Atchison County in Missouri. l The exercise will be conducted with the Cooper Plant Simulator in the interactive mode. Times given are for planning purposes only. Actual times may vary due to dynamic response of the operators on the Simulator. 0745 The drill begins with the plant at 100% power. The Operations shift will take the watch at approximately 0745. Initial Plagf Conditions: The plant is at 100% on day 325 of a continuous run. The plant is preparing to shutdown for a refueling outage in 14 days. Equioment Out of Service: HPCIis tagged out in day 3 of a 5 day Outage. The turbine is uncoupled. Meteorological Information: Forecast: Weather is clear Wind Direction from 320-350 degrees Wind Speed 10-20 mph Temperature High 75 Low 55 A cold front is expected to pass through the area around noontime. Winds may vary generally from the west Conditions at time of release: Wind Direction from 330 degrees Wind speed 13 mph Temperature 70 degrees Stability class D A wind shift will occur at approximately 1230 with wind direction from 260 l I I Drill Section 7.3 i Rev0
0755 Unusual Event The Control Room receives a report of a fire located at lunch trailer within the Protected Area. The fire lasts longer than 10 minutes. The Shift Supervisor should declare an Unusual Event based on a fire lasting longer than 10 minutes within the Protected Area per EAL 5.1.1. 0842 Alert l i A seismic alarm will be received. The Controller will repon to the operator that the seismic monitor reading is .12g (moderate tremor). The ED should declare an Alert based on greater than .lg on seismic instrumentation per EAL 7.2.1. This will require a controlled plant shutdown per procedure 2.1.4. j The System Dispatcher will call and request Cooper shutdown slowly as grid conditions are serious due to several plants tripping off-line due to the seismic event. The Dispatcher will request current power level maintained for 30 minutes followed by a power reduction of 50 MWe every 30 minutes. Plant Management has received a request from the Governor's Office to keep Cooper on-line as long as possible without violating federal regulations. l Contingency l Over the next 15 to 45 minutes, the Operations crew should reduce power by taking the Recirculation pumps back to minimum. When reactor power reaches approximately 80%, with Recirculation pumps at minimum, the annunciators on 9-5-1 and 9-5-2 will begin to flash. The annunciator failures will be a result of the earthquake and caused by trash in multiple relsys causing the relays to continuously flash. The operators should stop all plant transient activities until the annunciators can be repaired. This will become an additional classification after 15 minutes. The annunciators may be a success mission for the OSC. At approximately 1005, the cards will be reinstalled / replaced and annunciators will be restored to normal operation. 850 Nitrogen Leak At 0850, a mock Security guard calls to report a nitrogen leak a valve on the Nitrogen Tank is leaking downstream ofH283C. 0925 Security Challenge to Protected Area At 0915, a disgruntled former Security Guard will call naking threats to the plant. He then arrives at the plant at approximately 0925 and crashes through the Protected Area l Fence into the On-site Warehouse. Security should respond and take protective actions including subduing the aggressor. 1017 Site Area Emergency A second seismic event occurs (after shock) with a magnitude of.08g. i The Reactor Water Clean Up system (RWCU) will suffer a small line break into secondary i containment on the 931' elevation inside of the Heat Exchanger room. An RP will call the Drill Section 7.3 2 Rev 0
Control Room and report steam on the 931' in the area of the South West 931'. Since power level should be near 80%, radiation data will be available if RP responds to investigate the steam leak. Radiation levels will be minimal since there has been no fuel. failure and the readings are based on normal coolant activity. When Operators attempt to isolate the steam leak using RWCU-MO-15 (Inboard valve) and RWCU-MO-18 (Outboard valve), both valves remain open creating a loss of 2 of 3 Fission Product Barriers. The ED in the EOF should declare a Site Area Emergency per EAL 2.3.3. The Operations crew should also initiate a manual reactor scram. When the scram occurs there will be a spurious Group 1 Isolation (closure ofMSIVs). When the Operations crew attempts to operate Safety Relief Valves (SRVs) to reduce reactor pressure, all SRVs will fail to operate due to loss of Control Power caused by tripping of supply breakers in the DC Distribution Panels from faults on SRV Logic bus. SRV failure to operate will prevent reactor pressure from being reduced. SRVs will still lift on over-pressure causing a slow loss ofinventory.
' " Alpha" Control Rod Drive (CRD) pump fails. The " Bravo" pump may be started manually.
" Alpha" Standby Liquid Control (SLC) pump relief valve lifts causing the pump to run but not inject.
Approximately 1 hour and 15 minutes after the RWCU leak, the Reactor Core Isolation Cooling (RCIC) fails due to Governor Control problems. If an Operator is dispatched, he will find the Governor leaking oil and RCIC will have tripped. 1100-1130 NRC Initial Site Team is expected to arrive en plant site. 1100-1130 FEMA Evaluators FEMA Evaluators should suggest a shift change during this time for agencies needing to demonstrate this objective. 1151 General Emergency Upon reaching Top of Active Fuel (TAF), a fuel failure will result, as the core is uncovered.- By procedure, the Control Room Operators are required to Alternate Emergency Depressurize (AEDP) per ESP-5.8.2, the reactor to the Turbine Condenser (in the Turbine Building) by opening the Bypass Valves to reduce reactor pressure allowing water injection using low pressure systems. Low pressure water systems will function as designed to cover the core. A Turbine Condenser leak will occur (due to the seismic event). The Control Room will be unable to draw a vacuum on the Condenser. Due to no vacuum, the Turbine Rupture diaphragms will rupture causing a release into the Turbine building. Drill Section 7.3 3 Rev 0
Condensate pumps and Condensate booster pumps may be tripped to minimize cooling of : the steam into the condenser. ! lilg Off-site Release This vent path will create a monitored and unfiltered release from the Turbine Building through the Turbine Building Ventilation system. An elevated release from the Stack will occur accounting for approximately 10% of the release magnitude. This release path will be both monitored and filtered. Fuel failure may not be evident on Control Room instmmentation until the reactor is depressurized due to the failed fuel being contained within the vessel. When MSIVs and bypass valves are opened per AEDP, the Main Steam Line rad monitors will rise and Drywell High Range Radiation monitors will exceed 2500 R/hr under LOCA conditions. i This will indicate that the last Fission Product Barrier has been breached. The ED shou declare a General Emergency based on EAL 2.4.1. The ED may also declare the General Emergency when TAF is reached, before the AEDP is completed, based on a loss of 2 of 3 Fission Product Barriers with the potential for the loss of the third (EAL 2.4.1). Highest estimated radiation levels (CDE) at the nearest sample point to centerline at the site boundary will be approximately 20 Rem /hr 48 minutes after AEDP. Venting will continue until the exercise is terminated. 11}g Wind Shift Wind direction will be from 330 degrees at 13 mph. This will cause the plume to move in the general direction toward Indian Cave State Park. At 1230, a wind shift will occur causing the wm' d to come from 260 toward Rock Port, Missouri. l 1400 Termination The exercise will be terminated at approximately 1400. If all objectives have been demonstrated, the exercise may be terminated prior to this time at the discretion of the j Drill Coordinator. 141g Participant Critique SIMULATOR SETUP IC-184 IC-18 (Basic setup) Batch File EPIP/98-01 HPCI out of service
'A' CRD pump in service I ' Drill Section 7.3 4 Rev 0 1
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