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This Exercise Manual has been developed to provide the basis for the conduct of a simulated radiological accident at the Ginna Station facility located in Ontario, New York.This manual is to be utilized by the Exercise Controllers to initiate, control, and evaluate the activities of the participants in the Exercise.Exercise" la ers" will no have rior knowled e of the na ure of the simula ed incident or an r s thereof such as radiolo ical lume release information includin times content size and weather attern used.This Exercise Manual is the control mechanism for the conduct of the Exercise and consists of two parts, Part I provides a general description and overview of the emergency Exercise.Part II contains the scenario and time schedule of simulated plant conditions.
This Exercise Manual has been developed to provide the basis for the conduct of a simulated radiological accident at the Ginna Station facility located in Ontario, New York.This manual is to be utilized by the Exercise Controllers to initiate, control, and evaluate the activities of the participants in the Exercise.Exercise" la ers" will no have rior knowled e of the na ure of the simula ed incident or an r s thereof such as radiolo ical lume release information includin times content size and weather attern used.This Exercise Manual is the control mechanism for the conduct of the Exercise and consists of two parts, Part I provides a general description and overview of the emergency Exercise.Part II contains the scenario and time schedule of simulated plant conditions.
The Exercise Manual is subject to a limited, controlled distribution.
The Exercise Manual is subject to a limited, controlled distribution.
1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE SCENARIO DEVELOPMENT COMMITTEE" Thomas Alexander Wes Backus Richard Beldue Richard Biedenbach Dan Hudnut James-Knorr Frank Orienter Peter Polfleit James Regan Richard Watts James Zulawski" As authorized by the Emergency Planning Milestone Committee GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS FOREWORD INTRODUCTION SCENARIO DEVELOPMENT COMMITTEE TABLE OF CONTENTS LIST OF FIGURES 1.0 SCOPE AND OBJECTIVES 1.1 1.2 1.3 1.4 Scope Onsite Objectives Summary of Proposed Activities Offsite Proposed Activities
1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE SCENARIO DEVELOPMENT COMMITTEE" Thomas Alexander Wes Backus Richard Beldue Richard Biedenbach Dan Hudnut James-Knorr Frank Orienter Peter Polfleit James Regan Richard Watts James Zulawski" As authorized by the Emergency Planning Milestone Committee GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS FOREWORD INTRODUCTION SCENARIO DEVELOPMENT COMMITTEE TABLE OF CONTENTS LIST OF FIGURES 1.0 SCOPE AND OBJECTIVES 1.1 1.2 1.3 1.4 Scope Onsite Objectives Summary of Proposed Activities Offsite Proposed Activities 2.0 EXERCISE INFORMATION 2.1 Exercise Participants 2.2 Exercise Organization 2.3 Emergency Response Facilities 2.4 Exercise Conduct 2.5 Precautions and Limitations 2.6 Evaluation and Critique 3.0 TRAVEL INFORIVIATION 3.1 Directions to Ginna Station 3.2 Directions to EOF, ESC and JENC 3.3 Accommodations
 
===2.0 EXERCISE===
INFORMATION
 
===2.1 Exercise===
Participants
 
===2.2 Exercise===
Organization
 
===2.3 Emergency===
Response Facilities
 
===2.4 Exercise===
Conduct 2.5 Precautions and Limitations
 
===2.6 Evaluation===
and Critique 3.0 TRAVEL INFORIVIATION
 
===3.1 Directions===
to Ginna Station 3.2 Directions to EOF, ESC and JENC 3.3 Accommodations


==4.0 REFERENCES==
==4.0 REFERENCES==


ABBREVIATIONS-ACRONYMS
ABBREVIATIONS-ACRONYMS 4.1 References 4.2 Abbreviations-Acronyms 5.0 CONTROLLER AND EVALUATOR INFORIVIATION 5.1 5.2 5.3 5.4 5.5 Controller Instructions Evaluation Instructions Personnel Assignments Evaluation Packages Public Information, Rumor Control 5 Spouse Phone Questions 6.0 SCHEDULE OF EVENTS GIN NA STATION 1993 PLUME EXPOSURE EIVIERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)7.0 EXERCISE SCENARIO 7.1 7.2 7.3 7.4 Initial Conditions Onsite Sequence of Events Simulator Set Up Instructions Simulator Use Guidelines 8.0 IVIESSAGE FORIVIS AND PLANT DATA SHEETS 9.0 ONSITE RADIOLOGICAL AND CHEIVIISTRY DATA 9.1 Radiological Summary 9.2 ln-Plant Radiological Data 9.3.Post-Accident Sampling Results 10.0 METEOROLOGICAL AND OFFSITE RADIOLOGICAL DATA 10.1 Meteorological Data 10.2 Field Data and Maps 10.3 Field Air Isotopic Data GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)LIST OF FIGURES SECTION 3.0 Figure 3.1 Figure 3.2 Figure 3.3 Figure 3.4 Figure 3.5 Directions to Ginna Station Map of Rochester and Vicinity Map of Rochester Central Business District Directions to State Emergency Operations Center, Albany Map of State Office Building Campus, Albany SECTION 9.0 Figure 9.1 Figure 9~2 Figure 9~3 Figure 9.4 Figure 9.3 Assumed Source Term Release Vent Concentrations Vs Time Letdown Monitor Reading Vs Time Containment Radiation Vs Time RCS Concentrations Vs Time SECTION 10.0 Figure 10.1 Direction of Plume Figure 10.2 Plume Map (0-1 Mile)Figure 10.3 Large Plume Map (0-10 Mile)
 
===4.1 References===
4.2 Abbreviations-Acronyms
 
==5.0 CONTROLLER==
AND EVALUATOR INFORIVIATION 5.1 5.2 5.3 5.4 5.5 Controller Instructions Evaluation Instructions Personnel Assignments Evaluation Packages Public Information, Rumor Control 5 Spouse Phone Questions 6.0 SCHEDULE OF EVENTS GIN NA STATION 1993 PLUME EXPOSURE EIVIERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)7.0 EXERCISE SCENARIO 7.1 7.2 7.3 7.4 Initial Conditions Onsite Sequence of Events Simulator Set Up Instructions Simulator Use Guidelines
 
===8.0 IVIESSAGE===
FORIVIS AND PLANT DATA SHEETS 9.0 ONSITE RADIOLOGICAL AND CHEIVIISTRY DATA 9.1 Radiological Summary 9.2 ln-Plant Radiological Data 9.3.Post-Accident Sampling Results 10.0 METEOROLOGICAL AND OFFSITE RADIOLOGICAL DATA 10.1 Meteorological Data 10.2 Field Data and Maps 10.3 Field Air Isotopic Data GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)LIST OF FIGURES SECTION 3.0 Figure 3.1 Figure 3.2 Figure 3.3 Figure 3.4 Figure 3.5 Directions to Ginna Station Map of Rochester and Vicinity Map of Rochester Central Business District Directions to State Emergency Operations Center, Albany Map of State Office Building Campus, Albany SECTION 9.0 Figure 9.1 Figure 9~2 Figure 9~3 Figure 9.4 Figure 9.3 Assumed Source Term Release Vent Concentrations Vs Time Letdown Monitor Reading Vs Time Containment Radiation Vs Time RCS Concentrations Vs Time SECTION 10.0 Figure 10.1 Direction of Plume Figure 10.2 Plume Map (0-1 Mile)Figure 10.3 Large Plume Map (0-10 Mile)
GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)LIST OF TABLES SECTION 1.0 Table 1~1 Proposed Onsite Activities SECTION 5.0 Tabl'e 5.1 RG&E Onsite Controller Organization SECTION 7.0 Table 7.1 Simulator Set-up Data for Exercise Scenario (LATER)Table 7.2 Simulator Set-up Data (Rad Monitor Readings)(LATER)Table 7.3 Simulator Use Guidelines (LATER)SECTION 9.0 Table 9~1 Table 9.2 Table 9.3 Table 9.4 Table 9.5 Table 9.6 Table 9.7 Assumed Release Quantities Equilibrium Reactor Coolant Activity Post-Accident Reactor Coolant Samples Post-Accident Containment Atmosphere Samples Post-Accident Containment Sump Samples Continuous Air Monitor Readings (Auxiliary Bldg&TSC)Air Sample Results in TSC and Control Room SECTION 10.0 Table 10.1 Table 10.2 Table 10.3 Table 10.4 Table 10.5 Table 10.6 Forecast Information Plume Arrival/Departure Times Radiological Survey/Sampling Data (In Plume)Post-Plume Ground Survey Data (cpm)Post-Plume Micro-R/hr Data Air Sample Isotopic Analysis Data 1-8 SECTION 1.0 SCOPE AND ORIECTIVES SCOPE AND ONSITE OBJECTIVES
GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)LIST OF TABLES SECTION 1.0 Table 1~1 Proposed Onsite Activities SECTION 5.0 Tabl'e 5.1 RG&E Onsite Controller Organization SECTION 7.0 Table 7.1 Simulator Set-up Data for Exercise Scenario (LATER)Table 7.2 Simulator Set-up Data (Rad Monitor Readings)(LATER)Table 7.3 Simulator Use Guidelines (LATER)SECTION 9.0 Table 9~1 Table 9.2 Table 9.3 Table 9.4 Table 9.5 Table 9.6 Table 9.7 Assumed Release Quantities Equilibrium Reactor Coolant Activity Post-Accident Reactor Coolant Samples Post-Accident Containment Atmosphere Samples Post-Accident Containment Sump Samples Continuous Air Monitor Readings (Auxiliary Bldg&TSC)Air Sample Results in TSC and Control Room SECTION 10.0 Table 10.1 Table 10.2 Table 10.3 Table 10.4 Table 10.5 Table 10.6 Forecast Information Plume Arrival/Departure Times Radiological Survey/Sampling Data (In Plume)Post-Plume Ground Survey Data (cpm)Post-Plume Micro-R/hr Data Air Sample Isotopic Analysis Data 1-8 SECTION 1.0 SCOPE AND ORIECTIVES SCOPE AND ONSITE OBJECTIVES
-PLUIVIE EXPOSURE PATHWAY~Sco e The 1993 Emergency Preparedness Plume Exposure Pathway Exercise will be conducted on a full-participation basis and will simulate accident events culminating in a radiological accident resulting in the activation of onsite and offsite facilities.
-PLUIVIE EXPOSURE PATHWAY~Sco e The 1993 Emergency Preparedness Plume Exposure Pathway Exercise will be conducted on a full-participation basis and will simulate accident events culminating in a radiological accident resulting in the activation of onsite and offsite facilities.
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ITIES-E IPM NT Dl PL Y NDWOR NVIRONME T 2.Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.
ITIES-E IPM NT Dl PL Y NDWOR NVIRONME T 2.Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.
None JNC-I (State only)NI ATI 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.None 10.Demonstrate the capability to promptly alert and notify the public within 4one the 10-mile plume pathway emergency planning zone (EPZ)and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.
None JNC-I (State only)NI ATI 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.None 10.Demonstrate the capability to promptly alert and notify the public within 4one the 10-mile plume pathway emergency planning zone (EPZ)and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.
11.Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instructions to the public.4~ne R N 12.Demonstrate the capability to coordinate the development and dissemination of clear, accurate and timely information to the news medi~'I N()ne R N Y I F RMATI NTR 13.Demonstrate the capability.to establish and operate rumor control in a coordinated and timely manner.brine SECTION 2.0 EXERCISE INFORMA TION  
11.Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instructions to the public.4~ne R N 12.Demonstrate the capability to coordinate the development and dissemination of clear, accurate and timely information to the news medi~'I N()ne R N Y I F RMATI NTR 13.Demonstrate the capability.to establish and operate rumor control in a coordinated and timely manner.brine SECTION 2.0 EXERCISE INFORMA TION 2.0 EXERCISE INFORMATION 2.1 Exercise Partici ants 2.1~1 The participants in the Exercise will include the following:
 
ROCHESTER GAS AND ELECTRIC CORPORATION A.Facilities Mana ement and Su ort Personnel 1.Simulator Control Room 2.Technical Support Center (TSC)3.Operations Support Center (OSC)4.Survey Center (SC)5.Emergency Operations Facility (EOF)6.Joint Emergency News Center (JENC)7.Engineering Support Center (ESC)B.Emer enc Res onse Teams 1.Radiation Survey Teams (RSTs)2.First Aid Team (if necessary) 3.Emergency OSC Teams 4.Security Force 5.Post Accident Sampling System (PASS)Team 6.Chemistry/Health Physics Support 7.Fire Brigade (if necessary) 2.1.2 OFFSITE AGENCIES/ORGANIZATIONS Participation of the following agencies/organizations is expected: A.Federal 1~Nuclear Regulatory Commission 2.Federal Emergency Management Agency 3.National, Weather Service B.State 1.New York State Emergency Management Office 2.New York State Department of Health 3.New York State Police 4.Other Supporting State Agencies C.Local 1.Wayne County 2.Monroe County 3.Other Supporting County Agencies 2-2 2.2 Exercise Or anization The organization for this Exercise will consist of the Exercise Coordinator, the Controllers, the Players and the Observers, as follows: 2.2.1 The Exercise Coordinator will coordinate Exercise preparations including the development of the scenario and controller input messages.He will control all aspects of the conduct of the Exercise, prepare a consolidated evaluation and critique report at the conclusion of the Exercise, and prepare and follow up on an itemized list of corrective actions recommended as a result of the evaluation and critique, 2.2.2~C>>lied I I d f f follows: A.A Lead Controller is assigned to each emergency response facility.The Lead Controller is responsible for all Controller, Evaluator and Observer activities for that facility and, if appropriate, its associated teams.Controllers for teams or sub areas of a facility report to the Lead Controller of that facility.B.The Controllers will deliver"Exercise Messages" to the designated Players at various times and places during the Exercise, inject or deliver additional messages as may be required to initiate the appropriate Player response and keep the Exercise action moving according to the scenario and Exercise objectives, observe the Exercise participants at their assigned locations, and prepare evaluation forms.Controllers/Observers submit written recommendations on corrective actions to the Lead Controller, who in turn summarizes all comments for submittal to the Exercise Coordinator prior to the scheduled critique.The Controllers will be provided with a list of instructions in the Exercise scenario.C.Persons designated as Controllers/Observers for a given function will also be assigned as Evaluators of that function when feasible.Evaluators will record their observations using an evaluation form and provide recommendations on corrective actions to the Lead Controller in whose facility they evaluate exercise performance on the basis of standards or requirements contained in the appropriate Emergency Plan, Implementing Procedures, and Exercise messages as described herein.They will take steps, whenever possible, to collect data on the time qnd motion aspects of the activity observed for post-Exercise use for implementing improvements.
===2.0 EXERCISE===
INFORMATION
 
===2.1 Exercise===
Partici ants 2.1~1 The participants in the Exercise will include the following:
ROCHESTER GAS AND ELECTRIC CORPORATION A.Facilities Mana ement and Su ort Personnel 1.Simulator Control Room 2.Technical Support Center (TSC)3.Operations Support Center (OSC)4.Survey Center (SC)5.Emergency Operations Facility (EOF)6.Joint Emergency News Center (JENC)7.Engineering Support Center (ESC)B.Emer enc Res onse Teams 1.Radiation Survey Teams (RSTs)2.First Aid Team (if necessary) 3.Emergency OSC Teams 4.Security Force 5.Post Accident Sampling System (PASS)Team 6.Chemistry/Health Physics Support 7.Fire Brigade (if necessary)
 
====2.1.2 OFFSITE====
AGENCIES/ORGANIZATIONS Participation of the following agencies/organizations is expected: A.Federal 1~Nuclear Regulatory Commission 2.Federal Emergency Management Agency 3.National, Weather Service B.State 1.New York State Emergency Management Office 2.New York State Department of Health 3.New York State Police 4.Other Supporting State Agencies C.Local 1.Wayne County 2.Monroe County 3.Other Supporting County Agencies 2-2  
 
===2.2 Exercise===
Or anization The organization for this Exercise will consist of the Exercise Coordinator, the Controllers, the Players and the Observers, as follows: 2.2.1 The Exercise Coordinator will coordinate Exercise preparations including the development of the scenario and controller input messages.He will control all aspects of the conduct of the Exercise, prepare a consolidated evaluation and critique report at the conclusion of the Exercise, and prepare and follow up on an itemized list of corrective actions recommended as a result of the evaluation and critique, 2.2.2~C>>lied I I d f f follows: A.A Lead Controller is assigned to each emergency response facility.The Lead Controller is responsible for all Controller, Evaluator and Observer activities for that facility and, if appropriate, its associated teams.Controllers for teams or sub areas of a facility report to the Lead Controller of that facility.B.The Controllers will deliver"Exercise Messages" to the designated Players at various times and places during the Exercise, inject or deliver additional messages as may be required to initiate the appropriate Player response and keep the Exercise action moving according to the scenario and Exercise objectives, observe the Exercise participants at their assigned locations, and prepare evaluation forms.Controllers/Observers submit written recommendations on corrective actions to the Lead Controller, who in turn summarizes all comments for submittal to the Exercise Coordinator prior to the scheduled critique.The Controllers will be provided with a list of instructions in the Exercise scenario.C.Persons designated as Controllers/Observers for a given function will also be assigned as Evaluators of that function when feasible.Evaluators will record their observations using an evaluation form and provide recommendations on corrective actions to the Lead Controller in whose facility they evaluate exercise performance on the basis of standards or requirements contained in the appropriate Emergency Plan, Implementing Procedures, and Exercise messages as described herein.They will take steps, whenever possible, to collect data on the time qnd motion aspects of the activity observed for post-Exercise use for implementing improvements.
2-3 Controllers will be iden ified b wearin reen bad es wi h white let erin s a in"Controller".
2-3 Controllers will be iden ified b wearin reen bad es wi h white let erin s a in"Controller".
2.2.3~Pla ers include Ginna Station and other Rochester Gas and Electric Corporation personnel assigned to perform emergency functions, as described in the Emergency Plan and Implementing Procedures.
2.2.3~Pla ers include Ginna Station and other Rochester Gas and Electric Corporation personnel assigned to perform emergency functions, as described in the Emergency Plan and Implementing Procedures.
Players from offsite organizations and agencies (county, State and private industry)are participants in the Exercise as described in their respective Emergency Plans and Standard Operating Procedures.
Players from offsite organizations and agencies (county, State and private industry)are participants in the Exercise as described in their respective Emergency Plans and Standard Operating Procedures.
 
2.2.4 Observers from the Rochester Gas and Electric Corporation and other organizations may be assigned to participate in the Exercise solely for the purpose of observing/evaluating Exercise activity.They will be provided with orientation information and appropriate Exercise publications.
====2.2.4 Observers====
from the Rochester Gas and Electric Corporation and other organizations may be assigned to participate in the Exercise solely for the purpose of observing/evaluating Exercise activity.They will be provided with orientation information and appropriate Exercise publications.
Observers will be a ro riatel identified b wearin arm bands or bad es.Federal a enc observers will be identified b wearin arm bands or bad es wi h le erin s a in"NRC" or"FEMA".Visitors from the Rochester Gas and Electric Corporation and other organizations may be assigned, on a limited basis, for the sole purpose of observing Exerciseactivities for personal education.
Observers will be a ro riatel identified b wearin arm bands or bad es.Federal a enc observers will be identified b wearin arm bands or bad es wi h le erin s a in"NRC" or"FEMA".Visitors from the Rochester Gas and Electric Corporation and other organizations may be assigned, on a limited basis, for the sole purpose of observing Exerciseactivities for personal education.
They will be provided with orientation information and appropriate Exercise publications.
They will be provided with orientation information and appropriate Exercise publications.
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The simulated emergency will then de-escalate.
The simulated emergency will then de-escalate.
The Recovery Phase will be initiated and the Exercise will then be terminated.
The Recovery Phase will be initiated and the Exercise will then be terminated.
 
2.4.2 Actions Emergency response actions during the simulated emergency will include: recognition and classification of emergency conditions; assessment of onsite/offsite radiological consequences; alert/notification and mobilization of emergency response organizations; implementation of in-Plant corrective actions;activation/operation of emergency response facilities and equipment; preparation of reports, messages and record-keeping; and recommendation of protective actions.2-7 Communications The Exercise will also demonstrate the effective use of communications systems.An actual emergency operation usually requires the extensive use of both telephone and radios.The telephone is the primary means of communication and will be attempted first, with radio as a backup, unless radio is the only means available.
====2.4.2 Actions====
Emergency response actions during the simulated emergency will include: recognition and classification of emergency conditions; assessment of onsite/offsite radiological consequences; alert/notification and mobilization of emergency response organizations; implementation of in-Plant corrective actions;activation/operation of emergency response facilities and equipment; preparation of reports, messages and record-keeping; and recommendation of protective actions.2-7 Communications The Exercise will also demonstrate the effective use of communications systems.An actual emergency operation usually requires the extensive use of both telephone and radios.The telephone is the primary means of communication and will be attempted first, with radio as a backup, unless radio is the only means available.
Separate telephone numbers will be used for Controller communications to prevent the Players from learning in advance of the situation to which they are to be subjected during the Exercise.Close cooperation and coordination among Controllers is essential due to the number of persons assigned to the Controller role.RGKE offsite radiation survey, teams are equipped with portable radios, and are provided cellular telephones for back-up communications.
Separate telephone numbers will be used for Controller communications to prevent the Players from learning in advance of the situation to which they are to be subjected during the Exercise.Close cooperation and coordination among Controllers is essential due to the number of persons assigned to the Controller role.RGKE offsite radiation survey, teams are equipped with portable radios, and are provided cellular telephones for back-up communications.
Survey team controllers are encouraged to use the cellular telephones if clarifications of controller instructions are required while in the field.Controllers Lead Controllers will be stationed in the Simula or Con rol Room OSC CC 0 J C dd CC.Dlyy dC I dlfy Exercise messages or initiate free play messages.A.The Simulator Control Room will be the central point for organization of Exercise messages and is the key to ensuring that the Exercise progresses on schedule, Simulated Plant parameters will be provided to the Simulator Control Room operators either by panel indications displayed in the Simulator Control Room or through plant data and status sheets.Since it is necessary that the emergency escalate to the General Emergency level, it may d y d I-<<lldl I<<I.T~d will acce t th Exercise messa es as wri ten.If corrective actions are postulated that would terminate the emergency, they should be identified to the Lead Controller in the affected facility so that the scenario will progress as designed, The Exercise Players are expected to"free play" the scenario to the extent practical.
Survey team controllers are encouraged to use the cellular telephones if clarifications of controller instructions are required while in the field.Controllers Lead Controllers will be stationed in the Simula or Con rol Room OSC CC 0 J C dd CC.Dlyy dC I dlfy Exercise messages or initiate free play messages.A.The Simulator Control Room will be the central point for organization of Exercise messages and is the key to ensuring that the Exercise progresses on schedule, Simulated Plant parameters will be provided to the Simulator Control Room operators either by panel indications displayed in the Simulator Control Room or through plant data and status sheets.Since it is necessary that the emergency escalate to the General Emergency level, it may d y d I-<<lldl I<<I.T~d will acce t th Exercise messa es as wri ten.If corrective actions are postulated that would terminate the emergency, they should be identified to the Lead Controller in the affected facility so that the scenario will progress as designed, The Exercise Players are expected to"free play" the scenario to the extent practical.
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F.All telephone communications, radio transmissions and public address announcements related to the exercise must begin and end with the statement,"This is an ex reise".Should a Controller or Observer witness an Exercise participant not observing this practice, it is the Controller's/Observer's responsibility to remind the individual of the need to follow this procedure.
F.All telephone communications, radio transmissions and public address announcements related to the exercise must begin and end with the statement,"This is an ex reise".Should a Controller or Observer witness an Exercise participant not observing this practice, it is the Controller's/Observer's responsibility to remind the individual of the need to follow this procedure.
G.Any motor vehicle response to this Exercise, whether it be ambulance, fire fighting equipment, police/security vehicles or field monitoring teams, should observe all normal motor vehicle operating laws included posted speed limits, stop lights/signs, one way streets, etc.Should any onsite security actions be required in response to this Exercise, participants are to cooperate as directed by the Security Force, and security representatives are to be prudent and tolerant in their actions.Exercise participants are to inject as much realism into the Exercise as is consistent with its safe performance; however, caution must be used to prevent over-reaction.
G.Any motor vehicle response to this Exercise, whether it be ambulance, fire fighting equipment, police/security vehicles or field monitoring teams, should observe all normal motor vehicle operating laws included posted speed limits, stop lights/signs, one way streets, etc.Should any onsite security actions be required in response to this Exercise, participants are to cooperate as directed by the Security Force, and security representatives are to be prudent and tolerant in their actions.Exercise participants are to inject as much realism into the Exercise as is consistent with its safe performance; however, caution must be used to prevent over-reaction.
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 Exercise Controller or Observer who is aware of an individual or group of individuals in the immediate vicinity who may have become alarmed or confused about the situation, should approach that individual or group and explain the nature of the Exercise and its intent.2-11  
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 Exercise Controller or Observer who is aware of an individual or group of individuals in the immediate vicinity who may have become alarmed or confused about the situation, should approach that individual or group and explain the nature of the Exercise and its intent.2-11 2.6 Evalua ion and Criti ue The Exercise will be evaluated by Controllers/Observers who have expertise in, or qualifications to evaluate the activity in their assigned location.Controllers/Observers will evaluate Exercise performance on the basis of requirements contained in the Emergency Plan Implementing Procedures and Exercise messages.Controllers/Observers will prepare evaluation forms and provide recommendations on corrective actions to the Exercise Coordinator.
 
===2.6 Evalua===
ion and Criti ue The Exercise will be evaluated by Controllers/Observers who have expertise in, or qualifications to evaluate the activity in their assigned location.Controllers/Observers will evaluate Exercise performance on the basis of requirements contained in the Emergency Plan Implementing Procedures and Exercise messages.Controllers/Observers will prepare evaluation forms and provide recommendations on corrective actions to the Exercise Coordinator.
After the Exercise is completed, the Exercise Coordinator will conduct a post-Exercise critique..Deficiencies in the Emergency Plan, Implementing Procedures, emergency preparedness training program, facilities, equipment and/or other areas will be identified through the critique process.The deficiencies will be documented by the Exercise Coordinator and corrected by the individuals who have responsibility in the area of the identified deficiency.
After the Exercise is completed, the Exercise Coordinator will conduct a post-Exercise critique..Deficiencies in the Emergency Plan, Implementing Procedures, emergency preparedness training program, facilities, equipment and/or other areas will be identified through the critique process.The deficiencies will be documented by the Exercise Coordinator and corrected by the individuals who have responsibility in the area of the identified deficiency.
Controller and Observer information is contained in Section 5.0.The schedule for the critiques is shown in Section 6.0.2-1 2 SECTION 3.0 TRA VEL INFORMA TION  
Controller and Observer information is contained in Section 5.0.The schedule for the critiques is shown in Section 6.0.2-1 2 SECTION 3.0 TRA VEL INFORMA TION 3.0 TRAVEL INFORIVIATION This section of the Ginna Station Exercise Manual provides travel information to those individuals from RG&E, other utilities, local/State/Federal government, and/or other organizations who will participate/observe the Drill.Permission for Visitors to observe the Drill must be obtained from: Corporate Nuclear Emergency Planner Rochester Gas and Electric Corporation 49 East Avenue Rochester, NY 14649-0001,.31 Directions to Ginna Nuclear S a ion Ginna Station is located on the southern shore of Lake Ontario in Wayne County, New York, approximately 24 miles northeast of Rochester, New York (see Figure 3.1).3.1.1 Air Several airlines provide passenger service to the Rochester-Monroe County International Airport.3.1.2 Car A.Several car rental agencies are available at the Rochester-Monroe County International Airport to provide rental vehicles for ground transportation to Ginna Station.B.Persons traveling from the Rochester-Monroe County International Airport via auto should take Route 204 East to Route 390 South.Route 390 becomes Route 590 as one proceeds around the~Loop.Follow Route 590 North to Route 104 East.Follow Route 104 to Route 350 (Ontario Center Road).Turn left (North)and proceed to Ginna Station.Total distance is approximately 40 miles.3.2 Directions to the EOF ESC and JENC 3.2.1 Air From the Rochester-Monroe County International Airport take 204 to 390 North, 490 East into the City onto the Inner Loop to the East Avenue ramp to the third signal light.Turn right.3-1 3.2.2 From the Thruway, use Exits 45 or 46 into Rochester and the Inner Loop to the East Avenue ramp as in 3.2.1.3.2.3 To get to the Emergency Operations Facility (EOF)and Engineering Support Center (ESC), go to the intersection of East Avenue and Chestnut Street (black square on map)~EOF and ESC are in 49 East Avenue.The JENC is at 89 East Avenue (see Figure 3.2).3.3 Accommodations Hotel/motel accommodations may be obtained at the following locations:
 
===3.0 TRAVEL===
INFORIVIATION This section of the Ginna Station Exercise Manual provides travel information to those individuals from RG&E, other utilities, local/State/Federal government, and/or other organizations who will participate/observe the Drill.Permission for Visitors to observe the Drill must be obtained from: Corporate Nuclear Emergency Planner Rochester Gas and Electric Corporation 49 East Avenue Rochester, NY 14649-0001,.31 Directions to Ginna Nuclear S a ion Ginna Station is located on the southern shore of Lake Ontario in Wayne County, New York, approximately 24 miles northeast of Rochester, New York (see Figure 3.1).3.1.1 Air Several airlines provide passenger service to the Rochester-Monroe County International Airport.3.1.2 Car A.Several car rental agencies are available at the Rochester-Monroe County International Airport to provide rental vehicles for ground transportation to Ginna Station.B.Persons traveling from the Rochester-Monroe County International Airport via auto should take Route 204 East to Route 390 South.Route 390 becomes Route 590 as one proceeds around the~Loop.Follow Route 590 North to Route 104 East.Follow Route 104 to Route 350 (Ontario Center Road).Turn left (North)and proceed to Ginna Station.Total distance is approximately 40 miles.3.2 Directions to the EOF ESC and JENC 3.2.1 Air From the Rochester-Monroe County International Airport take 204 to 390 North, 490 East into the City onto the Inner Loop to the East Avenue ramp to the third signal light.Turn right.3-1 3.2.2 From the Thruway, use Exits 45 or 46 into Rochester and the Inner Loop to the East Avenue ramp as in 3.2.1.3.2.3 To get to the Emergency Operations Facility (EOF)and Engineering Support Center (ESC), go to the intersection of East Avenue and Chestnut Street (black square on map)~EOF and ESC are in 49 East Avenue.The JENC is at 89 East Avenue (see Figure 3.2).3.3 Accommodations Hotel/motel accommodations may be obtained at the following locations:
Depot Hotel, Pittsford Marriott Hotel, Greece Red Roof Inn, Henrietta Brookwood Inn, Pittsford Woodcliff Lodge, Perinton (716)381-9900 (716)225-6880 (716)359-1100 (716)248-9000 (716)248-4810 3-2 LAKE ONTARIO GINNA STATION+'Ioi N wotro~18 1~lD4 DHTAklo ClalTK L 4kb 3$o~~g g xi.z Q g 0 ROCHESTER ROCHESTER-MONROE COUNTY AIRPORT I 0 0 0&#xc3;0 T~8 10 ROCHESTER ANO VICINITY 1'a!I I~I I I~/I J~/I I/I I/)f,l C,.aae~~~Mva+aars&Weag sssmr aaeee~Q%is IOOeeso~I~/eaaaOI e OIO Qsea~Oe A eeeO eseasael I W~/~~I aae sess alp oooee~ose 0&>>~ease IL am g~~I I~(ooo/OIIa/I)
Depot Hotel, Pittsford Marriott Hotel, Greece Red Roof Inn, Henrietta Brookwood Inn, Pittsford Woodcliff Lodge, Perinton (716)381-9900 (716)225-6880 (716)359-1100 (716)248-9000 (716)248-4810 3-2 LAKE ONTARIO GINNA STATION+'Ioi N wotro~18 1~lD4 DHTAklo ClalTK L 4kb 3$o~~g g xi.z Q g 0 ROCHESTER ROCHESTER-MONROE COUNTY AIRPORT I 0 0 0&#xc3;0 T~8 10 ROCHESTER ANO VICINITY 1'a!I I~I I I~/I J~/I I/I I/)f,l C,.aae~~~Mva+aars&Weag sssmr aaeee~Q%is IOOeeso~I~/eaaaOI e OIO Qsea~Oe A eeeO eseasael I W~/~~I aae sess alp oooee~ose 0&>>~ease IL am g~~I I~(ooo/OIIa/I)
F9'Vat4atluw
F9'Vat4atluw
Line 201: Line 149:
$t AvKT SUILOIHCi.~~~~~SOC.AL StxvKLS 5IATT tOIKi 5TATS HLKT ACAOTMV TAAAIoOH AIIO t lies~'ISAlaPOATATION.....
$t AvKT SUILOIHCi.~~~~~SOC.AL StxvKLS 5IATT tOIKi 5TATS HLKT ACAOTMV TAAAIoOH AIIO t lies~'ISAlaPOATATION.....
~,.T.IA.LQ"Ii"l4~~~~..I~7 lt~....15 LSS~.~~~~.I.'TI.Q.4....LW5..t.l.t.TA gag LsAasyKI~ST~OITaee.
~,.T.IA.LQ"Ii"l4~~~~..I~7 lt~....15 LSS~.~~~~.I.'TI.Q.4....LW5..t.l.t.TA gag LsAasyKI~ST~OITaee.
Olla 54 Id."p C/l m n Cl m Th C mo n OT" 4 n rt I O 0~m tf~44l 4 TO TNIVWAT.ttlT tt~~TIKI, ST tt I+---Ooetae ALNT K"l li Nll LIvIWV lvl'ROH THE SOUTH or WEST take the N.Y.S.Thruvtay (1-.87 Northboundll-90 Eastboun to (alt.'i.After thL toll booth 3/v itrLT.c<J wtral)ht ith l-)3 to Exit 3.STATE OFFICE BUILDING CAMPUS 1220 lVASH I NG TON AV f N 0 f ALBAN Y.Nf W YORK\&I M~IWl IOCJOI~Illi~CItl IAJVlt lisle~Ilg jg lll~IILAKIIIINA4AICAA IIA1CI~IlllN*FROli THE, NORTH take the Adirondack Northway (I-87)South Exit IE.proceed East on I-90 to Exit 3.o FROiq MWNTOWN AI BANy take 1-90 Westbound to Exi t 3.s FRY jOWHTOWtl Al.BANy take Washington Avenue to Western Avenue (Rte gp)to the State Office Building Campus.to n SECTION 4.0 REI=ERENCES/ABBREVIA TIONS-ACRONYiNS  
Olla 54 Id."p C/l m n Cl m Th C mo n OT" 4 n rt I O 0~m tf~44l 4 TO TNIVWAT.ttlT tt~~TIKI, ST tt I+---Ooetae ALNT K"l li Nll LIvIWV lvl'ROH THE SOUTH or WEST take the N.Y.S.Thruvtay (1-.87 Northboundll-90 Eastboun to (alt.'i.After thL toll booth 3/v itrLT.c<J wtral)ht ith l-)3 to Exit 3.STATE OFFICE BUILDING CAMPUS 1220 lVASH I NG TON AV f N 0 f ALBAN Y.Nf W YORK\&I M~IWl IOCJOI~Illi~CItl IAJVlt lisle~Ilg jg lll~IILAKIIIINA4AICAA IIA1CI~IlllN*FROli THE, NORTH take the Adirondack Northway (I-87)South Exit IE.proceed East on I-90 to Exit 3.o FROiq MWNTOWN AI BANy take 1-90 Westbound to Exi t 3.s FRY jOWHTOWtl Al.BANy take Washington Avenue to Western Avenue (Rte gp)to the State Office Building Campus.to n SECTION 4.0 REI=ERENCES/ABBREVIA TIONS-ACRONYiNS 4.1 References 4.1.2 10 CFR 50.47, 50.54, Appendix E 44 CFR 350.9 4.1.3 NUREG-0654/FEMA-REP-1, Rev.1, Criteria for Pre ara ion and Evalua ion of Radiolo ical Emer enc Res onse Plans an Pre aredness in S ort of N clear Power Plan 4.1.4 4.1.5 4.1.6 4.1.7 4.1.8 4.1.9 RGSE Nuclear Emergency Response Plan (NERP)GS Radiation Emergency Plan Implementing Procedures (EPIPS)GS License and Technical Specifications GS Piping and Instrumentation Drawings New York State Radiological Emergency Response Plan Monroe County Emergency Preparedness Plan 4.1.10 4.1.11 Wayne County Radiological Response Plan INPO Emergency Preparedness Drill and Exercise Manual 4-1 4.2 Abbreviations
 
===4.1 References===
4.1.2 10 CFR 50.47, 50.54, Appendix E 44 CFR 350.9 4.1.3 NUREG-0654/FEMA-REP-1, Rev.1, Criteria for Pre ara ion and Evalua ion of Radiolo ical Emer enc Res onse Plans an Pre aredness in S ort of N clear Power Plan 4.1.4 4.1.5 4.1.6 4.1.7 4.1.8 4.1.9 RGSE Nuclear Emergency Response Plan (NERP)GS Radiation Emergency Plan Implementing Procedures (EPIPS)GS License and Technical Specifications GS Piping and Instrumentation Drawings New York State Radiological Emergency Response Plan Monroe County Emergency Preparedness Plan 4.1.10 4.1.11 Wayne County Radiological Response Plan INPO Emergency Preparedness Drill and Exercise Manual 4-1  
 
===4.2 Abbreviations===
-Acron ms A/E ALARA AOV ARMS ARV ATWS BAST CD CFR CV CR DOE DOE-IRAP EAL(s)EBS EC ECL(s)ENS EOC EOF EPA EPC EPIP(s)EPZ ERF(s)ERPA ESC FEMA FRERP GS HALM HP HPN HVAC INHB INPO JENC Kl LALM LCO LOCA LWR MOV MPC NERP Architect Engineer As Low As Reasonably Achievable Air-Operated Valve , Area Radiation Monitor(s)
-Acron ms A/E ALARA AOV ARMS ARV ATWS BAST CD CFR CV CR DOE DOE-IRAP EAL(s)EBS EC ECL(s)ENS EOC EOF EPA EPC EPIP(s)EPZ ERF(s)ERPA ESC FEMA FRERP GS HALM HP HPN HVAC INHB INPO JENC Kl LALM LCO LOCA LWR MOV MPC NERP Architect Engineer As Low As Reasonably Achievable Air-Operated Valve , Area Radiation Monitor(s)
Atmospheric Relief Valve Anticipated Transient Without Scram Boric Acid Storage Tank Civil Defense Code of Federal Regulations Containment Control Room Department of Energy DOE Interagency Radiological Assistance Plan Emergency Action Level(s)Emergency Broadcast System Emergency Coordinator Emergency Classification Level(s)Emergency Notification System (NRC)Emergency Operations Center Emergency Operations Facility Environmental Protection Agency Emergency Planning Coordinator Emergency Plan Implementation Procedure(s)
Atmospheric Relief Valve Anticipated Transient Without Scram Boric Acid Storage Tank Civil Defense Code of Federal Regulations Containment Control Room Department of Energy DOE Interagency Radiological Assistance Plan Emergency Action Level(s)Emergency Broadcast System Emergency Coordinator Emergency Classification Level(s)Emergency Notification System (NRC)Emergency Operations Center Emergency Operations Facility Environmental Protection Agency Emergency Planning Coordinator Emergency Plan Implementation Procedure(s)
Emergency Planning Zone Emergency Response Facility(s)
Emergency Planning Zone Emergency Response Facility(s)
Emergency Response Planning Area Engineering Support Center Federal Emergency Management Agency Federal Radiological Emergency Response Plan Ginna Station High Alarm Health Physicist Health Physics Network Heating Ventilation Air Conditioning Inhibited (Alarm Suppressed)
Emergency Response Planning Area Engineering Support Center Federal Emergency Management Agency Federal Radiological Emergency Response Plan Ginna Station High Alarm Health Physicist Health Physics Network Heating Ventilation Air Conditioning Inhibited (Alarm Suppressed)
Institute of Nuclear Power Operations Joint Emergency News Center Potassium Iodide Low Alarm Limited Condition of Operation Loss of Coolant Accident Light Water Reactor Motor-Operated Valve Maximum Permissible Concentration Nuclear Emergency Response Plan 4-2  
Institute of Nuclear Power Operations Joint Emergency News Center Potassium Iodide Low Alarm Limited Condition of Operation Loss of Coolant Accident Light Water Reactor Motor-Operated Valve Maximum Permissible Concentration Nuclear Emergency Response Plan 4-2 4.2 Abbrevia ions-Acron ms Cont'd NRC OSC OOS OOS PAG(s)PAR(s)PASS PIO PWR RCP RCS RHR RG&.E RST SC Sl SPING TSC Nuclear Regulatory Commission Operational Support Center Out of Service (on site)Out of Sequence (off site)Protective Action Guide(s)Protective Action Recommendation(s)
 
Post Accident Sampling System Public Information Officer Pressurized Water Reactor Reactor Coolant Pump Reactor Coolant System Residual Heat Removal Rochester Gas and Electric Corporation Radiation Survey Team Site Contingency (or Survey Center)Safety Injection High Range Effluent Monitor Technical Support Center 4-3 SECT/ON 5.0 CONTROLLER AND EVALUA TOR INFORMA TION 5.0 CONTROLLER AND EVALUATOR INSTRUCTIONS Each Controller and Evaluator should be familiar with the following:
===4.2 Abbrevia===
ions-Acron ms Cont'd NRC OSC OOS OOS PAG(s)PAR(s)PASS PIO PWR RCP RCS RHR RG&.E RST SC Sl SPING TSC Nuclear Regulatory Commission Operational Support Center Out of Service (on site)Out of Sequence (off site)Protective Action Guide(s)Protective Action Recommendation(s)
Post Accident Sampling System Public Information Officer Pressurized Water Reactor Reactor Coolant Pump Reactor Coolant System Residual Heat Removal Rochester Gas and Electric Corporation Radiation Survey Team Site Contingency (or Survey Center)Safety Injection High Range Effluent Monitor Technical Support Center 4-3 SECT/ON 5.0 CONTROLLER AND EVALUA TOR INFORMA TION  
 
==5.0 CONTROLLER==
AND EVALUATOR INSTRUCTIONS Each Controller and Evaluator should be familiar with the following:
a.The basic objectives of the Exercise.'.The assumptions and precautions being taken.c.The Exercise scenario, including the initiating events and the expected course of actions to be taken.d.The various locations that will be involved and the specific items to be observed when at those locations.
a.The basic objectives of the Exercise.'.The assumptions and precautions being taken.c.The Exercise scenario, including the initiating events and the expected course of actions to be taken.d.The various locations that will be involved and the specific items to be observed when at those locations.
e.The purpose and importance of the evaluation checklist and record sheets.5.1 Controller Instructions
e.The purpose and importance of the evaluation checklist and record sheets.5.1 Controller Instructions 5.1.1 Controllers will position themselves at their assigned locations prior to the activation of the facility for which they have responsibility (see Section 5.3).5.1.2 Communications will be tested to ensure satisfactory communications among Controllers prior to Exercise commencement.
 
====5.1.1 Controllers====
will position themselves at their assigned locations prior to the activation of the facility for which they have responsibility (see Section 5.3).5.1.2 Communications will be tested to ensure satisfactory communications among Controllers prior to Exercise commencement.
All watches and clocks will be synchronized with the Lead Simulator Control Room Exercise Controller as part of the communications testing.5.1.35.1.4 All Controllers will comply with instructions from the Lead Controller.
All watches and clocks will be synchronized with the Lead Simulator Control Room Exercise Controller as part of the communications testing.5.1.35.1.4 All Controllers will comply with instructions from the Lead Controller.
Each Controller will have copies of the messages controlling the progress of the Exercise scenario.No message shall be delivered out of sequence or other than as written unless specifically authorized by the Lead Controller.
Each Controller will have copies of the messages controlling the progress of the Exercise scenario.No message shall be delivered out of sequence or other than as written unless specifically authorized by the Lead Controller.
 
5.1.5 Messages controlling the progress of the scenario are noted with a number.Contingency messages are noted with a number followed by the letter"X" (e.g., 10X)~5.1.6 Each onsite Controller will have copies of time-related plant data sheets.Data sheets will be distributed only in the Control Room.Radiological and meteorological data will also be provided at locations where it is normally available.
====5.1.5 Messages====
5-1 5.1.7 Controllers will~no provide information to the Players regarding scenario development or resolution of problem areas encountered in the course of the simulated emergency.
controlling the progress of the scenario are noted with a number.Contingency messages are noted with a number followed by the letter"X" (e.g., 10X)~5.1.6 Each onsite Controller will have copies of time-related plant data sheets.Data sheets will be distributed only in the Control Room.Radiological and meteorological data will also be provided at locations where it is normally available.
5-1  
 
====5.1.7 Controllers====
will~no provide information to the Players regarding scenario development or resolution of problem areas encountered in the course of the simulated emergency.
The Exercise participants are expected to obtain information through their own organizations and exercise their own judgement in determining response actions and resolving problems.5.1g8 Some Players may insist that certain parts of the see n a ri o a re unrealistic, The Lead Controllers have the sole authority to clarify any questions regarding scenario content.5.1 g9 Each Controller will take detailed notes regarding the progress of the Exercise and the responses of the Exercise participants at their respective assigned locations.
The Exercise participants are expected to obtain information through their own organizations and exercise their own judgement in determining response actions and resolving problems.5.1g8 Some Players may insist that certain parts of the see n a ri o a re unrealistic, The Lead Controllers have the sole authority to clarify any questions regarding scenario content.5.1 g9 Each Controller will take detailed notes regarding the progress of the Exercise and the responses of the Exercise participants at their respective assigned locations.
Each Controller will carefully note the arrival and departure time for participants, the times at which major activities or milestones occur and problem areas encountered.
Each Controller will carefully note the arrival and departure time for participants, the times at which major activities or milestones occur and problem areas encountered.
Line 677: Line 606:
EPIP 1-5 PLANT STATUS POINT fn 53 FSIA 54 FSIB 55 P21h0 56 P2161 57 BNR041 58 BKR042 ,59 BKR043 60 INR044 DESCRIPTION SAFETY INJECTION LOOP A,AVG FLOM SAFETY Itt'ECTION LOCiP B AVG FLOM SERVICE MATER PUttPS A h B HEADER SERVICE MATER PUttPS C 5 O HEADER SERVICE MATER PUttP A SERVICE MATER PUttP B SERVICE MATER PUttP C SERVICE MATER PUtlP D ON ON ON ON VALUE 185.380.87.86.QUAL E.U.GOOD GPtt GOOIl Ptt GOOD PSIG GOOD PSIG GOOD GOOD GOOD Goon NOV 17>1993 09:30 R.E.Gite SIMULATOR TRFND GROUP A%16ttMENT SUtlMARY PAGE 1 6ROL'P: EVENT2 PROCEDLtRE:
EPIP 1-5 PLANT STATUS POINT fn 53 FSIA 54 FSIB 55 P21h0 56 P2161 57 BNR041 58 BKR042 ,59 BKR043 60 INR044 DESCRIPTION SAFETY INJECTION LOOP A,AVG FLOM SAFETY Itt'ECTION LOCiP B AVG FLOM SERVICE MATER PUttPS A h B HEADER SERVICE MATER PUttPS C 5 O HEADER SERVICE MATER PUttP A SERVICE MATER PUttP B SERVICE MATER PUttP C SERVICE MATER PUtlP D ON ON ON ON VALUE 185.380.87.86.QUAL E.U.GOOD GPtt GOOIl Ptt GOOD PSIG GOOD PSIG GOOD GOOD GOOD Goon NOV 17>1993 09:30 R.E.Gite SIMULATOR TRFND GROUP A%16ttMENT SUtlMARY PAGE 1 6ROL'P: EVENT2 PROCEDLtRE:
EPIP 1"5 PLANT STATUS I POINT 1 F0619 2 LRWST 3 WSO33 4 WD033 5 WT033 6 WT250 7 WDT2 8 R01 9 R02!0 R05 11 R09 12 R34 13 R35 14 RIOA 15 R11 16 R12 17 RIOB!8 R13 19 R14 20 R18 21 R19 22 R29 23 R30 24 P.15 25 R12A5 26 R12A6 27 R12A7 28 R12A9 29 R14AS 30 R14A7 31 R14A9 32 R15A5 33 R15A7 34 R15A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 fD DESCRIPTION COMPONENT COOLING LOOP TOTAL FLW REFUELIWG WARD STORAG"" TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVP WIND DIRECTIOtl 33 FOOT LEVEL TEMPERATURE
EPIP 1"5 PLANT STATUS I POINT 1 F0619 2 LRWST 3 WSO33 4 WD033 5 WT033 6 WT250 7 WDT2 8 R01 9 R02!0 R05 11 R09 12 R34 13 R35 14 RIOA 15 R11 16 R12 17 RIOB!8 R13 19 R14 20 R18 21 R19 22 R29 23 R30 24 P.15 25 R12A5 26 R12A6 27 R12A7 28 R12A9 29 R14AS 30 R14A7 31 R14A9 32 R15A5 33 R15A7 34 R15A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 fD DESCRIPTION COMPONENT COOLING LOOP TOTAL FLW REFUELIWG WARD STORAG"" TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVP WIND DIRECTIOtl 33 FOOT LEVEL TEMPERATURE
-.250 FOOT LEVP TENPERATURE 250 TO 33 FOOT LEVEl.DELTA TEllP AREA I-COWTRO'OON AREA 2-CONTAlt(MENT ARiA 5-SPEt(T FUiL PIT AREA 9-LETDQW LINE NONITOR ARE 34-AU)(BLDG CV SPRAY PL%i~AREA 35"PASS SAMPLE PANEL CONTAINMENT IODINE MONITOR R10A CGWTAI tST AIR PARTI'TE CONTAINMENT GAS MONITOR PLNT VB4T IODINE MONITOR R10B AUX BLDG EXMST AIR PARTICULATE AUX BLDG EXHAUST GAS tlQNITGR LIQJID WASTi DISPOSAL NQtlITQR STEAN GEtFRATGR BL(LDOW DRAIN ARE 29<Qt(TAIWMENT HI%RA)LK AREA 30-CONTAINMENT HIGH RANGE COND" tlSER AIR E JiCTOR EXHAUST CV VB(T CHAN 5-LOW RAtiGE GAS CV VENT C84 6-AREA GAMA CV VENT CHAW 7 NID RANGE GAS CV VENT CHAN 9-HIGH RAKiE 6AS PLOT VENT CH4tt 5-LGW R4NGE GAS PLANT VENT CHAtl 7-NID RANGE GAS PLANT VENT CK4N 9-HIGH RAN6i GAS AIR EJECTOR CHAN 5 LGW RANGE GAS AIR EJiCTGR CHAN 7-tlID RANGE GAS AIR EJECTCR CLIW 9-HI PANGE GAS AREA 31 STEAN LIR"" A (SPIt(6)ARE 32 STEAN LIRE B (SPING)CV HYDROGEN COt(CB(TRATIGW CV BASENEWT LEVH.6FT TEMP I3 CV INTERMEDIATE LVL 6FT TEMP l)7 CV IWTERYiEDIATE LVL 6FT TBP 58 CV IWTERNEDIATE LVL 6FT TEMP ()9 CV IWTERNEDIATE LVL 6FT TEMP I10 CV OPERATING LEVL 6FT TEMP l)17 VALUE LALtl GOOD 6009 6009 GOOD GOOD GOOD GOOD HALN GOOD GOOD GQQD GQQD HALN HALN HENG 6009 6009 GOOD GOOD 6009 6009 6009 GOOD GOOD GQGD 6009 GOOD GQGD GOOD 6009 GOOD GOOD GOOD 6009 GOOD 6009 GOOD GOOD 135.6 6009 135.9 6009 135.6 6009 133.1 892.78.1 5.6 295.43.3 44.0~7 8.81048-02 8.26987+03 3.14412+00 2.66072+01 2.90068+00
-.250 FOOT LEVP TENPERATURE 250 TO 33 FOOT LEVEl.DELTA TEllP AREA I-COWTRO'OON AREA 2-CONTAlt(MENT ARiA 5-SPEt(T FUiL PIT AREA 9-LETDQW LINE NONITOR ARE 34-AU)(BLDG CV SPRAY PL%i~AREA 35"PASS SAMPLE PANEL CONTAINMENT IODINE MONITOR R10A CGWTAI tST AIR PARTI'TE CONTAINMENT GAS MONITOR PLNT VB4T IODINE MONITOR R10B AUX BLDG EXMST AIR PARTICULATE AUX BLDG EXHAUST GAS tlQNITGR LIQJID WASTi DISPOSAL NQtlITQR STEAN GEtFRATGR BL(LDOW DRAIN ARE 29<Qt(TAIWMENT HI%RA)LK AREA 30-CONTAINMENT HIGH RANGE COND" tlSER AIR E JiCTOR EXHAUST CV VB(T CHAN 5-LOW RAtiGE GAS CV VENT C84 6-AREA GAMA CV VENT CHAW 7 NID RANGE GAS CV VENT CHAN 9-HIGH RAKiE 6AS PLOT VENT CH4tt 5-LGW R4NGE GAS PLANT VENT CHAtl 7-NID RANGE GAS PLANT VENT CK4N 9-HIGH RAN6i GAS AIR EJECTOR CHAN 5 LGW RANGE GAS AIR EJiCTGR CHAN 7-tlID RANGE GAS AIR EJECTCR CLIW 9-HI PANGE GAS AREA 31 STEAN LIR"" A (SPIt(6)ARE 32 STEAN LIRE B (SPING)CV HYDROGEN COt(CB(TRATIGW CV BASENEWT LEVH.6FT TEMP I3 CV INTERMEDIATE LVL 6FT TEMP l)7 CV IWTERYiEDIATE LVL 6FT TBP 58 CV IWTERNEDIATE LVL 6FT TEMP ()9 CV IWTERNEDIATE LVL 6FT TEMP I10 CV OPERATING LEVL 6FT TEMP l)17 VALUE LALtl GOOD 6009 6009 GOOD GOOD GOOD GOOD HALN GOOD GOOD GQQD GQQD HALN HALN HENG 6009 6009 GOOD GOOD 6009 6009 6009 GOOD GOOD GQGD 6009 GOOD GQGD GOOD 6009 GOOD GOOD GOOD 6009 GOOD 6009 GOOD GOOD 135.6 6009 135.9 6009 135.6 6009 133.1 892.78.1 5.6 295.43.3 44.0~7 8.81048-02 8.26987+03 3.14412+00 2.66072+01 2.90068+00 1.09648400 9.66051+06 9.95683~06 9.99992+06 1.23027%1 2.48313%2 7.03879tOI 1.0917&03 1.99813+03 8.00638+00 8.00638400 1.40241+03 4.20511-05 2.67992-02 4.20511-05 9.99787-04 2.30991-06 4.62984-06 9.10997M 6.22985-06 1.80975-05 1.52999-03 1.01004-02 1.01004-02
 
==1.0 9648400==
9.66051+06 9.95683~06 9.99992+06 1.23027%1 2.48313%2 7.03879tOI 1.0917&03 1.99813+03 8.00638+00
 
==8.0 0638400==
1.40241+03 4.20511-05 2.67992-02 4.20511-05 9.99787-04 2.30991-06 4.62984-06 9.10997M 6.22985-06 1.80975-05 1.52999-03 1.01004-02 1.01004-02
.0 138.4 135.9 E.U.GPN X AH D="G.DF6F DE6F DEGF l8/HR%/HR t8/HR NR/HR t8/HR t8/HR CPN CPN CPN CPN CPN CPN CPN CPN R/HR R/HR CPtl XI/CC)8/HR XI/CC UCI/CC UCI/CC XI/CC XI/CC XI/CC XI/CC XI/CC NR/HR t8/HR I/9" GF DEGF DEGF DE6F DEGF DEGF Time: 1000-1 500 Message: 27.1 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM:TECE g C Pt.Eggtg TM g dg pp M tt~Massa e: """THIS IS AN EXERCISE""" Please provide appropriate responses to the following questions/issues raised by simulated NRC staff: 1.What is the status of emergency?
.0 138.4 135.9 E.U.GPN X AH D="G.DF6F DE6F DEGF l8/HR%/HR t8/HR NR/HR t8/HR t8/HR CPN CPN CPN CPN CPN CPN CPN CPN R/HR R/HR CPtl XI/CC)8/HR XI/CC UCI/CC UCI/CC XI/CC XI/CC XI/CC XI/CC XI/CC NR/HR t8/HR I/9" GF DEGF DEGF DE6F DEGF DEGF Time: 1000-1 500 Message: 27.1 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM:TECE g C Pt.Eggtg TM g dg pp M tt~Massa e: """THIS IS AN EXERCISE""" Please provide appropriate responses to the following questions/issues raised by simulated NRC staff: 1.What is the status of emergency?
2.What if any PAR's have been recommended?
2.What if any PAR's have been recommended?
Line 853: Line 776:
VALUE E.U.2 3 4 5 6 7 8 9 In 11 12'13 t4 1U 16 17 l9 20 21 23 24)5 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 43 45 46 47 48 49 50 51 52 AIl6 RXT N31 tG2 N35 N36 NP PRCS LPER FRY FRCi3 RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GiNBKRI GENBKR2 BUS11A BUS118 8US12A BUS128 811A12A 8118128 PCY LSUNPA L0942E L0943E L0942D L0943D L0942C L0943C L09428 L09438 L0942A LO943A T0409A'0410A T04sn T0451 TAVGAWID TAVGBWID LRV TCCQRE FAUXFWA FAUXFWB BKR081 BKROB2 V3505 Y3504 ANTICiPATED TRANSIT(T W/0 SCRAN RE@".TOR TRIP BREAKER STATUS SMCE RA)IK DETECTDR tf-31 SEE=" RANK DETECTOR N-32 INT.=RNEDIATE RAN6E D"=TECTOR N-35 It~>"P~~DIATE RANGE DiTECTOR N-36 AVERAGE NUCLEAR POWiR REA TOR COOL@(T SYST>c AYG PRESS PK~SSURI EER AVERAGE LEVEL RBr"TQR COOLANT LOOP A AYG FLOW REACTOR CCCL@T LOOP R AVG FLQM RCPA BREAKER CAUS'i RX TRIP RCPB BRENER CAUSE RX TRIP INCORE TC SUBCOOLED NNGIN STtI Kt(A t(ARROW RA%: AVG LEVEl STt'i GiN R t(ARROW RANGc AVG LEVEL STtI Gi!(A AVERAGE PRESSURE STN GEI(8 AVERAGE PRESSURE GitKRATOR ON LINE BREAKER 161372 GENERATOR OM't(E BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 1!8 SL'PPLY BREAKER t(OT 7ERNINATED ON PPCS (7/19/91)t(QT'tiNIt(ATED QN FPCS (7/!9/91)BUS 11A TQ 12A TIE BRiNER BUS 118 TO 128 TiE BREAKER CQNTAINtIEt(7 AVERAGE PRESSURE CQtFiAIt&#x17d;ZiT SJtIP A AYERAK LEVEL MP 8 LEVEL 8 INCHES (TRAIt(A)Slat 8 LEVd.8 It(CHES (TRAIN 8)HJt.8 LEVd 78 INCfiiS (TRAltt A)SUtP 8 LPr~76 it(CHES (TRAltt 8)SU%8 LEVEL 113 INCHES(TRAIN A)SU%'LEVEL 113 It(CHciS(TRAIN 8)SUtF'LEYEI.180 INCHES(TRAIN A)SUPP 8 LEVEL 180 INCH""S(TRAIt(8)Rti.8 LEVEL 214 INCHES(7RAIN A)SUtP 8 I.EYEL 214 INCHES(7RAIN 8)RCL~HQT LEG TEtPERATURE RCLB HOT LEG TEtIPERATLK RCLA COLD LEG TE)IPERATNE RCLB COU)LEG TE)IPERATURE RCLA TAVG (THOT/TCQLD WiDE RNG)RCLB TAVG (THQT/TCOLD WIDE Rt(G)REk TOR VESSEL AVERAGE LEYEL Ei.l INCORE TC AVERAGE TEIIP S/6 A TOTAL AUX FEEDWATER FLOW S/6 8 TOTAL AUX FEEDMATER FLOW NTR AUXILIARY FEEDWATER PUtIP A)ITR AUXILIARY FEEDWATER PUIIP 8 AUX FW Ply STEA)I SUPPLY VALVE A AUX FW Pl&#xc3;'TEA)I SUPPLY VALVE 8 ATNS ALRtI RX TRIPPED ALRII 1.18713p05 HALI(3.94456+01 BAD 2.64239-10 6008 1.00001-11 Gm.00 6008 LALN.0 LALtI 1.0 It(H>>1.3 ItlHB TRIPPED ALRII TRiPPED ALRII-820.7 LAL>>67.4 HALII 27.9 LWR>>"4.LALt', uV II TRIPPED ALRN 7RIPPED ALRII TRIPPED ALRII TRIPPED ALRII NO.TRIP DEL t(OT TRIP DEL t(QT TRIP ALRN NOT TRIP ALRII.52 GOO>>31.2 HENS HI6HER INHB HI6HEP, INH8 HIGf&c I WB H16HER INHB HIGHER ALRtt HIGHER KRW LOWcD 6008 LONER 6008 LONER GQQD LONER C&8 215.5 GOOD 215.5~8 201.5 BAD 158.2 BAD 215.5 600>>215.5 CCO>>36.7 LALII 852.9 HAL>>0.6008 28, 6008 OFF'OOD ON 6008 CLOSED 6008 CLOSED GOOD/'" j3 r'PS CPS fNP A!IP PSIG/0//DEGF I/PSIG PS!G PSIG FKT DEGF DEGF IFM DEGF DEGF DEGF K DEGF VII Ptl NOV 17i H93 10:43 R.E.GINA SIMULATOR TREND GROiUP ARIGfffiEfii SUi"iftARY PAGE 2 e POINT ID 53 FSIA 54 FSIB 55 P2160 56 P2 161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 DESCRIPTIOV SAFETY INJECTION LOOP A AVG FLOW SAFETY INJECTION LKP B AVG FLOW SERVICE MATER PUMPS A h B KITER SERVICE MATER PUfFS C h D HEADER SERVICE MATER PUfft'SERViCE WATER PUfP 8 SHNICE MATER PUNP C SERVICE MATER PU!i?0 VALUE QUAL E.U.ON OiV ON ON 0, GOOD 9'N 0.GOOD GPN 87.GOOD PSIG 86.GOOD PSIG GOOD GOOD GOOD GOOD GROUP;EVENT1 PROCED~~E EPIP 1 5 PLANT STATUS NOV 17i 1993 10:4'.=.GitWA Slt'iLLATOP, TREND GROUP ASSIGNME)'T SUMNARY PAR GROUP;EVENT2 PRQCEDLRcE:
VALUE E.U.2 3 4 5 6 7 8 9 In 11 12'13 t4 1U 16 17 l9 20 21 23 24)5 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 43 45 46 47 48 49 50 51 52 AIl6 RXT N31 tG2 N35 N36 NP PRCS LPER FRY FRCi3 RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GiNBKRI GENBKR2 BUS11A BUS118 8US12A BUS128 811A12A 8118128 PCY LSUNPA L0942E L0943E L0942D L0943D L0942C L0943C L09428 L09438 L0942A LO943A T0409A'0410A T04sn T0451 TAVGAWID TAVGBWID LRV TCCQRE FAUXFWA FAUXFWB BKR081 BKROB2 V3505 Y3504 ANTICiPATED TRANSIT(T W/0 SCRAN RE@".TOR TRIP BREAKER STATUS SMCE RA)IK DETECTDR tf-31 SEE=" RANK DETECTOR N-32 INT.=RNEDIATE RAN6E D"=TECTOR N-35 It~>"P~~DIATE RANGE DiTECTOR N-36 AVERAGE NUCLEAR POWiR REA TOR COOL@(T SYST>c AYG PRESS PK~SSURI EER AVERAGE LEVEL RBr"TQR COOLANT LOOP A AYG FLOW REACTOR CCCL@T LOOP R AVG FLQM RCPA BREAKER CAUS'i RX TRIP RCPB BRENER CAUSE RX TRIP INCORE TC SUBCOOLED NNGIN STtI Kt(A t(ARROW RA%: AVG LEVEl STt'i GiN R t(ARROW RANGc AVG LEVEL STtI Gi!(A AVERAGE PRESSURE STN GEI(8 AVERAGE PRESSURE GitKRATOR ON LINE BREAKER 161372 GENERATOR OM't(E BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 1!8 SL'PPLY BREAKER t(OT 7ERNINATED ON PPCS (7/19/91)t(QT'tiNIt(ATED QN FPCS (7/!9/91)BUS 11A TQ 12A TIE BRiNER BUS 118 TO 128 TiE BREAKER CQNTAINtIEt(7 AVERAGE PRESSURE CQtFiAIt&#x17d;ZiT SJtIP A AYERAK LEVEL MP 8 LEVEL 8 INCHES (TRAIt(A)Slat 8 LEVd.8 It(CHES (TRAIN 8)HJt.8 LEVd 78 INCfiiS (TRAltt A)SUtP 8 LPr~76 it(CHES (TRAltt 8)SU%8 LEVEL 113 INCHES(TRAIN A)SU%'LEVEL 113 It(CHciS(TRAIN 8)SUtF'LEYEI.180 INCHES(TRAIN A)SUPP 8 LEVEL 180 INCH""S(TRAIt(8)Rti.8 LEVEL 214 INCHES(7RAIN A)SUtP 8 I.EYEL 214 INCHES(7RAIN 8)RCL~HQT LEG TEtPERATURE RCLB HOT LEG TEtIPERATLK RCLA COLD LEG TE)IPERATNE RCLB COU)LEG TE)IPERATURE RCLA TAVG (THOT/TCQLD WiDE RNG)RCLB TAVG (THQT/TCOLD WIDE Rt(G)REk TOR VESSEL AVERAGE LEYEL Ei.l INCORE TC AVERAGE TEIIP S/6 A TOTAL AUX FEEDWATER FLOW S/6 8 TOTAL AUX FEEDMATER FLOW NTR AUXILIARY FEEDWATER PUtIP A)ITR AUXILIARY FEEDWATER PUIIP 8 AUX FW Ply STEA)I SUPPLY VALVE A AUX FW Pl&#xc3;'TEA)I SUPPLY VALVE 8 ATNS ALRtI RX TRIPPED ALRII 1.18713p05 HALI(3.94456+01 BAD 2.64239-10 6008 1.00001-11 Gm.00 6008 LALN.0 LALtI 1.0 It(H>>1.3 ItlHB TRIPPED ALRII TRiPPED ALRII-820.7 LAL>>67.4 HALII 27.9 LWR>>"4.LALt', uV II TRIPPED ALRN 7RIPPED ALRII TRIPPED ALRII TRIPPED ALRII NO.TRIP DEL t(OT TRIP DEL t(QT TRIP ALRN NOT TRIP ALRII.52 GOO>>31.2 HENS HI6HER INHB HI6HEP, INH8 HIGf&c I WB H16HER INHB HIGHER ALRtt HIGHER KRW LOWcD 6008 LONER 6008 LONER GQQD LONER C&8 215.5 GOOD 215.5~8 201.5 BAD 158.2 BAD 215.5 600>>215.5 CCO>>36.7 LALII 852.9 HAL>>0.6008 28, 6008 OFF'OOD ON 6008 CLOSED 6008 CLOSED GOOD/'" j3 r'PS CPS fNP A!IP PSIG/0//DEGF I/PSIG PS!G PSIG FKT DEGF DEGF IFM DEGF DEGF DEGF K DEGF VII Ptl NOV 17i H93 10:43 R.E.GINA SIMULATOR TREND GROiUP ARIGfffiEfii SUi"iftARY PAGE 2 e POINT ID 53 FSIA 54 FSIB 55 P2160 56 P2 161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 DESCRIPTIOV SAFETY INJECTION LOOP A AVG FLOW SAFETY INJECTION LKP B AVG FLOW SERVICE MATER PUMPS A h B KITER SERVICE MATER PUfFS C h D HEADER SERVICE MATER PUfft'SERViCE WATER PUfP 8 SHNICE MATER PUNP C SERVICE MATER PU!i?0 VALUE QUAL E.U.ON OiV ON ON 0, GOOD 9'N 0.GOOD GPN 87.GOOD PSIG 86.GOOD PSIG GOOD GOOD GOOD GOOD GROUP;EVENT1 PROCED~~E EPIP 1 5 PLANT STATUS NOV 17i 1993 10:4'.=.GitWA Slt'iLLATOP, TREND GROUP ASSIGNME)'T SUMNARY PAR GROUP;EVENT2 PRQCEDLRcE:
EPIP 1-5 PLANT STATUS 0 POINT!D 24 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 R29 P30 R}5 R12A5 R!2Ab R12A?R}2A9 R}4A5 R}4A7 R}4A9 R!5A5 R}5A7 R}5A9 R3!R32 CVH TCV03 TCVO7 TCVOB TCV09 TCV10 TCV}7 1 F06}9 2 LSGT 3 NS033 4 t)9033 5 MT033 6 WT250 7 NDT2 8 RO}9 R02 10 R05!1 R09 12 R34!3 R35 14 R}OA 15 R!1, 16 R}2!7 R!OB 18 R13 R!4 20 R}8 2'!9 DES!AIPTIOW COtPOltcNT Coo." ING LKP TOTAL FLN FcCLING))ATER STORAGE TAt&#xc3;LVL 33 FQOT LEVEi WIND SPcB)33 FOOT LEVEL MIND DIfKCTIGN 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TQ 33 FOOT LEVEL DELTA TP~AREA}-Cot(TRg ROO AREA 2<ot(TAINNcERT AREA 5-SPENT FU9.PIT AREA 9-LETDOPa<
EPIP 1-5 PLANT STATUS 0 POINT!D 24 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 R29 P30 R}5 R12A5 R!2Ab R12A?R}2A9 R}4A5 R}4A7 R}4A9 R!5A5 R}5A7 R}5A9 R3!R32 CVH TCV03 TCVO7 TCVOB TCV09 TCV10 TCV}7 1 F06}9 2 LSGT 3 NS033 4 t)9033 5 MT033 6 WT250 7 NDT2 8 RO}9 R02 10 R05!1 R09 12 R34!3 R35 14 R}OA 15 R!1, 16 R}2!7 R!OB 18 R13 R!4 20 R}8 2'!9 DES!AIPTIOW COtPOltcNT Coo." ING LKP TOTAL FLN FcCLING))ATER STORAGE TAt&#xc3;LVL 33 FQOT LEVEi WIND SPcB)33 FOOT LEVEL MIND DIfKCTIGN 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TQ 33 FOOT LEVEL DELTA TP~AREA}-Cot(TRg ROO AREA 2<ot(TAINNcERT AREA 5-SPENT FU9.PIT AREA 9-LETDOPa<
LItF NONITGR AREA 34-AU(BLDG CV S, RAY Pot(P AREA 35-PASS SAMPLE PAtKL CGNTAINNiENT IODltZ NOtiITOR R10A CGNTAIHNENT AIR PART IC(LATE CO'lTA!t(MEt(T GAS tSNITGR PLAi7 VENT IODIttE MONITOR R}OB AUK BLDG E)(YAJST AIR PARTICULATE AU): BLDG E)(HAJST GAS NONITGR LINJID ViASTE DISPOSAL MONITOR STEAM GBlERATOR BLO)(DON DRAIN ARcA 29-CONTAINNEt)T HI(if RANGE AREA 30-CQWTAItNENT HI%RNi'GE Col(DENSER AIR EJECTOR E)(HAUST CV%Bing CSN 5-LOk'At(GE GAS CV VEW;CHAN 6-AREA GAB%CV VER!CHAN 7-NID RANGE GAS CV VEWi CHAN 9 HiGH RA'P~c 6AS PLANT VEtkT CIL4N 5-LOW RANGE GAS PL'Al)T VENT CHAN?+ID RANGE GAS PLNT VENT CMAtt 9-HIGH RAt(GE GAS AIR EJECTOR CHAN 5-LG)t RAN6E GAS AIR cJcCTOi RCHAN 7 NID RANGE GAS AIR EJcCTGR CHAtt 9+I RANGE GAS AREA 3!STEAN I.INEA (SPING)AREA i~STEAM LINE 9 (c It(6)CV HYDROGEt<COWCEttTRATION CV BASENEt(T LEVEL 6FT TEMP ti3 CV Iti HNEDIATE LVL 6FT TEMP ()7 CV INTERMEDIATE LVL 6FT TE)P 48 CV INTERNEDIATE LVL 6FTi TPiP N CV INTERMEDIATE LVL 6FT TEMP NO CV OPERATINS LEVL 6FT TEMP It}7 VALL!E 892.37.1 3.0 41.43.1 43;1.0 9,44062M 7.80727+03 3, 14412t00 2,75423t01 2.95121+00 1, 09648t00 9.66051t06 9.66051+06 1.01741+07 l.14}56t02 2.548Bt02 2.55563+03
LItF NONITGR AREA 34-AU(BLDG CV S, RAY Pot(P AREA 35-PASS SAMPLE PAtKL CGNTAINNiENT IODltZ NOtiITOR R10A CGNTAIHNENT AIR PART IC(LATE CO'lTA!t(MEt(T GAS tSNITGR PLAi7 VENT IODIttE MONITOR R}OB AUK BLDG E)(YAJST AIR PARTICULATE AU): BLDG E)(HAJST GAS NONITGR LINJID ViASTE DISPOSAL MONITOR STEAM GBlERATOR BLO)(DON DRAIN ARcA 29-CONTAINNEt)T HI(if RANGE AREA 30-CQWTAItNENT HI%RNi'GE Col(DENSER AIR EJECTOR E)(HAUST CV%Bing CSN 5-LOk'At(GE GAS CV VEW;CHAN 6-AREA GAB%CV VER!CHAN 7-NID RANGE GAS CV VEWi CHAN 9 HiGH RA'P~c 6AS PLANT VEtkT CIL4N 5-LOW RANGE GAS PL'Al)T VENT CHAN?+ID RANGE GAS PLNT VENT CMAtt 9-HIGH RAt(GE GAS AIR EJECTOR CHAN 5-LG)t RAN6E GAS AIR cJcCTOi RCHAN 7 NID RANGE GAS AIR EJcCTGR CHAtt 9+I RANGE GAS AREA 3!STEAN I.INEA (SPING)AREA i~STEAM LINE 9 (c It(6)CV HYDROGEt<COWCEttTRATION CV BASENEt(T LEVEL 6FT TEMP ti3 CV Iti HNEDIATE LVL 6FT TEMP ()7 CV INTERMEDIATE LVL 6FT TE)P 48 CV INTERNEDIATE LVL 6FTi TPiP N CV INTERMEDIATE LVL 6FT TEMP NO CV OPERATINS LEVL 6FT TEMP It}7 VALL!E 892.37.1 3.0 41.43.1 43;1.0 9,44062M 7.80727+03 3, 14412t00 2,75423t01 2.95121+00 1, 09648t00 9.66051t06 9.66051+06 1.01741+07 l.14}56t02 2.548Bt02 2.55563+03 1.01888t03 2,12263t03 7.99485t02 7.99485t02 1~41457t03 4.205}!M 2.00000tO}
 
==1.0 1888t03==
2,12263t03 7.99485t02 7.99485t02 1~41457t03 4.205}!M 2.00000tO}
4.205}}-05 9.99987-04 8.24988-04 8.24988-04 9.10997-04 6.22985-06 1.80975-05 1~52999M}.0}004M}.0}004<2.0 66.0 QUAL LAN 6009 6009 6009 G009 6009 6009 6009 BAD BAD BAD BAD 6009 HALtI HALN HEWS 6009 6009 HALN 6009 G009 fM HALN 6009 G009 O'Rt(6009 6009 HNRt(6009 GOOD 6009 6009 6009 6009 6009 GOOD 6009 70.6 6009 70.6=6009 70.6 GOOD 70.6 6009 75.3 6009 E.U.GPN'i(NPH DEG.IFGF DEGF IFGF t8/HR%/HR NR/HR l8/)I N/HR ts/HR CPN CPN CPN CPN CPN CPN CPN CPN R/HR R/HR PN UCI/CC N/HR UCI/CC XI/CC XI/CC XI/CC XI/CC XI/CC XI/CC XI/CC I)/tl N/MR\/DE6F DEGF IFGF IFGF DEGF DEGF 7 Time: 1050 Message: 45 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~Mt: 5 i L Simulated Plant Conditions:
4.205}}-05 9.99987-04 8.24988-04 8.24988-04 9.10997-04 6.22985-06 1.80975-05 1~52999M}.0}004M}.0}004<2.0 66.0 QUAL LAN 6009 6009 6009 G009 6009 6009 6009 BAD BAD BAD BAD 6009 HALtI HALN HEWS 6009 6009 HALN 6009 G009 fM HALN 6009 G009 O'Rt(6009 6009 HNRt(6009 GOOD 6009 6009 6009 6009 6009 GOOD 6009 70.6 6009 70.6=6009 70.6 GOOD 70.6 6009 75.3 6009 E.U.GPN'i(NPH DEG.IFGF DEGF IFGF t8/HR%/HR NR/HR l8/)I N/HR ts/HR CPN CPN CPN CPN CPN CPN CPN CPN R/HR R/HR PN UCI/CC N/HR UCI/CC XI/CC XI/CC XI/CC XI/CC XI/CC XI/CC XI/CC I)/tl N/MR\/DE6F DEGF IFGF IFGF DEGF DEGF 7 Time: 1050 Message: 45 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~Mt: 5 i L Simulated Plant Conditions:
See Attached Sheets~Messa e:<<""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Radiation levels increase substantially in Auxiliary Building.This due to the leaking pipe between Containment and MOV-850A opening up where the crack is.A release above technical specifications begins, Antici a ed Resul s;1)Operators may transition to ECA-1.1 (Loss of Emergency Coolant Recirculation) due to loss of both RHR pumps.2)TSC should be expediting the turning on of the AC power breaker to MOV-851A.3)TSC should be expediting the recovery of AC power to Bus 14.4)TSC should inform the EOF of the increased radiation levels in the Auxiliary Building.5)TSC should inform the EOF of plant status, actions being taken and needs required.
See Attached Sheets~Messa e:<<""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Radiation levels increase substantially in Auxiliary Building.This due to the leaking pipe between Containment and MOV-850A opening up where the crack is.A release above technical specifications begins, Antici a ed Resul s;1)Operators may transition to ECA-1.1 (Loss of Emergency Coolant Recirculation) due to loss of both RHR pumps.2)TSC should be expediting the turning on of the AC power breaker to MOV-851A.3)TSC should be expediting the recovery of AC power to Bus 14.4)TSC should inform the EOF of the increased radiation levels in the Auxiliary Building.5)TSC should inform the EOF of plant status, actions being taken and needs required.
Line 998: Line 918:
~OOP A AVG FLOP SAFETY INJECTIOW LOOP B AVG FLOP SERVICE tNTER PUTS A~~B HEABER SERVICE%TER PUttPS C 5 9 HEA9ER SERVICE LATER PUtlP A~""P'ICE WATER PUt'~B S~D'ICE MATE PUP.C EH)ICE STER PUt!P D ON ON Oli CA>'.6009 PN 232.6009 Ptt 87.6009 PSIG 86.6009 PSIG 6009 6009 6009 6009 tQV!7i 199a~~!do Xv P,.E.iGiit'iA SINN AT">PAGE 1 TREt i GRGU?ASSIGNIQT SUtt"~ARY GROU',".EV tiT'>PRQFDURE: EPIP!-5-"LANT STATUS 1 3 4 5 6 7 8 10 t~~S 13 16 t/F0619 LRMST MS033 MD033 MT033 MT250 MDT2 Rei RO.R05 R09 R34 R35 R!OA P.l 1 R12 R!OB 18=R13!9 20 r>1 22 23 25 Q~27 30 3t VC v'4 34 33 36 3 i 38 30 40 45 43 R!4 R!8 R!9 P io P~P R'15 R!2A Ri~&6 R!2A?R!2A9 R!4."5 R!4A7 R!4A9 R!5A5 R15A?R!5A9 RS!R32 CVtf TCV03 TCVO?TCVOS TCVO9 TCV!0 TCV!7 POINT!9 DESCRIPTiQN COtPONENT COOLING LOOP TOTAL FLW Rt""Lt-"i INB MAT%STORAGE TANK LVL 33 FOOT LEVEL M!ND SPEK 33 FOOT LEVP MitS DIRECTitON 33 FOOT LEVEL TEtt?ERATLIRE 250;GQT LEV" TEi.FERATURE 230 TO 33 FOQ LEVEL DELTA TEN'R=~!-CGNTRP RDO."i A.<<".=A 2-COhTAlht'iEtiT AFEA~-SPEtiT U:.L P.'T t5E".9 LETDQMN LltvE t'QiNITGR A>J".-" 3g-AUy BLDG CV&RA'/RJYP A.'tEA 3H'ASS SA,"t?LE PALP CONTAItNEt)i 1091tiE tati'ITOR R!OA CGtfiAIN KtiT AIR PARTICULATE CLtNTAIhNEt(T GAS ttDtiITOR PLA!IT Wc, iT IODIti.: t!QNITQR R!OB AU!B DG F&#xc3;HAUS.AiP.PARTICULATE AUi Bt DG EXHiiST GAS ttMTQP, l IBID MASTE DIS?QSA'QNITOR
~OOP A AVG FLOP SAFETY INJECTIOW LOOP B AVG FLOP SERVICE tNTER PUTS A~~B HEABER SERVICE%TER PUttPS C 5 9 HEA9ER SERVICE LATER PUtlP A~""P'ICE WATER PUt'~B S~D'ICE MATE PUP.C EH)ICE STER PUt!P D ON ON Oli CA>'.6009 PN 232.6009 Ptt 87.6009 PSIG 86.6009 PSIG 6009 6009 6009 6009 tQV!7i 199a~~!do Xv P,.E.iGiit'iA SINN AT">PAGE 1 TREt i GRGU?ASSIGNIQT SUtt"~ARY GROU',".EV tiT'>PRQFDURE: EPIP!-5-"LANT STATUS 1 3 4 5 6 7 8 10 t~~S 13 16 t/F0619 LRMST MS033 MD033 MT033 MT250 MDT2 Rei RO.R05 R09 R34 R35 R!OA P.l 1 R12 R!OB 18=R13!9 20 r>1 22 23 25 Q~27 30 3t VC v'4 34 33 36 3 i 38 30 40 45 43 R!4 R!8 R!9 P io P~P R'15 R!2A Ri~&6 R!2A?R!2A9 R!4."5 R!4A7 R!4A9 R!5A5 R15A?R!5A9 RS!R32 CVtf TCV03 TCVO?TCVOS TCVO9 TCV!0 TCV!7 POINT!9 DESCRIPTiQN COtPONENT COOLING LOOP TOTAL FLW Rt""Lt-"i INB MAT%STORAGE TANK LVL 33 FOOT LEVEL M!ND SPEK 33 FOOT LEVP MitS DIRECTitON 33 FOOT LEVEL TEtt?ERATLIRE 250;GQT LEV" TEi.FERATURE 230 TO 33 FOQ LEVEL DELTA TEN'R=~!-CGNTRP RDO."i A.<<".=A 2-COhTAlht'iEtiT AFEA~-SPEtiT U:.L P.'T t5E".9 LETDQMN LltvE t'QiNITGR A>J".-" 3g-AUy BLDG CV&RA'/RJYP A.'tEA 3H'ASS SA,"t?LE PALP CONTAItNEt)i 1091tiE tati'ITOR R!OA CGtfiAIN KtiT AIR PARTICULATE CLtNTAIhNEt(T GAS ttDtiITOR PLA!IT Wc, iT IODIti.: t!QNITQR R!OB AU!B DG F&#xc3;HAUS.AiP.PARTICULATE AUi Bt DG EXHiiST GAS ttMTQP, l IBID MASTE DIS?QSA'QNITOR
"-t="" GENERATOR E'0'~JR!DRAIh-'.,=.-'.2"i-CG.(TAIt<" t"!HIGH RPi.~i=AR=-'0-CQiiTAiti.BiT HIGH RANK CONiDEtS~m AIR EJECTOR EXHAUST CV VENT CHAN~LO'n RANK GAS"V VEN:.CHAN a-AREA GA~a@t V V"" C!.At'P GH PAt" GA<PLk!T VEt~t CHAti=-GA RANGE GAS.P="'!'EtiT CH~i 9-H"-".'.RP3:--" GAS AiR E:ECTOR CHAl&#x17d;='GM RAt(G" 6AS lc..3EL'TQR C'".:AN 7-tilD RA%-" GAS AIR EJECTOR CHttN 9-HI R46E GAS k>>-"='.3!STEA"'NE A (SPIt<6!~."~32 STER"i't(E B (SPltiB!CV%&QBEN COtiCEhTRATION CV BASEV~NT LEV=6~1 TEN?C CV INT""RiiEDIATE LV-'FT TP.".4?CV ItitERt'iEDIATE LV 6FT FJP 48 C" Il~trFN:DIATE LV'FT TEttP!!9 CV It!TERt(ED!ATE LV'FT TEt(P tt!0 CV QPERATINS i":t>>6F TEtP I!7 VALU=6493.22.3 3.1 41.43.!38.8-4.3 8.56051-02 3.05492+05 1.31069<01 3.00262+01 1.25!?~I 1.09648+(I 1.00432+07
"-t="" GENERATOR E'0'~JR!DRAIh-'.,=.-'.2"i-CG.(TAIt<" t"!HIGH RPi.~i=AR=-'0-CQiiTAiti.BiT HIGH RANK CONiDEtS~m AIR EJECTOR EXHAUST CV VENT CHAN~LO'n RANK GAS"V VEN:.CHAN a-AREA GA~a@t V V"" C!.At'P GH PAt" GA<PLk!T VEt~t CHAti=-GA RANGE GAS.P="'!'EtiT CH~i 9-H"-".'.RP3:--" GAS AiR E:ECTOR CHAl&#x17d;='GM RAt(G" 6AS lc..3EL'TQR C'".:AN 7-tilD RA%-" GAS AIR EJECTOR CHttN 9-HI R46E GAS k>>-"='.3!STEA"'NE A (SPIt<6!~."~32 STER"i't(E B (SPltiB!CV%&QBEN COtiCEhTRATION CV BASEV~NT LEV=6~1 TEN?C CV INT""RiiEDIATE LV-'FT TP.".4?CV ItitERt'iEDIATE LV 6FT FJP 48 C" Il~trFN:DIATE LV'FT TEttP!!9 CV It!TERt(ED!ATE LV'FT TEt(P tt!0 CV QPERATINS i":t>>6F TEtP I!7 VALU=6493.22.3 3.1 41.43.!38.8-4.3 8.56051-02 3.05492+05 1.31069<01 3.00262+01 1.25!?~I 1.09648+(I 1.00432+07
;78647+06'.03068407
;78647+06'.03068407 1.02772406
 
==1.0 2772406==
,46178+02 5.43249te!
,46178+02 5.43249te!
1.01888+03 1.9'89 2+03 2.99398+02 2.99398+02 1.39035403 4.20511-05
1.01888+03 1.9'89 2+03 2.99398+02 2.99398+02 1.39035403 4.20511-05 1.00000I02 4.20511-05 9.99987-04 2.3099!~"'20996-03 2.20996-03 6.22985-06 ii80975-05
 
==1.0 0000I02==
4.20511-05 9.99987-04 2.3099!~"'20996-03 2.20996-03 6.22985-06 ii80975-05
!.52999-03 1.00000+00 1 00000<M 7'?.5 QUAL GOOD LMRti 6009 6009 6009 6009 6009 6009 HALtt 6009 6009 HMRN GOOD HENS HA'HEti6 HALL!6009 GQQD GOOD 6009 HALE(HALtt 6009 6009 HAU', GMD BGQD 6009 6009 6009 6009 6009 HALH 6009 GOOD 99.7 GOOD 99.7%009 99.?6009 99.7 GOOD 120.0 6009 E.U.6%i/AH IFG.IFBF IFGF DEBF t(R/HR tS/HR tS/HR tS/HR tg/HR tS/HR CPt!CPt!CPtt CPA CPt!CPN CPt!CPtt R/HR R/HR CPN Xl/CC tS/HR UCI/CC KI/CC KI/CC KI/CC KI/CC KI/CC UCI/CC KI/CC tS/HR tS/HR X DEGF DER DEGF DEBF DEG!.DEGF Time: 1330 Message: 67 GINNA STATION 1993 EVALUATED EXER ISE MESSAGE FORM Fi I<<C<<IR Simulated Plant Conditions:
!.52999-03 1.00000+00 1 00000<M 7'?.5 QUAL GOOD LMRti 6009 6009 6009 6009 6009 6009 HALtt 6009 6009 HMRN GOOD HENS HA'HEti6 HALL!6009 GQQD GOOD 6009 HALE(HALtt 6009 6009 HAU', GMD BGQD 6009 6009 6009 6009 6009 HALH 6009 GOOD 99.7 GOOD 99.7%009 99.?6009 99.7 GOOD 120.0 6009 E.U.6%i/AH IFG.IFBF IFGF DEBF t(R/HR tS/HR tS/HR tS/HR tg/HR tS/HR CPt!CPt!CPtt CPA CPt!CPN CPt!CPtt R/HR R/HR CPN Xl/CC tS/HR UCI/CC KI/CC KI/CC KI/CC KI/CC KI/CC UCI/CC KI/CC tS/HR tS/HR X DEGF DER DEGF DEBF DEG!.DEGF Time: 1330 Message: 67 GINNA STATION 1993 EVALUATED EXER ISE MESSAGE FORM Fi I<<C<<IR Simulated Plant Conditions:
See Attached Sheets Messacee:<<~"THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes: 1)Accident evaluation and response continues.
See Attached Sheets Messacee:<<~"THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes: 1)Accident evaluation and response continues.
Line 1,064: Line 979:
><" FT TB'=4~CV Iti'TERt>EBIA:E LV>.6FT TET ll!0 CV G-.ERATli~i.-.
><" FT TB'=4~CV Iti'TERt>EBIA:E LV>.6FT TET ll!0 CV G-.ERATli~i.-.
:=V'?T EH?~17 6009 LMRR 6009 6QGD GOOD GOOD 6009 6009 HALtl GOOD 6009 6009 6009 HENS HALtl HEt/6 HAM 6009 6009 GOOD GGQD HALH HAUf K09 6009 6009 6009 6009 GOOD K09 6009 GOOD 6009 6009 G009~0 6009 8S.3 KGD 100.9 6009 100 9'QOGD 100.9 C009 100.9 KOD 116.4 6009 6493.19.7 3.0 41.'3,1 38.8-4.3 9.225?2-02 3.05492+05 5.72137+00 2.93427+01 1.01742+00 1.09648>00 1.00432+07 9.78647+06 1.04864+07 1.02772+06 2.4I963+02 5.59917+01 1.01012+03 2.00678%3 2.99398+02 2.99398+02
:=V'?T EH?~17 6009 LMRR 6009 6QGD GOOD GOOD 6009 6009 HALtl GOOD 6009 6009 6009 HENS HALtl HEt/6 HAM 6009 6009 GOOD GGQD HALH HAUf K09 6009 6009 6009 6009 GOOD K09 6009 GOOD 6009 6009 G009~0 6009 8S.3 KGD 100.9 6009 100 9'QOGD 100.9 C009 100.9 KOD 116.4 6009 6493.19.7 3.0 41.'3,1 38.8-4.3 9.225?2-02 3.05492+05 5.72137+00 2.93427+01 1.01742+00 1.09648>00 1.00432+07 9.78647+06 1.04864+07 1.02772+06 2.4I963+02 5.59917+01 1.01012+03 2.00678%3 2.99398+02 2.99398+02
!.46428~03 4.20511-05
!.46428~03 4.20511-05 2.00000400
 
==2.0 0000400==
>>.205!1-05 9.9998?M 2.30991-06 2.20996-03
>>.205!1-05 9.9998?M 2.30991-06 2.20996-03
.20996-03<.22985-06 i.809M105 1'2999-03 1997-03 3.61997-03 GPH/ttPH BEG.BFGF BEGF DEGF t8/HR tS/HR t-/HR HR/HR tS/ta%/HR PN CPtl CPtt CPtl CPtl CPtt CPtl CPtl R/HR R/HR CP>'l XI/CC N/HR XI/CC XI/CC XI/CC XI/CC Xl/CC XI/CC XI/CC XI/CC tg/HR t8/HR BEGF DEGF DEGF D"-6F BEGF BEGF Time: 1415 Message:~6 GINNA STATION 1993 EVALUATED EXERCISE MES AGE FORIVI 8 I C I R Simulated Plant Conditions:
.20996-03<.22985-06 i.809M105 1'2999-03 1997-03 3.61997-03 GPH/ttPH BEG.BFGF BEGF DEGF t8/HR tS/HR t-/HR HR/HR tS/ta%/HR PN CPtl CPtt CPtl CPtl CPtt CPtl CPtl R/HR R/HR CP>'l XI/CC N/HR XI/CC XI/CC XI/CC XI/CC Xl/CC XI/CC XI/CC XI/CC tg/HR t8/HR BEGF DEGF DEGF D"-6F BEGF BEGF Time: 1415 Message:~6 GINNA STATION 1993 EVALUATED EXERCISE MES AGE FORIVI 8 I C I R Simulated Plant Conditions:
Line 1,184: Line 1,097:
Date: Time: Inst.Type: ger/al/r's:/Power: LLD: Note: All readings are in mr/hr unless otherwise noted.AUXOPg.M I M No, dpnt/100ttrn2 A Monitor Tank~a 0 Bus 14 Ooor 26 B Monitor Tank A Aux.Bldg.Supply A/H Unit~~~~a<I 07:30-10:50 All Areas (Clean)Radiation Levels 0.1mR/tir.Smears 250dpm Airborne Activi iodine=1 E-11 uCi/cc Part=1E-10 uCi/cc ooooo~Prooeasing 0 0 I s X 0 g a~X Ooor 28 Ooor 27 6 A~O Pogtharg<<&#xb9;~Smear Location-x-x-a Rad/Cont.Barrier W~Radiation Level+I Neutron Radiation Level&#xb9;c~Contact Reading Technician Remarks:~~Cont.Area Qs m High Cont.Area+~Radiation Area Qc m High Rad-.Area O Locked High Rad.Area R.E.GINNA STATlON""'je84"" 8@.."Wfaa3rSndti Technician:
Date: Time: Inst.Type: ger/al/r's:/Power: LLD: Note: All readings are in mr/hr unless otherwise noted.AUXOPg.M I M No, dpnt/100ttrn2 A Monitor Tank~a 0 Bus 14 Ooor 26 B Monitor Tank A Aux.Bldg.Supply A/H Unit~~~~a<I 07:30-10:50 All Areas (Clean)Radiation Levels 0.1mR/tir.Smears 250dpm Airborne Activi iodine=1 E-11 uCi/cc Part=1E-10 uCi/cc ooooo~Prooeasing 0 0 I s X 0 g a~X Ooor 28 Ooor 27 6 A~O Pogtharg<<&#xb9;~Smear Location-x-x-a Rad/Cont.Barrier W~Radiation Level+I Neutron Radiation Level&#xb9;c~Contact Reading Technician Remarks:~~Cont.Area Qs m High Cont.Area+~Radiation Area Qc m High Rad-.Area O Locked High Rad.Area R.E.GINNA STATlON""'je84"" 8@.."Wfaa3rSndti Technician:
Date: Tlm e: tnst.Type:/Serial&#xb9;'s: I Power: LLD: Note: All readlnge-are ln mr/hr unless otherwise noted.AUxops~I M No, dpm/100cm2 A Monitor Tank Bus 14 Ooor 26 B Monitor Tank A Aux.Bldg, Supply A/H Unit~~10:50-12:50 All Areas Radiation Levels 62R/h Smears 200,000dpm Airborne Activi iodine=4E-1 uCi/cc part.=3E+0 uC!/cc OOOOO~O.0 s x P B A Posahara Ooor 28~Smear Location-x-x-~Rad/Cont.Barrier OjF~Radiation Level+~Neutron Radiation Level&#xb9;c~Contact Reading Technician Remarks: Qo+Qi Cont.Area High Cont.Area Radiation Area High Rad-.Area Locked High Rad.Area I R.E.GINNA STATlON Technician:
Date: Tlm e: tnst.Type:/Serial&#xb9;'s: I Power: LLD: Note: All readlnge-are ln mr/hr unless otherwise noted.AUxops~I M No, dpm/100cm2 A Monitor Tank Bus 14 Ooor 26 B Monitor Tank A Aux.Bldg, Supply A/H Unit~~10:50-12:50 All Areas Radiation Levels 62R/h Smears 200,000dpm Airborne Activi iodine=4E-1 uCi/cc part.=3E+0 uC!/cc OOOOO~O.0 s x P B A Posahara Ooor 28~Smear Location-x-x-~Rad/Cont.Barrier OjF~Radiation Level+~Neutron Radiation Level&#xb9;c~Contact Reading Technician Remarks: Qo+Qi Cont.Area High Cont.Area Radiation Area High Rad-.Area Locked High Rad.Area I R.E.GINNA STATlON Technician:
Date: Time: inst.Type: Sedal&#xb9;'e: I power: LLD.Note: Ail readlnga are in mr/hr unless otherwise noted.+mott.se I M No.ttpml100oma A Monitor Tank 8us 14 Ooor 26 8 Monitor Tank A AUx.B(4g SUPPiy A/H Unit tat 0 1:50-1: Radiation Leyele~~17m R/hr smears 500.000dpm Airborne Actin locNAOWE-7 tIQl/cc Part~2EA ulcc OOOOO~itrooeaaina 0 0 I s x P S~X 8 A Ooor 28 Door 27~0~Smear Location-x-x-a Rad/Cont.Barrier Radiation Level+~Neutron Radiation Level&#xb9;c~Contact Reading Technician Remarks: 0-6-Cont.Area High Cont.Area Radiation Area High Rad-.Area Locked High Red.Area SECTION 9.0 ONSITE RADIOCOGICAL AND CHEM/STRY DA TA  
Date: Time: inst.Type: Sedal&#xb9;'e: I power: LLD.Note: Ail readlnga are in mr/hr unless otherwise noted.+mott.se I M No.ttpml100oma A Monitor Tank 8us 14 Ooor 26 8 Monitor Tank A AUx.B(4g SUPPiy A/H Unit tat 0 1:50-1: Radiation Leyele~~17m R/hr smears 500.000dpm Airborne Actin locNAOWE-7 tIQl/cc Part~2EA ulcc OOOOO~itrooeaaina 0 0 I s x P S~X 8 A Ooor 28 Door 27~0~Smear Location-x-x-a Rad/Cont.Barrier Radiation Level+~Neutron Radiation Level&#xb9;c~Contact Reading Technician Remarks: 0-6-Cont.Area High Cont.Area Radiation Area High Rad-.Area Locked High Red.Area SECTION 9.0 ONSITE RADIOCOGICAL AND CHEM/STRY DA TA 9.1 Radiolo ical Summar A.Source Term The radiological source term assumed for this scenario was selected to include appropriate quantities of noble gas and radioiodine resulting from the postulated 3%fuel melt accident scenario.Protective action recommendations i.e., sheltering or evacuation for certain Emergency Response Planning Areas (ERPAs)-will be required based upon the anticipated declaration of a General Emergency and plant conditions.
 
===9.1 Radiolo===
ical Summar A.Source Term The radiological source term assumed for this scenario was selected to include appropriate quantities of noble gas and radioiodine resulting from the postulated 3%fuel melt accident scenario.Protective action recommendations i.e., sheltering or evacuation for certain Emergency Response Planning Areas (ERPAs)-will be required based upon the anticipated declaration of a General Emergency and plant conditions.
As a result of accident release rates, the projected whole body and thyroid doses will exceed EPA Protective Action Guides beyond the Site Boundary.The assumed noble gas and radioiodine release quantities are shown in Figure 9.1 as a function of time.The scenario involves one release point which is from the Plant Vent.This occurs as follows: Time Release Poin Release Rate Ci sec 10:50-12:50 Plant Vent 3.21 E+2 (Noble Gas)3.21 E-2 (Radioiodine)
As a result of accident release rates, the projected whole body and thyroid doses will exceed EPA Protective Action Guides beyond the Site Boundary.The assumed noble gas and radioiodine release quantities are shown in Figure 9.1 as a function of time.The scenario involves one release point which is from the Plant Vent.This occurs as follows: Time Release Poin Release Rate Ci sec 10:50-12:50 Plant Vent 3.21 E+2 (Noble Gas)3.21 E-2 (Radioiodine)
The noble gas-to-radioiodine ratio assumed is 10 000:1 during this period of release.Isotopic breakdowns of assumed noble gas, radioiodine and particulate release quantities are provided in Table 9.1.B.Inte rated Offsite Doses Due to Plume Ex osure The downwind integrated doses at 3.5 miles, based upon a 2.0 hour actual release duration are: Time 10:50-12:50 Release Poin Plant Vent Inte ra ed Dose Rem 1.50E+0 (Whole Body)2.63E-1 (Child Thyroid)Princi al Plant Radiolo ical Indications Figures 9.1 through 9.5 provide trend plots for key plant radiological indications, including plant vent concentration, letdown monitor level, containment radiation level and reactor coolant concentration.
The noble gas-to-radioiodine ratio assumed is 10 000:1 during this period of release.Isotopic breakdowns of assumed noble gas, radioiodine and particulate release quantities are provided in Table 9.1.B.Inte rated Offsite Doses Due to Plume Ex osure The downwind integrated doses at 3.5 miles, based upon a 2.0 hour actual release duration are: Time 10:50-12:50 Release Poin Plant Vent Inte ra ed Dose Rem 1.50E+0 (Whole Body)2.63E-1 (Child Thyroid)Princi al Plant Radiolo ical Indications Figures 9.1 through 9.5 provide trend plots for key plant radiological indications, including plant vent concentration, letdown monitor level, containment radiation level and reactor coolant concentration.

Revision as of 05:35, 6 May 2019

1993 Plume Exposure Emergency Preparedness Exercise.
ML17309A531
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/17/1993
From: BELDUE R J, POLFLEIT P S, WATTS R J
ROCHESTER GAS & ELECTRIC CORP.
To:
References
NUDOCS 9312020559
Download: ML17309A531 (548)
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Text

THE ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION EMERGENCY PREPAREDNESS EXERCISE h/IANUAL 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE November 171993 Prepared By: e,.P f t Wesl H.Backus Reviewed By: Richard J.Watts Approved By: Ric d.Beldue (Emergency Planning Milestone Committee)

CONTROLLED COPY NO.93i2020559,931117 PDR ADOCK 05000244 F PDR.I-1

,A g g I er 4" C'1 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE FOREWORD This Exercise package has been developed to provide the basis for the conduct of a simulated radiological accident at the Ginna Station located in Ontario, New York.Through this Exercise, the capabilities and effectiveness of the Emergency Response Plans for the Rochester Gas and Electric Corporation, the State of New York, and Monroe and Wayne Counties will be evaluated.

This package is to be utilized by the Exercise Controllers and observers to initiate, control and evaluate the activities of the participants in the Exercise.The Rochester Gas and Electric Corporation approves this document as the standard for'conduct in performance of the November, 1993 Emergency Preparedness Exercise.

THE ROCHESTER GAS AND ELECTRIC CORPORATION, GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE INTRODUCTION The Nuclear Emergency Response Plan (NERP)describes the emergency response capabilities for a nuclear emergency at the Ginna Station, including support from Federal, State, and local government agencies and private organizations.

The Nuclear Emergency Response Plan provides for continuous emergency preparedness, including an annual Exercise.The purpose of the Plume Exposure Emergency Preparedness Exercise is to activate and evaluate major portions of the emergency response capabilities and other aspects of the Emergency Plan and associated Emergency Plan Implementing Procedures, in accordance with NUREG-0654, and with Nuclear Regulatory Commission (NRC)Regulation 10CFR50.47(b) and Appendix E.This Exercise will be with the participation of the State of New York, and the Counties of Wayne and Monroe in order to assess State and Local Government Agency Emergency Response.The conduct and evaluation of the Exercise provide additional training for the Plume Exposure Pathway emergency response organization personnel and a means to further enhance Rochester Gas and Electric Corporation's emergency response capability.

This Exercise Manual has been developed to provide the basis for the conduct of a simulated radiological accident at the Ginna Station facility located in Ontario, New York.This manual is to be utilized by the Exercise Controllers to initiate, control, and evaluate the activities of the participants in the Exercise.Exercise" la ers" will no have rior knowled e of the na ure of the simula ed incident or an r s thereof such as radiolo ical lume release information includin times content size and weather attern used.This Exercise Manual is the control mechanism for the conduct of the Exercise and consists of two parts, Part I provides a general description and overview of the emergency Exercise.Part II contains the scenario and time schedule of simulated plant conditions.

The Exercise Manual is subject to a limited, controlled distribution.

1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE SCENARIO DEVELOPMENT COMMITTEE" Thomas Alexander Wes Backus Richard Beldue Richard Biedenbach Dan Hudnut James-Knorr Frank Orienter Peter Polfleit James Regan Richard Watts James Zulawski" As authorized by the Emergency Planning Milestone Committee GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS FOREWORD INTRODUCTION SCENARIO DEVELOPMENT COMMITTEE TABLE OF CONTENTS LIST OF FIGURES 1.0 SCOPE AND OBJECTIVES 1.1 1.2 1.3 1.4 Scope Onsite Objectives Summary of Proposed Activities Offsite Proposed Activities 2.0 EXERCISE INFORMATION 2.1 Exercise Participants 2.2 Exercise Organization 2.3 Emergency Response Facilities 2.4 Exercise Conduct 2.5 Precautions and Limitations 2.6 Evaluation and Critique 3.0 TRAVEL INFORIVIATION 3.1 Directions to Ginna Station 3.2 Directions to EOF, ESC and JENC 3.3 Accommodations

4.0 REFERENCES

ABBREVIATIONS-ACRONYMS 4.1 References 4.2 Abbreviations-Acronyms 5.0 CONTROLLER AND EVALUATOR INFORIVIATION 5.1 5.2 5.3 5.4 5.5 Controller Instructions Evaluation Instructions Personnel Assignments Evaluation Packages Public Information, Rumor Control 5 Spouse Phone Questions 6.0 SCHEDULE OF EVENTS GIN NA STATION 1993 PLUME EXPOSURE EIVIERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)7.0 EXERCISE SCENARIO 7.1 7.2 7.3 7.4 Initial Conditions Onsite Sequence of Events Simulator Set Up Instructions Simulator Use Guidelines 8.0 IVIESSAGE FORIVIS AND PLANT DATA SHEETS 9.0 ONSITE RADIOLOGICAL AND CHEIVIISTRY DATA 9.1 Radiological Summary 9.2 ln-Plant Radiological Data 9.3.Post-Accident Sampling Results 10.0 METEOROLOGICAL AND OFFSITE RADIOLOGICAL DATA 10.1 Meteorological Data 10.2 Field Data and Maps 10.3 Field Air Isotopic Data GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)LIST OF FIGURES SECTION 3.0 Figure 3.1 Figure 3.2 Figure 3.3 Figure 3.4 Figure 3.5 Directions to Ginna Station Map of Rochester and Vicinity Map of Rochester Central Business District Directions to State Emergency Operations Center, Albany Map of State Office Building Campus, Albany SECTION 9.0 Figure 9.1 Figure 9~2 Figure 9~3 Figure 9.4 Figure 9.3 Assumed Source Term Release Vent Concentrations Vs Time Letdown Monitor Reading Vs Time Containment Radiation Vs Time RCS Concentrations Vs Time SECTION 10.0 Figure 10.1 Direction of Plume Figure 10.2 Plume Map (0-1 Mile)Figure 10.3 Large Plume Map (0-10 Mile)

GINNA STATION 1993 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd)LIST OF TABLES SECTION 1.0 Table 1~1 Proposed Onsite Activities SECTION 5.0 Tabl'e 5.1 RG&E Onsite Controller Organization SECTION 7.0 Table 7.1 Simulator Set-up Data for Exercise Scenario (LATER)Table 7.2 Simulator Set-up Data (Rad Monitor Readings)(LATER)Table 7.3 Simulator Use Guidelines (LATER)SECTION 9.0 Table 9~1 Table 9.2 Table 9.3 Table 9.4 Table 9.5 Table 9.6 Table 9.7 Assumed Release Quantities Equilibrium Reactor Coolant Activity Post-Accident Reactor Coolant Samples Post-Accident Containment Atmosphere Samples Post-Accident Containment Sump Samples Continuous Air Monitor Readings (Auxiliary Bldg&TSC)Air Sample Results in TSC and Control Room SECTION 10.0 Table 10.1 Table 10.2 Table 10.3 Table 10.4 Table 10.5 Table 10.6 Forecast Information Plume Arrival/Departure Times Radiological Survey/Sampling Data (In Plume)Post-Plume Ground Survey Data (cpm)Post-Plume Micro-R/hr Data Air Sample Isotopic Analysis Data 1-8 SECTION 1.0 SCOPE AND ORIECTIVES SCOPE AND ONSITE OBJECTIVES

-PLUIVIE EXPOSURE PATHWAY~Sco e The 1993 Emergency Preparedness Plume Exposure Pathway Exercise will be conducted on a full-participation basis and will simulate accident events culminating in a radiological accident resulting in the activation of onsite and offsite facilities.

The Exercise will involve events that test the effectiveness of the Ginna Station Emergency Preparedness Program and the integrated capabilities of certain elements of the State of New York, Wayne County and Monroe County emergency organizations.

The Exercise will include the mobilization of state and local resources to adequately verify their capability to respond to an accident at the Ginna Nuclear Power Plant.Onsite Ob ectives for the 1993 Ginna Evaluated Plume Ex osure Pathwa Exercise The major objective of the Exercise is to demonstrate the response capabilities of the Rochester Gas and Electric Corporation Emergency Organization.

Within this overall objective, numerous individual objectives are specified as follows: Demonstrate the ability to mobilize, staff and activate Emergency Response Facilities promptly.Demonstrate the ability to fully staff facilities and to maintain staffing on an around-the-clock basis through the use of relief shift rosters tlimited shift changes may occur to allow for operational restrictions).

Demonstrate the ability to make decisions and to coordinate emergency activities.

Demonstrate the adequacy of facilities and displays and the utilization of procedures to support emergency operations.

Demonstrate the ability to communicate with all appropriate locations, organizations, and field personnel.

Demonstrate the ability to mobilize and deploy Radiation Survey Teams.1-1 Demonstrate the appropriate equipment and procedures for the determination of ambient radiation levels.Demonstrate the proper use of appropriate equipment and procedures for measurement of airborne radioiodine concentrations as low as 1.0 E-7 uCi/cc in the presence of noble gases.Demonstrate the ability to project dosage to the public via plume exposure, based on Plant and field data, and to determine appropriate protective measures, based on plant conditions, Protective Action Guidelines, available shelter, evacuation time estimates, expected release duration, and other appropriate factors, Demonstrate the ability to notify offsite officials and agencies within 15 minutes of declaration of an emergency.

Demonstrate the ability to periodically update offsite officials and agencies of the status of the emergency based on data available at Ginna Station.Demonstrate the ability to notify emergency support pools as appropriate (Le., INPO, ANI, etc.).Demonstrate the ability to notify onsite personnel using plant alarms and public address systems.Demonstrate the organization's ability to assess plant parameters and symptoms indicative of degrading plant conditions, and relate such symptoms to prescribed Emergency Action Levels.Demonstrate the organization's ability to properly classify emergency conditions.

Demonstrate the organizational ability and resources necessary to manage an accountability of personnel within the restricted area.Demonstrate the organizational ability and resources necessary to control access to the site.Demonstrate the ability to continuously monitor and control emergency workers'xposure.

1-2 Demonstrate the adequacy of facilities and displays to support the Joint Emergency News Center operations.

Demonstrate the ability to brief the media in a clear, accurate, and timely manner.Demonstrate the ability to provide advanced coordination of information released to the public.Demonstrate the ability to establish and operate rumor control in a coordinated fashion.Demonstrate the adequacy of in-plant post-accident sampling techniques and analysis.Demonstrate the ability to develop a preliminary action plan to support plant recovery.Demonstrate the ability to respond to information requests from simulated NRC staff during the course of the Exercise.Demonstrate the ability to effect a timely shift change of key emergency response staff positions during the Exercise.Demonstrate the ability to conduct a post-exercise critique which adequately characterizes licensee performance based upon controller and observer assessments.

Summar of Pro osed Activities Table 1.1 provides a list of proposed RGSE activities.

1-3 TABLE 1.1 1993 GINNA STATION EMERGENCy PREPAREDNESS EXERCISE PLUIVIE EXPOSURE PROPOSED ONSITE ACTIVITIES RG&E Notification of Agencies Call Up of Personnel Activate Organization Maintain Security Plant Evacuation

&Accountability Conduct Dose Assessment Protective Action Recommendations Operate Joint Emergency News Center Dispatch Field Survey Teams Obtain PASS Sample Shift Change-Key Personnel Actual Actual Actual Actual Actual Actual Actual Actual Actual-3" Actual Actual" Field teams will be deployed and will demonstrate appropriate field monitoring techniques and communications with respective emergency response facilities.

A minimum of 1 onsite and 2 offsite teams will be deployed.Shift change will include principal positions in the TSC, OSC, EOF and JENC.P 1-4 SIMULATIONS o Respiratory protection and protective clothing will be simulated by onsite/offsite survey teams.In-Plant teams will don respiratory protection and protective clothing prescribed by Health Physics and Chemistry personnel according to postulated scenario plant conditions.

o In general, Exercise participants should follow applicable plant procedures as closely as possible, and will be stopped by Controllers before actual equipment is manipulated (except PASS).Simulated repairs and other corrective actions should be described to Controller-

/Evaluators as fully as possible.o Informational requests from controllers simulating NRC staff.1-5

SUMMARY

OF PROPOSED OFFSITE OBJECTIVES AND ACTIVITIES P p d ffi bj i d i"ii d it di~A A.1-6 A TTACHMENT A OFFSITE EXERCISE OBJECTIVES 1-7 PROPOSED OB JECTIVES FOR GINNA Wayne County Emergency Operations Center (WCEOC)OBJECTIVE¹PEA ARCAs BIL ATI F R E Y PER 1.Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations.

Demonstrate the capability to activate and staff emergency facilities for emergency operations.

S-I TD L W R VIR 2.Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

None IR T NA D 3.Demonstrate the capability to direct and control emergency operations.

None 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.None W R R 5.Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers.None 7.Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering.

WC-l E PR TIV D I N 9.Demonstrate the capability to make timely and appropriate protective action decisions (PAD).None OBJECTIVE¹PROPOSED OB JECTIVES FOR GINNA Wayne County Emergency Operations Center (WCEOC)PEA ARCAs E ND TIFI 10.Demonstrate the capability to promptly alert and notify the public within None the 10-mile plume pathway emergency planning zone (EPZ)and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.

LI INSTRU TIO S ND R EN F RMAT 11.Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instructions to the public.None T F A I L AND 14.Demonstrate the capability and resources to implement potassium iodide None (KI)protective actions for emergency workers, institutionalized individuals, and, if the State plan specifies, the general public.P NTATI F PROT p p p 15.Demonstrate the capability and resources necessary to implement appropriate protective actions for special populations.

None IMP PR T V H 16.Demonstrate the capability and resources necessary to implement protective actions for school children within the plume pathway emergency planning zone (EPZ).None QT D T 17.Demonstrate the organizational capability and resources necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas.None PROPOSED OBJECTIVES FOR GINNA Wayne County Field Activities PVCFA)OBJECTIVE¹PEA ARCAs OBILI ATI N FEMER N P R L 1.Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations, Demonstrate the capability to activate and staff emergency facilities for emergency operations.

T I Y W E V NME4T 2.Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

  • WC-16 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.None E R E YW 5.Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers.None DR Dl MO TI R 6.Demonstrate the appropriate use of equipment and procedures for determining field radiation measurements.

ED J N 7.Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering.

None ELD RADI I AL N P RTI A IN-I VITY'RADI 8.Demonstrate the appropriate use of equipment and procedures for the~measurement of airborne radioiodine concentrations as low as 10'0.0000001) microcuries per cubic centimeter in the presence of noble gases and obtain samples of particulate activity in the airborne plume.*Field verification is not required.-3-4one OBJECTIVE¹PROPOSED OBJECTIVES FOR GINNA Wayne County Field Activities (WCFA)PEA ARCAs MPLEMENTATION OF PR T OR EM RGENCY WO R DTHE E'ERA P I VE TIONS-SE F K IONALIZED I IVID S 14.Demonstrate the capability and resources to implement potassium iodide None (KI)protective actions for emergency workers, institutionalized individuals, and, if the State plan specified, the general public.LEMENTATI N F PR T V PE IAL POP LATI N 15.Demonstrate the capability and resources necessary to implement appropriate protective actions for special populations.

None NTATI N F V L 16.Demonstrate the organizational capability and resources necessary to None implement protective actions for school children within the plume pathway emergency planning zone (EPZ).TR IC D A 17.Demonstrate the organizational capability and resources necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas.None E PTI N ENTE RE I TRATION 18.Demonstrate the adequacy of procedures, facilities, equipment and personnel for the radiological monitoring, decontamination and registration of evacuees.None A E A 19.Demonstrate the adequacy of facilities, equipment, supplies, personnel and procedures for congregate care of evacuees.<<KC-5'AC-8*Field verification is not required.*

OBJECTIVE¹PROPOSED OBJECTIVES FOR GINNA Wayne County Field Activities (WCFA)PEA ARCAs MER W R R P T ANDVEHI L Nl R ND D TA ATI N 22.Demonstrate the adequacy of procedures for the monitoring and decontamination of emergency workers, equipment and vehicles.WC-6 WC-7 PROPOSED OBJECTIVES FOR GINNA Monroe County Emergency Operations Center (MCEOC)OB JECTIVE 0 PEA ARCAs I TION OF R 1.Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations.'emonstrate the capability to activate and staff emergency facilities for emergency operations.

IT S-IP E TD Y NDW R VRON 2.Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

None MAND 0 3.Demonstrate the capability to direct and control emergency operations.

None I ATI 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.None Y W RKER XP 5.Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers.None D SE PR JE 7.Demonstrate the capability to develop dose projections and protective action recommendations regarding eva'cuation and sheltering.

None PR ECTIVEA I ND I N KI 9.Demonstrate the capability to make timely and appropriate protective action decisions (PAD).None PROPOSED OBJECTIVES FOR GINNA Monroe County Emergency Operations Center (MCEOC)OBJECTIVE 0 PEA ARCAs LERT AND NOTIFI TI 10.Demonstrate the capability to promptly alert and notify the public within None the 10-mile plume pathway emergency planning zone (EPZ)and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.

UBLIC INSTR Tl N ND EMER N Y INF 11.Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instructions to the public.None T 8 FP OR EMER E W T A R IVID A ND 14.Demonstrate the capability and resources to implement potassium iodide None (KI)protective actions for emergency workers, institutionalized individuals, and, if the State plan specifies, the general public.MPLEMENTAT PE IALP P 15.Demonstrate the capability and resources necessary to implement appropriate protective actions for special populations.

None PLE M T I P T TI 16.Demonstrate the capability and resources necessary to implement protective actions for school children within the plume pathway emergency planning zone (EPZ).None FFI AND A TR 17.Demonstrate the organizational capability and resources necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas.None PROPOSED OBJECTIVES FOR GINNA Monroe County Field Activities (MCFA)OBJECTIVE¹PEA ARCAs OB IZATI N F EMER PER EL 1.Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations.

Demonstrate the capability to activate and staff emergency facilities for emergency operations.

ITIES-E IPM NT DISPLAYS AND W RK ENVIR NMENT 2.Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

None Nl T 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.None RE NT 5.Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers.MC-3 MC-4 B 6.Demonstrate the appropriate use of equipment and procedures for determining field radiation measurements.

None E PROJ I 7.Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering.

None RIILDR M'T-I D P RT IV Y RIN 8.Demonstrate the appropriate use of equipment and procedures for the measurement of airborne radioiodine concentrations as low as 30 7 (0.0000001) microcuries per cubic centimeter in the presence of noble gases and obtain samples of particulate activity in the airborne plume.Xone PROPOSED OBJECTIVES FOR GINNA Monroe County Field Activities (MCFA)OBJECTIVE¹PEA ARCAs PLEMENTATI F P OTE TIVE TI N-E ORE ER EN YW RK R TIT D E ENERAI I 14.Demonstrate the capability and resources to implement potassium iodide (KI)protective actions for emergency workers, institutionalized individuals, and, if the State plan specified, the general public.None MPLEMENTATI N F PR PE IAL POP LA 10 IV A I 15.Demonstrate the capability and resources necessary to implement appropriate protective actions for special populations.

MC-1 L 16.Demonstrate the organizational capability and resources necessary to None implement protective actions for school children within the plume pathway emergency planning zone (EPZ).I ND 17.Demonstrate the organizational capability and resources necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas.MC-2 E PTION ENTER-D ONT 18.Demonstrate the adequacy of procedures, facilities, equipment and personnel for the radiological monitoring, decontamination and registration of evacuees.None.R 19.Demonstrate the adequacy of facilities, equipment, supplies,.personnel and procedu'res for congregate care of evacuees.None EDI ERVI-RA SP RT TI N 20.Demonstrate the adequacy of vehicles, equipment, procedures, and personnel for transporting contaminated, injured, or exposed individuals.

None 4 OBJECTIVE¹PROPOSED OBJECTIVES FOR GINNA Monroe County Field Activities (MCFA)PEA ARCAs DI AL ERV S-F 21.Demonstrate the adequacy of the equipment, procedures, supplies, and None personnel of medical facilities responsible for treatment of contaminated, injured, or exposed individuals.

MER E YW RKERS E P ENT ND I R 6 AND E NT M T 22.Demonstrate the adequacy of procedures for the monitoring and decontamination of emergency workers, equipment and vehicles.None OBJECTIVE¹PROPOSED OB JECTIVES FOR GINNA Lake District Emergency Operations Center (LDEOC)PEA ARCAs MOBILIZATION OF EMER EN Y PERSO EL 1~Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations.

Demonstrate the capability to activate and staff emergency facilities for emergency operations.

None FACILITIES

-E UIPMENT DISPL Y AND W RK ENVIR N NT 2.Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

None IR T ND NTR L 3.Demonstrate the capability to direct and control emergency operations.

None ATION 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.None OB JECTIVE 0 PROPOSED OBJECTIVES FOR GINNA New York State Emergency Operations Center (SEOC)PEA ARCAs BZTI NF 1.Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations.

Demonstrate the capability to activate and staff emergency facilities for emergency operations.

r IE-P NT D P VI 2.Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

None RE TI AND T 3.Demonstrate the capability to direct and control emergency operations.

None 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.None 5.Demonstrate the capability to continuously monitor and control radiation exposure to.emergency workers.None P ED P T a 7.Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering.

None T V T I 9.Demonstrate the capability to make.timely and appropriate protective action decisions (PAD).None OBJECTIVE 0 PROPOSED OBJECTIVES FOR GINNA New York State Emergency Operations Center (SEOC)PEA ARCAs LERTANDNOTIFI ATI N a 10.Demonstrate the capability to promptly alert and notify the public within None the 10-mile plume pathway emergency planning zone (EPZ)and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.

P BLI INSTRU TIONS ANDEM R EN Y F RMATI N a 11.Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instructions to the public.None MPLEMENTATI N F PROTECTIVE ACTIO-S F K F R EMERGEN Y WORKER INSTIT TI NAL DIVID AL AND THE GENERAL P B I 14.Demonstrate the capability and resources to implement potassium iodide None (KI)protective actions for emergency workers, institutionalized individuals.

and, if the State plan specifies, the general public.(a)This objective will be evaluated for SEOC should the Governor declare a State of Emergency.

OBJECTIVE 0 PROPOSED OBJECTIVES FOR GINNA Emergency Operations Facility (EOF)PEA ARCAs BILIZATI N F EMER EN R L 1.Demonstrate the capability to alert and fully mobilize personnel fo'r None both emergency facilities and field operations.

Demonstrate the capability to activate and staff emergency facilities for emergency operations.

FACIL S-E IPMENT Dl P AY DW RKENVIR'MENT 2.Demonstrate the adequacy of facilities, Equipment, displays, and other materials to support emergency operations.

None C MM Nl Tl 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.EOF-1 (State only)

PROPOSED OBJECTIVES FOR GINNA Joint News Center (JNC)OBJECTIVE¹PEA ARCAs 0 ILIZATION F EMER EN P NNEL 1~Demonstrate the capability to alert and fully mobilize personnel for None both emergency facilities and field operations.

Demonstrate the capability to activate and staff emergency facilities for emergency operations.

ITIES-E IPM NT Dl PL Y NDWOR NVIRONME T 2.Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.

None JNC-I (State only)NI ATI 4.Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.None 10.Demonstrate the capability to promptly alert and notify the public within 4one the 10-mile plume pathway emergency planning zone (EPZ)and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.

11.Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instructions to the public.4~ne R N 12.Demonstrate the capability to coordinate the development and dissemination of clear, accurate and timely information to the news medi~'I N()ne R N Y I F RMATI NTR 13.Demonstrate the capability.to establish and operate rumor control in a coordinated and timely manner.brine SECTION 2.0 EXERCISE INFORMA TION 2.0 EXERCISE INFORMATION 2.1 Exercise Partici ants 2.1~1 The participants in the Exercise will include the following:

ROCHESTER GAS AND ELECTRIC CORPORATION A.Facilities Mana ement and Su ort Personnel 1.Simulator Control Room 2.Technical Support Center (TSC)3.Operations Support Center (OSC)4.Survey Center (SC)5.Emergency Operations Facility (EOF)6.Joint Emergency News Center (JENC)7.Engineering Support Center (ESC)B.Emer enc Res onse Teams 1.Radiation Survey Teams (RSTs)2.First Aid Team (if necessary) 3.Emergency OSC Teams 4.Security Force 5.Post Accident Sampling System (PASS)Team 6.Chemistry/Health Physics Support 7.Fire Brigade (if necessary) 2.1.2 OFFSITE AGENCIES/ORGANIZATIONS Participation of the following agencies/organizations is expected: A.Federal 1~Nuclear Regulatory Commission 2.Federal Emergency Management Agency 3.National, Weather Service B.State 1.New York State Emergency Management Office 2.New York State Department of Health 3.New York State Police 4.Other Supporting State Agencies C.Local 1.Wayne County 2.Monroe County 3.Other Supporting County Agencies 2-2 2.2 Exercise Or anization The organization for this Exercise will consist of the Exercise Coordinator, the Controllers, the Players and the Observers, as follows: 2.2.1 The Exercise Coordinator will coordinate Exercise preparations including the development of the scenario and controller input messages.He will control all aspects of the conduct of the Exercise, prepare a consolidated evaluation and critique report at the conclusion of the Exercise, and prepare and follow up on an itemized list of corrective actions recommended as a result of the evaluation and critique, 2.2.2~C>>lied I I d f f follows: A.A Lead Controller is assigned to each emergency response facility.The Lead Controller is responsible for all Controller, Evaluator and Observer activities for that facility and, if appropriate, its associated teams.Controllers for teams or sub areas of a facility report to the Lead Controller of that facility.B.The Controllers will deliver"Exercise Messages" to the designated Players at various times and places during the Exercise, inject or deliver additional messages as may be required to initiate the appropriate Player response and keep the Exercise action moving according to the scenario and Exercise objectives, observe the Exercise participants at their assigned locations, and prepare evaluation forms.Controllers/Observers submit written recommendations on corrective actions to the Lead Controller, who in turn summarizes all comments for submittal to the Exercise Coordinator prior to the scheduled critique.The Controllers will be provided with a list of instructions in the Exercise scenario.C.Persons designated as Controllers/Observers for a given function will also be assigned as Evaluators of that function when feasible.Evaluators will record their observations using an evaluation form and provide recommendations on corrective actions to the Lead Controller in whose facility they evaluate exercise performance on the basis of standards or requirements contained in the appropriate Emergency Plan, Implementing Procedures, and Exercise messages as described herein.They will take steps, whenever possible, to collect data on the time qnd motion aspects of the activity observed for post-Exercise use for implementing improvements.

2-3 Controllers will be iden ified b wearin reen bad es wi h white let erin s a in"Controller".

2.2.3~Pla ers include Ginna Station and other Rochester Gas and Electric Corporation personnel assigned to perform emergency functions, as described in the Emergency Plan and Implementing Procedures.

Players from offsite organizations and agencies (county, State and private industry)are participants in the Exercise as described in their respective Emergency Plans and Standard Operating Procedures.

2.2.4 Observers from the Rochester Gas and Electric Corporation and other organizations may be assigned to participate in the Exercise solely for the purpose of observing/evaluating Exercise activity.They will be provided with orientation information and appropriate Exercise publications.

Observers will be a ro riatel identified b wearin arm bands or bad es.Federal a enc observers will be identified b wearin arm bands or bad es wi h le erin s a in"NRC" or"FEMA".Visitors from the Rochester Gas and Electric Corporation and other organizations may be assigned, on a limited basis, for the sole purpose of observing Exerciseactivities for personal education.

They will be provided with orientation information and appropriate Exercise publications.

Visitors will b iden ifi bad es statin"Visi or".b wearin arm ban or 2.2.5 Requests to participate as a Visitor should be made in writing and contain the Visitor's full name, home address, phone number and organization affiliation.

Requests to participate as Visitors must be submitted to the RGSE Corporate Nuclear Emergency Planner (CNEP)no later than one week before the Exercise.2.3 Emer enc Res onse Facili ies During the Exercise, special facilities must be activated to manage, assess and support emergency response.2-4 RGBcE FACILITIES The Rochester Gas and Electric Corporation Emergency Res p o n s e Facilities are: A.Simila or Con rol Room The Ginna Simulator Control Room will be used.Control Room emergency response measures will be-exercised--under the direction of the Exercise Shift Supervisor, acting as the Emergency Coordinator, until relieved by the Plant Manager or alternate.

The Simulator Control Room is located in the Simulator Building next to the Ginna Training Center.B.Technical Su ort Center TSC When emergency conditions escalate to an Alert status or higher, coordination of the emergency response will shift from the Control Room to the TSC, located off the Mezzanine Level of the Turbine Building.The TSC Director relieves the Shift Supervisor as Emergency Coordinator and directs activities from the TSC.The TSC is the location from which technical management personnel utilize information on Plant status provided in the TSC to support actions being performed in the Control Room.The TSC serves as the primary communications source to the NRC, OSC, EOF and offsite agencies, and will perform other functions of the EOF until the EOF is activated.

C.0 erations Su ort Center The OSC, which is located in the TSC, provides a location where emergency response teams can be assembled and coordinated during an emergency.

The OSC will be activated for emergency conditions classified as an Alert or higher, and may be activated for an Unusual Event at the discretion of the Emergency Coordinator.

D.Emer enc 0 erations Facilit EOF The EOF, which is located in the basement of 49 East Avenue in Rochester, will be activated for emergency conditions classified as a Site Area Emergency or General Emergency (optional for the Alert status).The EOF/Recovery Manager directs the activities of the EOF/Recovery Organization from the EOF.I 2-5 The TSC Emergency Coordinator reports to the EOF/Recovery Manager.The EOF is the command post for coordination of response measures with offsite organizations, assessment of radiological and environmental conditions and determination of recommended protective actions for the public.The EOF also provides direction and management of recovery operations.

E.Joint Emer enc News Center JENC The JENC, which is located at 89 East-Avenue.

in-Rochester, provides the point of contact for the coordinated release of news and information to the news media and the general public..The JENC is staffed by RGSE Corporation, County, State and Federal officials and will be activated for emergency conditions classified as an Alert, Site Area Emergency or General Emergency.

2-6 24 Exercise Conduct 2.4.1 Overview The Exercise will simulate an abnormal radiological incident at Ginna Station which will start with an Unusual Event and escalate to a Site Area Emergency.

During the course of the Exercise, in order to evaluate coordination with appropriate State and local agencies,-incidents will arise which require response by offsite emergency response organizations.

The Exercise will also simulate an offsite radiological release which will require deployment of Ginna.Station, and Wayne County and Monroe County radiological survey teams for offsite monitoring.

The conduct of the Exercise will demonstrate the effectiveness of selected organizations, personnel, functions, and/or activities of the appropriate Emergency Plans and Implementing Procedures.

The simulated emergency will then de-escalate.

The Recovery Phase will be initiated and the Exercise will then be terminated.

2.4.2 Actions Emergency response actions during the simulated emergency will include: recognition and classification of emergency conditions; assessment of onsite/offsite radiological consequences; alert/notification and mobilization of emergency response organizations; implementation of in-Plant corrective actions;activation/operation of emergency response facilities and equipment; preparation of reports, messages and record-keeping; and recommendation of protective actions.2-7 Communications The Exercise will also demonstrate the effective use of communications systems.An actual emergency operation usually requires the extensive use of both telephone and radios.The telephone is the primary means of communication and will be attempted first, with radio as a backup, unless radio is the only means available.

Separate telephone numbers will be used for Controller communications to prevent the Players from learning in advance of the situation to which they are to be subjected during the Exercise.Close cooperation and coordination among Controllers is essential due to the number of persons assigned to the Controller role.RGKE offsite radiation survey, teams are equipped with portable radios, and are provided cellular telephones for back-up communications.

Survey team controllers are encouraged to use the cellular telephones if clarifications of controller instructions are required while in the field.Controllers Lead Controllers will be stationed in the Simula or Con rol Room OSC CC 0 J C dd CC.Dlyy dC I dlfy Exercise messages or initiate free play messages.A.The Simulator Control Room will be the central point for organization of Exercise messages and is the key to ensuring that the Exercise progresses on schedule, Simulated Plant parameters will be provided to the Simulator Control Room operators either by panel indications displayed in the Simulator Control Room or through plant data and status sheets.Since it is necessary that the emergency escalate to the General Emergency level, it may d y d I-<<lldl I<<I.T~d will acce t th Exercise messa es as wri ten.If corrective actions are postulated that would terminate the emergency, they should be identified to the Lead Controller in the affected facility so that the scenario will progress as designed, The Exercise Players are expected to"free play" the scenario to the extent practical.

Notifications of, and contact with, supervisors, Plant management and offsite agencies will be made in accordance with the Emergency Plan Implementing Procedures.

2-8 B.The TSC will be the coordination point for onsite emergency response activities.

TSC personnel will also coordinate offsite emergency response activities until activation of the EOF.TSC and EOF personnel will be aware that if the Exercise is to proceed as planned, and if the offsite organizations are to be exercised, it may be necessary to postulate non-credible situations.

This is done to ensure that various aspects of the onsite and offsite emergency response organizations are tested.TSC and EOF ersonnel will acce Exercise messa es as wri en.The in ended res onse is not o ex lain wh a situation could not occur but o react as thou h it did occur.If corrective actions are postulated that would terminate the emergency, they should be noted to the Lead Controller.

The Exercise Players in the TSC and EOF are expected to"free play" the scenario to the extent practical.

Notifications of, and contact with, supervisors, Plant management and offsite agencies should be made in accordance with the Emergency Plant Implementing Procedures.

The scenario is designed to activate onsite and offsite emergency response capabilities.

The Lead Controller may inject other information or change a message to ensure that the Exercise progresses as planned.~Pla ere The success of the Exercise is largely dependent upon Player reaction, Player knowledge of their appropriate Emergency Plan and Implementing Procedures and an understanding of the purpose of the Exercise.Initial conditions which will affect Player action or reaction will be provided to the Players at the time the Exercise begins.However, most of the elements of the Exercise play will be introduced through the use of controlled Exercise message forms and messages generated by Players as a result of the particular emergency activity performed.

Players, therefore, are responsible for initiating actions during the Exercise in accordance with instructions, responsibilities and tasks for their particular function.Each Player will advise his/her Controller prior to performing required emergency actions during the play of simulated activities-to ensure that the Player is credited for his/her actions.2-9 Players are reminded not to be excessively concerned with the mechanics or cause of the Exercise scenario.This Exercise is designed to evaluate the Emergency Plan, Implementing Procedures and emergency preparedness training program and not the probability, feasibility or detailed mechanics of the simulated accident.Additionally, the Exercise is a training vehicle for Rochester Gas and Electric Corporation personnel to practice coordinating with outside g I I I I I d~P I.~PI Id no e an needed im rovemen s h c me o their a en ion rin the Exerci and submi hem he a ro ria e Con roller a he conclusion of he Exercise.2.5 Precautions and Limitations This section provides information for all Exercise Controllers and Observers related to the rules and guidelines to be followed throughout the conduct of this Exercise.Prior to initiation of the Exercise, a pre-Exercise briefing will be held to review the entire Exercise process with all the Exercise Controllers and Observers identified in this manual.A.Should at an time durin the course of the conduc of this Exercise an ac ual emer enc si ua ion arise all ac ivities and comm nica ions related to he Exercise will be sus ended.It will be the responsibility of any Exercise Controller or Observer that becomes aware of an actual emergency to suspend exercise response in his/her immediate area and to inform the Lead Exercise Controller of the situation, Upon notification of an actual emergency, the Lead Exercise Controller may notify all other Controllers/Observers to suspend all Exercise activities, The Lead Exercise Controller will make a determination at that point whether to continue, place a temporary hold on, or terminate the Exercise.B.Should, at any time during the course of the conduct of this Exercise, an Exercise Controller or Observer witness an Exercise participant undertake any action which would, in the opinion of the Controller/Observer, place either an individual or component in an unsafe condition,.the Controller/Observer is responsible for intervening in the individual's actions and terminating the unsafe activity immediately.

Upon termination of the activity, the Controller/Observer is responsible for contacting the Lead Exercise Controller and informing him of the situation.

The Lead Exercise Controller will make a determination.

at that point whether to continue, place a temporary hold on, or terminate the Exercise.2-10 C.No pressurization of fire hoses, discharging of fire extinguishers, or initiation of any fire suppression systems will be required for the Exercise.D.Manipulation of any Plant operating systems (except for the PASS system), valves, breakers, or controls in response to this Exercise are only to be simulated.

There is to be no alteration of any Plant operating equipment, systems or circuits during the response to this Exercise.E.All repair activities associated with the scenario will be simulated with extreme caution emphasized around operating equipment.

F.All telephone communications, radio transmissions and public address announcements related to the exercise must begin and end with the statement,"This is an ex reise".Should a Controller or Observer witness an Exercise participant not observing this practice, it is the Controller's/Observer's responsibility to remind the individual of the need to follow this procedure.

G.Any motor vehicle response to this Exercise, whether it be ambulance, fire fighting equipment, police/security vehicles or field monitoring teams, should observe all normal motor vehicle operating laws included posted speed limits, stop lights/signs, one way streets, etc.Should any onsite security actions be required in response to this Exercise, participants are to cooperate as directed by the Security Force, and security representatives are to be prudent and tolerant in their actions.Exercise participants are to inject as much realism into the Exercise as is consistent with its safe performance; however, caution must be used to prevent over-reaction.

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 Exercise Controller or Observer who is aware of an individual or group of individuals in the immediate vicinity who may have become alarmed or confused about the situation, should approach that individual or group and explain the nature of the Exercise and its intent.2-11 2.6 Evalua ion and Criti ue The Exercise will be evaluated by Controllers/Observers who have expertise in, or qualifications to evaluate the activity in their assigned location.Controllers/Observers will evaluate Exercise performance on the basis of requirements contained in the Emergency Plan Implementing Procedures and Exercise messages.Controllers/Observers will prepare evaluation forms and provide recommendations on corrective actions to the Exercise Coordinator.

After the Exercise is completed, the Exercise Coordinator will conduct a post-Exercise critique..Deficiencies in the Emergency Plan, Implementing Procedures, emergency preparedness training program, facilities, equipment and/or other areas will be identified through the critique process.The deficiencies will be documented by the Exercise Coordinator and corrected by the individuals who have responsibility in the area of the identified deficiency.

Controller and Observer information is contained in Section 5.0.The schedule for the critiques is shown in Section 6.0.2-1 2 SECTION 3.0 TRA VEL INFORMA TION 3.0 TRAVEL INFORIVIATION This section of the Ginna Station Exercise Manual provides travel information to those individuals from RG&E, other utilities, local/State/Federal government, and/or other organizations who will participate/observe the Drill.Permission for Visitors to observe the Drill must be obtained from: Corporate Nuclear Emergency Planner Rochester Gas and Electric Corporation 49 East Avenue Rochester, NY 14649-0001,.31 Directions to Ginna Nuclear S a ion Ginna Station is located on the southern shore of Lake Ontario in Wayne County, New York, approximately 24 miles northeast of Rochester, New York (see Figure 3.1).3.1.1 Air Several airlines provide passenger service to the Rochester-Monroe County International Airport.3.1.2 Car A.Several car rental agencies are available at the Rochester-Monroe County International Airport to provide rental vehicles for ground transportation to Ginna Station.B.Persons traveling from the Rochester-Monroe County International Airport via auto should take Route 204 East to Route 390 South.Route 390 becomes Route 590 as one proceeds around the~Loop.Follow Route 590 North to Route 104 East.Follow Route 104 to Route 350 (Ontario Center Road).Turn left (North)and proceed to Ginna Station.Total distance is approximately 40 miles.3.2 Directions to the EOF ESC and JENC 3.2.1 Air From the Rochester-Monroe County International Airport take 204 to 390 North, 490 East into the City onto the Inner Loop to the East Avenue ramp to the third signal light.Turn right.3-1 3.2.2 From the Thruway, use Exits 45 or 46 into Rochester and the Inner Loop to the East Avenue ramp as in 3.2.1.3.2.3 To get to the Emergency Operations Facility (EOF)and Engineering Support Center (ESC), go to the intersection of East Avenue and Chestnut Street (black square on map)~EOF and ESC are in 49 East Avenue.The JENC is at 89 East Avenue (see Figure 3.2).3.3 Accommodations Hotel/motel accommodations may be obtained at the following locations:

Depot Hotel, Pittsford Marriott Hotel, Greece Red Roof Inn, Henrietta Brookwood Inn, Pittsford Woodcliff Lodge, Perinton (716)381-9900 (716)225-6880 (716)359-1100 (716)248-9000 (716)248-4810 3-2 LAKE ONTARIO GINNA STATION+'Ioi N wotro~18 1~lD4 DHTAklo ClalTK L 4kb 3$o~~g g xi.z Q g 0 ROCHESTER ROCHESTER-MONROE COUNTY AIRPORT I 0 0 0Ã0 T~8 10 ROCHESTER ANO VICINITY 1'a!I I~I I I~/I J~/I I/I I/)f,l C,.aae~~~Mva+aars&Weag sssmr aaeee~Q%is IOOeeso~I~/eaaaOI e OIO Qsea~Oe A eeeO eseasael I W~/~~I aae sess alp oooee~ose 0&>>~ease IL am g~~I I~(ooo/OIIa/I)

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Olla 54 Id."p C/l m n Cl m Th C mo n OT" 4 n rt I O 0~m tf~44l 4 TO TNIVWAT.ttlT tt~~TIKI, ST tt I+---Ooetae ALNT K"l li Nll LIvIWV lvl'ROH THE SOUTH or WEST take the N.Y.S.Thruvtay (1-.87 Northboundll-90 Eastboun to (alt.'i.After thL toll booth 3/v itrLT.c<J wtral)ht ith l-)3 to Exit 3.STATE OFFICE BUILDING CAMPUS 1220 lVASH I NG TON AV f N 0 f ALBAN Y.Nf W YORK\&I M~IWl IOCJOI~Illi~CItl IAJVlt lisle~Ilg jg lll~IILAKIIIINA4AICAA IIA1CI~IlllN*FROli THE, NORTH take the Adirondack Northway (I-87)South Exit IE.proceed East on I-90 to Exit 3.o FROiq MWNTOWN AI BANy take 1-90 Westbound to Exi t 3.s FRY jOWHTOWtl Al.BANy take Washington Avenue to Western Avenue (Rte gp)to the State Office Building Campus.to n SECTION 4.0 REI=ERENCES/ABBREVIA TIONS-ACRONYiNS 4.1 References 4.1.2 10 CFR 50.47, 50.54, Appendix E 44 CFR 350.9 4.1.3 NUREG-0654/FEMA-REP-1, Rev.1, Criteria for Pre ara ion and Evalua ion of Radiolo ical Emer enc Res onse Plans an Pre aredness in S ort of N clear Power Plan 4.1.4 4.1.5 4.1.6 4.1.7 4.1.8 4.1.9 RGSE Nuclear Emergency Response Plan (NERP)GS Radiation Emergency Plan Implementing Procedures (EPIPS)GS License and Technical Specifications GS Piping and Instrumentation Drawings New York State Radiological Emergency Response Plan Monroe County Emergency Preparedness Plan 4.1.10 4.1.11 Wayne County Radiological Response Plan INPO Emergency Preparedness Drill and Exercise Manual 4-1 4.2 Abbreviations

-Acron ms A/E ALARA AOV ARMS ARV ATWS BAST CD CFR CV CR DOE DOE-IRAP EAL(s)EBS EC ECL(s)ENS EOC EOF EPA EPC EPIP(s)EPZ ERF(s)ERPA ESC FEMA FRERP GS HALM HP HPN HVAC INHB INPO JENC Kl LALM LCO LOCA LWR MOV MPC NERP Architect Engineer As Low As Reasonably Achievable Air-Operated Valve , Area Radiation Monitor(s)

Atmospheric Relief Valve Anticipated Transient Without Scram Boric Acid Storage Tank Civil Defense Code of Federal Regulations Containment Control Room Department of Energy DOE Interagency Radiological Assistance Plan Emergency Action Level(s)Emergency Broadcast System Emergency Coordinator Emergency Classification Level(s)Emergency Notification System (NRC)Emergency Operations Center Emergency Operations Facility Environmental Protection Agency Emergency Planning Coordinator Emergency Plan Implementation Procedure(s)

Emergency Planning Zone Emergency Response Facility(s)

Emergency Response Planning Area Engineering Support Center Federal Emergency Management Agency Federal Radiological Emergency Response Plan Ginna Station High Alarm Health Physicist Health Physics Network Heating Ventilation Air Conditioning Inhibited (Alarm Suppressed)

Institute of Nuclear Power Operations Joint Emergency News Center Potassium Iodide Low Alarm Limited Condition of Operation Loss of Coolant Accident Light Water Reactor Motor-Operated Valve Maximum Permissible Concentration Nuclear Emergency Response Plan 4-2 4.2 Abbrevia ions-Acron ms Cont'd NRC OSC OOS OOS PAG(s)PAR(s)PASS PIO PWR RCP RCS RHR RG&.E RST SC Sl SPING TSC Nuclear Regulatory Commission Operational Support Center Out of Service (on site)Out of Sequence (off site)Protective Action Guide(s)Protective Action Recommendation(s)

Post Accident Sampling System Public Information Officer Pressurized Water Reactor Reactor Coolant Pump Reactor Coolant System Residual Heat Removal Rochester Gas and Electric Corporation Radiation Survey Team Site Contingency (or Survey Center)Safety Injection High Range Effluent Monitor Technical Support Center 4-3 SECT/ON 5.0 CONTROLLER AND EVALUA TOR INFORMA TION 5.0 CONTROLLER AND EVALUATOR INSTRUCTIONS Each Controller and Evaluator should be familiar with the following:

a.The basic objectives of the Exercise.'.The assumptions and precautions being taken.c.The Exercise scenario, including the initiating events and the expected course of actions to be taken.d.The various locations that will be involved and the specific items to be observed when at those locations.

e.The purpose and importance of the evaluation checklist and record sheets.5.1 Controller Instructions 5.1.1 Controllers will position themselves at their assigned locations prior to the activation of the facility for which they have responsibility (see Section 5.3).5.1.2 Communications will be tested to ensure satisfactory communications among Controllers prior to Exercise commencement.

All watches and clocks will be synchronized with the Lead Simulator Control Room Exercise Controller as part of the communications testing.5.1.35.1.4 All Controllers will comply with instructions from the Lead Controller.

Each Controller will have copies of the messages controlling the progress of the Exercise scenario.No message shall be delivered out of sequence or other than as written unless specifically authorized by the Lead Controller.

5.1.5 Messages controlling the progress of the scenario are noted with a number.Contingency messages are noted with a number followed by the letter"X" (e.g., 10X)~5.1.6 Each onsite Controller will have copies of time-related plant data sheets.Data sheets will be distributed only in the Control Room.Radiological and meteorological data will also be provided at locations where it is normally available.

5-1 5.1.7 Controllers will~no provide information to the Players regarding scenario development or resolution of problem areas encountered in the course of the simulated emergency.

The Exercise participants are expected to obtain information through their own organizations and exercise their own judgement in determining response actions and resolving problems.5.1g8 Some Players may insist that certain parts of the see n a ri o a re unrealistic, The Lead Controllers have the sole authority to clarify any questions regarding scenario content.5.1 g9 Each Controller will take detailed notes regarding the progress of the Exercise and the responses of the Exercise participants at their respective assigned locations.

Each Controller will carefully note the arrival and departure time for participants, the times at which major activities or milestones occur and problem areas encountered.

The Controllers will retain their notes for the purposes of reconstructing the Exercise chronology and preparing a written evaluation of the Exercise.5.2 Evaluation Instructions Each Controller/Evaluator will take detailed notes regarding the progress of the Exercise and the response of the Exercise participants at, their respective assigned locations.

Each Controller/Evaluator should carefully note the arrival and departure times of participants, the times when major activities or milestones occur and problem areas encountered.

The standards below should be used by the Controller/Evaluator to evaluate assigned areas pertaining to the emergency response.A dual purpose will be served by this rating system.First, the capability of each facility or response area will be evaluated and second, the system will provide a vehicle for guiding and directing improvement.

The rating scale is as follows: Good-Personnel and equipment generally performed better than expected.Any errors or problems were minor and easily correctable.

g I-d I g II f d expected.Any errors noted were not severe and could be corrected without undue labor or expense.I-P I d~p g llfP I dg I expectations and there were several significant deficiencies noted.The area's ability to carry out its functions was diminished.

NA-Not applicable to the situation or not observed.5-2 Controller/Evaluator comments should consider the demonstration of the following facility and team evaluation elements: 5.2.1~Facilit o Accurate and timely determination of emergency action and classification levels.o Timely activation and staffing for each classification level~o Familiarity of personnel with appropriate emergency instructions, duties and responsibilities.

o Timely notification of Rochester Gas and Electric Corporation, local, State and Federal personnel/agencies (information updates performed).

o Adequacy of internal information systems (i.e., message handling, displays, status boards and maps).o Properly controlled documentation and accurate, timely record-keeping.o Utilization of correct communications procedures and techniques.

o Capability of facility supervisors/directors to interface with personnel and coordinate facility activities.

o Consideration of personnel safety (exposure control).o Adequacy of interface between emergency response facilities.

o Adequacy of equipment and supplies.o Timely initiation of onsite protective/corrective actions.o Development of protective action recommendations.

o Radiological surveys and assessment of plant damage and hazardous conditions performed.

o Timely request of emergency support services.o Coordinated, accurate and orderly dissemination of information to the news media.o Proper assumption of command and control.5-3 5.2.2 Team o Timely notification and activation.

o Adequacy of staffing.o Familiarity with appropriate emergency procedures, duties and responsibilities.

o Availability and utilization of proper equipment.

o Performance of contamination/decontamination control.o Proper interface with emergency support personnel.

o Utilization of correct communications instructions and techniques.

o Availability of referenced documents to team members.o Utilization of proper radiological control practices (i.e., access control, protective clothing, shielding, stay time).o Performance of radiological surveys.o Timely and proper performance of damage assessment.

o Properly maintained survey records and maps.o Adequacy of briefing sessions prior to dispatch.o Direction and control by team leaders.o Timely requests for offsite assistance if required.o Coordination and interface between emergency response team members.o Proper interfaces with plant supervisory personnel.

Controllers/Observers will record their comments for the purpose of reconstructing the Exercise chronology and preparing a written evaluation of the Exercise.5.3 Personnel Assi nments Table 5.1 lists the personnel assignments for the on-site Controller organization.

5-4 Evaluation Packa es The following evaluation packages will be provided to the appropriate Controllers/Observers at the pre-Exercise briefing: Simulator Control Room Technical Support Center , Operational Support Center Survey Center Emergency Operations Facility Joint Emergency New's Center Health Physics Personnel Dose Assessment (TSC and EOF)Radiation Survey Teams (SC and EOF)Post-Accident Sampling System Fire Brigade Engineering Support Center 5-5 TABLE 5.1 O The following personnel have been designated to act as Controllers during the 1993 Exercise activities (SEE ATTACHED LIST).5-6 Attachment 2 EXERCISE CONTROLLER LIST~Position Personnel Assi ned Exercise Coordinator Control Room Simulator Control Room (Real}R.Beldue D.Hudnut (Lead)J.O'oole M.Ruby J.Zulawski Day Shift Supervisor in Operations Office Technical Su ort Center Lead Technical 8 Operations Security Dose Assessment Health Ph sics 8 Chemist General 0 erations Su ort Center Lead Fire Operations l8C Mechanical Electrical Post Accident Sam lin S stem T.Alexander B.Zollner T.White R.Wood R.Benne T.Hed es B.Thomson P.Polfleit J.Huff J.Knorr D.Biedenbach M.Cavanau h S.Carter R.Jenkins T.Joachimczyk E.McGrattan S.Meister G.Gibaud J.Liese R.Yates R.Marriott J.Raike Attachment 2 EXERCISE CONTROLLER LIST Position Personnel Assi ned Surve Center Lead Other Evacuation/Re-Ent Red Team Blue Team Green Team Yellow Team Oran e Team S.Poulton A.Jones D.Gansko J.Edler J.Mazzeo J.Za etis S.Stinson Erner enc 0 erations Facili Lead 8 0 erations Communications 8 Data Flow Dose Assessment Surve Teams General W.Backus B.Stanfield Outside Utilit Personnel G.Haverl R.Watts J.Neis Engineering Support Center Joint Emergency News Center C.Herschell F.Orienter TBD (Outside Utility Personnel)

National Weather Service G.English GINNA STATION 1993 EMERGENCY EXERCISE 5.5 PUBLIC INFORMATION, RUMOR CONTROL AND SPOUSE PHONE QUESTIONS FOR THE EVALUATED EXERCISE A significant aspect of emergency response is to provide the news media and general public with accurate and timely information about the incident.Public perception and reaction are influenced by the information relayed to them.To ensure that the Rochester Gas and Electric Corporation Emergency Organization is prepared to deal with outside inquiries during an incident at the Ginna Station, the exercise provides certain elements that test Public Information and Rumor Control activities.

During the course of the Exercise, the Joint Emergency News Center (JENC)will be activated and exercised.

The RGSE"Spouse Phone" will also be manned by the RG&E Medical Department.

Exercise Controllers have been selected to test the Rumor Control and News Media Contact Staffs, as well as the JENC.Controllers will act as concerned citizens, employees, employee relatives and as members of the media, posing questions to the staffs.When acting as members of the media, controllers shall make up a name and a media outlet (print or electronic) located outside of the Rochester area.Each time a rumor control message is delivered, a different fictitious name and address will be given.The phone number to be given will be the number from which the exercise controller is calling so as to allow the county Rumor Control person(s)to return calls with appropriate information, if necessary.

The exercise controllers should maintain the theme of each rumor control message and answer inquiries of the counties'umor Control persons appropriately.

The following pages denote questions that these controllers can use.The questions are grouped by time in relation to the events specified in the Exercise Scenario.The Controllers are allowed to use questions previously utilized.The lead JENC Controller shall verify that the exercise is adhering to schedule, otherwise time adjustments will be necessary.

Space is provided for controllers to make notes on the response.Controllers need not use the questions herein;free play is encouraged.

However, controllers must not get carried away with unusual or pointless questions.

When calling in questions,~alwa s grecede guestions with"THIS IS AN EXERCISE".

If you are playing a reporter at the JENC, develop free play questions based on the information given during the briefing.Additionally,ask questions about RGSE, the State or counties, Ginna Station, radiation, state/county/utility interface, protective actions, etc.Questions and relevant telephone numbers will be distributed at the special Pre-Exercise Controllers Briefing.5-9 Pg>>I I 3 2 II f Rggg;2 II gl C R C IG dll I 3 I I d ldlld Attachment 4 lists sample questions for testing the"Spouse Phone" in the RGRE Medical Department.

5-10 GINNA STATION 1993 EMERGENCY EXERCISE ATTACHMENT 1 SAMPLE PUBLIC INFORMATION QUESTIONS TIME 0900~IVly husband works in the Wayne County Sheriff's Office.He said he'heard that there's some sort of problem at the nuclear plant.~Is that true?~Will this be on the news?~How dangerous a situation is it?~This is from TV Station WGRC.We'e heard that there is an accident of some kind at the Ginna Nuclear Plant.Can you tell us what is happening?

0915~This is from the Wolf Newspapers.

I understand that you have an accident at the Ginna Nuclear Plant.What's going on up there?~How bad is the problem?~How did the trouble start in the plant?~Is it under control?~What's the state of the plant?~What kind of danger is involved?0930~This is WBBT AM Radio News.We'e heard that your plant has had a fire and explosion.

Can you confirm?~Have any workers been injured?~If so what is the extent of their injuries?~Is the safety of the public threatened?

~At what time will you have a press conference?

5-1 1

~Where will it be held?~We'd like to send someone to the plant, for interviews and photos..Where do they go?0945~This is from TV 11 News.We have a report you have some serious problems at Ginna Station.Would you tell our listeners the story?~Is the plant experiencing an uncontrolled release of radiation?

~How do you know?~Who is in charge of the emergency?

~What is his/her title?~Can we get a statement from him/her?1000~This is calling from the Associated Press.Can you give me a summary on the problem at your Ginna Nuclear Plant?~Are you under a state of emergency?

~Was the reactor damaged?~Did,you evacuate the site?~Why not?~Are you going to evacuate the public living by the plant?~Is this worse than the 1982 Ginna accident?~Where exactly is the plant located?5-12 1000 Yes, this is , I'm the Webster Town Supervisor.

My office is getting flooded with calls from local residents.

~What is happening at Ginna?~Is the plant still under your control?~Have the local authorities been notified?~Which ones?~Are we in Local State of Emergency?

~Is there any danger to the public?-1015 This is Channel 9 News.We have some questions on the Ginna problem.~What exactly is going on at Ginna?~Has the situation been resolved or are things getting worse?~Are you evacuating the site?~Are you going to tell the public to evacuate the area around the plant?~Has Governor Cuomo been notified?~Have the sirens been activated?

1015~This is~I'e heard you declared an",ALERT" earlier today.~What does that signify--how bad a problem do you have?~What time did it happen?~How did the problem start?~Has anyone been killed?~Are there any injuries?~The situation appears to be getting worse..~is this true?5-13 1030.This is.I'm at the news desk at the Times Union.I'm trying to help write tonight's story on the Ginna disaster.~I'm confused about what's going on at Ginna...is the problem a fire or a radiation leak to the atmosphere?

~Has the problem ended?~What is the significance of an"ALERT"?~How serious a problem is that?~Which government officials been called?~What is RGSE doing now?~What time did you declare the emergency?

~Didn't Ginna have a similar problem several years ago?~Ginna seems to be having more"technical malfunctions" than other US nuclear plants, how do you explain that?1045~This is~I'm calling from WRTQ Radio in Oswego.~How do I get"official" information..

~.who's in charge?~Who do I talk to for getting more information about radiation being released from the plant?~Are farmers supposed to be sheltering livestock?

1045~I'e got a small dairy farm in Williamson and I need to know what I should do.~Where would I get more stored feed for my cattle if my pasture gets contaminated?

~I think I heard the sirens...do I need to evacuate'5-14 1100~I heard that you declared a"General Emergency".

~When did this happen?~How much of the plant has been damaged?~Is there is a release of radiation?

~Has anyone been injured in or around the plant?~Is the plant safe or in big trouble?1115~What does a"General Emergency" mean?Doesn't that mean that no one can go near the plant for the next several weeks?~Is this accident similar to or worse than the one you had before?~Why didn't we have more warning about this problem before now?~When will this problem be over, or don't you know?~Will you evacuate people around the plant?~In simple terms, what are you doing to control this emergency situation?

~Will lots of radiation be released, or has it already started?~Is this as bad as the disaster at Chernobyl?

1130~My father is in the Hill-Haven Nursing Home in Webster.~What will happen to him?~How long will this emergency last?~How do we keep informed?~Is this as bad as Chernobyl?

~I just heard on my scanner that someone found evidence of terrorist sabotage on a plant safety system, is the plant going to blow up?5-15 1200~Do you expect that any radiation will be released?~Is the radiation like bomb fallout?~How dangerous is it?~Who is in charge of the emergency?

~When will the next press briefing be held?~Where is the radiation heading?~What protective actions have been recommended?

~Whom should I call for further information concerning the Webster area (or Ontario)?~If we'e evacuated, will my house ever be safe to return to?~Where are people supposed to go if they evacuate?1215~What is the problem at Ginna?~I'm confused--How did the problem start?~Is this plant similar to Chernobyl or TMI?~Can it blow up?~How much radiation is being released off site?~What protective actions are in effect for Wayne (Monroe)County?~If people around the plant have to evacuate their homes, when will they be allowed return?5-16 1215~Are farm animals on pasture grazing safe?~What about the apple orchards around the plant, how will they be impacted?~Are you releasing radiation?

~If so what are the levels?~Are farmers supposed to take any action to protect their livestock?

~Who is the best source of truthful information on this emergency?

1230~This is from WRKU Radio in Albany.~How serious is the Ginna situation now?~Is the problem under control yet?~How many people live around the plant?~What are you going to do to fix the situation?

~When is the next press briefing?~Can we interview anyone at the plant?~Where is your News Center located?~How do I get there?~Where is the wind going?~Who's in charge of the emergency?

~We heard that there was sabotage resulting in both a fire and serious release of radiation, what can you tell us about how this came about?1245~I live in Webster on Lake Road.I'm worried about leaving my cats behind if I evacuate my home.~Can I take them along with me to a county evacuation shelter?~What else should I take along if I go?~How many days of pet food should I bring?5-17 1300~This is TV 25 in Kingston, Ontario.Is it true that your G-e-e-na reactor is suffering a mishap and can you give us an update a-boot the severity of the problem?~Briefly, what happened this morning to begin this problem?~Do you Americans consider this to be worse than Three Mile Island?~Do the authorities believe there's chance that the winds may carry radioactive material across Lake Ontario to Canada?~Can you tell our viewers how your reactor is different from ours?~For example, will there be heavy water contamination in the Lake?~We also heard that there was a toxic leak at the plant, what is your comment?1315~I hear there's an emergency at the nuclear power plant.~What happened and how bad is it?~How do we get additional information?

I live in Ontario, NY.1330~I'm of Radio Station WTTY.You'e on our"NEWS LINE" and could you tell our listeners what's happening at the Ginna Nuclear plant?~Is the Monroe County Executive going to declare a state of emergency?

~What does the County Executive intend to recommend to the public?~Are there any recommendations for people living within a few miles of Ginna?~Should Monroe or Wayne County residents take any kind of proactive measures because of the problem we'e hearing about on the news?1345~Is there a security problem at Ginna?~Was there sabotage?~Is the plant under control?5-18 ATTACHMENT 2 SAMPLE RUMOR CONTROL MESSAGES FOR WAYNE COUNTY TIME 0910~Could you tell me about the problem at Ginna?I'm a Sodus resident.~Is there a chemical or a radiation problem at Ginna?~Is the problem at Ginna or Nine Mile Unit II?~Is the plant shut down?0945~I hear there's an emergency at the nuclear power plant.~What happened and how bad is it?~I'm of Radio Station WOOR.We'd like to tape a short interview...can you provide the answers?~Could you tell our listeners what's going on at the Ginna Nuclear plant?~Is the County Executive going to declare a state of emergency?

~What does the County Executive intend to recommend to the public?~Are there any recommendations for people living within a few miles of Ginna?~Should County residents take any kind of proactive measures because of the problem we'e hearing about on the newswires?

1000~Has any dangerous radiation leaked yet?~How can you be sure?Are you checking it?~How can I find out when there is a release?~Who is in charge of the emergency?

~Is the plant shut down at this time?5-19 1015~My son works at Hardee's in Ontario...

he's there now.~How will he know about the Ginna problem?~Is he safe where he is?~Does RGSE have an emergency plan?~If so, how does the County figure in it?~We'e lost our emergency information handbook and need one right away.Will one of the emergency people you have deliver one to us?1030~Is there a security problem at Ginna?~Was there sabotage?~Is the plant under control?~What damage was done?1045~I heard there was an explosion and fire at Ginna.What is really happening?

~Are you in a general state of emergency?

1110~I live on Lake Road in Williamson.

I'm just east of the Town Line with the Town of Ontario.I need some information.

~If there's an evacuation, I'm going to need help with my two infant twins.Can you help me?We only have one car.1125~How many nuclear plants are in the area?~Which one is having the problem now?~Where's our power going to come from if the plant is shut down for a while?~Have you guys called for extra help with your problem?~Who's running the emergency?

5-20 1145~What station on the radio should we be listening to?~I need to talk to the County Executive.

What's his number?I need to know what to do.~Is RGRE telling us'the truth?We all remember the Ice Storm and how they lied then to save their buttsl 1200~I live in Newark, but I could live 50 miles away and wouldn't feel safe...are you going to let us know'if we need to get out?~How?~I heard you'e bring all the irradiated people from around the plant to Newark High School...is that true?We'l all be radioactive!

1215~I live near the plant and heard there is an"GENERAL ALERT", and then I heard it called something else.~.What's going on?~Are you checking the radiation levels outside?~Did the World Trade Center terrorists do this?1225 What's this I hear about a fire at Ginna?~Was that because of a big explosion or something?

~How many people got hurt and who's running the plant now?~Somebody told me the Ginna workers"bail out" from the plant when there's a problem.Is that true?1230~Is Cuomo or Clinton sending help?~What's happening right now at the Ginna plant?~Is the plant burning out of control?1245~My neighbors are saying that something blew up at the Ginna plant.Is this true?5-21 1245~Has a State of Emergency been declared?~What should the public do to protect itself?~My wife and I are concerned because we haven't heard the sirens go off...we live over in Macedon.~Shouldn't we hear sirens now or sometime real soon?~We don't think you county disaster people are being told everything by RG&E.I can't even get a straight answer on my monthly electric bill~What's really going on?1~I don't trust the power plant people;they'd lie to save their own skins.~Do you have anybody checking on them to make sure they'e trying to control it?~Will the County Board of Supervisors look into this accident and stop Ginna from starting up again?1300~Yeah...l got one question....

Who's going to pay for all the clean-up from this accident?If you think the ratepayers are going to take it you-know where again.....you'e dead wrong!What's going to happen?1315~Should I close my restaurant due to the accident at Ginna Station?I'm over in Ontario Village.~What are we supposed to do?~Who do I call to find out if we'e going to have to leave?~Who will guard my place if we evacuate?1320~I'm calling from California, I have family in Rochester.

~..what's going on at your plant?1330~What's happening at Ginna?5-22 1340~I heard that at Ginna a disgruntled employee sabotaged the plant and that's what caused this accident!Have they caught the person yet?~Has there been a radiation release?~What's happening to all the school kids in the Williamson School District?I heard the siren but nobody said which way to go.My neighbor says the siren means to leave your house immediately.

~Is he right?1350~What do I do?I live on Paddy Road near route 350 in Ontario.1400~I hear that the Maplewood Nursing Home will keep its patients where they are.My wife works there, but I can't reach her because the phones are busy.Will they be safe there?1415~I'm leaving now.Where do I go for temporary housing?I live on State Road near Route 250.1420~I'm calling from Penfield.....has there been a release of radiation from Ginna?~I'm calling from Pennsylvania....l live 5 miles from Ginna.....can we return home tomorrow?1430~What's happening at Ginna?1435~I'm evacuating now.Which way is safe to travel?We live next to the intersection of Kenyon and Stony Lonesome Roads in Ontario.We need temporary housing.I'e got 4 kids with me.1445~I am supposed to leave but don'-have a place to stay.Which school can I stay at?I live on Lake Road near County Line Road in Wayne County.~How do I get there?~Who's going to pay my expenses?~Who do I call to get a check for my expenses?5-23

SAMPLE RUMOR CONTROL MESSAGES FOR MONROE COUNTY TIME 0940~I hear there's an emergency at the nuclear power plant.~How serious is the problem?~Are schools going to be dismissed early?~Can I pick up my two children at the RL Thomas School in Webster?~I'm of Radio Station WTZ..Can=you tell our listeners what'happening at the Ginna Nuclear plant?You'e live on our"MORNING SHOW".~Have officials in Monroe County declared a state of emergency?

~What is Monroe County doing to assist in this emergency?

~Will you have a press conference?

~Has there been a problem at the Ginna Plant?0950~I live down on Plank Road near Jackson Road....Have any chemicals or radiation been released, can they get into the drinking water?~Is the problem under control?~Should we leave our home because of the mishap at the plant?We'e very concerned about this.~What's the problem at your plant?~When will the emergency be over?~What caused the problem at Ginna?1000~My daughter and a friend are out shopping in Irondequoit.

~How are they going to be warned about the plant problem?~We live in West Webster on Backus Road...are we safe?~Are you going to block off the roads...my daughter needs to be able to drive back homel 5-24 1010~What's happening at the nuclear plant?~Is the problem I'e been hearing about at Russell Station or Ginna?~Who caused the accident?~My mother works in the library in Webster.~How do they know there's problem?~Are they safe?~I can't get through to the library..the line is busy.~What do you recommend I do?1015~We live in Penfield Village...are we far enough away?~Is the plant under control now?~Will we lose our power because of the accident?~ls there a brochure we'e supposed to have to tell us what to do?~Who.is in charge of your emergency?

~Is it under control?1020~I'm calling from Consolidated Edison....could you give me some information about the event this morning at Ginna?1025~We'e lost our emergency information handbook and need one right away.Which Zone do we live in?~We live on Shoecraft Road near State Road-are we going to have to evacuate?We'e very close to Ginna!~Where are we supposed to go if we'e told to leave?1030~What happened at Ginna this morning?~What do I do if the sirens blow?-~Are all RGSE's plants under attack?~What happened this morning?~Where can I buy a radiation instrument to check the outside?5-25 1100~I have some milk goats out in our field.~.out on County Line Road by State Road.What do I do with the goats?Bring'em inside?~We live in a one-story wood-frame house.The calendar we received from RGRE talks about"sheltering".

Isn't that supposed to apply only to brick buildings with thick walls?We don't even have a basement!~Is the Ginna plant running now?~Will you be blowing the sirens?~If so, what do we do?~I need to know what's going on and what to do.~My neighbors are frightened

.~..we live on Holt Road near Woodhull~Can we go outside?Are we in danger?~Are you people checking the radiation?

~What are we supposed to do when sirens go off?1115~My neighbor's a cop....we says you'e got a security problem.How bad is it?~How many security people are at Ginna?~Have you called for help?~Did the sabotage cause the chemical release?~Did terrorists blow up Ginna?~Were employees or outsiders involved in the destruction of safety equipment?

~Are the plants in Oswego having problems too, or is it just Ginna?1130~We hear that emergency shelters are open now....what do we bring if we need to stay for awhile and how much will it cost?~How do we get checked for radiation?

My whole family is feeling nauseated and weak.5-26

~Is Wayne County going to be declared a disaster area?~Is this accident as bad as Chernobyl or TMI?~Where do the school kids go?My daughter goes to State Road Elementary School.~Should I close my business due to the accident?Who will pay for the lost income'?(The business is on Empire Blvd.near Bay Road).1200~Are schools closing in Fairport...my kids are at the High School?~What are we supposed to do?-we live on Route 31~~What should I do for-my chickens'to protect them from radiation?

~I heard Ginna is melting down.Is it true that State people are coming to take over?~We heard the Governor is coming to take charge of Ginna.~How wide an area will be evacuated-20, 30 miles?~How far is Ginna from Fairport?~Should Fairport residents leave their homes?~Is there a plan for nuclear emergencies?

~Is it finished?~Who wrote the plan and who approved it?~Is RGSE responsible for the accident that happened?5-27 1230~I heard the siren but now what do we do?We live just down the road from Ginna...and I don't see anyone leaving the plant....are they all dead?~Would you send out the sheriff's department to check?~What's happening at the Ginna plant?~I'm leaving now.Can I pick my son?He's got a job at Taco Bell in Webster.~I live in East Rochester...we just had a problem a few weeks ago with the drinking water, heavy metals in the water or something.

~Are we going to have to boil our drinking water again because of the plant's radiation?

~Can my pets be outside, can they drink water that's outside?1300~I think I am supposed to leave but don't have a place to stay.I live in Monroe E-R-P-A Number 4.~Which county shelter can I stay at?~How do I get there?~Who's going to pay my expenses?~I heard the accident at the Ginna Station is just a false rumor, What'going on?~I live exactly 5 miles southwest of the plant....there's never been a problem before and I'm not going to leave now.I'm sure the media's just blowing this out of proportion.

~Why haven't you made the announcement on radio?~Who's going to guard all the neighbor's houses after they run away to the shelters?~Is the Ginna emergency over yet?~Is the Ginna reactor shut down?~Is the plant burning?5-28 1330~What is the Ginna problem that occurred this morning?~I'e heard people are being asked to leave.Is that true?~Were we supposed to hear the sirens?~What radio station or T.V.channel should we have on?~Who is running the reactor at Ginna?I hear the safety equipment was tampered with this morning by someone in the plant.~Where is the emergency information in the phone book.I can't find it.~What should we take if we leave our home?~How do we get transportation if we don't have a car and need to evacuate?We live on Holt Road near Lake Road.~Is the accident over with at Ginna?~Who's going to pay for the mess you created?1345~Is there contamination on the ground now from Ginna?~My homeowners insurance states I'm not covered for nuclear accidentsl What do I do now?~Who will check my home and property to make sure there's no radiation?

We live on Jackson Road.~I'm calling from Buffalo...l got my family out of our house in Webster this morning.When will it be safe to go home again?~Can we be checked for nuclear radiation somewhere, on our way home?~Who can we get to check our farm pond to see if there's any contamination?

~I'e got a well on my property (about 6 miles west of Ginna on Lake Road).Can we still drink from our well?~Who can I contact if I have more-questions, and I'm sure I will!~I'm calling from England.....what kind of plant is Ginna?~Has there been a release to the atmosphere?

~Was there iodine in the release?5-29 1400~How long will people who evacuate from Monroe ERPA 1 have to stay away from home?~Can homeowners go back and check their homes in the meantime?~What if there's a fire in one of our houses?Are you just going to let it burn?~Are residents supposed to take potassium iodide?~If we can't get the potassium, can we take salt tablets?~What is happening at Ginna now?~We caught some trout just east of the plant this morning, around 8 or 9 am.~What should we do with the fish?~Is my boat contaminated now and am I?5-30 ATTACHMENT 3 SAMPLE PRESS CORPS QUESTIONS~What happened to the turbine at Ginna?~Was there a fire...is it out....what's the damage?~Is it true a leak occurred?~What kind of leak was it-chemical or radiation?

~Isn't it true the plant is always releasing to the atmosphere?

~Is the reactor stable and under control?~Is this plant similar to Indian Point?~Were any workers injured or contamiriated?

~.How much radiation was released around the plant?~What protective actions are in effect for Wayne (Monroe)County?~How many people live in Wayne (Monroe)County?~What are you going to do to manage the situation over the next several hours?~How long will the emergency be in effect?~When is the next press briefing?~How many media representatives are at the News Center?~What agencies are at the News Center?~Where is the wind heading now?~What is the weather forecast?What effect will that have on your recommendations?

~Who's in charge of the emergency?

~Please explain the relationship of the State, the two Counties and.RGKE in terms of how decisions are made during this emergency.

5-31

~Who makes the decision the activate the sirens, who decides to evacuate or shelter, and how is that decision reached?~How can we be sure that the best interests of the public are paramount in the decision-makers mind?~How does the County Executive and County Chairman get the technical information they need to make informed decisions?

~For any news organization wishing to take footage of Ginna, who do we see at the plant gate?~How will home-bound, mobility impaired or nursing home patients be protected?

~What exactly does"sheltering" involve..does.

this apply to any type of home?~When can people who have sheltered, stop sheltering?

~What effect will the release of radioactivity have on Lake Ontario fish?~What impact will the radiation released have on unborn babies?~How many cancer deaths are there likely to be in Wayne and Monroe counties as a result of this accident?~When do you expect to enter"Recovery"?What does that mean exactly?~Will there be any further radioactive releases?~Will the sirens be sounded any further?~How do tourists know how to protect themselves?

How is the plant getting power now to run its safety systems?~Will the shareholders or ratepayers absorb the cost of this mishap?~Will Ginna need to be decommissioned?

~Is this the same type of problem that Ginna experienced in 1982?~Who will pay for all the damage to personal property from this accident?~After cleaning up the radioactive waste from this accident, where does it all get sent?Has RGSE significantly added to the State's low-level waste crisis?5-32

~Why doesn't RGSE distribute potassium iodide to the publica...do RGSE people get it?~How close have you come to a meltdown'How do you know the extent of damage to the Ginna reactors 5-33 ATTACHMENT

'4 SAMPLE"SPOUSE PHONE" QUESTIONS 0930~This is Rick Watts's wife calling....do you have any information concerning a problem at Ginna?I just heard something on the radio about a fire.1005~Do you have any news on Ginna?My husband works in the warehouse....l don't want to bother him, but am just checking to see that everything's okay.1015~My husband works at Ginna, and is there now.He works in the Training Center (Jim Huff).~Has there been a fire?~Is it out yet?~Can I drive to the plant and drop off some sandwiches for Jim if he'got to stay overnight?

1045~My sister called me this morning and said there was a problem at the plant, and said she'd keep me posted.I haven't heard anything from her for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.~She said she might be sent to sent to work in the EOF.Is everyone there now?~Will the workers have to stay at the plant?~I need to get through to the EOF to ask her what arrangements I should make concerning her kids at day care...since I'm.at work.Her name is Barb Butler.1100~My son-in-law works at Ginna as a Trainer (Jim Knorr).~Where are the plant workers now...have they left the plant?~Is the plant under control now?5-34

~How long will the emergency last?1115~My father, Wesley Backus works in Operations at Ginna.~What's happening at the plant?~How bad is it?~Are the workers in danger?My father works around the back-up safety equipment.

~'re Ginna employees allowed to call home?~If he can, have Wesley Backus call home so I can stop worrying.1130~My husband works in the Ginna Training Department.

I can't reach him at Ginna.His name is Sam Poulton.~My neighbor told me there was a problem with an explosion at the plant, and that there's a fire too.Is that true?~Has everyone evacuated the plant?~Were any of the employees hurt?~How can I reach my husband?He's on blood pressure medication.

I need to know he's all right.1145~This is Gail Beldue.My husband, Dick is either at Ginna Station or East Avenue today.I need to get a message to him.We live 3 miles from the plant and may need to evacuate.~Do you know for sure if residents will have to evacuate?~If we evacuate, tell Dick that I will go to my parents house.~Tell him I hope he's okay.1200~My wife is a secretary at Ginna Station, and I'e heard they'e had an emergency.

How serious is it?~How long is this accident expected to go on?~Do you know if workers have evacuated the plant?5-35

~Are the workers all okay?~Can I pick my wife up?If so, where do I meet her?1230~My dad works at the plant..could you tell us what's happening?

5-36 SECT/ON 6.0 SCHEDUCE OF EVENTS 1993 GINNA PLUME EXPOSURE PATHWAY EXERCISE SCHEDULE OF EVENTS DA TE TIME PERSONNEL GROUPS ACTIVITY 1 1/15 11-12 ALL (JENCJ 9-1030 AM ALL IEOFJ PLA YER BRIEFING PLA YER BRIEFING 3-4 PM ALL PLANT PLA VERS IBROOKWOODJ PLA YER BRIEFING 1 1/16 8-11 AM AS ASSIGNED/BROOK WOODJ 1-5 PM NRC TEAM IBROOKWOODJ CON TROLLER BRIEFING BADGING BRIEFING 1 1/17 ALL 1993 EXERCISE 1 1/18 8-10 AM CONTROLLERS IBROOKWOODJ PRE-CRITIQUE MEETING 1 1/18 1 1/18 10-11 11-12 OPEN IBROOKWOODJ OPEN IBROOK WOOD J RGE CORPORA TE CRITIQUE NRC CRITIQUE.1 1/19 8-12 AM FEMA/N YS/CO/RGE PRE-CRITIQUE MEETING (OFFSITE EXERCISE ACTIVITIESJ

  • 1 1/19 OPEN I89 EAST A VE BSMTJ FEMA CRITIQUE 6-1 SECT/ON 7.0 EXERCISE SCENARIO NARRATIVE

SUMMARY

The scenario begins with the R.E.Ginna Nuclear Power Plant operating at approximately 98%rated thermal power.The Plant has been operating at this power level continuously for approximately 180 days.Initial conditions of note are:~Offsite power 34.5 KV circuit 751 is out for pole replacement and cable repair due to a tractor trailer truck hitting a pole.Subsequently normal power was restored to buses 14 and 18 from offsite power 34.5 KV circuit 767.~The"B" Safety Injection Pump is held and disassembled because of high vibration on the pump's outboard bearing.The"B" Safety Injection Pump electrical breaker"b" contact has been jumpered.~"B" Charging Pump is held for plunger replacement and the maintenance is approximately 50%completed.

~Thermographic checks have detected a hot spot on Bus 14 Station Service Transformer.

~A0730 a loud bang is heard outside the Control Room door to the turbine building, and annunciator I-27 (ROTOR ECCENTRICITY OR VIBRATION) alarms almost immediately.

An Auxiliary Operator sent out to check the turbine-generator reports that a turbine blade has penetrated the¹2 LP turbine casing at its southeast corner and the turbine blade is lying by the Control Room door.An Alert is declared.At 0805 a fire is detected in the Charging Pump Room.The fire brigade is activated.

The"C" charging pump trips.Operators control pressurizer level and seal injection flow with the remaining charging pump.The fire is extinguished.

There should be no change of emergency classification.

~A0810, a LOCA inside Containment occurs (with initial assumed leakage=10,000 gpmi.All safeguards equipment operates normally except the"B" safety injection pump, which is out for corrective maintenance.

A Si e Are Emer enc is declar At 1005 with the tripping of the 480-volt safeguards bus, ail safety injection to the core is terminated.

A General Emer enc is declared.This will warrant licensee-recommended protective actions.At 1050 a release above Technical Specifications begins.~At 250 the release is terminated and offsite radiological levels begin to decrease rapidly.Recovery and re-entry discussions begin at a roxima el 1315 hrs.The Exercise is terminated at approximately 1400-1500 hrs.NOTE: 'An'::::ac uLaf,",:;shift:,:::::,ch~~ge$

'of~,:.ksy:;;:,:EffO!::pasftj~anp~~wl!!porn'i vb'ei'ca'goIp'liteerd':::ib jr':.:Ajt'.:20~0 vhrs 7-1 GINNA STATION 1993 EMERGENCY PREPAREDNESS EXERCISE INITIAL CONDITIONS The R.E.Ginna Nuclear Power Plant is operating at approximately 98%rated thermal power.The Plant has been operating at this power level continuously for approximately 180 days.Equilibrium primary Coolant Isotopic activity as of 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> (11/17/93) is provided in Table 9.2 of scenario section 9.3.Total activity is 2.56 Microcuries/Gram.

Chemistry Log Sheet available from controller.

The Reactor Coolant'System (RCS)total leakage is 0.250 GPM as of 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> this morning.Identified RCS leakage is 0.092 GPM.General Weather conditions are partly cloudy with no current precipitation

.For purposes of the exercise, additional meteorological information in the simulator control room should be obtained from the plant process computer system (PPCS)~Offsite power 34.5 KV circuit 751 is out for pole replacement and cable repair due to a tractor trailer truck hitting a pole on Slocum Road North at 0600 this morning.The"A" emergency diesel generator started and energized safeguards buses 14 and 18.Subsequently, normal power was restored to buses 14 and 18 from offsite power 34.5 KV circuit 767 and the"A" emergency diesel generator was stopped and aligned for auto standby.The"B" Safety Injection Pump is held because of high vibration on the pumps outboard bearing.The high vibration was detected yesterday (11/16/93) during the performance of PT-2.1Q (Safety Injection System Quarterly Test).The pump's outboard bearing is disassembled, cleaned and new bearings have been checked out of QA Storage.The pump is now awaiting re-assembly and an A-52.4 has been submitted for the"B" Safety Injection Pump.The"B" Safety Injection Pump electrical breaker"b" contact has been jumpered per EM-777 (MOV-871 and 871B Control Circuit Jumpers)."B" Charging Pump is held for plunger replacement.

The pump was held yesterday morning (11/16/93) at 0700 and the maintenance is approximately 50%completed.

A preventive maintenance analyst, while doing thermography on Bus 14 during the early morning hours, reports to the shift supervisor that he has found a hot spot on Bus 14 Station Service Transformer.

He also informs the shift supervisor that he will talk to maintenance later this morning about planning a Bus 14 outage to check out the transformer.

7-2 GINNA STATION 1993 EMERGENCY PREPAREDNESS EXERCISE ONSITE SEQUENCE OF EVENTS APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹0700 0715 0730-00/1 5 00/00+00/1 5 Initial Conditions established

(¹1 C).Announcement to Commence Annual Emergency Exercise (¹1).A loud bang is heard outside the Control Room door to the turbine building and annunciator I-27 (ROTOR ECCENTRICITY OR VIBRATION).

Alarms almost immediately

(¹4).ANTICIPATED RESULTS Con rol Room Operators should perform the actions of AR-I-27 and transition to AP-TURB.3 (Turbine Vibration) and perform the action of tripping the turbine as vibration on¹6 bearing is higher than the trip criteria of 14 mils.Operators transition to E-0 (Reactor Trip or Safety Injection) and perform the applicable actions and then transition to ES-0.1 (Reactor Trip Response)and perform its applicable actions.Operators should send an auxiliary operator out to check the main turbine-generator (¹5).7-3 APPROPRIATE TIME SCENARIO TIME EVENT DESCRIPTION AND MESSAGE¹0732+00/17 Annunciator F-21 (COND Hl PRESS 20" Hg OR LOSS OF BOTH CIRC WTR PMPS)alarms and condenser vacuum is 19" Hg and decreasing

(¹6).ANTICIPATED RESULTS 0740 ALERT+00/25~C Operators performing the applicable actions of ES-0.1~The Auxiliary Operator sent out to check the turbine-generator reports that a turbine blade has penetrated the¹2 LP turbine casing at its southeast corner and the turbine blade is lying by the Control Room door (¹7)~ANTICIPATED RESULTS Control Room Operators performing the applicable actions of ES-0.1 (Reactor Trip Response).

Appropriate notifications should be made per EPIP 1-5.If an ALERT is not declared in approximately 15 minutes, a contingency message should be given out to declare it (¹9x)~7-4 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹0805+00/50 Fire zone Z-01 (AUX BLDG 235-8 BSMT E.CHP ROOM)Alarms (¹11).ANTICIPATED RESULTS Control Room Operators should sound the fire alarm and activate the fire brigade per SC-3.1.1 (¹12).Operators should inform the TSC of the Charging Pump Room fire alarm.0807 Operators should be transitioning to 0-2.2.+00/52 The"C" charging pump trips out.Annunciator G-25 (MOTOR OFF CTR SECT PMPS EXCEPT MAIN AND AUX FEED PMPS)alarms (¹13).ANTICIPATED RESULTS Control Room-0815 Operators should control pressurizer level and seal injection flow with the remaining charging pump.-+01/00 Fire Brigade captain, after arriving at the Charging Pump Room, reports that the fire appears to be on the"C" charging pump motor with much smoke present and they are fighting the fire (¹14).ANTICIPATED RESULTS Control Room NOTE: Offsite fire fighting assistance is not participating.

if assistance is requested, controllers will intercede to prevent off-site fire department response.Operators should be performing the applicable actions of 0-2.2.Operators should inform TSC of the fire on the"C" charging pump.7-5 APPROPRIATE TIME SCENARIO TIME EVENT DESCRIPTION AND MESSAGE¹TECHNICAL SUPPORT CENTER TSC should be assuming command and control at approximately this time.TSC, when operational, should check into the loss of 34.5KV circuit 751 problem.TSC, when operational, should evaluate the fire in the Charging Pump Room.EMERGENCY OPERATIONS FACILITY 0825+01/10 EOF may be activating at this time due to plant conditions.

Fire Brigade captain reports to the Control Room that the fire in the Charging Pump Room is extinguished and that it was on the"C" charging pump motor.He also reports that the"A" charging pump is running normal with no apparent damage from the fire (¹15).ANTICIPATED RESULTS Control Room Operators should inform the,TSC of the fire being extinguished on the"C" charging pump and the condition of the"A" charging pump.TECHNICAL SUPPORT CENTER TSC should re-evaluate the emergency classification per EPIP 1-0.There should be no change of emergency classification.

7-6 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹0910+01/55 The following events occur simultaneously

(¹21): SITE AREA EMERGENCY'ressurizer level and pressure decreases uncontrollably.

'Safety Injection Actuation occurs automatically from pressurizer Lo pressure.'ontainment pressure is increasing.

~'afety Injection Flow is greater than 100 GPM.'ll safeguards equipment operates normally except the"B" safety injection pump.It is out for corrective maintenance.

ANTICIPATED RESULTS Control Room Operators perform the appropriate actions of E-0 (Reactor Trip or Safety Injection).

Operators should inform TSC of the loss of coolant accident.Operators should transition to E-1 (Loss of Reactor or Secondary Coolant)and then to CR-FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) and then back to E-1 and start performing applicable actions.TECHNICAL SUPPORT CENTER TSCjjho'ii!d:;:."dec!-'ri:'a',":"'TE~A'REA'::~EME

.GENC~Y",ii Evalii'atio'nj Sll,":.:t'ota!':::::f!

oN::.';>."':.'l:00.':,::!6P M':,6i'ina!

F4='824'/Fl-.',,826'Y wv YANCE: r5:cwk~xviicA+%cN446 u%xR:mÃwÃv4cwv'.GN 9?~AaFRSN>xA&vm+"v~%rwM Appropriate notifications should be made per EPIP 1-5.7-7

'PPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹TSC should be expediting the maintenance on the"B" safety injection pump.If a Site Area Emergency is not declared in approximately 15 minutes, a contingency message should be given out to declare it (¹26x).EOF should be activating at this time, if not done earlier.0915+02/00 The"B" RHR pump trips out, Annunciator J-9 is received in Control Room (¹23).ANTICIPATED RESULTS Control Room Operators should try to restart the"8" RHR pump 5 times per AR-J-9.It will not restart.Operators should notify an auxiliary operator to check the"B" RHR pump and motor.An auxiliary operator may already be in the Auxiliary Building per step 18C of E-1.Operators should notify the TSC of the tripping and failure to restart of the"B" RHR pump.Operators performing the applicable actions of E-1.Technical Su ort Center TSC should send a team into Auxiliary Building to check out the"8" RHR pump trip problem if the auxiliary operator-not already in there.7-8 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹TSC should be evaluating the loss of safeguards equipment and be expediting repairs as quickly as possible.TSC should be informing the EOF of plant status, actions being taken and any required needs.-EMERGENCY OPERATIONS FACILITY EOF should be evaluating plant conditions and taking actions as required.0920+02/05 The"A" emergency diesel generator trips out.Annunciator (J-24)is received in the Control Room (¹24).ANTICIPATED RESULTS Con rol Room Operators should send an auxiliary operator out to the"A" Emergency Diesel Generator Room to check the local alarm panel and the emergency diesel generator.

Operators should inform the TSC of the"A" emergency diesel generator tripping out.0935+02/20 The auxiliary operator sent out to the"A" Emergency Diesel Generator Room to check the local alarm panel and the emergency diesel generator, reports to the Control Room/TSC that the local alarm panel indicates a"lube oil low pressure"alarm and there is a large amount of oil on the floor by the large lube oil filter on-the east side of engine, and the engine oil level is extremely low (¹25).ANTICIPATED RESULTS~C Operators should inform TSC of the"A" emergency diesel generator problem.7-9 APPROPRIATE SCENARIO'IME TIIVIE'VENT DESCRIPTION AND MESSAGE¹TECHNICAL SUPPORT CENTER TSC should send a repair team out to evaluate and repair the"A" emergency diesel generator problem.0950+02/35 Radiation levels start to increase slowly in the Auxiliary Building (¹30).ANTICIPATED RESULTS'ontrol Room Operators performing the applicable actions of the E-1 (Loss of Reactor or Secondary Coolant).Operators should inform the TSC of increasing radiation levels in the Auxiliary Building.TECHNICAL SUPPORT CENTER TSC should be evaluating plant conditions and taking actions where required.TSC should be informing the EOF of plant status, actions being taken and any required needs, TSC should be evaluating the increase of radiation in the Auxiliary Building as to its source and its effect on the personnel in the Auxiliary Building.EMERGENCY OPERATIONS FACILITY EOF should be evaluating plant conditions and taking action as required.EOF Dose Assessment should be evaluating the increasing radiation levels in the Auxiliary Building.REPAIR TEAMS Performing actions as required to return equipment to service as soon as possible.7-10 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹1000+02/45 The auxiliary operator and/or TSC team in the Auxiliary Building to check the Auxiliary Building Sub Basement per step 18C of E-1 and the"B" RHR pump trip problem reports to the TSC/Control Room that the"B" RHR pump motor has a burned insulation smell and it is hot to the touch.He/they also report(s)that while in the Auxiliary Building Sub Basement, he/they observed a small amount of water dripping from the large pipe between Containment and MOV--850A.

He/they also report(s)that after closer inspection of the dripping water, he/they observed what looked like a three (3)inch long crack at the bottom of the pipe.He/they also inform the TSC/Control Room that they are evacuating the Auxiliary Building as radiation levels have started to increase.(¹22,31).ANTICIPATED RESULTS C R If the Control Room is informed, the operators should inform the TSC of observed dripping water and crack on the pipe between Containment and MOV-850A.Operators performing the applicable actions of E-1 (Loss of Reactor or Secondary Coolant)~When TSC requests Control Room to close MOV-851A, Control Room should request TSC to send a team into the Auxiliary Building to turn the breaker on for MOV-851A as it is turned off during operations.

NOTE: If breaker is urned on rior to Bus 14 tri in he breaker will tri as the valve comes off i s back seat.TECHNI AL SUPPORT CENTER TSC should be evaluating the dripping and cracked pipe and request Control Room to close MOV-851A to isolate the leak from Containment.

TSC should be evaluating the increasing radiation levels in the Auxiliary Building and possibly evacuate the Auxiliary Building.7-1 1 APPROPRIATE TIME SCENARIO TIME EVENT DESCRIPTION AND MESSA E¹.TSC should be evaluating plant conditions and taking actions where required.TSC should be informing the EOF of plant status, actions being taken and any required needs.EMERGENCY OPERATIONS FACILITY EOF should be evaluating the increasing radiation levels in the Auxiliary Building and taking action as required.1005+02/50 Repair Team sent out to check the"A" emergency diesel generator problem reports that a gasket has blown out on the lube oil line between the engine lube oil pump and the large lube oil filter.They estimate it will take approximately two and one half hours to repair and refill the engine with oil.ANTICIPATED RESULTS TECHNICAL SUPPORT CENTER TSC should inform the"A" emergency diesel generator repair team to expedite repairs.TSC should inform the EOF of The"A" emergency diesel generator problem and the estimated repair time.EMERGENCY OPERATIONS FACILITY EOF should be assuming command and control at approximately this time.Preparations for an actual shift change of key ERO personnel will begin shortly after EOF assumes command and control.1005 GENERAL EMERGENCY+02/50 480 Volt.safeguards Bus 14, trips out.Annunciators (J-29, J-7, J-9)alarm.All safety injection to the core is terminated

(¹33).7-1 2 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND IVIESSAGE¹ANTICIPATED RESULTS Con rol R om Operators should inform the TSC immediately of the loss of Bus 14 and safety injection to the core.Operators should try to start the"C" S.l.Pump on Bus 16.If they do, the breaker will not close.They may also transfer the"B" instrument bus to maintenance supply.TECHNICAL SUPPORT CENTER TSC should inform the EOF of the loss of Bus 14 and safety injection to the core.TSC should be evaluating the time to core uncovery and request that the EOF also evaluate this time projection.

TSC may send a team into the Auxiliary Building to turn on the breaker for MOV-851A.TSC may send a team into the Auxiliary Building to check on the loss of Bus 14.TSC should try to expedite the repair of the"A" emergency diesel generator.

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TSC should be evaluating possible methods of water injection to the core, such as cross-tying Bus 14 and Bus 16 or using the"B" reactor coolant drain tank pump.If TSC decides to cross-tie the Buses 14-16, one of two tie-breakers will not close.If TSC decides to use the"B" reactor coolant drain tank pump, the suction strainer will plug after approximately 2 minutes of operation and will have to be cleaned prior to any further use (¹33).7-13 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹EMERGENCY OPERATIONS FACILITY ga",~~~g~~~c'4'.~wxMC~t'pw't'j sf'wgc'ip.'xr wpaeYM~xDYpceat ates'.Ys+ox<~~<'~iwtara+Yceot

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'GENE.'K!EMER E"::iri~',ai:"jord Rieec'terr'Coofa'NMTai~n" I'n'o!ECCS::;,'deiftre ray!to;:,.the'!RCSjt%I Appropriate notification should be made per EPIP 1-5.EOF should be making immediate Protective Action Recommendations in accordance with EPIP 2-1,"Protective Action Recommendations".

If a GENERAL EMERGENCY not declared in approximately 15 minutes, a contingency message should be given out to declare it (¹42x).REPAIR TEAMS Performing actions as required to return equipment to service as soon as possible.~1015~03/00 Core exit thermocouples and R-29, R-30 start increasing and RVLIS starts decreasing

(¹41).ANTICIPATED RESULTS Control Room Operators should inform the TSC of the increasing core exit thermocouples, the increasing radiation in Containment, and the decreasing RVLIS.Operators should perform the applicable actions of CR-FR-C.1 (Response to Inadequate Core Cooling)when required.TECHNICAL SUPPORT CENTER TSC should be evaluating plant status and taking actions as required.TSC should inform the EOF of the increasing core exit thermocouples, the increasing radiation in Containment, 7-14 APPROPRIATE TIME SCENARIO TIME EVENT DESCRIPTION AND MESSAGE¹and the decreasing RVLIS.TSC should inform the EOF of the general plant status, actions being taken and need required.TSC may realize by this time that in order to recover core cooling, they will need to complete repairs on the"A" emergency diesel generator, tie it into Bus 14, and start all available safety injection pumps, even though they may not be completely sure of why Bus 14 tripped out.The thermography report given in the initial conditions should give them confidence that the problem is in the transformer connections and not the Bus.TSC should also realize that once they energize Bus 14, MCC-1C will be energized and they can now close MOV-851A when the breaker's AC power is turned on, thus terminating the radioactive leak source from Containment to the Auxiliary Building.TSC may also evaluate the possibility of back feeding Bus 14 from Bus 13 using the 14-13 breaker.EMERGENCY OPERATIONS FACILITY EOF evaluating plant status and taking action as required.1050+03/35 Radiation levels increase substantially in the Auxiliary Building, This is due to the leaking pipe between Containment and MOV-850A opening up where the crack.AW~~C)~~WRNMCAV~.

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is.A".i'i.-'issue

~86ovi:;:i:'e'cn'riicai::S-e'eitic5tiorie".:be iris ANTICIPATED RESULTS Control Room Operators may transition to ECA-1.1 (Loss of Emergency Coolant Recirculation) due to loss of both RHR pumps.TECHNI AL SUPPORT CENTE TSC should be expediting the turning on of the AC power breaker to MOV-851A.7-1 5 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹TSC should be expediting the recovery of AC power to Bus 14.TSC should inform the EOF of the increased radiation levels in the Auxiliary Building.TSC should inform the EOF of plant status, actions being taken, and needs required.EMERGENCY OPERATION FACILITY EOF should be evaluating plant conditions and taking actions as required.EOF Dose Assessment should be evaluating the plant vent release and making protective action recommendations to the Recovery Manager.The EOF/Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should recommend protective actions to offsite agencies as required.REPAIR TEAMS Repair teams should be expediting repairs as conditions permit.1100+03/45 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START)Alarms (¹46).ANTICIPATED RESULTS Control Room Operators should perform the applicable actions of AR-L-10.Operators should inform the TSC of the operation of the Auxiliary Building sump pump.TECHNICAL SUPPORT CENTER TSC should evaluate the Auxiliary Building sump pump operation and the possibility of the leak in the pipe 7-1 6 APPROPRIATE SCENARIO TIME'IME EVENT DESCRIPTION AND MES AGE¹between Containment and MOV-850A getting worse.EMERGENCY OPERATIONS FACILITY 1110 EOF evaluating plant status and taking actions as required.+03/55 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START)Alarms (¹47).ANTICIPATED RESULTS Control Room Operators should perform the applicable actions of AR-L-10.Operators should inform the TSC of the operation of the Auxiliary Building sump pump, Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).When they attempt to start the RCP's they trip out immediately.

TECHNICAL SUPPORT CENTER TSC should be evaluating the plant status and taking actions as required.1120+04/05 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START)Alarms (¹49).ANTICIPATED RESULTS Control Room Operators should perform applicable actions of AR-L-10.Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).7-1 7 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND ME SAGE¹1125+04/10 Power Control informs the Control Room that offsite 34.5KV circuit 751 is ready to be restored to service (¹50).ANTICIPATED RESULTS Con rol Room Operators should inform the TSC that circuit 751 is ready to be restored to service.Operators should, if directed by the TSC, restore circuit 751 to service per 0-6.9.2.1130+04/1 5 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START)Alarm (¹51).ANTICIPATED RESULTS Control Room Operators should perform the applicable actions of AR-L-10.Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).TECHNICAL SUPPORT CENTER TSC should be expediting the return of the"A" emergency diesel generator to service.EMERGENCY OPERATIONS FACILITY EOF Dose Assessment should be evaluating the release from the plant vent and making protective action recommendations to the Recovery Manager as necessary.

The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should make protective action recommendations to offsite agencies as neccessary.

7-1 8 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND ME AGE'¹1140+04/25 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START)Alarms (¹52).ANTICIPATED RESULTS~R Operators should be performing the applicable actions of AR-L-10 1145+04/30 Repair Team working on the"A" emergency diesel generator reports to the TSC that the emergency diesel generator repairs should be completed in approximately fifteen minutes (¹53).ANTICIPATED RESULTS TECHNICAL SUPPORT CENTER TSC should be planning the recovery of core cooling and the termination of the release from the Auxiliary Building when the"A" emergency diesel generator is returned to service.TSC should request operations to check the"A" emergency diesel generator line-up as much as they can to expedite the return to service of the D/G, TSC should inform the EOF of the estimated time that the"A" emergency diesel generator will be ready for return to service.1150+04/35 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START)Alarms (¹54).ANTICIPATED RESULTS~R'R Operators should perform the applicable actions of AR-L-10.7-19

'APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹1155+04/40 Repair Team working on the"A" emergency diesel generator reports to the TSC that it is ready to be returned to service (¹55)~ANTICIPATED RESULTS Con rol Room Operators, when requested by the TSC, should line up the"A" emergency diesel generator per T-27.1 (¹56).Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).TECHNICAL SUPPORT ENTER TSC should request that the Control Room have the"A" emergency diesel generator lined up for normal operation and to allow it to tie into Bus 14.TSC should inform the Control Room to start all safety injection pumps and Containment recirc fans available as soon as Bus 14 is energized by the"A" emergency diesel generator.

TSC should inform the Control Room to close MOV-851A as soon as MCC-C is energized if MOV-851A AC ower breaker was urned on.1200+04/45 Annunciator L-10 (AUX BLDG SUMP PUMP START)Alarms (¹57).ANTICIPATED RESULTS Con rol Room Operators should be performing the applicable actions of AR-L-10.7-20 APPROPRIATE TIME SCENARIO TIME EVENT DESCRIPTION AND MESSAGE¹1210+04/55 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START)Alarms (¹58).ANTICIPATED RESULTS Control Room 1215+05/00 Operators should be performing the applicable actions of AR-L-10.Auxiliary Operator lining up the"A" Emergency Diesel Generator informs the Control Room/TSC that the"A" emergency diesel generator is lined up per T-27.1 (¹59).ANTICIPATED RESULTS Control Room Operators should start the"A" diesel generator and ensure it ties into Bus 14.Operators should start the"A" and"C" safety injection pumps, the"A" RHR pump and the"A" and"D" Containment recirc fan coolers.All equipment starts except the"C" safety injection pump (burned out motor).Operators should attempt closure of MOV-851A, if the AC power to the breaker has been previously turned on.If the AC power to the breaker has been previously turned on then.the value will come off its back seat and the breaker will trip out.Indication of this will be, mid-position indication of value will not change.If the AC power to the breaker has not been turned on then no valve closure should be attempted at this time.Operators should inform the TSC of S.l.pumps and Containment recirc fan coolers starting.Operators should inform TSC of MOV-851A failure to close if the AC power was previously turned on to the breaker.7-21 APPROPRIATE SCENARIO TIME TIME" EVENT DESCRIPTION AND MESSAGE¹Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling and then return to E-1 (Loss of Reactor or Secondary Coolant).TECHNICAL SUPPORT ENTER TSC should send a team into the Auxiliary Building to turn on the AC power to MOV-851A.If the AC power to the valve breaker had been turned on previously, the TSC may send an electrician with this team to check the breaker (¹60)~TSC should be evaluating plant conditions, checking on progress of repair teams and taking action as required.TSC should be informing the EOF of plant status and actions being taken for plant recovery.EMERGENCY OPERATIONS FACILITY EOF should be evaluating plant conditions and taking actions as required.EOF should be requesting the Engineering Support Center to perform a core damage assessment.

EOF Dose Assessment should be tracking the release plume.The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies as required.io'm'p'lii'i'iikby".:.":~ppiox'imit'ety)thi~::xiii'i'y".

REPAIR TEAMS 1220+05/05 Repair Teams should be expediting repairs as conditions permit.Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START)Alarms (¹61).7-22 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹ANTICIPATED RESULTS Control Room Operators should be performing the applicable actions of AR-L-1 0.Operators should be performing the applicable actions of E-1 (Loss of Reactor or Secondary Coolant).1235+05/20 Annunciator L-10 (AUX BLDG SUMP PUMP AUTO START)Alarms (¹63).Plant vent reading are decreasing due to Containment pressure reduction, reducing the leak out of the pipe between MOV-850A and Containment and also due to the resumption of core cooling reducing the radiation levels in Containment

(¹65)~ANTICIPATED RESULTS Con rol Room Operators should be performing the applicable actions of AR-L-10.Operators should be performing applicable actions of E-1 (Loss of Reactor or Secondary Coolant).Operators may realize, at this time, that the Auxiliary Building sump pump operation interval is increasing and should inform the TSC of this.TECHNICAL SUPPORT CENTER TSC should be expediting sending a team into Auxiliary Building to check and/or turn on the AC power breaker for MOV-851A.TSC should be evaluating plant status and taking action as required.7-23 APPROPRIATE TIME SCENARIO TIME EVENT DESCRIPTI N AND MES AGE¹TSC may be evaluating the Auxiliary Building sump pump down interval change.TSC should be informing the EOF of plant status and actions being taken for plant recovery.EMERGENCY OPERATIONS FACILITY EGF should be evaluating plant conditions as required.EOF Dose Assessment should be tracking the release plume and coordinating/recommending protective action recommendations to the Recovery Manager.The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies as required.REPAIR TEAMS Repair Teams should be expediting repairs as conditions permit.1245+05/30 The team sent into the Auxiliary Building to check and/or turn on the AC power breaker for MOV-851A reports the following, de endin on he si uation: If the AC power breaker for MOV-851A~wae no previously turned on, then the team will turn it on and report this to the TSC.If the AC power breaker for MOV-851A was previously turned on and then tripped, the team will report their findings to the TSC and await.further instruction.

After evaluation the TSC should request the breaker be reset and turned on.This should be done by the team (¹60).ANTICIPATED RESULTS Control Room Operators should close MOV-851A when requested by the TSC.MOV-851A will be considered closed at 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br />, isolating the leak on the pipe between CV and 7-24 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹MOV-850A.NOTE: MOV-851A will be con i ered clo 1250 h rs for cen ri ur ose.Operators should inform the TSC of MOV-851A closure.TECHNICAL'UPPORT CENTER If the as power breaker for MOV-851A was previously turned on and then tripped, TSC should evaluate this and most probably decide the following:

the breaker could have tripped starting the closing cycle of the valve due to not being operated for a long period of time, or the breaker may not have been completely reset the first time by the Auxiliary Operator.Based on the above and the emergency conditions that exists, the TSC should have the.team reset and turn on the breaker for MOV-851A and then request the Control Room close MOV-851A.If the AC power breaker for MOV-851A~wae no previously turned on, TSC will request the Control Room to close MOV-851A.1300+05/45 With the leak from Containment isolated, the Auxiliary Building sump pump is no longer operating at short intervals and the plant vent radiation readings are beginning to decrease significantly

(¹65).ANTICIPATED RESULTS Control Room Operators should be performing the applicable actions of E-1 (Loss of Reactor or Secondary Coolant).TECHNICAL SUPPORT CENTER TSC should inform the EOF of the closure of MOV-851A and the decreasing plant vent radiation readings.TSC evaluating plant conditions and taking action as required.TSC should be checking on progress of repair teams.7-25 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION AND MESSAGE¹TSC should be informing the EOF of plant status and actions being taken for plant recovery.EMERGENCY OPERATIONS FACILITY EOF should be evaluating plant conditions and taking actions as required.EOF Dose Assessment should be tracking the release plume and coordinating/recommending protective action recommendations to the Recovery Manager.The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies as required.REPAIR TEAMS Repair teams should be expediting repairs as conditions permit.~1315+~06/00 Recovery/Re-entry discussions may commence.This should include preliminary discussions about short term and intermediate term concerns, including preliminary designation of the recovery organization.

State and counties may also conduct parallel discussions.

Recovery/Re-entry interface between TSC/EOF and offsite agencies should be demonstrated as time allows.After all exercise objectives have been demonstrated, the~1400-1500

+~06/45-exercise will be terminated.

07/45 7-26 0

SEC TION 8.0 MESSAGE FORMS AND PlANT DA TA SHEETS MINI SCENARIOS (1)"B" Safety Injection-pump outboard pump bearing replacement, 0715 Hours (2)"B" Charging pump plunger replacement, 0715 Hours mechanics.(3)Checking Turbine Generator noise and vibration problem, 0730 Hours auxiliar~oerator (4)Charging Pump Room fire, 0805 Hours fire bri ade.(5)"C" Charging pump fire repair, 0825 Hours mechanics electricians and!8 C.(6)Checking Auxiliary Building sub-basement for RHR system leakage per E-1 and"B" RHR pump trip problem, 0910 Hours auxiliar o erator TSC team.(7)Checking"A" emergency diesel generatorlocal alarm panel and the Emergency Diesel Generator, 0920 Hours auxiliar o erator.(8)"A" emergency diesel generator problem, 0935 Hours i e fitters and-""'"'**I.(9)Checking Bus 14 tripping out problem, 1005 Hours electricians

.

t (10J Checking"Cts Safety Injection pump breaker on Bus 16 problem, 1005 Hours alii*i (11J Turning on AC power breaker for MOV-851A, 1005 Hours auxiliar o erator TSC team.(12)Bus 14-16 cross-tie breaker problem, 1005 Hours electricians

.(13)Possible back feeding Bus 14 from,Bus 13 using 14-13 tie-breaker problem, 1005 Hours electricians

.f14J Possible line up of the"B" RCDT pump to CNNT sump"B" or the RWST, 1005 Hours TSC Control Room and auxiliar o erator.(15)Cleaning the"Bts RCDT pump suction strainer, 1005 Hours i efitter.(16)Line up of"A ts emergency diesel generator per T-27.1, 1155 Hours Auxiliar~oerator (17)Check andlor turn on the AC power breaker for MOV-851A, 1215 Hours auxiliar o erator and or electrician

.

CONTROLLERS FOR MINI-SCENARIOS A.AUXILIARY OPERA TOR CONTROLLERS 1.0730: Checking Turbine-Generator for noise and vibration problem.2.0910: Checking Auxiliary Building sub-basement for RHR system leakage per E-1 and"B" RHR pump trip problem.3.0920: Checking"A"Emergency Diesel Generator Loca/A/arm Panel and the Emergency Diesel Generator.

4.1005.Turning on AC power breaker for MOV-851A.5.1005: Possible line up of the"B" RCDT pump to CNMT sump"B" or the RWST.6.1 155: Line-up of the"A"Emergency Diesel Generator per T-27.1.7.1215: Check and/or turn on the AC power breaker for MOV-851A fan electrician may be involved also).B.ELECTRICIANS CONTROLLERS 1.0825: 2.1005: 3.1005: "C" Charging pump fire repair.Checking Bus 14 tripping out problem.Checking"C" Safety Injection Pump failure to start on Bus 14 and 16 problem.4.1005: 5.1005: Bus 14-16 cross-tie breaker problem.Possible backfeeding Bus 14 from Bus 13 using 14-13 tie breaker problem.6.1215: Check andlor turn on the A C power breaker for MOV-851A (An Auxiliar 0 erator ma be involved also.

C.MECHANICS CONTROLLERS 1.0715: 2.0715: 3.0825: 4.0935: "B" Safety Injection Pump outboard bearing repair."B" Charging Pump plunger replacement."C" Charging Pump fire repair."A" Emergency Diesel Generator Repair.D.I AND C CONTROLLER 1.0825: "C" Charging Pump fire repair.E.FIRE BRIGADE CONTROLLERS 1.0805: Charging Pump room fire.F..PIPE FITTER CONTROLLERS 1.0935: 2.1005: "A" Emergency Diesel Generator problem.Cleaning of"B" RCDT suction strainers.

Time 0700 Message: IC GINNA STATION 1993 EVALUATED EXERCI E MESSAGE FORM Si I<<C<<IR Simulated Plant Conditions; See the Attached Sheets~essa<ee: """THIS IS AN EXERCISE">>" FOR CONTROLLER USE ONLY Controller Notes: 1)Review initial conditions and Plant Status Sheets with the Exercise operating crew.2)Review Exercise precautions/limitations and any Exercise activities that are normal (pre-staging, simulated notifications, extent of participation of offsite agencies, etc.).3)Ensure that the operating crew understands that the Exercise is not to interfere with safe plant operations.

4)Explain that abbreviation"OOS" means"out of service," i.e.repairs must be made before the equipment can be used.Antici ated Resul s: 1)Participants should review conditions, plant data, and other procedures as applicable.

GINNA STATION 1993 EMERGENCY PREPAREDNESS EXERCISE INITIAL CONDITIONS The R.E.Ginna Nuclear Power Plant is operating at approximately 98%rated thermal power.The Plant has been operating at this power level continuously for approximately 180 days.Equilibrium primary coolant isotopic activity as of 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> (11/17/93) is provided in table 9.2 of Scenario Section 9.3.Total activity is 2.56 microcuries/gram.

Chemistry log sheet available from controller.

The Reactor Coolant System (RCS)total leakage is 0.250 gpm as of 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> this morning.Identified RCS leakage is 0.092 gpm.General weather conditions are partly cloudy with no current precipitation.

For purposes of the Exercise, additional meteorological information in the Simulator Control Room should be obtained from the Plant Process Computer System (PPCS).Offsite power 34.5 kv circuit 751 is out for pole replacement and cable repair due to a tractor trailer truck hitting a pole on Slocum Road, north at 0600 this morning.The"A" Emergency Diesel Generator started and energized safeguards buses 14 and 18.Subsequently normal power was restored to buses 14 and 18 from offsite power 34.5 kv circuit 767 stopped and aligned for auto standby.The"B" Safety Injection Pump is held because of high vibration on the pumps outboard bearing.The high vibration was detected yesterday (11/16/93) during the performance of PT-2.1Q (Safety Injection System Quarterly Test).The pumps outboard bearing is disassembled, cleaned and new bearings have been checked out of a QA storage.The pump is now awaiting re-assembly.

An A-52.4 has been submitted for the'"B" Safety Injection Pump.The"B" Safety Injection Pump electrical breaker"b" contact has been jumped per EM-777 (MOV-871 and 871B Control Circuit Jumpers)."B" Charging Pump is held for plunger replacement.

The pump was held yesterday morning'11/16/93) at 0700 and the maintenance is approximately 50%completed.

A preventive maintenance analyst, while doing thermography on Bus 14 during the early morning hours, reports to the shift supervisor that he has found a hot spot on Bus 14 station service transformer.

He also informs the Shift Supervisor that he will talk to maintenance later this morning about planning a Bus 14 outage to check out the transformer.

MAJOR PARAMETER 1993 EVALUATED EXERCISE 0+fg sh'z87 ENGINEERED 8AFEGUARDS Time: fgbb Reactor'hutdown YES 0 N-31~CPS N-32 o CPS N-35 8~-0 AMPS N-36 AMPS Avg.Nuclear Power~I RCS Pressure ZZ PSIG PRZR Level~2 A RCP UNNIN STOPPED B RCP'UNNIN/STOPPED 1A S/G Level 1B S/G Level 1A S/G Pressure~O~PSIG 1B S/G Pressure PSIG Turbine/Generator ONLIN OFFLINE 4 KV Buses NERG D DEENERGIZED 480V Buses ZE DEENERGIZED DC Batteries AQgVOLTS BQgUOLTS Cnmt Pressure~2.PSIG Cnmt Sump A Level~0 FEET Cnmt Sump B Level INCHES" Loop Hot Leg 0.'F A Loop Cold Leg&~2-'F B Loop Hot Leg~O~QF B Loop Cold Leg~QF RVLIS.l*CET~~QF S/G A Total Aux FW Flow C7 GPM S/G B Total Aux FW Flow~GPM DIESEL GENERATORS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TBY OOS TSC RUNNING ED OOS Security RUNN UNLOADED B OOS ENGINEERED SAP DS Hi h Head S.I.Pum s FI-924~GPM FI-925~>GPM 1A.INS RV TB OOS 1B.INSERV STBY 1C.INSE V TB OOS BAST Level=Low Head 8..Pum s FI-626 0 G M 1A.INSERV TB OOS REC RC 1B.INSE V B OOS RECI C RWST Level=~~~4 Containment 8 ra Pum s FI-931A~GPM FI-931B~GP 1A.NSE U TB OOS 1B.INSERV T OOS NaOH Tank Level=~%Containment Recirc Fans 1A.SER STB OOS 1B NSERV STBY OOS 1C.INSER S OOS 1'N ERV TB OOS Post Accident Dampers OPEN CLOSED Service W.Pum s 1A.NSER STBY OOS 1B.I SER STBY 0 S 1C.INSER STBY OOS 1D.INSERU TB OOS A&B Header Pressure PSIG Com onen colin Water Pum s lA.INSER STBY 00 1B INSERV TB OOS Surge Tank Level=Aux.Feedwate um s 1A.INSERV OOS 1B.INSERV TB OOS Turb.Driven INSERV TB CST Level~0 FEET OOS 8tandb Aux.Feedwater Pum s 1C.INS V TB 00 1D.INSERV B OOS*CET=Average of-Selected Core Exit Thermocouples gled CF/~+Gi+6/GYPS gZ Sq~q>>S"g',8~gWg Pmp A'S:Lcm' t(QV 17)1'993 Oa'" R.E..'i~iA S!t(ULATOR PAGE TRitlD CROUP ASSIGN",Ft(T S)JtWARY GR):"'P: EVENT!PROCEDORc:

EPIP 1-5 PLANT STATUS 1 2 3 4 5 6 7 8 a 10 12 18 20)1 23 2S 3-37 38 3o 40 41 JA'i 4w 46 48))o y 51 POINT ID A~)AS RXT N31 N32 ti'35 N35 NP PRCS LPIR FRY A FRCLB RXT16 RXT!7 TiSUBTC LSGA LSGB PSGB GENS(P BSR2 BUS!!A B)JS1!B BUS!2A BUS!2B Bi!A!2A 81!PI PCV LSIU./PA L0942i L0943E)PA4oD L0943D L09420 LO943C L0942B L0943B LP942A L0943A T0409A T04!OA T0450)045'AV)GA)AID TAVGBt'I 0 LRV TCCDRE FAUXFWA FAUXFWB BNR081 BXR082 voAD V3504 VALUE DESCRIPT I 0)J 2!'"!'ATED TRANSIEt))

M/0 SCRAJt P A TD<TriP"PEA)(ii STATUS SQB E RANGE DETECTG)', ll.";!SDURCF RANGE DETECTOR)Y-2 It)TTciRNEDIATE RANGE DETECTOR N-35 INTERt)ED I ATE RANGE DETECTOR N-36 AVERACi tlL'CLEAR PONER REACTOR COOLANT SYSTEt)AVG PRESS cgcoc)loT7EA g)J+c)Gc)c(~GP ANT LGDP A AVG FLG)!Ri~)C<~00'NT iu"==..<6 F'N RCPA BRiAXER WdJSE RX TRIP RCPB EREAXER CAU)-"w RX TRIP I tÃJRE TC UBCOGLED"AS@IN ST(')GEN A t(ARRQ)t RANGE AVG LEVEL STt(GEN B NARRGN RANGE AVG LEVEL ST):-.=(A AVciRASE PRES%RE Sit=='-'4)JERASE PRESSURi Gitt)i-"RATGR ON Lit(i:".".i-'XER

!G!372 6":tFRATOR ON LINE BFEAXER 9X!372 BUS!!A SUPPLY BP)FAKER BU" llB SUPPLY BREAKER NGT TERNIhATED DN PPCS (7/!9/91)tlQT)ER~))IhATED ON PPCS (7/19/91)BUS l!A TQ 12A TIE ERE)NER cga)l)qgii+i)i)AV)'RAEc cc cSUcc CcYA;'(Nit(T S')t')P t!gv=".AEE LEVEL SL~~c."" LEUcL 8 ItiCHES (TRAIN A)cLt~i.">EV:-L 8 INCH"S (TRA!t(9)8)~8 LEVE)78I:KHc i(TRAltl A)SU.""" LEVEL 7S It(C))ES (Kit)t B).-LEVc 113 tlCHES(TRAIN A)SL')'-'LEVil.113 lt(CHES(TRA!N B)":.':;~,"-.

'VEL 180 I NCH=6(TRAIN A)St!c"=LEVc'80 INCHES(TRAItl B)c)J~:" LE()EL 214 IN'.HES(TRAIN B)R".L>>'.HGT LEG TEt&RATL'."=P;L: HGT LEG TE)(PERATLr W).'-'OLD LEG TEhPiRATURE R'B COLD LEG TEtiPERATL-":.E R L-'AVG (THGT/TCGLD lilDi RNG)RC.'-)AVG (TbŽ)T/;COLD ViIDi Rh6)Ri-'."'.:;9 V SSEL AVERAGE LEVEL iii!1)SCORE TC AVcRAS=TEtLP S/6.-'GTA'UX XFii:CATcR F 0,(S/6":OTA)PJX FEEDVATcER FLGN~i"""'XILIPRY FE~t'4))".T""R PUt(c A t')TR P~";ILIARY FEEDAATER PUk" B c""..-i rUt(P)cNi SL)P)Y VALV" A AU!c)oUK~STEAN SUPPLY VALVi B DUAL ti'0 AThS 6009 NGT TP IP 6009!.00000+00 It<HB:.00000+00 INHB 8.12829-04

!NHB 8.12829-04 INHB 98.08 GOOD 2248.6009 4S,2 6009 98.1 GOOD 97.3 C~ZD NO)TRIP 6009 NGT TRIP 6009 47.4 GDD>>52.1 G009 52.1 6009 701.GOOD 701.GGQD t61 TRIP C<09 NG: TRIP 6009 tl01 TRIP 6009 NOT TRIP 6009 tlDT TRIP DEL NOT TRIP DEL TRIPPED 6009 TPIFFiD 6009.24 6009 2.0 6009 LG~~R GGGD LG'r)ER 6049 LOPER 6009 LOW""R G009 LOVER GGDB LO)tiR GD09 LONER 6009)LO)(ER GGGD LO)liR 6009 LSliP 6009 60!.1 C~ZD 601.1"6009 44.2 6009 544.1 6009 572.7 GOOD 572,5 G009 99.1 6009-600,6 600>>0, Gl)09 0.GCCD 6009 6009 G009 GGDD 0 F OFF CLOSED CLOSED E.U.CPS CPS A!(P ANP 0/PSIG/I//P%/PSIG PSIG PSIG FiET DEGF DcGF DcGF DEGF DEGF DEGF/D" 6F GPN GPtt hR 17~1993 Ob:5~R.:.Gite'A SI)%PATOR TREND GROUP ASSIGViCtsT PJ,",NAR'>'AGE 2 GRX~:=iENT!PROCE&iw",'PIP 1-5 PLANT STAT%POia/T rD 53 FSIA 4 iSIB 55 P21b0 56 P2lb1 57 BKR041 5S BkR042 59 F~R043 b0 Bc<R044 DESCRIPTION SAFET'i IW:ECTION LOOP S.'.~,'>'n~<<Tiara

'DP SERVICE RATER FNPS A SB,'iCE NTER PU"iPS C SEE"liCE@TER PUt'iP A:-~V!C=RATER PUK?B SERVICE WATER PUtlP C SEr7viC=VJATER PfNP D A AViG FLO'A B NG FLOA 4 B HEADER h D HEADER VALUE ON OW ON OFF 0.0.84.75.lcUAL E.U.6OOD GPN 6000 GPN GOOD PSIG GOOD PSi6 GOOD GOOD GOOD GOOD t(R,'!7i 1993 R, E.614iA Slt(ULATOR TREtfD 6RQUY ASSIGNt(EtiT S<JYiitARY PAGE 1 GROUP: EV="h!2 PRO!".EDL'8='.

EPIP 1-5.LANT STATUS POItfT ID DESCRIPTION

!/ALUE 0UAL E.U.l 3 4 6 l 8 lP 1!i rz lk 13~~<5~Q 17!8 19 20 21 l)R~4 Cv 2d i5 27 28 l)P'0<31 33 34 35 vC'0 40 Pg Zl 42 43 F0619 LR~~T<AS033 ((9033 NT033 WT250 t<fDT2 Rp}R02 R05 R09 R34 R35 R}0A R}1 R!2 R!0B R}3 R14 R18 R!'9 R29 R30 R!5 R12A5 R!ZA6 R!2A7 R!2A9 R14AS R!4A/R!4A9 R!5A5 R}M7 R31 R32 CVH TCV03 TCV07'CV08 TCV09 TCV}0 TCV}7 CDPQffitIT COOLING LOOP TOTAL FL(l REFL!SLING WAT~D STORAGE TANt(LVL 33 FOOT LEVEi MItlD SFEED 33.OQT LEVEL Witi'9 DiiiCTION 33~DOT LEVEL TENPE!ATURE 250 FOOT LEVEL TEtfPERATURE 2;0 TQ 33 FOOT LEVEL D=iTA!ENP ARi>>1-COtfTROL RC<0rt AREA 2-CQt(TAINYENT kii<'-5-SPEfG FUEL PIT AREA 9-LETDD~<t LINE Y'fITQR A.'Z-'4-AU!(BLDG CV PRAY PUY~AR=~35-PASc-"AY<PL"" PA!FL CQ<MTAlffNit(T IODINE NCiNITOR R!OA ceNI'AIfiYif(T AIP, PARTlcULATE CO'PAPAIN:"icit(T GAS tG'f: CR PLA'lT Vit!T IODINE tier(ITDR R!OB AUÃBi-DG E)(HAUST AIP, PARTICU<ATE AUj(BLDG EI(HAUST GAS Yet(ITOR LID:.'ID ttASTE DISPOSAL aGNITGR ST==".'ENERATOR BLO<~!,0'~f DRAIN A.":""<<.':9-CC<NTAIt'.".Et(T HIGH RAN"-: A>>c.-3>-CONTA!r;Nit,'~

HIGH RANGc CC,"":-USER AIR Ea":CTCR i>'HAUST CV V"-NT CHAfl 5-LO)f Rf!!)-6AS CV V=.'lT CHAN 6-ApcA 6-"'i'fA C'"f~i CHAN 7-i"<ID EAf(i GAS CV",:-".!CHAN 9"H!iH RAf<GE GAS PLA,:'17'f'EtfT CHA<'LO"'AI(GE CAS PLA,"l Vif(T CHAfl 7-NID P>>USE GAS PLA'!i')ir(T CHAN 9-HIGH RA!<Gc GAS AIP.i:ECTC<R CHAN 5-LQ'-'ANGE CAS AIR=.'iCTOR CHAM 7-tiiD RAMGE GAS AIR<ECTCR CH>>nrt c-H!I R>>s><GE GAS AR:-A 31 STEAN LItfi A (SPING)A;".EA 32 STEAN LINE 8 (SP!tfG)C'!PvDRD<3 it MriCEt<~!PAT!0ti CV B-':SEYit(T LEVE!6FT!"t~Z 03 CV GPERY<EDIATE LVL 6FT TEY>>(f8 CV ItJTERiiEDIATE LVL 6""T TBP N CV!MT RN DIATE LVL 6FT TEN ft}0 CV Opi>>AT!ti'6 Li'fi'L 6FT TEY<P C}7 LALN C'009 GOOD GKO GKO 6009 GOOD GQQO GOGO GQOO 6MO C<09 6009 GQQO 6009 6009 GOQO 6009 GOOD GKO 6009 GKO 6009 6009 GOOD GKO 6009 C<09 6009 GQQO GOGO GOQO 6MO GOQO 6009 6009 6MO 6009 GQDO 81~0"K09 S}.0 81.0 94.1 6009 6009 GOGO 1427, 94.5 drQ 320.44,4 43,8 eO 9.33255-02 4.62382+00 F 01975-01 2.91742+01 1 F 01742 00}.09648>00

}.72782~02 1.60555+02 2.63785+02 8.74732~00 2.55932<02 5.52712+01

}.06844~03 2.04}73~03 9.75!30-0!

9.75130-01

}.35480v03 4~05}'-0-2.67992-02 4.205M 9.99987"04 2.30991-06 4.62984-06 9.10997-04 6.22985-06 }.80975"05 }.52999-03 1.0!004-02 }.01004-02 ~0 67.9 Si.p GPti/NPH DEG.DiGF DEGF DEGF tS/HR NR/1$NR/HR NR/HR/8/HR NR/HR CPN CPtt CPN CPN C!'N CPN CPN CPN R/HR R/HR CPN UCI/CC NR/HR UCI/CC UCI/CC UOI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC%/HR Ya/HR I/9" GF DEGF DE6F DEGF D"6F DiGF Time: 0715 Message: 1<<tNN BTAT10 1993 EVALUATED EXERCISE MESSAGE FORM<<I<<L IR Simulated Plant Condi ions: See.the Attached Sheets~Messa e:<<<<"THIS IS AN EXERCISE"" Make the following PA announcement after sounding the"Attention" signal: "Attention; Attention all personnel. The Ginna Nuclear Station is now starting its 1993 Emergency Preparedness Evaluated Exercise, All Exercise messages must be started and ended with'THIS IS AN EXERCISE'," Announce twice.FOR CONTROLLER USE ONLY Controller Notes: 1)Ensure that the PA announcement is made.Antici ated Results: 1)Simulator Control Room makes the PA announcement.

1993 EVALUATED EXERCISE Time:~/I MA JOR PARAMETERS Reactor Shutdown YES 0 N-31 G CPS N-32 O CPS N-35 AMPS N-36~-AMPS Avg.Nuclear Power'K.l~RCS Pressure'PS IG PRZR Level el A RCP UNNI STOPPED B RCP UNNING/STOPPED 1A S/G Level 1B.S/G Level Ze 1A S/G Pressure 0/PSIG 1B S/G Pressure PSIG Turbine/Generator ONLI OFFLINE 4 KV Buses ER/DEENERGIZED 480V Buses ENERGIZE/DEENERGIZED DC Batteries A~SOVOLTS B~BO VOLTS Cnmt Pressure a 2.(o PSIG Cnmt Sump A Level~~FEET Cnmt Sump B Level o 0 INCHES A Loop Hot Leg A Loop Cold Leg 8 SZ-OF B Loop Hot Leg'F B Loop Cold Leg RVLIS*CET Ma.~'F S/G A Total Aux FW Flow C2 GPM S/G B Total Aux;FW Flow C>GPM DXESEL GENERATORS A.RUNNING UNLOADED OOS B.RUNNING UNLOADED Y OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED STB OOS ENGINEERED SAFEGUARDS Aux.Feedwater um s 1A.INSERV STB OOS 1B.INSERV STBY OOS Turb.Driven NSERV TB OOS CST Level~%F T ENG1NEERED SAFEGUARDS Hi h Head S.X.Pum s FI-924 0 GPM FI-925 Z5 GPM 1A.INSERV OOS 1B.INSERV STBY 00 lc.INSERV OOS BAST Level=Low Head S.I.Pum s FI-626 M 1A.INSERV TB OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=Containment 8 ra Pum s FI-931A~GPM FI-93 1B~GPM 1A.INSERV S OOS 1B.INSERV STB OOS NaOH Tank Level=Contai ecirc Fans 1A.STBY OOS 1B.V STBY OOS 1C.SE S Y OOS 1D.INSERV B OOS Post Accident Dampers OPEN LOSED Service Pum s 1A.SERV STBY OOS 1B.S STBY OOS 1C.NSE S OOS 1D.INSERV OOS AGB Header Pressure 8 PSIG Com onent Coolin Water Pum s 1A.NSERV STBY OOS 1B.INSERV TB OOS Surge Tank Level=~D Standb Aux.Fe water Pum s 1C.INSERV T OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples t(GV!7<1993 07: 13 F;.E, GIt'.(A Slf"iULATOR TRB(D GROUP ASSIGN<it(T SU)<NARY PAGE GRDCE: EVii"T!PROCEDUF,=,'PIP!-5 PLANT STATUS PQIi(T'D DESCRIPTIOt(VALLi>>MAL E.U.5 7 8 9 10<2 f3!4 lg 16:/18<q<<0 21 2f>>d 24 25 26>>l 28 29 IO 31 33 34 35 36 37 38 39 4(I 41 42 43 45 46 C,'>><>>a ATWS RXT t!3f N32 555 N36 NP PiF~U'1R FRCLA FRCLB RXT!6 RXT!7 TSUBTC LSGA LSGB PSGA PSGB GENBXRf Cd(BKR2 BUS!!A BUS!18 BUS12A BiJS128 Bi!A!2A 8!f8128 PCV LS(IPA L0942E L0943E LO'?429 L0943D L0942C L094iC L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TAVGAWID TAVGBWID LRV TCCGPE FAUXFWA FAUXFWB BRROSf BNR082 V3505 V3504 ANTICIPATED TRAt(:"IEt(T W/0 SCRI'<RiA"TOR TRIP BRENER STATUS SGiSCE RAtiK DETiCTOR V.-31 SOUKE RANcE DETiECTGR N-32 INicPJ(EDIATE RANKLE DETECTOR N-35 INTcRt'.EDIATE RANGE DET>>TOR N-36 AV=wAGE NKLEAR PGWEK REA:.TOR CCG ANT SYSTEtl AVG PRESS PRESSURIIER AVENGE L""bcL RFACTOR COOLAt!T LOOP A AVG FLN REA"TGK CGP.ANT LMP 8 AVG FLOW RCrA BREA"ER CAUSc RX TRIP RCPT"RcAi(cr("AUSc R'/TRIP Ital=.E TC SUKOGi cD t4RGIN STt(EcN A NARROW RA!(6c AVG LEVE STt<Fit".8 NArROW RANGE AUG LEVEL ST<" 6<<:N A AVERAGE PRESPJRE STN EEN 8 AVERAGE PRESSURi 6~'GATOR ON i IN": BREA)E'ER 16!372 CENERATGR ON LINE BREA)(ER 9X!372 BUS ffh SUPPLY BREAXER BUS.'!B SLiPPLY BREAXER t(OT TERt(INATED Gtt PPCS (7/!9/913 N<OT TERtflt@TED ON PPCS (7/19/91)BUS!!A TO!2A T!E BRENER BUS!!8 TO!28 TIE BRENER CGN A: t(i"<ENT AUERA=PRESSURE C<3)(TAIS"ct(T SUltp A AVEKAGE LEVEL SUN~i~LEVEL 8 INCHES (TRA!tv A)SiJ r 8 LEVEL 8 It(CHicS (TRAIN 8)SU!F'LEVEL 78 lt<CHcS (TRAIN A)SURF 8 LiVEL 78!NCHES (TRAIt(8)SPP: LEVEL 113 INCHES(TRAIN A)SU<~<8 LEVEL!13 It(CHES(TRAIN 8)PN 8 LcVEL 180 INCHES(TRAIN A)SL~"" LiVEL 180 INCHES(TRAIN 8)SU

>ERATURE RCLB HOT LEG TEt'PERATUFc RCLA COLD LEG TEt(FEPATNE RCLB CO(.D LEG TEt(PERATURE RCLA TAVG (T)6T/TCO' WIDE Rt(S)RCLB TAVG (THQT/TCOLD WIDE Rt(G)RECTOR VESSF AVERAGE LEVEL Ei~!INCORE TC AVERAGi TEt(P S/6 A TOTAL A(JX FEEDPTcR FLOW S/6 TOTAL NJX FEEDWATcB FLOW i'>~~PUt(P STEAt(SUPPLY VALVc 8 t(0 ATViS NOT TRIP 1.00000+00 !,000(&00 S.!2829-04 8.12829-04 98.08"248.48.1 9S.!97.3 t(QT TP,IP tlOT TRIP 47,4 52.1 52.1 701.701.NOT TRIP NQT TRIP NOT TRIP NOi TRIP tlGT TRIP NOT TRIP TRIPPED TRIPPED ,26 2,0 LOi)ER LG((ER LOWcR LONER LONER LOWER LQ)tER LGWcR LOA"R LONeR 6009 6009 It(HB INHB It(HB IhHB 6009 6009 G009 GGGD GM9 GOOD 6009 600>>GMD G009 GOOD 6009 GMD GOOD KOD 6009 DEL DEL 6M9 GOOD GG09 6009 6009 GOOD G009 GMD 6009 6009 6MD 6009 GGGD 6009 601.1 6009 601'-6009 6009 KO9 6009 GOOD GGOD 544.2 544,1 572.7 572.6 99.1 600~6009 GMD 6009 600.6 0.0.GFF OFF CLOSED CLOSED KOD GOOD 6009 CPS CPS Al(P A!(P/PSIG//DEGF//PSIG PSIG PSIG FEET DiGF DEGF DEGF DEGF DEGF 886F/986F Gpt(GPt( NOV 17i 1993 07'3 R.E.GINA SIP"LATOR TREND GROUP ASSIGiiIiEt1T Ski"iARY PAGE 2 GROUP;EVENTI PROCEDURE: EPIP 1-5 PLANT STATUS POI<'8 DESCRIPTION VALL'E QUAL E.U.53 54 i 5 55 57 58 59 60 FSIA FSIB P2160 P2161 MR041 BKR042 BNR043 BnR044 SAFETY IN'ECTION LOOP A AVG FLLC SAF"TY IN.'ECTION LOOP 8 AVG FLOW SBJ'l!CE 4'ATER PUMPS A h 8 H"ADER SERVICE WATER PUMPS C 0 O HEADER SERVICE WA ER PU1LP A SERVICE WATER PiNP 8 S"RVICE N'ATER PUhP C SE%>ICE WATER PUL'~8 ON ON ON OFF 0.0.84.75.GOOD PN GOOD GPN COOn PSIG GOOD PSIG GOOD GOOD KOD GOOD ti'OV 17i 1993 07: 14 R.F.Git'lA SI"GATOR TR"t)9 GRIP ASSIGNYiit!T

SUMMARY

6 EL~: EV=WT2 PROCEDU"i: EPIP 1-5 PLANT STATUS POINT fD DES RIPTIOW VALUE E.U.2 3 6 7 8 9}0 12 I~14!5 16 17 18}9 22'3 24 25'lg, 27')8 30 31 J 34 35 37 38 3D 40 4}42 43 F0619 LRNiT WS033 WD033 WT033 MT250 WDT2 R01 R02 R05 R09 R34 R35 R}OA Rll R12 R108 R}3 R14 R}8 R!9 R29 R30 R}5 R!2A5 R}2A5 R12A7 R}2A9 R}4A5 R!4A7 R14A9 R}SA5 R15A7 R}SA9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV}0 TCV17 CC~"i.QWENT COO'NG LQQP TOTAI FLW RE%" iNG WATER STQPAGE ETAttk LVL 33 FOOT LEVEL W!AD SPEED 33 FOOT LEVEI WfND DIRECTiOW 33 FGDT LEVEL TEMPERATURE 250 FOOT LEV: TEMPERATURE 250 TO 33 FOOT LEVcL E+~TA TEN'RiA 1"COt!TROL ROON AREA 2-CONTA IWNEIIT AREA 5-SPENT FUiL PIT AREA""-LETDONW L!tfi I'iQNITOR AREA 34-AUX BLDG CV PRA7 PUi'~~AREA 35-PASS SAMPLE PANEL COi'ITAiNiiENT IODINE tl0"t!TQR R}OA CONTAINMENT AIR PARTICu ATE CM'P.INtlit!T 6AS t!0iNITOR F'WiT VENT IODItfi NOW!TOP, R}09 AUX BLDG EXHAUST AIR PARTICULATE AUX~DG EXHAUST GAS iiugITOR LNUI'ASTE DISPOSAL tXINITOR STEAN CitiiRATOR DLQWDQl'N DRAIN AF A 29-CQtJTAIt/NittT HIGH RANGE Ac;="A 30-KWTAIk'"iitiT HIGH RANCE CON'"N-R AIR JECTOR cXPAUH CV VENT CION 5-LOW RANEE GAS CV VENT CiiAtt 6-AREA GANA CV VENT CSN 7-NID RANK GAS CV Vit!T CHAN 9"HiGH RANGE GAS PLA'iT VENT CHAtk 5-LOW PfitiGE GAS i.VENT CHAN 7-MiID PPNGE 64S PL(ii V t<T CHAW 9 HIGh'ANGE CAS AiR EJECTOR C%'I 5-LOS RAiNGE GAS AIR EJ CTOR CHAN 7-I"iID RANGE CAS AIR E.ECTOR Catt 9-HI ANGE CAS kR""~;l STEAN LIIIE A!BRING)N=A 32 STEA"i Lftii 8 (PING!CV HIiROGEW CQtiCEt)TRATIQN CV BASEMENT LEVEL hei TEMP tt3 CV!INTERMEDIATE LVL 6F't TEIIP 47 CV itITERNEDIATE LVL 6FT TEMP tt8 CV INTERiNEDIATi LVL 6FT TEMPÃCV INTcRNEDIATE LVL hFT TEMP!I}0 CV i"FERATItF~ LEVL hFT 7ciiP 5}7 LALII GQQD 6009 GOOD GOOD GOOD GQQD GOOD GCGD GOOD GOOD 6009 6009 6009 GOOD GOOD GOOD GOOD GQQD GOOD 6009 600D C<09 6009 6009 GQQD GOOD 6009 GOOD GOOD GQQD 6009 6009 6009 GOOD 6009 GRID 6009 81.5 6009 81'"6009 81.5 81,5 94.4 GOOD 6009 GOOD 1427.94.S 5.1 321.44.2 43.4<<.8 9.33255-02 4.62382400 3,0!995-01 2.9}742~0} }.04}}2+00 }.09648~00 1.6548}w02 1.60555+02 2.63785+02 8.63474~M 2.55932>02 5.64774+01 1,05925+03 2.!}348~03 9.75130-01 9.75130-01 1.45797+03 4.20511-03 2.67992-02 4.20511"05 9.99987-04 2.30991-06 4.62984-05 9.10997-04 5.22'?85-05 }.80975-05 1.52999-03 }.01004-02 1.01004-02 ,0 68.6 PN IFG.IZING DEGF D"=6F NR/HR NR/HR NR/HR ts/HR CPM CPN CPN CPN CPM CPN CPN CPN R/HR R/HR CPM UCI/CC NR/HR KI/CC UCI/CC Kl/CC UCI/CC KI/CC KI/CC KI/CC UCI/CC t8/HR IQ/HR X DEGF DE6F IFGF DEGF DEGF DEGF GINNA STATION TIme: 0715 Message: 2 1993 EVALUATED EXERCISE MESSAGE FORM Mh i keg""et ylj i Pp 1 dt ig replacement. Simula ed Plant Conditions; See Attached Mini-Scenario ~essa<ee: "<<" THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate actions are simulated or investigations are conducted. Antici ated Results: 1)As per Mini-Scenario. ROCHESTER GAS AND ELECTRIC GINNA STATION 1993 EVALUATED EXERCISE MINI SCENARIO TITLE: "B" Safe In'ection Pum Ou board Bearin Re lacement.Scenario expected start time: 0715 INITIAL CONDITIONS: "B" Safety Injection Pump is held in accordance with"A" procedure A-1401.Bearing is disassembled, with shaft cleaned up for new bearing installation. Bearing obtain from inventory control"QA" storage.METHOD OF INITIATION: Start of work day crew begins preparation to replace bearing on pump, lubricating new bearing in Machine Shop.INDICATIONS: CONTROL ROOM: Trouble card submitted by RST on pump high vibration readings during PT-2.1Q (Safety Injection System Quarterly Test)~Machine shop initiated work package for outboard bearing replacement on"B" safety injection pump.EXPECTED SEQUENCE OF ACTIONS: Machine Shop crew will start work for day on bearing assembly at 0730 Bearing will be reinstated per M-11.12.1 (Safety Injection Pump, Mechanical Inspection). After completion of maintenance RST to conduct test.Pump returned.to service after test completion 24 hours from scenario start.REPAIR TIME: Bearing installation will take 8 hours to complete after crew renews work, before given to RST to test.FINAL CONDITIONS: Pump bearing in final stages of reassembly. Time: 0715 Message: 3 GINNA STATION 1 93 EVALUATED EXERCISE MESSAGE FORM M t i ling"BeCt gigPPPI gRpl Simulated Plant Conditions: See Attached Mini-Scenario ~Messs e: '""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate actions are simulated or investigations are conducted. An ici ated Results: 2)As per Mini-Scenario. ACTIVITY: GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO"B" Char in Pum Plun er Re lacement.Scenario expected start time: 0715 INITIAL CONDITIONS: The pump was held yesterday=for* repack of plunger due to leakage requirements. The replacement of the spare repacked plunger assemblies is 50%complete, repacked units need to be installed. METHOD OF INITIATION: Normal work day start will have the machinist on the job as initial conditions for exercise.INDICATIONS'ONTROL ROOM'uxiliary Building, Auxiliary Operator reported excessive leakage on the pump two days ago and a trouble report written for the Machine Shop to repack the"B" Charging Pump.Hold request and work order for machine shop have been processed to repack the pump.LOCAL: Operator when calculating leakage from the charging pumps determined the"C" charging pump leak rate was high and a trouble report was written against the pump.EXPECTED SEQUENCE OF ACTIONS: Work crew from the Machine shop was removed from this job to help change the bearing on the"B" Safety Injection Pump.Work order is active and SWP for task is active, pump is disassembled and needing spare plunger placed in the pump and torqued down, REPAIR TIME: When a crew returns to the task it will take 6 hours to complete the pump to restore to service.FINAL CONDITION: Pump is in some state of repair, not completed at conclusion of Exercise. Time: 0730 Message: 4 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM.MMMf'.8 I<<c IR Simulated Plant Conditions: See Attached Sheets~ll/lessa e:<<<<"THIS IS AN EXERCISE"""'loud bang is heard outside the Control Room door to the Turbine Building.'nnunciator I-27 (Rotor Eccentricity or Vibration) alarms.FOR CONTROLLER USE ONLY Controller Notes: 1)Simulator Control Room Controller to bang door just prior to the simulator operator starting event.Antici ated Results: 1)Operators should perform the actions of AR-I-27 and transition to AP-Turb.3 (Turbine Vibration) and perform the actions of tripping the turbine as vibration on¹6 bearing is higher than the trip criteria of 14 mils.2)Operators should transition to E-0 (Reactor Trip or Safety Injection) and perform the applicable actions and then transition to ES-0.1 (Reactor Trip Response)and perform its applicable actions.3)Operators should send an Aux'iliary Operator out to check the main turbine-generator. 1993 EVALUATED EXERCISE Time:~O~O A.RUNNING UNLOADED OOS B.RUNNING UNLOADED STBY OOS TSC RUNNXNG UNLOADED OOS Security RUNNING UNLOADED STB ENGINEERED SAFEGUARDS OOS Aux.Feedwater Pum s 1A.INSERV B OOS 1B.INSERV TBY OOS Turb.Driven INSERV TB OOS CST Level FEET MAZOR PARAMETERS Reactor Shutdown YES 0 N-31 CPS N-32 CPS N-35 AMPS N-36 AMPS Avg.Nuclear Power~I RCS Pressure PSXG PRZR Level~3 A RCP UNNIN STOPPED B RCP RU N/STOPPED 1A S/G Level 1B'S/G Level 2 1A S/G Pressure 70 PSIG 1B S/G Pressure 6 PSXG Turbine/Generator ,ONLIN OFFLINE 4 KV Buses NERG Z/DEENERGIZED 480V Buses E 1ZE/DEENERGIZED DC Batteries A~t VOLTS B)REVOLTS Cnmt Pressure o 2~PSIG Cnmt Sump A Level Na I FEET Cnmt Sump B Level XNCHES o Loop Hot Leg G'F A Loop Cold Leg A'2'F B Loop Hot Leg Oa OF B Loop Cold Leg'F RVLIS*CET~~'F S/G A Total Aux FW Flow D GPM 9/G B Total Aux FW Flow~GPM DIESEL GENERATORS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 GPM FI-925 G'P 1A.INSERV TB OOS 1B."INSERV STBY 0 1C.INSERV TB OOS BAST Level=Low Head S.I.Pum s FI-626 C3 M 1A.INSERV TB OOS RECIRC 1B.INSERV STB OOS RECIRC RWST Level=Containment 8 ra Pum s FI-931A~GPM FI-931B~GPM 1A.INSERV T OOS 1B.INSERV STB OOS NaOH Tank Level=Containment Recirc Pans 1A.NSERV STBY OOS 1B.INSERV STBY OOS 1C.INSER STBY OOS 1D.IN RV TB OOS Post Accident Dampers OPEN CLOSED Service Water Pum s 1A.RV STBY OOS 1B.SER STBY OOS 1C.STBY OOS 1D.INSERV TB OOS A&B Header Pressure k PSIG Com on'en oolin Water Pum s 1A.NSERV STBY OOS 1B.INSERV TB OOS Surge Tank Level=~Q Standb Aux.Feed ater Pum s 1C.INSERV TB OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples NOV 17>1993,07l28 R E 6 1(>:lA SIMiULATQR TREtlD GRQU ASS!6)>'Mit(T StU>>t(ARY PAGE 1 GRQLPl EVENT!PROCEDUR":: EPfP 1-5 PLAt(T STATUS 2 3 4 5 6 7 8 t 10>1 t'2>A 15 Ib 17!8',70 21 2d 26 r>/28 29 30 31 32 33 3'i 35 36 37 38 39 40 43 44 t5 46 47 48 49 50 5'i 52 POItlT fD ASS RXT N31 N32 N35 tl36 NP PRCS LPI>%FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PS68 GcENBKRl GENBKR2 BUS11A BUS118 BUS!2A BUS!28 811A!2A 8118128 PCV LS(IPA L0942E L0943E L0942D L09439 L0942C L0943C L09428 L09438 L0942A L0943A T0409A'0410A T0450 T0451 TAVGAI(ID TAVGB)tfD TCCORE FAUXF(lA FAUXFMB BKROB!BKR082 V3r"5 V3504 DESCRIPT I Qtl AtlTIC!PATED TRANSIENT)t/0 SCRAt(REACTOR TRIP BREAKER STATUS SQ(PCE RAt(GE DTECTGR hl-31 SGLtRCE RANGE DETECTOR tl"32 INt"RtlcDIATE RANGc DcTECTOR N-35 ItlTERMEDIATE RANci DiTECTGR tl-36 At>ERASE NXLF4R PG'ilcR RcA"TOR CQQLA!(T SYSTEM NG PRESS PRESSLRIIER AVERAGE LEV=L REACTOR COOLANT LO>GP A AVG FLON RiACTGR COOLANT LGQF 8 AVG FLOW RC>..<<.PREAKER CAUSE RX TRIP RCPB B>tEAKER CAUSE RX TRIP ItloDRE TC SUBCOQLED MARGItl STii Gil(A NARROW" RANGE AV6 LEVEL STM GEN 8 tlARROW R4tlGc NG LEVEL STM Gitl A AVERAGE PRESSURE STM Citl 8 AV"RAGE PRESSURE GitFRATQR ON LINE BRiAXFR 161372 Gc>>ERATQR Otl LINEB>REAKER 9X!372 BL(c l!A SLtPPLY BREAKER BUS!18 SUPPLY BFiEAKER NOT TERMlt(ATED 0)t FPCS (7/19/91)iNOT TERMINATED Otl PPCS (7/;9/91)BUS 1!A TC 12A T!E BRcNER BUS 1fB TQ 128 Tfi BREAKER CO(P>AINMit(T AVERAGE PRESSURE CGNt A!NMEt!T S>Ji"iP A At/ERASE LEVEL St&'LEVEL 8 It>CHcS (TRAitl A)SNF 8 LEVEL 8 INCH 8 (TRA!tl 8)SU"P 8 LEVEL 78!NCHES (TRAItl A)S(t~8 LcVEL 78 fNCHcS (TRAItl 8)SU>P 8 LEAL 113 ItlCf:cS(TRA!tl A)SIP 8 LEVEL 113 it.HES(TRAItl 8)SU~8 LEVcL 160 It>CHES(TRAltl A)SLttP 8 LEVEL 180 ItZHES(TRAIt(8)SUNUP 8 LEUcL 214 ItlCHES(TRAIN A)SU>~8 LEVcL 214 Itl".HES(TRAItl 8)RCLA HOT LEG TEMPERATURE RCLB HOT LEG TEMviRATUPcE RiLA COLD LEG TE)>FERATURE RCLB COLD LE6 TEt(FEFATlRE RCLA TAVG (T),"OT/TCGLD WIDE RNS)Rl+Z TAVG (THQT/TCOLD >>>IDE RtlG)RJC OR VESSc'UERASc 'V L Ei.l itlCOFc TC AVERAGE TEMP S/6 A:OTAL AtUX FEED"AT":R FLO((S/G:"":GT4t AUX FEc9y>TciR FLQ'A MTR At.tXILIARY FEEL;.>ATicR PLiMP P MI R AUXILIARY FEEE4AIER FL0'iP 8 AUX.cw PU"F STEAlt SUPPLY VALVi A AUX.4>PUMP STEA)l SU PLY VALVc 8 C-,"F OFF Ct 0SED CLGci9 VALUi QUAL NO AT4S GOOD tlQT TRIP C~aQD 1.00000+00 It(HB l.00000<00 it'HB 8.12829-04 INHB 8.!2829-04 ItlHD 98.09 6009 2248.GOOD 48.3 6009 98.1 KQD 97.3 GKD tiGT TRIP KQD tlQT TRIP 6001)47.4 KQ>>52.1 GOOD 52.1 GOOD 701.GOOD 701, 6009 NGT TPIP 6009 tlQT TRIP GGQD tlQT TRIP GOOD NQT TRiP 6009 tlQT TRIP DEL NOT TRIP DEL TR!FPiD KQD TR!FPED 6009.26 GQQD 2.1 6009 LG)>ER KOD LOVER 6009 LGtlc&6009 LQ)tER CO>09 LO)>ER 6009 LG)'ER 6009 LO"ER KQD LONER 6009 LG)>ER GOOD LONER 6009 601 F 1 GOOD 601.1 6GOD 544'GQ>09 544.1 6009 572.7 KQD 572.6 GOOD 99.1 6009 600.6 600>>O.GGQD 0.6009 GQQD GQQD GGQD KQD E.U.CPS CPS ANP/PSIG>//X DE6F/PSIG PSIG PSIG FiET DEGF KGF DEGF DcGF DEGF 9"6F DE6F GPM GPM NV 17'993 07>: R.E.City SItIL&TQR TREt8 GROJ" ASSIGN)tEttT SUi"GAMY PAGE 2 GROUP: E)EttTI PROCEDL'RE: EPIP 1-5 FiN<T STATUS POIttT 19 DESCRIPTIOtl VALUE CUAL E.U.FSIA 54 F BIB 55 P2 150 56 P 2161 57 BNR041 56 NR042 So BVR043 50 IIR044 Sn,=STY It(.'ECTIOti'OOP A AVG FLN SP""TY It)3ECTION LOOP B AV6 FLOW SERVICE t'ATER PUMPS A 6 B HEADER S""%ICE RATER PUllFS C L D F""ADER 6""RVICE@TER PutP A SERV:CE t ATER Pur~B SERV1CE HATER PUtiP C S=RV!2 MATER PUttP 9 ON Ot'i<0&%0.0.84.75.6009 GPt1 6009 GPN GOOD PSIG 6009 PSIG GOOD 6009 GOOD 6009 t(OV 17<1993 07;29, R c 6 it<RA 8INULATOR TR~t<<9 GRGsJP ASSIGttNEhT PJN<ttARY GRO()P.'FVcNT2 PROCEDUR""l EPIP 1-5 PLAttT STATUS 1 2 3 4 5 6/8 9 10 i?<>>13 14!r~>><16 j7 ie>24 25'?6'?/28 29 30 3!u>>33 36 37 38,!b 40 4}42 43 POlttT ID F0619 LRWST ttS 033 M9033 WT033 MT250 NDT2 R01 R02 R05 R09 R34 R35 R10A R}1 R}2 R108 R13 R}4 R}8 Ri'9 R29 R30 R}5 R}2A5 R}2A6 R}2A7 R}2A9 R}445 R}4A7 R14A9 R}5A5 R}5A7 R}5A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV}0 TCV17 OESCRIPTIRt CO~GNEtti COO': IttG LOOP TOTAL FLW RE 0='NG VATER STORAGE TA)C LVL 33 FOOT LEVEL WlttD SPccD 33 FOOT LEVEL ttlttD DI!scCTIOtt 33 FOOT LEVEL TBPERATURE 250!QOT LEVEL TENPERA7JRE 250 TO 33 FOOT LEVEL DELTA TEt!J'REA}-CQt(TROi ROON AREAs 2-COttTAIttNE!ti AREA 5-SPENT FUEL PIT AREA 9-LETDQN L!tsc NOÃITOR AREA 34-AU)(BLDG CV VRN PUNP Abc/-;35-PASS SANPLE PAPL COttTAIt<Et(T IODINE NOttITOR R}OA CC4<tlAI ttiNiENT AIR PART ICL>ATE CGltTAItiNEt(T GAS tiGttITGR PLOT VEtti IODINE NGttITOR R}09 AUK B: BG E)(HAUST AIR PNTICU!ATE AU)(O'G EM@ST CAS t'MTOR LIKIID t(ASTE DISPOSAL NO!tITOR STc-"";GEttERATQR BLNBQ!~".t DRAIN AREA 29-CG<<tTAIttt(Ettl HIGH RANK AREA 30>>CO!tTAIt<f=ttT HIGH RAts'c CCCr/EttSER AIR EJECTOR EXHAUST CV VEtsi Ct!Jst'"LG) RA'l~CAS CV VE!.<CHAN 6"AREA GN"A CV V t<T CRAtt 7-MID RA!iGE GAS CV V=NT CHAit 9-HIGH RÃE GAS PLktT VEttT CHAN 5-LQ'O'A!i'.E GAS FLNli's!EttT CHA<Y 7-NID RANGE GAS PL@.V<Vi CHAtt 9-HIGH RPJtGE GAS AIR=JECTOR CHAN 5-LOn'A'<GE GAS AIR EJECTOR CHAN 7-NID RAttGE CAS AIR EJECTOR CHAN 9-HI PAlt<uE GAS AP""-"..3} STEANi LINE A (SeittG)AREA 32 STFAN LItic 8 (cbitt6)CV H'(DROGEtt CQ<<CEttTRATIGtt C'/BASENE!ti LEVEL 6FT TEt<P tt3 CV lttTERNEDIATE LVL 6cT TEt&t!7 CV It<TERNEDIATE LV!6FT TEt<<P 48 CV Il)TER¹DIATE LVL 6FT TENP t!9 CV It<TERNEDIATE LVL b T TcNb tt}0 CV QPERATI!(G LEVL bF!!ctP 0}7 VA<LLrE 1427.94~5 5.1 317>>43.8 43.1-7 8.75992-02 4.75882~00 3,09030-01 2.75423<0} }F 01742+00}.09648~00 1.69093+02 1.60 55+02 2.63785~02 8.23426<00 2.55932+02 5.527}2~0} 1.05925>03 2.00678+03 9.75130-01 9.75130-0} }.46428>03 4,205}1 05 2,67992?-02 4,20511-05 9.99987"04 2.JO991,"06 4.62984-06 9.}0997-04 6.2'?985-06 }.80975-05 1.52999-03 1~01004-02 1.01004-02 .0 68.7 LALN 6009 GOOD 6009 KQD 600D GOOD GOOD GOOD 6009 GGQD 6MD G009 GOOD 6009 GOGO GOGO 6009 GOOD GOOD GOOD 6009 GQOD GOOD GOOD GOM GOOD 6009 6009 GOOD GOOD 6009 GOOD 6009 GOOD GOOD 6009 6009 81.6 GQQD 81.6 GOGO 81.6 GOOD 8!.6 GOOD 94.4 E.U.GPN>>/ttPH DEG.DEGF, DEGF DEGF NR/HR NR/HR NR/HR t8/HR ta/HR NR/HR CPN CPN CPN CPN CPN CPN CPM CPN R/HR R/HR CPN UCIICC N/HR UCI/CC XI/CC UCI/CC XI/CC UCI/CC Xl/CC UCI/CC XI/CC YR/HR%/HR I DECF DEGF DcGF DEGF DEGF DEGF Time 0730 Message: 5 all~N NT Tl~1 9 EVALUATED EXER I E MESSAGE FORM A ill Egg<<<<k<<gl-g Simulated Plant Conditions: See the Attached Mini-Scenario ~Meaaa e: """TH)S lS AN EXERCISE+"" FOR CONTROLLER USE ONLY Controller Notes: E 1)Provide information verbally when appropriate actions are simulated or investigations are conducted. Antici ated Results: 1)As per Mini-Scenario

GINNA STATION 1993 EVALUATED EXERCISE MINI SCENARIO TITLE: he kin T rbine n r r nois n vibr ion roblem.Expected Scenario start time: 0730 INITIAL CONDITIONS: Turbine generator on line.IVIETHOD OF INITIATION: A loud bang is heard outside the Control Room door.Control Room requests that Auxiliary Operator check out the Turbine Generator for abnormalities. INDICATIONS: CONTROL ROOM:~Alarm window I-27"Rotor Eccentricity or Vibration"~Bearing vibration indication ~A turbine blade has penetrated the¹2 LP turbine casing at its southeast corner and is lying by the Control Room door.~Sound of air rushing into condenser through the penetration. ~Feel of turbine generator vibrating EXPECTED SEQUENCE OF ACTIONS'Investigate Turbine Generator for signs of abnormalities ~Notice penetration of turbine casing.~Notice turbine blade lying by Control Room door.~Notice turbine generator vibrating. ~Notice sound of air rushing into condenser through the penetration. ~inform Control Room of findings no la er than 0740.FINAL CONDITIONS: Turbine Generator is tripped and comes to rest and all condenser vacuum is lost. Time:~732 Message: 6 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM 8 I C I R Simulated Plant Conditions: ~Messa e: """THIS IS AN EXERCISE"""'Annunciator F-21 (Cond Hl Press 20" Hg or Loss of Both Circ Wtr Pmps)alarms FOR CONTROLLER USE ONLY Controller Notes: 1i~Wh n operators check condenser vacuum, inform them that it is 19" and decreasing, Antici ated Results: 1)Operators continue to perform the applicable actions of ES-0.1. Time: 0740 Message: 7 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~M: M I<<R IR Simulated Plant Conditi ns:~ll/lessa e: """THIS IS AN EXERCISE">>>>Auxiliary Operator checking the turbine generator informs Control Room of conditions er mini-scenario messa e¹5 b 0740.FOR CONTROLLER USE ONLY Controller Notes: 1)Auxiliary Operator sent out to check the turbine generator must report his findings to Control Room by this time (i.e.0740).Antici ated Results: 1)Operators should be performing the applicable actions of ES-0.1 (Reactor Trip Response)~2)An ALERT should be declared in accordance with EPIP 1-0,"Ginna Station Event and Evaluation and Classification," EAL:Hazards Being Experienced or Projected; Turbine Blade Failure which Penetrates the Turbine Casing. ~Time: 0745 Message: 8 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~NI: 8 I C<<IR Simulated Plan Conditions: See the Attached Sheets Messacee: """THIS IS AN EXERCISE">>>>FOR CONTROLLER USE ONLY Antici ated Results: 1)Operators should be performing the applicable actions of ES-0.1 (Reactor Trip Response). 1993 EVALUATED EXERCISE Time: 697&MAZOR PARAMETERS YES NO~SCPS~~~CPS~e~/AMP S ANPS~$2.PSXG~iO 4 UNNING STOPPED UNNIN STOPPED~20.9~Z.2.PSIG D/PS G FFLIN ERGI DEENERGIZED ERGIZE DEENERGIZED OLTS B~lo VOLTS~2PSIG~FEET INCHES ZQ2 F'F~E~'F~TI 20.F~b~~2'F Flow~~GPN Flow~~GPM Reactor Shutdown N-31 N-32 N-35 N-36 Avg.Nuclear Power RCS Pressure PRZR Level A RCP B RCP 1A S/G Level 1B S/G Level 1A S/G Pressure 1B S/G Pressure Turbine/Generator 4 KV Buses 480V Buses EN DC Batteries A Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level Loop Hot Leg A Loop Cold Leg B Loop Hot Leg B Loop Cold Leg RVLIS*CET S/G A Total Aux FW S/G B Total Aux FW DIESEL GENERATORS A.RUNNING UNLOADED 8 OOS B.RUNNING UNLOADED BY OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED STB OOS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 GPM FI-925~GPM 1A.INSERV TB OOS 1B.INSERV STBY OS 1C.INSERV STB OOS BAST Level=Low Head S.X.Pum s FI-626GPM 1A INSERV OOS RECXRC 1B.INSERV TB OOS RECXRC RWST Level=Containment S ra Pum s FI-931A O GPM FI-931B~GPM 1A.INSERV B OOS 1B.INSERV TB OOS NaOH Tank Level=Containment Recirc Pans 1A.SERV STBY OOS 1B.STBY OOS 1C.SER STBY OOS 1D.XNSERV STB OOS Post Accident Dampers OPEN CLOSED Service Water Pum s 1A.NSE STBY OOS 1B.ERV STBY OOS 1C.SERU STBY OOS 1D.XNSERV TB OOS A&B Header Pressure~5 PSIG Com onen olin Water Pum s ENGINEERED SAFEGUARDS Aux.F water Pum s 1A.INSER STBY OOS 1B.NSERV STBY OOS Turb.Dr1ven INSERV STB CST Level 2 SO FEETOOS 1A.SERV STBY OOS 1B.XNSERV TB OOS Surge Tank Level=,~W 4 Standb Aux.Peedwater Pum s 1C.XNSERV TB OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples I NOV f7(1993 07:44 R.E, GitW4 BI("ULATOR TREt(D GROUP ASSIGN"(ENT PJt(("(ARY PAGE 1 GRP~~: EVENii PRGCEDURc: EPIP 1-5 PI.ANT STATUS 2 3 5 6 7 8!0 (Q>>~f3!4 15!6 17!8 20 21 22 23 24 26 (7 29 30 31 32 33 34 35 36 37 38 39 40 41 43 44 45 46 47 48 49 50 51 52 Polt(T ID AT)S RXT t)31 t]32 N35 N36 N, PRCS LPIR FRC'FRC'RXT!6 RXT!7 TSUBTC LSGA LSGB PSGA PSGB GEtSKR GEt(BKR2 BUS!1A BUSlfB BUS!2A BUS!2B B!1A!2A Bl!B!29 PCV LB(@PA).094 2i L0943E L0942D L09439 L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGA))ID TAVGBNID LRV TCCORE FAUXFNA FAUXF((9 BKR081 BKR082 V3505 V"504 DESCRIPTION ANTICIPATFD TRANSIE)IT W/0 BCRAN ROTOR TRIP BREAKER STATUS BPJRCE RAIIGE DiTECTGR t>>-3!SOURCE RANGE DETECTOR ti(-32 It)T" R)FDIATE RANEE DETiCTOR N-35 It(TER)'cDIAT" RANEE DETECTOR t(-36 AVERAA NUCLEAR PGA"R REA".TGR COMIT SYSTEN AVG PRESS PRESSURIZER AVERACE LEVEL RECTOR COOLANT LOOP A AVG FLOiA RcACTOR CGGLAVi LOOP B AVG FLG((RCPA BREAKER CA(J":E RX TRIP RCPB BREAKER CAUSE R)(TRiP It(COPE TC SUB"GOLED tlARGIN STtf Git(A NARRON RANCE AVG LEVFL STt)GEN B t(AKA RA)t.i AVG LEVEL STi(Gitt A AVERAGE PREBJRE SW G=N B AVERAGE PRESSURE GitFRATOR GN Lite BREN(R 161372 GEN'.RATGR GN LINE BREAKER 9X!372 B(J.!!A SUPPLY BREAKER BUB f!B SUPPLY BREAKER NOT TERt(IN4TED ON PPCS (7/19/'?1) NOT TERNINATED Gtt(PFCS (7/!9/91)EUB ilA To!24 TfE BRBZER BUS'.lB To f2B TIE BRENER CGNTAINNENT AVERAGE PRiSBURE CONI'AINNENT BUt(P A AVER46E LEVEL BSP B LEVEL 8 INCHES (TRAIN A)SUN B LEVEL 8 INCHES (TR4IN 9)SU~B LEVEL 78 ft("HES (TRAIt)A)SU@'LEVEL 78 IN."HEB (TRAItt B)S(~>>" B LEVEL 113 INCHES(TRAIN A)BUN B LcYEL 1!3 INCHES(TRAItt B)SUN 8 LEVEL 180 Iti'CHES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIti 8)BUN B LEVEL 214 It(CH"S(TRAIt(A)S'J~(F'LEVEL 214 INCHES(TRAIN B)RCL4 HOT LEG TE)(PERATURE RCLB HGT LiG TEt)PERAT(IK~. RELA COLD LEG TEttPERATURE RCLB COLD LEG TE)(PciRATURE RCL4 TAVG (TENT/TCGLD NIDE RNG)RCLB TAVG (THOT/TCGLD 'AIDE RNG)REACTOR VESSEL AYERAGE LEVEL Ef.i It)CORE TC AYERAGE TEi".P S/G A TOTAL AUX FEiDNATER FLG((S/6 B TOTAL AUX FEEDNATiR FLON t(TR AUXILIARY FEEDMATER PUt(P A NTP.AUXILIARY FEED(PATER PiNP 9 AUX P>>)PUN'TEAN SUPPLY VALVE A AUX FW PUil STEA)f BUFPLY VALVE B ALRt(ALRN 6009 6009 6009 GM9 6009 GMD 6009 Goon 600D 6009 Goon 600>>LNRI(1022.GM9 1019.6009 TRIPPED TRIPPED TRIPPED TRIPPED t)QT TRIP NOT TRIP NOT TRIP NQT TRIP ,24 2,f LONER LONER LONER LONER ALRt(DEL ALRi"(6009 GX9 Goon GOOD LONER LONER LQNER LONER LONifi 551'GOOD GOOD 6009 Goon 551.9 6009 550.4 Goon 550.2.Goon 55!.2 551.1 99.2 551.7 163.171.GN ON CLOSED CLOSED, 6009 Kon 600>>GO09 GOOD GO09 coon 6M9 VRL li ATNS RX TRIPPED!.27057+N 1.27497+04 3.41977-11 2.96481-ff .00 2!32.25.0 97.1 96.3 t(OT TRIP NO.TRIP 93.9 20.4 21~6 E.U.CPS CPS ANP fk":P/PSIG///DEGF/\/PSIG PSIG PSIG FEET DEGF DEGF DEGF DEGF DE6F DEGF DEGF GPI(GPtf NOV 17~1993 07'.44 R.E.Gi@lA SItkiLATOR TREND GROUP ASSI Gtt~+EttT SUtlNRY PAGE 2GROUPS EVENT1 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P2160 56 P2161 57 ECR041 58 BKR042 59 BKR043 60 BttR044 DESCRIPT I C4 SkcETY INJECTION LOOP A AVG FLOW SUETY INJECTION LOOP 8 AVG FLOW SBNICc WATER PUtFS A Iti 8 HEADER SJPICE WATER PUttPS C h 9 HEADER SERVICE WATER PUtiP A SERVICE WATER PUttP 8 SERVICc WATER PUNP C SERVICE WATER PUNP D VALL'E Otf ON ON OFF 0.0.84.75.KAL E.U.6009 PN GCCD GPtt 6009 PSIG 6009 PSIG 6009 600D G009 6009 hGV 17i 1993 07:45 R.E, GINA slril" ATGR TRFND GROUP AKIGVBfT SUN)(ARY PAGE BROLLY" EVit'T2 PROCEDURE'PIP 1-5 PLANT STATUS POItJT ID DEKRIPTI 0W VALUE QUAL E.U.1 2 4 5 6 7 8 9 fn 11 lg lw 13 14 15 i7 18 19 20 2f 22 23 25 26 27 28 30 31 3r>33 34 35 36 37 38 39 40 43 F0619 LRNST NS033 89033 iAT033 WT250 MDT2 Rnl 802 R05 R09 R34 R35 R10A Rfl R12 RlOB R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 Rf2A9 R1495 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 Tcv08 Tcv09 TCV10 TCV17 CGtl-'GtliNT CODLING LGG?TOTAL FLW REFT fNG WATER STORAGE TA)JK LVL 33 FQQT LEVE'IND SPEED 33 FOOT LE&it N?tJD DIRECTION 33 FGGT LEVEL TENPERATURE 250 FOOT LEV=i TBu"ERATUR 250 TO 33 FOOT LEVci.DELTA TEriP AR="4 I-CONTRO: RR ARcEA-CEJTAINtJENT AREA 5-SPFNT FUEL PIT AREA 9-LETDGRI LINE riG)JITOR AREA 34-AU)(BLDG CV PRAY PUriP AREA 35-PASS Sk"i?LE PAttiL CGi%'AIN<SNT IODIJJE tiGNITGR R10A CO;~VAieaJT AIR PARTICt!ATE CGNTAINt(ENT GAS riGtJITGR PLNT VENT IODINE-MONITOR R109 U)(BLDG EEHPdST AIR PNTICUl ATE AU)(BLDG E)(MAUBT GAs ripJITGR LIQUID hAST DISPOSAL ICiJITOR STEAN GBBATOR BL1:i>PJ DRAIN kRcA 29-CGNTAItJNENT HIGH RAtKE AREA 3i)-CQ'iiJTAI tJi'lit(T HIGH RANGE CONDENSER AIR EJECTOR E)(HAUST CV VENT CHAtJ 5-LGW RA)JGE GAS CV VENT C)LAJJ 6-AREA GAYi"iA CV VENT CHAW 7-ttID RANK GAS CV VitJT CHAN 9-HICH RID'JE BAS PLANT VENT Cl(AN 5-LGit RAtlGE GAS PLA!JT VEti'1 CHAti'-t'ilD RAtJGE GAS PLA!JT Vit(T CHAN 9-HIGH RANG 6AS AIR EJiCTGR CHA)J 5~0ÃRAtJCc GAS AIP, iJECTCR CHAN 7-HID RANGE GAS AIP.EJECTOR D(Atl 9-HI RANGE GAS AREA 3f STEAil LINE A (BRING)A%A 32 STEAN LItE 8 (6?Its)CV H'$9RQGcEN CQtcCEt(TRATION CV BASPiitiT LcVEL 6FT TEN?03 CV IhTERNEDIATi LVL 6FT TEt(P tti CV INTERNiDIATE LVl 6FT TEt(P J(8 CV INTERi"iEDIATE LVL 6FT TEt(P JJ9 CV INTiRI'iEDIATE LVL 6FT TEri?Jtfn CV OPERATIC LEVL EFT TEtl?ttf7 LALri G009 6009 6009 6009 BC'609 6009 G009 GGQD 6009 6009 6009 GQGD GGQD GOOD 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 G009 6009 6009 K09 GQQD 6009 82.0 6009 82.0 6009 82,0 82.0 93.5 6009 6009 GG09 1438.94.5 5.2 317.43.8 43,1-7 8.81048-02 4.75882%0 3.14412<1 2.75423%f 1.02920~00 1.09648+00 1.69093t02 1.57806+02 2,59268q02 8.23426+M 2.48313+02 5.64774%1 1.01888+03 2.00678+03 9.751 4-01 9.75130-0f 1.45797+03 4.205f1-05 2.67992-02 4.20511-05 9,99987-04 2.30991-06 4.62984-06 9.10997<4 6.22985-06 1.80975-05 1.52999-03 f.01004"02 1.01004-02 .0 70.7 Ptf MPH DEG.DEBF DEGF DEGF ts/HR t(R/HR ts/HR N/HR ts/HR N/HR CPN CPtf C?tt CPtt CPN CPtf C?tt CPtt R/HR R/HR CPtt XI/CC ts/HR UCI/CC XI/CC XI/CC UCI/CC XI/CC XI/CC XI/CC XI/CC ts/MR N/HR 7.DEGF DiGF DEGF DE6F DLGF DEGF Time: 0755 Message: 9x GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORIVI~f: Si I<<C<<IR Sp i/E 1 YC di Simulated Plant Conditions: ~Messa e: """THIS IS AN EXERCISE""" Declare an ALERT in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification", EAL: Hazards Being Experienced or Projected; Turbine Blade Failure which Penetrates the Turbine Casing.FOR CONTROLLER USE ONLY Controller Notes: t l Deliver only if an ALERT has not been declared.Do Not deliver if amer enc classification discussions are in ro ress.Antici ated Results: 1)Deliver contingency message if alert not declared or is not being discussed. Time:~OI~O Message: 10 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORIVI MMM t: 8'<<C<<I R Simulated Plant Conditions: See Attached Sheets~Meaaa e:<<<<"THIS IS AN EXERCISE>><<<< FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1)Operators, should be performing the applicable actions of ES-0.1 (Reactor Trip Response). 1993 EVALUATED EXERCISE Time: QPOG MA JOR PARAMETERS Reactor Shutdown~YES NO N-31 Z2$CPS N-32%le CPS N-35 I~O/-AMP 5 N-36/~~IAMPS Avg.Nuclear Power RCS Pressure PSIG PRZR Level A RCP NX STOPPED B RCP RUNNIN/STOPPED 1A S/G Level 1B S/G Level~a~o 9 1A S/G Pressure/0/8 PSIG 1B S/G Pressure O 5 PSXG Turbine/Generator NE FFLIN 4 KV Buses ENERGIZE DEENERGIZED 480V Buses NERGIZED DEENERGXZED DC Batteries A~OVOLTS BUBO VOLTS Cnmt Pressure o~<QPSIG Cnmt Sump A Level G/FEET Cnmt Sump B Level INCHES A Loop Hot Leg'F A Loop Cold Leg 5I.'F B Loop Hot Leg Std&OF B Loop Cold Leg.5'F RVLXS*CET~06 OF S/G A Total Aux FW Flow~6 9 GPM S/G B Total Aux FW Flow~~GPM DIESEL GENERATORS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED S B OOS TSC RUNNING UNLOADED TB OOS Security RUNN NG UNLOADED STB OOS ENGINEERED SAFEGUARDS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 C>GPM Fl-925 H GPM 1A.XNSERV T OOS 1B.XNSERV STBY 0 1C.INSERV TB OOS BAST Level=Low Head S.I.Pum s FI-626 PM 1A.INSERV OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s FZ-931A~GPM FI-93 1B C'PM 1A.INSERV OOS 1B.INSERV TB OOS NaOH Tank Level=~4 Containment Recirc Fans 1A.NSER STBY OOS 1B.ER STBY OOS 1C.NSER STBY OOS 1D.INSERV TB OOS Post Accident Dampers OPEN LOSED Service ater Pum s lA.STBY OOS 1B.SE STBY OOS 1C.ER STBY OOS 1D.INSERV TB OOS A&B Header Pressure PSIG Com onent Coolin Water Pum s 1A.NSER STBY OOS 1B.'NSERV TB OOS Surge Tank Leve Aux.Feedw Pum s 1A.SERV OOS 1B.R TBY OOS Turb.Driven INSERV TB CST Level~baaLFEET OOS Standb Aux.Feedwater Pum s 1C.INSERV OOS 1D.INSERV B OOS*CET=Average of Selected Core Exit Thermocouples t OY 17 i 1993 07 a gQ R.E.GINNA SIt(ULAT(S TREt(D GROUP ASSIGNtlit(T SUi'L4iARY PAGE GROL'P: EVENT!PRocEKRE: EPIP 1-5 PLANT STATUS 1 2 3 4 5 6 7 8 9 10 12 15 16 17!8 19 20 21 22 23 25 27 28/)9 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 8/48 49 50 POI"(T iD AT(iS RXT N31 t(32 N35 t(36 NP PRCS LPIR FRCLA FRCLB RXT!6 RXT17 TSUBTC LS6A LSGB PSGA PSGB GcNBKR1 GENBKR2 BUS!1A BUS!18 BUS12A BUS128 811A!2A 811812B PCV LM'iPA L0942E L0943E L09420 L0943D L0942C L0943C L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TA VGA))ID TAVBBt(ID LRV TCCORi FAUKFNA FAUXFMB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT W/0 SCRN REKTOR TRIP BREAKER STATUS SOLACE RANGE DETECTOR t1-31 SMCE RAtiGE DcHECTGR ti~32 It)TERiirDIATE RAt(GE DETECTOR N-35 INTER,"~cDIATE RANGc DcTECTOR N-36 A'/ERASE t(UCLEAR PO'wcR REACTOR CGOLNT SYSTEtl AVG PRESS PRESSURIIER AVERAGE LEVcC REA"-TOR COOLANT LOOP A AY6 FLON RFA".TGR COOLANT LOOP 8 AVG FLGiN RCPA BREAKER CAUSE RK TRIP RCPB BRFAKER CAUSE RK TRIP It(CORE TC SUBCOOLED t'ARGIN STtt GEN A ttARROM RAiNGE AYG LEVEL STN GEN 8 t(ARROW RANGE AYG LEVEL STt(Git(A AVcRAGE PRESSURi STtt GEN 8 AVERSE PRESSURE GiiERATOR ON LINE BREAKER 1G137 GitFZATGR GN LIiNE EREAKFR 9K!372 BUS!!A BLPPLY BticAKER BUS!!B SLiPPLY BREAKER t(OT!ERt(lt(ATED Ott PPCS (7/!9/91)NOT TERttlt(ATED Ott PPCS (7/19/91)BUS 1 lA TO 12A TIE BRcENER BUB 118 TG 128 TIE BRBNER Cot(TAIt(t(ih7 AVcRAGE FRccSURE CQ'(TAINNENT BJt(P A AYERACE LEVEL BUYi 8 LEVEL 8 INCHES (TRAIN A)Uii&LEVEL 8 INCHES (TRAIN B)BEP 8 LEVEL 78 INCHES (TRAIN A)BEP 8 LEVEL 78 ItlCHES (TRAIN 8)SU."P 8 LEVEL 113 INCHES(TRAItt A)SU%8 LEVEL 113 INCHES(TRAIN 8)PJ~i 8 LicVEL 180 IWCHEB(TRAIN A)BUi~8 LEVEL 180 INCHEB(TRAIN 8)SU(P 8 LcYEL 214 It(CHES(TPAIN A)SUYL-'LEVEL 214 INCHES(TRAIN 8)RCLA HOT LEG TEt(PERATK RCLB HOT LEG TEtlPEc RATUR RCLA Coi 0 LEG Tct(PiRATURE RCLS COLD LEG TBlPBQTLRE RCt A TAVG (THOT/TCOLD l'IDE Rt(6)RCLB TAVG (THOT/TCOLD MiDE RNG)RFA".TGR VESSci AUiRAGE LEVEL El,i IN"ORE TC AVERAGE TEt(P S/6 A TOTAL AUK FEEC4ATciPi FLO'A B/6 8 TOTAL NJK FEEDlATcR FLO'A tiTR AUXILIARY FEEDMATER PUlP A NiTR AUXILIARY FEED'iATER PUtP 8 AUK FN PU".,P STEAtl SUPPLY VALVE A AUK.">>t PUt(P STEAN SUPPLY VALVE B C.YALUc QUAL ALRt(ALRtt 600D 6009 GOOD GOOD 6009 6009 6009 C<09 6009 GOOD GOOD 600>>LWt(LNRtt GOOD GOOD ALRt(ALRt(ALRt(ALRtt DEL DEL ALRi"i ALRt(6009 6009 6009 6009 6009 GOOD 6009 6009 6009 6009 GQQD 6009 550.6 GOOD 550.6"6009 549~7 549.3 550,1 550.0 99~4 550,6 163.172.Gft Ott CLOSED CLOSED 6009 GOOD 6009 6009 6009 600>>6009 GOOD 6009 AT))S RK TRIPPED 2.25683e02 2.15030e02 1~04232-11 1,03753-11 .00 s.2't 1~20.3 97.3 96.5 NOT TRIP NOT TRIP 102.2 28.8 29.0'018 1015.TRIPPio TRIPPED TRIP PiD TRIPPED t(OT TRIP tlOT TRIP ttoT TP,IP t(OT TRIP~24 2.1 LoiJER Lot)ER LG)liR LoiAER LONER LONER LG)'ER LO'iER Lot(E LO)lER ED U.CPS CPS NP A%'PSIG//7 DEGF//PBIG PSIG PSIG FEET DcGF DEGF DEGF DEGF DEGF DEGF/DE6F GPM GPH tlOV 17~1993 07158 R.E.GieA SINUATOR TREt6 SOUP ASS!CADENT SUGARY PAGE 2 SOAP;EY""tiTl PROCEOLiR-.-; EPIP 1-5 PLAli'T STATUS POINT 19 BESCRIPT ION 5'A'E OUAL E.U.53 FSIA 54 FSIB 55 P21b0 5b P21bl 57 BKR041 58 Bl(R042 59 8/R043 60 BNR044 SALTY IWJECTIOtt LOOP A AVG FLOW SAFETY INiECTIOtt LOOP 8 NG FLOW SERVICE WATER PUtl?S A h 8 HEA9ER SLUICE WATER RNPS C h 9 HEA9ER SER'PICE WATER PUttP A SERVICE WATER PUltP 8 SERVICE WATER PUP C SER'i'ICE WATER PUttP 8 Ott Ot<ON OFF 0.6009 0.GOOD 84.6OO9 75.GO09 6OO9 COOO GOO9 6609 GPtt PN PSIG PSIG t(GU 1?i 1993 07:58 R.E.Git"(A SINiULATQR PAGE TREND GROUP ASSIGNt(it(T SUNNARY GROUP: EV=NT2 PRQCEDUR":: FPIP!"5 PLAriT STATUS 1 3 5 6 7 8 9 10 11 12 13 14'15 16 17 ie 19 20 22 23 24 QC 26 27 28 30 31 39 33 34 35 36 37 38 39 40 41 42 43 POINT ID F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R!OA R!1 R!2 R!OB R!3 R!4 R!8 R19 R29 R30 R!5 R12A5 R!2A6 R!2A7 R!289 R!4A5 R!4A7 R!4A9, R!595 R!5A7 R!5A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV!0 TCV17 DESCRIPTION CQtPQ)I"t(T COOLING LOOP TGTA'LW RiFU""'ti6 WATER STORACE TAI(X LVL 33 FOOT LEVEL Wit(D SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TE('iPERATURE 250 FOOT LEVEL TENPFPATURE 250 TG 33 FOOT LEVEL DELTA TEt(P AREA I-CONTR(X. ROO'I AREA 2-CONTAIN)IEcNT AREA 5-SPENT FUFL PIT AREA 9-LETDOWN Lit(i NQt>ITGR AREA 34-AUX BL06 CV PRAY PUt(P AREA 35-PASS SAMPLE PAtFL CQNEAlt(NEWT IODINE t(0i"ITQR R1OA CQNTAINNENT AIR PART ICLMTE CONTAIt(NEt(T GAS tfOt(ITOR PLNT VENT IODINE t(Ot(ITOR R!OB AUX BLDG EXHAUST AIR PARTICULATE A1JX BEG EXHAUST GAS NiONITOR LI9.iiD WASTE DISPOSAL tX)NITGR STEAN GENERATOR BLOWDOWN DRAIN AREA 29-CONTAINNit(T HIB{RAh'6" At(ccA 30-CQNTAIt(NEWT HIG)(RANGE CONDENSER AIR EJECTOR EXHAUST CV Viti: CHAN 5-LOW RAN-"'AS CV VENT CHAN 6-AREA GANA CV V tiT CHAN 7 NID RAt&GAS CV VFN;CHAr(9-HIGH RANGE GAS PLNT VEt(T CHAti'-LQW RAt(SE GAS PLNT VENT CHAN 7-NID RANK GAS PLANT VFNT CMAt(9-HIGH RAN6E 6AS AIR E'ECTGR CHAN 5 LGW RPi(6E GAS AIR EJECTQP.CHAN 7-NID RANGE CAS AIR EJECTOR Ct(At(9"Hl RAt<GE GAS AREA 3!STEAN Llh'E A (SPING)AREA 32 STEP~~i Llt(c B (BRING)CV HYDRQGEtk CONCENTRATION CV BASEtIENT LcViL 6FT T="I'iP (t3 CV INiiRNiiDIATE LVL 6FT TENP N7 CV INTERNEDIATE LVL 6FT TENP NB CV It(TERNiiDIATE LVL 6FT TENP t(9 CV li'ITERt(EDIATE LVL 6FT TENP (IIO CV Q."":RATING LEVL 6FT TENP Il?VALUi (EQUAL LALI(6000 K00 6000 6009 6000 6009 6000 6000 GOOD 6000 6000 GOOD 6000 6009 6000 6009 6000 G000 GOOD GOOD 6000 6009 6000 GOOD 6000 K09 6000 6009 6000 6000 6000 6009 6009 6009 G009 6000 GCGD 82.5 K09 82,5 6000 82.5 82.5 93.1 6000 6000 6000 1427.94.5 5.5 339.43.5 42.4"1.1 8.75992M 4,49262+00 3.09030-01 2.660?2+01 1.01742+00 I~09648~00 1.62648~02 1.51138<02 2.61516+02 8,45036+00 2.55932+02 5.40910401 1.06844+03 1.99813+03 9.75130-01 9.75130<1 1,40241+03 4.20511-05 2, 6?CP-(P 4.20511-05 9.99987"04 2.3099!-06 4.62984-06 9..'0997-04 6.22985-06 1~80975-05 1.52999-03 1.01004-02 1 01004-02.0 71.8 E.U.GPN 0/t9'H DEG, DEGF DEGF DEGF NR/HR NR/MR NR/HR NR/HR t(R/HR NR/HR CPN CPN CPN CPN CPtt CPN CPN PN R/HR R/HR CPN Xl/CC ta/HR Xl/CC XI/CC XI/CC Xl/CC Xl/CC XI/CC XI/CC XI/CC NR/MR%/HR X DEGF DEGF DE6F DEGF DEGF DEGF Time: 0805 Message;11 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM MMMf: s t C<<IR Simulated Plant Conditions: ~Massa e:<<<<"THIS IS AN EXERCISE""" The following fire zone alarms: Z-01 (Aux Bldg 235-8 Bsmt E.Chp Room)FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1)Operators should sound the fire alarm and activate the fire bridge per SC-3.1.1~2)Control, Room should inform the TSCaf the Charging Pump Room fire alarm.3)Operators should be transitioning to 0-2.2~

Time: 0805 Message: 12 GINNA STATION 1993 EVALUATED EXERCISE MESSA E FORM~IN f: Ct gigP pR Fi.Fi Bigd Simulated Plant Conditions: See Attached Mini-Scenario Messacee:<<<<<<THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~OII N 1)Provide information verbally when appropriate actions are simulated or investigations are conducted. Antici ated Results: 1)As per Mini-Scenario. GINNA STATION TITLE: 1993 EVALUATED EXERCISE MINI-SCENARIO Char in P m Room Fire Fir Bri ade.Expected Scenario start time: 0805 INITIAL CONDITIONS: "C" Charging Pump Running METHOD OF INITIATION: Fire zone Z-01 (Aux Bldg 235-8 Bsmt E.Chp Room)alarms in Control Room.Control Room sounds the fire alarm and activates the fire brigade per SC-3.1,1 at 0807 hours the"C" charging pump trips out.INDICATIONS: CONTROL ROOM:~Alarm window K-31 fire system alarm panel.~Fire alarm panel alarm Z-01"Aux Bldg 235-8 Bsmt E.Chp Room".LOCAL:~Much smoke in area of the"C" charging pump motor.EXPECTED SEQUENCE OF ACTIONS'Investigate Charging Pump Room for signs of fire~Notice smoke in area of"C" Charging Pump Motor.~Notice"A" charging pump running normalp~Notice no other fire related problems in Charging Pump Room.R b b I<<0 C I.~08 5 hours.~Extinguish fire using accepted fire fighting practices. Rp<<II I*I 0Ibd<<b C Itl~0825~Return all fire fighting equipment to its proper storage. FINAL CONDITIONS'ire is extinguished and reported to the Control Room at 0825 hours end ell fire fighting equipment is properly stored. TIme: 0807 Message: 13 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM MMM: Si I<<C IR Simulated Plant Condi ions;~Massa e: ""<<THIS IS AN EXERCISE""" The following annunciator is received: '-25 (Motor Off CTR Sect PMPs Except Main and Aux Feed Pmps).FOR CONTROLLER USE ONLY Controller Notes: 1)WHEN operators check the control board, inform them that the"C" charging pump switch indicates a white light and the"C" charging pump indicates tripped.Antici ated Results: 1)Operators should perform the applicable actions of AR-G-25.2)Operators should control pressurizer level and seal injection"flow with the remaining charging pump.3)Control Room should inform TSC of"C" charging pump trip.4)Operators should be performing the applicable actions of 0-2.2. Time: 0815 Message: t4~CA 5 5 1993 EVALUATED EXERCISE MESSAGE FORM f: 5 I<<C IR Simula ed Plant Conditions: See Attached Sheets~essacee: ""THIS IS AN EXERCISE""+ FOR CONTROLLER USE ONLY Controller Notes: 1)Fire Brigade captain, after arriving at the Charging Pump Room, should report to 5 IR I=555<<I II I I"5" charging pump motor with much smoke present and that they are fighting the fire.2)Offsite,fire fighting assistance is not participating. If assistance is requested, controllers will intercede to prevent off-site fire department response.Antici ated Results: 1)Operators should inform TSC of, the fire on the"C" charging pump.2)Operators should be performing the applicable actions of 0-2.2, 3)TSC should be assuming command and control at approximately this time.4)TSC, when operational, should check into the loss of 34.5 kv circuit 751 problerri. 5)TSC, when operational, should evaluate the fire in the Charging Pump Room.6)EOF may be activating at this time due to plant conditions. 1993 EVALUATED EXERCISE Time:~8 MAO'OR PARAMETERS ENGINEERED SAFEGUARDS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED OOS TSC RUNNING UNLOADED 0 Security RUNN NG UNLOADED TB ENGINEERED SAFEGUARDS OOS Aux.Feedwater Pum s 1A.STBY OOS 1B.INSERV STB OOS Turb.Driven INSERV TB OOS CST Level~0 FEET Reactor Shutdown YES NO N-3 1 CPS N-32~~CPS N-35~~LAMPS N-36~IMPS Avg.Nuclear Power RCS Pressure~'Q PSIG PRZR Level (Q~A RCP RUNNIN STOPPED B RCP RUNNING/STOPPED 1A S/G Level 1B'S/G Level~H='B<lA S/G Pressure PSIG 1B S/G Pressure.O PSIG Turbine/Generator ONLINE/LIN 4 KV Buses NERGIZE DEENERGIZED 480V Buses NERGIZE/DEENERGIZED DC Batteries A~OVOLTS B~/VOLTS Cnmt Pressure~~PSIG Cnmt Sump A Level FEET Cnmt Sump B Level INCHES" Loop Hot Leg 0 F A Loop Cold Leg F B Loop Hot Leg~OF B Loop Cold Leg~~~F RVLIS~f1'CET F S/G A Total Aux FW Flow k1 GPM 9/G B Total Aux FW Flow~o GPM DIESEL GENERATORS Hi h Head S.I.Pum s FI-924 V GPM FI-925 D GPM 1A.INSERV TB OOS, 1B.INSERV STBY OS 1C.INSERV TB OOS BAST Level=Low Head S.1.Pum s FI-626 C)PM 1A.INSERV OOS RECIRC 1B INSERV OOS RECIRC RWST Level=Containment S ra Pum s FI-931A~GPM FI-93IB~GPM 1A.INSERV TB OOS 1B.INSERV TB OOS NaOH Tank Level=Containment Recirc Pans 1A.ER STBY OOS 1B.STBY OOS 1C.NSERV STBY OOS 1D.INSERV TB OOS Post Accident Dampers OPEN CLOSE Service ater Pum s 1A.STBY OOS 1B.N RV STBY OOS 1C.INSERV S Y OOS 1D.INSERV TB OOS A&B Header Pressure OPSIS Com onent Coolin Water Pum s 1A.NSERV STBY OOS 1B.INSERV TB OOS Surge Tank Level=Standb Aux.Feedwater Pum s 1C.INSERV OOS 1D.INSERV OOS*CET=Average of Selected Core Exit Thermocouples t(OV 17~1993 08:13 R.E.GINA SIML4JlTOR TREtiD GROUP ASSIGNNit(T SUiMMARY GROUP: EVENT1 PROCEDURE; EPIP 1-5 PLANT STATUS 1 2 3 4 e 6 7 8 9 10'z 1 lg 13 14 15 17 18 19 20 21 22 23 24 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 46 47 48 49 50 51 POINT ID ATM RXT N31 N32 N35 t(36 t(P PRCS LPIR FRY A FRC'RXTib RXT17 TSUBTC LSGA LSGB PSGA PSGB GBSKRl GENBKR2 BUS11A BUS11B BUS12A BUS128 B11A12A 811B129 PCV LSUMPA LO942E L0943E L09429 L09439 L0942C LO943C L0942B L0943B L0942A L0943A T0409A'0410A T0450 T0451 TA VGA)(ID TAVGBMID LRV TCCORE FAUXFN FAUXFHB BKRO81 BKR082 V3505 V3504 DESCRIPT IQW ANTICIPATED TRANSIENT l4/0 SCRAN R":ACTOR TRIP BREAKER STATUS SG(HCE RAt(GE DETECTOR ki-31 SOiRCE RAt(GE DETECTGR W-32 IWTGNEDIATE RANK DETECTOR W-35 IWTcPNiiDIATi RANGED E-"TECTOR N-36 AVERAGE NLGHR FG)tER REA"TQR COOLANT SYSTEM AVG PRESS PRESSURIZER AVERAGE LEVcL ROTOR COOLANT LQQi'AVG FLQiN REKTOR COOLANT LOOP 8 AVG FLQ)t RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSc, RX TRIP It@",ORE TC SUF330LED MARGIN STM GEN A NARROW RANGE AVG LEVEL STM GEN B NRttGW RAt(GE AVG I.EVEL STM Gitt A WVAGE FFcSSURc STN GEN B AVERAGE PRESSURE GEtFRATOR ON LINE BREAKER iG1372 C-.GATOR OW LINE BREAKER 9X1372 BUS llA SUPPLY BREAKER BU" llB SUPFLY BREAKER NOT TERNit(ATED QN PPCS (7/19/91)t(OT TERNINATED Ott PPCS (7/19/91)BUS liA TG 12A T!E BReNER BUS'11B TQ 128 TIE BRENER CO'ATAINMEt(T AVERAGE PRESSURE CO)(TAIttt(ENT SUMP A AVERAGE LEVEL SUt>>B LEVEL 8 INCHES (TRAIt(A)SLt+'LEVEl 8 ItlCHES (TRAIN 9)SUPP 8 LEVEL 78 It(CPS (TRAIN A)cEP B LEVEL 78 ritKHES (TRAIN B)SUiV B LEVEL 113 iNCHES(TRAIN A)SUMP B LEVEL 113 INCHES(TRAIN B)SlPiP 8 LEVEL 180 INCHcS(TRAIN A)SUMP B LEVEL 180 INCHES(TRAItl 8)SUtP 8 LEVEL 214 INCHES(TRAIN A)SUiP 8 LEVEL 214 IWCHcS(TRAIN 8)RCLA HOT LEG TBPERATURE RCLB HQT LEG TEMPERATURE RCLA COLD LEG TEt)PERATiBE RCLB COlD LEG TEt(PERAT(IE RCLA TAVG (THOT/TCOLD WIDE RWG)RCLB TAVG (THQT/TCQLD WIDE RNG)REii"-TOR VESSEL AVERAGE LEVEL Ei.'.INCORE TC AVERAGE TEMP S/6 A TOTAL PJX FEED)tATER FLGl(S/6 B TOTAL AUX FEED)iATER FLOiA t(TR AUXILIARY FEEDS'ATER PUMP A NTR AiJXILIARY FEED)STER FU)(P B AUX t%PU(P STEAN SUPPLY VALVE A AUX Ft'UMP STEAN SUPPLY VALVi B U AT))S RX TRIPPED 2.16520+02 2.16520402 1.04232-11 1.03276-11 .00 2247.18.5 97.3 96.5 ttGT TRIP NOT TRIP 102.6 34.4 K.4 1019.1016.TRIPPED TRIP PiD TRiPPED TRIPPED NQt'RIP tiOT TRIP NOT TRIP NOT TRIP~24 2.2 LOi)ER LO)tiR LO)tER LG)E'ER LO)iER LOUR LO~iER LO'"R LGNiR ()UAL ALRt(ALRM GOOD 600D GOOD 6009 6009 G009 LNRtl 6009 6009 6009 6009 600>>GOOD GOOD 6009 6009 ALfm ALRtl ALRti ALRt(DEL DEL ALRt(ALfm GOOD 6009 GOOD 6009 GOOD 6009 6009 GOOD G009 6009 49.9 549.7 550.3 550.2 99.4 550.6 70.ON OFF CLOSED CLOSED 6009 G009 GQQD 6009 6009 GGO>>6009 6009 G009 6009 GOOD LO)tER GOOD 550.8 GQ09 550.8 6009 E.U.CFS CPS A'V AMP/PSIG/I/DEGF 0/FSIG PSIG PSIG FEET D="GF DEGF DEGF DEGF DEGF DEGF DEGF GPM PN NOV 17>1993 08l13 R.E;GINA SINiLATGR TREttD GROUP AKIGtttlM'Ut~1ARY PAGE 2 GROUP: EVENT1 PRXEDUREl EPIP 1"5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P2}50 5b P21bl 57 BRR041 58 B~R042 59 BKR043 e0 Bnm44 DESCRIPT IGt,'AFETY Itt3ECTIGtl LGGP A AVG FLOW SAFETY IW.'ECTION LGGP B AVG FLOW SBVVICE WATER PUttPS A h B HEADER SERVICE MATER PUMPS C 5 D HEADER SERVICE WATER PUMP A SERVICE MATER PUMP B c""fNICE WATER PUtlP C SERVICE WATER PUMP 9 ON Olt ON GFF 0, 6009 0, GGGD 84.6009 75.6009 GGGD 6009 GOOD 6009 GPM PM PSI6 PSIG VALUE QUAL E.U. t)OV 17>1993 08:13 R, E.Bit@A SIMULATOR TREND GROUP ASSIGNNBlT SUi"DARY PA6E 1 BR(K4ENT2 PROCEDL%i: EPIP 1-5 PLANT STAT!JS POINT ID 1 F0619 2 LRWST W~033 4 N)033 5 WT033 6 WT250 7 WDT2 8 ROl R02 10 R05 11 R09.'2 R34 f3 R35 14 R10A 15 Rff.'6 R12 17 RIOB!8 R13 19 R14 20 R}8 21 R19 22 R29 23 R30 24 R15 25 R12AS 26 R1246 27 R12A7 28 R1249 29 R!485 30 R14A7 31 R14A9 32 R15A5 33 R15A7 34 R1549 35 R31 36 R32 37 CVH 38 TCV03 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 DESCRIPTIGM COi~0hit(T CGGLIN6 LOOP TOTAL FLW RiFL!ELINB WAl&STORAGE TA31 LVL 33 FQQT LEVEL Wit(D SPEED 33 FOOT LEVP WIND DIRcCTIGt< 33 FOOT LEVEL TEt(PERATURE 250 FOOT LEVP TEi(PERAT!JRE 250 TO 33 FOOT LEVEL ETTA Tits ARc4 f-CGhTR(3: ROQt(ARiA 2-CQtiTA INNEttT ARiA 5"SPEt(T FUEL PIT AREA 9-LETDG'4 Lit("" MONITOR AREA 34-AU)(BLDG CV PRAY PUtit'RcEA 35-PASS SAMPLE PAtKL CGt(TAI t(t(ENT IODINE HQNITQR R10A CONTAIMHit(T AIR PARTICULATE COt(TAIN<"i NT GAS NiONITQR PLANT Vit(T IODINE tfAITGR RIOD AUN BLDG E3(HAUST AIR PNTICUATE AU3(BLDG.E3(HAUST GAS tie((ITGR LAID WASTE DISPOSAL YDNITQR STEAi"~GEt(ERATOR BLOWDG'4 DRAIN AREA~9-Cet(TAIt(t(ittT HI(c(PAt"Sc AREA 0-CONTAINS".t(T HIGH RANGc Ce>CENSER AIR EJECTOR E3(HAUST CV VENT CHAM 5"LOW RAtitK GAS CV VENT CHAN 6-AREA GAl'C CV VEN!CHAN 7-<<ID RAtl'=GAS CV Vitii CHAN 9-HIGH RAMBc BAS PL%(T VENT CHAtt 5<0M RANGE BAS Pdk(T VENT CHAN 7-ttID RANBc GAS PLANT VENT CHAtl 9-HIGH RANGE GAS AIR EJECTOR CHAtt 5<0M RANGE BAS AIR i-CTOR CHAM 7-t,ID RAt(6c GAS AIR i JECTCR CHAN 9 HI RANGE GAS ARFA 31 STEAN LINi A (SPINBt ARE;",'2 STEAN LINE 8 (SPINB)CV HYDROGEN Cot(cicNTRATIOM CV BA-"it!ENT LciVEL 6FT TEt(P I3 CV It(TcRttiDIATE LVL 6FT TctP I7 CV It(T RtiEDIATE LVL 6FT TEt(P I8 CV It(TERMEDIATE LVL 6FT TEt(P I9 CV itt!cRt(EDIATE LVL 6FT TEt(P I10 CV OPERATING LEVL 6FT TEMP ttf7 VALUE 1432.LALt(94.5 BQQD 7.0 GOOD 321.6009 42.9 6009 42.0 6009 GOOD 9.44062M 6009 4.59727+00 GOOD 2'5121-01 GQQD 2.85101<01 6009 1.02920+00 6009 f.09648>00 GOOD 1.62648~02 GOOD 1.59f75~02 6009 2,68380+02 6009 8.45036i00 6009 2.59268402 6009 5.40910~01 6009 1.09175+03 6009 1.99813+03 GOOD 9.751~1 6009 9.75f30-01 6009 1.40241+03 6009 4.205f1-05 6009 2.67992-02 GCi09 4.20511-05 6009 9.99987-04 6009 2.30991"06 6009 4.62984-06 6009 9.10997-04 GOOD 6.22985-06 6009 1,80975-05 6009 1.52999-03 6009 f.01004-02 6009 1.01004-02 GOOD.0 6009 71.8 82.3 GOOD 82.3 6009 82.3 82.3 92.8 E.U.GPtf 7.tfPH DEG.DE6F DEGF DEGF t8/Htt N/HR N/HR N/HR ta/HR N/HR CPM CPM CPM CPtf CPM CPtt CPM CPtf R/HR R/HR CPtt XI/CC N/HR XI/CC UCI/CC XI/CC KI/CC XI/CC KI/CC XI/CC KI/CC N/HR N/HR DEBF DcGF DEGF DEGF DEGF DEGF Time: 0825 Message: 15 GINNA STATION'993 EVALUATED EXERCISE MESSAGE FORM MMMf: R I<<C<<IR C Simula ed Plant Conditions: See the Attached Sheets~Meeee e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1}Fire Brigade captain should report to Control Room at this time that the fire in the Charging Pump Room is extinguished and that it was on the"C" charging pump motor.He should also report that the"A" charging pump is running normal with no apparent damage from the fire.Antici ated'esults: 1)Operators should inform the TSC of the fire being extinguished on the"C" charging pump and the condition of the"A" charging pump.2)TSC should re-evaluate the Emergency Classification per EPIP 1-0.There should be no change of Emergency Classification. Time: 0825 Message: 16 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM f: M 1 i keg"eC" Ch gigP pM Fi 0 g Simulated Plant Conditions: See the Attached Mini-Scenario ~Messe e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY 1)Provide information verbally when appropriate actions are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenario. GINNA STATION 1993 EVALUATED EXERCISE MINI SCENARIO TITLE: "C" Char in Pum Motor Fire.Scenario expected start time: 0825 INITIAL CONDITIONS: The reported fire on the"C" charging pump is declared out by the Fire Brigade.Fire captain reports the fire was located in the motor of the charging pump.METHOD OF INITIATION: Control Room reports to the Emergency Coordinator that the fire is out and the"C" charging pump is out of service.INDICATIONS'ONTROL ROOM: Fire Zone 2-01 alarm was responded to by fire brigade,"C" charging pump trip from the fire, and Brigade Captain reports the fire in the motor has been put out.LOCAL: Fire Brigade Captain reports the fire is out to Control Room.EXPECTED SEQUENCE OF ACTIONS: Trouble report is written to repair motor on"C" charging pump.Planner puts together work order and package for major repair to vari-drive procedure M-11.4.4 and motor procedure M-45.0.Possible trouble-shooting inspection of unit by the planner and mechanic.Check of inventory to see if replacement motor available for unit.REPAIR TIME'ependent on: amount of time to have a new motor shipped in to replace the damaged unit, to have the stator sent out for rewind, or whether a rotor is in inventory control, unit will not be repaired for at least 1 month.FINAL CONDITIONS: Clean up of Charging Pump Room by maintenance shop and b machine shop and electrical shop evaluating the course of action to take for motor repair. Time: 0825 Message: 17 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM MMMf: El<<ii ling eC" Lt gi gP pM'Fi 0 g Simulated Plan Conditions: See the Attached Mini-Scenario ~essacee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provided information verbally when appropriate actions are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenario. GINNA STATION 19S3 EVAI UATED EXERCISE Il MINI-SCENARIO TITLE: Ch r in P m R mFir 1Cchr in m Expected scenario start time: 0825 INITIAL CONDITIONS: Charging Pump 1C running, METHOD OF INITIATION: Fire Zone Alarm.Zone 2-01 (Aux Building 235-8 Basement, Charging Pump Room).Charging Pump 1C breaker trips.INDICATIONS: CONTROL ROOM: Fire Alarm Zone 2-01 Annunciator Window: "J-25" Motor Off: CHP1A"F-14" Charging Pump Speed White (disagreement) light: CHP1A BUS 16/POS15C Amptector: "Instantaneous" trip indication If meggered-0 Q to ground, 0 Q p to p CHP1A MOTOR: Smell of burnt insulation EXPECTED SEQUENCE OF ACTIONS: Investigate fire alarm, Zone 2-01, Auxiliary Building~Smoke discovered in vicinity of Charging Motor 1C~Auxiliary Operator/Electricians check CHP1C o Discover Amptector"instantaneous" button is out Obtain holds, clearances, and test equipment. Simulate measuring resistance phase to phase and meg gering motor from Bus 16/Pos 15C readings: Megger readings: 0 Q Phase to ground Phase to phase resistance 0 Q FINAL CONDITIONS: Motor requires replacement/rewinding due to shorted windings. Time: 0825 Message:~1 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM f: tBCW k g"C'Ct gi igP pM Fi i0 g Simula ed Plant Condition: See the Attached Mini-Scenario ~IVlesss e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate actions are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenario. GINNA STATION 1993 EXERCISE MINI-SCENARIO TITLE: "C",Ch r in P m Room Fir Expected scenario start time: 0825 INITIAL CONDITIONS: Charging Pump"C" operational. METHOD OF INITIATION'ire in Charging Pump Room.INDICATIONS: Solenoids 14306S and 14305S are charged and leaking air.EXPECTED SEQUENCE OF ACTIONS: Replace both Solenoids FINAL CONDITIONS: Both Solenoids are replaced and tested. Time: 0830 Message: 19 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM 8 I C<<IR Simulated Plant Conditions: See Attached Sheets~Messe e:<<""THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1993 EVALUATED EXERCISE Time: O'P3~MAZOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YES NO N-31/CPS N-32 CPS N-35/~~/AMP S N-36~FN~QAMPS Avg.Nuclear Power 0 RCS Pressure/PSIG PRZR Level c A RCP UNNIN STOPPED B RCP UNNIN STOPPED 1A S/G Level 1B'S/G Level 29 1A S/G Pressure lOIB PSIG 1B S/G Pressure PSIG Turbine/Generator LINE/FFLIN 4 KV Buses NERGIZED DEENERGIZED 480V Buses N G ZED DEENERGIZED DC Batteries A~O B~/VOLTS Cnmt Pressure PSXG Cnmt Sump A Level FEET Cnmt Sump B Level CP INCHES A Loop Hot Leg ZO.Z.0F A Loop Cold Leg 5'M OF B Loop Hot Leg F B Loop Cold Leg PQL'F RVLIS~F l/*CET OOF S/G A Total Aux FW Flow~G-GPM S/G B Total Aux FW Flow~~GPM DIESEL GENERATORS A.RUNNING UNLOADED TBY OOS B.RUNNING UNLOADED OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED STB OOS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 GPM FI-925 O GP 1A.INSERV OOS 1B.INSERV S Y 00 1C.INSERV STB OOS BAST Level=Low Head S.I.Pum s FI-626 GPM 1A.INSERV TB OOS RECIRC 1B.INSERV S OOS RECIRC RWST Level=~<~4 Containment S ra Pum s FI-931A 0 GPM FI-931B~GPM 1A.INSERV TB OOS 1B.INSERV S OOS NaOH Tank Level=Containment Recirc Fans 1A.NSER STBY OOS 1B.INSE STBY OOS 1C.NSERV STBY OOS 1D.INSERV TB OOS Post Accident Dampers OPEN CLOSED Service Water Pum s 1A.NSERV STBY OOS 1B.NS STBY OOS 1C.INSER STBY OOS 1D.INSERV TB OOS A&B Header Pressure 5 PSIG Com onent Coolin Water Pum s 1A.INSER STBY OOS 1B.INSERV TB OOS Surge Tank Level=~0 Aux.Fe ater Pum s 1A.NSER STBY OOS 1B.INSERV STB OOS Turb.Driven INSERV CST Level~FEET OOS Standb Aux.Feedwater Pum s 1C.INSERV OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples t<QV 17>>1993 08:32 R.E.GIN(A SltSLATOR TREt(D 6ROUP ASSIGtNEt(T SUt<<"~ARY PAGE 1 6RQUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STA'PJS 1 3 4 5 6 7 8 9 10 11 12 13~4 15 ib 17 18 19 20 21 22 23 24 25 26 27 28 29 30 3f 32 33 34 35 36 37 38 39 40 41 42 43 45 46 47 48 49 50 51 52 POINT ID ATMS RXT N31 t(32 N35 t(36 NP PRCS LPIR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PS6A PSGB GENBKR1 GMKR2 BUSl iA BUS118 BUS12A BUS128 811A12A 8118128 PCV LSU!)PA L0942E L0943E L0942D L0943D L0942C L0943C L09428 L09438 L0942A L0943A T0409A'0410A T0450 T0451 TAVGAM!D TAVGBMID LRV TCCQRE FAUXFMA FAUXFt'8 Bt(R081 BKR082 V3505 V3504 DES"RIP TIC4 ANTICIPATED TRANSIENT M/0 SCRNI REACTOR TRIP BREAKER STATUS SOItCE RANGE DETECTOR N-31 SOURCE RAttGE DFTECTQR N-32 INTERMEDIATE RANGE DETECTOR N-35 It(TERYEDIATE RANGE DETECTOR N"36 AVcMGE NUCLEAR POWER REACTOR CO(LP<<(T SYSTBl AVG PRESS PRESSURIlER AVERAGE LEVEL REA".TOR COOLA%'OOP A AVG FLOM REACTOR COQLNT LOOP 8 AVG FLQM RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP ItZORE TC SUBCOOLED tlARGIN STtl G N A NARROM RANGE AVG LEVEL STtt GEN 8 t>>ARROM RAt(GE AVG LEVEL STtt GEN A AVERAGE PRESPJRE STtf GEN 8 AVERAGE PRESSURE GB~~RATQR ON LINE BREAKER 16f372 GEtFRATOR ON LINc BFEAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 118 S5'PLY BREAKER tiOT TERt(ltlATED ON PPCS (7/f9/91)NOT TEMlt(ATED ON PPCS (7/19/91)BUS 11A TO 12A TIE BRFAKER PJS!18 TO 128 TIE BREAKER CQt(TAIt(tLct(T AVERAGE PRESSURE CON'AINttEt)T SUNUP A AV RAG LEVEL SU%8 LEVEL 8 INCHES (TRA!N A)SU@'LEVEL 8 It(CHES (TRAIN 8)SUi%8 LEVEL 78 INCHES (TRAIN A)SU'P 8 LEVEL 78 ft>>'CHES (TRAIN 8)SUiP 8 LE'PJ.113 It(CHES(TRAIN A)SOP 8 LEVEL 113 INCHcS(TRAIN 8)SU'P 8 LEVEL 180 INCHES(TRAIN A)SUi%'LEVEL f80 INCHES(TRAIN 8)SU%'LEVEL 214 INCHES(TRAlt(A)SUi%'LEVEL 214 INCHES(TRAIN 8)RCLA HQT LEG TEtPERATURE RCLB HOT LEG TEt'FERATURE RCLA COLD LEG TEN'ERAT(RE RCLB CO'LEG TEt(PERATlRE RCLA TAVG (THQT/:COLD MIDc RNG)RCLB TAVG (THOT/!COLD MIDE RNG)REA'QR VESSEL AVERAGE LEVE(.Ef.1 INCORE TC AVERAGE TEMP S/G A TOTAL AUX FEEDMATER FLOW S/G 8!OTAL AJX FEEC Ai"R FLOW t(TR AUXILIARY FEEDMATER PUMP A NTR AUXILIARY FEEDMATER PUMP 8 AUX FM PUiP STEAN SUPP(.Y VALVE A AUX FM PU",P STEAN SUPPLY VALV." 8 VALUE@NL Ott OFF CLOSED CLOSED ATMS ALRN RX TRIPPED ALRtt 2.17270~02 600D 2.06300~02 GOOD 1~04232-11 600D 1.03276-11 6009.00 6009 2251.6009 19.4 LMRtt 97.4 GOOD 96.6 6009 t(OT TRIP 6009 NO: TRIP G009 103.5 600>>36.5 GOOD 32.8 GQQD 1018.6009 1014.6009 TRIPPED ALRN TRIPPED ALRN TRIPPFD ALRN TRIPPED ALRt(NOT TRIP DEL NQT TPIP KL NOT TPIP ALRN t(QT TRIP A'N.23 6009 1.4 6009 LQ)tER 6009 LORER GQOB LONER 6009 LQMcR 6009 LONER GOOD LORER 6009 LONER 6009 l.OM R 6009 LONER 6009 LlNER 6009 50.2 GOOD 550.2 GQQD 549.5 GOOD 549 F 1 6009 549.8 6009 549.6 6009 99.4 6009 550.0 GOQ>>82.6Q09 109.6009 6009 6009 6009 GQQD E.U.CPS CPS tIP AÃP/PSIG///DEGF PSIG PSIG PSIG FEET DEGF DEGF DEGF DEGF DEGF DcGF/DEGF GPtf GPtf NOV 17~1993 08:32'.E.GINNA SIMULATOR PAGE 2TREND GRGU?AKIGNHEttT PJi JSRY GROLtt'VcNT1 >ROCcPPc'PIP 1-5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P 2160 56 P2161 57 BXR041 58 BXR042 59 BXR043 60 BXR044 DEKRIPTICti'k ~TY iNJECTION LOOP A AVG FLOM SAFETY IttJECTIGN LGOP B AVG FLGM ScRVICE MATER PUtt?S A 5 B HEADER SBNICE MATER PUtt?S C 5 9 HEADER S RVICE MATER PUttP A SERVICc MATER PUtl?B SER'VICE,MATER PUMP C ScRVICE MATER PLY,P D ON Ott GN OFF 0.0.84.75.VALUE QUA'U 6009 PH 6009 PM 6009 PSIG 6009 PSIG 6009 6009 GOOD GOOD NOV 17i 1993 OB:32 R.E.'GINNA SIMULATOR TREND GR(LiP ASSIGNYZP

SUMMARY

6RQL'P: EVENT2 PRQCEDUREl EPIP 1-5 PLANT STATUS POINT ID F0619 2 LR'i(ST 3 WS033 4 WD033 5 WT033 6 WT250 7 iWDT2 8 R01 9 R02!0 R05 il R09 12 R34 13 R35!4 R!OA 15 Rl 1!6 R!2 17 R10B!8 R!3 19 R!4 20 R18 21 R!9 22 R29 23 R30 24 R15 25 R!2AS 26 R12A6 27 R!2A7 28 R!2A9 2'?R!485 30 R14A7 3!R14A9 32 R!5A5 33 R!5A7 34 R!SA9 35 R31 36 R32 37 CVH 38 TCV03 3'9 TCV07 40 TCVOB 41 TCV09 42 TCV!0 43 TCV17 DEKRIPT ION CQi'POTENT COOLING LOOP TOTAL FLW REPJELING WATER STORAGE TANK LVL 33 FOOT LEVE!WIND SPciED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL Tit.ERATURE 250 FOOT LEVP TEMiPERATL'Ri 250 TCi 33 FOOT LEVEL DELTA TEMP AREA 1-COt(TR&'00M AREA 2-CONTAlt(NEtiT AREA 5-SPFNT FUcL PIT ARiA 9-LETDOWN LINE?%t(ITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PAtKL CQNTAINMiENT IODINE tiONITQR R!OA COl(TAIt(YirriT AIR PARTICIJ ATE CQtlTAIt(MENT GAS MQt(ITGR PLANT VENT IODINE t!Ot(ITOR R!OB AUX B'G EXHAUST AIR PARTICLILATE AUX BLDG EXHAUST GAS MONITOR LIK'ID WASTE DISPOSAL MOt(ITOR STcki GLNERATGR BLOWDO'n':l DRAIN AREA 29 CQt(TAIt,'MENT HIGH RANGr AREA 30-CQNTAINMEt(T HI%RANGE CONDENSER AIR EJECTOR EXHAUST CV Vitf!'HAN MOW RANK GAS CV VENT CCH 6-AREA GAMMA CV V-N: CHAN 7-t(ID RANK 6AS CV VENi CHAtt 9-HIGH RAtKE GAS PLOD VENT Cf1-"N 5-LGW RANGi GAS PLNi(VEt(T CfLAtt 7-NID RANGr EGAS PLQ(T VENT CfIN 9-HIGH RAt(6E 6AS AIR E.rCTQR CHAN 5 LQA, RANGE GAS AIR i:-ECTQR WAN 7-NID RAiNGE GAS AIR EJECTOR CHAN 9-Hl RANGE GAS ARFA 31 STEAN LIt)E A (BRING)AREA 32 STEA,f LIHE 9 (BRING CV HYDROGEN CONCENTRATION CV BASEMENT LEVEL 6FT T:MP I3 CV INTERMEDIATE LVL 6FT TEMP I7 CV It(TERMrEDIATE LVL 6FT TEMP ((8 CV INTERMEDIATE LVL 6FT TEMP I9 CV It(IERNEDIATE LVL 6FT TEtP (f!0 CV OPERATING LEVL 6FT lcMP (f17 VALUE 1427.94.5 6.2 343.42.6 42,8.2 8.75992-02 4.49262+00 3,09030-01 2, 66072IO!1.01742+00 1.09648~00 1.62648<02 1.51138+02 2.61516+02 8.45036+00 2.559 2<02 5.40910~01 1.059 5+03 1.99813+03 9.75130-01 9.75130-01 1.40241+03 4.20511-05 2.67992-02 4'05!1-05 9.99987-04 2.30991-06 4.62984-06 9.10997M 6.2298~1.80'?75-05 1~52999-03 1 010*4-02!F 01004-02.0 75.2 83.9 LALM GOOD 6000 GOOD 6000 C&9 GOOD 6000 6000 GOOD 6000 GOOD 6000 6000 6000 6009 GOOD 6000 6000 GOOD 6000 6009 GOOD GOOD 6000 GCiOD GOOD 6009 KGD 6009 GOOD GOOD GGOO 6009 GGQD GOOD GOOD 6000 GOOD 83.9 6000 83.9 6000 83.9 92.5 E.U.6PN MPH IFG.DE6F IFGF DEGF NR/HR NR/HR MR/HR NR/HR MR/HR MR/HR CPN CPM O'CPN CPM CPN CPN CPN R/HR R/HR CPM Kl/CC MR/HR KI/CC KI/CC KI/CC KI/CC KI/CC KI/CC L",I/CC KI/CC MR/HR MR/HR/IFGF KGF DEGF DEGF DE6F DEGF Time:~084 Message:~2 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM 8 I<<C<<IR Simulated Plant Conditions: See Attached Sheets Messacee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1993 EVALUATED EXERCISE Time:~GF'/MA JOR PARAMETERS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED STB OOS TSC RUNNING UNLOADED STBY OOS Security RUNNING UNLOADED STB ENGINEERED SAFEGUARDS OOS Aux.F water Pum s 1A.ST OOS 1B.INSERV TB OOS Turb.Driven INSERV STBY OOS CST Level~0.0 FEET Reactor Shutdown YES NO N-31 3 CPS N-32 0 CPS N-35 0-I AMPS N-36/OE./-AMP 5 Avg.Nuclear Power C)RCS Pressure~~PSXG PRZR Level e 2 A RCP UNNIN/STOPPED B RCP RUNNIN STOPPED 1A S/G Level~T~i 1B S/G Level.~e j 1A S/G Pressure/el PSIG 1B S/G Pressure l SIG Turbine/Generator LXNE OFFLXNE 4 KV Buses NERGXZE DEENERGIZED 480V Buses ENERGIZED DEENERGIZED DC Batteries A~bVOLTS Bfno VOLTS Cnmt Pressure o2 PSIG Cnmt Sump A Level o FEET Cnmt Sump B Level INCHES*Loop Hot Leg QKI.<'F A Loop Cold Leg~PM'F B Loop Hot Leg~50~'F B Loop Cold Leg 0F RVLXS*CET SD.O'S/G A Total Aux FW Flow 72-GPM S/G B Total Aux FW Flow id~GPM DIESEL GENERATORS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924&GPM FZ-925 (5 GPM 1A.INSERV TB OOS 1B.INSERV STBY 0 1C.INSERV STB OOS BAST Level=Low Head S.I.Pum s FI-626 Q GPM 1A.INSERV OOS RECIRC 1B.INSERV STB OOS RECIRC RWST Level=Containment 8 ra Pum s FI-931A GPM FX-931B'PM 1A.INSERV TB OOS 1B.INSERV B OOS NaOH Tank Level=Containment ecirc Fans 1A.STBY OOS 1B.SER STBY OOS 1C.INSE STBY OOS 1D.INSERV TB OOS Post Accident Dampers OPEN CLOSED Service Water Pum s 1A.NSERV STBY OOS 1B.ERV STBY OOS 1C.NSERV STBY OOS 1D.INSERV B OOS A&B Header Pressure~PSXG Com onent Coolin Water Pum s 1A.NSERV STBY OOS 1B.INSERV TB OOS Surge Tank Level=~O Standb Aux.Feedwater Pum s 1C.INSERV S B OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples t(OV 17~1993 08:43 R.E.GINA SIMULATOR TREIID GRGU ASSIGI(M hT

SUMMARY

PAGE 1 GROLc EVENTl PROCEDL!Rc EPIP 1 5 PLANT STATUS 1 2 3 4 5 6 7 8!0 11 12 13 IS!6 17 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 45 46 47 48 49 50 5!52 PQI"IT!D ATWS RXT N31 N32 N35 N36 NP PRCS LPlR FRC." A FRCLB RX716 RXT17 TSUBTC LSBA LSGB PSGA PSGB GENBKRI Git(BXR2 BUSliA BUS118 BUS12A BUS128 Bl!A!2A 8118128 PCV LSUMPA L0942E L0943E LO942D L0943D L0942C LO943C LO9428 L09438 I 0942A I 0943A T0409A T0410A T0450 T0451 TAVGAWID TAVBBWID LRV TCCQRE FAUXFWA FAUXFWB Pi(R081 BKR082 V3505 V3504 DESCRIPTION At(TICIPATED TRANSIENT W/0 SCR(!M REA".TOR TRIP BREAKER STATUS SMSCi RAI(GE D TECTOR)I-31 SESCE RAti&c DETECTOR N 32 It(TERMEDIATE RANGi DETECTOR N"35 It(TERMiDIATE RAI(GE DETECTOP.N-36 AVERAGE NUCLEAR PO)lER REACTOR COOLANT SYSTEM AVG PRESS PRESSURIZER AVERAGE LEVcC REA"TGR CCC.NT LOOP A AVG FLOW REACTOR CCQ.A!IT LOOP 8 AVG FLN RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSc PX TRIP ItiCORE TC SUBCOOLED t!A%It<STM C=N A t(ARROW RANi" AVC LEVEL STM GEN 8 NAMW RANCE AVB LEVicL STM C tl A AVERAGE PRESSJRE S7M BBl 8 AVBQBE PRESRJRE GB'KRA GR GN LINE BREAKER lG!372 GBKRA!GR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 118 SUPPLY BREAKER NOT TERiMilt(ATED ON PPCS (7/19/91)NOT TERMINATED OiN PFCS (7/19/91)BUS 11A 70 12A TIE BRENER BUS 118 TQ 128 TIE BRiA'(ER CONTAINMit(7 AVERAGE FRESSURE CGt(TAINMictiT S'JMP A AViRAGE LEVEL SUMP 8 LEVEL 8 INCHES (TRAlt(A)SUi~8 LEVEL 8 INCHES (TRAIt(8)SBF 8 LEVEL 78 INCHES (TRAIN A)SUtP 8 LEVFL 78 INCHES (TRAIN 8)SUtp 8 LEVEL 113 INCHES(TRAIt(A)SNP 8 LEVEL 113 INCHES(TRAIN 8)SUtP 8 LEVEL 180 INCHES(TRAIN A)SUMP 8 LEVEL 180 Iti'CHES(TRAIiN 8)SUi'P 8 Li(&c 214 INCI'=S(TRAIN A)PJM'LEVEL 214 INCHES(TRAIN 8)RCLA HOT LEG TEMPERATURci RCLB HQT LEG TEMPERATURE RCLA COLD LEG TEt(PERATLRE RCLB COLD LEG Tit!PERATURE RCL'AVG (THQT/TCQ: D WIDE RNG)RCLB TAVG (THO7/TCGLD WIDE RNG)REACTOR VESSEi AVERAGE LEViL El.i!((CORE TC AVERAGE TEMP S/G A TOTAL AUX FEEDNATLR FLS S/6 8 TOTAL AJX FicDiWA!cR FLN t(TR AUXILIARY FEEDWATER PUMP A MTR AUXILIARY FEEDWATiR PUMP 8 AUX FW Pro STEAM SUPPLY VALVE A A!JX FW PUhP STEAli SUPPLY VALVE 8" OUAL ALRM ALRII 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 GQO>>GOOD GOOD GQOD CMD ALRM ALRII ALRMi ALRI(DEL DEL ALRt(ALRt(KOD 6009 6009 KQD KOD 6009 6009 G009 GOOD 6009 GOOD 6039 50.2 G009 550.2"6009 549.5 549.1 549.8 549.6 99.4 550.0 6009 6009 6009 6009 600>>72'02.Gtf GFF CLOScD CLOSED KQD GQQ9 GOOD GQQD GQQD GOOD r p f%VALUE ATNS RX TRIPPED 2.1355&02 2.03469+02 1~04232-11 1~03276-11.00 2252.21.2 97,4 96.6 t(QT TRIP NOT TRIP 103.5 37.7 37.1 1017.1014.TRIPPED TRIPPED TRIPPED TRIPPED NGT TRIP NQT TP,IP t]OT TRIP t(Q;TP.IP.24 1.4 LONER LONER LONiR LONER LONER LONER LONER LONER LONER LONER E.U.CPS CPS NP A:"iP Y PSIG/Y.Y.DEGF Y PSIG PSIG PSIB FEET DEGF DEGF DEBF DE6F DEGF DiGF/DiGF GPt(PN NOV 17~1993 08:43 R.E.GINA SItfULATOR TREND GROUP ASSIGtNENT SUtf"fARY PAGE 2 6ROUP: EVBIT1 PROCEDURE: EPIP 1-5 PLAtfT STATUS POINT ID DESCRIPTION VALUE DUAL E.U.53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 SAFETY INJECTION LOOP A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SM~ICE MATER PUtiPS A h B HEADER S":FQICE MATER PUtfPS C h 0 HEADER SERVICE MATER PUtfP A SERVICE WATER PUtfP 8 SEfIIC"" MATER PUtfP C SERVICE WATER PUtfP 0 ON 0N ON OFF 0.GOOD 0.GOOD 84.GOOD 75.GOOD GOOD 600D GOOD GOOD GPtf GPtf PSIG PSIG 0 NOV 17i 1993 08:44 R.E.GIt@A SIML&TGR TREND GROUP ASSIGNMENT SJMIIARY GROUP: EVitIT2 PROCEDURi: EPIP 1-5 PLANT STATUS POINT ID 1 F0619 2 LRIiIST 3 WS033 4 II9033 5 WT033 6 WT250 7 WDT2 8 R01 R02 10 R05 11 R09 12 R34 13 R35 14 R}OA!5 Rii 16 R}2 17 R}OB 18 R}3 R14 20 R}8 21 R}9 R29 23 R3Q 24 R}5 25 R12A5 26 R}2A6 27 R12A7 28 R}2A9 29 R}4A5 30 R14A7 31 R}4A9 32 R}5A5 33 R}5A7 34 R15A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV}7 DESCRIPTION CGIPOt(ENT COP ING LGQP TOTAL FLW REFJELING MATER STORAGE TA)IX LVL 33 FGGT I.EVB.W}ND SP"'9 33 FOOT LEVB WIND DIRECTION 33 FOOT LEVB TEtlPERAT!JRE 250 FGQT LEVEL TitPERATURE 250 TO 33 FOOT LEVEL DELTA TPJ'}-COt(TR9 ROOM ARE-"..2-CONTAI!ANENT AREA 5-SPENT FUEL PIT ARiA 9-LETDOWN LIN" I'iOtii TOR AREA 34-AUX BLDG CV SPRAY PUMiP AREA 35-PASS SAtIPLE PEEL CQ)ITAIIIMEtlT IQDItIE MOttITGR R}OA CGIITAINMEtIT AIR PARTICLLATE CGiNTAINMENT C<S tfGI'IITGR PLANT VENT 109ltti MGttITQR R109 AUX BLDG EXHAiJST AIP, PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIPJID WASTE DISPOSAL Nt(ITGR STEAM GENiRATGR BLOWiDGWN DRAlti AREA 29-CGNTAINMiti'T HIS RAKE ARi=".30-CGMTAItl<itiiT HI&i RA)IGE CO)QBISER AIR EJECTOR EXHAUST CV VEt<T Ct!J!J(5-LGW RANK GAS CV VENT CHAN 6-AREA GANA CV VENT!C85 7-MID RANK GAS CV VEN;CHAN 9-HIGH RANGE 6AS PLANT VENT CHAt<5-LGW RANGE 6AS PLWT VEIIT CHAN 7-MID RANGE GAS PLANT ViNT CHAtJ HIGH RANG"" GAS AIR EJECTA CHAN 5<0M RAtIGi GAS AIR EJECTOR CHAN 7"MID RANGE GAS AIR EJECTA CHAN 9 HI RANGc GAS AREA 3.'TEAM LINE A (SPING)AIIEA 32 STEAM Llt(E 9 (BRING)CV HYDROGEN CGNCENTRATIQtI CV BASEMEtlT LEVEL 6FT TEMP II3 CV INTERMEDIATE LVL 6FT TEMP II7 CV ltITiRMEcDIATE LVL 6FT TEMP II8 CV INTERMEDIATE LVL 6FT TEMP II9 CV INTERMEDIATc. LVL 6FT TEMP II}0 CV OPERATING LEVL 6FT TEMP tt}7 QUAL LALH G009 6009 6009 6009 6009 6009 GOOD G009 G009 6009 6009 6009 6009 6009 6009 6009 GOOD 6009 6009 6009 6009 6009 6009 6009 GG09 6009 6009 GQQD 6009 6009 6009 G009 89.3 6009 89.4 89.3 92.4 GGD9 6009 VALLic 1427.94.5 5.7 342.42.6 42.9.3 8.8}048<2 4.62382+00 3.14412-01 2.91742+01 1.02920+00 1~09648+00 1.65481+02 1~57806+02 2.59268M 8.63474+00 2.483}3%02 5.64774+01 }.0}888t03 2.11348+03 9.75130-01 9.75}3M}}.45797+03 4.20511-05 2.67992-02 4.20511-05 9.99987-04 2.3Q991-06 4.62984-06 9.10997-04 6~22985-06 1.80975-05 1.52999-03 }F 01004-02 1.01004-02 .0 86.3 89.4 E.U.6PM 7 MPH DEG.DEGF DEGF DE6F 0/HR t8/HR N/HR t8/HR t8/HR t8/HR CPM CPM CPM PN CPM CPM CPM CPM R/HR R/HR CPM XI/CC t8/HR XI/CC Xl/CC XI/CC Xl/CC XI/CC Xl/CC Xl/CC XI/CC t8/HR t8/HR/DEGF DEGF DEGF DEGF D=GF DEGF GINNA STATION Time: 0910-0915 Message: 21 1993 EVALUATED EXERCISE MESSAGE FORM~f'.RI I R<<IR Simulated Plant Conditions: See Attached Sheets~essacee: """THIS IS AN EXERCISE""" The following annunciators are received: '-20 (Pressurizer Lo Press Trip 1873 psi)'-19 (Pressurizer Lo Press Sl 1750 psig)FOR CONTROLLER USE ONLY Controller Notes: 1)All safeguards equipment operates normally except the"B" Sl Pump.It is out for maintenance. 2)Sl flow is greater than 100 GPM.Actions Ex ected: 1)Operators should perform the immediate and subsequent actions of E-0 (Reactor Trip or Safety Injection). 2)Operators should inform TSC of the loss of coolant accident.3)TSC should declare a SITE AREA EMERGENCY in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification," EAL: Reactor Coolant Leakage (RCS);LOCA identified inside Containment ~n Sl total flow)100 GPM using Fl-924/Fl-925. Appropriate notifications should be made per EPIP 1-5.4)TSC should be expediting the maintenance on the"B" Sl pump.5)EOF should be activating at this time, if not done earlier. 1993 EVALUATED EXERCISE Time: OV/~MA JOR PARAMETERS Reactor Shutdown ES NO N-31 CPS N-32 CPS N-35 AMPS N-36 AMPS Avg.Nuclear Power RCS Pressure 7CH PSIG PRZR Level Q.o g A RCP RUNNXNG TOPP B RCP RUNNING STOPPED 1A S/G Level 1B S/G Level 1A S/G Pressure~~OPSIG 1B S/G Pressure PSXG Turbine/Generator ONLINE/FFLIN 4 KV Buses NERGIZE DEENERGIZED 480V Buses NERGIZE/DEENERGIZED DC Batteries A~BOVOLTS Bl OVOLTS Cnmt Pressure PSIG Cnmt Sump A Level o FEET Cnmt Sump B Level INCHES" Loop Hot Leg (2'F A Loop Cold Leg 3~.3 oF B Loop Hot Leg~//~'F B Loop Cold Leg OF RVLIS.3 4*CET~o-~O'F S/G A Total Aux FW Flow~9GPM S/G B Total Aux FW Flow~~GPM DIESEL GENERATORS A.UNNING UNLOADED STBY OOS B.RUNNING U OADED S BY OOS TSC R ING UNLOADED TB OOS Security RUNNING UNLOADED STB OOS ENGINEERED SAFEGUARDS Aux.w ter Pum s 1A.ERV STBY OOS 1B.INSERV STBY OOS Turb.Driven INSERV TB OOS CST Level~a~FEET ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 8 GPM FI-925 GPM 1A.NSER STBY OOS 1B-INSERV STBY 0 1C.XNSER STBY OOS BAST Leve Low Head S.I.Pum s FI-626 GPM 1A.NSER STBY OOS RECIRC 1B.NSER STBY OOS RECIRC RWST Level=Containment S ra Pum s FI-931A 0 GPM FI-931BGPM 1A.SER STBY OOS 1B.INSERV STBY OOS NaOH Tan Level=~%Containm Recirc Fans 1A.NSERV STBY OOS 1B.SERV STBY OOS 1C.S R STBY OOS 1D.INSERV STBY OOS Post Aces en Dampers PE CLOSED Service Water Pum s 1A.NSER STBY OOS 1B.I STBY OOS 1C.STBY OOS 1D.STBY OOS A&B Header Pressure~pl PSIG Com onent Coolin Rater Pum s 1A.NSER STBY OOS 1B.INSERV STB OOS Surge Tank Level=~~Standb Aux.Feedwater Pum s 1C.INSERV B OOS 1D.XNSERV TB OOS*CET=Average of Selected Core Exit Thermocouples NOV 17i 1993 09'5 R.E.GINNA SII"iULATOR TREND GROUP ASSIGIINENT SUGARY PAGE 1 GRGL!P: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POII(T ID DESCRIPTION VA'i E.U.1 2 3 5 6 7 8 9 10 11 12 13 14 45 16 17!8 19 20 2122 24 25 26 27 28 29 30 31 33 34 35 36 37 38'i9 40 41 42 43 44 45 46Fs 49 50 51 52 ATMS RXT N31 t132 N35 N36 NP PRCS LPIR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GENBKR1 Git(BKR2 BUS11A BUS118 BUS12A BUS128 Bl}A12A 8118128 PCV LSUNPA LO942E L0943E L0942D L0943D L0942C LO943C L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TAKAMiD TAVGBMID LRV TCCORE FAUXFMA FAUXFMB BKRO81 BKR082 V3505 v3504 ANTICIPATED TRANSIENT M/0 SCRAN REA"TGR TRIP BREAKER STATUS SOISCE RANGE DETECTOR N-31 SGlHCE RAt(GE DETECTOR N-32 INTERNEDIATE RANGE DETECTOR N-35 INKFFDIATE RANBE DETECTOR t("36 AVERACE NUCLEAR POWER RiACTOR COOLANT SYSTEN AVG PRESS PRESSURIIER AVERAGc LEViL REKTOR CCCLA."O'OOP A AVG FLQM REA.TGR CGOLNT LOOP 8 AVG FLGM RCPA BREAKER CAUS" RX TRIP RCPB BREAKER CAUSE RX TRIP It,%RE TC SUBCOGLcC) NARGIN STN Giti'NARROW RA%E AVG LEVEL STN GEN 8 NARROW RAhGE AVG LEVEL STN CEN A AVERAGE PRESSURE STN icEN 8 AVERAGE PRESSURE GitKRA!OR GN LINE BREAKER 1G1372 GBFRATOR ON LINE BRcEAKcER 9X1372 BUS 11A SIMPLY BREAKER BUS 118 SUPPLY BREAKER NOT TERNINATEB ON PPCS (7/19/91)t(OT TERNINATED ON PPCS (7/19/91)BUS 11A TO 12A TIE BREAKER BUS 118 TQ 128 TIE BREAKER CQNTAIt(tiENT AVERAG" PRcESSURE COtlTAI)INENT SUNP A AVERAGE LEVEL SUtP 8 LEVEL 8 INCHES (TRA!N A)SUtP 8 LEVEL 8 INCHicS (TRAiN 8)SUtF'LEVEL 78 INCHES (TRAIN A)SUi%'LEVEL 78 INCHES (TRAIN 8)SUP 8 LEVEL 113 INCHES(TRAIN A)SUNUP 8 LEVEL 113 ItKHES(TRAIN 8)SUtP 8 LB'80 INCHES(TRAIN A)SUtP 8 LEVEL 180 INCHES(TRAIN 8)SUtt?8 LEVEL 214 It<CHES(TRAIN A)SU"P 8 LEVEL 214 It(CHcS(TRAIN 8)RCLA HGT LEG TEtiPERATURE RCLB HOT l.EG TENF'ERATUR-" RCLA COLD LEG TEIZERATURE RCLB COLD LEG TEYiPERAT(BE RCLA TAVG (THOT/TCGLD MIDE RNG)RCLB TAVG (THOT/TCGLD MIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.l Ih ORE TC AVERAGE TBP S/6 A:OTAL AUX Ftt'DMATER FLOW S/6 8 TOTAL AUX FEEOMATER FLOW NTR AUXILIARY FEEDMATER PUIIP A tlTR AUXILIARY FEEBMATER PU)IP 8 AUX FM PUI(P STEA)I SUPPLY VALVE A AUX FM PUtiP STEAN SUPPLY VALVE 8 Ot(GN CLOccD CLOSED ATWS AI.RN RX TRIPPED ALRN 1.27497+04 6009 1.27937~04 G009 4.46682-10 6009 3.64755-10 G009 F 00 6009 704.HALN.0 LALN.0 It(HB.0 It(HB TRIPPED ALRtl TRIPPED ALRtl-8.9 LAL>>38.8 6009 43.6 GOOD 1010.6009 1002.6009 TRIPPED ALRN TRIPPED ALRN TRIPPiD ALRtl TRIPPED ALRI(t/OT TRIP DiL t(OT TRIP DcEL NOT TRIP ALRN NQT TPIP ALf4 28.Z HALI(lb.2 KALI!LGMcER 6009 LOWiR 6009 LOWER 6009 LOMER GOOD LOMER 6009 LBERR 6009 LOWER G009 LOWER G009 LOMER G009 LOWER GOOD 512.7, 6009 516.9 6009 354.3 6009 201.3 6009 433.5 6009 361.6 GOOD 54.3 LALN 507.0 600>>49.6009 51.6009 G009 6009 GOOD 6009 CPS CPS ANP ANP/PSIG i/D=GF/X PSIG PSIG PSIG FEET DE6F DEGF BiGF DEGF DE6F DE6F/BE6F GPiN GPN NGV 17)1993 09:15 R.E.GIt5A SIMLVTOR TREND GROUP ASSIGIENT I)")MARY PAGE 2GRGL'P: EVEt<T1 PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID, DFS"RIPTIGN VALUE QUAL E.U.53 FSIA 54 FSIB 55 P 2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 SAF""TY INECTIOM LOOP A AVG FLOW SAFETY IN:ECTION LOOP B AVG FLOW SERVICE MATER PUttPS A<<" B HB&R SENICE WATER PUMPS C h D HEADER SBNICE MATER PUttP A SERVICE MATER PUtfP B SERVICE MATER PUMP C SHNICE MATER PUttP D GVi Ott GN GW 163.GOOD GPM 281.GOOD PM 87.GOOD PSIG 86.GOOD PSIG GOOD GOGO KGD ROD t(QV 1?i 1993 09'16 R.E.GINA SIMULATOR TREND GROUP ASS IGNNBIT PJN'IARY PAGE GROIP: EVEt(T2 PROCEDURE: EPIP 1-5 PLAtIT STATUS POINT ID 1 F0619 2 LRMST 3 MS033 4 MD033 5 MT033 6 MT250 7 MDT2 8 RO!R02 10 R05!1 R09 12 R34!3 R35 14 R!OA!5 Rli 16 R!2!7 R!OB 18 R13!9 R!4 20 R!8 21 R19 22 R29 23 R30 24 R15 25 RIZA5 26 R!2A6 27 R12A7 28 R!2A9 29 R14A5 30 R!4A7 31 R14A9 32 R!5A5 33 R15A7 34 R!5A9 35 R31 36 R32 3?CVH 38 TCV03 39 TCV07 40 TCVOB 41 TCV09 42 TCV!0 43 TCV!7 DESCRIPTION CGi%'ONENT CGQ'NB LOOP TOTAL FLM REFUELING MATER STORAGE TAII LVL 33 FOOT LEM Mlt(D SPEED 33 FOOT LEVEL MIND DIRECTION 33 FOOT LEVEL TEMPERATUR." 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL H.TA TEMP AREA I-COI(TR(X. ROOM AREA 2 CQI(TAIIENT AREA 5-SPENT FUEL PIT AREA 9"LETDOWN LINE tlONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SL(PLE PANEL COWTAI tlMB1T IODINE I',OWITQR R!OA COt(TA!NNENT AIR PART ICIJ ATE CGWTAIt(MEt(T GAS MONITOR PLWT VENT IODINE MONITOR R!OB AUX BLDG EXHAUST AIR PNTICULATE AUX BLDG EXHAUST GAS M(NITOR LIKIID MASTE DISPOSAL NNITOR STEA!I GEt(ERATQR BLOMDOW DRAIN AREA 29-CGWTAINNEWT HI%RANGE AREA 30-CGt(TAIti&t(T HIGH RANGE COtlDENSER AIR EJECTGR EXHAUST CV VEt(T CHAW 5-LGM RAI(K GAS CV VENT CHAN 6-AREA GAtIA CV VENT CHAN 7-N!0 RAtlGE GAS CV VENT CHAN 9-HIGH RANE 6AS PU5T VEt<T CHAt)5-I.OM RANGE GAS HA"IT VENT Cf!AW 7-NID RAt(GE GAS PLANT VEt(T Cf!At(9-HIGH RANGE GAS AIR EJECTOR CHAW 5-LGM RANGE GAS AIR EJECTOR CHAt(7-M!0 RANGE GAS AIR EJECTOR CHAW 9 HI RANGE GAS AREA 3!STEAN'LINE A (SPlt(6)AREA 32 STEAN LINE B (SPING)CV HYDROGEN COt(CEt(TRATIOt(CV BASENEt(T L"VEL 6FT TEMP (I3 CV It(TERNEDIATE LVL 6FT TEtIP II?CV IWTERI(EDIATE LVL 6FT TEMP I8 CV INTERMEDIATE LVL 6FT TEtlP I9 CV INTERNEDIATE LVL 6F'T TEMP IIO CV QPERATItiG LEVL 6FT TEMP ttl?VALLEY MAL 8.00638+N 1~40241~03 4.20511-05 2.67992<2 4.2051!-05 9.99987-04 2.30991-06 4.62984M 9.l099?M 6.2298~1.80975-05 1.52999-03 !.01004-02 1.01004-02 .0 203.1 6009 6000 G000 6000 K00 6000 6000 GOOD 6000 K09 G000 6009 6000 G000 6009 215.8 K09 215.7 GC00 215.8 2!5.7 228.2 884.LALN 93.5 6000 6.0 K00 356.6000 43.3, GOOD 43.9 6000~6 6009 8.75992"02 6000 7.80727403 HALN 3,09029~M 6000 2.66072+01 6000 3.14412+00 GGOD 1.096484N GOD0 9.66051+06 HALI(9.57744+06 HALM 1.01303407 HEt(6 8.45036~N 6000 2.55932+02 GOOD 5,40910<01 6000 I~05925403 6000 I~99813<03 6000 8.N638~00 6000 E.U.GPN/NPH DEG.DEGF DEGF DEGF t8/HR ts/HR N/HR tm/HR%/HR ta/HR CPM C%CPN CPM CPN CPM CPN CPN R/HR R/HR CPN UCI/CC t8/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC NR/HR N/HR/0""GF DEGF DEGF DEGF DEGF DEGF Time: 0910 Message: 22 GINNA STATION 1993 EVALUATED EXER ISE MESSAGE FORIVI MMMI: A III ygg<<ITBBT B gl gA ll yB Igl gg BB for RHR System leakage per E-1 and"8" RHR pump trip problem.Simulated Plant Conditions: See the Attached Mini-Scenario ~Messa e: """THIS IS AN EXERCISE>>>>>> FOR CONTROLLER USE ONLY Controller Notes: 1)Provided information verbally when appropriate actions are simulated or investigations conducted. Antici ated Results: 1 j As per Mini-Scenario. GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Checking Auxiliary Building Sub-Basement for RHR system leakage per E-1 and"B" RHR Pum ri roblem.Expected scenario start time: 0910 hours INITIAL CONDITIONS: 'CS has experienced a large break LOCA.'A" and"B" RHR pumps running.METHOD OF INITIATION: 'tep 18 of E-1 dispatches an Auxiliary Operator/TSC Team to check the Auxiliary Building Sub-Basement for RHR System leakage.'t is expected that this action will be requested in conjunction .with the checking of the tripping of the"B" RHR pump at 0915 hours.INDICATIONS: CONTROL ROOM: 'larm window J-9 (Safeguard Breaker Trip).EXPECTED SEQUENCE OF ACTIONS'Investigate Auxiliary Building Sub-Basement for signs of RHR system leakage.='otice water dripping from the large pipe between Containment and MOV-850A.Notice, after closer inspection of the dripping water, what appears to be an approximately 3 inch crack at the bottom of the pipe.'otice that radiation levels in the area are increasing rapidly.

'nvestigate"B" RHR pump for signs of any problems: 'otice burnt insulation smell.'otice motor is hot to the touch.'eport all of the above observations to the Control Room/TSC at 1000 Hours i.e.no before or no a er~FINAL CONDITIONS: Observations are reported to Control Room at 1000 Hours and Auxiliary Operator/TSC Team leaves the area immediately due to increasing radiation. I GINNA STATION 1993 EVALUATED EXERCISE Time: 0915 Message: 23 MESSAGE FORM MMM: M I C<<IC Simulated Plant Conditions: ~Messa e:<<<<<<THIS IS AN EXERCISE""" The following annunciator is received:~J-9 (Safeguard Breaker Trip)'OR CONTROLLER USE ONLY Controller Notes: 1)When board operators check Control Board, inform them that the"B" RHR pump switch light indicates a white light.2)Operators should attempt to restart the"B" RHR pump 5 times per AR-J-9.IT Wll I NOT RESTART.Antici ated Results: 1)Operators should try to restart the"B" RHR pump 5 times per AR-J-9.IT WILL NOT RESTART.2)3)Operators should notify an Auxiliary Operator to check the"B" RHR pump and motor.An Auxiliary Operator may already be in the Auxiliary Building per step 18C of E-1.Operators should notify the TSC of the tripping and failure to restart of the"B" RHR pump. 4)Operators performing the applicable actions of E-1.5)TSC should send a team into Auxiliary Building to check out the"8" RHR pump if Auxiliary Operator not already in there.6)TSC should be evaluating the loss of safeguards equipment and be expediting repairs as quickly as possible.7)TSC should be informing the EOF of plant status, actions being taken and any required needs.8)EOF should be evaluating plant conditions and taking actions as required. Time: 0920 Message: 24 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~Mf: 8 I C tR Simulated Plant Conditions: ~INesse e:+""THIS IS AN EXERCISE""" The following annunciator is received:~J-24 (Emergency Diesel Gen I A Panel)FOR CONTROLLER USE ONI Y Controller Notes: 1)When board operators check Control Board, inform them that the"A" Emergency Diesel Generator indicates no voltage.Antici ated Results: 1)Operators should send an Auxiliary Operator out to the"A" Emergency Diesel Generator Room to check the local alarm panel and the Emergency Diesel Generator. 2)Operators should inform the TSC of the tripping out of the"A" Emergency Diesel Generator. Time: 0920 Message: 25 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM A*ii~li iOp<<1 ki i9"A'" E g yO'i I G L Alarm Panel and the Emergency Diesel Generator. Simulated Plant Conditions: See the Attached Mini-Scenario ~Messe e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate actions are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenario. GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Checking"A" Emergency Diesel Generator Local Alarm Panel and the Emer enc Diesel Genera or.Expected scenario start time: 0920 Hours INITIAL CONDITIONS'"A" Emergency Diesel Generator running due to a'safety injection activation at 0910 hours.'afety Injection was activated due to an RCS large break LOCA.METHOD OF INITIATION: 'A" Emergency Diesel Generator trips out at 0920 due to low level lube oil pressure.'ontrol Room requests Auxiliary Operator to check the local alarm panel and the emergency diesel generator. INDICATIONS'ONTROL ROOM: 'larm window J-24 (Emergency Diesel Generator 1A Panel).'o voltage on"A" Emergency Diesel Generator. LOCAL: "Lube Oil Low Pressure" A'larm.EXPECTED SEQUENCE OF ACTIONS: 'nvestigate"A" Emergency Diesel Generator local alarm panel an"A" Emergency Diesel Generator for signs of trouble.'otice on Local Alarm Panel a"Lube oil low pressure" alarm.'otice a large amount of oil on the floor by the large lube oil filter on the east side of engine. 'otice engine oil level extremely low if he checks engine oil level.'eport all of the above observations to the Control Room/TSC at~9935 9 FINAL CONDITIONS: Observations are reported to Control Room/TSC at 0935 hours. Time: 0925 Message: 28X GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~f: E g YG d Simulated Plant Conditions: ~IVlesss e: "+"THIS IS AN EXERCISE">>" Declare a SITE AREA EMERGENCY in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification; EAL: Reactor Coolant Leakage (RCS): LOCA Identified Inside Containment and Sl Total Flow)100 GPM using Fl-924/FI-925, FOR CONTROLLER USE ONLY Controller Notes: 11 ll lylfG RG GYR d d 1 d.if emer enc classification discussions are in ro ress.Antici ated Results: 1)Deliver contingency message if SITE AREA EMERGENCY not declared or is not being discussed. Time:~09 0 Message: 27 GINNA STATION 1993 EVALUATED EXERCISE IVIINI-SCENARIO <<<<<<t:<<I<<C<<Itl Simulated Plant Conditions: See Attached Sheets~Messe e:<<"<<THIS IS AN EXERCISE">>" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1)Operators performing the applicable actions of E-1. 1993 EVALUATED EXERCISE Time: 873<MAZOR PARAMETERS ENGINEERED SAPEGUARDS Reactor Shutdown ES NO N-31 OO CPS N-32~~CPS N-35~o-/I AMPS N-36~o~iAMPS.Avg.Nuclear Power Q?RCS Pressure~3PSXG PRZR Level QF0 A RCP RUNNING STOPPED B RCP RUNNING STOPPED lA S/G Level~ZS~1B S/G Level lA S/G Pressure gj~6 PSIG 1B S/G Pressure>'f PSIG Turbine/Generator 0 LINE/FFLINE 4 KV Buses NERGIZE DEENERGIZED 480V Buses NERGIZE/DEENERGIZED DC Batteries A~90 VOLTS B~3d VOLTS Cnmt Pressure~I PSIG Cnmt Sump A Level la 2 FEET Cnmt Sump B Level)7/~9 INCHES" Loop Hot Leg OF A Loop Cold Leg i0.8'F B Loop Hot Leg g73'I'F B Loop Cold Leg~+OF RVLIS*CET 0F S/G A Total Aux FW Flow~GPM S/G B Total Aux FW Flow~/GPM DIESEL GENERATORS A.RUNNING UNLOADED STBY OS B.RUNNING UNLOADED STBY OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TBY OOS ENGINEERED SAPEGUARDS Hi h Head S..Pum s FI-924 5 GPM FI-925 GPM 1A.INSERV STBY OOS 1B.INSERV STBY 1C.NSER STBY OOS BAST Leve=0 Low Head S.I.Pum s FI-626 OO GPM 1A.NSER STBY OOS RECIRC 1B.INSERV STBY 0 RECIRC RWST Level=Containment S ra Pum s FI-931A 0 GPM FI-931B A GPM 1A.STBY OOS 1B.NSER STBY OOS NaOH,Tank evel=QQ Containment Recirc Pans 1A.STBY OOS 1B.INSERV STBY OOS 1C.S R STBY OOS 1D.INSER STBY OOS Post Accident Dampers OPEN CLOSED Service Water Pum s 1A.STBY OOS 1B.STBY OOS 1C.STBY OOS 1D.S STBY OOS A&B Header Pressure PSIG Com onent olin Water Pum s 1A.SER STBY OOS 1B.INSERV TB OOS Surge Tank Level=~>Aux.Fee ater Pum s 1A.STBY OOS 1B.NSERV TBY OOS Turb.Driven INSERV TB CST Level~~~a FEE OOS Standb Aux.Feedwater Pum s 1C.INSERV OOS 1D.INSERV STB OOS*CET=Average of Selected'Core Exit Thermocouples NQV 17i 1993 09:29 R.E.GINA SIHL&TQR PAGE 1 TREND GROUP ASSIGtttKt(T S(J)IHARY GROUP: iVENT1 PROCEDURE: EPIP 1-5 PLAttT STATUS POINT!D DESCRIPTION VALL'E ()UAL E.U.2 3 5 6 7 8 10!3 i4!5 ib (7 18 20 21 22 24 25 26 27 28 29 30 3!32 33 34 3J 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 ASS RXT N31 N32 t)35 N36 HP PRCS LP2R FRCLA FRC'RXT16 RXT}7 TSUBTC LSM LSBB PSBA PSGB GER!BEIL((KR2 BUS1}A BUS}}B BUS}2A BUS128 Bl}A}2A 8!18128 PCV LSU;"PA L0942E L0943E L0942D L09439 L0942C L09430 L09428 L09438 L0942A L0943A T0409A T04}OA T0450 T0451 TAVGAMID TAVGBNID LRV TCCORE FAUXFNA FAUXFNB BKR081 BKRO82 V3505 V3504 At(TICIPATED TRANSIENT N/0 SCRAN REA.TGR TRIP BREAKER STATUS SQRCE RANGE DETECTOR I(-3}SOIRCE RANK DETECTOR N-32 1)ITERHEDI ATE RANGE DETECTOR N-35 INl cRHiDI ATE RANGi DETECTOR N-36 AVERAGE NL(CLEAR PQ)IER RiACTOR COOLANT SYSTEHi AVG PRESS PRESSURI2ER AVERAGc l&S REACTOR COOLANT LOOP A AVG FLFA REACTOR CGOLNT LOOP 8 AVG FLN RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSL RX TRIP ItiZR TC SUBCOOLED t}4%IN STH GEN A t(ARRO)t RANGE AVG LEVcJ.STH BEI'i't)ARRO'A RAN6E AVG LEVciL STH BEN A AVERAGE PRESSJRE STH Bitt 8 AVERAGE PRESSURE BcC=RATGR GN LINE BRcEAKER!61372 GitKRATQR ON LINE BREAKER 9X}372 BUS 11A SL'PPLY BREAKER BUS 118 SUPPLY BREAKER IQT TcRHINATED ON PPCS (7/!9/91)NOT TERHINATED Ot(PPCS (7/19/91)BUS!!A TG 12A T!E BRiAKER BUS 118 TO 128 T!E BREAKER CONTAII,'Hit(T AVERABc PRESSURE CGNTAINHENT SUt}P A AViRA6E LEVEL S(JP 8 LEVciL 8 INCHES (TRAIN A)SU~>>'LEVEL 8 INCHES (TRA!t(8)SU"P 8 LEVEL 78!NCI:"S (TRAIN A)SU%8 LEVEL 78 INCHES (TRAIN 8)SUHP 8 LEVEL l}3 INCHES(TRAII(A)SUN'LEVEL 113 INCHES(TRAIN 8)SSP 8 LEVEL 180 INCHcS(TRAIN A)SUtP 8 LEVEL 180 INCHES(TRAIN 8)PJ'S 8 LEVEL 214 Iti HES(TRAIN A)SUtP 8 LEVciL 214 ItiCHES(TRAIN 8)RCLA HOT LEG TEHPERATSK RCLB HOT LEG TEHPERATURE RCLA COLD LEG TENPERATLRE RC(LB COLD LEG TENPERATURE RCLA TAV6 (THOT/TCO(9 WIDE RNG)RCLB TAVG (THOT/TCOLD HIDE RNB)RHETOR VESSEiL AVcERABE LEVEL E}.l ItiiCGPE TC AVERAK TEHP S/G A TOTAL AUX FEEDS(ER FLGN S/G 8 TOTAL AUX FEEDKA(cR FLM HTR AUXILIARY FEED'AATER FUI(P A t!TR AUXILIARY FEEOWATER FU)IP 8 AUX Fti PUNP STiAN SL(PPLY VALVE A A(JX FM PUK STEAN SUPPLY VALVE 8 AT)IS RX TRIPPED 4.0}328~0} 4.}543}+0} 1~00925-1}1.00461-1} .00 39.~0~0.0 TRIPPED TR!PPED 5.7 42.7 47.7 885.869.TR!PPED TR!PPED TRIPPED TRIPPED NOT TRIP t(0":(TRIP t(OT TF(IP t(QT TRIP 4.91 3}.2 HIBHEP, HIB)(HIBIKR HI6HEP.LOMER L04'ER LO)lER LQ)iciR LG)IER LONER 271.5 273.9 148.8 131.2 210.1 202.5 74.4 265.1 0.}7.GN ON CLOSED CLOSED P5 ALRN ALRt!6009 6009 6009 6009 6009 LALN LALt(i'NHB Iti(IB ALRN ALRII L'kR>>GOOD 6009 6009 6009 ALRt(ALRH ALRH ALRII OEL DEL ALRN A'N HALH HEtiB It(!(9 INHB ALRN ALRII 6009 8009 6009 G009 6009 6009 G009 6009 G009 6009 6009 6009 LALN 600>>C009 6009 GOOD 6009 6009 6009 CPS CPS Al(P AHP PSIG//DEBF/7 PSIG PSIG PSIG FiZT DEGF I)=BF DEGF DEGF DEBF DEGF DFGF GPH GPt! t/OV 17i 1993 09:29 R.E.Glt5A SlttULATOR TREND GRQUP AssIGOEhT BURRY PAGE 2GROUP: LVENT1 PROCEOLSE: EPIP 1-5 PLANT STATUS POINT fn 53 FSIA 54 FSIB 55 P21h0 56 P2161 57 BNR041 58 BKR042 ,59 BKR043 60 INR044 DESCRIPTION SAFETY INJECTION LOOP A,AVG FLOM SAFETY Itt'ECTION LOCiP B AVG FLOM SERVICE MATER PUttPS A h B HEADER SERVICE MATER PUttPS C 5 O HEADER SERVICE MATER PUttP A SERVICE MATER PUttP B SERVICE MATER PUttP C SERVICE MATER PUtlP D ON ON ON ON VALUE 185.380.87.86.QUAL E.U.GOOD GPtt GOOIl Ptt GOOD PSIG GOOD PSIG GOOD GOOD GOOD Goon NOV 17>1993 09:30 R.E.Gite SIMULATOR TRFND GROUP A%16ttMENT SUtlMARY PAGE 1 6ROL'P: EVENT2 PROCEDLtRE: EPIP 1"5 PLANT STATUS I POINT 1 F0619 2 LRWST 3 WSO33 4 WD033 5 WT033 6 WT250 7 WDT2 8 R01 9 R02!0 R05 11 R09 12 R34 13 R35 14 RIOA 15 R11 16 R12 17 RIOB!8 R13 19 R14 20 R18 21 R19 22 R29 23 R30 24 P.15 25 R12A5 26 R12A6 27 R12A7 28 R12A9 29 R14AS 30 R14A7 31 R14A9 32 R15A5 33 R15A7 34 R15A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 fD DESCRIPTION COMPONENT COOLING LOOP TOTAL FLW REFUELIWG WARD STORAG"" TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVP WIND DIRECTIOtl 33 FOOT LEVEL TEMPERATURE -.250 FOOT LEVP TENPERATURE 250 TO 33 FOOT LEVEl.DELTA TEllP AREA I-COWTRO'OON AREA 2-CONTAlt(MENT ARiA 5-SPEt(T FUiL PIT AREA 9-LETDQW LINE NONITOR ARE 34-AU)(BLDG CV SPRAY PL%i~AREA 35"PASS SAMPLE PANEL CONTAINMENT IODINE MONITOR R10A CGWTAI tST AIR PARTI'TE CONTAINMENT GAS MONITOR PLNT VB4T IODINE MONITOR R10B AUX BLDG EXMST AIR PARTICULATE AUX BLDG EXHAUST GAS tlQNITGR LIQJID WASTi DISPOSAL NQtlITQR STEAN GEtFRATGR BL(LDOW DRAIN ARE 29<Qt(TAIWMENT HI%RA)LK AREA 30-CONTAINMENT HIGH RANGE COND" tlSER AIR E JiCTOR EXHAUST CV VB(T CHAN 5-LOW RAtiGE GAS CV VENT C84 6-AREA GAMA CV VENT CHAW 7 NID RANGE GAS CV VENT CHAN 9-HIGH RAKiE 6AS PLOT VENT CH4tt 5-LGW R4NGE GAS PLANT VENT CHAtl 7-NID RANGE GAS PLANT VENT CK4N 9-HIGH RAN6i GAS AIR EJECTOR CHAN 5 LGW RANGE GAS AIR EJiCTGR CHAN 7-tlID RANGE GAS AIR EJECTCR CLIW 9-HI PANGE GAS AREA 31 STEAN LIR"" A (SPIt(6)ARE 32 STEAN LIRE B (SPING)CV HYDROGEN COt(CB(TRATIGW CV BASENEWT LEVH.6FT TEMP I3 CV INTERMEDIATE LVL 6FT TEMP l)7 CV IWTERYiEDIATE LVL 6FT TBP 58 CV IWTERNEDIATE LVL 6FT TEMP ()9 CV IWTERNEDIATE LVL 6FT TEMP I10 CV OPERATING LEVL 6FT TEMP l)17 VALUE LALtl GOOD 6009 6009 GOOD GOOD GOOD GOOD HALN GOOD GOOD GQQD GQQD HALN HALN HENG 6009 6009 GOOD GOOD 6009 6009 6009 GOOD GOOD GQGD 6009 GOOD GQGD GOOD 6009 GOOD GOOD GOOD 6009 GOOD 6009 GOOD GOOD 135.6 6009 135.9 6009 135.6 6009 133.1 892.78.1 5.6 295.43.3 44.0~7 8.81048-02 8.26987+03 3.14412+00 2.66072+01 2.90068+00 1.09648400 9.66051+06 9.95683~06 9.99992+06 1.23027%1 2.48313%2 7.03879tOI 1.0917&03 1.99813+03 8.00638+00 8.00638400 1.40241+03 4.20511-05 2.67992-02 4.20511-05 9.99787-04 2.30991-06 4.62984-06 9.10997M 6.22985-06 1.80975-05 1.52999-03 1.01004-02 1.01004-02 .0 138.4 135.9 E.U.GPN X AH D="G.DF6F DE6F DEGF l8/HR%/HR t8/HR NR/HR t8/HR t8/HR CPN CPN CPN CPN CPN CPN CPN CPN R/HR R/HR CPtl XI/CC)8/HR XI/CC UCI/CC UCI/CC XI/CC XI/CC XI/CC XI/CC XI/CC NR/HR t8/HR I/9" GF DEGF DEGF DE6F DEGF DEGF Time: 1000-1 500 Message: 27.1 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM:TECE g C Pt.Eggtg TM g dg pp M tt~Massa e: """THIS IS AN EXERCISE""" Please provide appropriate responses to the following questions/issues raised by simulated NRC staff: 1.What is the status of emergency? 2.What if any PAR's have been recommended? 3.NRC response team members will be arriving in Rochester; please assure adequate working space at EOF (2 people), TSC (2 people)and JENC (1).4.Please provide qualified staff member to man the HPN line in the EOF.5.Please have most recent radiological and meteorological data provided via the HPN line or by fax.6.How many EBS messages have been issued?'~What PARS have been implemented by the Counties and NYS?FOR CONTROLLER USE ONLY Controller Notes: 1)Deliver throughout the Exercise between 0930-1400 hrs.per Controller discretion. 2)Deliver by telephone call or by speed message.Actions Ex ected: 1)TSC Emergency Coordinator or EOF/Recovery Manager should be responsive to information requests, but should not allow the simulated NRC staff member to prevent them from attending to their principal duties. Time: 0935 Message: 28 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM RpiTRpiigAEgyOi IG<<P Simulated Plan Conditions: See the Attached Mini-Scenarios ~essacee:<<<<<<THIS IS AN EXERCISE"<<" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information when appropriate actions are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenarios. GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: "A" Emer enc Diesel Generator. Scenario expected start time: 0935 INITIAL CONDITIONS: The diesel generator tripped on a"Lube Oil Low Pressure" at 0920 after being started at 0910 from a safety injection activation. METHOD OF INITIATION: Remote alarm in the Control Room on"A" Diesel Generator. Auxiliary Operator reports on Low Pressure on Lube Oil was cause for trip, this is reported to Emergency Coordinator of Diesel failure.INDICATIONS: CONTROL ROOM: LOCAL: Alarm on"A" Diesel Generator"Lube Oil Low Pressure" alarm at 45 psi indicator flashing.Oil on floor near lube oil filter and under engine.EXPECTED SEQUENCE OF ACTIONS: Trouble report written for repair of"A" Diesel Generator. Planner and Mechanic sent to Diesel Room to trouble shoot problem with unit.Team reports back of flange failure at 1005 hours, work order developed to replace gasket and refill the engine with lube oil.Maintenance crew sent to Diesel Room to clean up the oil spill.(1/~hours to complete)Inventory control personnel make arrangements to go to warehouse off site to bring in lube oil for Diesel Delvac 1240.Security will need to be contacted to allow for transporting oil through gate.Procedure M-15.2"A" or"B" Diesel Generator Minor lns ection and Maintenance Chan e Flex Hos on Lube Oil S s em.M-37.130 Dis ssembl S.Re ssem I of Pi e Flan e Connec ions.Steam Fitters and Machinist go to shops for tools and gasket material to replace failed gasket and return oil to sump.Gasket is replaced by fitters in a 1 hour time frame.The machinist add oil to engine after oil arrives from warehouse. (1 hour to pump in 225 gals of cold oil).Oil level in sump returned to proper level, line up of engine made by operation to put unit back into service.REPAIR TIME: The repairs to the engine to be completed by 1145, estimate of 2/2 hours to complete.(Note: this time frame may not be long enough due to the oil being stored in offsite warehouse in real conditions.) FINAL CONDITIONS: 1A Diesel Generator is back in service supplying power for the scenario.(1155 hours) GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: "A" Emer enc Diesel Genera r Problem from L w Lube Oil~Press re.Scenario expected start time: 0935 INITIAL CONDITIONS: Started automatically because of Safety Injection actuation, tripped out at 0920 hours.METHOD OF INITIATION: Tripped out, operations sent out Auxiliary Operator to investigate. INDICATIONS: ""A" Emergency Generator tripped out at 0920 hours." Auxiliary Operator checks local alarm, low lube oil pressure." Located large amount of oil on floor by the large lube oil filter on'ast side of the engine.EXPECTED SEQUENCE OF ACTIONS: " Repair team investigation finds oil leak on flange between pump and oil filter." Reports to TSC at 1005 hours approximately 2/~hours for repairs, and obtains holds as required for maintenance," Fitters simulates installing new gasket." Inventory Control transporting oil from storage." Mechanics simulates replacing oil as required." Maintenance to clean area as required for safe operation. FINAL CONDITIONS: At 1145 hours the repair team will report to TSC that the Generator repairs on"A" Diesel will be completed in approximately 15 minutes.At 1155 hours the repair team will report that repairs are completed. Time: 0945 Message: 29 GINNA STATION 1993 EVALUATED EXERCISE IVIESSAGE FORIVI 5 I 5<<IR Simulated Plant Conditions: See the Attached Sheets Messa<ee:>>">>THIS IS AN EXERCISE">>>>FOR CONTROLLER USE ONLY Controller Notes: 1)At 0935 hours the Auxiliary Operator checking the"A" Emergency Diesel Generator trip problem reports his observations to Control Room/TSC.See 25.Antici ated Results: 1)Operators should inform TSC of"A" Emergency Diesel Generator problem.2)TSC should send a repair team out to evaluate and repair the"A" Emergency Diesel Generator problem.R')RR IRR 1993 EVALUATED EXERCISE Time: MAZOR PARAMETERS Reactor Shutdown YE NO N-31 CPS N-32~L CPS N-35~0~(AMP S N-36/~~/AMP S Avg.Nuclear Power CI RCS Pressure E PEXG PRZR Level O A RCP RUNNING 0 B RCP RUNNING S OPPE 1A S/G Level.r 1B S/G Level 1A S/G Pressure PSIG 1B S/G Pressure 2 PS G Turbine/Generator ONLINE/FLINE 4 KV Buses ENERGIZE/DEE RGIZED 480V Buses NE GIZED DEENERGIZED DC Batteries A~VOLTS B/ZO VOLTS Cnmt Pressure o~fPSIG Cnmt Sump A Level~MFEET Cnmt Sump B Level+'$00/)INCHES " Loop Hot Leg 2 OF A Loop Cold Leg@g,Z OF B Loop Hot Leg;M4M'F B Loop Cold Leg~(2 OF RVLIS 8'I e*CET 0F S/G A Total Aux FW Flow&GPM S/G B Total Aux FW Flow f GPM DIESEL GENERATORS A,.RUNNING UNLOADED STBY OS B.RUNNING UNLOADED OOS TSC RUNNING UNLOADED T OOS Security RUNNING UNLOADED TB OOS ENGINEERED SAFEGUARDS Aux.Feed ter Pum s 1A.SERV STBY OOS 1B.INSERV STBY OOS Turb.Driven INSERV STB OOS CST Level~FEET ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 GPM FI-925 2.3 GPM 1A.INSER STBY OOS 1B.INSERV STBY 0 1C.NSER STBY OOS BAST Leve Low Head S.I.Pum s FI-626/00 GPM 1A.R STBY OOS RECIRC 1B.INSERV STBY S RECIRC RWST Level=Containment 8 ra Pum s FI-93 1A~~~GPM FI-93 1B&GPM 1A.R STBY OOS 1B.INSERV STBY OOS NaOH Tank Level=~G 4 Containment Recirc Pans 1A.ER STBY OOS 1B.NSE STBY OOS 1C.NSER STBY OOS 1D.INSER STBY OOS Post Accident Dampers PE CLOSED Service Water Pum s 1A.SER STBY OOS 1B.SER STBY 0 S 1C.'ER STBY OOS 1D.SE STBY OOS A&B Header Pressure PSIG Com onent Coo1in Water Pum s 1A.NSERV STBY OOS 1B.INSERV TB OOS Surge Tank Level=., Standb Aux.Feedwater Pum s 1C.INSERV B OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples t(OV 17i 1993 09:44 R E GI I't(A SItiULATQR TREND GROUP ASSIGNNEhT SUt(NARY PAGE 1 0 GROI': EVEt(TI PROCEDURE: EPIP 1-5 PLANT STATUS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 2Q 21 22 23 24 25 26 27 28 30 31 32 33 34 35 36 37 38 39 40 41 43 44 45 46 47 48 49 5Q 51 52 DESCRIPTIQN ANTICIPATED TRANSIENT W/0 SCRAN REA TOR TRIP BREAKER STATUS SMCE RAtiK DETECTOR)i~31 SOIKE RANGE DETECTOR N-32 It)Tc&tKOIATE RAt<SE DETECTOR N-35 INTERt(EDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWcR REACTOR COOLANT SYSTEN AVG PRESS PRESSURIZER AVERAGE LEVEL REiACTGR CGQLAi'T LQQP A AVG FLOW RBKTOR COOPT LOOP 8 AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCGRE TC SUKOGLED t(AKilN STtk GEN A NARROW RANGc AVG LEVEL STtt Gal 8 tNSGW RANGE AVG LEVEL STN GEN A AVERAGE PRESPJRE STt(GEtii 8 AVERAGE PRESSURE GENERATOR Otk LINE BREAKER 1G1372 6B&~ATGR Gt(LINc BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 118 SL'PPLY BREAKER t<QT TERtfltiATED ON PPCS (7/!9/91)NOT TERNINATED GN PPCS (7/19/91)BUS 11A TG 12A TIE BREAKER BUS 118 TQ 128 TIE BREAKER CONTA It(t(ENT AVERAGE PRHSURE i".QNTAINl'~ENT M(P A AVERAGc LEVEL SUN'LE4EL 8 It(CHES (TRAIN A)SUl..8 LEVEL 8 ItlCHES<TRAIN 9)SUiP 8 LEVEL 78 It)CHES (TRAIN A)SL&8 LEVEL 78 ItiCHcS (TRAIN B)SCP B LEVEL 113 INCHcS(TRAIN A)SU%'LE4EL 113 INCHES(TRAIN B)SUi%'LEVEL 180 INCHES(TRAIN A)SUtF'LEVEL 180!NCHES(TRAIN B)SNP 8 LEVEL 214 INCHES(TRAIN A)SU%'LE4EL 214 INCHFS(TRAIN B)RCLA HOT LEG TEt(PERATURE RCLB HOT (.EG TE)(PERATUK RCLA COLD LEG TPiPERAT(JK RCa COLD LEG TE)(PERATm RCLA TAVG (THQT/TCOLD WIDE RNG)RCLB TAVG<THQT/TCOLD WIDE Rt(G)REA"TOR VESSEL AVERAcc LEVEL Ei.l INCGRE TC A'/ERAGE TEiiP NTR AUXILIARY FEEDWATER PUN'AUX FW PUP STEA))SUPPLY VALVE A AUX FW PU!P STEA)l SUPPLY VALVE 8 POINT ID ATWS RXT N31 N32 tf35 N36 tP PRCS LP1R FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GENBKRI GMNR2 BUS11A BUS/8 BUS12A BUS128 811A12A 8118128 PCV LS(NPA L0942E L0943E L'0942D LO9439 L0942C L0943C L0942B I 09438 LO'942A L0943A T0409A" T0410A T0450 T0451 TAVGAWID TAVGBWID LRV TCCORE FAUXFWA'/6 A:OTAL AUX FEEDMATER FLOl(FAUXFMB S/6 8 TOTAL AUX FEEOMATER FLOW BKR081 t)TR AUXILIARY FEEDWATER PUtiP A BKR082 V3505 V3504 ATWS RX TRIPPED 4.12570+01 3.71962+01 1'0925-11 1.00461-11 .(X)34,~0 ,0~0 TRIPPED TRIPPED 16.8 43.1 48.1 847.825.TRIPPED TRIPPED TRIPPED TRIPPED NQT TRIP NQT TRIP ttQT TRIP t(QT TR!P.96 31.2 HIGHER HI6HER HI6HER HI6HER HIGHER HIER LO)lER ALRtf ALRtf GOOD 6009 GOOD 6009 GQQD LALN LALtf IN)I INHD ALRN ALRtf LWR~GQOD GQOD 6009 GOOD ALR)f ALR)(ALRt(ALR((DB DEL ALfm ALRt(H((Rt(HBi6 IM It(HB INHB ItBD ALRt(ALRl'i GOOD 142.2 206.3 206.0 78.1 248.4 0.ON ON CLOSED CLOSED 6009 GQQD GOOP LALN 6001 6009 6009 6009 , GOOD GOOD 6009 LQ)(ER 6009 LONER GOOD LOWER 6009 254.2 6009 269.7"6009 158.4 GOOD E.U.CPS CPS M'P/PSIG/X DEGF Y.i/PS16 PSIG PSIG FLET DEGF DEGF DEGF DEGF DEGF KGF DEGF GPtf GPt( ttOV 17~1993 09'44 R.E.GIWQ SItCLATGR TREIS GROUP ASSIGAi&7 SUttttARY PAGE 2 6ROLtP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTIOtt VALUE OUAL E.U.53 FSIA 54 FSIB 55 P2 160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 S~c INJECTION LOOP A AVG FLOW SAFETY INACTION LOOP 8 AVG FLOW SBSICE WATER PUttPS A 4 B HEADER SERVICE MATER PUttPS C 4 9 HEADER SPLICE MATER PUttP A SERVICE WATER PUttP B SERVICE MATER PUttP C SERVICE MATER PUttP 9 ON ON ON Ot4 163.293.87.86, GOOD GPtt GGGD GW GOOD PSIG GOOD PSIG GOOD GOOD GOOD GOOD

NOV 17~1993 07:45 P,.E.GINNA SltLLATOR TREtlD GROUP ARIGNNEhT

SUMMARY

GROUP: FViNT2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID F0619 2 LRMST 3 MS033 4 MD033 5 MT033 6 MT250 7 MDT2 8 R01 9 R02 fo ROS ff R09 12 R34 13 R35 f4 R10A 15 R11 16 R12 17 R103 18 R13 R14 20 R18 21 R19 22 R29 23 R30 24 R15 25 R12A5 26 R12Ab 27 R12A7 28 R12A9 29 R14A5 30 R14A7 31 R14A9 32 R15A5 33 R15A7 34 Rf5A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 DEPAIPTION CEPONENT CGO'NG LOOP TOTAL FLW REFUELING MATBt STORAGE TAlC LVL 33 FDOT LEVEL MIND SPEED 33 FOOT LEVB MIND DIRECTION 33 FOOT LEVB.TENPERATURE 250 FOOT LEVB TENPiRATURi 250 TO 33 FOOT LEVEL DELTA TB(P AREA I-COtlmO ROON NB 2-CONTAIeENT AREA 5-SPENT FlCL PIT AREA 9-LETD(M Lit(i MONITOR AREA 34-AUN BLDG CV SPRAY PUNP AREA 35-PASS SANPLE PAWL CONTAINMENT IODItti NOtlITOR RiOA CONTAINNENT AIR PARTIC(LATE COtfTAIt(NENT GAS NONITGR PLNlT VENT IODItii l'iOtfITOR R103 AU)(BLDG EXHAUST AIR PNTICULATE AU)(BLDG EXHAUST GAS NNITGR LIQUID MASTF DISPOSAL Nt(ITOR STEAN GENBQTOR BLOMDON DRAiN AREA 29-CONTAIt(NEtfT HI%RANGE AREA 30-CGtfTAItlNcJ(T HI%RANK CGtlDEtlSER AIR EJECTOR EXHAUST CV VB(T CS)N 5-LOM RANK GAS CV VEN", CHAN 6-AREA GAlW CV VEtlT Cath 7-NID RA)<K GAS CV VENT CHAtl 9+IGH RAtÃaE 6AS PLA'i~i VENT CHAtt MOM PLUNGE GAS PLOT VENT CHAtf 7-NID RANGE GAS Pfu)Vite CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOM RAN6E GAS AIR EJiCTGR NAtl 7-NID RAtfGE CAS AIR EJECTOR CHAN 9-Hl RANGE GAS AREA 31 STEAN l.llF A (SPlt(G)AREA 32 STEAN LINE 8 (SPING)CV HYDR06EN CGNCEt(TRATION CV BASBHT LcVEL 6FT TENP N3 CV INTERNEDIATE LVL 6FT TENP t)7 CV IhiERNEDIATE LVL 6FT TENP t)8 CV IHTERNEDIATE LVL 6FT TENP ()9 CV It(TERNEDIATE LVL 6FT TENP ttfo CV OPERATltiG 'VL 6FT TENP l)17 VALUE QUAL 892.LALN 59.9 GOOD 5.4 6009 8 600D 43.5 GOOD 45.0 GOOD 1.5 600a 9.33~6009 8.03526+03 HALN 3.03739~00 GOOD 2.91742+01 GOOD 3.01995+00 GOOD 1.09648+00 GOOD 9.87i3686 HALN 1.01741+07 HBiG 1.02182+07 HENG 2.90486+01 GOOD 2.55932+02 GOOD 1.24990+02 GOOD 1'6844+03 Gm 2.!1348<03 GOOD 8.00638~00 GOOD 8.00638~00 GOOD 1.45797+03 GOOD 4.20511-05 GOOD 2,67992"02 GOOD 4.205f1-05 GOOD 9.99987-04 6000 2.3099&5 GOOD 4.62984-06 6000 9.10997-04 GOOD 6.22%&06 GOOD 1.80975-05 GOOD 1.52999-03 6000 1.01004M GOOD 1.01004M 600D.0 GOOD 98.5 GGGD 94,0 GOOD 93.9=GOOD 94.0 GOOD 93,9 GOOD 89.4 6000 E.U.PN/NPH DEG, DE6F DEGF DEGF t(R/HR NR/HR NR/HR)S/HR NR/HR NR/HR PN CPN CPN PN CPN CPN PH CPN R/HR R/HR CPN KI/CC ts/HR KI/CC XI/CC KI/CC XI/CC KI/CC XI/CC KI/CC XI/CC NR/HR NR/HR)(KGF DEGF DEGF DEGF DE6F DEGF Time: 0950 Message:~0 GINNA STATION 93 EVALUATED EXER I E MES A E FORM MMM t: 8 I<<C<<IR C Simulated Plant Conditions: ~Massa e:<<""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY 1)If operators check Auxiliary Building Radiation Monitors, inform them that they are beginning to increase slowly.Antici ated Results: 1)Operators performing the applicable actions of E-1.2)Operators should inform the TSC of increasing radiation levels in the Auxiliary'uilding if they notice them increasing, 3)TSC should be evaluating plant conditions and taking actions where required.4)TSC should be informing the EOF of plant status, actions being taken and any required needs.5)TSC should be evaluating the increase of radiation in the Auxiliary Building as to its source and its effect on personnel that may be in the Auxiliary Building (assuming they are cognizant of the increase). 6)EOF should be evaluating plant conditions and taking actions as required.7)EOF Dose Assessment should be evaluating the increasing radiation levels in the Auxiliary Building (assuming they are cognizant of the increase). 8)Repair teams should be performing actions as required to return equipment to service as soon as possible. Time: 1000 Message: 31 GINNA STATION 19 3 EVALUATED EXER ISE MESSAGE FORM.MMMf:~I C<}993 10:00 R.E.GINA SIÃJLATGR MND GROUP ASSIGtOBiT PJMt(ARY PAGE 1 6ROUP: EVENT2 PROCEDURE: EPIP 1-5 PLAt(T STATUS 1 2 3 4 5 6 7 8 9 10}}12 13 14 15 16.'7 18 20 2}22 23 24 25 26 27 28 A9 30 31 32 33 35 36 37 38 39 40 41 43 POINT F0619 LRMST MS033 MD033 MT033 MT250 MDT2 Rol R02 R05 R09 R34 R35 R}OA Rll R}2 R}OB R}3 R}4 Ris R19 R29 R30 R15 R}M R}286 R}2A?R}'ZA9 R14A5 R14A?R14A9 R}5A5 R}5A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV}0 TCV}7 ID DESCRIPT I 0W COMPONENT CGQ'NG LOOP TOTAL FLM REFUELING MATE STORAGE TAtII(LVL 33 FOOT LEVEL MIND SPED 33 FOOT LEVEL MIt(D DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEt"J'ERATURE 250 TO 33 FOOT LEVEL DELTA TPJ'REA}-CONTR(X. ROON AREA 2-CONTAIeEIIT AREA 5-SPENT FUEL PIT NFD 9 LETDQMN LINE MONITOR AREA 34-AUX BLDG CV SPRAY Pttt(P ARB~ASS SAttf'LE PN8 CQttTA ItltIENT IQDIt(E MQltITQR R10A CGtiTAIt(>>ENT AIR PARTICK ATE CQNTAIL"&T GAS tlONITGR PLANT VEt(T IODINE MONITOR R}09 AUX BLDG EXHAUST AIR PNTICUATE AUX BLDG EXf%JST GAS tt(X>IITGR LIQUID MASTE DISPOSAL NNITOR STLAtt GENERATOR BLQMDGN DRAltt ARB 29"CONTAINS(T HIKE!RAtIGE AREA 30-CONTAINMENT HI&I RAtiGE CQtL>~NSER AIR EJECTOR EXHAUST CV Vigil CPJttl 5-LOM RAtiK GAS CV VENT CHAN 6-AI(EA GANA CV V=>(T CM 7-MID RANK GAS CV VENT CHAN 9-HIGH RANGE 6AS PLAUDIT VENT CHAN MOM RANGE GAS PLANT VFNT Ct(AII 7-MID RANGE GAS PAINT VENT CHAN 9-HIGH RANK CAS AIR EJECTOR Ct(AN 5-LGM RANGE GAS AIR EJECTOR CHAW 7-I>ID RANGE GAS AIP, EJECTA CHAN9-HI RAt>C<GAS AP..A 3}STEN LINE A (Plt(G)AREA 32 STEAM LltitE 9 (SPINGt CV HYDRQGBt COtiCENTRATIQN CV BASEYBIT L""VEL 6FT TEY>P tt3 CV IWTERtIEDIATE LVL 6FT TEtIP (I?CV INTERtIEDIATE LVL 6FT TEMP IIB CV ItITERMEDIATE LVL 6FT TEYiP II9 CV It>~icRMEDIATE LVL 6FT TEttP tt}0 CV OPERATING LEVL 6FT TB>P tt}7 VALUE QUAL 892.LALI(41.0 6009 7.1 6009 17.6009 43.5 GOQ9 43.5 6009.0 6009 9.44062M GOOD 8.03526+03 HALN-""95121+00 6009 2.91742+01 G009 2.98539+00 6009}.09648%0 GOOD 9.87}36~06 HALtt 1~00867+07 HENG 1.03962+07 HENS 4.98310<0} G009 2.59268+02 6009 1.95828+02 6009 1.01888+03 6009 2.!}348+03 GOOD 8.00638400 6009 S.OO638+OO 6009 1~45797+03 6009 4.20511-05 G009 2.67992-02 6009 4.205}}M GOOD 9.99987-04 6009 2.3099}M GOOD 4.62984-06 G009 9.!099?M 6009 6.22985-06 G009}.80975-05 GOOD 1.52999-03 6009}.01004-02 6009 1.01004-02 6009~0 6009 82,3 6009 81.?.GOOD 8}.7=6009 81.7 G009 81.7 6009 81.3 6009 E.U.'PM>/tPH IH.KGF KGF DEGF MR/HR t8/HR MR/HR t8/HR t8/HR t8/HR CPtt CPM CPtt CPtt CPM PN CPM CPM R/HR R/HR CPM UCI/CC t8/HR UCI/CC XI/CC tt" I/CC UCI/CC UCI/CC UCI/CC UCI/CC KI/CC tS/HR t8/HR DE6F DEGF DEGF DEGF DEGF DEGF Time: 1005 Message: 32 GINNA STATlON 1993 EVALUATED EXER ISE MESSAGE FORM f: TCCC Simulated Plant Conditions: ~essacee:>>>>"THlS lS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes: 1)Repair team sent out to check the"A" Emergency Diesel Generator problem C f fff f f.Cf<<ff f pf f.f¹28.Antici ated Results: 1)TSC should inform the"A" Emergency Diesel Generator repair team to expedite repairs.2)TSC should inform the EOF of the"A" Emergency Diesel Generator repair team to expedite repairs.3)TSC should inform the EOF of the"A" Emergency Diesel Generator problem and the estimated repair time.4)EOF should be assuming command and control at approximately this time. Time: 1005 Message: 33 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM Si I C I R Simulated Plant Conditions: ~essacee: """THIS IS AN EXERCISE""" The following Annunciators are required: J-29 (480V Transformer Trip)'-7 (480V Main or the Tie Breaker Trip)'-9 (Safeguard Breaker Trip)FOR CONTROLLER USE ONLY Controller Notes: 1)When Board Operators check the Control Room Board inform them that the Bus 14 high side and low side breaker switches indicate white lights and Bus 14 indicates"0" voltage, Also indications of Safety Injection to the core indicates no flow.Antici a ed Resul s: 1)Operators should inform the TSC of the loss of Bus 14 and Safety Injection to the core.2)Operators should try to start the"C" Sl Pump on Bus 16.If they do, the breaker will keep tripping out.They may also transfer the"B" instrument Bus to the maintenance supply. 3)TSC should inform the EOF of the loss of Bus 14 and Safety Injection to the core.4)TSC should be evaluating the time to core uncovery and request that the EOF evaluate this time also.5)TSC may send a team into the Auxiliary Building to turn on the breaker for MOV-851 A.6)TSC may send a team into the Auxiliary Building to check on the loss of Bus 14.7)TSC should try to expedite the repair of the"A" Emergency Diesel Generator. 8)TSC should recommend to the EOF that A GENERAL EMERGENCY should be declared in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification; EAL: Reactor Coolant Leakage (RCS);LOCA Identified Inside CNMT and no ECCS Delivery to the RCS.9)TSC should be evaluating possible methods of water injection to the core, such as cross-tying Bus 14 and Bus 16 or using the"B" Reactor Coolant Drain Tank pump.If TSC decides to cross-tie Bus 14-16, one of the two tie-breakers will not close.If TSC decides to use the"B" Reactor Coolant Drain Tank pump, the suction strainer will plug after approximately 2 minutes of operation and will have to be cleaned prior to any further use.10)EOF, after evaluating plant conditions, should declare a GENERAL EMERGENCY in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification,"EAL: Reactor Coolant Leakage (RCS);LOCA Identified Inside CNMT and no ECCS Delivery to the RCS.Appropriate notifications should be made per EPIP 1-5.h 11)EOF should be making immediate protective action recommendations in accordance with EPIP 2-1,"Protective Action Recommendations". 12)Repairs teams performing actions as required to return equipment to service as soon as possible.

TIme: 1005 Message: 34 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM.>>>>>>: R PI 4 hh hf PL IB 14IB 144 I<

>>>FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information when appropriate actions are simulated or investigations conducted. Actions Ex ected: 1)As per Mini-Scenario. GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Loss of Bus 14 Bus 14 Transformer Expected scenario start time: 1005 INITIAL CONDITIONS: Bus 14 energized. Thermography performed on Bus 14 at 0730 indicates a hot spot on transformer high side connection (Phase A).METHOD OF INITIATION: Bus 14 supply breaker opens (52/14SS). INDICATIONS: CONTROL ROOM: 'nnunciator Windows: "J-7" 480V main or tie breaker trip"L-14" Bus 14 under voltage safeguards 'hite (disagreement) lights: 52/14SS Highside breaker 52/14 Lowside breaker Bus 12A/Unit 15: '50G" Relay tripped (red flag showing)Bus 14/Unit 18B: 'o abnormal indications,"as found" Bus 14 Trans: 'hase A'onnection on the transformer is charred and tracking to ground.EXPECTED SEQUENCE OF ACTIONS:~Repair team forms to: 'nspect Bus 14'nspect Bus 14 transformer Check Bus 14, 480V supply breaker indications 'heck Bus 14, 4KV supply breaker indications ~Obtain holds, clearances, test equipment, and safety equipment. <Simulate meggering station service transformer from Bus 12A/Unit 15 readings: Megger readings: 0 Q phase to ground (phase A)100 Gig Q to ground (phase BSC)Phase to phase resistance <1 QSimulate meggering Bus 14, readings: Megger readings: 150 Gig Q to ground 100 Gig Q (phase-phase) FINAL CONDITIONS: Station service Transform r 14 out of service and requires replacement. Time: 1005 Message: 35 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~fg fP:pi y CP ifgg fgf yij*i P p C P gi Simulated Plant Conditions: ~Masse e:<<<<" THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information when appropriate actions are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenario GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Loss Of Safe In'ec ion Pum 1C SIPC Expected scenario start time: 1005 INITIAI CONDITIONS: Safety Injection Pump 1C is not running METHOD OF INITIATION: SIP1C pump fails to start when attempted from either supply (Bus 14 or 16)~INDICATIONS'ONTROL ROOM: 'us 16 power supply breaker (SIP1C1)opens'hite disagreement light, Bus 16'us 14 deenergized NOTE When Bus 14 is reenergized, if SIPIC2 breaker (Bus 14 supply).is attempted to shut, trips open immediately, white disagreement light.Bus 16/POS13A: 'mptector: "Instantaneous" trip indication 'f meggered-0 Q to ground, 0 Q p to p 1 SIP1C Motor: 'mell of burnt insulation EXPECTED SEQUENCE OF ACTIONS'Repair team and Auxiliary Operator investigates loss of Sl pump 1C.'ight smoke discovered in vicinity of Sl motor 1C'uxiliary Operator/Electricians check SIP1C'iscover Amptector"instantaneous" button is out >Obtain holds, clearances, and test equipment>Simulate measuring resistance phase to phase and meggering motor from Bus 16/Pos 13A readings: Megger readings: 0 Q Phase to ground Phase to phase resistance 0 Q FINAL CONDITIONS: Motor requires replacement/rewinding due to grounded windings. Time: 1005 Message:~3 GINNA STATI N 1993 EVALUATED EXERCISE MESSAGE F RM Rpl 6 PP 616B Plgpl B I<<gll 6 Pl Simulated Plant Conditions: ~Messs e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information when appropriate actions are simulated or investigation conducted. Antici ated Results: 1)As per Mini-Scenario GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Bus 14-16 Tie Breaker Failure Bus 16 Expected scenario time: 1005 INITIAL CONDITIONS: Bus tie breaker 14-16 (Bus 16 open)METHOD OF INITIATION: 'oss os Bus 14 and"A" Diesel Generator is out of service,'SC orders the 14-16 Bus tie breakers closed.Mechanically (Bus 14 5.16).NOTE'peration of 14-16 Bus tie breaker from control requires jumpering of contracts in the control circuitry. This breaker MUST NOT be repaired and returned to service until Emergency Diesel Generator"A" is supplying Bus 14 (approx 1 220).INDICATIONS: CONTROL ROOM: 'o indications Bus 16/POS12C: 'reaker"trips free" when manually shut and will not latch shut.Bus 14/POS19C: 'mptector: as found.'reaker operates normally.EXPECTED SEQUENCE OF ACTIONS'Repair forms to: Determine how/if possible to defeat interlocks to operate Bus 14-16 tie breaker (Bus 16)from control.<Form team to operate Bus 14-16 tie breakers locally.'btain Health Physics coverage and dosimetry. 'btain key for operation of Bus 14 tie breaker. >Simulate operating Bus 14-16 tie breaker (Bus 14).~Simulate attempting to operate Bus 14-16 tie breaker (Bus 16).FINAL CONDITIONS: Bus'l4-16 breaker (Bus 16(open and~will no shut (will not latch shut). INNA STATION Message: 37 1993 EVAL ATED EXER ISE MES AGE FORM MMM 1:331TgpplgB1113Tl BR PBI Simulated Plant Conditions: ~Messa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information when appropriate actions are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenario. GIN NA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Bu 14-13 Ti Breaker F il re B 14 Expected scenario start time: 1005 INITIAL CONDITIONS: Bus tie breaker 14-13 (Bus 14)open.METHOD OF INITIATION: Loss of Bus 14 and"A" Diesel Generator is out of service.'SC orders the 14-13 bus tie breakers closed mechanically (Bus 14 5.13).NOTE: Operation of 14-13 bus tie breaker (Bus 14)from control requires jumpering of contacts in the control circuity.This breaker MUST NOT be repaired and returned to service until Emergency Diesel Generator"A" is supplying bus 14 (approx 1 220).INDICATIONS: CONTROL ROOM: 'us 14-13 (Bus 13)tie breaker light indicates correctly. Bus 14lPOS19B: 'reaker"trips free" when manually shut and~will no latch shut.Bus 13/POS10C: 'mptector: as found'reaker operates normally.EXPECTED SEQUENCE OF ACTIONS:>Repair team forms to: 'etermine how/if possible to defeat interlocks to operate Bus 14-13 tie breaker (Bus 14)from control.~Form team to operate Bus 14-13 tie breaker locally.Obtain Health Physics coverage and dosimetry. 0' 'btain key for operation of Bus 14 tie breaker.~Simulate operating Bus 14-13 tie breaker (Bus 13).>Simulate attempting to operate Bus 14-13 tie breaker (Bus 14).FINAL CONDITIONS: Bus 14-13 breaker (Bus 14)open and~will no shut (will not latch shut). Time: 1005 Message:~i l!IINN BTATI N 1993 EVALUATED EXERCISE MESSAGE FORIVI Ik:**III ygp<<ITBC T I 5 ACB 5 I MCTSBIA Simula ed Plant Condi ions: See the Attached Mini-Scenario ~Masse e:<<""THIS IS AN EXERCISE">>" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate actions are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenario. GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE'urnin on AC Breaker for MOV-851A Expected scenario start time: 1005 INITIAL CONDITIONS: 0 RCS has experienced a large break LOCA.'tep 18 of E-1 dispatches an Auxiliary Operator/TSC team to check the Auxiliary Building Sub-Basement for RHR system leakage.'uxiliary Operator/TSC team observes water dripping and what appears to be a 3 inch long crack at the bottom of the pipe between Containment and MOV-850A.The above observations <<d 1 C<<IR ITSl:~DDDl METHOD OF INITIATION: 'he Control Room/TSC may, after learning of the dripping water and cracked pipe, request the Auxiliary Operator/TSC team to turn on the AC Breaker to MOV-851A so it may be closed.INDICATIONS: CONTROL ROOM: 'OV-851A open.LOCAl'MOV-851A AC Breaker locked in off position.EXPECTED SEQUENCE OF ACTIONS: 'btain locked valve key from Shift Supervisor. Proceed to Auxiliary Building operating floor at MCC-1C position 10M.Unlock and turn on AC Breaker to lVlOV-851A. 'eport to Control Room/TSC the AC power to MOV-851A is on. NOTE: Auxiliar 0 rator SC earn con roller will coor ina r with simula pro era orswhenbre keri urned on o M V-851A.FINAL CONDITIONS: 'OV-851A Ac power breaker is turned on and this is reported to the Control RoomlTSC. Time: 1005 Message: 39 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~Mf: TPC/C<<IR A*ill ypp<<ll l g p"g" RCOTP p , Containment Sump"8" or the RWST.Simulated Plant Conditions: See Attached Mini-Scenario Messacee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate actions.are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenario, GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO TITLE: Linin u of the"B" RCDT Pum CNMT Sum B or he RWST.Expected scenario start time: 1005 INITIAL CONDITIONS: 'CS has experienced a large break LOCA.'t 1005 hours Bus 14 normal supply breaker tripped and the"A" Emergency Diesel Generator could not tie in as it was out for emergency maintenance. 'ecause of the above and other equipment out of service, all safety injection to the core is lost.'ll Safety Injection pumps available are powered by Bus 14.'he TSC, as an emergency action, may request that the"B" RCDT pump be lined up to pump from either Containment sump"B" or RWST to the core.INDICATIONS: 'o safety injection to the core with a large break LOCA in progress.'adiation levels are extremely high in the Auxiliar'y Building.EXPECTED SEQUENCE OF ACTIONS: 'ontainment Sump"8'-'ine-up: 'btain a copy of ER-RHR.1 (RCDT Pump Operation for Core Cooling)and simulator alignment of the"8" RCDT pump per the post accident sump recirculation section.'nform TSC/Control Room when alignment is complete.NOTE: TSC Control Room Auxiliar 0 er or con roller will coordina e with sirnula or o era or when RCDT um from Con ainment sum i simula ed lined u'WST Line-up: 'sing PAID's 33013-1247 and 33013-1272 sheet 2 of 2, research and simulate lining up"B" RCDT.from RWST to the core.'nform TSC/Control Room when alignment is complete.MOTE: TSC Control Room Auxiliar 0 era or con roll r will coordinate wi h simula or o era or when RCDT um from RWST is simula ed lin u.FINAL CONDITIONS: 'f"B" RCDT pump is aligned and started, its suction strainer will plug in approximately 2 minutes. Time: 1005 Message: 40 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~M: Mp R<<CI P g"B" RCDTP pp i M Simulated Plant Condi ions: See Attached Mini-Scenario ~Massa"""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate actions are simulated or investigations conducted. Antici ated Results: 1)As per Mini-Scenario. TITLE: GINNA STATION 1993 EVALUATED EXERCISE MINI-SCENARIO Cleanin of"B" RCDT Pum Suc ion S rainer Expected scenario start time: 1005 INITIAL CONDITIONS'us 14 tripped out and the"A" Emergency Diesel Generator could not tie in, and all safety injection to core is lost.METHOD OF INITIATION: As an emergency action, the TSC may request the Control Room to line up the"B" RCDT pump.INDICATIONS: 'B" RCDT Pump Suction Strainer is plugged.EXPECTED SEQUENCE OF ACTIONS'Operation aligns"B" RCDT pump for service'ump strainer will plug after two minutes of operation. 'igh levels of radiation in Auxiliary Building.'itters on standby for cleaning suction strainer.FINAL CONDITIONS: 't 1220 hours"A" Emergency Diesel Generator is supplying Bus 14.'uction strainer on"B" RCDT pump no longer requires cleaning. Time: 1015 Message: 41 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM I: 8 I<<C<<IR Simulated Plant Conditions: See Attached Sheets~ll/lesss e:<<<<"THIS IS AN EXERCISE"<<<<FOR CONTROLLER USE ONLY~CII R 1)Core exit thermocouples and R-29, R-30 start increasing and RVLIS starts decreasing. Antici ated Results: 1)Operators should inform the TSC of the increasing core exit thermocouples, the increasing radiation in Containment, and the decreasing RVLlS.2)Operators should perform the applicable actions of FR-C.1 (Response to inadequate Core Cooling)when required.3)TSC should evaluating plant status and taking actions as required.4)TSC should inform the EOF of the increasing core exit thermocouples, the increasing radiation in Containment and the decreasing RVLIS.5)TSC should be informing the EOF of the general plant status actions being taken and needs required.6)TSC may realize by this time that in order to recover core cooling they will need to complete repairs on'the"A" Emergency Diesel Generator, tie it into Bus 14, and start all available Sl pumps, even though they may not be completely sure of why Bus 14 tripped out.The thermography report given in the initial conditions should give them some confidence that the problem is in the transformer connections and not the Bus.7)TSC should also realize that once they energize Bus 14, MCC-1C will be energized and they can now close MOV-851A, when the breakers AC power is turned on, thus terminating the radioactive leak source from Containment to the Auxiliary Building.8)TSC may also evaluate the possibility of back feeding Bus 14 from Bus 13 using the 14-13 tie breaker.9)EOF evaluating plant status and taking action as required. 1993 EVALUATED EXERCISE Time:/D/~MAiTOR PARAMETERS YE NO 0 CPS DIESEL GENERATORS A.RUNNING UNLOADED STBY 00 B.RUNNING UNLOADED B OOS TSC RUNNING UNLOADED OOS Security RUNNING UNLOADED B OOS ENGINEERED SAPEGUARDS Aux.Peedwat T.Pum s 1A.INSERV~8 0 1B.INSERV OOS Turb.Driven INSERV STB OOS CST Level~62 4 F Reactor Shutdown N-31 N-32 CPS N-35 Mm~/AMPS N-36 AMPS Avg.Nuclear Power RCS Pressure V~PSIG PRZR Level Q.O A RCP RUNNING PPE B RCP RUNNING TOPPE 1A S/G Level 4z.1B S/G Level e 1A S/G Pressure PSIG 1B S/G Pressure SIG Turbine/Generator 0 E FFLINE 4 KV Buses NERGIZE DEE RGIZED 480V Buses jg8~5 NERGIZED DEEN GIZ DC Batteries~~ A~VOLTS B~OVOLTS Cnmt Pressure~a~PSIG Cnmt Sump A Level~2-FEET Cnmt Sump B Level IG XNCHES A Loop Hot Leg~QB~'F Loop Cold Leg a.OI~'F B Loop Hot Leg 883 3'F B Loop Cold Leg XB~F RVLIS 87 2-2 4F S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow O GPM ENGINEERED 8APEGUARDS Hi h Head S.I.Pum s FI-924~GPM FI-925~GPM 1A.INSERV STBY 1B.INSERV STBY 1C.INSERV STBY OS BAST Level=~O Low'Head S.I.Pum s FI-626~GPM 1A.INSERV STBY RECIRC 1B.INSERV S BY 0 RECIRC RWST Level=Containment 8 ra Pum s FI-931A GPM FX-931B GPM 1A.INSERV BY 00 1B.INSERV TB OOS NaOH Tank Level=~%Containment Recirc Fans 1A.IN RV STBY 1B.STBY OOS 1C.SER STBY OOS 1D.INSERV STBY Post Accident Dampers OPEN CLOSED Service er Pum s 1A.NSERV STBY OOS 1B.SERV STBY OOS 1C.NSER STBY OOS 1D.ERV STBY OOS A&B Header Pressure (o PSXG Com onent Coolin Water Pum s 1A.INSERV STBY 0 1B.NS STBY OOS Surge Tank Level=, Standb Aux.Peedwater Pum s 1C.INSERV STBY 1D~INSERV T OOS*CET=Average of Selected Core Exit Thermocouples ~.~4-/a-' NQV 17i 1993 10:14 R, E.GINA Sltt(KJ)TGR TREND GROUP ASS IGt(tB(T SUHt(ARY PAGE 1 GRQLPl EVENT1 PRGCEDUR"": EPIP 1-5 PLANT STATUS 2 3 5 6 I 8 9 10 ll~J7>>&!3 f4!5 16!7 18 f9 20 21 22 23 24 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 43 44 45 46 47 48 49 50 51 52 POP(T ID ATMS RXT N31 tG2 N35 tQ6 HP PRCS LPIR FREYA FRCLB RXT16 RXT!7 TSUBTC LSGA LS68 PSGA PS68 GcCBKRf GFNBKR2 BUS!!A BUSl!B BUS!2A BUSI28 81!A!2A 8118128 PCV LS(SPA L0942E L0943E L09420 L0943D L0942C L0943C l.09428 L09438 L0942A L0943A T0409A T04!OA T0450 T0451 TAVGAMID TAVGBMID LRV TCCGRE FAUXFMA FAUXFMB BKR081 BKR082 V3505 V3504 DESCRIPTIC4 ANTICIPATED TRANSIEHT M/0 SCRAtl RStTOR TRIP BREAKER STATUS SGU(iCE RANGE DETECTGR H-31 SM(CE RAhGE DETECTOR N-32 It FRt(EDIATE RAN6E EKTOR N-35 It(FR)(EDIATE BANK DETECTOR H-36 AVERAGE NUCLEAR POWER Rcjf"TGR COOLANT SYSTit)AVG PRESS PlicSSURI lER AVERAGc LE4$.REACTOR COOLANT LOOP A AVG FLOM RiA"TOR CCQ ANT LOOP 8 AVG FLGiA RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INURE TC SUBCOQLED ttAMIN STtl EH A tNRROM RAhGE AVG LEVEL ST)i Gctl 8 NARROW RANGE AVG LEVEL STH GEN A AVERAGE PRESSURE STtf GB(8 AVERAGE PFZSSURE GEtGQTGR'GN 'HE BREAKER 161372 GBeRATOR ON LINE BREAKER 9X1372 BUS 1!A SUPPLY Bl(EAKER BUS 118 SUPPLY BREAKiR HQT TERtlIHATED OH PPCS (7/f9/91)tlOT TERNINATED OH PPCS (7/f9/91)BUS l!A TO 12A T!E BREAKER BUS 118 TG 128 TIE ERQgER CO'!TAI)Nit! T AVERAC~P cURE CQNTAIHt(EtlT SUt!P A AVFRAGE LEVEL SUiV 8 LEVEL 8 ItKHES (TRAIN A)SU%8 LEVB 8 Ih'CHcS (TRAIN 8)SUN" 8 LEVEL 78 IHCHES (TRAIN A)SUiP 8 LEVEL 78 fhCHES (TRAIN 8)S PP 8 l cVEL 113 It(CHES(TRAIN A)SIJtP 8 LEVEL 113 INCHES(TRAIN 8)SUtF'LEVEL!80 INCHES(TRAIN A)SUlP 8 LEVEL 180 IHCHcS(TRAIN 8)RIP 8 LEVEL 214 INCHiS(TRAIN A)SU."P 8 Li'4'EL 214 INCHES(TRAIN 8)RCLA HOT LE6 TEt(PERATURE RCLB HGT LEG TEt(PERATURE RCLA COLD LEG TENPERATNE RCLB COLD LEG TEt(PERAME RCLA TAVG (THQT/TCGLD HIDE RHG)RCLB TAVG (THQT/TCOLD MIDE RN6)REACTOR VESSEL AVERAGE LEVEL El.1 IHCORE TC AVERAGE TE)(P S/6 A TOTAL AUX FEEDMATER FLGM S/6 8 TOTAL AUX FEEDMATR FLOW tlTR AUXILIARY FEEDMATER PUt(P A NTR AUXILIARY FEEDMATER PUt!P 8 AUX FM PUN'TEA)l SUPPLY VALVE A AUX FM PU)F STEAN SUPPLY VALVE 8 OFF OFF CLOS D CLQScD AT MS ALRl'i RX TRIPPED ALR)f 5.00609+01 GOOD 3.94456+01 BAD 1.00925-11 600!)1.00001"11 Gm~(9 GOOD 46.LALN.0 LAL)(2.4 INHB.0 INHS TRiPPED ALRtl TR!PPED ALRt(-11.3 LAL>>42.4 6008 48.7 600>>Bl l.GQQ>>784.GOO>>TRIPPED ALRt(TRIPPED ALR)(TRIPPED ALR)l TRIPPED ALRN NQT TRIP DEL NQT TRIP DEL t]QT TRIP ALRt(t)QT TRIP ALR)(1.18 HMR>>31.2 HENS H!6HB?INHB HI6HER INH8 HIGHER INHB HI6HER INHB H!6HER ALRtf HI6HER ALRtl LOWER GOOD LOWER GOOD LOWER Gm LOWER GOOD 293.8 GOOD 293.3 400!)201.5 BAD 158.2 BAD 293.8 600>>293.3 600>>51.2 LALH 289.5 600>>0.6008 0.6008 6000 GQQD 6009 GQQD E.U.CPS CPS Al(P NP/PSIG)!/I/DEGF/a/PSIG PSIG DEGF IFGF DEGF KGF DEGF KGF/DEGF GP)l GPtl NOV 17F93 10'>>14 R.E.GINA Sltl8.ATOR TREND GROLP ASSIGQLchT SUtt!SRY PA6E 2 GROLP;EVENT1 PROCCEDURE; EPIP 1 5 PLANT STATUS POINT Io DESCRIPTION 53 FSIA SAFETY It<.'ECTION LOOP A 54 FSIB SAFETY INJECTION LOOP B 55 P2160 SERVICE MATER PUttPS A 5 56 P2161 SERVICE MATER PUttPS C t.57 BKR041 SERVICE MATER PUttP A 58 BKR042 SERVICE MATER PUttP 8 BKR043 SERVICE MATER PNP C 60 BKR044 SERVICE MATER PUttP 9 VALUE QUAL AVG FLPM 0, 6009 AVG FLOW 0.6009 B HEADER 87.GOOD 9 HEADER 86, 6009 GOOD 6009 6009 GOOD E.U.GPtt Ptt PSIG PSIG NQY 17i 1993 10!15 R.~GINtA Sit!Q.ATOR TRcND GROUP ASSIGN!ENT SUtlttARYPOINT ID DcSCRIPT ION VALUE GROL'P: EVEtlT2 PRQCEDL4?E: EPIP 1"5 PLANT STATUS E.U.1 2 3 5 6 7 8 10 J 13 14 jS 16 l7 18 19 20 22 23 24 26 2/28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 F0619 LRMST MSO33 MD033 MT033 MT250 MDT2 R01 R02 R05 R09 R34 R35 RIOA RI1 R12 RIOB R13 R14 R18 R19 R29 R30 R15 R12A5 R12Ab R1287 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 RISA9 R31 R32 CVH TCV03 TCY07 TCV08 TCV09 TCV10 TCV17 CQVQNENT Cm ING LOOP TOTAL FLM REFUELING MAT""R STORAGE TA%LVL 33 FOOT LEVB MIND SPEED 33 FOOT LEVEL MIND DIRECTION 33 FOOT LEVE'EHPERATURE 2SO FOOT LEVE'EtlPERATURE 2SO TO 33 FOOT LEVEL DELTA TEt!P AREA 1-CONTR!?'Mi At?EA"-CQt)7AI"NEttT AREA 5-SPENT RE PIT ARcA 9-LETDOMN Lit=mttiTGR AREA 34-AUX BLDG CV PRAY PL4!P AREA 35-PASS SAMPLE PAL COtA'AINt!EttT IODINE tGRITOR R10A CQiiTAINt!ENT AIR PARTI ClJ ATE CONTAINten GAS tlONITOR PLNT YENT I09INE tlQNITOR R109 AUX P DG EXHAUST AIR PAt?TICULATE AUX BLDG EXHAiJST GAS tiQNITQR LIQ!ID MASTE DISPOSAL Nt/ITOR STEA>>GEt!ERATGR BLGMEF4'RAIN AREA 29 CQt!TAINHENT H1%RANGE AREA 30-CGNTAINiEttT Hi&I RANK COl8ENSER AIR EJECTOR EXHAUST CV VEN: CHAN M.QM RANGE GAS CV VEttT CNW 6-AREA GAMA CV VEN: CHAN 7-tllD PANGS GAS CV VEN!CSN 9+I'GH RANGc GAS PLA".T VENT CHAN 5-LCA RANGE GAS PLAliT VENT Ct!4N 7-HID RANGE GAS PLANT YENT CNN 9-HIGH RANGE 6AS AIR EJECTOR 995 5-LGM RANGE 6AS AIR EJECTOR RW 7&ilD RAN6E GAS AIR EJECTOR MN 9+I RAtKE GP3 AREA 3;STEAtt Lit!E A (BRING)AREA 32 STEAtt LIE 8!PIttG>CV HYDROGEN CON CEttTRAT ION CY BASEt8!T DE 6FT T2P 03 CV INTERtLcDIATE LVL 6FT TEt!P.N7 CY IttTERt!EDIATE LYl.6, T TEtP tl8 CV IttTERtlEDIATE LVL 6FT TPiP tt9 CV IttTERt!EOIATE LVL 6FT TEt!P 110 CV GPERATIttG LEVL 6FT TEt!P 417 884.37.1 3.0 24.43.1 43.1.0 8.75992-02 7.80727+03 3.14412M 2.75423>01 2.95121+00 1.09648+00 9.57744+06 1.03068+07 9.49508+06 7.381}4+01 2.60390+02 1,98380+02 9,97126+02 2.16895+03 2.00245%1 2.00245+01 1.40241+03 4.2051&5 8.00000+00 4.20511M 9.99987M 2.30991M 4.62984-06 9.10997-04 6.22985-06 1.8097~1.52999<3 1.01004-02 1.01004-02 .0 75.6 83.6.83.6=83.6 83.6 91.7 l ALtl GPtl 6009 Y.GOOD ttPH 6009 DEG.GOOD lFGF 6009 DEGF 6009 KGF 6009 tS/HR BAD tSIHR BAD tS/HR BAD N/HR BAD t8/HR 600D t8/HR HALN CPit HENS CPtl HALtl CPtt 6009 Ptt 6009 PM GQQD CPtl 6009 CPtl GOOD CPN HWRtt R/HR hARH R/HR 6009 CPtl 6009 XIICC HMRtt tB/HR 6009 XI/CC 6009"'I/CC 6009 XI/CC 6009 Xl/CC 6009 XI/CC 6009 XI/CC 6009 XI/CC GQQD XIICC 6009 ttR/HR 6009 NIHR 6009 1!6009 DEGF 6009 IFGF 6009 DEGF GOOD DEGF GOOD DEGF GQQD lFGF v~(~ Time: 1020 Message: 42X GINNA STATION 1993 EVALUATED EXE I E.MESSAGE FORM~M:RMR Simula ed Plant Conditions: ~INessa e:<<<<<<THIS IS AN EXERCISE"""'Declare a GENERAL EMERGENCY in, accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification,"EAL: Reactor Coolant Leakage (RCS);LOCA Identified Inside CNMT and no ECCS Delivery to the RCS.FOR CONTROLLER USE ONLY Controller Notes: 1)Deliver only if a GENERAL EMERGENCY has not been declared.Do not deliver if emer enc classification discussions are in ro ress.Antici a ed Results: 1)Deliver contingency message if GENERAL EMERGENCY not declared or is not being discussed. Time 1030 Message:~4 GINNA STATION 1993 EVALUATEO EXERCISE MESSAGE FORM C I R Simulated Plant Conditions; See Attached Sheets~Massa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1)Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling). 1993 EVALUATED EXERCISE Time:~103 MAJOR PARAMETERS ENGINEERED SAFEGUARDS A.RUNNING UNLOADED STBY OOS B.'RUNNING UNLOADED OOS TSC RUNNING UNLOADED OOS Security RUNN NG UNLOADED B ENGINEERED SAFEGUARDS OOS Aux.Feedwater Pum s 1A.IN V STBY OS 1B.NSE V STBY OOS Turb.Driven INSERV TB OOS CST Level Q~eo F Reactor Shutdown ES NO N-3 1 2 xZ CPS N-32~CPS N-35 I~-i>AMPS N-36 l~6-11 AMPS Avg.Nuclear Power Q RCS Pressure IZi PSIG PRZR Level+~0 A RCP RUNNING TOPPED B RCP RUNNING STOPPED 1A S/G Level 1B S/G Level 2.~1A S/G Pressure~&6 PSIG 1B S/G Pressure PSIG Turbine/Generator LINE FFLINE 4 KV Buses NERGIZE DEENERGIZED 480V Busesi98waiT NERGIZED/DEENE GIZE DC Batteries A~VOLTS B~SOVOLTS Cnmt Pressure~~PSIG Cnmt Sump A Level~l.2 FEET Cnmt Sump B Level QI80'INCHES A Loop Hot Leg'F A Loop Cold Leg+01~F B Loop Hot Leg uMk'F B Loop Cold Leg 2-'F RVLIS*CET'F S/G A Total Aux FW Flow&GPM 5/G B Total Aux FW Flow~I2-GPM DIESEL GENERATORS Hi h Head S.I.Pum s FI-924 GPM FI-925~GPM lA.INSERV STBY OOS 1B.INSERV STBY 0 1C.INSERV STBY OS BAST Level=~/Low Head S.I.Pum s FI-626~GPM 1A.INSERV STBY 0 RECIRC 1B.INSERV STBY RECIRC RWST Level=Containment S ra Pum s 9 I-9 3 1A~GPM FI-931B (3 GPM 1A.INSERV S Y OS 1B.INSERV TB OOS NaOH Tank Level=~4 Containment Recirc Fans 1A.V STBY 0 1B.R STBY OOS lc.ERV STBY OOS 1D.INSERV STBY 0 Post Accident Dampers PEN CLOSED Service Rater Pum s 1A.NSERV STBY OOS 1B.NS R STBY OOS 1C.NS STBY OOS 1D.INSER STBY OOS A&B Header Pressure PSIG Com onent Coolin Rater Pum s 1A.INSERV STBY 0 1B.NSERV STBY OOS Surge Tank Level=~D Standb Aux.Feedwater Pum s lc.INSERV STBY 0 1D.INSERV OOS*CET=Average of Selected Core Exit Thermocouples NOV 17~1993 10:28 R.i,.GINNA SitNLATOR TREND GROUP AKIBNtZNT S~J44(ARY PAGE 1 GRGJP: EVENTI PROCEDURE: EPIP 1-5 PLA){T STATUS POINT ID DESCRIPTION VALUi E.U, 3 5 6 7 8 10 ll 12 13 15 16 17 18 19 20 21 22')3 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 43 44 45 46 47 50 51 c2 ATt6 RXT tQI N32 N35 N36 tP PRCS LPIR FRC A FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PS68 GENBKRs GBSKR2 BUSl lA BUS118 BUS12A BUS128 811A12A 8118128 PCV LSIP>PA L09428 L0943E L09420 L09439 L0942C L0943C L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TA VGA~A ID TAVBBWID LRV TCCQRE FAUXFMA FAUXFWB BXRO81 BXR082 V3505 V3504 ANTICIPATED TRANSiENT W/0 SCRA)f RiA"TOR TRIP BREAKER STATUS SMCE RAt{GE DETECTGR N-31 SKRCE RAt{GE DETECTQP.N-32 lt~cDIATE RANGE DETECTOR N-35 It{TER{(EDI ATE RANGE KTcECTGR N 36 AVERA6i NUCLEAR POkR REA".TQR COOLANT SYSTEt(AVG PRESS PRESSURIlER AVc cAGE LEVcC REACTOR COOLANT LOOP A AVG FLGM ROTOR CGGLAtti LGGc 8 AV6 FLG)I RCPA BREAKER CAUSE RX TRIP RCPB BRiAKER CAUSE RX TRIP IMCQRE TC SUBCQGLED NRBIN STt(~Dc{A t(%RGA RA){GE AVG LEVEL STt(GEI(8 t(ARRQN RANGE AVB LEVEL STt{Girl A AVERAGE PRESSURE Sit{GEH 8 AVEftAGE PRESRIRE KtERATOR ON LINE BREAKER 1G1372 GEtERATOR ON LINE BREAKER 9X1372 BUS llA SLePLY BR>J(cER BUS 118 SUPPLY BREAKER NOT TERt(INATED ON PPCS (7/19/91)NOT TERl(INATED Ot(PPCS (7/19/91)BUS 11A TO 12A TiE BREAKER BUS 118 TQ 128 TIE BRACER CQNTAINt(ENT AVERAGc PRHSURE CGt(TAIN)IEt{T S!J<d'AVER"Gi LEVEL SUtP 8 LEVil 8 ItlCHES (TRAiN A)SNP 8 LEVEL 8 INCHES (TRAItt 8)SUPP 8 LEVEL 78 INCHES (TRAIN A)SSP 8 LEVEL 78!tKHES (TRAIN 8)RAP 8 LEVEL 113 IN¹S(TRAIN A)SOP 8 LBr'EL 113 INCHES(TRAIN 8)SUtP 8 LE'PcL 180 INCHES(TRAIN A)SU5'LEVEL 180!NCHES(TRAIN 8)SUNUP 8 LEVEL 214 It<CH=S(TRAIt(A)SSP 8 LEVEL 214 INCHES(TRAIN 8)RiLA HOT LEG TEMPERATURE RC!!)HGT LEG TE)(PERATURE RCLA COLD LEG TEIIPERATURE RCLB COLD LEG TENPERATNE RCLA TAVB (THGT/TCOLD WIDE RNG)RCLB TAVB (TNT/TCOLD RIDE Rt(0)REACTGR VESScii AVERAGE LEVEL El~1 INCQRE T" AVERAGc TEtiP S/6 A TOTAL AUX FEED~AATcR FLPA S/G 8 TOTAL AUX FEED){ATER FLO'A le AUXILIARY FEEDWATiR PUtP A t,TR AUXILIARY FEED)IATER PUN 8 A!JX FW PUlF STEAtf SUPPLY VALVc A AUX R{PUtP STEAII SUPPLY VALVE 8.AT)IS ALRt(RX TRIPPED ALRt{6.22297+04 fNRt{3.94456+01 BAD 1.78648-10 GOOD 1.0000!-11 6009.00 6009 15.LALt{.0 LAL{(.0 lt{HB 20.3 INH>TRIPPED ALR{(TRIPPED ALR{{-716.6 LALt 41.7 6009 21.1 LWR~766.600~3.LALN TRIPPED ALRI(TRIPPED ALRI(TRIPPED ALR)I TRIPPED ALR{(NOT TRIP DEL t(GT TRIP DEL NOT TRIP ALRt{NOT TRIP ALR(1.33 Hf(R!31.2)Let)G HI6HER INHB HIGI{ER I t(HB HIGPZB INHB HIGHER It(HB HIGHER ALRt(HIGHcR ALR{(LONER G009 LG)IER 6009 LONER GOOD LQMER 6009 249,4.6009 249.6=GOOD 201.5 BAD 158.2 BAD 249.4 600~249.6 GGQc 38.4 LALti 803.0 HAL+0.GOOD 129.6009 C<F 6009 Qt(6009 CLOSED 6009 CLOScD 6009 CPS CPS At(P NP y.PSIG 0/7.DEGF/PSI6 PSIG PSIG FEET IFGF DEGF DEGF DEGF KGF DEBF DEGF FN PN ttOV 17i 1993 10'X R.E.GINNA Sit'LMTOR TREND GROUP ASSIGNYiEt/T PJiiRY PAGE 2 GROUPS EVENT1 PROCEDURE: EPIP 1 5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P 2160 56 P2161 57 BKR041 58 BXR042 59 BKR043 60 NR044 SAFcC'Y IN:ECTION LOOP A AVG FLOW SAFETY ItQECTION LOOP B AVG FLOW SHNICE MATER PNPS A h B HEADER SERVICE MATER PUttPS C&D HEADER SERVICE MATER PNP A SERVICE MATER PUttp B SERVICE MATER PUttP C SERVICc WATER PlNP 0 Otf ON ON as 0.6009 GPtt O.6009 Gpt1 87.GOOD PSIG 86.6009 PSI6 6009 GOOD GOOD 6009 DESCRIPTION VA'c CUAL E U }7>>}993}0:29 fi.E.GINA SIN}tLATOR TREND GROU, ASS IGNYZttT SUN>>NARY GROUP: BrcNT2 PROCH)UR-"~EPTP 1-5 PLANT STA'PJS e}2 3 4 5 6 7 8 9!0'}~Q 13}4 15}6}7}8 20 C>>>>a 24"5 26 27 28 29 30 31 V 33 34 5 36 37 38 39 40 4}42 43 POINT ID F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R}OA R}1 R}2 R}OB R!3 R14 R}8 R}9 R29 R30 R15 R12A5 R}286 R12A7 R}2A9 R}4"5 R}4A7 R14A9 R}595 R15A7 R}5A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV}0 TCV17 DEKRIPTIQN COtPONENT COOLINS LOOP TOTAL FLW REFUELING WATER STORAGE TANk LVL 33 FOOT LEVE'}ttD SPEED 33 FOOT LEVB.WIND DIRECTION 33 FOOT LEVc TENPERATURE 250 FOOT LEVE TENPERATURi 250 TO 33 FOOT LEVEL DELTA TEYP AREA}~ONTRQ ROON AREA 2-COtiTAINtB<T AREA 5-SPENT FUEL PiT At}EA 9-LETDOWN~>>'it>>c NONITQR ARB 34-AUX BLDG CV SPRAY PL'NP AREA 35-PASS SANPLE PA>>'K CONTAINNit>T IODIN"" NOttlTQR R}0A COtifAItti~>>chT AIR PARTIC(J ATE CQNTAIt<NEtIT GAS NQNITOR PLN.>>VENT IODINi NQttITOR R}09 AUX B~~EXHAJST AIR PNTICULATE AUX BLDG EXHAUST GAS ttONITOR LIKID WASTE DISPOSAL YONITOR STiA>>"~FB}ERATOR BL}tWDQWN DRAIN ARiA 29<OtiTAIt}NENT HIGH Rdi'Gi AREA 30-CQt}TAINYiENT HIS RANGE CONDih:ER AIR EJECTOR EXHAUST CV V"l>>:.CHAM 5-LOW RAl>>>>F GAS CV V""~i": CNtt 6-AKA GMcA CV Vit>>T CHAN 7-t>>19 RANGE GAS CV VENT CNM 9-HIGH RANGE GAS PLNT VENT CNN 5-LCA RANGE GAS PLCii VENT CNtt 7-NID FAttSE 6AS PLANT VENT CHAN 9"HIGH RAttSE 6AS AiR i:ECTQR CHAN=LCn'At}GE GAS AIR E-,ECTQR QfAlt 7 YID RAN6i 6AS AIR EQECTQR CHAN 9-HI RANGE GAS AREA 3}STEAN Llt,c, A{SPINz)AREA 32 STEAN LINE B (PING)CV HYDROGEN CONCEtlTFAT IQtt CV BASENEttT t Rlr"L 6~>>TEY~~tt3 CV itfiRNEDIATE LVL 6FT TEYZ tt7 CV IttlcR~IATE LVL 6FT TENP 48 CV INTERNEDIATE LVL 6FT TENP tt9 CV IH~"RNEDIATE LVL 6FT TENP tt}0 CV QiiRATING LEVL 6FT TENP C}7 VALUE ttUAL 892.LALN 37.1 6009 3.0 GOOD 4}.GOOD 43.1 6009 43.}6009.0 6009 8.91250-02 GOOD 7.80727+03 BAD 3.}44}2+00 BAD 2.75423~0} BAD 2.95}2}400 BAD 1.09648+00 6009}.03068%7 Hite}.03068+07 HENS}.0}741+07 HENS 9.8997440} 6009 2.4092}~02 GOOD 5.42468402 6009 9.'?7}26+02 6009 2.}9722+03 GCCD 8.0006}40} HNRtt 8.00061+01 HWRN}.48337+03 GOQ9 4.205!1-05 GOQD 8,00000~m Wm 4.20511-05 GQQ9 9.99987-04 GOOD}.77994-05 6009}.77994-05 6009 9.}0997-04 GOD9'.22985-06 GOOD 1.80975-05 6009 1,52999-03 K09}.01004-02 GOOD!.0}004<2 6009.0 GOOD 69.2 GOQ9 80.9.GQQ9 80.8 4009 80.9 K09 80,8 C<09 92.5 6009 E.U.GPN/NPH DEG.DEGF DEGF IEGF NR/HR tS/HR NR/HR}S/HR NR/HR NR/HR CPt}CPN CPN CPN CPN CPN PN CPN R/HR R/HR CoN UCI/CC tS/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCIICC NR/HR NR/HR 7 DEGF}EGF DE6F}EGF D=GF'EGF Time;1045 Message: 44 6INNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM I: Ri I R I R Simulated Plant Conditions: See Attached Sheets~Messa e:<<<<"THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1)Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling). 1993 EVALUATED EXERCISE Time:~0~~MAZOR PARAMETERS Reactor Shutdown ES NO N-31 7/3 CPS N-32 CPS N-35~~OAMPS N-36~t~lAMPS Avg.Nuclear Power RCS Pressure PSIG PRZR Level A RCP RUNNING/TOPP B RCP RUNNING STOPPE 1A S/G Level 1B S/G Level%7s lA S/G Pressure PSIG 1B 5/G Pressure PSIG Turbine/Generator ONLINE/FLINE 4 KV Buses NERGIZE/DEE GIZED 480V Buseslgdgat G EENERGIZ DC Batteries Agb VOLTS B~OVOLTS Cnmt Pressure s'~~PSIG Cnmt Sump A Level FEET Cnmt Sump B Level/~~INCHES" Loop Hot Leg OF A Loop Cold Leg~2,o/, 4F B Loop Hot Leg~~OF B Loop Cold Leg~1':~'F RVLIS'Bkr 7 Q*CET 5K~M'F S/G A Total Aux FW Flow O GPM 5/G B Total Aux FW Flow~2.GPM DIESEL GENERATORS A.RUNNING UNLOADED STBY OS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED B OOS Security RUNNING UNLOADED TB OOS ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.INSERV STBY 0 18.ER STBY OOS Turb.Driven INSERV B OOS CST Level g~s~FEET ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 C>GPM FI-925~GPM 1A.INSERV STBY 00 1B-INSERV STBY 0 1C.INSERV STBY OOS BAST Level=~)Low Head S.I.Pum s FI-626~>GPM 1A.INSERV STBY 0 RECIRC 1B.INSERV STBY RECIRC RWST Level=Containment 8 ra Pum s FI-9 3 1A~GPM FI-931B C3 GPM 1A.INSERV STBY 00 1B.INSERV STB OOS NaOH Tank Level=~4 Containment Recirc Fans 1A.INS RV STBY 0 1B.STBY OOS 1C.INSERV STBY OOS 1D.INSERV STBY OS Post Accident Dampers OPEN CLOSED Service Water Pum s 1A.N RV STBY OOS 1B.IN ERV STBY OOS 1C.INSERV STBY OOS 1'SERV STBY OOS A&B Meaaer Pressure@7+Co PsIG Com onent Coolin Water Pum s 1A.INSERV STBY 0 1B.NSER STBY OOS Surge Tank Level=.~>Standb Aux.Feedwater Pum s 1C.INSERV STBY 0 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocoup1es NOY 17'993 10'4 R.E.GIt@A SltIULATQR TRit(D GROUP ASSIGt<<~t(T SUINRY PAK 1.GROL+: EVENTI PROCEP>>.F: EPIP 1-5 PLANT STATUS POINT iD DESCRIPTION: VALUE E.U.2 3 4 5 6 7 8 9 In 11 12'13 t4 1U 16 17 l9 20 21 23 24)5 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 43 45 46 47 48 49 50 51 52 AIl6 RXT N31 tG2 N35 N36 NP PRCS LPER FRY FRCi3 RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GiNBKRI GENBKR2 BUS11A BUS118 8US12A BUS128 811A12A 8118128 PCY LSUNPA L0942E L0943E L0942D L0943D L0942C L0943C L09428 L09438 L0942A LO943A T0409A'0410A T04sn T0451 TAVGAWID TAVGBWID LRV TCCQRE FAUXFWA FAUXFWB BKR081 BKROB2 V3505 Y3504 ANTICiPATED TRANSIT(T W/0 SCRAN RE@".TOR TRIP BREAKER STATUS SMCE RA)IK DETECTDR tf-31 SEE=" RANK DETECTOR N-32 INT.=RNEDIATE RAN6E D"=TECTOR N-35 It~>"P~~DIATE RANGE DiTECTOR N-36 AVERAGE NUCLEAR POWiR REA TOR COOL@(T SYST>c AYG PRESS PK~SSURI EER AVERAGE LEVEL RBr"TQR COOLANT LOOP A AYG FLOW REACTOR CCCL@T LOOP R AVG FLQM RCPA BREAKER CAUS'i RX TRIP RCPB BRENER CAUSE RX TRIP INCORE TC SUBCOOLED NNGIN STtI Kt(A t(ARROW RA%: AVG LEVEl STt'i GiN R t(ARROW RANGc AVG LEVEL STtI Gi!(A AVERAGE PRESSURE STN GEI(8 AVERAGE PRESSURE GitKRATOR ON LINE BREAKER 161372 GENERATOR OM't(E BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 1!8 SL'PPLY BREAKER t(OT 7ERNINATED ON PPCS (7/19/91)t(QT'tiNIt(ATED QN FPCS (7/!9/91)BUS 11A TQ 12A TIE BRiNER BUS 118 TO 128 TiE BREAKER CQNTAINtIEt(7 AVERAGE PRESSURE CQtFiAItŽZiT SJtIP A AYERAK LEVEL MP 8 LEVEL 8 INCHES (TRAIt(A)Slat 8 LEVd.8 It(CHES (TRAIN 8)HJt.8 LEVd 78 INCfiiS (TRAltt A)SUtP 8 LPr~76 it(CHES (TRAltt 8)SU%8 LEVEL 113 INCHES(TRAIN A)SU%'LEVEL 113 It(CHciS(TRAIN 8)SUtF'LEYEI.180 INCHES(TRAIN A)SUPP 8 LEVEL 180 INCH""S(TRAIt(8)Rti.8 LEVEL 214 INCHES(7RAIN A)SUtP 8 I.EYEL 214 INCHES(7RAIN 8)RCL~HQT LEG TEtPERATURE RCLB HOT LEG TEtIPERATLK RCLA COLD LEG TE)IPERATNE RCLB COU)LEG TE)IPERATURE RCLA TAVG (THOT/TCQLD WiDE RNG)RCLB TAVG (THQT/TCOLD WIDE Rt(G)REk TOR VESSEL AVERAGE LEYEL Ei.l INCORE TC AVERAGE TEIIP S/6 A TOTAL AUX FEEDWATER FLOW S/6 8 TOTAL AUX FEEDMATER FLOW NTR AUXILIARY FEEDWATER PUtIP A)ITR AUXILIARY FEEDWATER PUIIP 8 AUX FW Ply STEA)I SUPPLY VALVE A AUX FW PlÃ'TEA)I SUPPLY VALVE 8 ATNS ALRtI RX TRIPPED ALRII 1.18713p05 HALI(3.94456+01 BAD 2.64239-10 6008 1.00001-11 Gm.00 6008 LALN.0 LALtI 1.0 It(H>>1.3 ItlHB TRIPPED ALRII TRiPPED ALRII-820.7 LAL>>67.4 HALII 27.9 LWR>>"4.LALt', uV II TRIPPED ALRN 7RIPPED ALRII TRIPPED ALRII TRIPPED ALRII NO.TRIP DEL t(OT TRIP DEL t(QT TRIP ALRN NOT TRIP ALRII.52 GOO>>31.2 HENS HI6HER INHB HI6HEP, INH8 HIGf&c I WB H16HER INHB HIGHER ALRtt HIGHER KRW LOWcD 6008 LONER 6008 LONER GQQD LONER C&8 215.5 GOOD 215.5~8 201.5 BAD 158.2 BAD 215.5 600>>215.5 CCO>>36.7 LALII 852.9 HAL>>0.6008 28, 6008 OFF'OOD ON 6008 CLOSED 6008 CLOSED GOOD/'" j3 r'PS CPS fNP A!IP PSIG/0//DEGF I/PSIG PS!G PSIG FKT DEGF DEGF IFM DEGF DEGF DEGF K DEGF VII Ptl NOV 17i H93 10:43 R.E.GINA SIMULATOR TREND GROiUP ARIGfffiEfii SUi"iftARY PAGE 2 e POINT ID 53 FSIA 54 FSIB 55 P2160 56 P2 161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 DESCRIPTIOV SAFETY INJECTION LOOP A AVG FLOW SAFETY INJECTION LKP B AVG FLOW SERVICE MATER PUMPS A h B KITER SERVICE MATER PUfFS C h D HEADER SERVICE MATER PUfft'SERViCE WATER PUfP 8 SHNICE MATER PUNP C SERVICE MATER PU!i?0 VALUE QUAL E.U.ON OiV ON ON 0, GOOD 9'N 0.GOOD GPN 87.GOOD PSIG 86.GOOD PSIG GOOD GOOD GOOD GOOD GROUP;EVENT1 PROCED~~E EPIP 1 5 PLANT STATUS NOV 17i 1993 10:4'.=.GitWA Slt'iLLATOP, TREND GROUP ASSIGNME)'T SUMNARY PAR GROUP;EVENT2 PRQCEDLRcE: EPIP 1-5 PLANT STATUS 0 POINT!D 24 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 R29 P30 R}5 R12A5 R!2Ab R12A?R}2A9 R}4A5 R}4A7 R}4A9 R!5A5 R}5A7 R}5A9 R3!R32 CVH TCV03 TCVO7 TCVOB TCV09 TCV10 TCV}7 1 F06}9 2 LSGT 3 NS033 4 t)9033 5 MT033 6 WT250 7 NDT2 8 RO}9 R02 10 R05!1 R09 12 R34!3 R35 14 R}OA 15 R!1, 16 R}2!7 R!OB 18 R13 R!4 20 R}8 2'!9 DES!AIPTIOW COtPOltcNT Coo." ING LKP TOTAL FLN FcCLING))ATER STORAGE TAtÃLVL 33 FQOT LEVEi WIND SPcB)33 FOOT LEVEL MIND DIfKCTIGN 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TQ 33 FOOT LEVEL DELTA TP~AREA}-Cot(TRg ROO AREA 2<ot(TAINNcERT AREA 5-SPENT FU9.PIT AREA 9-LETDOPa< LItF NONITGR AREA 34-AU(BLDG CV S, RAY Pot(P AREA 35-PASS SAMPLE PAtKL CGNTAINNiENT IODltZ NOtiITOR R10A CGNTAIHNENT AIR PART IC(LATE CO'lTA!t(MEt(T GAS tSNITGR PLAi7 VENT IODIttE MONITOR R}OB AUK BLDG E)(YAJST AIR PARTICULATE AU): BLDG E)(HAJST GAS NONITGR LINJID ViASTE DISPOSAL MONITOR STEAM GBlERATOR BLO)(DON DRAIN ARcA 29-CONTAINNEt)T HI(if RANGE AREA 30-CQWTAItNENT HI%RNi'GE Col(DENSER AIR EJECTOR E)(HAUST CV%Bing CSN 5-LOk'At(GE GAS CV VEW;CHAN 6-AREA GAB%CV VER!CHAN 7-NID RANGE GAS CV VEWi CHAN 9 HiGH RA'P~c 6AS PLANT VEtkT CIL4N 5-LOW RANGE GAS PL'Al)T VENT CHAN?+ID RANGE GAS PLNT VENT CMAtt 9-HIGH RAt(GE GAS AIR EJECTOR CHAN 5-LG)t RAN6E GAS AIR cJcCTOi RCHAN 7 NID RANGE GAS AIR EJcCTGR CHAtt 9+I RANGE GAS AREA 3!STEAN I.INEA (SPING)AREA i~STEAM LINE 9 (c It(6)CV HYDROGEt<COWCEttTRATION CV BASENEt(T LEVEL 6FT TEMP ti3 CV Iti HNEDIATE LVL 6FT TEMP ()7 CV INTERMEDIATE LVL 6FT TE)P 48 CV INTERNEDIATE LVL 6FTi TPiP N CV INTERMEDIATE LVL 6FT TEMP NO CV OPERATINS LEVL 6FT TEMP It}7 VALL!E 892.37.1 3.0 41.43.1 43;1.0 9,44062M 7.80727+03 3, 14412t00 2,75423t01 2.95121+00 1, 09648t00 9.66051t06 9.66051+06 1.01741+07 l.14}56t02 2.548Bt02 2.55563+03 1.01888t03 2,12263t03 7.99485t02 7.99485t02 1~41457t03 4.205}!M 2.00000tO} 4.205}}-05 9.99987-04 8.24988-04 8.24988-04 9.10997-04 6.22985-06 1.80975-05 1~52999M}.0}004M}.0}004<2.0 66.0 QUAL LAN 6009 6009 6009 G009 6009 6009 6009 BAD BAD BAD BAD 6009 HALtI HALN HEWS 6009 6009 HALN 6009 G009 fM HALN 6009 G009 O'Rt(6009 6009 HNRt(6009 GOOD 6009 6009 6009 6009 6009 GOOD 6009 70.6 6009 70.6=6009 70.6 GOOD 70.6 6009 75.3 6009 E.U.GPN'i(NPH DEG.IFGF DEGF IFGF t8/HR%/HR NR/HR l8/)I N/HR ts/HR CPN CPN CPN CPN CPN CPN CPN CPN R/HR R/HR PN UCI/CC N/HR UCI/CC XI/CC XI/CC XI/CC XI/CC XI/CC XI/CC XI/CC I)/tl N/MR\/DE6F DEGF IFGF IFGF DEGF DEGF 7 Time: 1050 Message: 45 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~Mt: 5 i L Simulated Plant Conditions: See Attached Sheets~Messa e:<<""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Radiation levels increase substantially in Auxiliary Building.This due to the leaking pipe between Containment and MOV-850A opening up where the crack is.A release above technical specifications begins, Antici a ed Resul s;1)Operators may transition to ECA-1.1 (Loss of Emergency Coolant Recirculation) due to loss of both RHR pumps.2)TSC should be expediting the turning on of the AC power breaker to MOV-851A.3)TSC should be expediting the recovery of AC power to Bus 14.4)TSC should inform the EOF of the increased radiation levels in the Auxiliary Building.5)TSC should inform the EOF of plant status, actions being taken and needs required. 6)EOF should be evaluating plant conditions and taking actions as required.7)EOF Dose Assessment should be evaluating the plant vent release and making protective action recommendations to the EOF/Recovery Manager.8)The EOF/Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should recommend protective actions to offsite agencies as required.9)Repair teams should be expediting repairs as conditions permit. Time: 1100 Message: 46 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM IN: 8 I C<<IR-Simula ed Plant Conditions: See the Attached Sheets~IVlesss e: """THIS IS AN EXERCISE""" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump Auto Start)FOR CONTROLLER USE ONLY Controller Notes: 1)The"8" Auxiliary Building sump pump starts and runs for approximately one minute.Antici a ed Results: 1)Operators should perform the applicable actions of AR-L-10.2)Operators should inform the TSC of the operation of the Auxiliary Building sump pump.3)TSC should evaluate the Auxiliary Building sump pump operation and the possibility of the leak in the pipe between Containment and MOV-850A getting worse, 4)EOF evaluating plant status and taking actions as required. 1993 EVALUATED EXERCISE Time: A.RUNNING UNLOADED STBY OS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED OOS Security RUNN NG UNLOADED TB ENGINEERED SAFEGUARDS OOS Aux.Feedwater Pum s 1A.XNSERV STBY OS 1B.SER STBY OOS Turb.Driven XNSERV B OOS CST Level~FEET MAJOR PARAMETERS Reactor Shutdown YES NO N-31 CPS N-32 CPS N-35~o~iAMPS N-36~~AMPS Avg.Nuclear Power Q RCS Pressure PSIG PRZR Level OG A RCP RUNNING/TOPPED B RCP RUNNING/TOPP D 1A S/G Level~Gv 1B S/G Level~B>1A S/G Pressure PSXG 1B S/G Pressure 5 PSIG Turbine/Generator ON NE FFLIN 4 KV Buses ENERGIZED DEENERGXZED 480V Buseslit'&ov7 ED ENERGIZE DC Batteries A@@VOLTS B~VOLTS Cnmt Pressure PSZG Cnmt Sump A Level Ie~FEET Cnmt Sump B Level Q INCHES" Loop Hot Leg OF A Loop Cold Leg s5 0F B Loop Hot Leg g/CLGL F B Loop Cold Leg~K.M OF RVLIS 8 0*CET'F S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow~g GPM DIESEL GENERATORS ENGINEERED SAFEGVARDS Hi h Head S.I.Pum s FX-924 r2 GPM FI-925~GPM 1A-INSERV STBY S 1B.XNSERV STBY 1C.INSERV STBY OOS BAST Level=~g Low Head S.I.Pum s FI-626 (3 GPM 1A.INSERV STBY 0 RECIRC 1B.INSERV STBY RECIRC RWST Level=~LL Containment 8 ra Pum s FZ-931A~GPM FZ-931B~GPM 1A.INSERV S 0 lB.INSERV STB OOS NaOH Tank Level=~4 containment Recirc Fans 1A.INSERV STBY OS 1B.NSER STBY OOS 1C.R STBY OOS 1D., XNSERV STBY 0 Post Accident Dampers OPEN CLOSED Service Water Pum s 1A.SERU STBY OOS 1B.STBY OOS 1C.SERV STBY OOS 1D.NSERU STBY OOS A&B Header Pressure~0 PSXG Com anent Coolin Water Pum s 1A.INSERU STBY OS 1B.NSER STBY OOS Surge Tank Level=,~Q Standb Aux.Feedwater Pum s 1C.INSERV S Y 0 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples NQV li.1993 lll00~R.E.GINA SIMULATOR PAGE 1 TREND Bf(GUP ASSIGNtfit(T SUi"it(ARY GROUP;cVENT!PROCEDURE: EPIP 1"5 PLANT STATUS POINT ID 1 ATNS 2 RXT 3 M31 4 N32 5 N35 6 N36 7 tfP 8 PRCS LP2R 10 FRCLA F¹8 12 RXT16!3 RXT!7 14 TSUBTC!5 LSBA 16 LSGB 17 PSBA'8 PSGB!9 GB(BKRI 20 GENBKR2 2!BUS!1A 22 BUS!18 23 BUS!2A 24 ,BUS!28 25 B!1A12A 26 81!8128 27 PCV 28 LB@PA 2'?L0942E 30 L0943i 31 L09429 32 L09439 33 L0942C 34 L0943C 35 L09428 36 L09438 37 L0942A 38 L0943A 39 T0409A 40 T04!OA 41 T0450 42 T0451 43 TAVBAWID 44 TAVBB)(ID 45 LRV 46 TCCGRE 47 FAUXFWA 48 FAUXR)8 49 BKR081 50 BKR082 5!V3505 52 V3504 DES"RIPTIGN ANTICIPATED TWNS!ENT H/0 SCRA)f REACTOR TRIP BREAKER STATUS SOURCE RAhBE DETECTOR tf-31 SO(BCE RANGE DETECTOR N-32 It(TENEDIATE RANSE DETECTOR N-35 INT"R,IEDIATE RANGE DETECTOR N-36 AVEAGE NUCLEAR POKER REA"TOR CCQ.NT SYSTEtf AVB PRESS PRESSURI2ER AVERAG" LEVEL REACTOR COOLS(T LOOP A AVG FLGA REACTOR COOLANT LOOP 8 AVG FLO)f RCPT BRiAKER CAUSE RX TRIP RCPB BRE'AKER CAUSE RX TRIP It'ZRc TC SIS"OQLED t(ARBIN STtf CW A t(AIR)>f RANGE AVB LEVEL STtf Citf 8 NARRPA RA%"" AVG LEVEL STtf BEN A AVEABE PRESSURE STtf BEN 8 AMYLASE PRESSURE BEtKRATGR ON LINi BREAKE 161372 GYRATOR ON LINE BREAKER 9X1372 BUS!1A SIR'LY BREAKER BUS 118 SUPPLY BREAKER t(OT TERtfltNTED GH PPCS (7/19/91)t'GT TERtf INATED GH PPCS (7/!9/91)BUS!!A TG 124 TIE BREAKER BUS 1!B TO 1'28 TIE BREAKER COWTAIHtfit(T AVERC~PKSSURE CONTAItlYZhT SUtfP A AViRABE LEVEL SOP 8 LEVEL 8 INCHES (TRAIt<A)SUtf'LEVEL 8 INES (TRAIN 8)Sue 8 LEVEL 78 It(CHES (TRAIt A)KN'LEVEL 78 It(CH<<ES (TRAIN 8)SUtP 8 LEVEL 113 INCHES(TRAIN A>SUN 8 LEVEL 113 INCHES(TRAIN 8)SU~<<'LEVEL 180 INCHES(TRAIN A)SU".8 LEVEL!80 INCHES(TRAltf 8>SUN'LEViL 214 INCH-"S(TRAItf A)SU)fr 8 LEVEL 214 It(CHES(TRAIN 8)RCLA HGT LEG TEMPERATURE RCLB HOT LEG TEtfPERATIR-" RVD COLD LEG TEt)PERAT5tE RCLB COLD LEG TEtfPERATNE RCLA TAVG (Tf(OT/TCOLD WIDE RNB)RCLB TAVB (THOT/TCOLD WIDE RtiYi)REACTOR VESSEL AVERAGE!LEVEL El.1 It(CORE TC AVERAGE TEt!P S/6 A TOTP.'UX FEECCATE FLQI(S/6 8 TOTAL AUX FEH'yfAT~B FLOH tfTR AUXILIARY FiEDMATER PUtfP A'ITR AUXILIARY FEEDHATER PUtfP 8 AUX FH PUI(P STEAN SUPPLY VALVE A AUX FH PU!!P STEN)SL'PPLY VALVE 8'ALUE OVAL ATNS ALRI(RX TRIPPED ALRtf 1.01976+05 HALI(3.94456+01 BAD 2.02302-10 6009!.00001-11 GOOD.00 GOOD LALtf.Q LALI(2.4 IM6.0 It(HD TRIPPED ALRII TRIPPED ALRtf-814.9 LAL>>67.7 HALI(32.9 600>>-5.LM-5.LALI(TRIPPED ALRt(TRIPPED ALRtf TRIPPED ALR)f TRIPPED ALRtf NOT TRIP DEL t(OT TRIP DEL tfOT TRIP ALRtf NOT TRIP ALRII.11 GOO>>31.2 HEtlB HIGHER INHD HIGHER Itff(8 HIGM INHD HIBHE It'IHD HIGf(ifl ALRtf HI6HER ALRN LONER 6009 LONER 6009 LOUR 6009 LONER GOOD 214.4, GQOD 214.4=GOOD 201.5 BAD 158.2 BAD 214.4 600>>214,4 600>>39.Q LALtf 845.5 HAL>>0.GOOD 28.6009 QFF GQQD Qtf GOOD CLOSED GGQD CLOSED GOOD."-/~/2.E.U.CPS CPS NP NP K PSI6'/.y./DE6F 0/PSIG PSIG PSIG FEET DEGF DEGF DEGF DEBF DEGF DEGF y.D=GF Ptf GPtf NOV 17i 1993 ll!0~R.E.GINA SIMULATOR TREND GROUP ASSIGNMENT

SUMMARY

PAGE 2 GROUP: EVENT1 PROCEXRE: EPIP 1-5 PLANT STATUS Polt~r ID DESCRIPTION VALLEY QUAL E.U.53 FSIA 54 FSIB 55 P2150 56 P2161 57 IWR041 58 BKR042 59 BkR043 h0 BKR044 SAFHY INJECTION LOOP A AVG FLOW SAFE INDECTION LOOP B AVG FLOW SERVICE WATER PtNPS A&B HEADER SHNICE WATER PUtFS C&0 hcAKR SERVICE WATER PUttP A SERVICE WATER PUN&B SERVICE WATER PUtP C SERVICE WATER PUttP 0 OH ON ON ON 0.GOOD PM 0.600D GPM 87.Gooa PSIG 86.600D PSIG GOOD GOOD 600D 600D hOU 17i 1993 IOl59 R.E.Gite Sit'i'TOR TREND GROUP ASSIGNttchT SUMttARY GRQL>>';EFJT2 PROCEDLcti EPIP 1 5 PLANT STATUS POINT ID 1 F0619 2 LRWST 3 WS033 4 WD033 5 MT033 6 WT250 7 WDT2 8 R01 9 R02!0 R05 R09.'2 R34 13 R35 14 RIOA ii5 Rl 1 16 R12 17 RIOB 18 R13 R14 20 R18 21 R19 R29 23 R30 24 R15 25 R12A5 26 R12A6 27 R12A7 28 R12A9 29 R14A5 30 R14A7 31 R1 489 32 R15A5 33 R1587 34 R15A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 DESCRIPTION COtPONENT COB.IN6 LOOP TOTAL FLM REFUELING WATER STORAGE TAX LVL 33 FOOT Lied.MIND SPED 33 FOOT LEVEL WIND DIRECTIQti'3 FQQT LEVEL TittPERATURE 250 FOOT LEVEL TEYiPERATURE 250 TO 33 FOOT LEVEL DELTA TEN'REA I-CONTRt)." ROON AREA 2-CONTAINttitlT PEA 5 SPENT FUcL PIT ARiA 9-LETDO'rtN Litle NQNITOR AREA 34-AUX BLDG CV SPRAY PLOP AREA 35-PASS SAHPLE PAWL CONTAINttENT IODINE NQNITGR RIQA CQNTAINt'cNT AIR PARTICt i ATE CONTAIeiNT GAS ttQNITGR PLNT VENT IODINE ttONITOR R109 AUX BLDG EXHAUST AIR PNTIClLATE AUX B'G EXHAiJST GAS tiONITOR LICJID WASTE DISPOSAL N)NITGR STE>",i GENERATOR BLOWDO'4 DRAIN ARcA~CCNAIttttBtT HICI RAtRE PEA 30-CQN'Alh~8tT HIS RAttG"" COtKiiNcER AIR EJECTOR EXHAUST CV VihT Cf2Pl MOW RAi!K GAS CV VENT CHAW 6-AREA GNN CV VENT CHAN 7-ttiD RAtK GAS CV VBit CPA<9+IGH RAQGE GAS PLNT VENT CHAN 5"LN RANGE GAS FLAN~VENT CNt(7-HID RANGE 6AS PLQ" VENT CNN 9+IS RANGE 6AS AIR FJECTOR CHAtl 5-LGW RAN6E CAS AIR EJECTOR CHAN 7~iilD RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS 4REA 31 STEAN LINi A (BRING)ARcEA 32 STEAN LINE B lSPINS>CV HYDROGEN CONCEWTPATION CV BASBL~NT LEVEL bfT TER~tt3 CV IWTERNEDIATE LVi 6FT TEttP 47 CV INTERMEDIATE LVL 6FT TEHP lt8 CV ittTERttEDIATE LVL 6FT TEtP tt9 CV ItficRttEDIATE LVL 6FT TEHP tt10 CV OFERATltlG LEVL 6FT TcttP tt17 VALE LALI'i G009 6009 G009 6009 6009 G009 G009 BAD BAD BAD BAD 6009 HENG HENS HALH HALl', 6009 HAJJt HALN HALl', HALtt HALtl 6009 6009 HALtt 6009 6009 HALf!SUt 6009 6009 GQ09 6009 6009 K09 65.3 GOOD 65.3 4009 65.3 6009 65.3 G009 66.3 6009 892.37.1 3.0 41~43.1 43.1.0 8.912~2 7.80727+03 3.14412+00 2.75423401 2.95121+00 1.09648~00 1.02182+07 1~02182+07 9.74430~06 1.02772+06 2.54829+02 9.78647+06 9,8855&05 7.07943~03 1.90134+03 1.90134~03 1.47698%3 4.20511M 5.20000~02 4.20511-05 9.99987M 9.96974-03 8.85986+00 8.85986+00 6.229~1.80975-05 1.52999"03 1.01004-02 1.01004M~0 64.4 E.U, GPN X AH D:6, DE6F DEGF ItGF ta/HR lg/HR ttR/HR N/HR HR/HR t8/HR CPH CPN PN CPN CPtl tl 9'H CPN R/HR R/HR CPN KI/CC l8/HR KI/CC UCI/CC KI/CC KI/CC KI/CC KI/CC KI/CC KI/CC ta/HR t8/HR DEGF 0-"GF DEGF, DEGF 0" GF DEGF Time: 1110 Message: 47 GINNA STATI N 1993 EVALUATED EXER I E MESSAGE FORM~M: M I R<<IR Simulated Plant Conditions: See the Attached Sheets~Massa e: """THIS IS AN EXERCISE""" The following annunciator is received: '-10 (Auxiliary Building Sump Pump Auto Start)FOR CONTROLLER USE ONLY Controller Notes;1)The"B" Auxiliary Building sump pump starts and runs for approximately one minute.Antici a ed Results: 1)Operators should perform the applicable actions of AR-L-10.2)Operators should inform the TSC of the operation of the Auxiliary Building sump pump.3)Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling).When they attempt to start the RCP's they trip out immediately. 4)TSC should be'evaluating the plant status and taking actions as required. Time: 1115 Message: 48 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM I: W I<<C IR Simulated Plan Condi ions: See the Attached Sheets~Messe e:<<<<"THlS IS AN EXERClSE""" FOR CONTROLLER USE ONLY~CI I N Antici ated Results:

1993 EVALUATED EXERCISE Tuae:~/IK MAZOR PARAMETERS Reactor Shutdown YES NO N-31 CPS N-32 CPS N-35 giif/0 AMP S N-36~54-AMps Avg.Nuclear Power RCS Pressure~PSIG PRZR Level A RCP RUNNING/PPED B RCP RUNNING/TOPPE 1A S/G Level 1B S/G Level 1A S/G Pressure PSIG 1B S/G Pressure PSIG Turbine/Generator ONLXNE/FFLIN 4 KV Buses GIZED DEENERGIZED 480V BuseslgdqAwl NE G zED EN DC Batteries AQo VOLTS B~i.0 VOLTS Cnmt Pressure~r~PSIG Cnmt Sump A Level FEET Cnmt Sump B Level/~~3 INCHES" Loop Hot Leg F A Loop Cold Leg Re/z OF B Loop Hot Leg'F B Loop Cold Leg DER~'F RVLIS 3$,0 g*CET EQM F S/G A Total Aux FW Flow D GPM S/G B Total Aux FW Flow~g GPM DIESEL GENERATORS A.RUNNING UNLOADED STBY OOS B.RUNNING UNLOADED OOS TSC'UNNING UNLO DED OOS Security RUNNING UNLOADED TB OOS ENGINEERED SAFEGUARDS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924~GPM FI-925~GPM 1A.INSERV STBY 00 1B.XNSE V STBY 00 1C.NSERV STBY 0 BAST Level=~O Low Head S.I.Pum s FI-626 GPM 1A.INSERV STBY 1B.INSERV STBY RWST Level=~~4 RECIRC RECIRC Containment S ra Pum s FI-931A GPM FI-9 31B~GPM 1A.INSERV STBY OS 1B.XNSERV TB OOS NaOH Tank Level=~S Containment Recirc Fans 1A.INSERV STBY OS 1B.NSER STBY OOS 1C.SERV STBY OOS 1D.INSERV STBY OS Post Accident Dampers PEN CLOSED Service Water Pum s 1A.NSER STBY OOS 1B.SERV STBY OOS 1C.STBY OOS 1D.NSERV STBY OOS A&B Header reeeure~(n PSIG Com onent Coolin Water Pum s 1A.INSERV STBY 00 1B.NSERV STBY OOS Surge Tan Level=Aux.Feedwater Pum s 1A.INSERV STBY 0 1B.NSER STBY OOS Turb.Driven INSERV CST Level FEET OOS Standb Aux.Feedwater Pum s 1C.INSERV STBY 0 1D.XNSERV STB OOS*CET=Average of Selected Core Exit Thermocouples t(OV 17~1993 12!14 R.E.GINNA SIMULATOR TREND GROUP ASSIGtttct(T SUNDRY PAGE 1 6RGLP'4PP! PROCEDURE: EPIP 1-5 PLANT STATUS 1 3 4 5 6 7 8 9 10 11~g 44 13!4 15 16 17 18 19 20 21 22 23 24 26 27 28 OD*t 30 3i 33 34 35 3b 37 38 39 40 41 42 43 44 45 46 47 48 49 51 52 POINi ID ATWS RXT tQI N32 N35 tl3b NP PROS LP2R FRC A FRCLB RXT!b RXT17 TSUBTC LSGA LSGB PSGA PSGB GENBKP.!GENBKR2 BUS!!A BUS118 EUS!2A BUS!28 Bl!AI2A B!18128 PCV LSD"H L09428 L0943E L09429 L09439 LO942C L0943C L09428 L09438 L0942A L0943A T0409A TO4!OA TO450 T0451 TAVGAMID TAVGBWID LRV TCCORE FAUXF@FAUXFWB BKR081 BKRO82 V3505 V3504 DESCRIPTION At(TIC!PATED TRANSIENT W/0 SCRAM REA".TOR TRIP BREAKER STATUS SOURCE RAt(C~DETECTOR N-31 SO(RZE RANGE DETECTOR N-32 l¹RNEDI ATE RANGE DETECTOR N-35 IMIc&i""DIATE RANSc DETECTOR N-3b AVERAGE tLCLEAR PS,"R REA"TQR COOLANT(T SYSTEM AVG PRESS PRHSURIIER AMe.AGE LcKL RiACTQR COOLNP LOOF'AVG FLOW RcACTOR CC9 ANT LKP 8 AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BRiAKER CAUSE RX TRIP It'ZRc TC SUB GOU3 MARGIN STM GB(A NARROW RA%i AVG LEVEL STM GEN 8 t(ARROW RAl(GE AVG LEVEL STM Gct, A AVERAGE FISSURE STM Gest 8 AVERAGE PRESRNE EBEPATOR GN Llt/E BREAKER 161372 GchsRATOR ON I INc EFEAKER 9XI37>BUS llA SLiPPLY BREAKER BUS 118 SL9'PLY ERFAKER NOT 7 RMINATED Otf PPCS (7/!9/91)t(QT TERMINATED 0)t PPCS (7/19/91)BUS 1!A TQ 12A TIE BREAKER EUS!!8 TG 128 T!E ER-"VER CONTiAIN"8<i AVEc RA"-PRcSSURE CGNTAINMEtr'T SUMP A AVERAGE I sVEL SUMP 8 LEVEL 8 INCi(ES (TRAIN A)SUNUP 8 LEVEL 8 INCHES (TRAIN 8)SUti'LEVEL 78 INCR S (TRAIN A)SUMP 8 LE4sL 76 INCHES (TRAIt(8)SUNUP 8 LEVEL 113 It&ES(TRAIN A)S(PP 8 LEVEL 113 It(CHES(TRAIN 8)SUtP 8 LEVEL 180 Il(NrS(TRAIN A)SUtc.8 LEVEL 180 INCHES(TRAIN 8)SUtF 8 LEVEL 214 INCHES(TRAIt(A)SU%'LEVEL 214 ItlCHES(TRAItt 8)RCLA HOT LEG TENPERATLiRE RCLB HOT!.EG TsEMPERAT(R RCLA COLD LEG TE)FERATLRE RCLB COLD LEG TENPERAT(RE RCLA TAVG (THOT/TCQLD WIDi RNG)RCiLB TAVG (THOT/TCGLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 It(COFE TC AVERA6E TEt'4 S/G A TOTE.AUX FiEDWATER FLQN S/G 8 TOTAL AUX FEED((AT&FLOW MTR AUXILIARY FEEDWATsER PUMP A MTR AUXILIARY FEEDWATER PM'AUX Ft'UMP STEAN SUPPLY VALVE A AUX FW FUNP STEAN SUPPLY VALVE 8.VALUE OFF ON CLOSED CLQSH)ATWS ALRN RX TRIPPED ALRN 1.OOK&05 HALN 3.9445b%1 BAD 2.079?1-10 6009 1.00001-11 GOOD.00 GOOD i.LALN.0 LALt(~6 INHB 1.3 INHB TRIPPED ALRN TRIPPED ALRt(-819.5 LAL~68.2, HALN 38.1 I<-5.LALN-5.LALN TRIPPED ALRN TRIPPED ALRN TRIPPED ALRN TRIPPED ALRN NOT TRIP DEL NOT TRIP DEL t(OT TRIP ALRN NO: TRIP ALRN.08 600~31.2 HEND HI6HcP, INHB HIG)':-R It<HE HIGH&INHB HIG)<R.INHB HIGHER ALRN HI6HER ALRN LOWER 6009 LOWER 6009 LOWER GQQD LOWER GOOD 214.4 6009 214.4=6009 201.5 BAD 158.2 BAD 214.4 GOO~214.4 600<39,0 LNP.823.4 HAL~0.6009 28, 6009 600D GCCD GOOD 6009 E.U.CPS CPS AMP A!(P X PSI6/X/DEGF X PSIG PSIG DE%'iGF DEGF DEGF DEGF DE6F X Dc.GF GPM GPM tlOV 17i 1993 1!:14 R.E.GINA SltiEATOR TREND GROUP AKIGtlttEttT SUt>NARY PAGE 2 GROL'P: LVENT1 PRGCEDLtRE: EPIP 1-5 PLANT STATUS POINT ID DES RIPTIO'1 VA'cE INL E.U.53 FSIA 54 FSIB 55 P2160 56 P2161 57 RtR041 58 NR042 59 BNR043 60 BRR044 SAMcY Itt.'ECTION LOOP A AVG FLOW SAFETY INJECTION LOOP B AUG FLOW SERVKE WATER PUttPS A ti B HEADER SHÃICE WATER PUttPS C h D~c'R SERVICE WATER PUtP A SERVICE WATER PUtiP B SERVICE WATER PUttP C SB"ICE WATER PUttP D Gti'N Otl Gtt 0.GOOD O.GOOD 87.GOOD 86.GOOD GOOD GOOD GOOD GOOD GPtt PN PSIG PSIG NOV 1?i 1993 1::15 P..i.GMlA SIÃLATOR PAGE 1;REND GRQJP Ass16NriNT sUYNPY BROLLY: EVENT2 PROCEDLt":: EPIP 1-5 PLANT STATUS POPtT ID DES"RIPTIDE VALUE C4A'.U.1 2 3 4 5 7 8 fl~r>13 14 15 16 17 18 20 23 24 26 28 30 31 32 33 34 35 36 37 38 39 40 41 42 43 F0619 LR4ST NSO33 N9033 NT033 twlT250 NDT2 R01 R02 R05 R09 R34 R35 RfOA Rfi R12 RiOB R13 R14 R18 R19 R29 R30 R15 R12A5 R12Ab R1287 R12A9 R14A5 R14A7 R!4A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOS TCV09 TCV10 TCVl?CQ'PQ¹ttT CQQ'NB LQQP TOTAL FLM REPJELINB WATER STORABc TAN LVL 33 FQOT LEVEL MftlD SPccD 33 FOOT LEVE'it<9 DIF"CTION 33 FOOT LEtt"'ENPERAPJRE 250 FOOT LEVEL TENciRATURE 250 TQ 33 FOOT LEVEL DELTA Tile AREA 1-CQNTRQ'OON AREA 2-CONTAINMit/T EA 5-SPitP.FUEL PIT ARiA 9-LcTDO'AN LitF NQtlITOR AREA 34-AUY BLDG CV SPRAV PLiriP AREA 35-PASS SANPLE PANEL CONTAINMENT IODINE tlQNITOR R10A CQNTAINNitlT AIR PARTI'TE CQllTAINYEtlT GAS YiONITOR PLCtT Villi IODItli t'iOtlITOR RfOE AN BLD6 EXHAUST AIR PARTICULATi AUK BLDG EXHAUST GAS MPtITQR LIE~ID NASTE DISPOSAL NOtlI:OR STEA"i GENERATOR BLQtt90'4 DRAItt AREA 29-CBiTAItlMBtT HIGH RAltSic ARih 30-ZttTAItOlEtlT HICH RAtPaE CKiiNSER AIR EJECTOR EXHAUST CV VitlT CHAN 5-LQN RAi'lGE GAS CV VEltT Ct'JlN 6-ARK BAiM CV VENT CHAN?+ID RAlS:.GAS CV VENT CHAN 9-HIGH RtLNGE BAS PLQiT VHF;CHAt'-LGW RANGE GAS PLANT VENT Catt 7-NID RAGE GAS PLAttT VitPi CNN 9-HIGH RAtiSE GAS AIR EJECTOR CHAN 5-LOlt RANGE GAS JECTQR Cvgl 7 NID RAtlGE GAS AIR EJECTOR CllAN 9-HI RANGE BAS AREA 31 STiAtl LINE A (SPltlB)AR""A 32 S EAN LIl-'c B lSPItlB CV:"MROGEN CONCRATIOtt CV BASEMENT LEVL 6FT TEMP I3 CV INTERMEDIATE LVL 6FT TEMP%7 CV INTERMEDIATE LVL 6FT TEYiP tlS CV IttTEQG)IATE LVL 6FT TEMP I9 CV INTERNiDIATE LVi 6FT TEYiP ttf0 CV OPERATItlG LEVL 6FT TEMP ll17 884.LALtl 37.0 6009 3.1 6009 41.GOOD 43.1 600D 43.1 6009.0 GOOD 8.81048-02 GOOD 7.8072?+03 BAD 3.!4412+00 BAD 2.75423+01 BAD 2.95121+00 BAD 1.09648+00 GOOD 1.04S64+07 HENG 9.70232+06 HALtl 1.02624+07 HEttB 9.71623~05 HALr, 2.57039402 GOOD 9.57744m HALN 9.80051+05 HALN 6.75108~03 HALN 1.60209+03 HALN 1.60209+03 HALll 1.42683%3 6009 4.20511-05 GOOD 5.20000+02 HALN 4,20511-05 6009 9.9998?M 6009 9.98974-03 HALri 8.85986+00 HALN 8.85986400 Haiti 6.229~6009 1.80975-05 6009 1.52999<3 GMD 3.61997"03 6009 3.61997<3 K09.0 6009 63.7 6009 64.3 6009 64.3 MOD 64.3 6009 64.3 6009 64.9 6009 GPtl/AH IFG, DEGF DEBF DEBF NR/HR NR/HR tS/HR tS/HR IS/HR N/HR CPN CPN PN CPtl CPN CPN CPN CPN R/HR R/HR CPN UCI/CC IS/HR UCI/CC UCI/CC XI/CC UC!/CC UCI/CC UCI/CC UCI/CC UCI/CC NR/Htt t8/ts/DEGF DE6F IFBF Di6F IFBF DE6F Time;1120 Message: 49 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM t: R I<<1'R Simula ed Plant Conditions: See the Attached Sheets~essacee: """THIS IS AN EXERCISE""" The following annunciator is received: '-10 (Auxiliary Building Sump Pump Auto Start)FOR CONTROLLER USE ONLV Controller Notes: 1)The"B" Auxiliary Building sump pump starts and runs approximately one minute.Antici ated Results: 1)Operators should be performing the applicable actions of AR-L-10.2)Operators should be performing the applicable actions of FR-C.1 (Response to Inadequate Core Cooling). Time;1125 Message: BO GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM R C I R Simulated Plant Conditions: See the Attached Sheets~Messe e: "<<"THIS IS AN EXERCISE">>" The following message is received from Power Control: 'ffsite 34.5KV circuit 751 is ready to be restored to service.FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1)Operators should inform the TSC that Circuit 751 is ready to be restored to service.2)Operators should, if directed by the TSC, restore Circuit 751 to service per 0-6.9.2 Time: 1130 Message: 51 GINNA TATION 1993 EVALUATED EXERCISE MESSAGE FORM R I C ill Simulated Plant Conditions: See Attached Sheets~Messs e:<<" eTHIS IS AN EXERCISEe>>" The following annunciator is received: '-10 (Auxiliary Building Sump Pump)FOR CONTROLLER USE ONLY Controller Notes: 1)The"B" Auxiliary Building sump pump starts and runs approximately one minute.Actions Ex ected: 1)Operators should perform the applicable actions of AR-L-10.2)Operators should be perform the applicable actions of FR-C,1 (Response to Inadequate Core Cooling).3)TSC should be expediting the return of the"A" Emergency Diesel Generator to service.4)EOF Dose Assessment should be evaluating the release from the plant vent and making protective action recommendations to the EOF/Recovery Manager.5)The EOF/Recovery Manager, after=evaluating the EOF Dose Assessment recommendations, should make protective action recommendations to offsite agencies. 1993 EVALUATED EXERCISE Time:~90 MAi70R PARAMETERS ENGINEERED SAFEGUARDS aL3 8-I>AMPS l~~AMPS O~PSIG DIESEL GENERATORS A.RUNNING UNLOADED STBY OS B.RUNNING UNLOADED T OOS TSC RUNNING UNLOADED TB OOS Security RUNN NG UNLOADED TB OOS ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.INSERV STBY 00 1B.SER STBY OOS Turb.Driven INSERV TB OOS CST Level~s'~FEET Reactor Shutdown N-31 N-32 N-35 N-36 Avg.Nuclear Power RCS Pressure PRZR Level A RCP RUNNING/T PPED B RCP RUNNING STOPPED 1A S/G Level C 1B.S/G Level o 1A S/G Pressure PSIG 1B S/G Pressure SIG Turbine/Generator ON E/FFLINE 4 KV Buses NERGIZED DE GIZED 480V BusesigamouT ENERGIZED/DEENERGIZED DC Batteries A~VOLTS Cnmt Pressure~~~PSIG Cnmt Sump A Level~o~F EET Cnmt Sump B Level g INCHES A Loop Hot Leg~~OF A Loop Cold Leg 2b s'F B Loop Hot Leg/~'F B Loop Cold Leg$~9.2 F RVLIS*CET OF S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow~GPM Hi h Head S.I.Pum s FI-924~GPM FI-925~GPM 1A.INSERV STBY 00 1B.INSERV STBY 1C.INSERV STBY OOS BAST Level=Low Head S.I.Pum s FI-626 C7 GPM 1A.INSERV STBY 0 RECIRC 1B.NSERV STBY RECIRC RWST Level=~SD Containment S ra Pum s FI-931A GPM FI-93 1B (3 GPM 1A.INSERV Y 0 1B.INSERV TB OOS NaOH Tank Level=~~%Containment Recirc Fans 1A.INSERV STBY OOS 1B.NSER STBY OOS 1C.NSERV STBY OOS 1D.INSERV STBY OS Post Accident Dampers E CLOSED Service W Pum s 1A.SERV STBY OOS 1B.NSERV STBY OOS 1C.NSER STBY OOS 1D.NSER STBY OOS A&B Header Pressure~G PSIG Com onent Coolin Water Pum s 1A.IN RV STBY 0 1B.N E V STBY OOS Surge Tank Level=,~D Standb Aux.Feedwater Pum s 1C.INSERV STBY 1D.INSERV OOS*GET=Average of Selected Core Exit Thermocouples NGV!7i 1993!1:31 Fi.E.GINNA SIMULATOR PAGE TRct(9 GnO"c ASSIG>>PÃSU(>>v>>WY GROUP: EY=NT!PRGCH)URE: O'IP 1-5 Pl.ANT STATUS4 5 D 7 8 9 10~>>12 14!5 16!7 18!9 20 2!22+i'T CV 24 26 27 28 29 30 31 32 34 35 36 37 38 39 40 41 4v 44 45 46 47 48 49 50 c'1 52 POINT ID ATMB RXT N31 W32 N35 t(36 NP PRCS LPER FR4 A FRCLB RXT!6 RXT17 TSUBTC LSGA LBGB PSGA RuuB Git(BKRl GENBKR2 BUB!!A BUB!18 BUB!M BUS!28 B!1A!2A 8!!812B PCV LSUMPA L0942E L0943E L0942D L0943D L0942C L0943C'09428 L09438 L0942A L0943A T0409A T04!OA T0450 T0451 TAVGAMID TAVGBMID LRV TCCGRE FAUXFMA FAUXFMB BKROB!BKR082 V3505 V3504 DEKRIPTIGtt ANT?CIPATH) TRANSIENT M/0 SCRAM REACTOR TRIP BREAKER STATUS SOlRCE RANGE D TECTOR N-31 SOURCE'ANGE DETECTOR h~32 It(TERMEDIATE RANGE DETETOR N-35 INT:RMEDI ATE RANG BETE:"TOR N-36 AVERAGE ttXLEAR POMER REA".TOR COOLANT SYSTEM AVG PRESS PRE"SURIIER AVERACE LEVE RiACTOR COOLANT LQGP A AVG FLOM REACTOR COOLNT LOOP 8 AVG FLOM CPA BREAKER CAUSc Py TRIP RCPB BREAKER CAUSE RX TRIP It(CORE TC SUKGOM t@RuGlN STM GEN A t(ARRGM RAt(t":i AVG LEVEL STM~t(8 NARROM RN4cc AVG LEVEL STN GEN A A'vchASE PRiSBURE STN GEN 8 AY=RAGE PPxSB'JRE Git-RATGR ON LINE BRiAKiR 161372 GctKRATQR ON LINE EPEAKER 9X!372 BUB.'!A SPPLY BREAKER BUB 118 SUPPLY BREAKER OT TERMINATED GN PPCB (7/!9/9 hOT TERt(It(ATED Qtf PPCB (7/19/91)BUB 1!A TO!2A TiE BREAKER BUB!!8 TG 128 Tii BREAKER COt(TAIi[Mct(T AVERAGE PRcSBURE CONTAINMENT SUMP A AVERAGE LEVEL BUS 8 LEVEL 8 INCHES (TRAIN A)SUt.-8 LEVEL 8 It(LHES (TRAIN 8)SU~8 LEViL 78 It(: t(EB (TRAIN A)SU%'LEVEL 78 INCH S (TRAIN 8)SUMP 8 LEVEL 113 INCtccB(TRAIt< A)SUP 8 LEVEL 113 INC(="S(TRAIN 8)SUPP 8 LEVP 180 It(CHES(TRAIN A)BUtF'LEK'80 INCHciB(TRAIN 8)SUMP 8 LEVEL 214 It(CHES(TRAIN A)SUtP 8 LEAL 214 INCHEB(TRAItt 8)RCL4 HOT LEG TEMPERATL% RCLB HOT LEG TBPERATURE RCL4 CGU)LEG TEt'PEP'>>TNE RCLB COLD LEG TEt(PERATLR"- RCLA TAVG (Tf6T/TCOLD MIDc.RNG)RCLB TAVG (THGT/TCGLD MIDE RNG)REACTOR VESSEL AVERAGE LLVcL E1.!!NCORE TC AVERAGE TEMP S/6 A TOTAL AUX FEEDMATER FLOM S/6 8 TOTAL NJX FEEDWATER FLOM HTR AUXILIARY FEEDMATER PUttP A MTR AUXILIARY FFcDMATcR PUMP 9 AUn FM PUMP STEAN SUPP'VALVi A AUX FM PU)>>9 STEAN SUPP'VALVE 8 VALUE ATMS RX TRIPPED 1,04111+05 3.94456+0! 2.31206-10 !.00001-11 .00 1 J~.0.0 TRiPPED TRIPPED-830.8 67.8 43,9-5-5 TRiPPED TRIPPED TRIPPED TRIPPED NOT TRIP NQT TPIP NO TRIP NOT TRIP.06 31.2 HI6HEP.HI~HI6HER HIGHiR HIGHER HIGHciP, LONER LOMER LOMER LOM R 214.4 214.4 201.5 158.2 214.4 214.4 38.9 816.2 0.28.OFF Gll CLOS""9 CLOSED QUA'LRN ALRN HALN BAD 6009 GOOD GOOD LALN LALN INHE INHB ALRN ALRN LAL>>HAUt 600>>LALN LAUI ALRt(ALRN ALRN ALRN DEL DEL N.RI': ALRN 600>>HENS INHB!ttHB INHB INHB ALRN ALRt(GOOD 6009 6009 6009 6009 X<09 BAD BAD 600>>GQO>>LALt(HAL>>6009 6009 GOOD GQQD GOOD 6009 E.U.CPS CPS AMP NP/PSIG'//.DEGF X 7 PSIG PSIG PSIG FEET DEGF DEGF DEGF DEGF Dc6F DEGF 0/DE6F GPt(GPM NO'P 17i 1993 11:3!R..:.GIt4A SI%LATOR TREtQ GRCUF ASSIGtt%SUDSY PAGE 2 GRQtPl EV'<Tl PROC~M'~"": EPIP 1-5 PLANT STATUS POINT!9 53 FSIA 54 F GIB 55 P2160 56 P2151 57 BkR041 58 BkRO42 59 BKR043 oG BKR044 BES;"RIPTIO SAF:"Ti't4ECTION LOOP A AVG FLOW SAFETY INJECTION LGGP B AVG FLOW SP/ICE WATER PUtPS A 5 B tL-".K>B S:t,itiCs WATER PUtL~S C 5 0 NEAIiER SK)ICE WATER PUttP'.S"WCE WATER PUe B SERVICE WATER PUttP C SERVICE VATER.UYP 9 ON ON OM ON VALLE QUAL 0.BOOB 0.6009 87.GOOD ee.GOOO 6000 GOOB GOOD GQOO Ea U.PN GPtt PSIG PSIG NOV 17i 1973 R.E..Git~~(A SltZATOR TREt(9 GROUP ASSIGtlNEl(T M~"u"fARY PAGE 1 GRi'UP: EVE!i~i'ROCEDUR":: EPIP!"5 PLANT STATUS 0 7 8 9 10 12 13 14~g f~ib 17 18 20 Pp q 22 23 24 i.3 2b 2/28 31 32 33 34 35 37 38 39 40 43 POI"" ID FOb!9 LRWST MSO"3 W9033 WT033 WT"50 l'lDT'O!RO2 R05 R09 R34'35 RlOA Ril R12 R!OB R13 R!4 R!8 Rl v R29 R30 R!5 R!2A5 R!2Ab R1287 Rl 4>>R14AS R!4A7 R!4A9 R!SA5 R!SA7 R!SA9 R31 R32 CVH TCV03 TCV07 TCVOS TCV09: CV!O TCV!7 DESCR!PT!Ot'OPGVi"=HT COO'.IN"=LQQP TOTAL FLW RErd=i ING WATER STO.",A" TAt(K LVL 33 FOOT LEVP WIND SPEED 33 FOOT LEVEL Wit(D DIRECTIOi'l 33 FOOT LEVrEL TENPERATURE 250 FQQT Laic TENPERATURE 250 TO 33 FOOT LEVr DELTA TPJ'REA'!-COSIRO: ROO."i AREA 2-CONTAINNENT Ar","<5-SPEI'iT F(LL PIT@Re.4 9-LETDG'AN L!ttE l'iONITOR.ARE-.".34-AUX BLDG CV SPRAY PUtlP AR=.-'5-PASS SANPLE PAtZL.CQ!iAINNENT IODIti=-NONITOR RIOA CQNTAMB(T AIR PARTICULATE COtlTA!NNEtfT GAS NQNITOR+ANT VEtlT IODINE NQNITOR R!OE AUX B'6 EXHAUST AIF, PARTICULATE AUX BLDG EXHAUST CAS NNITOR LIKIID WASTE DISPOSAL NNITOR STEAt', GENEPATR:." R5~(DRAIti AR="A 2=.-CQhTAIt'"i~%'IGH RAt(G.: r5-"=" 3v-CQl(TAIt~!(T HI GH RANGE COtCEt(SER AIR EJECTOR El(HAUST CV VEtti CHAN 5-LOW RAtii=" GAS CV VENT CHAN b-AREA GA@1A C'v'ENT!CHAN 7-NID RNlK GAS CV VEN: CHAN 9-HIGH RANGE GAS.Loci VENT CHAN 5-LON RAt>6=GAS PLY(VENT CHAN 7"NID R4NK GAS PL%'lT VEt(T CHAN 9-HIGH RANGE GAS AIR FJECTQR CHAM 5"LOW RANGE GAS AIR EJECTOR CHAN 7-NID RANGE GAS AIR EJECTOR CHat 9-HI RANGE GAS AREA 3.'TEAN LINE A (SPIt(6)AREA 32 STEAN LINE 9 (SPING)C" HYDROGEN CONCENTRATION CV BASIN NT LEVEL bFT TBF ft3 CV ittTERNEDIATE LV!.GFT TEtP ft7 CV ItiTEPNEDIATE LVL bFT TEtfP ft8 CV IHTERNEDIATE LVL bFT TENP ff9 CV IliTERN."DIATE LVL bFT TENP ft!0 CV OPERATItl6 LEVL bFT TENP<<17 QUAL UM 600D 6009 6009 6009 6009 6009 6009 BAD BAD BAD BAD GOOD HALtf HENS HALN HALN GOOD HALN tfALtf HAUt HALli HALN 6009 6009 HALtf GOOD GOOD HALN HALN HNRtt 6009 GOOD GOOD 6009 GOOD GOOD 6009 b4.0 GOOD b4.0=GOOD b4.0 GOOD be 0 b4.b GOOD VALUE 892.37.0 3,0 41, 43.1 43.1.0 8.?5992-02 7.8072/+03 3.14412+00 2.75423+01 2.95121+00 1.09b48~00 9.95b83~0b 1.030b8+07 9.49508+Ob 9.92827+05 2.b039&02 9.91393~0b 9.54989+05 7.14084+03 1.303!b+03 1.303lb+03 1.40847+03 4.20511-05 5.20000>02 4.2051!M 9,99987-04 9.98974-03 8.8598b+00 8.8598b400 b.22985-0b 1.80975M 1.52999-03 3.o!997-03 3.bl997-03 .0 b3.4 E, U.GPNi I/lPH DCG.DEGF KGF DEGF tfR/HR tS/HR tfR/HR NR/HR tfR/HR tfRIHR CPN PN CPN PN PN CN CPM PN R/HR R/HR CPN UCI/CC ts/HR UCI/CC LI/CC UCIICC L"I/CC UCIICC XI/CC UCI/CC (L" I/CC tS/HR%/HR/DE6F DEGF KGF DEGF DE6F DEGF GlNNA STATION TIme:~114 Message: 52 1993 EVALUATED EXERClSE MESSAGE FORM MMM f: 8 I<<C IR Simulated Plant Conditions: ~ll/lesse e: "<<"THIS IS AN EXERCISE>>"" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start)FOR CONTROLLER USE ONLY Controller Notes: 1)The"B" Auxiliary Building sump pump starts and runs for approximately one minute.Actions Ex ected: 1)Operators should be performing the applicable actions of AR-2-10. TIme: 1145 Message: 53 GINNA STATION 1993 EVALUATED EXERCISE~MESSAGE R RM MESSAGE FOR: TSC/Simulator Control Room Simulated Plant Conditions: See Attached Sheets~Messa e: G"",THIS IS AN EXERCISE""" The following information is received in TSC from repair team working on the"A" Emergency Diesel Generator: 'epairs should be completed in approximately fifteen minutes.FOR CONTROLLER USE ONLY Controller Notes: Actions Ex ected: 1)TSC should be planning the recovery of core cooling and the termination of the release from the Auxiliary Building when the"A" Emergency Diesel Generator is returned to service.2)TSC should request operations to check the"A" Emergency Diesel Generator line-up as much as they can to expedite the return to service of the D/G.3)TSC should inform the EOF of the estimated time that the"A" D/G will be ready for return to service. 1993 EVALUATED EXERCISE Time:~45 MAJOR PARAMETERS Reactor Shutdown E NO N-31 65 CPS N-32 CPS N-35:-lO AMPS N-36 j~c~~AMPS Avg.Nuclear Power RCS Pressure~PSIG PRZR Level A RCP RUNNING/TOPPE B RCP RUNNING/TOPPE 1A S/G Level 7eb 1B.S/G Level 1A S/G Pressure 1B S/G Pressure PSIG Turbine/Generator ON E FFLIN 4 KV Buses GIZED DE N XZED 480V Buses NERGIZED DEENERGIZE DC Batteries A~90VOLTS B VOLTS Cnmt Pressure PSIG Cnmt Sump A Level~2-FEET Cnmt Sump B Level QI INCHES A Loop Hot Leg~MM'F A Loop Cold Leg 0 IF~F B Loop Hot Leg OF B Loop Cold Leg~~OF RVLIS ,0 g*CET 073 OF S/G A Total Aux FN Flow~GPM S/G B Total Aux FW Flow~2.GPM DIESEL GENERATORS A.RUNNING UNLOADED STBY OS B.RUNNING UNLOADED OOS TSC RUNNING UNLOADED B OOS Security RUNNXNG UNLOADED TB OOS ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.XNSERV STBY 0 1B.STBY OOS Turb.Driven INSERV STB OOS , CST Level~~FEET ENGINEERED SAFEGUARDS Hi h Head S.X.Pum s FI-924~GPM FI-925~GPM lA.INSERV STBY OS lB.NSERV STBY OS lc.INSERV STBY OOS BAST Level=Low'Head S.I.Pum s FI-626 GPM 1A.INSERV STBY 0 RECXRC 1B.INSERV STBY RECIRC RMST Level=~g Containment S ra Pum s FI-931A GPM FI-93 IB~GPM 1A.INSERV S BY 0 1B.INSERV TB OOS NaOH Tank Level=~%Containment Recirc Fans 1A.INSERV STBY 0 1B.NSERV STBY OOS 1C.NSER STBY OOS 1D.INSERV STBY 00 Post Accident Dampers PE CLOSED Service Water Pum s 1A.NSERV STBY OOS 1B.NSER STBY OOS 1C.STBY OOS 1D.STBY OOS A&B Header Pressure 4 PSIG Com onent Coolin Mater Pum s 1A.INSERV STBY 0 1B.NSER STBY OOS Surge Tank Level=, Standb Aux.Feedwater Pum s 1C.INSERV STBY OS 1D.INSERV T OOS*CET=Average of Selected Core Exit Thermocouples NOV 17.1o93}'.l43 i,".6!t'<A S!t<ULATGR PAGE 1 TREND 6ROU." ASSIGQtt(T SUtJiARY GROUP: EVE)IT}PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DES"RIPTION VALL!E QUAL E.U.3 6/8 o 10~~tP iC!4 15 57!8!o 2P Cd 25 26 27 20 30 3}d VI 35 36 3/38 3a 4p 41 4<+46 4/48 4o 50 51 52'T((S RXT t)3}N32 ted t(36 t(P PRCS LPIR FRCLA ,"RCLB RXTlo RXT17 TSUBTC Lou4 LSGB PSGA.PSGB GEt(BKR!GE)(EKR2 BUS}lA 8!08!2A BUS!28 811A!2A 8118128 PCV LSPlPA'94 L0943E LO9429 LO9439!.094"." L09430 L09428 L09438 L0942A LO943A T0409A.T04}OA T0450 T0451 T-"VG4WID T<<<<+W<LRV TCCORE FAUXFWA FAUXFWB p(opo1 BKROSi V3505 V3504 Al~ICIPATED T!?At(S!Et'T W/0 SCRN REA"TOR TPIP BREAKER STRTUS SOKE RAl<uic D:"TECTCR ti~3}SOUSE RANGE DETiiTGP t(-32 IHTERNEDIATE RANGE DETECTOR N"35 It(!" RNicDI ATE RANGE DETECTOR N-36 AVERAGE NUCLEAR PO)!cR REACTOR CGGLA)IT SYSTEt<AVu PRESS PRESSURIIER AVERAGE LEVEL RE@",TOR CGGLAt(T LOOP 4 AVG FLG<A PEA"TiV CGOUtVi LOGo 8 AVG FLOW ROAR BREAKER CA<JSE RX TRIP R'"ro'RFAKER MUSE RX T<RIP IN%RE TC SUB."COLED t<ARGItt STt(Gc'l A NAR!?GW RAl(Gc AVG LEVE ST", GEN 8 t(ARROW RAt(SE AVG LEVEL STti 6itl A AVERAGE PFESoJRE STN GEN 8 AVE(?AGE PRESSURE GitKRATQR ON LINE BPEAKER 1G!372 GENERATOR ON't<i BREAKER 9X}372 BU"}}A SUPPLY BREAKER 8;!8 1!8 SLPPLY BREAKER t(3", ToRt(ItNTED Otl PPCS (7/19/91)t(OT TERt(ItlATcED GN PPCS (7/!9/91)BUS i}A TO 12A Tii Bii-"KcR BUS 118 TO}28 TIE BREAKER CG)tiAI<'ll'lct(T AVERAGE PRESSURE COh!AIhNctiT SUNP A AVERAGE LEVEL SUtP 8 LEVEL 8 I))CHES (TRAIN A)PJ<<'LEVP 8 INCHES (TRAIN 8)SU%'LE!/EL 78!NCHES (TRAIN A)SUNP 8 LE!/EL 78!t(CHcES (TRAIN 8)SUNP 8 LEV13.}}3 INCHES(TRAIt(A)S<JlF"-LEViL 113 INCHES(TRAIN 8)SU5'LEVEL 180 INCHES(TRAIN A)S(9.8 LEVEL 180 Il(Ci'cS(TRAIN 8)SUtc'LEVc!214 ItKHES(TRAit(A)SNP 8 LR'r.L 214 ItlCHES(TRAIN 8)RCQ HOT LEG TEtIPERATLFe RCLB HOT LEG TENPERATURE RCLA COLD LEG TENPERATURE PCLB COLD LE6 TEt'J'ERATNE RCLA TAVG (THOT/TCOLD WIDE RNG)I?CLB TAVG (%3T/TCOLD WIDE RNG)RELTOR VESS": AViRAGc'EVc'i.!!NCORE TC A</cRASc TENP S/6 A TOTAL NX FEECQATd?r!.Ol!S/6 8 TOTAL AUX FEEDWATER FLON NTR AUX?L!ARY cccD)tATER PUNP A t(TR AuXILIARY F~D~ATER FOP 8 AU)(FW PUNP STEAN SUPPLY VALVE A AUX FW PUNP STEAN SUPP!.Y VALVE 8 CcF GN CI.OS ED CLOSED F-/4/AT)IS ALRN RX TRIPPED A'N}.05559tp5 HALN 3.94456+0} BAD 2.30143-10 GOOD 1.0000}-}l 6009.00 6009 1.LALN<.0 LAL'I.6 It(KE 1.3 INHE TRIPPED ALRN TRIPPED ALRN-791,2 LA'67.6 HALN 48.5 600e-5.LA<EN<"5.LA'TRIPPED ALRN TRIPPED ALRN TRiPPED ALRl'<TRIP PiD ALRN NOT TRIP DEL NOT TRIP DEL NO!TRIP ALRN t(OT TRIP ALRN F 06 600~31.2 HENS HIGHER.'tD(E H 16H""R INHE HIGH%iNHB HIGHER INK E HIG).cR ALN, HIGhD ALRN LONER 6009 LONR 6009 I OWcl?6009 LOn'ER 6009 214.4 6009 214.4=6009 201.5 BAD 158.2 BAD 214.4 6004 214.4 600~39.0 LALN 807.3 HAL<0.6009 28.GOOD 6009 6009 6009 6009 CPS CPS ANP A"J'PSIG/\/DEGF<//PSIG PSIG PSIG FEET DEGF DEGF DE6F DEGF DEGF DEGF DEGF PN GP)I 0 NOV ll:4 P..L~6INNA SIGNATOR BRED'iP ASIGhtE!iT SJNQRY 6RO~P: EVBlTI PROCEDLRE: EPIP!-5 PLANT STAPJS POINT ID DESCRIPTION VcVLiF QUAL E.U.53 FSIA 54 FSIB 5b P21bl 57 BKRD41 58 8 F4" 59 BKR043 bv e's SAFETY IN'~"->"N'ODP A AV"-FLOW SA~=i')INJECTION LOOP B AVG FLOW SLUICE WATER PUtFS A h B OKER SERVICE WATER PtNiPS C h D HEADER SGÃICE WATER PINP A SERVICE WATER PUNP B SERVICE WATER POP C~rf'>T~[!Q+>>f pl%P'N ON ON ON 0.60OD PH 0.GOOD PN 87.600D PSIG Gb.6000 PSIG 600D 6000 6009 KZ h3V 17.1;:44."-,."".GItQ SIMULATOR TREND GRO!JF ASSN'.'="hT SilttARY pj0'-.P:=VcEtlT2 PR04EQRE, EPIP f-5 PLAttT STAT JS rOltti iD 0" 6'"RIP 7 IO!t VALUc QUAL E.U, 2 4 5 6 I 8 9 Ie 13 14 f5 16 17~g I 19 20 22 23 24 25 w>~6')7 28 29 30 31 32 33 34 35 36 37 38 39 40 41 p 43 hC!C vcr 0 t.Rt'ST'85033 ND033 NT033 WT250 Ref Re: P05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 Rf~P,.'2A5 R12A6 R12A?R12A9 R1485 R14A7 R14A.R15A5 R15A7 R1599 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 LALY GOOD GOOD 6009 6009 KOD K09 GOOD BAD BAD BAD BAD GQQD HALtt HALtt HFNG HALYi GMD HENS HALtt HAS HALtt HALYi GOOD 6009 HAD 6009 6009 HP'i HAiit HNFi GOOD GOOD G009 6009 GOOD 6009 KOD 892.37.0 3.0 41.43.1 43.1.0 9.44062-02 7.8072?+03 3.14412@00 2.75423~01 2.9512fiee 1.09648+00 9.66051+06 9.66051+06 1~01741407 9.50877+05 2.54829+02 f.02182<07 9.80051+05 6.86868+03 1.30316+03 1.303fbt03 '1.41457 03 4.20511-05 5 20000+02 4.205ffM 9.99987-04 9.96974-03 8.85986+00 8.85986+M 6.22985-06 1.80975-05 1.52999"'03 3.61997-03 3.61997-03 ~0 63.3 63.9 6009 63.9=6009 63.9 6009 63.9 6009 64.5 6009 COA ONEtlT CO>>ING l.GOP TOTAL FLV REFiicLING RATER STORAGE TANtt LVi 33 FOOT LEVEt ttittD SPEED 33 FOOT LEVEL 4itt9 DIRECTIO;t 3~FOOT LE!/c'E!'!'""RA?OS 0 FOOT LB%TE."ZERATURE "50 TO 33 FOOT LE!" H.TA T!="8 HB f<ONTRG: ROO,"i AR"".'-CONTAINYEf'! AREA 5 SPcNT FU L Pt i AREA 9-'TDO'~~i LINE tfOttITOR AREA 34-AUX BLDG CV SPRAY PL!ttP ARB 35-PASS SANF" E PAteL CC!i!AIN!tEtiT IODINE ti0!tITOR R10A C3i',~AirtikttT AiR PARTIC!MTE CQv>AINtfEhT G.-'.S YiOhiTCR:"":."iti VEttl IODIttE ttONiTOR R109 AiJ<B'G EXHAUST AIR PPRTICULATE AJX PUG EXHAUST GAS YmtITOR LINID ttASTE DISPOSAL NNITOR STEN 6ENERATOR BLO'ADON DRAIN ARM 29-CONTAIN"tEttT HIPrl RANG AREA 30-COttTAik".cttT HIGH RAttGE CQ!CENSER AIP, E3ECTQR DHAUST CV VEtii CHAtt 5-LM RAttÃGAS CV V:-t.Rh 6-AFEA GAYi"iA"'dti CtN 7-" 9 PAt GP-CV V.",'T CttAN 9+IGH RAhEE GAS FLAilT VENT CHAN 5-LG'rl RANGE GAS PLNT VENT CNtt 7"tiID RANGE GAS R.0:i VENT CNN 9-HI6H RANGE GAS AIR E3ECTOR CHAt'ON RANGE GAS A!R EIECTGR CHAN 7 tiID RANGE SAS AiR c~cCTCR C"4t'-O'AGE GAS AR~31 STENi LINE A (GRINS)A<EA 32 STEA".i LINE 8 tSt'ItlG).""'"'DRGGE" CGNCEttTPATIO"'V BASEHEtii!LEVcL 6FT TEtP<<3 CV INTER!'cDIATE LVL br!TEtP tt?V Ih!ERYiEDIAT LVL 6F: TEIP<<8 CV'.NTERYiEDIATEc LVL 6FT TEY!P<<9 CV iNTERNEDIATE LVL 6FT TEYiP<<10 CV OPERATING LEV 6FT TEMP<<17 PN ttPH DEG.DEGF DEGF DEGF tS/HR t8/HR tS/HR tS/HR Yitt/HR tS/HR CPN CPH Ci'M CPtt PN CPN CPN CPtf R/HR R/HR Cl'tf XI/CC tS/HR XI/CC KI/CC Xl/CC Kl/CC XI/CC Kl/CC XI/CC KI/CC tS/HR tS/HR/DEGF DEGF 986F KGF DEGF DEGF GINNA STATION 1993 EVALUATED EXERCISE Time: 1=-150 Message: 54 MESSAGE FORM~I C I R Simulated Plant Conditions: ~Meaaa e: """THIS IS AN EXERCISE">>" The following Annunciator is received: r'-10 (Auxiliary Building Sump Pump auto start).FOR CONTROLLER USE ONLY Controller Notes: 1)The"B" Auxiliary Building sump pump starts and runs for approximately one minute.Actions Ex ected: 1)Operators should perform the applicable actions of AR-L-10. Time: 1155 Message: 55 GlNNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM TSC Simulated Plant Conditions: ~essa<ee: ""THIS IS AN EXERCISE""" The following information is received in TSC from repair team working on the"A" Emergency Diesel Generator: 'he"A" Emergency Diesel Generator is ready for return to service.FOR CONTROLLER USE ONLV'ontroller Notes: Actions Ex ected: 1)Operators, when requested by the TSC, should line up the"A" Emergency Diesel Generator per T-27.1.2)Operators should be performing the applicable actions of FR-C.1.3)TSC should request that the Control Room have the"A" Emergency Diesel Generator lined up for normal operation and allow it to tie into Bus 14.4)TSC should inform Control Room to start all Safety injection pumps and Containment recirc fans available as soon as Bus 14 is energized by the"A" Emergency Diesel Generator. 5)TSC should inform the Control Room to close MOV-851A as soon as MCC-C is energized, if MOV-851A AC ower breaker was turned on.

Time: 1155 Message: 56 GINNA STATION.1993 EVALUATEO EXERClSE MESSAGE FORM*il yap li g pl"*" 6 g Di IG<<p T-27.1 Simulated Plant Condi ions: See Attached Mini-Scenario ~Massa e:<<e"THIS IS AN EXERCISEe>>" FOR CONTROLLER USE ONLY.Controller No es: 1)Provide information verbally when appropriate actions are simulated or investigations conducted. Actions Ex ected: 1)As per Mini-Scenario. GINNA STATION 1993 EVALUATED EXERCISE-MINI-SCENARIO TITLE: Linin u he"A" Emer enc Diesel Genera or er T-27.1 Expected scenario start time: 1155 Hours INITIAL CONDITIONS: 'CS has experienced a large break LOCA.'he"A" Emergency Diesel Generator tripped on low lube oil pressure ten minutes after the LOCA.'t 1005 hours Bus 14 tripped out due to a transformer problem.'ecause of the above events and other equipment out of service, all safety injection to the core is lost.The core is now uncovered and sustaining major damage.'he maintenance repair team has repaired the"A" Emergency Diesel Generator and has informed the TSC it is ready for return to service.METHOD OF INITIATION: 'he TSC requests the control room to have the"A" Emergency Diesel Generator expeditiously lined up per T-27.1.I N DI CATION S: 'one EXPECTED SEQUENCE OF ACTIONS: 'btain a copy of T-27.1.'erform T-27.1 expeditiously (simulate). 'nform TSC/Control Room at 1215 hours that the"A" Emergency Diesel Generator is lined up per T-27.1 (whether it is or not).1 FINAL CONDITIONS' The"A" Emergency Diesel Generator is considered lined up and reported to TSC/Control Room at 1215 hours.'ontroller must no if Sim I or 0 er or'ust rior to Auxiliar 0 era or notif in Control Room SC. GINNA STATION Time: 1200 Message: 57 1993 EVALUATED EXERCISE MESSAGE FORM ,MMM:>>~I'C'R Simulated Plant Conditions: ~INessa e:>><<>>THIS IS AN EXERCISE>>"" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start).FOR CONTROLLER USE ONLY Controller Notes: 1)The"B" Auxiliary Building sump pump starts and runs for approximately one minute.Actions Ex ected: 1)Operators should be performing the applicable actions of AR-L-10. GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM Time: 1210 Message: 58.MMM: Si I<<C<<IR Simulated Plant Conditions: ~essacee:<<""THIS IS AN EXERCISE>>"" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start).FOR CONTROLLER USE ONLY Controller Notes: 1)The"B" Auxiliary Building sump pump starts and runs for approximately one minute, Actions Ex ected: 1)Operators should be performing the applicable actions of AR-L-10.

Time: 1215 Message: 59 INN A TATI ON 1993 EVALUATED EXERCISE MESSAGE FORM MMM: 8 I<<C<>The following information is received in the Control Room/TSC from the Auxiliary Operator lining up the"A" Emergency Diesel Generator: 'he"A" Emergency Diesel Generator is lined up per T-27.1.FOR CONTROLLER USE ONLY Controller Notes: Actions Ex ected: 1)Operators should start the"A" Emergency Diesel Generator and ensure it ties into Bus 14.2)Operators should attempt to start the-,"A" and"C" safety injection pumps, the"A" RHR pump and the"A" and"D" containment recirc fan coolers.All equipment starts except the"C" Sl pump (burned out motor).3)Operators should attempt closure of MOV-851A if the AC power to the breaker has been previously turned on, If the AC power to the breaker has been previously turned on,~hen the valve will come off its back seat and the breaker will trip out.If the AC power to the breaker has not been previously turned on,~hen no valve closure should be attempted at this time. 4)Operators should inform the TSC of the equipment started on Bus 14.5)Operators should inform the TSC of the failure of the"C" Sl pump to start on Bus 14.6)Operators should inform TSC of MOV-851A failure to close if AC power was previously turned on to the breaker.7)Operators should be performing the applicable actions of FR-C.1 and then return to E-1.8)TSC should send a team into the Auxiliary Building to turn on the AC power to MOV-851A, lf the AC power to the valve breaker had been turned on previously, the TSC may send an electrician with this team to check the breaker.9)TSC should be evaluating plant conditions and taking action as required.10)TSC should be checking on progress of repair teams.11)TSC should be informing the EOF of plant status and actions being taken for plant recovery.12')EOF should be evaluating plant conditions and taking actions as required.13)EOF should be requesting the engineering support center to perform a core damage assessment. 14)EOF Dose Assessment should be tracking the release plume and coordinatinglrecommending protective action recommendations to the Recovery Manager.15)The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies.16)Repair teams should be expediting repairs as conditions permit.EOF,:,: 4h4hw.R~~~CC44AWM4%W""wk>N"w.&V@.'.... PKOX~KNOPJy&twr.ANMvGVAOAMw v.4!vVvWr. wQPh4CvWWC 1993 EVALUATED EXERCISE Time.A.UNNING UNLOADED S OOS B.RUNNING UNLO DED TBY OOS TSC RUNNING 0 DED TB 0 S Security RUNN UNLOADED TB ENGINEERED SAP DS OOS Aux.Feedwat 8 1A.INS V STB OOS 1B.NSERV TBY OOS Turb.Driven NSERV TB OOS CST Level~FEET MAZOR PARAMET Reactor Shutdown ES NO N-31>>CPS N-32 CPS N-35 (8-l0 AMPS N-36 lac 8->AMPS Avg.Nuclear Power 0 RCS Pressure Q PSIG PRZR Level A RCP RUNNING/OPPE B RCP RUNNING OPPE 1A S/G Level Tet 1B S/G Level/,'4 1A S/G Pressure PSIG 1B S/G Pressure SIG Turbine/Generator E/FFLINE 4 KV Buses NERGI D DEE IZED 480V Buses ENERGIZED/DEENERGIZED DC, Batteries A)REVOLTS B~IDVOLTS Cnmt Pressure~DP PSIG Cnmt Sump A Level~Z-FEET Cnmt Sump B Level 4/~0~r'B INCHES" Loop Hot Leg~2l 3;OF A Loop Cold Leg ,'F B Loop Hot Leg~/3.OF B Loop Cold Leg~iP DF RVLIS~3~i*CET eq'2 e'F S/G A Total Aux FW Flow V GPM 5/G B Total Aux FW Flow~2GPM DIESEL GENERATORS ENGINEERED SAFEGUARDS 'i h Head S.I.Pum s FI-924 0 GPM FI-925~GPM 1A.SERV TB OOS 1B.NS RV S 1C.NSERV TBY OOS BAST Level=Law Head S.I.Pum s FI-626&G M 1A.V OOS REC RC 1B.'TBY 00 RECIRC RWST Level=Cantainmen S ra Pum s FI-931A GPM FI-93 1B~GP 1A.INSERV OOS 1B.NSE V B OOS NaOH Tank Level=Containment Recirc Fans 1A.INSERV TB OOS 1B.NS STBY OOS 1C.SERV STBY OOS 1D.INSERV TB OOS Post Accident Dampers 0 E CLOSED Service Water Pum s 1A.NS STBY OOS 1B.STB OOS 1C.IN V STBY OOS 1D.NSERV STBY 00 A&B Header Pressure 7 (PSIG Cam anent Cooli Rater Pum s 1A.TB OOS 1B.SERV STBY OOS Surge Tank Level=~Q Standb Aux.Feedwater Pum s 1C.INS V 00 1D.NSERV STB OOS*CET=Average of Selected Core Exit Thermocouples 0 NOV 17!1993 12(14 R.E.GII4'IA SIILLATGR TPEND GRGU?ASSIGN~&7 SUI(l(ARY PAGE 1 GROJP: EVE)(71 PROCEDUREI EPIP 1-5 PLANT STATUS 1 2 3 4 5 6?8 9 10 11 CQ 13'4 15 16 17 18 19 20 22 23 24 26 27 28 30 31 32 34 35 36 37 38 39 40 41 42 43 44 45 46 4748 50 51 52 PG>>IT;9 ATMS RXT N31 N32 N35 N36 NP PRCS O'R FRCLA FRC~8 RXTib RKT17 TSUBTC I SGA LSGB PSGA PSGB GEIIBKRs GENBKR2 BUSilA BUS118 BUS12A BUS128 811A12A 8118128 PCV LSU,"PA L0942E L0943E L0942D L09439 L0942C L0943C L09428 L09438 L0942A L0943A T0409A T041OA T0450 T0451 TAVGA MID TAVGBMID LRV TCCGRi FAUXFMA FAUXFMB BKR081 BKR082 V3505 V3504 KKRIPTIGN ANTICIPATED TRANSIENT M/0 SCR4Jf REACTOR TRIP BREAKER STATUS SMICE RANGE DETECTOR N 31 SONCE RANGE DFTECTGR N-32 INTER>IEDIATE RANGE DiTECTGR N-35 I@rRMEDIATc GRANGE DETECTOR N-36 AVcERAGE NL'CLEAR POMER REACTOR CGOLAtiT SYSTEM AVG PiKSS PRESSURIEER AVERAGE LEVEL REACTOR CGGLAIT LOOP A AVG FLGM REA".TGR COOLANT LOG," 8 AVG FLGM RCPA BRFAKER CAUS RK TRIP RCPB BREAKER CAUSi RK TRIP INXRE TC SUB%GLED MARGIN STt'i GEN A NARROM RANGE AVG LR'EL STI(GEN 8 IIARRGM RANGE AVG LEVEL ST)I Gert(A AVERAGr PFZSSUR:" STN GrJ(8 O'ERAGE PRESSURE GYRATOR Gtt LINE BREAKiR 1G1372 GEIEJATOR GN'NE BRiAKER 9X1372 BUS 11A Sl!PPLY BREAKER BUS 118 SUPPLY Bf(EAKE4 t(07 TERNINATED ON PPCS (7/19/91>NOT TERMINATED OII PPCS (7/!9/91)BUS llA TG 12A TIE BREAKER BUS 118 TG 128 TIE BREAKER CGI(fAINIIEI(l'VERAGE PRESS!JRE CGNTAINIIENT SU!"!P A 4VciWK LEVEL SU~r'LEVEL 8 INCHES (TRA!N A)SUI.8 LcVEL 8 II(CHES (TRAB(8)SUtf'LEST 78 It(C>7S (TRAIN A)SUtF'LE%'8 it(CHES (TRAIN 8)SUB'LEVEL!13 INCHciS(TRAIN A)SU!"P 8 LEVEL 113 INCHcS(TRAIN 8)SUtf 8 LEI!S.180 IIICHES(TRAIII A)SUtF'LEVEL 180 INCHcS(TRAlti') UlF 8 LEIIEL 214 INCHES(TRAIN A)SUtP 8 LEVE'14 INCHES(TRAIt(8>RCLA HOT LEG TEtFERATURE RCLB HOT LEG TEI(PERATURE RCLA COLD LEG TEIIPERAT(RE RCLB COLD LEG TEIFERATIRE RCLA TAV6 (THGT/TCOLD MIDE Rt(6)RCLB TAVG (THOT/TCOLD MIDr RNG)REA TOR VESSEL AYiRAGE LEVEL Elo1 It(!.ORE TC AVERAG"" TEIIP S/6 A TOTA'JK FEEDMATER FLOM S/6 8 TOTAL AUK FEEDMATER FLGM tITR AUXILIARY FEEDMATER P(9IP A NTR AUKILIARY FEEDMATER PUtP 8 AUK FM PUMP STEAII SL'PPLY VALVE A AUX FM PUII~STERh SL4'PLY VALVc 8 AT>IS ALRII RK TRIPPED ALRII 6.33138404 HMRII 3.94456+01 BAD 1.34276-10 6009 1.00001-11 6009.00 6009 0.LENS.0 LALN.0 INHB 1.3 INHB TRIPPED ALRII TRIPPED ALfN-779.5 LAL<67.1 HALI(61.2 HMRe-5.LCD-5.LAO(TRIPPED ALRII TRIPPED ALRII TRiPPED ALRII TRIPPED ALRt(NOT TRIP DEL NOT TRIP DrEL NOT TRIP ALRN NOT TRIP ALRN.(8 GOO~31.2 HEIPi HIGftR IN{9 HIGfKR It(f(9 HI6 HER INHB HIGfFP, INHB HIGHER ALRII HISHER'LRt(LONER 6009 LONER GOOD LONER 6009 LONER G009 213.9 6009 213 9 6009 201.S BAD 158.2 BAD 213.9 600~213.9 600~38.9 LALYi 792.6 HAL~0.6009 27.GG09 OFF 6009 ON 6009 CLGSH)6009 CLOSED 6009/)P CPS CPS AIIP A,">P/PSIG K/I>EGF X X PSIG PSIG PSIG FEET D" 6F DEGF DEGF DEGF DE6F DEGF K DEGF GPII PI(VAOlE@NL E.U. NOV 17~1993 1"l]4 R.E.GltflA SItlULATOR TREND GROUP AKIGlNrAT SUtfARY PA6E 2 GROK.: EVENT!PROCEDURE: EPIP 1-5 PLAttT STATUS POINT ID 53 FSIA 54 FSIB 55 P2ih0 56 P2161 57 BKRO41 58 BKRN2 5S BKR043 b0 BKRO44 DFSCRIPTION SAFETY INJECTION LOOP A AVG FLOM SAFETY INJECTION LOOP B AVG FLOM SERVICE MATER PUttPS A 5 B HEADER SERVICE MATER PUttPS C 5 D HEADER SERVICE MATER PUttP A SERVICE MATER PUttP 8 SERVICE MATER PUt1P C SERVICE MATER PUttP D ON ON ON ON 0.0.87.86.VALUE QUAL E.U.GOOD GPN 6000 GPM 6009 PSIG GOOD PSIG Gm 600D Goan GOOD

tfQV 1?r 1993 12: 15 R.E.GINA SINL'LATQR TRB8 GROUP ASSIGNNB(T SUIPiARYPOINT ID 1 F0619 2 LRIIST 3 MS033 4 MD033 S WT033 6 MT250 7 WDT2 8 R01 9 R02 10 R05 11 R09'2 R34.'3 R35 14 R10A!5 Ril 16 R12 17 R10B 18 R13 19 R14 20 R18 21 R19 22 R29 23 R30 24 R15 25 R12A5 26 R12A6 27 R12A7 28 R12A9 29 R14A5 30 R14A7 31 R14A9 32 R1SA5 33 R1587 34 RISA9 3S R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 DES"RIPTIQtf COMPONENT COQLINa LOOP TOTAL FL(f REFUELING MAT%STQRAGi TANK LVL 33 FOOT LEVcEL M!t(D SPEED 33 FOOT LiVEL MIND DIRECTION 33 FOOT LEVP TENPiRATURi 250 FQQT LEVEL TEN<PERATURi 250 TO 33 FOOT LEVEL DP TA TEMP ARFA I-COt(TRQL ROQi"i AREA 2-CQI(TAINNEHT AREA 5-SPENT FUcL PIT AREA 9-LETDOM<f LltF I'iONITOR AREA 34-AUK BLDG CV S.'RAY PU<P AREA 35-PASS SA"IPLE PANEL CQNTAltfMB(T IQDItfE MONITOR R1CA CONTAINMENT AIR PART IC(LATE CONTAI tfNEt(T GAS NON ITOR PLM'ENT IODINE NQI(ITQR RIOB AUK BLDG EKHAUST AIP.PARTICULATE AUX B(J)G EXHAJST GAS MONITOR l NUID WASTE DISPOSAL MONITOR STEAN GB(ERATQR BLO'ADO%I DRAlt(AREA 29"CONTAlt9LctfT HI%RANKc ARc4 30-CQtfTAItfNEt(T HIGH RAI(GE CQtfDENSER AIR EJECTOR EXHAUST CV VBIT CSW 5-LQM RNfK GAS CV VENT CHAN 6-AREA GANA CV KNT CS(tf?<ID RAI(K GAS CV t tfT CHAN 9+IGH RAISE 6AS PLANT VBiT CHAN 5-LOM RANGE GAS PUN VEI'iT CHAN 7-NID RAN6E GAS PL@(T VENT CHAN 9+IGH RAt(GE 6AS AIR EJECTOR CHAN 5-LOM RANGE GAS AIR EJECTOR D(Atf 7-NID RANK GAS AIR EJECTOR DQN 9 HI RANGE GAS KR 3'1 STEAN<Lit<i A (Plt(6)ARFA 32 STEAtl Lit(E B (S IN6)CV HYDROGEtf CQtiCENTRAT IOi'f CV BASENENT MliL 6FT 78P<<3 CV INTERMEDIATE LVL 6FT TEt'P<<?CV INTERt(EDIATE LVL 6FT TENP<<8 CV INTERMEDIATE LVL 6FT TENP<<9 CV It(TERNEDIATE LVL 6FT TElP<<10 CV OPERATING LEVL bFT FJP<<17 VALLE 884.36.8 3.0 41.43.1 38.8-4.3 8.81048<2 7.80727403 3.(4412+(e 2.75423+01 2.95121+00 1,09648<00 1.04864+07 9.702%+06 1.02624+07 9.71623~05 2.57039%2 9.57744+06 1.00577+06 6,75108+03 9.02219+02 9.02219+02 1.42683+03 4.20S11-05 5.200CO+02 4.20511-05 9.9998?M 9.98974-03 8.85986+00 8.85986+(5 6.22985-06 1.80975-05 1.52999-03 5.00000+(e 5.00000+00 .0 GOAL LALN G009 GOOD 6009 6009 6009 GOOD 6009 BAD BAD BAD BAD GOOD HENS HALN HEt(6 HALM 6009 HALN HALN HALN HALN HALN 6009 GOOD HALN 6009 6009 HALN HMRN 6009 6009 6009 HALN HALN 6009 63.3 6009 64.0 6009 64.0%009 64.0 G009 64.0 6009 64.7 6009 6ROUP.'VENT2 PROCEDURE: EPIP 1"5 PLAtfT STATUS E.U.GPN K NPH DEG.KGF DEGF DEGF NR/HR)S/HR NR/HR NR/HR ta/HR NR/HR CPN CPN CPM CPN CPN CPN CPtl CPN R/HR R/HR PN UCI/CC N/HR Xl/CC XI/CC XI/CC UCI/CC XI/CC XI/CC XI/CC XI/CC%/HR%/HR 7 DEGF DEGF DEGF DEGF DEGF DEGF GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM TIme:~121 Message: 60~f:A ill yOpdl I<<ii 1 keg'dl<<kglAC power breaker for MOV-851A.Simulated Plan Conditions: See Attached Mini-Scenario ~IVlessa e: """THIS IS AN EXERCISE">>" FOR CONTROLLER USE ONLY: Controller Notes: 1)Provide information verbally when appropriate actions are simulated or investigations conducted. Actions Ex ected: 1)As per Mini-Scenario. GINNA STATION 1993 EVALUATED EXERCISE lVIINI-SCENARIO TITLE: Checkin nd or Turnin on the AC Power Breaker for MOV-851 A.Expected scenario start time: 1215 Hours INITIAL CONDITIONS: 'CS has experienced a large break LOCA.'ecause of a leak from the large pipe between Containment and MOV-850A, it is imperative that the breaker from MOV-851A be turned on so MOV-851A can be closed to isolate the leak from Containment. 'd d d t t t ddd dd been re-energized at approximately 1220 hours.MOV-851A receives its AC power from MCC-1C position 10M.MCC-1C receives its power from Bus 14.'t is possible that the AC power breaker to MOV-851A was turned on subsequent to the restoration of Bus 14.If this is true, then when power is restored to Bus 14 and the Control Room attempts to close MOV-851A,. the AC power breaker will trip on overload as the valve attempts to come off its backseat.METHOD OF INITIATIONS: 'SC requests the AC power breaker for MOV-851A be checked and/or turned on.INDICATIONS: 'f team is to check breaker before they turn it on it will be normal.'C power breaker for MOV-851A it either locked off or is tripped off. EXPECTED SEQUENCE OF ACTIONS: Breaker previously turned on and has tripped: 'btain locked valve key.'roceed to MCC-1C, position 10M.'nspect breaker for signs of a problem.'bserve no problems.'nlock breaker and turn on.Note: The breaker will be c nsidered urned on at 1245 hours no ooner no la er for cenario ur ose.'eport the breaker is turned on at 1245 hours to the Control Room/TSC.Note: Con roller to coordina e this wi h he Sirnula or 0 era or.Breaker not previously turned on: 'btain locked valve key.'roceed lo MCC-1C, position 10M.'nlock breaker and turn on.Note: The breaker will be considered turned on at 1245 hours no sooner no later for scen rio ur oses.'eport the breaker is turned on at 1245 hours to the Control Room/TSC, Note: Controller to coordinate this with he Simula or 0 era or.FINAL CONDITIONS: 'he AC power breaker for MOV-851A will be considered turned on at 1245 hours.'OV-851A will be considered closed at 1250 hours for scenario purposes. ~GN T TD 1993 EVALUATED EXERCISE MESSAGE FORM Time: 1220 Message: 61<<I C I il Simulated Plant Conditions: ~Messa e: "<<"THIS IS AN EXERCISE<<>>>> The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start)FOR CONTROLLER USE ONLY Controller Notes: 1)The"B" Auxiliary Building sump pump starts and runs for approximately one minute.Actions Ex ected: 1)Operators should be performing the applicable actions of AR-L-10.2)Operators should be performing the applicable actions of E-1 (loss of reactor or secondary coolant). GINNA STATION Time: 1230 Message: 62 1993 EVALUATED EXERCISE MESSAGE FORM Si t<<C IR Simulated Plant Conditions: See Attached Sheets~Messa e: "" THIS IS AN EXERCISE FOR CONTROLLER USE ONLY Controller Notes: Actions Ex ected: 1)Operators should be performing the applicable actions of E-1. 1993 EVALUATED EXERCISE Time:~>3>A.RUNNIN UNLOADED STBY OOS B.RUNNING 0 DED OOS TSC RUNNING ED TB OOS Security R OADED TB ENGINEERED SAP DS OOS Aux.Peedwater Pum s 1A.I RV T OOS 1B.NSERV TB OOS Turb.Driven INSERV TB OOS CST Level~.FE T MA JOR PARAMET Reactor Shutdown ES NO N-31 CPS N-32 CPS N-35 AMPS N-3 6.OIS-I AMPS Avg.Nuclear Power RCS Pressure O PSIG PRZR Level C3 A RCP RUNNING/DPP B RCP RUNNING TOPPE 1A S/G Level ,2 1B S/G Level 1A S/G Pressure 0 PSIG 1B S/G Pressure Z&PSZG Turbine/Generator ONLI E FFLIN 4 KV Buses NERGIZE/DEENERGIZED 480V Buses ENE ZE/DEENERGIZED DC Batteries A VOLTS BQgVOLTS Cnmt Pressure~dZ-PSZG Cnmt Sump A Level~2 FEET Cnmt Sump B Level QigQ~I<INCHES" Loop Hot Leg 2,o7.w OF A Loop Cold Leg~l'F o'F B Loop Hot Leg OF B Loop Cold Leg OF RVLIS~12..*CET'F S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow~2GPM DIESEL GENERATORS ENGINEERED SAPEGUARDS Hi h Head S.I.Pum s FI-924~GPM FI-925 2-2-GPM 1A ER STBY OOS 1B.NSE V STBY 00 1C.NSERV STBY OOS BAST Level=0 Low Head S..Pum s FI-626 2oO GPM 1A.'Y OOS REC RC 1B.INS V STBY 0 R CIRC RWST Level=~~4 Containment S ra Pum s FI-931A 0 GPM FI-931B D GPM 1A.NS RV 00 1B NSERV STB OOS NaOH Tank Level=~4 Containme Recirc Pans 1A-NSERV STBY OOS 1B NSER STBY OOS 1C.STBY OOS 1D.NSER STBY OOS Post Ace>ent Dampers PE CLOSED Service%Pum s 1A.NSER S BY OOS 1B.NSE STBY OOS 1C.STBY OOS 1D.SER STBY OOS A&B Header Pressure~la pSZG Com onent Coo1%ate Pum s 1A.INSERV OOS 1B.NSE STB OOS Surge Tank Level=.~G Standh Aux.Pe wate Pum s 1C.S V TB 00 1D.INS RV TB OOS*CET=Average of Selected Core Exit Thermocouples

17i 1993 12!2:" R.".GINA SltfiJLATQR TREt<9 GROUP ASSIBNt<it<T SUNARY PAGE 1 BRGLc'VcNTf PROCEDURE EPIP 1 5 PLANT STATUS 5 6 7 8 10 11 12 13 15 fb 17 18 19 20 21 22 23 24 26 27 28 29 30 31 32 33 34 35 3b 3?38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 POINT I ATWS RXT N31 N32)<35 N36 NP PRK LPIR FRCLA FRCLB RXT16 RXTf7 TSUBTC LSGA LSBB PSGA PSGB GEt<BKR1 GENBKfQ BUSllA BUS118 BL'S12A BUS128 811A12A 8118128 PCV LSUvPA L0942E L0943E L09429 L0943D L0942C L0943C L09428 L09438 LO'942A L0943A T0409A TO410A T0450 T0451 TAVGAWID TAVBB))ID LRV TCCQRE FAUXFMA FAUXF)jfB BKR081 BKR082 V3505 V3504 DiSCRIPTIQN ANTICIPATED TRANSIEt<T M/0 SCRAJ<REA".TOR TRIP BREAKEP.STATUS SOLACE RANGE DETECTGP, N-31 SMCE RANGE DETECTOR N-32 INGOT)IATE RANGE DETECTOR N-35 It<TER)LcDIATE RANGE DETECTOR N-36 AVEf<A!i" NL!CLEAR PONER RE@".TQR CCGA"<T SYSTEt<AVG PRESS PRcESSURIZER AViRABE l RIEL ROTOR CQOLRil LOOP A AVG FLN REA".TOR COOLANT LOOP 8 AVG FLOW RCPA'BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP IhZR" TC SUBCODLED HA%IN STNi BFN A NARROW'A<Pei AYG LEYJ STh GEN 8 tlARROA RANGE AYG LEVEL STNi GEN A AVERAGE PRESRSE STt<BEN 8 AVERAGE PRESSURE GENERATOR ON LINE BREAKER 161372 Git&ATQR Oh'INE BREAKEc R9X1372 BUS 11A SUPPLY BREAKcR BUS 118 SUPPLY BRciAKER NOT TcRtilNATED Ot<PPCS<7/19/91)t<QT TERtfit<ATED ON PPCS (?/19/91)BUS 11A TQ 12A Ti'E BREAKER PJS 118 TO 128 TIE BREA<ER COt<TAIt<t<c>! AVERABi PRHSURE CQNTAIt<tiEt<T PJiip A AVERAGE LEVEL SL>5'LEVEl.8 It<CHES<TRAIN A)SUP 8 LEVEL 8 INCHES<TRAIN 8)SUtP 8 LEVEL 78 NQ'cS (TRAIt<A)SU)P 8 LE(tc'8!t<Cf!"S (TRAlhi 8)SUi~~8 LEYciL 113 It<CHES(TRAIh At SUtP 8 LEVEL 113 INCHES(TRAIN 8)SiJYP 8 LEVEL 180 INCHcS(TRAItk A)SÃ'LEVEL 180 It<CffiS(TRAIt< 8)SUPP 8 LEVEL 214 It<CH S(TRAIN A)SUtP 8 LP(cL 214 INCf!cS(TRAIN 8)RCLA HOT LEG TE)PERATUP= RCLB HOT LEG TEtfPERATUiK RCLA COLD LEG TE)fPERAT(RE RCLB CGiJ)LEG TEt<PERATlRE RO" TAVG (T83T/TCOLD WIDE RNB)RCLB TAVG<THOT/TCOLD WIDE Rtl6)RECTOR ViSSc'YERABi 'YEL El.f INCQRE TC AVERAGE TEt<P S/6 A TOTAL AUX FEEC4)ATER FLY(S/G 8 TQTAL AUX FEEDS'ATcCt FLQN hTR AUXILIARY FEEPAATER PUttp A NTR AUXILIARY FEEDf<ATER PUt<P 8 AUX FM PUi",P STEA1'i SUPPLY YALVE A AUX FN PUt<P STEAK!SUPPLY VALVE 8 Q.F Qt<CLOSED CLOSED/g~4/c ATNS ALRN R)<TRIPPED ALRt<2.9?166+01 6009 2.85101401 6009 1.00461-11 GOOD 1~00461-11 6009.00 6009 0.Lit<6.0 ftu~0 INHB.0 INHB TRIPPED ALf9<TRIPPED ALRN-1.5 LAL*66.2 Hf<R)<66.8 Ht<R)<0.LAu<0.LAN TRIPPED ALRtt TRIPPED ALRN TRIPPED ALRtf TRIPPED ALRtf NOT TRIP DEL NOT TRIP DEL NQ!TRIP ALRti NO!TRIP ALRtt.02 6009 31.2 HEh'G HI6HER Ihf<9 HIGHER INH9 HIBHP IN HE HIGHER INH9 HI6HER ALRt<HIBHiR ALRlt LO)tER 6009 LOUR GOOD LONER 6009 LOUR 6009 207.2 GOOD 207.4 5009 197.0 6009 119.4 GGG9 202.1 6009 163.4 6009 72.9 LALt<202.4 600~0.G009 27.6009 6009 GOOD 6009 GOOD E.U.CPS CPS NP NPÃPSIG X y 0/DEGF/K PSIG PSIG DEGF DE6F DEGF DcGF DE%KGF X DEBF GPtf IPt<

NOV I j~1993 12129 R.E.GINA SIN<ATOR TREt6 GROUP AKIGteittT SiXAARY PAGE 2 GROLP: EVEt<TI PROC="OUR":: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE OUAL E.U.53 FSIA 54 FSIB 55 P2 160 56 P2161 5?BttR041 58 BKR042 59 BKR043 60 BkR044 Sk~INJECTION LOOP A AVG FLOW SAFETY INJECTIOtt LOOP B AVG FLOW SERVICE%TER PlIPS A h B PEAG%SERVICE ttATER PUttPS C tnt 0 HEADER SHNICE WATER PlNP A ON SERVICE WATER PlIP B ON SERVICE WATER PUttP C , ON SERVICE NTER PUtlP 0 ON 0.GOOD 232.GOOD 87.6000 86.6009 GOOD GOOD GOOD 6000 8'N GPtt PSIG PSIG MN.17i}993}2:>R.E.GINA SINL4.ATOR TRE8 GPOUP ASSIGtit}EtiT SUJLSRY0 POINT ID 1 F0619 2 LRMST 3 MS033 4 MDO33 5 MT033 6 MT250 7 MDT2 8 ROl 9 RQ2 10 RO5!!R09!2 R34!3 R35 14 RfOA}5 Rll 16 R12}7 R10B 18 R13!9 R!4 R!8 2}R19 22 R29 23 R30 24 R!5 25 R!2A5 26 R}2Ao 27 R12A2 28 R12A9 29 R!4A5 30 R!4A7 3!R}4A9 32 R}5A5 33 R15A7 34 Rf5A9 35 R3!36 R32 37 CVH 38 TCVO3 39 TCV07 40 TCVOB 4!TCV09 42 TCV10 43 TCVf7 0""Si".RIP TI 0" CEMENT G8 ING LGQP TOTAL FLM REFUELING MATcR STORAG" TANK LVL 33 FOOT LEYE'!ND SPEED 33 FOOT LEVEiM!ND DIRECTION 33 FOOT LEVEL TENPERATURE 250 FOOT LEVEL TENPERATURE 250 TO 33 FQQT LEVEL DcELTA TE5'REA f-CONTRQ'OO:"i AREA 2-CONTAINNENT AREA 5-SPBlT FUEL PIT AREA 9-'TDQMN'tic NOttlTOR ARFA 34-AUX BLDG CV PRAY PUNP AREA 35-PASS P4PLE Pic'OtiTAItti<ctiT IODIttE NOti'ITQR R}OA CQNTAINNENT AIR PARTICR,ATE CQNTAINNENT GAS NGNITGR PLANT VENT IODINE MQt}ITOR R1QB AUX BLDG EXHAiJST AIR PARTICULATE AUX BLDG EXHAUST GAS NONITOR LIE)ID MASTE DISPOSAL NGNITOR STEAN GB)ERATOR IiLOMDGLN DRAItt AREA 29-COttTAINNEt(T HIS RANGE AREA 30-CQNTAIt'NEttT HIGH RANGE COtQENSER AIR EJECTOR EXMST CV VEttT CHAN 5-LOM RANGE GAS CV VENT OA'4 6-AREA GANA CV VB)T CHAtt 7-N!9 RANGE GAS CV YBF>CHAt'-HIGH RAtGE GAS PU67 YENT CHAN 5-LOM RANGE GAS PLANT YB(T Cf@tt 7"NID RhtiiGE GAS PLY!T VENT CHAN 9"HIGH RANGE GAS AIR EJECTOR RAM 5 LOM RANGE GAS AIR EJECTOR CHAN 7-tilD RAt<GE GAS AIR EJECTOR WNt 9-HI RANGE GAS AREA 3!STEAN LINE A<PING)AREA 32 STEAN LINE B (PIt!6)CV HYDROGEN CQttCENTRAT ION CV BASEST LEtIEL 6FT TcNP I3 CV INTERNEDIATE LVL 6FT TPiP 47 CV INTERNEDIATE LVL 6FT TENP I8 CV INTERNH)IATE LVL 6FT TENP 19 CV ItiTERNBIATE LVL 6FT TENP tt}0 CV PERATlt)G'VL 6FT TEt'P)t}7 YALL~QUA'84.LALN 33.5 6009 3.0 6009 41.GOOD 43.!G009 38.8 G009-4.3 GOOD 9.22572M 6009 5.099}6~05 HALN 6.34598~04 HALE, 6.06036+04 HALN 6.13055~04 HALN 1,09648%0 6009 9.57744~06 HALN 9.78647<06 HALN 1.04864+07 HEttG 1,04562406 HALN 2.41963+02 6009 1.04864+07 KNG 1~03663+06 HALt}6.80964+03 HMRN 5.0046&02 HAU'i 5.0046&02 HALN 1.42069+03 6009 4.2051!-05 6009 5.20X~2 HALN 4.205!}M 6009i 9.99987-04 6009 9.98974-03 HAU!8.85986+00 HALti 8.85986~00 H)tRN 6.22985-06 G009 1~8097~6009 1.52999-03 6009 5.00000e00 HALN 5.00000~00 HALN.0 GOOD 63.3 6009 63.3 G009 63.3-6009 63.3 6009 63.3 6009 63.4 6009 GRE)7: EVEWT2 PRKEDPF'PIP }-5 PLANT STATUS E.U.PN NPH 0""G.DEGF I)" GF DEGF NR/HR l8/HR N/HR NR/HR NR/HR N/HR CPN CPN CPN CPN V,'N CPN CPN CPN R/HR R/HR CPN UCI/CC N/HR UCI/CC fK:I/CC UCI/CC XI/CC UCI/CC XI/CC UCI/CC KI/CC NRIHR N/HR X DEGF DEGF KGF DE6F DE6F DEGF Time: 1235 Message: 63 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM 8 I C I il Simulated Plant Conditions: Messa<ee:<<""THIS IS AN EXERCISE"" The following Annunciator is received: '-10 (Auxiliary Building Sump Pump auto start).FOR CONTROLLER USE ONLY Controller Notes: 1)The"A" Auxiliary Building sump pump starts and runs for approximately one minute.2)Plant vent readings are decreasing due to Containment pressure reduction, reducing the leak out of the pipe between MOV-850A and Containment and also due to the resumption of core cooling reducing the radiation levels in containment. Actions Ex ected: 1)Operators should be performing the applicable actions of AR-L-10.2)Operators should be performing the applicable actions of E-1.3)Operators may realize at this time that the Auxiliary Building sump pump operation interval is increasing (decreased leakage)and should inform the TSC of this.4)TSC should be expediting sending a team into Auxiliary Building to check and/or turn on the AC power breaker for MOV-851A.5)TSC should be evaluating plant status and taking action as required.6)TSC may be evaluating the Auxiliary Building sump pump down interval change.7)TSC should be informing the EOF of plant status and actions being taken for plant recovery.8)EOF should be evaluating plant conditions and taking action as required.9)EOF Dose Assessment should be tracking the release plume and coordinating/recommending protective action recommendations to the Recovery Manager.10)The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action'recommendations to offsite agencies as required.11)Repair teams should be expediting repairs as conditions permit. Time: 1245 Message: 64~GI NA T TIGN 1993 EVALUATED EXERCISE MESSAGE FORM MMM I: 6 I 5 I 6 Simulated Plan Conditions: See Attached Sheets~Messa e:<<"eTHIS IS AN EXERCISE"~>>FOR CONTROLLER USE ONLY Controller Notes: 1)The team sent into the Auxiliary Building to check and/or turn on the AC power breaker for MOV-851A reports the following; de ndin n he si ua ion: 'f the AC power breaker for MOV-851A wa;~nip previously turned on,~hen the team will simulate turning it on and report this to the TSC at 1245 hours.'f the AC power breaker for MOV-851A~wa previously turned on and then tripped, the team will report there findings to the TSC and await further instructions. After evaluation the TSC should request the breaker be reset and reported turned on.This should be simulated by the team and reported to the TRG 2 5.~65. Actions Ex ected: 1)Operators should close MOV-851A when requested by TSC.MOV-851A will be consider d closed com le el at 1250 h urs isola in he leak on the i e be ween C n ainmen and IVlOV-85OA. 2)Operators should inform the TSC of MOV-851A closure.3)If the AC power breaker for MOV-851A was previously turned on and then tripped, TSC should evaluate this and most probably decide the following: 'he breaker could have tripped starting the closing cycle of the valve due to not being operated for a long period of time or the breaker may not have been completely reset the first time by the Auxiliary Operator.'ased on the above and the emergency conditions that exists, the TSC should have the team reset and turn on the breaker for MOV-851A and then request the Control Room to close MOV-851A.4l If the AC power breaker for MOV-551 A~wa no previously turned on, TSC will request the Control Room close MOV-851A. 1993 EVALUATED EXERCISE Time.-MAZOR PARAMET Reactor Shutdown YES NO N-3 1 CPS N-32~>~CPS N-35$~~AMPS N-36 l AMPS Avg.Nuclear Power RCS Pressure PRZR Level A RCP RUNNING/B RCP RUNNING OPPED lA S/G Level&6-~e 1B S/G Level lA S/G Pressure~PSTG 1B S/G Pressure PSIG Turbine/Generator ON E/FFLIN 4 KV Buses NERG ZE/DEENERGIZED 480U Buses ERGIZE/DEENERGIZED DC Batteries A l3QVOLTS B 8~VOLTS Cnmt Pressure~6G PSIG Cnmt Sump A Level~~FEET Cnmt Sump B Level INCHES" Loop Hot Leg G'F A Loop Cold Leg 0F B Loop Hot Leg I oF B Loop Cold Leg OF.RVLIS~IO*CET~ae'F S/G A Total Aux FW Flow~GPM S/G B Total Aux FW Flow 2 7 GPM DIESEL GENERATORS A.RUNNIN UNLOADED STBY OOS B.R NG UNLOADED OOS TSC RUNNING ED TB OOS Security RUNN UNLOADED B OOS ENGINEERED SAPEGUARDS Hi h Head S.I.Pum s FI-924 O GPM FI-925 GPM 1A.R S BY OOS 1B.NSE V STBY 1C.INSE V STBY 0 BAST Level=0 Low Head S..Pum s FI-626~O GPM 1A.NSER S Y OOS R C RC 1B.NSERU S B 0 C C RWST Level Containment S ra Pum s FI-931A~GPM FT-931B~GPM 1A.SERV TBY 00 1B.S V T OOS NaOH Tank Level=~Containment Recirc Pa s 1A.STBY OOS 1B.S STB OOS 1C.NSERV STBY OOS 1D.INS STBY OOS Post Aces ent Dampers OPE CLOSED Service Q er Pum s 1A.NSE S BY OOS 1B.SER S B OOS 1C.SERV S BY OOS 1D.SERV STBY OOS A&B Header ressure Qgg(n PSTG Com onent Coolin Mater Pum s ENGINEERED SAP DS 1A.INSERV TB OOS 1B.ER STBY OOS Surge Tank Level=~~Aux.Feedwater Pum s 1A.INSERU TB OOS 1B.ERV TBY OOS Turb.Driven INSERV TB OOS CST Level~0~FEET Standb Aux.Fee ate Pum s 1C.NS V STB 00 1D.INSERV TB OOS*CRT=Average of Selected Core Exit Thermocouples

NOV 17~1993 R.E.GINA SIHULATGR TRctG GROU.ASSIGtirUr(T SUl'il(ARY PAGE 1 GRQL!u'VE 1 PRQCEDL!Rr: EPIP 1"5 PLANT STATUS POINT iD ATMS 2 RXT 3 ti'3f 4 tt32 5 N35 6 tGb 7 NP 8 PRCS O'R!0 FR(A 1 1 FRCLB i2 RXT!6 13 RXT!7!4 TSUBTC!5 LSGA fb LS!iS!7 PSGA 18 PSGB GENBKR'0 GENBKR2 BUS!fA 22 BUS!!B 23 BUS!2A 24 BUS!2B 25 B!1A!2A 26 Bf!B!29 27 PCV 28 LSUHiPA 29 L09428 30 L0943E 31 L0942D 32 L09439 33 L0942C 34 L0943C 35 L09428 36 L0943B 37 L0942A 38 LO943A 39 T0409A 40 T0410A 41 T0450 42 T0451 3 TAVGAM!0 44 TAVGBMID 45 LRV 46 TCCQRE 47 FAUXFMA 48 FAUXFMB 49 B)(R081 50 BKR082 51 V3505 52 V3504 KS"RIP TIQN ANTICIPATED TRAtiSIEt(T M/0 SCRAH REACTOR TRIP BREAKER STATUS SOURCE RANGE DETECTOR N-31 SOURCE RA)iGE DFTECTOR N-32 ItlTERHEDIATc RANGE DETECTOR N-35 IurRH-DIATE RAN6 KTECTOR tt-36 AVERAGE t<UXEAR PGisER REKTOR CC9.4'O'YSTEH AV6 PRESS PRESS!JRIEER AVERAGE LEVEL PZA".TOR COOLANT LOOP A AVG FLOM REACTOR COOLS~!LQQP B AVG FLQM RCPA BRFAKER CAUSE RX TRIP RCPB BREAKER CAJS RX TRIP INCQRr TC SUKOOLED NARGItt STH GB~A t(ARRQM RANGE AVG LEVEL STH Get)B NARRDM RANCE AVG LEVEL STH GE)<A AY~RASE PRcSSURE STH GEN AVERAGE PRESSURE GE(PA!QR QN LINE BREAKER!61372 GEtERATGR QN'tt:-F.":EAKER 9X!372 BUS iih SLYLY BRBNER BUS f1B SL'PPLY BRACER NOT TERHINATED OM PPCS (7/!9/91)tlOT!cRHINATcD Oh PPCS (7/19/91)BUS 1!A TQ 12A TiE BREAKER BUS 118 TQ 128 T!E BREAKER CQNTAItlHEHT AVERAGE PRESSURE cQNT!AliNriEHT sUHP A AvERAGE LEAL SUi~8 LE%;~8 itlCHrS (TRAIN A)SLitF'LEVEL 8 ltlCHES (TRAIN 9)SUP B LEVEL 78 It&~':S (TRAIN A)St",P 8 LEVEL 78 ltlCHES (TRAItt B)S&i B LEVE.113 It(CHES(TRAlti') S%'LEVEL 113 INCHES(TRAIN B)SU..B ia~!180 INCHcEs(TRAit, A)SU)P 8 LEVrL 180 ItlCH S(TRAIN B)SL!HP B LEVEL 214 It(CHES(TRAIN A)SUNUP B LEViEL 214 It(CHES(TRAIN B)RCLA HOT LEG TEHPERATL!)K RCLB HOT LEG TEHPERATURcE RCLA COLD LEG TEHPERAT(RE RCLB COLD LEG TEHPERATm RCLA TAVG (THQT/TCQLD MIDE RNG)RCLB TAVG (THQT/TCOLD MIDE RNG)PEACTGR VESSEL AVERAGE!EVEL Ei.i INCORE TC AVERA6E TEHP S/6 A TOT4!A!JX FELDMATER FL(I S/6 B TOTA'iJX~cJNATER FLOM I'iTR AiJ)(ILIARY FEEDMATER PUHP A HTR AUXILIARY FEEDMATER PUHiP B AUX FM PUHP STEAH SUPPLY VALVE A AUX FM PUHP STEAN SUPPLY VALVE B VALK ATMS RX TRIPPED 3.02342+01 3.40015+01 1'0461-11 1.0046!-11 .00 2.~0~0.0 TRiPPED TRIPPED 9.4 66.2 74.1 0.0.TRIPPED TRiPPED TRIPPED TR!PPED NGT TRIP NQT TRIP NOT TRIP tiOT TRIP.N 31.2 HI6HER HIGH%HI6HER HIGHER HIG)irR HIGfB L(IER LQ))ER ALRH ALRH GQGD GDOD 6009 600!)6009 LEtl6 LALli INHB INHD ALRH ALRH LMR~HMRH HALtl LALH LA!H ALRH ALRr, ALRH ALRH KL DEL ALRH ALRH GOOD H@@i iNHB iNHB IH)(B IWE ALRH ALRH 6009 168.3 188.6 i80.1 81.0 190.6 0.27.OFF ON CLOSED CLQcED 6009 6009 6009 LA!!(600~600D GOOD LONER GOOD LQMER 6009 191.8 GOOD 191.8=-GOOD 185.4 E.U.P,S CPS AHP A!(P X PSI6//0/KGF//PSIG PSIG DEGF KGF DEGF KGF KGF KGF X KGF Gl'H GPH NGV 17>I'7'73 12.'45 R.E.GIt5A SlttULATGR TPEND GROUP ASSIGNtt>c'T SUttttARY PAGE 2 6ROL'P: EVBT1 PRGCEDLtR":: EPIP 1-5 PLAN'TATUS POINT ID DESCRIPTION VALUE OUAL E, U.53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BXR043 60 BKR044 SA.=TY INJECTION LOOP A AV6'FLOW SAF""TY Itl>3ECTIGN LOOP B AVG FLGtt SERVICE MATER PUtPS A t>.B HiADER SERVICi MATER PUttPS C 1 9 HEADER SiRVICE MATER PUYrP A S.:RVICE MATiR PUttP 9 SERVICE WATiR PUttP C SERVICE MATER PUCP 9 ON GN GN ON 0.GOOD 8'tt 232.6009 PN 87.600D PSIG 86, 6009 PSIG 600D GOOD 6009 6009 NOV 17(1993 12:46 R.i.GIQtA SIMULATOR TREttD GROUP ASS IGttNEhT SUNM(ARY 6ROUP: EVENT2 PROCEDURE: EPIP 1-5 PLAttT STATUS POINT ID 1 F0619 2 LNtS7 3 MS033 4 t(t9033 5 WT033 6 WT250 7 NDT2 8 RO!R02 10 RO5!1 R09 R34 13.R35 14 R!OA!5 Rll R12!7 R10B 18 R!3!9 R!4 20 R!8 21 R19 22 23 R30 24 R!5 25 R!2A5 26 R12A6 27 R!2A7 28 R12A9 29 R14A5 30 R!4A7 31 R!4A'9 32 R!5A5 33 R15A7 , 34 R!5A9 35 R31 36 R32 37 CVH 38 TCVO3 39 TCY07 40 TCVOB 41 TCV09 42 TCV10 43 TCV17 DESCRIPTION CQ(('0<cNi COQ'NG LOOP TOTAL FLW REFUELING t(tATBt STORAG" TAttk LVL 33 FOOT L~c N!t!D S~33 FOOT LEVE!.MIND DIRECTIOtt 33 FOOT LEVEL TENŽcRATURE 250 FOOT LEVcii TENPERATIJRE 250 TO 33 FOOT LEYEL DELTA TPJ'REA 1-COttTROL RGONi AREA 2-COtiTAINMEtt7 APEA 5-SPENT FUEL PIT AREA 9-LETDQtt."t Litt"" NGNITOR AREA 34-AUX BLDG CV SPRAY PtÃP APiA 35-PASS SAMPLE PA(M~CGttTA!tlNENT IODINE NOttITOR RiCA CONTAINMENT AIR PAR7ICLLA7E COttTAI ttMcCIT GAS NONITOR PLAUDIT YEttT IODltii tiQNITQR R!OB AUX B'G EXHAUST AIP, PARTICULATE AUX PJLG EXIST GAS NNITOR LISJID WASTE DISPOSAL KNITOR STEAN GBtERATQR&LOCON DRAIh AREA 29-CGttTAIN("LcttT MIGH RAttGE ARcA 30-COttTAINN(ENT HIBl RANGE CQcGB!SER AIR EJECTOR EXHAUST CY VBtT CHAtt 5-LOW Rk4(GE GAS CY VENT CHAL 6-a"EA GAte CV YB~!CHAN 7-NID RAttSE 6AS CV VENT CHAh 9+IGH RAttGE 6AS PLOtT Vitti CHAtt 5-LQN RANGE GAS PLgtT VittT CftAtt 7 NID RANGE GAS P'47 YEtt7 CHAh 9-HIGH RAttGE C+S AIR EJECTOR CHAN 5-LN RAtlGE GAS AIR iJECTOR CHAN 7-NID RANG'E GAS AIR EJECTOR CHAtt 9"HI RANGE GAS AREA 3!S7EAN Llki A (SPING)AREA 32 STEAM LINc, B (SPIN6)CV HYDROGEtt CONCENTRATION CV BASENENT LiVEL 6FT TENP tt3 CV IttTERNEDIATE LVL 6FT TEMP t!7 CV INTERMEDIATE LYL 6FT TEMP ttB CV INTFRNEDIATE LVL cFT TEMP tt9 CV!ttTERNEDIATE LVL 6FT TEMP tt10 CV OPERATING LEVL 6FT TEtP, 417 884.LALN 27.8 LORN 3.0 6009 41.6009 43.1 6009 38.8 6009-4,3 6009 8.86136M 6009 4.95448%5 HALN 3.19888+04 HALN 3,18053404 HALN 3.07255+04 HALti 1.09648+00 6009 1.02624<07 MENS 9.57744+06 HA'1.01303+07 fBt6 1.05014+06 HALN 2.55932+02 6009 9.66051+06 HALN 1~04562+03 6009 1.8972&03 6009 5.00465~02 HA!!l 5.00465+02 HALN 1.3548&03 G009 6009(2.00000+02 HALt', 4.20511-05 6009 9.99987M 6009 9.98974"03 HALN 4.42993-01 MA!!1 4'2993"01 6009 6.22985-06 6009 1'0975"05 GOOD 1.52999<3 6009 2.0000&00 HALN 2.00000+00 HALI!.0 G009 65.7 6009 64.4 G009 64.4"6009 64.4 6009 64.4 6009 63.2 GOOD E.U.GFN I NPH DEG.D:"GF IEF DEGF NR/HR NR/HR N/HR NR/HR NR/HR NR/MR CPN CPN CPN CPN CPN CPN CPN R/HR R/HR PN KI/CC t8/HR KI/CC XI/CC Kl/CC Xl/CC KI/CC XI/CC KI/CC XI/CC NR/HR t8/HR/KGF IFGF DE6F IFGF DEGF DEGF TIme: 'I300 Message:~E GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM~I C<<IR Simulated Plant Condi ions: See Attached Sheets~Massa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONI Y Controller Notes: 1)With the leak from Containment isolated, the.Auxiliary Building sump pump is no longer operating at short intervals and the plant vent radiation readings are beginning to decrease significantly. Actions Ex ected: 1)Operators should be performing the applicable actions of E-1.2)TSC should inform the EOF of the closure of MOV-851A and:the decreasing plant vent radiation readings.3)TSC evaluating plant conditions and taking action as required.4)TSC should be checking on the progress of repair teams.5)TSC should be informing the EOF of plant status and actions being taken for plant recovery. 6)EOF should be evaluating plant conditions and taking actions as required.7)EOF Dose Assessment should be tracking the release plume and coordinating/recommending protective action recommendations to the Recovery Manager.8)The Recovery Manager, after evaluating the EOF Dose Assessment recommendations, should update protective action recommendations to offsite agencies as required.9)Repair teams should be expediting repairs as conditions permit. 1993 EVALUATED EXERCISE Time: 13GD MAZOR PARAMET ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 O'PM FI-925 E2-GPM 1A SERV STBY OOS 1B.NSERV STB OS 1C.INSERV STBY OOS BAST Level=Low Head S.I.Pum s FI-626 D GPM 1A.INSERV B 00 RECIRC 1B.INSE V S BY 00~RECl~C RWST Level=~'.4 Containment S ra Pum s FI-931A O GPM F I-9 3 1 B~GP 1A.SE V 00 1'S RV TB OOS NaOH Tank Level=Containment Recirc Pans 1A.STBY OOS 1B.NS STBY OOS 1C.STBY OOS 1D.INSERV STBY OOS Post Accident Dampers PE CLOSED Service Rater Pum s 1A.SER STBY OOS 1B.SERV STB OOS 1C.NSE V STBY OOS 1D.NSE STB OOS A&B Header Pressure DIESEL GENERATORS A.UNNIN UNLOADED STBY OOS B.RUN NG UNLO DED OOS TSC RUNNING D BY OOS Security R UNLOADED STB@PSIG OOS'om onent Cooli Rater Pum s Reactor Shutdown YE NO N-31 CPS N-32 CPS N-35~o8 IA-MP9 N-36 AMPS Avg.Nuclear Power Q RCS Pressure PSIG PRZR Level CI A RCP RUNNING OPPED B RCP RUNNING 0 D 1A S/G Level 1B S/G Level 1A S/G Pressure PSIG 1B S/G Pressure PSIG Turbine/Generator NLINE OFFLI 4 KV Buses NERGIZE/DEENERGIZED 480V Buses NERGIZE/DEENERGIZED DC Batteries A~SOVOLTS B B~VOLTS Cnmt Pressure AF O~PSIG Cnmt Sump A Level FEET Cnmt Sump B Level g/8/L~INCHES e*Loop Hot Leg OF A Loop Cold Leg~2l~0F B Loop Hot Leg moe 3.OF B Loop Cold Leg ZGV.o QF RVLIS 27.5*CET~05'3 F S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow 0 GPM ENGINEERED SAP DS Aux.Feedwater Pum s 1A.INSERV OOS 1B.NSER TB OOS Turb.Driven INS RV B OOS CST Level~~FEET 1A.NSERV T OOS 1B.NSER STB OOS Surge Tank Level=Standb Aux.Pee wate Pum s 1C.INSE V B 00 1D.INSE V B OOS*CET=Average oi'elected Core Exit Thermocouples NGY 17)1993 13:00 R.i.GINA SltQLATG)" TREND GROUP ASSIGN)SAT SUNttARY PAGE GROS: EVÃt PROrcEDL)oc'PIP 1-5 PLANT STAT)JS 2 3 5 6 7 8 10 11~o 4 i')IV 14 15)6 17 18 19 20 21 22 23 24 26 27 28 30 3i'7'7 33 34 35 36 37 39 40 41 42 43 44 45 46 47 50 51 52 POINT ID AT)tS RXT N31 tf32 t)35 t(36 NP PRCS LPIR FRC A FRCLB RXTi6 RXTi7 TSUBTC LSGA LSo8 PSGA PSaB GENBKR!GENBKR2 BUSllb BUS!18 BUS!2A BUS!28 8!1A!2A 8!18128 PCV LSL)NPA LO942E L0943E L09429 L09439 l.0942C L0943C L0942B L09438 L0942A LO943A T0409A 704!OA T0450 T045.'AVGAMID TAVGB))ID LRV TCCQRE FAUXFN FAUXFWB BKRO81 BKROS" V3505 V3504 DEKRIPT ION ANTICIPATED TRAl(SIEt(T ft/0 SCRANi RiACTQR TRIP BRiAKER STATUS SWEE RANGE DETECTOR N-31 SOLRCi RAttGE DHcCTQR t&32 INTERNcDI ATE RA)tSc DcTECTOR N-35 It(TERNEDIA7i RA)i'Si DE7ECTOR N-36 A%RAGE t)UCLEAR PQNER RiA"TOR COOLANT SYSTEtt AVG PRESS PRcSSURIIER AVERAGE LEEK RE@".TOR COOL)'<T LOOP A AVG FLG)f RiACTGR CCCLANT LGQP 8 AVG FLGN RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP!t(%RE TC SUBCOGLED NARGIN STH iciN A t'ARROM RANGi AVG LEVEL S7tf Gib 8 NNM)t RA)(6=AVG mW STN GB)A AVERAGE PRESSURE STt)rD 8 AVERAGE PRESPJRE CURATOR Ot(LINc BRiAKER!G!372 Gci)IK)tATGR Qtl INE BREAKER 9X1372 BUS 1!A SUPPLY BREAKER F)!S!18 SUPPLY BREAKcER t(QT TERNlt)ATED Gft PPCS (7/!9/91)tST TPt)INTED Oft PPCS (7/!9/91)BUS 1!A TG!2A TIE BREAKER BUS 1'8 TG 128 T)E Befit'"ER CQt()Alt)NB(T ACR/)Gi PPESSU)RE CON)Alt<NEcN)T SJt)P A AVERAGc LEYFL SU~8 LEYiL 8 INCHES (TRAit(P)SLtF 8 LEVEL 8 It)CHES (TRAIti 8)SU)~B LEVEL 78 Iti".HES (TRAIN A)S)J)", 8 L VEL 78 INCHES (TRAItt 8)SUNP 8 LEYE'13 It),(ES(TRAIN A)S(trP 8 LEVEL 1 i3 It'Cf'cS(TRAIN 8)SU~8 LcVEL 180 INCHcS(TRAItl) A)-").)..8 LEVci 180!NCHES(TRAIt(8)SU'P.LEVEL 214 INCHES(TRAIN A)SURF 8 LEVEL 2!4 INCHES(7RAIN 8)RC)LA HOT LEG TEtPERATURE RCLB HQT LEG TEtff)ERATUR=" RCLA COLD LEG TE)FERATNE RCLB COLD LEG TEE ERATO~RCL".TAVG (Tf(07/!COLD f(IDE Rt(S)RCLB TAVG (THQT/TCQLD HIDE Rt(6)REA"TOR VEA:.i Aver)AGE LEVEL Ei..: INCQRc TC AVERAGE TENP S/6 A TOTAL AUX F:cDRATER FL(L)S/6 8 TOTP'UX FEEMTER FLGr NiR A'J.'(ILIARY FEED~ATER PUlP A NTR AUXILIARY FEED)(ATER PU5'A)JX FN PUNP STEA)i SL)r'PLY VALVE A AUX FW PUNP STEAN SUPPLY VALV 8 YALUE OFF GiN Ct.OSED CLOSED ASS ALRti RX TRIPPED ALRN 8.37527+01 6009 8.!1894%1 GOOD i.Oi859-ii 6009 1.01859-11 6009 ,00 6009 2.LEND.0 LALN 40.2 INH>>~0 INHB TRIPPED ALRN TR IPPED ALRN-54.1 LAL>>66.4 fNRN 78.i HALN 2, LALt,'.LA))f TRIPPED ALRN 7RIPPED ALRN TRiPPED ALRN 7R!PPiD ALRN t>QT TRIP IFX t87 TRIP DEL t))Q": TRIP ALRt')t(DT 78IP O'N 2.01 Haiti 31.2 HEt(6 HI6HER IN)(B HIS(FR It(HB HIGHER INHB HI SHE rR INN B Hlsr)ER ALRtf HIGHER ALRN LG)lER 6009 LONER 6009 LO)!ER 6009 LG'wP KQD 216.8 6009 200.2-6009 214.8 6009 204.5 6009 215.8 6009 202.3 6009 27.3 LALti 303.3 600>>0.GOOD 0.GOOD GOOD 6009 GOOD GOOD E.U.CPS CPS Al(P A%'SIG 7//IFGFÃ7 PSIG PSIG PSIG FEET DEGF!FGF DE6F IFGF DEGF DEGF X DcGF GPtt/;$ NOV 17~1993 13:M R.E.BIO!A Sll~LATOR PAGE 2 TRBG GROUP ASSIGIENT S'JltNARY 6ROUP: EVENT1 PROCEDURE: EPIP 1"5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P 160'6 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 DES"RIPTION SAFETY IN.'ECTIOlt LOOP A AVG FLOM SALTY IN:ECTION LOOP B AVG FLOW SERVICE MATER PUllPS A 6 B HEADER SERVICE WATER PUltPS C 4 D HEADER SERVICE WATER PUlP A SERVICE MATER PUhP B SZVICE Mem PUltP C SERVICE WATER PurP 9 ON ON ON ON VALUE 0.232.87.86.QUAL E.U.GOOD GPlt GOOD PN 6009 PSIG 6009 PSI6 6009 6009 6009 6009 NGV 17i}993}'1~05 R."".ulNNA SitPJLATGR PA6E 1 TREND GRQU?ASSIGttttiti~i SU"DIARY GROUP: "uVittT2 PROCES}Ri; EP:P}-5 PLAIIT STATUS POI (T 9 DESCRIPTION VALLF E.U.3 10.'3 f$a5$C~4 16!7 18!9 40 21 23 24 25 26 27 28 29 30 31 f I3 v0 34 35 3o 37 38 39 40 41 42 43 F0619 LRMST h'S033 hm33 NT033 NT250 NDT" RO}RO2 RO5 R09 R34 R35 R!OA Rli R}2 R}OB R!3 P,14 R!B R}9 R29 R30 R15 R12A5 R}2A6 R}?A7 R}289 k}4A5 R14A?R}499 R15A5 R!5<<7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCVO9 TCV10 TCV!7 CWPQt<Et<T COO'NG LOOP TQTAL FLN REFUELING NATE STORAGE TAtR LVL 33 FOOT LE(~MitiD SPED 33 FOOT LEVEi NIND DIRECTIGtt 33 FOOT LE(P TEMPERATURi 250 FOOT LE(j~TEMPERATURu 250 TO 33 FOOT LEVEL DELTA TEIIP 4REA}-COW(9 ROQMi N~o-Gt'TAI"M-N AR":A 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MGiNITQR AREA 34-AUX BLDG CV SPRAY PUtL>AREA 3~PASS oA"(om PANEL CONTAINi!ENT IODINE MQtiITGR R}CA CG!(TAI tIMEt(T AIR PART ICS.ATE CQttTAINMENT GAS MONITOR PLANT VEt(T IQDItF.MC>tITOR R!OB AUK P DG EXHAUST AIP, PARTICULATE AUt(BLDG E!EXHAUST GAS t(GNITOR LIQUID hASTE.DISPOSAL MONITOR STEAM GENEPATOR Bt ONDGII(DRAIN AREA 29-CGNTAINMEWT Hi&RAVoE AREA 30-CGt)TAINMEtti HI&I RANGE CGtIDBISER AIR EJECTOR E)(KAUST CV'JitiT CHAti'-LON RAt<"='AS CV VENT Ci'At 6-AREA 6@TtA CV VIP.CNtt 7-M!9 RA4'u=GAS CV V t'ai CHAtt 9-HIGH RkNGi GAS PLklT VEttT Catt 5-LU>>RANG:" uAS PL4/Pi VENT CHAN t'iID RANGE GAS PLANT VENT CHAN o-HIGH RANGE 6AS AIP, E3ECTOR CHAN 5-LO'A Rk><ui 6AS AIR EJECTOR CHAti 7-MID RANGE CAS AIR EJECTOR CHAN o HI RANGE 6AS AREA 3}STEAMi LINE A (SPING)AREA 32 STEAM LINE 9 (SPING}CV HYDRGGEtl CQNCEt(TRAT ION CV BASEMENT L-"V SFT TBI?<<3 CV INTERMEDIATE LVi.6FT~TEMP<<7 CV ItiTERMEDIATE LVL SFT TBP<<8 CV'.INTERMEDIATE LVi 6FT'TEMP<<9 CV INTERtfiDIATE LVL hri TEMP<<10 CV OPERATING L VL SFT TEMP<<17 6494, 6009 23.6 LNRII 3.0 GOOD 41.6009 43.1 6009 38.8 6009-4.3 6009 9.44062-02 6009 2.98538<05 NLtt 1~23027+01 6009 2.8346&0}G009 3.42767+01 SFut 1.09648+00 GOOD 9.66051+06 HALtt 9.99992+06 HALtt 1.03962+07 HENS 1.0}449+06 NLII 2.46178+02 6009 9.78647+06 HALM 1.05014+03 6009 1,89725+03 GOOD 2.99398~02 HALM 2,99398+02 HALtt}.4024}<03 6009 4.20511-05 6009".00000+02 HALM 4.20511-05 6009 9,99987-04 GOOD 9.98974-03 HALM 4.42993-01 HALM 4.42993-0} 6009 6.22985-06 6009 1.80975-05 6009}.52999M 6009 2 00000>%HM 2,00000+00 HALt!.0 6009 84.4 6009 92,o 6009 93.1".6009 92.9 GOOD 93.1 6009 101.8 6009 GPM X MPH DEG, DEGF DEGF DEGF MR/HR MR/HR MR/HR MR/HR MR/HR N/HR CPM CPM CPM CPM CPM CPM CPM CPM R/HR R/HR CPM KI/CC%/HR KI/CC XI/CC KI/CC UCI/CC KI/CC UCI/CC KI/CC XI/CC MRIN t8/HR I/DEGF DEGF DEGF DEGF DEGF DEGF Time: 13'I5 Message: 66 GINNA STATION 1SS3 EVALUATED EXERCISE IVIE A E F RM 8 I<<L'R Simulated Plant Conditions: See Attached Sheets~Massa e:<<"<<THIS IS AN EXERCISE FOR CONTROLLER uSE ONLy Controller Notes: Actions Ex ected: 1)Recovery/Re-entry discussions may commence.This should include preliminary discussions about short term and intermediate term concerns, including preliminary designation of the Recovery organization. 2)State and counties may also conduct parallel discussions. Recovery/Re-entry interface between TSC/EOF and offsite agencies should be demonstrated as time allows. 1993 EVALUATED EXERCISE Tuse: j 3/+MAZOR PARAMET ENGINEERED SAPEGUARDS Hi h Head S.I.Pum s FI-924~GPM FI-925 2'B~GPM lA.RV STBY OOS 1B.S V STB OS 1C.INSERV STBY OS BAST Level=~0 Low Head S..Pum s FX-626 00 GPM 1A NSER ST Y OOS RECIRC 1B.INS V STBY 00 REC C RWST Level Containment S ra Pum s FZ-931A 0 GPM FZ-93 1B~GP 1A.NSERV TB 00 1B.S V TB OOS NaOH Tank Level=Containment Recirc Pans 1A.STB OOS 1B.NSER STB OOS 1C.NSERV STB OOS 1D.NSERV STBY OOS Post Aces ent Dampers OPEN CLOSED Service Water Pum s 1A R TBY OOS 1B.SER STB OS 1C.SER STB OOS 1D.NSER STB OOS A&B Header Pressure~PSZG DIESEL GENERATORS A.UNNIN UNLO DED STBY OOS B.RUNNING UNLOADED B OOS TSC RUNNING D OOS Security R UNLOADED TB OOS Com onent Coolin Wate Pum s Reactor Shutdown YE NO N-3.1 CPS N-32 CPS N-35-/I AMPS N-3 6/.OS-I AMP S Avg.Nuclear Power 0 RCS Pressure~PS IG PRZR Level O A RCP RUNNING TOP B RCP RUNNING E 1A S/G Level 1B.S/G Level~), I a 1A S/G Pressure PSIG 1B S/G Pressure~PSIG Turbine/Generator E OFFLXNE 4 KV Buses NERGI DEENERGIZED 480V Buses ENERGXZE DEENERGXZED DC Batteries A~3VOLTS B f80 VOLTS Cnmt Pressure'~I~PSIG Cnmt Sump A Level FEET Cnmt Sump B Level (Q~Q.INCHES " Loop Hot Leg H,'F A Loop Cold Leg Pop oF B Loop Hot Leg~lO+oF B Loop Cold Leg F RVLIS 3~I*CET 7 oF 9/G A Total Aux FW Flow~GPM S/G B Total.Aux FW Flow C'PM ENGINEERED S DS Aux.Peedwater Pum s 1A.INSERV STB OOS 1B.NSER T Y OOS Turb.Driven INSERV STBY OOS CST Level~~e F 1A INSERV STB OOS 1B.NS STB OOS Surge Ta evel=~0-4 St ndb Aux.Pe wate Pum s 1C SE V 00 1D.XNSE V B OOS*CET=Average of Selected Core Exit Thermocouples NOV 17r 1993 13'1 R.E.GINA STATOR TREND GRQ'UP ASSIGt(t(B(T SU4iARY PAGE 1 GROUP: EVENT!PROCEDN" EPIP I"5 PLANT STATiJS POlt'IT iD DESCRIPTION YA's" OUAL E.U.ATtlu 2 RXT 3 N31 4 N32 5 N35 6 N36 7 NP 8 PRCS 9 LPlR 10 FRC'11 FRCLB!2 RXT!6 13 RXT17!4 TSUBTC 15 LSGA.'6 LSGB 17 PS6A!8 PSGB 19 GENBKRI 20 GENBKR2 21 BUSl!A 22 BUS!18 23 BUSI2A 24 BUS!28 25 811A!2A 26 8118!28 27 PCV 28 LSNPA 29 L094 c 30 L09438 3!L0942D 32 L0943D 33 L0942C 34 L0943C 35 L09428 36 L09438 37 L0942A 38 L0943A 39 T0409A 40 T04!OA 4!T0450 42 T0451 43 TAVGAWID 44 TAVGBNI 9 45 LRV 46 TCCQRi 47 FAUXFWA 48 FAUXFMB 49 BKR081 50 BKR082 51 V3505 52 V3504 At(TICIPATED TRAt'SIBIT N/0 SCRAt(REA"TGR TRIP BREAKER STATUS SOURCE RANK D""TECTOR N-3!SO(RCE RANGE DcTECTQR 4~32 It MDIATE RAt(SE DETETQR N-35 It)T-Rt)EDIATE RANK DETECTOR N 36 AVERAGE tNCLEAR PGNER REACTOR COOLLY'YSTEt(AVu PRESS PRBPJRIlER AViRACc LEVEL REACTOR CC@LAltIT LOOP A AYG FLQN REACTOR COOLANT LQQP 8 AVG FLN RCPA BREAKER CAUci RX TRIP RCPB BREAI(ER CAUSE RX TRIP Iti'ZRE TC SUBCGOLED NARuGlN STH Gcdt A NAIIO'rt RANGi AVG Ls Ski GEN 8 t(ARRO'rt R/N(6c AVu LEVY.STtl Sett A AVERAGE PRcSSURE STt)GEN 8 AVcDAGE PRESSURE GchERATGR QN LINE BEAKER 1G1372 KteRATOR ON LINE BREAKER 9X!372 BUS!!A SPPLY BPrEAKER BUS 118 SUPPLY BRFAKER NGT TERNINATED Oti PPCS (7/19/91)AT TERNINATED Qt(PPCS (7/'19/91) BUS I!A TO IM TiE BREAKER BUS 118 TO 128 Tli B.""=AKER COt(TAINt(Et(T AVERAGc PRESSURE CONTiAINNENT SU'P A AVERAGE LEYEL SUPP 8 Li()EL 8 It(CrtcS (TRAIN A)SUt..8 IEIsc'INCHES (TRAit(8)SUtP 8'YrL 78 INCHcS (TRAIN A)SU~8 Lied 78 itiCPcS (TRAIt)8)SU!(r'LEVEL 113 It(CHcS(TRAIN A)SUtP 8 LEY"L 113 It(CHES(TRAlt(8)SUli'LEVEL 180 It)CHES(TRAIN A)SN, 8 LcYEL 180 INCHciS(TRAIt, 8)SU,"P 8 LEVEL 214 It(CHiS(TRAIN A)SUN'I EYEL 214 ItZHES(TRAIN B)RCLA HQT LEG TEt(PERATUic RH9 HOT LEG TEt(PERATiJRci RCLA COLD LEG TBiPERATNE R"LB COLD LicG TE))PERATLRE RCLA TAVG (THOT/TCQLD WIDE RIIG)RCLB TAVG (THOT/TCOLD NIDE RNG)RiA.TGR VESSEL AYrRAGc LEVEL El.!It<CORE TC AYB(AGE TEt(P S/6 A TOTAL PJX FEEDS'ATiR FLG'A S/G 8 TOTAL AUX FHGNATER FLOÃt)TR AUXILIARY FEEPAATER PUN.-" A i",TR AUXILIARY Fc D(IATER PUIIP 8 AiJX FM PU)IP STEA)I SUPPLY VALVE A AUX FN PU)IP STEA))SL'PPLY VALVi 8 ATNS RX TRIPPED 1.72981+02 1.72981+02 1.03276-11 1,02330-11 .00 3,~0 69.9 38.8 TRIPPED TRiPPED-480.3 65.1 80.1 0.0.TRIPPED TRiPPED TRIPPED TRIPPED NQT TP,IP t(0;TRIP tl0";TRIP tIGT TRIP 3.15 31.2 HIGF&c, HIGHcCc HIGHER HIGHS HIGHS HIGHcR LONER LONiR LONER ALN'i ALRt{GOOD 6009 6009 GOOD 6009 LENC LALN ItfrfB INH~ALR)I ALRN LALt HtARII HAL)I LALVi LALl(ALRII ALRt(ALRti ALRN DiL Dii ALRII ALR)I HNRI(HENS INHB It(HB INHB It(HB ALRH ALRt(GOOD 6009 6009 209.9 209.4 211.5 209.9 39.1 625.7 0~0.Gr;Gtt CLOSED CLOSED'j'/~3 6009 6009 6009 gtRe 6009 G009 6009 G009 G009 G009 LVAER 6009 213.1 GOOD 210.4".6009 CPS CPS A)P A."IP X PSIG X X X DEGF/X PSIG PSIG PSIG DEGc DEGF DiGF DEGF DEGF DEGF/DEGF GPt(GPtt NOV 17'993 13l15 R.E.GINtA SNiLATOR TREtG GROUP ASSIGtttHT SL4:"4RY PAGE 2 6ROU,: EVit/Tl ROCEOURi;EPIP 1"5 PLAt,i STATUS POINT IB 9""SCRIPT IOti'ALL~'UAL E.U.53 FSIA 54 FSIR 55 P2160 56 P2161 57 BhR041 58 BKR042 59 BKR043 60 MR044 SAF"=TY INiECTIOt> ~OOP A AVG FLOP SAFETY INJECTIOW LOOP B AVG FLOP SERVICE tNTER PUTS A~~B HEABER SERVICE%TER PUttPS C 5 9 HEA9ER SERVICE LATER PUtlP A~""P'ICE WATER PUt'~B S~D'ICE MATE PUP.C EH)ICE STER PUt!P D ON ON Oli CA>'.6009 PN 232.6009 Ptt 87.6009 PSIG 86.6009 PSIG 6009 6009 6009 6009 tQV!7i 199a~~!do Xv P,.E.iGiit'iA SINN AT">PAGE 1 TREt i GRGU?ASSIGNIQT SUtt"~ARY GROU',".EV tiT'>PRQFDURE: EPIP!-5-"LANT STATUS 1 3 4 5 6 7 8 10 t~~S 13 16 t/F0619 LRMST MS033 MD033 MT033 MT250 MDT2 Rei RO.R05 R09 R34 R35 R!OA P.l 1 R12 R!OB 18=R13!9 20 r>1 22 23 25 Q~27 30 3t VC v'4 34 33 36 3 i 38 30 40 45 43 R!4 R!8 R!9 P io P~P R'15 R!2A Ri~&6 R!2A?R!2A9 R!4."5 R!4A7 R!4A9 R!5A5 R15A?R!5A9 RS!R32 CVtf TCV03 TCVO?TCVOS TCVO9 TCV!0 TCV!7 POINT!9 DESCRIPTiQN COtPONENT COOLING LOOP TOTAL FLW Rt""Lt-"i INB MAT%STORAGE TANK LVL 33 FOOT LEVEL M!ND SPEK 33 FOOT LEVP MitS DIRECTitON 33 FOOT LEVEL TEtt?ERATLIRE 250;GQT LEV" TEi.FERATURE 230 TO 33 FOQ LEVEL DELTA TEN'R=~!-CGNTRP RDO."i A.<<".=A 2-COhTAlht'iEtiT AFEA~-SPEtiT U:.L P.'T t5E".9 LETDQMN LltvE t'QiNITGR A>J".-" 3g-AUy BLDG CV&RA'/RJYP A.'tEA 3H'ASS SA,"t?LE PALP CONTAItNEt)i 1091tiE tati'ITOR R!OA CGtfiAIN KtiT AIR PARTICULATE CLtNTAIhNEt(T GAS ttDtiITOR PLA!IT Wc, iT IODIti.: t!QNITQR R!OB AU!B DG FÃHAUS.AiP.PARTICULATE AUi Bt DG EXHiiST GAS ttMTQP, l IBID MASTE DIS?QSA'QNITOR "-t="" GENERATOR E'0'~JR!DRAIh-'.,=.-'.2"i-CG.(TAIt<" t"!HIGH RPi.~i=AR=-'0-CQiiTAiti.BiT HIGH RANK CONiDEtS~m AIR EJECTOR EXHAUST CV VENT CHAN~LO'n RANK GAS"V VEN:.CHAN a-AREA GA~a@t V V"" C!.At'P GH PAt" GA<PLk!T VEt~t CHAti=-GA RANGE GAS.P="'!'EtiT CH~i 9-H"-".'.RP3:--" GAS AiR E:ECTOR CHAlŽ='GM RAt(G" 6AS lc..3EL'TQR C'".:AN 7-tilD RA%-" GAS AIR EJECTOR CHttN 9-HI R46E GAS k>>-"='.3!STEA"'NE A (SPIt<6!~."~32 STER"i't(E B (SPltiB!CV%&QBEN COtiCEhTRATION CV BASEV~NT LEV=6~1 TEN?C CV INT""RiiEDIATE LV-'FT TP.".4?CV ItitERt'iEDIATE LV 6FT FJP 48 C" Il~trFN:DIATE LV'FT TEttP!!9 CV It!TERt(ED!ATE LV'FT TEt(P tt!0 CV QPERATINS i":t>>6F TEtP I!7 VALU=6493.22.3 3.1 41.43.!38.8-4.3 8.56051-02 3.05492+05 1.31069<01 3.00262+01 1.25!?~I 1.09648+(I 1.00432+07

78647+06'.03068407 1.02772406

,46178+02 5.43249te! 1.01888+03 1.9'89 2+03 2.99398+02 2.99398+02 1.39035403 4.20511-05 1.00000I02 4.20511-05 9.99987-04 2.3099!~"'20996-03 2.20996-03 6.22985-06 ii80975-05 !.52999-03 1.00000+00 1 00000<M 7'?.5 QUAL GOOD LMRti 6009 6009 6009 6009 6009 6009 HALtt 6009 6009 HMRN GOOD HENS HA'HEti6 HALL!6009 GQQD GOOD 6009 HALE(HALtt 6009 6009 HAU', GMD BGQD 6009 6009 6009 6009 6009 HALH 6009 GOOD 99.7 GOOD 99.7%009 99.?6009 99.7 GOOD 120.0 6009 E.U.6%i/AH IFG.IFBF IFGF DEBF t(R/HR tS/HR tS/HR tS/HR tg/HR tS/HR CPt!CPt!CPtt CPA CPt!CPN CPt!CPtt R/HR R/HR CPN Xl/CC tS/HR UCI/CC KI/CC KI/CC KI/CC KI/CC KI/CC UCI/CC KI/CC tS/HR tS/HR X DEGF DER DEGF DEBF DEG!.DEGF Time: 1330 Message: 67 GINNA STATION 1993 EVALUATED EXER ISE MESSAGE FORM Fi I<<C<<IR Simulated Plant Conditions: See Attached Sheets Messacee:<<~"THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes: 1)Accident evaluation and response continues. Actions Ex ected: 1)Recovery/Re-entry and declassification discussions should commence per the guidance provided in EPIP 3-4,"Emergency Declassification and Recovery". Discussions should include but not be limited to the following: A)Preliminary discussions between the EOF and the TSC on the following: 'hort Term plant concerns such as;1.Cool down of the plant 2.Repair and return to service of 480 volt Bus 14 transformer. 3.Repair and return to service of the"B" RHR pump, 4.Repair and return to service of the"B" Sl pump.5.Repair and return to service of the"C" Sl pump.6.Repair and return to service of the Bus 14-16 tie breaker. 'ntermediate term plant concerns such as: 1.Core damage assessment. 2.Clean-up of Auxiliary Building.3.Clean-up of water in containment. 4.Long-term core cooling.5.Radiological release calculations and evaluation.-B).Preliminary designation of the recovery organization. C).State and counties may also conduct parallel recovery/re-entry discussions, 2)Recovery/Re-entry interface between the EOF/TSC and offsite agencies should be demonstrated as time allows. 1993 EVALUATED EXERCISE Time:~~0 MAZOR PARAMET Reactor Shutdown~Y(YES NO N-31 CPS N-32 0 CPS N-35 I~0-I AMPS N-36/~~AMPS Avg.Nuclear Power RCS Pressure PSIG PRZR Level A RCP RUNNING OPPED B RCP RUNNING STOPPE 1A S/G Level 1B S/G Level 1A S/G Pressure C'SIG 1B S/G Pressure 0 PSIG Turbine/Generator ONLINE FFLI 4 KV Buses NERGIZE/D ENERGIZED 480V Buses RGIZED/DEENERGIZED DC Batteries A~VOLTS BQgVOLTS Cnmt Pressure~e'j 2 PSIG Cnmt Sump A Level~~FEET Cnmt Sump B Level p~~<LINCHES A Loop Hot Leg~IG 7 OF A Loop Cold Leg!'ok F B Loop Hot Leg~~a'7 DF B Loop Cold Leg 0F RVLIS*CET OWAQ OF S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow D GPM DIESEL GENERATORS A.NING UNLOADED STBY OOS B.RUNNING UNLO ED TB OOS TSC RUNNING D TB OOS Security RUNN UNLOADED TB OOS ENGINEERED 8 DS ENG1NEERED SAPEGUARDS Hi h Head S.I.Pum s FI-924 GPM FI-925 0 GPM 1A.NSER STBY OOS 1B.INS RV STBY 0 1C.I SERV STBY OOS BAST Level=Low Head S.I.Pum s FI-626 GPM 1A.NSER ST OOS RECIRC 1B.NSERV STBY 0 RECI C RWST Level=Containment. S ra Pum s FZ-931A C>GPM FI-93 1B~GP 1A.NSERV TB OOS 1B.NS RV STB OOS NaOH Tank Level=~%Containment Recirc Pans 1A.NSER STBY OOS 1B.NSER STBY OOS 1C.NSERV STBY OOS 1D.SERV STBY OOS Post Ace>ent Dampers PE CLOSED Service Rater Pum s 1A.SER S BY OOS 1B.E S B OOS 1C.SERV STBY OOS 1D.NSER STBY OOS A&B Header Pressure~PSZG Com onent Coolin Rater Pum s 1A.INSERV B OOS 1B.NSER STBY OOS Surge Tank Level=Aux.Peedwater Pum s 1A.INSERV OOS 1B.INSERV TB OOS Turb.Driven INSERV TB CST Level FEET OOS~Standb Aux.Reedwate Pum s 1C.INSE V 00 1D.NS V B OOS*CET=Average of Selected Core Exit Thermocouples

17~1993 13:31 P..=.GIM4 SI""GATOR TREND GRG!!;" AcSSIGMttB)T SXNRY PAGE 1 GRQ"?: EVEMTl PRGCcDU((=: EPIP I"5 PLANT STATUS POINT ID DcS"RI PTIGtt VALUE<K)AL i.U.1 ATMS 2 RXT 3 N31 4 tG2 5 t(35 6 t(36 7 HP 8 PRCS 9 LPIR s'0 FRCLA 11 FRCLB.'2 RXT16 13 RXT17 14 TSUBTC 15 LSGA 16 LSGB'7 PSM 18 PS68 19 GENBKR'i 20 GENBKR2 21 BUS11A BUS118 23 BUS!2A 24 BUS128 25 811A12A 26 8118129 27 PCV 28 LSU,'(PA 29 L0942E 30 L0943E 31 L09429 32 L09439 33 L0942C 34 L0943C 35 L09429 36 L09438 37 L0942A 38 L0943A 39 T0409A 40 T0410A 41 T0450 42 T 0451 43 TA VGA))ID 44 TAVGBWI9 45 LRV 46 TCCORE 47 FAUXF((((48 FAUXFWB 49 BKR081 50 BKRO82 51 V3505 52 V3504 AMTICIPATED TRANSIENT 4/0 SCRAt(REACTOR TRIP BR""AKER STATUS SG(RCE RAt&e DTECTOR N 31 SGURCi RANGE 0""TECTC~. )(~32 It(T"-RADIATE RANai 0:"TEiTOR N-35 ltfFRNEDIATE RN(ci DETECTOR M-35 AVERAGc NUCLEAR POWDER REACTOR LGOLAN SYSTEtt AVG PRFSS PRESSURIZER AViRAGE LEWD.REA TOR COOLANT LQQP A AVG FLSi REACTOR CGiLA!)T LGGP 8 AVG FLG)t RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAJSE RX TRIP It(OGRE TC SUB':03LED NRGIN STV(GEtl(A NA)mOW RAt<GE AVG LE'l(~r STN GEM 8 t(ARRQ~RANCE AV6 LEVEL STtt 6EN A AVEPA"" PPZSSiJRE STN GcC(8 AVERAGE PRESc()R"= Gc(ORATOR QN LitK B."",EAKER 161372 GitZRATOR GM'tr=SPEAKER 9r1372 B(JS 11A St)PPLY BF"-VR, B(JS 118 SUPPLY BREA(~" P t(GT TERttlt(ATED Ou PfiS (7/!9/91)t(()T TERV(lt(ATED OM PPCS (7/19/91)BUS llA TO 12A Tii BREClER BL'S 118 TG 128 Tli BREAKER CGWTAIN!(Et(T AVERt(GE PRESSURE CGt<TAINNEt(T SiJl'AVERAGE 1.LVEL SU(&, 8 LEVEL 8 IN'ES (TRAltt A)SUtt 8 LE4cL 8 ItlCHES (TRAlt(8)SU~('LEVEL 78 ItlCHES (TRAItt A)SU P 8!LEVEL 78!tG-"S (TRAIN 8)SU~8 LEVP 113 It<;"MES<TRAIN A)SU('P 8 LB~J.113 INCHES(TRAIt(8)SUP 8 LBrrL 180 It("'.HES{TRAItt A)SU~i.8'V"'80 It)CHES(TRAItt 8)SUi~8 LEVEL 214 INCHES(TRAItl A)SUN'LEVEL 214 It(CHES(TRAIt(8)RCLA HQT LEG TEt(PER4TU(RE RCiB HOT LEG TEttPERATU~ RCLA COLD LEG TEt(PERATNE RC(8 CG'LEG TE)(PERATNE RCLA TAVG<THGT/TCQLD WIDE Rt(6)RCZ TAVG (TttOT/TCQ' WIDE R)Pi:)REA"TGR VESSEL AVERAGE'V="L El.1 INCORE T" AVERAGi Tir,'P S/6 A TOTAL AUX FERA;"!TER FLG'(S/6 8:OTAL A'JX FEED)(ATER F'N gR AUXILIARY FEcPAATER PUV(P A t(TR AUXILIARY FEEDS'ATER PUt'.9 A(JX R!PUt(J'TEA)l SU-EELY VA'c A A!J)'FR PUlP STEAtl S('rPLY VALV"" 8 OFF OFF CLOSED CLOS"9 AT)tS ALRtt RX TRIPPED ALR)t l.36301+02 6009 1.40119402 6009 1.02801"11 6009 1.02330-11 GOOD.00 6009 4.LENG.0 LALtt.6 INHS~0 INHS TRIPPED A(.Rtt TRIPPED ALRt(-169.4 LAL~64.3 Ht((Rti 82.1 HALM 0.LALtt 0.LALtt TRIPPED ALRtt TRIPPED ALRN TRiPPED ALR)t TRIPPFD ALRtt t(0!TRIP DEL NOT TRIP DEL t<GT TRIP ALRtt NG!TPIP ALR(t 3.62 H)tR)t 31.2 HENS HI6)&INHS HI6HEP, INHS H16HER It(HS HIGHER It<HS HI6H":P.INH9 HI6H:R'NHS HIGH ALRt(HIGHER A'tt LG((ER 6009 LO)tiR 6009 210 7 6009 210.7%009 214.5 6009 212.9 6009 212.3 6009 211.9 6009 34.7 LALtt 305.6 600>0.6009 0.6009 6009 6009 6009 6009 CPS CPS Al(P NP/PSIG/7 DEGF I/K PSIG PSIG PSIG FEET KGF DEGF DE6F DEGF D"6F DEGF D='GF GP(t GPtt t<OV 17~1993:13:3.: .R.E.Sly'A SIN&TOR TRE!6 GROUP ASSIGNt~ctPi S3t'NARY PAGE 2POPIT iD 53 FSIA 54 FSIB 55 P2150 56 P2161 57 BKR041 58 BYR042 59 IIR043 60 BKR044 DESCRIPT IGI'~cY INJECTION LOOP A AV6 FLOW SA,HY ItbcCTIOM LOOP 8 AVG FLO'A SERVICE WATER PUtfPS A h B HEAD.R SERVICE WATER PUtrPS C 5 D HEADER ScRVICE WATER PLttP A SERVICE MATER PUtlP B SINCE WATER PU5'SERVICE WATER PU'P 8 VALUE QUAL E.U.0'<Oh'N ON 0.408.87, 86.6000 SPY GOOD 6.X 6000 PSIG 6009 PSIG 6009 GOOD 6000 6000 GROUP.'VENT1 PRO."EDURE: EPIP 1-5 PLANT STAPJS NQV 17!993}3'34 R.E.Glt.".}A SIMULATOR Toto RiLtP ASSIGNMENT

SUMMARY

PAGE 11 2 3 5 6 7 8 10 1}f3 14 t5 POINT ID F0619 LRNST NS033 N033 MT033 MT250 ttDT2 R01 R02 R05 R09 R34 R35 R}OA R}1 16 R!2!7 R}0B 18 Rf3 19 20 23 24 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 43 R}4 Rle R}9 R29 R30 R!5 R}2A5 R!2Ab R12A7 R}2A9 P.}4A5 R}4A7 R}4A9'!5A5 R}5A7 R15A9 R3!R32 CVH TCV03 TCV07 TCV08 TCV}0 TCV}7 DESCRIPT IOt>>COt>>.GCNT COQ'NG LOOP TOTAL FLW R>JELIt>>G NATtER STORAGE TAC LVL 33 FOOT LEVEL}tits SPED 33 FOOT LEVB HIND DIKCTIOt>>i 33 FQQT LEVEL TEMPtERATtJRE 250 FQQT LE4~TEMPERATURE 250 TO 33 FQQT LEVFL DELTA TEMP AREA}-COttTRO: ROOM>>AREA 2-CONTAINt'i NT AREA 5-SPEt>>T FUEL PIT AR""4 9-LETDQ}t!>> LINE MQti'ITOR AREA 34-AUX BtLDG CV SPRAY PUYP AREA 35"PASS SAMPLE PANEL CONTiAItltEii IODIt>>E%!>>ITOR R}OA CQi%'Aih~iB>>T AIP.PART ICV ATE COttTAINMEtti GAS MONITOR PLANT VENT IODINE tiONITOR R}09 AtJX BL96 EXHAUtST Afl?PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIKIID HASTE DISPOSA'NITOR STF>>M GENERATOR Fi KM DRAIN AR="A 29-CONTAIttMit}T HIS RAiNGE K.A 30-COttTAIttMEt>>T HIGtl RANGE COND NSER AIR EJECTOR EXHAUST CV VEttT CHAt>>MO~RANC-': GAS CV VEltT CHAt'"AREA GAi.~A CY VENT CttA'>>7-MID Rt'NGE GAS CV VENT CHAt>>9+IGH RANGE GAS PLk>>T VENT Ctf-"ttt 5-LOW RANGE GAS PLY@>>Vaa'HAtl 7-MID RANGE GAS PLA'>>ti VENT CHAN 9-HIGH MGE GAS AIR"" tECTQR CPA~>>>>5-LON RANGE GAS AIR Ei"=CTOR CHAN 7-t'>>ID RAt>>iGE CAS AIR EJECTOR CHk'>>9-HI RAttGE GAS AK>>3.'TEAMi LINE A (P'It>>~}ORFA 32 STEAMi Litt"" 9<SPIN5)V HYDRAE!<K4CEHTRATION CV BASEMEt!T LEVE-'FT TEMP!t3 CV It>>TERMEDIATE LYL oFT TEMP tt7 CV It}TERMEDIATE LVL 6FT TEMP tte CV ItiTERMEDIATE LVL 6FT TEMP Ng CV IttT~RM"DIAt"'L 6 T TEM~tt}0 CV OPERATIt!6 L-"Y" 6FT TEMP<<}7 IIL 6493.20.8 3.0 41.43.1 38.8-4.3 9.}72~3,05492405 6.2733bi00 2.93427+0} 1.00000+00 }.09648+00 1.00432+07 9.78647~06 1.04864+07 }.02772+06 2.4}963~02 5.599}7+0} 1.01012+03 }.98952403 2.99398~02 2.99398+02 }.39035+03 4.205}}-05 2.00000~00 4,205f}-05 9.99987-04 2.3099}-06 =".20996-03 2.20996-03 6.22985-06 1.80975-05 1.52999-03 3.61977-03 3.61997-03 6009 NRN G009 6009 GOOD 6009 6009 6009 HAttt.6009 GOOD 6009 GQ09 HEt!6 Htu HENS HAttt 6009 6009 GOOD 6009 HALI!HALM 6009 GOOD GOOD 6009 6009 GOOD 6009 6009 GOOD 6009 GOOD 6009 GOOD.0 6009 94.6 6009 107.0 GQQD 106.7'4009 107.0 6009 106.7 6009 119.0 GOOD GROUP: EVENT2;RQCEDURE'P'IP 1-5 PLLT STATUS E.U.MPH DEG, DEGF DEGF DEGF t8/HR 18/HR t8/HR MR/HR t8/HR t8/HR CPM CPM CPM CPM M CPM CPM VN R/HR R/HR CPM XI/CC MR/}8 KI/CC XI/CC XI/CC XI/CC XI/CC XI/CC KI/CC XI/CC t8/HR MR/HR/DEGF DEGF IFEF DEGF DEGF DEGF Time:~134 Message: 68 GINNA STATION 199 EVALUATED EXERCl E MESSAGE FORM~f:R C<<iii Simulated Plant Conditions: See Attached Sheets~Massa e;"<<"THIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes: 1)Accident evaluation and response continues. Actions Ex ected: 1)RecoveryiRe-entry and declassification discussions should commence per the guidance provided in EPIP 3-4,"Emergency Declassification and Recovery". Discussions should include but not be limited to the following: A)Preliminary discussions between the EOF and the TSC on the following: 'hort Term plant concerns such as: 1.Cool down of the plant 2.Repair and return to service of 480 volt Bus 14 transformer. 3.Repair and return to service of the"B" RHR pump.4.Repair and return to service of the"B" Sl pump.5.Repair and return to service of the"C" Sl pump.6.Repair and return to service of the Bus 14-16 tie breaker. 'ntermediate term plant concerns such as: 1.Core damage assessment. 2.Clean-up of Auxiliary Building.3.Clean-up of water in containment. 4.Long-term core cooling.5.Radiological release calculations and evaluation. B).Preliminary designation of the recovery organization. C).State and counties may also conduct parallel recovery/re-entry discussions. 2)Recovery/Re-entry interface between the EOF/TSC and offsite agencies should be demonstrated as time allows. 1993 EVALUATED EXERCISE PXDoe: IB~<MAZOR PARAMET Reactor Shutdown ES NO N-31 CPS N-32 CPS N-35~WAMPS N-36 AMPS Avg.Nuclear power Ql RCS Pressure~PSXG PRZR Level C)A RCP RUNNXNG TOPPED B RCP RUNNING STOPPED 1A S/G Level 1B S/G Level~SS 1A S/G Pressure 0 PSIG 1B S/G Pressure XX PSXG Turbine/Generator ONLINE/FFLIN 4 KV Buses GIZ/DEENERGIZED 480V Buses ZE/DEENERGIZED DC Batteries A79O VOLTS B~3D VOLTS Cnmt Pressure Q~~PSIG Cnmt Sump A Level~r~FEET Cnmt Sump B Level gt INCHES" Loop Hot Leg I 0F A Loop Cold Leg~Zi O oF B Loop Hot Leg NQ=2'F B Loop Cold Leg~(~'F RVLIS~~DO 4*CET~DXSoF, S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow C'PM DIESEL GENERATORS A.RUNNIN UNLOADED STBY OOS B.RUNNING UNLO DED TB OOS TSC RUNNING D OOS Security RUNN UNLOADED TB OOS ENGINEERED S DS Aux.Peedwater Pum s 1A.INSERV TB OOS 1B.INSERV TB OOS Turb.Driven INSERV B OOS CST Level~~~FEET ENGINEERED SAPEGUARDS Hi h Head S.I.Pum s FX-924~GPM FI-925~>~GPM 1A.ER STBY OOS 1B.INSERV STBY 0 1C.INS RV STBY 00 BAST Level=/O Low Head 8.I.Pum s FX-626 OO GPM 1A.SER STBY OOS RECIRC 1B.NSERV STBY 0 RECIRC RWST Level=Containment 8 ra Pum s FX-931AGPM FX-931B&GPM 1A.NSE V 00 1B.INSERV B OOS NaOH Tank Level=~4'ontainment Recirc Fans 1A.SER STBY OOS 1B NSER STBY OOS 1C.NSERV S BY OOS 1D.NSERV STBY OOS Post Aces ent Dampers PE CLOSED Service Water Pum s 1A.NSER STBY OOS 1B.NSER STBY OOS 1C.ER STBY OOS 1'ER STBY OOS A&B Header Pressure PSIG Com onent Coolin Water Pum s 1A.NSERV OOS 1B.E STBY OOS Surge Tank Level=~O Standb Aux.Feedwater Pum s 1C.NSE V 00 1D.INSE V S OOS*CET=Average of Selected Core Exit Thermocouples t(OV 17i 1993 13:4'.i..GINNA Sit)ULATGR PAGE 1 TREND GROUP ASSIGNt(it<'T S<JN(ARY GR'<<JP'VE(P; PRQ(;ED<!-'P!P]-5 PLANT 2 3 4 5 6 7 8 9 10 11!>>z~4 13 14 16!7 18 19 20 21 23 24 26 27 28')9 30 31 32 33 34 35 36 37 38 39 40 42 43 44 45 46 47 48 49 POINT ID AT%RXT N31 tG2 N35 N36 NP PRCS LPM FRCLA FRC'RXT!6 RXT17 TSUBTC LSGA LSGB PSGA PSGB GENEKR!GEt(BKR2 BUS11A BUS!18 BUS!2A BUS!28 811A12A 8!18128 PCV LSU:"lPA l.0942E L0943E L09429 L09439 L0942C L0943C L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TAVGAWIDi TAVGBWID LRV TCCORE FAUXFWA FAUXFMD BKR081 BKR082 V3505 V3504 DEKRIPTIGtl At(TICIPATED TRAllSIEt<< W/0 SCRAl(REA-TOR TRIP BRFAKER STATUS SOKE RAt(Gic 0="TECTGR N-31 SOURCE RAti<GE DcTECTOR K-32 It(TERt(EDIATE RAt(K Dc~TOR N-35 It(TER<"iciDIATE RANK DETc"TOR N"36 AVcRAGE NUCLEAR POWiR l?cA"=TOR COOLA!(T SYSTB1 AVG PRESS PRESURIIER AVERAGE LEVEL REA".TGR COOLANT LOOP A AVG FLOW REACTOR CGGLNT LOOP 8 AVG FLCW RCPA BREAKER CAiJ:.E RX TRIP RCPB BREAKER CAU:.i RX TRIP It<'CORc iTC SUB"OQLcD t(felt(STtr CEN A t(ARROW RAhGE AVG LEVE STN GEN 8 NAMOW RANci AVG LEE.Siti GB)A AVcRAGE PRESS<JRE Tti Cit(8 A%RAG: PRESSURE GitKRATGR Ot('t(i BREAKER!61372 Git.-"RATOR GN'NE BREAKER 9K137 BL'6 11A SL'PPLY BREAKER BUS!'8 SUPPLY 8<<cAKER tiOT TEPJ(It(AT% 0)'PCS (7/19/91)t(OT TERt(lt!ATED Qti PFCS (7/'.9/91) BUS 1!A TO 12A T!i BREAKER 8<J."!!8 TG 128 Tii BREAKER CONT<AIN.":ENT AVE!?AGE FRFSSURc CGN AINt(ct<T SU<"<c'AViRA6c LEVcL SU~<-8 LEViL 8 ItiCHES (TRAIN A)SL<<~8 l cVEL 8 INCHES (TRAIN 8)SUtP 8 LE%78 It(C<<CS (TRAIN A)SL<~t'LiVEL 78 INCHES (TRAIN 8)SUiP 8 LEVEL 113 iti~HcS(TRAIN A)SU$8 LEVEL 113 IttCt S(TRAIt(8)SU~8 LEVFL 180 INCh"S(TRAIN A)5<JAP 8 LEVcL 180 it)DES(TRAIt(8)S<Ji'P 8 LEVEL 214 It(CHES(TRAIN A)=Ut 8 LE<rcL~14 IN'HicS(TRAIN 8)RCLA HQT LEG TENFERATU+= RCLB hOT LEG TEtlPERATCmc RC<A COLD LEG TEt!PERATLRE RCLB COLD LEG TctPERATLRE BC<LA TAVG (Ttr3T/TCO< 9 HILii RtK)RCL".TAVG (THQT/!CO:9 WIDE RNG)REACTOR VESSc: AVERAGE'VEL E'It(CO""=TC AVERAG>>Tit(P S/6 A:OTA" AUX FEEL~<AT='R FLGI(S/6 8 TOTA'UX Fc>>DWATER FLOW."iTR AJXILIARY FEEDWATER PUt!P A tiTR AUXILIARY FEEDWATER PU)lP 8 AUX Fh PUtF 6<cd(SUPPLY VALVi A A!J).=W PUii>STEA." SUPPLY VALVE 8 OFF CLOSED CLO"9 E (, f>>/r VA'i QUAL ATWS ALR))RX TRIPPED ALR)<1.2808&02 6009 1.33045+02 GQQD 1.02801-11 6009 1,02330-11 GOOD.00 GOOD 3.LENG ,0 LALt(75.3 INH>>43.1 INHD TRIPPED ALRt(TRIPPED A<<(-785.6 LAL>>65.6 H)<$(84.3 H(ui 0.LALN 0.LALt(TRIPPED AL(I TRIPPED ALNi TRIPPED ALRtt TRIPPED ALRt', tiOT TRIP DEL NO!TRIP DEL t>OT TRIP ALR)(hO!TRIP ALRl', 3.17 HWRN 31.2 HENG H!GHEP, INHD HIGHER It(HD HIGHER INHD HIGHER INHD HI6HEF.ALRt(HIG)<=P,'LRt(LOWER 6009 LOWER 6009 LO)(if?6009 LOITER 6009 210.4 6009 210.7%009 215.0 6009 204.5 6009 212.7 GXD 207.6 GQQD 39.0 LALt(802.3 HAL>>0.G009 0.GOOD GQOLi 6009 6009 6009 E, U.CPS CPS Al(P At(P PSIG//7, 9-"GF 0//PSI6 PSIG PSIG FKT DEGF DEGF DEGF DEGF DECF DcGF DEGc GPN GPt( ttOV 17>1993 13:4 E.6ltctA SlttLtLATOP. TREt~i" GRGU~ASSIGNidiT SU"ttAR)GROUP VEtaT 1 PROC DUR": EP I P 1 5 PLANT STATUS POIi"tl ID DESCRIPTIOi"'g.LE OVAL E.U.53 FSIA 54 FSIB 55 P2fa0 55 P2161 57 BKf$41 58 BKR042 59 BKR043 60 BKR044 SA."cT'i IN:ECTION LOOF A SA.>>Y Itt'ECTIGtt LGGP B SERVICE WAMe, PUtZS A k SERVICE WATER PUttPS C<;SERVICE WAMc PUlP A SERVICE ttATER PUK B<"RVIC" WATER K<>~" SERVIC": WATER PUttP D AVG FLOW AVG FLOW B lZABER D HEADER 0 1 I OV Gt'l Ott 0.GOOD 232.600 D 87.6009 86.6000 6000 GOOD GOOD GOOD GPtt PN PSIG PSI6 tiGV 17>1993>i~mo Gite Sit!BLAT/8 PAGE 1 PG>>y I Py TREND>690.'~ASSIGNHihT StJt>>ARY~RG"="'>".E'PIP 1"5>"'9 STATUS POINT!0 DES"RIP'ON VA'>('UAL E.U.1 r 5 6 7 8 9!0 11~r2 13 15>7 F06!9 LfNST VS033 t>t9033 MT033 t>T250 NT2 RO!RO" R05 R09 R34 R35 R10A R!1 R!2 R!08 1'?R!4 R!S ng C>>'>nc'6 28'P9 30 3!tl~33 ZJ 40 41 P~W R30 R!5 R12A6 12A?R!2A9 P,!4A5 F;14A7 R!4A9 p$5>>c R!5A7 R!SA9 R3!+30>CVH:CV03 TV/07 TCVOB TCVO9 TCV'10;CV!7.'8=R!3 C05'Ot!Et!T CQO>IN" LGQ?TOTAL FLll RH'ELING WATcR STORAGE TANX LVL 33 FGQT LEVEL Hit!D c~EB 33 FOOT LEVE.*W!tiB DIRECTION 33 FOOT LE'F~>TEtL.ERATURE 250 FOOT LEVE: TEt!PFRAT>JRE 250 TG 33 FQGT LEV='=TA TE!lP AR="" I-CONTRO: RH;">ARE-"-CONTAIIBll A?Z.'"6?Et!T FL~>PIT A"'-LETDOWN) L't~t"Gt>ITGR A>>".4 34-AUX DLBG CV SPRAv PLl>?AR:.~Z-PASS~At!?~P@cL CP)RAINY>=ttT IODINE tlONITGR R10A CGt!TAII'l>~elhi AIP, PART ICV ATE CQtA!eENT C."8 r>QNITOR PLyl?VEttT IODINE tl0!tITQR R!09 A>JX 9>96 EXf'.>>""ST AIR PARTIC!F ATE AOX 8'G EXHAOST GAS tlGNITQR LIQJIID l>ASTE BISPOS>".'r3ttITOR ST":i>;6""NERATOR 9ABER BRAIN AREA 29WATAltP ti HIP RAl>-""" AREA 30-CGNTA!t4lEt~i HIGH RANGE CGtP=:USER AIP.EZCTC>R EXHAUST CV VitiT Cl'>A!!5~Gil RAt>>or.GAS>.V v"N CHAti"-A>,""A 6.-"."c">A CV VBiŽCHAN>j-tl>B RAtÃ6AS CV V-"N: CNN"-H'GH RA%.""GAS P'." V"NT CHAtl S-LG'A RAtlGE GA..LAiT VEN>T M!?->>IB RANGE GAS P A'>VER CHAt'H.'GH R4Jtii GAS AIR E3ECTGR CHAN='RANGE GAS AIR E:ECTCR CHAt'->>IB RANGE GAS AIR EZCTOR CH>>W 9-H!PARSE GAS-",.-'" 31 STD">'P..l..Itt~)"=;:~"".STE@'i LIRE P.(-.Itt6)V-~~%6 P C"""'>"'>>"'.9 >t!I-"RttiBIAT= '.-" 6.I TEl">" ti?CV'N>TER~!ED!ATE LVL 6F: TEt'>P N""'"'T"<""DIAT- ><" FT TB'=4~CV Iti'TERt>EBIA:E LV>.6FT TET ll!0 CV G-.ERATli~i.-.

=V'?T EH?~17 6009 LMRR 6009 6QGD GOOD GOOD 6009 6009 HALtl GOOD 6009 6009 6009 HENS HALtl HEt/6 HAM 6009 6009 GOOD GGQD HALH HAUf K09 6009 6009 6009 6009 GOOD K09 6009 GOOD 6009 6009 G009~0 6009 8S.3 KGD 100.9 6009 100 9'QOGD 100.9 C009 100.9 KOD 116.4 6009 6493.19.7 3.0 41.'3,1 38.8-4.3 9.225?2-02 3.05492+05 5.72137+00 2.93427+01 1.01742+00 1.09648>00 1.00432+07 9.78647+06 1.04864+07 1.02772+06 2.4I963+02 5.59917+01 1.01012+03 2.00678%3 2.99398+02 2.99398+02

!.46428~03 4.20511-05 2.00000400 >>.205!1-05 9.9998?M 2.30991-06 2.20996-03 .20996-03<.22985-06 i.809M105 1'2999-03 1997-03 3.61997-03 GPH/ttPH BEG.BFGF BEGF DEGF t8/HR tS/HR t-/HR HR/HR tS/ta%/HR PN CPtl CPtt CPtl CPtl CPtt CPtl CPtl R/HR R/HR CP>'l XI/CC N/HR XI/CC XI/CC XI/CC XI/CC Xl/CC XI/CC XI/CC XI/CC tg/HR t8/HR BEGF DEGF DEGF D"-6F BEGF BEGF Time: 1415 Message:~6 GINNA STATION 1993 EVALUATED EXERCISE MES AGE FORIVI 8 I C I R Simulated Plant Conditions: See Attached Sheets~essacee:<<"~THIS IS AN EXERCISE~">>FOR CONTROLLER USE ONLY Controller Notes: 1)Accident evaluation and response continues. Actions Ex ected: 1)Recovery/Re-entry and declassification discussions should commence per the guidance provided in EPIP 3-4,"Emergency Declassification and Recovery". Discussions should include but not be limited to the following: A)Preliminary discussions between the EOF and the TSC on the following: 'hort Term plant concerns such as: 1.Cool down of the plant 2.Repair and return to service of 480 volt Bus 14 transformer. 3.Repair and return to service of the"B" RHR pump.4.Repair and return to service of the"B" Sl pump.5.Repair and return to service of the"C" Sl pump.6.Repair and return to service of the Bus 14-16 tie breaker. 'ntermediate term plant concerns such as: 1.Core damage assessment. 2.Clean-up of Auxiliary Building.3.Clean-up of water in containment. 4.Long-term core cooling.5.Radiological release calculations and evaluation. B)~Preliminary designation of the recovery organization. C).State and counties may also conduct parallel recovery/re-entry discussions. 2)Recovery/Re-entry interface between the EOF/TSC and offsite agencies should be demonstrated as time allows. 1993 EVALUATED EXERCISE Time:~/MAJOR PARAMET Reactor Shutdown E NO N-31 CPS N-32 CPS N-35~)AMP S N-36 AMPS Avg.Nuclear Power 42 RCS Pressure PSIG PRZR Level 0 A RCP RUNNING/OPP B RCP RUNNING TOPP 1A S/G Level 1B.S/G Level 1A S/G Pressure PSIG 1B S/G Pressure 0 PSIG Turbine/Generator ONLINE FFLIN 4 KV Buses GIZE/DEE RGIZED 480V Buses ERGIZE/DEENERGIZED DC Batteries A~SO VOLTS B l3OVOLTS Cnmt Pressure~Cr PSIG Cnmt Sump A Level~R,~FEET Cnmt Sump B Level D.INCHES" Loop Hot Leg OF A Loop Cold Leg~/~.'F B Loop Hot Leg~)~0F B Loop Cold Leg F RVLIS Sk=%*CET~/S2A'F S/G A Total Aux FW FlowGPM 9/G B Total Aux FW Flow~GPM DIESEL GENERATORS A.RUNNIN UNLOADED STBY OOS B.RUNNING UNLOADED OOS TSC RUNNING ED TB OOS Security RUNN UNLOADED T OOS ENGINEERED SAP DS Aux.Feedwater Pum s 1A.INSERV 8 OOS 1B.INSERV TB OOS Turb.Driven INSERV T OOS CST Level~)~FEET ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 42 GPM FI-929 GPM 1A.NSER STBY OOS 1B.INSERV STBY 00 1C.INSERV STBY OOS BAST Level=~0 Low Head S..Pum s FI-626'PM 1A.INSERV TB OOS ECIRC 1B.INSE V B OOS RECIRC RWST Level~~9~%Containment S ra Pum s Fl-933A~GPM FI-93 1B~~GPM 1A.NSERV T OOS 1B.NSERV TB OOS NaOH Tank Level=~%Containment Recirc Pans 1A.NSER STBY OOS 1B.SER STBY OOS 1C.NSERV STB OOS 1D.NSER STBY OOS Post Accident Dampers OPE CLOSED Service Water Pum s 1A.R S B OOS 1B.STB OOS 1C>>STBY OOS 1D.SER STBY OOS A&B Header Pressure PSIG Com onent Coolin Water Pum s 1A.INSERV TB OOS 1B.NSER STB OOS Surge Tank Level=Standh Aux.Peedwater Pum s 1C.INSE V B 00 1D.NSERV TB OOS*CET=Average of Selected Core Exit Thermocouples NOV 17~1993 14: 15 R.E.GIM(A Sit(ULATOR TREND GROUP ASSIS)ST SUtft(ARY PAGE 1 GRmlP: EVENT1 PfmCEDURE: EPIP I<PLANT STATUS1 2 3 5 6 7 8 9 10 11 12 13 14 15 16 17)8 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 POINT ID ATMS RXT N31 N32 N35 N36 PRCS LPlR FRCLA FRCLB RXT16 RXT17 TSUBTC LS6A LSGB PSGA PSGB GENBKR1 GENBXR2 BUS 11A BUS118 BUS12A BUS 128 Bi1A12A 8118128 LSNPA L0942E L0943E L09429 l.0943D L0942C L0943C L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TAWQID TAV6BMID LRV TCCORE FAUXFMA FAUXFMB S(R081 S(R082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT M/0 SCRAt(REACTOR TRIP BREAXER STATUS SSRCE RAN6E DETECTOR N-31 SSSCE RANGE DETECTOR N-32 INTER)(H)IATE RANGE DETECTOR N-35 INTERtKDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POMER REACTOR COOLANT SYSTEtl AVG PRESS PRESSURILER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOM REACTOR COOLANT LOOP 8 AVG FLOM RCPA BS(ER CAUSE Rr TRiP RCPB BRENER CAUSE RX TRIP INCORE TC SUBCm)LED t(ARGIN STN 6EN A NARROM RANGE AVG LEVEL ST)(GEN 8 NARROM RANGE AVG LEVEL STN 6EN A AVERAGE PRESSURE STN GEN 8 AVERA6E PRESSURE 6EKRATOR ON LINE BREA)(ER 161372 GEGQTOR ON LINE BREAXER 9X1372 BUS 11A SUPPLY BRENER BUS 118 SUPPLY BREAXER NOT TERtfit(ATED Otf PPCS (7/19/91)NOT TERHINATED ON PPCS (7/19/91)BUS 11A To 12A TIE BRENER BUS 118 TO 128 TIE BRENER CONTAINttENT AVERAGE PRESSlRE CONTAItft(E)(T SUt(P A AVERAGE LEVEL SU)P 8 LEVEL 8 INCHES (TRAIN A)SU)P 8 LEVEL 8 INCHES (TRAIN 8)SU)P 8 LEVEL 78 INCHES (TRAIN A)SU)P 8 LEVEL 78 MHES (TRAIN 8)SU(P 8 LEVEL i13 INCHES(TRAIN A)SU)P 8 LEVEL 113 INCHES(TRAIN 8)SU)P 8 LEVEL 180 INCHES(TRAIN A)SOP 8 LEVEL 180 INCHES(TRAIN 8)SQP 8 LEVEL 214 INCHES(TRAIN A)SUtP 8 LEVEL 214 INCHES(lRAIN 8)R(XA HOT LEG TEt(PERATURE RCLB HOT LE6 TBiPERATURE RCLA COLD LEG THPHNTNE RCLB COLD LEG TE)(PH(AT(SE RCLA TAVG (THOT/TC(LD MIDE RNG)RCLB TAVG (THOT/TCOLD MIDE RNS)REACTOR VESSEL AVERAGE LEVEL Ei.i INCORE TC AVERAGE TE)P S/6 A TOTAL AUX FEHNATER FLO((.6/6 8 TOTAL AUX FEEINATER FLOM t(TR AUXILIARY FEH)MATER PU)P A NTR AUXILIARY FEEDMATER PU)P 8 AU)(FM PUt(P STEAtf S(PPLY VALVE A AUX FW PU)P STEA)f SUPPLY VALVE 8 ATMS ALRtl RX TRIPPED ALR((3.91741+01 6009 3.63077%1 6009 1.00925-11 Goon 1.00461-11 6009.00 6009 6.LALt(.0 LALN.0 IQS.0 1%9 TRIPPED ALRtf TRIPPED ALRtf 69.6 Goo<69.7 HALN 88.5 HALN 0.LALtf 0.LAL)(TRIPPED ALRtf TRIPPED ALRt(TRIPPED ALRtf TRIPPED ALRtf NOT TRIP DEL NOT TRIP DEL NOT TRIP AU%NOT TRIP ALRt(.64 6009 31.2 HE%HIGHER IQS HIGHER INH))HI6HER INHB HIGHER I%6 HI6HER ALRtf HIGHER ALR)f Lof(ER 6009 Lo))ER 6009 Lo))ER 6009 UNER 6009 141.7 6009 139.8..GOOD 152.6 6D09 124.1 6009 147.2 GOOD 131.9 600D 87.6 LALN 150.1 6(me 0.Goon 0.GOM OFF 6009 OFF 6009 cLosED Goon CLOSED 6009 E.U.CPS CPS AtP NP X PSI6 X X DE6F X X PSIG PSIG NY 17'993 14:15 R.E.GINA SINULATN TREND GROUP ASSIGNNENT RNMY PA6E 2 6ROUP: EVENTi PRXHIRE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE GUN.E.V.53 FSIA 54 FSIB 55 P21<e 5b P2 161 57 NR041 58 NR042 59 NR043 60 NR044 SAFETY INACTION LOOP A AVG FLN SAFETY IN3ECTION LOOP 8 AV6 FLOW SERVICE WATER PNPS A h 8 HEADER SERVICE WATER PlIPS C h D HEADER SERVICE WATER PlIP A SERVICE WATER PNP.8 SERVICE WATER PNP C SERVICE WATER PNP D 0.6009 GPN 361.600D GPN 81.6009 PSIG 86.6009 PSIG 6009 6009 6009 600D NOY 17~1993 14:16 L E.GIMO SINULATOR TREND Gfm'SSIBQKNT SUNNARY GROUPS EVENT2 PROCEDURE: EPIP 1%PLAt(T STATUS POINT ID 1 F0619 2 LSST 3 MS033 4 MD033 5 MT033 6 MI250 7 MDT2 8 R01 R02 10 R05 11 R09 12 R34 13 R35 14 R10A 15 R11 16 R12 17 R10B 18 R13 19'R14 20 R18 21 R19 22 R29 23 R30 24 R15 25 R12A5 26 R12A6 27 R12A7 28 R12A9 R14A5 30 R14A7 31 R14A9 32 R15A5 33 R15A7 34 R15A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 DESCRIPTION COMPONENT COOLING LOOP TOTAL FLM REFUELING MATER STORAGE TANK LVL 33 FOOT LEVEL MIND SPEED 33 FOOT LEVEL MIND DIRECTION 33 FOOT LEVEL TENPERATURE 250 FOOT LEVEL TB(PERATURE 250 TO 33 FOOT LEVEL DELTA TENP AREA IMNTRQ.MN AREA 2~AIN)K)fT AREA 5-SPENT FUEL PIT AREA 9~DOMN LINE NNITOR AREA 34-AU)(fuG CY SPRAY PUNP AREA ZrPASS SANPLE PA)EL CONTAlt(NENT IODIt(E NONITOR R10A CONTAINNENT AIR PARTIC(uTE CONTAINBfT 6AS t)ONITOR PLANT VENT IODINE NONITOR R10B AUX BLDG EXHAUST AIR PARTIC(LATE AUX BLDG EXHAUST 6AS te)ITOR LIQUID MASTE DISPOSAL NONITOR STEAN GENERATOR BLO@M DRAIN AREA 29-CONTAINNENT HIS RANGE AREA 3MONTAINNENT HI%RAN6E CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN MN RANEE GAS CV VENT CHAN b~GANA CV VENT CHN 7+ID RANK GAS CV VENT C)N 9+IGH RA%iE GAS PLANT YENT CHAN MOM RANGE 6AS PLANT VENT CHAN 7+ID RANGE 6AS PLANT VENT CHAN 9+IGH RANGE GAS AIR EJECTOR CHAN MOM RANGE 6AS AIR EJECTOR CHAN 7+ID RANGE GAS AIR EJECTOR CHAN 9+I RANK GAS AREA 31 STEAN LINE A (SPING)AREA 32 STEAN LINE B (SPING)CV HYHROGEN CONCENTRATION CV BASENENT LEYEL&FT TENP$3 CV INTERNEDIATE LVL&FT TB(P ()7 CV INTERNEDIATE LVL&FT TENP f)8 CV INTEftNEDIATE LVL&FT TENP H CV INTERtKDIATE LVL&FT TENP 410 CV OPERATING LEVL 6FT TENP ND E.U.6493.6009 6PN 17.1 LMRtf 3.2 GOOD 5%71.6009 OEG.46.9 6009 OEGF 47.9 6009 XGF 1.0 6009 DEGF 9.22572M%09 N/HR 3.05492+05 HALN.NR/HR 9.495IMI 6009 N/HR 2.73842+01 6009 NR/HR 1.00577+00 6009 NR/HR 1.0964888 6009 NR/HR 9.57744+06 HAU(CPN 1.02182+07 HENS CPtl 1.00867+07 HENS CPtl 1.04562Kb HALN CPN 2.58151+02 6009 CPN 5.59917%1 6009 CPN 1.01888+03 6009 CPN 1.938&SAG 6009 CPN 2.9939&HQ HAUl R/HR 2.993%H02 HALN R/HR 1.420&9%3 6009 CPN 4.20511M 6009 XI/CC 2.000NHOO 6009 NR/HR 4.20511~6009 UCI/CC 9.99987M 6009 XI/CC 2.30991M 6009 XI/CC 9.98974M 6009 UCI/CC 2.20996<3 6009 XI/CC 6.22985-06 6009 XI/CC i.(O9~6009 XI/CC 1.52999M 6009 Xl/CC 3.61997<3 6009 N/HR 3.61997M 6009 NR/HR.0 6009 X 71.1 6009 DEGF 69.4 6009 DE6F&9.4-.6009 DEGF 69.4 6009 DEGF 69.4 6009 DEGF 67.7 6009 DEGF Time: 1430 Message: 70 GINNA STATI N 1993 EVALUATED EXERCISE MESSAGE FORM MMM f.:<<I<<C<<IR Simula ed Plant Conditions: See Attached Sheets~Messe e:<<<<<<THIS IS AN EXERCISE<<FOR CONTROLLER USE ONLY Controller Notes: 1)Accident evaluation and response continues. Actions Ex ected: 1)Recovery/Re-entry and declassification discussions should commence per the guidance provided in EPIP 3-4,"Emergency Declassification and Recovery". Discussions should include but not be limited to the following: A)Preliminary discussions between the EOF and the TSC on the following: 'hort Term plant concerns such as: 1.Cool down of the plant 2.Repair and return to service of 480 volt Bus 14 transformer. 3.Repair and return to service of the"8" RHR pump.4.Repair and return to service of the"8" Sl pump.5.Repair and return to service of the"C" Sl pump.6.Repair and re'turn to service of the Bus 14-16 tie breaker. 'ntermediate term plant concerns such as: 1.Core damage assessment. 2.Clean-up of Auxiliary Building.3.Clean-up of water in containment. 4.Long-term core cooling.5.Radiological release calculations and evaluation. B).Preliminary designation of the recovery organization. C).State and counties may also conduct parallel recovery/re-entry discussions. 2)Recovery/Re-entry interface between the EOF/TSC and offsite agencies should be demonstrated as time allows.3):::: L'ead.'ontrollers";.'should'nsure::;th t'e'.:shi':::":ch n e.'demonstra ion":has..been a'de""u"tel'"'::co'm'e e'd::; 1993 EVALUATED EXERCISE Time: (83a MAJOR PARAMET Reactor Shutdown YE NO N-3'1 CPS N-32 3 CPS N-35 F08 AMP S N-36 AMPS Avg.Nuclear Power RCS Pressure'~PS I G PRZR Level A RCP RUNNING QPP B RCP RUNNING OPPE 1A S/G Level~II 9 1B S/G Level 1A S/G Pressure 0 PSIG 1B S/G Pressure PSIG Turbine/Generator ONLINE/FFLINE 4 KV Buses NERGIZED DEE IZED 480V Buses RG DEENERGIZED DC Batteries A~VOLTS BQQVOLTS Cnmt Pressure.PSIG Cnmt, Sump A Level~e 2-FEET Cnmt Sump B Level INCHES" Loop Hot Leg 2'A Loop Cold Leg OF B Loop Hot Leg OF B Loop Cold Leg d7.ra DF RVLI S Q,*CET OF S/G A Total Aux FW Flow+GPM S/G B Total Aux FW Flow>GPM DIESEL GENERATORS A.RUNNIN UNLOADED STBY OOS B.R ENG UNLOADED TB OOS TSC RUNNING D OOS Security RUNN LOADED STB OOS ENGINEERED SAP DS ENGINEERED SAPEGUARDS Hi h Head s..Pum s FI-924 GPM FI-925 6%GPM 1A.ER STBY OOS 1B.NSE V STBY 0 1C.NSERV STBY OS BAST Level=Low Head S..Pum s FI-626 OO GPM 1A.NSER STBY OOS C RC 1B.S V STBY REC C RWST Level=Containment S ra Pum s FI-93 1A~GPM FI-93 1B~GPM 1A NSERV TB 00 1B.NSERV OOS NaOH Tank Level=~4 Conta nm t Recirc Fa s 1A NS STBY OOS 1B.NSE STB OOS 1C.NSE STBY OOS 1D.NSER STBY OOS Post Accident Dampers P CLOSED Service Water Pum s 1A.SER STBY OOS 1B.NS R S BY OOS 1C.NSER STBY OOS 1D.NSE STBY OOS A&B Header Pressure~~~>PSIG Com onent Coolincr Water Pum s 1A.IN V B OOS 1B.SERV S BY OOS Surge Tank Level=~Aux.Feedwater Pum s 1A.NSERV T OOS 1B.INSERV TB OOS Turb.Driven NSERV CST Level~i.~FEET OOS Standb Aux.Peedwate 1C.S V OO 1D.INSERV S B OOS*CET=Average oi'elected Core Exit Thermocouples HOV 17i 1993 14'29 R.E.GINA SINULATGR TRE)m 6ROUP ASSIS)ST SUNNY GROUP: EVEHTf PROCEDURE: EPIP f<PLANT STARS1 2 3 5 6 7 8 10 11 12 13 14 15 lb 17 18 19 20 21 22 23 24 25 26 27 28 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 49 50 51 52 POINT 1D Al%RXT H31 N32 H35 H36 NP PRCS LPIR FRCLA FRCLB R)(T16 RG17 TSUBTC LS6A LSGB PSGA PSGB 6ENBKRt GENS)(R2 BUS 11A BUSilB Bt$12A BUS12B B11A12A B11B129 PCV LSQ(PA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVBAWID TAVGBMID TCCQRE FAUX FWA FAUX FWB Bt(ROBI Bt(R082 V3505 V3504 DESCRIPTION AHTICIPATED TRANSIENT W/0 SCRAN REACTOR TRIP BREA)(ER STATUS SO(SCE RA)(BE DETECTOR N-31 SSSCE RANGE DETECTOR N-32 INTERNEDIATE RANGE DETECTOR H-35 INTERNEDIATE RANBE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEN AVG PRESS PRESSURIIER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOW 8',TOR COOLANT LOOP B AVB FLOW RCPA BRENER CAUSE RK TRIP RCPB BRENER CAUSE R)(TRIP INCORE TC SUBCGOLED NARBIN STN GEt(A HARROW RANGE AVG LEVEL STN 6EN B HARROW RANGE AVG LEVEL STN GEN A AVERAGE PRESRRE STN GEN B AVERAGE PRESRRE 6ElGQTGR GN LINE BREAKER 161372 GE)G(ATOR ON LINE BREAKER'51372 BUS iiA SUPPLY BRENER BUS iiB SUPPLY BREA)(ER NQT TERNINATED 0)t PPCS (7/19/91)NOT TERttl)(ATED N PPCS (7/19/91)BUS ilA TG 12A TIE BREA)(ER BUS ifB TO 12B TIE BRFNER CONTAINNEHT AVERAGE PRESSURE CONTAIN)(Et(T SUNP A AVERAGE LEVEL RlP B LEVEL 8 INCHES (TRAIN A)SSP B LEVEL 8 INCHES (TRAIN B)RRP B LEVEL 78 INCHES (TRAIN A)SNP B LEVEL 78 INCHES (TRAIN B)RlP B LEVEL 113 INCHES(TRAIN A)SUtP B LEVEL 113 INCHES(TRAIN B)SIP B LEVEL 180 INCHES(TRAIN A)SW'LEVEL 180 INCHES(TRAIN B)SUNP B LEVEL 214 INCHES(TRAIN A)SOP B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TENPERATURE RCLB HOT LEG TENPERATURE RCLA COLD LE6 TENPE)(AllSE RCLB COLD LEG TE)IPE)(AT(SE RCLA TAVG (THOT/TCGLD WIDE RNG)RCLB TAVG (TNT/TC(LD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 INCGRE TC AVERAGE TENP S/6 A TOTAL AUX FEEDWATER FLS(S/6 B TDTAL AUX FEEDWATER FLO)(Nm AU)(ILIARY FEEDWATER PU)(P A NTR AUXILIARY FEEDWATER PUNP 9 AUK FM PUNP STEAtt SUPPLY VALVE A AUX FW PtNP STEA)t SUPPLY VALVE B ATWS ALRtt RK TRIPPED ALRt(3.9039041 6009 3.95821+01 GOM 1.00925-11 6009 1.00461"11 6009.00 6009 5.LAUI.0 LALN~0 INHS.0 INHS TRIPPED ALRt(TRIPPED ALR)t 82.7 6(m~71.8 HAU(90.7 HAUI 0.LALN 0.LALN TRIPPED ALRt(TRIPPED ALRt(TRIPPED ALRN TRIPPED ALRt(NOT TRIP DEL NOT TRIP DEL NGT TRIP ALRtt NOT TRIP ALRtl.66 GO09 31.2 HENG HIGHER IQS HI6HER INHS HIGHER INHS HIGHER INHS HIGHER ALRtt HIGHER ALRtl LOWER 6009 LS)ER 6009 Lo))ER 6009 L(WER GOOD 132.1 6009 132.1-.6009 137.4 6009 107.6 6009 134.7 6009 119.8 6009 90.4 LALt(138.1 600~0.6009 0.6009 OFF 6009 DFF GQO9 CLOSED 6009 CLOSED 6009 E.U.DEGF X X PSIG PSIB MN 17>1993 14:29 R.E.GINA SINLATOR TREND GROUP ASSIGNENT RNNSY PA6E 2 6ROUP: EVENT1 PRXEDUfK: EPIP I<PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E.U.53 FSIA 54 FSIB 55'P2160 56 P2161 57 IIR041 58 IIR042 59 IWR043 60 BKR044 SAFETY INACTION LOOP A AVS Flti SAFETY INACTION LOOP B AVG FLN SERVICE NTER PNPS A 5 B HEADER SERVICE NTER PUNPS C h D HEADER SERVICE NIER RIP A SERVICE NTER PNP B SERVICE NTER PNP C SERVICE NTER PlIP D 0.GOOD 6N 458.6009 GPN 87.6009 PSIG 86.600D PSIG 600D 6009 GOOD 6009 NOV 17>1993 14:30 R.E.GINA SltmLATGR TREND GRIP ASSIGNNENT SUtlMY GROUP: EVENT2 PROCEDURES EPIP 1-5 PLANT STATUS 1 2 3 5 6 7 8 9 10 li 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 34 36 37 38 40 41 42 43 POINT ID F0619 LR)tST NS033 N$33 NT033 NT250 NDT2 R01 R02 R05 R09 R34 R35 R10A Rii R12 RiOB R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 Ri2A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 DESCRIPTION Co)PGMENT CI.ING LOOP TOTAL FLN REFUELING NTER STORAGE TAN LVl.33 FOOT LEVEL ttIND SPEED 33 FOOT LEVELl)IND DIRECTION 33 FOOT LEVEL TBPERATURE 250 FOOT LEVEL TB)PHQTURE 250 To 33 FOOT LEVEL DELTA TBP AREA i<ONTRGL Root)AREA 2~AIMNBIT AREA~ENT FUEI.PIT AREA 9-LETDON LlNE t)GNITOR AREA 34-AUX BLDG CV SPRAY PU)P AREA 35+ASS SANPLE PAhEL CONTAIN)lENT IODINE tloMITOR R10A CGMTAINENT AIR PARTIMATE CGNTAINt)EMT GAS t)GNITGR PLANT VENT IODINE NNITGR R10B AUI BLDG EXHAUST AIR PARTICULATE AUK BLDG EXHAUST GAS tlONITOR LIGUID WASTE DISPOSAL ti)MITOR STEA)1 GENERATOR BLM)GN DRAIN AREA 2HZNTAINtlENT HIGH RANGE AREA 30-CGMTAINtlglT HI6H RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN~Sl RANK 6AS CV VENT CHAN b~GAttN CV VENT GIN 7+ID RANK GAS CV VENT CNN 9+IGH RAKE GAS PLIT VENT CHAN MN RANGE GAS PLANT VENT CHAN 7+ID RANGE 6AS PLNT VENT CHAN 9+IGH RANGE 6AS AIR EJECTOR CHAM MOM RANGE GAS AIR EJECTOR CHAN 7+ID RANGE GAS AIR EJECTOR CHAN 9+I RANGE 6AS AREA 31 STEA)l LINE A lSPING)AREA 32 STEAtl LINE 8 (SPING)CV HYDROGEN CONCENTRATION CV BASBlENT LEVEL 6FT TBP 13 CV INTERNEDIATE LVL 6FT TBP 47 CV INTERHEDIATE LVL 6FT lBP IG CV INTERHEDIATE LVL 6FT TBP I9 CV INTERHEDIATE LVL 6FT TBP IIO CV OPERATING LEVL 6FT TEtP 117 6009 LII 6009 GOOD 6009 GOOD 6009 6009 HALtl 6009 6009 Goon 6009 HALN HENS HENS HALtl 600D 6009 Goon 6009 HAL)l HALtl GOOD 6009 6009 6009 Goon 6009 6009 6009 GOM Gm Goon 6009 6009 6009 Goon 6009 69.7-.Gm 69.7 6009 69.7 6009 67.7 6009 6493.15.4 2.8 71.47.0 48.1 1.1 9.17~3.12608%5 9.9425'M 2.69153+01 9.~1 1.09648+00 9.91393+06 1.0i74807 1.02182+07 9.8005&5 2.55932+02 5.67216%1 1.01012+03 2.05057M 2.99398+02 2.99398+02 1.41457%3 4.20511M 2.00000H)0 4.20511M 9.99987M 2.30991M 9.98974M 2.20996M 6.2298~1.809~1.52999<3 3.61997M 3.61997<3.0 71.6 69.7 E.U.6Ptl X tPH IKG.DEGF DEGF K6F N/HR t8/HR t8/HR N/HR N/HR t8/HR CPN CPtl CPtl CPtl CPM CPtl CPtl CPM R/HR R/HR CPtl UCI/CC N/HR XI/CC UCI/CC XI/CC XI/CC Xl/CC UCI/CC XI/CC UCI/CC t8/HR N/HR X DEGF DEGF K6F DEGF DEGF DEGF Time:=1500 Message: 71 GINNA STATION 1993 EVALUATED EXERCISE MESSAGE FORM Ei I<<C<1993 14:59 R.E.GINA Sit((LATOR TREND GROUP ASSIBHNENT SUNNARY PA6E 1 GROUP: EVENT1 PROCEDURE: EPIP I<PLANT STATUS POINT ID DESCRIPTIOH E.U.1 2 3 5 6 7 8 10 11 12!3 14 15 16 17 LG 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 ATl6 RXT N31 N32 N35 N36 NP PRCS LPlR FRCLA FRCLB RKT16 RXT17 TSUBTC L%A LSBB PS6A PSGB'EHBKR1 GEHBKR2 BUS11A BUS11B BUS12A E812B Biih12A B11B128 PCV LSQ(PA L0942E L0943E L0942D L0943D L0942C L0943C L09428 L09438 L0942A L0943A T0409A T0410A'0450 T0451 TAVGAMID TAVBB)tlD LRV TCCORE FAUX FIN FAUX F)IB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT W/0 SCRAN REACTOR TRIP BREAKER STATUS SMICE RAH6E BETE(:TOR N-31 SMICE RANGE DETECTOR N-32 IH)ERNEDIATE RANGE DETECTOR N-35 INTERNEDIATE RANBE DETECTOR N-36 AVERAGE NUCLEAR POMER REACTOR COOLA)(T SYSTEN AVG PRESS PRESSURIIER AVERAGE LEVEL REACTOR COOLANT LOOP A AVB FLOH REACTOR COOLANT LOOP B AVB FLO)t RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED HARBIN ST)t 6EN A NARRO)t RANGE AVG LEVEL STN GEN B HARRmt RANGE AVB LEVEL STN GEN A AVERAGE PRESSURE STt(6EN B AVERAGE PRESSURE BBGtATOR OH LINE BREAKER 161372 BE%RATOR ON l.lHE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SUPPLY BREAKER HOT TERNIHATED Ot(PPCS (7/19/91)NOT TERtlIHATED 0)t PPCS (7/19/91)BUS 11A TO 12A TIE BREA)(ER BUS 11B TO 12B TIE BREA)(ER'OHTAINNEHT AVERAGE Pt(ESSURE CONTINENT SUNP A AVERAGE LEVEL SQP B LEVEL 8 INCHES (TRAIN A)SU)P B LEVEL 8 INCHES (TRAIN B)SUtP B LEVEL 78 INCHES (TRAIN A)SU)P B LEVEL 78 INCHES (TRAIN B)SU)P B LEVEL 113 INCHES(TRAIN A)SU)P B LEVEL 113 INCHES(TRAIN B)SU)P B LEVEL 180 INCHES(mAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SUIP B LEVEL 214 IHCHES(TRAIN A)SUtP B LEVEL 214 INCHES(TRAIN B)RCuI HOT LEG TEMPERATURE RCLB HOT LEG TENPE)tATUfK RCLA COLD LEG TENPERATNE RCLB COLD LEG TE)IPERATuIE RCLA TAVG (TNT/TCOLD HIDE RNB)RCLB TAVB (TNT/TC(U) HIDE RNB)REACTOR VESSEL AVERAGE LEVEL E1.1 IHC(mE TC AVERA6E TEMP S/6 A TOTAL AUK FEEDNTER FUN S/6 B TOTAL AUX FEEDNTER FLN t(TR AUXILIARY FEEDNTER PUNP A t(TR AUXILIARY FEEDHATER PUNP B AUX F)t PUNP STEAN SUPP).Y VALVE A AUX F)t PUtP STEAN S(FPLY VALVE B ATHS ALRN RX TRIPPED ALRN 3.50752101 Gm 3.91741+01 6009 1.00925-11 6009 1.00461-11 6009.00 6009 5.LALN.0 LALN.0 INH8.0 IN{8 TRIPPED ALRN TRIPPED ALRN 75.8 600<76.4 HALN 95.6 HALN 0.LALN 0.LALN TRIPPED ALRN TRIPPED ALRN TRIPPED ALRN TRIPPED ALRN NOT'IHIP DEL NOT TRIP DEL NOT TRIP ALRN NOT TRIP.64 GOOD 31.2 HEMi HIGHER IHH8 HIGHER INH8 HI6HER INH8 HI6HER 1%8 HI6HER ALRN HIGHER ALRN Lm 600D LNER 6009 LNER GOOD L(mER 6009 136.9 6009 136,9-60R 134.4 6009 134.0 GOOD 135.7 GOOD 135.5 6009 90.3 LALN 139,0 600'.6009 0.6009 OFF 6009 OFF 6009 CLOSED 6009 CLOSED GOR CPS CPS At(P AtP X PSIG X X X DEBF'X X PSIB PSIG>z/ NOV 17~1993 14:59 R.E.GINA SIIILATOR TREND 6ROUP ASSIGQKKT SLY PA6E 2 GROUP!EVENT1 PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P2160 56 P2161 57 NR041 58 IIR042 59 NR043 60 IR044 DESCRIPTION SAFETY INJECTION LOOP A AVG FLN SAFETY IN ECTION LOOP B AVG FLN SERVICE NTER PNPS A h B HEADER SERVICE NTER PtIPS C h D fKAOER SERVICE NTER PNP A SERVICE@TER PNP B SERVICE NTER PUNP C SERVICE NTER PNP D 0.0.87.86.600D GPN 600D GPN GOOD PSIG 600D PSIG GOM 600D 600D GOOD VALUE QUAL E.U. NOV O~f993 15:00 R.E.GIWA SINLATOR ,TREND GROUP ASSIMENT RNMY GROUP: EVENT2 PROCEDURE: EPIP 1-5 PLA)fT STATUS POINT ID 1 F0619 2 LRMST 3 MS033 4 MD033 5 MT033 6 MT250 7 MDT2 8 R01 9 R02 10 R05 11 R09 12 R34 13 R35 14 R10A 15 Rli 16 R12 17 R10B 18 R13 19 R14 20 R18 21 R19 22 R29 23 R30 24 Ris 25 R12A5 26 R12A6 27 R12A7 28 R12A9 29.R14A5 30 R14A7 31 R14A9 32 R15A5 33 R15A7 34 R15A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCVO9 42 TCV10'3 TCV17 DESCRIPTION Co)FONENT Cm.ING LOOP TOTAL FLM REFUELIN6 MATER STORAGE TAN LVL 33 FOOT LEVEL MIND SPEED 33 FOOT LEVEL MIND DIRECTION 33 FOOT LEVEL TEtlPERAIURE 250 FOOT LEVEL TBfPERAIURE 250 To 33 FOOT LEVEL DELTA TBF AREA 1M)ff89 Rootl AREA 2~AINNENT AREA 5-SPENT FUEL PIT AREA 9~f)MN LINE tfoNITOR AREA 34-AUr BLDG CV SPRAY PU)F AREA~ASS SA)FLE PQKL CONTAIt)NENT IODINE 5NITOR RiOA CONTAINMENT AIR PARTICKATE CONTAINBfT GAS tlONITOR PLANT VENT IODINE t)ONITOR R10B AUK BLDG EXHAUST AIR PARTIMATE AUI BLI)6 E)(HAUST 6AS tloNITOR LIQJID MASTE DISPOSAL KNITQR STEAtf GENERATOR BLO)fDMf DRAIN AREA 29~AIQKNT HIGH RANGE AREA 3MONTAIN%NT HI%RANGE CONDENSER AIR EJECTOR E)(HAUST CV VENT CHAN~QM RANK GAS CV VENT CHAN~GQtQ CV VENT CHAN 7+ID RANK GAS CV VENT CHAN MfGH RA%K GAS PLANT VENT CHAN MQM RANGE GAS PLANT VENT CHAN 7&ID RAN6E GAS PLANT VENT CHAN 9+IGH RANGE GAS AIR EJECTOR CHAN MQM RANGE GAS AIR EJECTOR CHAN 7+ID RANGE GAS AIR EJECTOR CHAN 9+I RANGE GAS AREA 31 STEAtf LINE A lSPING)AREA 32 STEAN LINE B lSPING)CV HYDROGEN CONCENTRATION CV BASBKNT LEVEL 6FT TBF$3 CV INTERtlEDIATE LVL bFT TBF N7 CV INTERtfEDIATE LVL 6FT TBF f)8 CV INTERtfEDIATE LVL 6FT TBF H CV INTERtlEDIATE LVL 6FT TBF 410 CV OPERATING LEVL 6FT TBF Ci7 6493.GOOD 14.6 LMR)f 3.6 Gom 74.6009 48.5 GOOD 48.6 6009.1 6009 9.44062M 6009 3.07254%5 HALN 9.54~1 6009 2.85101%1 Gm 1.0174240 6009 1.09648+00 Gm 1.02624+07 HENB 9.99992+06 HALN 9.78647+06 HALtl 1.0144&5 HALN 2,61516+02 6009 5.69671+Of 6009 1.09175I03 6009 1.8972&03 6009 2.99398M HALtl 2.99398+02 HAUI 1.40241+03 6009 4.20511M 6009 2.00000+00 6009 4.20511M 6009 9.99987M 6009 2.30991M 600D 9.98974M 6009 2.20996M 6009 6.229~6009 1.80~6009 1~52999M 6009 3.61997-03 6009 3.61997M 6009.0 6009 71.2 6009 69.3 6009 69.3-6009 69.3 859 69.3 6009 67.3 6009 E.U.GPtl X)FH DEG.DE6F DE6F DEGF N/HR NIN N/HR NIN NIHR N/%CPtf CPtf CPN CPtl CPtf CPN CPN CPtl R/HR R/N CPtl XI/CC N/HR UCI/CC UCI/CC UCI/CC UCI/CC XI/CC XI/CC XI/CC UCI/CC N/HR N/HR X DE6F OEGF OE6F DEGF BEGF EEGF NOV 17~1993 15:14 R.E.GIMI(A Sit(ULATOR TRE)m GROUP ASSIGNNENT SUt(t(ARY PA6E 1 GROUP: EVENT1 PROCEDURE! EPIP 1"5 PLANT STATUS 1 2 3 5 6 7 8 9 10 fi 12 13 f4 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 POINT ID ATMS RKT N31 N32 N35 N36 NP PRCS LPIR FRCLA FRCLB RKT16 R)(T17 TSUBTC LSGA LSGB PS6A PSGB GENBKRl GENBKR2 BUSilA BUSliB BUS12A BUS12B B11A12A B11B128 PCV LS(IPA L0942E L0943E L09429 L0943D L0942C L0943C L09429 LO9438 L0942A L0943A T0409A T041OA T0450 TO451 TAVGAMED TAVGBMID LRV TCCORE FAUrFMA FAUrFWB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT M/0 SCRI(REACTOR TRIP BREAKER STATUS SIBCE RAN6E DETECTOR N-31 SIKE RANGE DETECTOR N-32 INTERfKDIATE RANGE KlECTOR N-35 INTERtEDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTE)f AVG PRESS PRESSURIlER AVERAGE LEVEL REACTOR CO%ANT LOOP A AVG FLOW RECTOR COOLANT LOOP B AVG FUN RCPA BREWER CAUSE Rr TRIP RCPB BREAKER CAUSE Rr TRIP INCORE TC SUBCOOLED tIRGIN STt(GEN A NARROW RANGE AVG LEVEL STt(GEN B NARR(N RANGE AVG LEVEL STN 6EN A AVERAGE PRESE)RE STt(6EN B AVERAGE PRESSURE GBERATOR ON LINE BREAKER 161372 696NTOR ON LINE BREAKER 9r1372 BUS ilA SUPPLY BREAKER BUS 1 lB SUPPLY BREAKER NOT TERt(INATED ON PPCS (7/19/91)NOT TERNINATED Oti PPCS (7/19/91)BUS 11A TO 12A TIE BREAKER BUS 11B TO 128 TIE BREAKER CONTAIIENT AVERAGE PRESSURE CONTAIt(HENT SIP A AVERAGE LEVEL SUtP B LEVEL 8 INCHES (TRAIN A)SQP B LEVEL 8 INCHES (TRAIN 8)SUtP B LEVEL 78 INQKS (TRAIN A)SUtf'LEVEL 78 INCHES (TRAIN B)SUtP B LEVEL 113 INCHES(TRAIN A)SOP B LEVEL 113 INCHES(TRAIN B)SUtP B LEVEL 180 INCHES(TRAIN A)SSP B LEVEL 180 INCHES(TRAIN B)SUtP B LEVEL 214 INCHES(TRAIN A)SUtP B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TE)(PERATURE RCLB HOT LEG TE)(PERATURE RCU)COLD LE6 TE)(PERAT(BE RCU)COLD LEG TEtIPERAT(mE RCLA TAVG (THOT/TCOLD WIDE RNG)RCLB TAVG (THOT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 INCORE TC AVERAGE TEt(P S/6 A TOTAL AU)(FEEINATER FUN S/6 B TOTAL AUr FEEDMATER FL(W t(TR AUrILIARY FEHNATER PU)(P A tfTR AUKILIARY FEHNATER PU)(P 8 AUr FM PU5'TEA)(SUPPLY VALVE A AUr FM PI(P STEAt(SUPPLY VALVE B ATMS ALRt(Rr TRIPPED ALR)f 3,471 35tOf 6009 3.7454(HOI 6009 1.00461-11 6009 1.00461"li 6009.00 6009 6.LAU(.0 LAU(.0 INH8.0 INH8 TRIPPED ALR(f TRIPPED ALRN 88.6 600~78.7 HAU(98.0 HAUf 0.LALN 0.LAL)(TRIPPED AUI TRIPPED ALRf(TRIPPED'LRN TRIPPED ALRt(NOT TRIP DEL NOT TRIP DEL NOT TRIP ALRN NOT TRIP ALRN.66 6009 31.2 HENS HI6HER W8 HI6HER W8 HIGHER INH8 HIGHER INH8 HI6HER ALRN HI6HER ALR)f L(NER 6009 LOWER 6009 LOWER 6009 L(NER 6009 125.8 6009 125.8~6009 128.2 6009 127.8 6009 127.0 6009 126.8 6009 90.4 6009 130,4 GX~0.6009 0.6009 OFF.GX9 OFF 6009 CLOSED 6009 CLOSED 6009 E.U.CPS CPS At(P At(P X PSIG X X X DE6F'X X PSIG PSIG DEGF lKGF OEGF OEGF OEGF DE6F X DEGF GPt(GPt( NOV 17>1993 15:14 R.E.GINA SINULATOR TREND GROUP ASSIQNENT SUNQRY PAGE 2 GROUP: EVENTI PROCEDURE: EPIP 1<PLANT STATUS POINT ID DESCRIPTION VALUE 53 FSIA 54 FSIB 55 P21b0 5b P21bi 57 NR041 58 NR042 59 NR043 b0 BKR044 SAFETY INJECTION LOOP A AVG FLOM SAFETY INJECTION L00P B AVG FLOM SERVICE MATER PNPS A fc B HEADER SERVICE MATER PIIPS C h D HEADER SERVICE MATER RIP A SERVICE MATER PINP B SERVICE MATER PNP C SERVICE MATER PNP D 0.0.87.Bb.QUAL E, U.600 D GPN GOOD GPN GOOD PSIG 600D PSIG 600D 600D GOOD 600D NOV 17>1993 15:15 R.E.61%A SINULATOR TREND GROUP ASSIGNNENT SUNNARY 6ROUP: EVENT2 PROCEDURE(EPIP 1"5 PLANT STATUS POINT ID 1 F0619 2 LSST 3 MS033 4 M9033 5 NT033 6 NT250 7 MDT2 8 Roi 9 R02 10 R05 11 R09 12 R34 13 R35 14 RloA 15 Rii 16 R12 17 R109 18 R13 19, R14 20 R18 21 R19 22 R29 23 R30.24 R15 25 R12A5 26 R12A&27 R12A7 28 R12A9 29 R14A5 30 R14A7 31 R14A9 32 R15A5 33 R15A7 34 R15A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 DESCRIPTION CQR)NENT Cm.ING LOOP TOTAL FLM REFUELING NTER STORA6E TAN LVL 33 FOOT LEVEL NIND SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TENPERATURE 250 FOOT LEVEL TENPERATURE 250 TO 33 FDOT LEVEL DELTA TBP AREA i~t(TROL R(mN AREA 2-CONTAINNENT AREA 5-SPENT FUEL PIT AREA 9&.IImN LINE NONITOR AREA 34-AUX DLD6 CV SPRAY PUNP AREA ZrPASS SANPLE PQKL CONTAINENT IODINE)SNITOR RiOA CONTAINNENT AIR PARTIOlATE CONTAI)mB(T 6AS NONITOR PLANT VENT IODINE N(NIT(R R109 AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS N(NITOR LIQUID ((ASTE DISPOSAL NNITOR STEAN 6ENERATOR DLO(m(DRAIN AREA 29~AIN)(ENT HI%RANGE AREA 3(HXNTAINNENT HI%RANGE COt(DENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOj(RANGE BAS CV VENT CHAN 6~GAPA CV VENT CHAN 7+ID RANK 6AS CV VENT CHAN 9+IGH RA%E GAS KA(T VENT CHAN~RANGE GAS PLANT VENT CHAN 7+ID RANGE GAS PLNT VENT CHAN 9+IGH RANGE BAS AIR EJECTOR CHAN MN RAN6E BAS AIR EJECTOR CHAN 7-NID RANGE BAS AIR EJECTOR CHAN H(I RANGE GAS AREA 31 STEAN LINE A (PING)AREA 32 STEAN LINE B (SPINB)CV HYDROGEN CONCENTRATION CV BASB(ENT LEVEL 6FT TB(P ()3 CV INTERNEDIATE LVL&FT TENP 47 CV INTERNEDIATE LVL 6FT TBF ()8 CV INTERNEDIATE LVL&FT TBF 49 CV INTERNEDIATE LVL&FT TENP 410 CV OPERATlNG LEVL&FT TENP 417 6493.BOM 14.6 L((RN 4.3 GOM&8.6009 48.9 6009 48.9 600D.0 GOM 8.912RHQ 6009 3.07254M HALN 9.828~i 6009 2.&&072+01 6009 1.00577400 600D 1~09648%0 6009 9.&&051+06 HALN 9.57744+06 HALN 1.02624+07 HENS 1.01449%6 HALN 2.55932+02 60M 5.38579+01 6001}1.059ZWa 6009 1.91370%3 GOOD 2.99398+02 HALN 2.99398%2 HALN 1.46428+03 600D 4.20511~6009 2.0000QHO 6009 4.20511-05 6009 9.99987-04 6009 2.30991M BOM 9.98974M GOOD 2.20996<3 6009&.22985-06 6009 1.8097~GOOD 1.52999M GOOD 3.&1997M 6009 3.61997M 6009.0 Gm 71.8 6009 69.8 6009 69.8-.6009 69.8'ma 69.8 600D 67.8 GOOD E.U.6Ptl lFH DEG.DE6F DEGF DE6F NR/HR N/HR t8/HR NR/N t8/HR NR/HR CPN CPtl CPN CPtl CPtl CP)l CPN CPN R/HR R/HR CPN UCI/CC ta/HR UCI/CC XI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC%/HR NR/HR KGF XBF IHiF DE6F DEGF NOV 17~1993 15:29 R.E.GINA SII(ULATOR TREND GROUP ASSIGNtKI(T SUt(t(ARY PAGE 1 6ROUP: EVENT1 PROCEDURES EPIP 1-5 PLA)IT STATUS 1 2 3 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 POINT ID ATMS RXT N31 N32 N35 N36 NP PRCS LPlR FRCLA FRCLB RXT16 RXT17 TSUBTC LS6A LSGB PSGA PSGB GENBKRl GEMNR2 BUS11A BUS118 BUS 12A BUS)28 811A12A 8118128 PCV LSUI(PA L0942E L0943E L0942D L0943D L0942C L0943C L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TAVGAWID TAVGBWID LRV TCCORE FAUXFWA FAUXFWB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT W/0 SCRAt)REACTOR TRIP BRENER STATUS SMICE RAN6E DETECTOR N-31 SONCE RANGE DETECTOR N-32 INIERIKDIATE RANGE DETETOR N-35 INTERtKDIATE RANGE DETKTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTB(AV6 PRESS PRESSURI2ER AVERAGE LEVEL REACTOR COOLANT LOOP A AV6 FLOW REACTOR COOLANT LOOP 8 AVG FLOW RCPA BREAKER CAUSE R)(TRIP RCPB BRENER CAUSE R)(TRIP INCORE TC SUBCOOLED t(ARGIN STt(GEN A NARROW RAKE AV6 LEVEL STN GEN 8 NARROW RANGE AVG LPiEL STN GEN A AVERAGE PRESSURE STtl GEN 8 AVERAGE PRESSURE GBERATOR ON LINE BRENER 161372 GE%RATOR ON LINE BRENER 9X1372 BUS 11A SUPPLY BRENER BUS 118 SUPPLY BRENER NOT TERt(INATED Oti PPCS (7/19/91)NOT TERIIINATED ON PPCS (7/19/91)BUS iiA TO 12A TIE BRENER BUS 118 TQ 128 TIE BRENER CONTAIQKNT AVERAGE PRESSURE CONTAI)WENT SUI(P A AVERAGE LEVEL SUIP 8 LEVEL 8 INCHES (TRAIN A)SUtP 8 LEVEL 8 INCHES (TRAIN 8)SOP 8 LEVEL 78 INC)KG (TRAIN A)SUtP 8 LEVEL 78 INQKS (TRAIN 8)SUtP 8 LEVEL 113 INCHES(TRAIN A)SUIP 8 LEVEL 113 INCHES(TRAIN 8)SmP 8 LEVEL 180 INCHES(TRAIN A)SUIP 8 LEVEL 180 INCHES(TRAIN 8)SUtP 8 LEVEL 214 INCHES(TRAIN A)SUNUP 8 LEVEL 214 INCHES(TRAIN 8)RCLA HOT LEG TB(PERATURE RCLB HOT LEG TB(PERATURE RCLA COLD LEG TE)PERATNE RCLB COLD LEG TBIPERATNE RCLA TAVG (THOT/TCOLD WIDE RN6)RCLB TAVG (TNT/TC(LD WIDE RNG)REACTOR VESSEL AVERA6E LEVEL Ei.i INCORE TC AVERAGE TBP 6/6 A tate.AUX FEEDWATER FLO((S/6 8 TOTAL AUX FEEDWATER FLOW NTR AUXILIARY FEEDWATER PU)P A NTR AUXILIARY FEEDWATER PU)P 8 AUX FW P(WP STEAt(SUPPLY VALVE A AUX FW PUt(P SIEA)I SUPPLY VALVE 8 VALUE ATWS ALRt(RX TRIPPED ALRt(3.27340401 6009 3.36511%1 6009 1.00461-11 6009 1~00461-11 6009.00 GOOD 6.LAL)I.0 LAUI.0 INHB.0 INHD TRIPPED ALRt(TRIPPED ALR)(92.6 600~81.0 HALt(100.0 HENS 0.LALII 0.LALt(TRIPPED ALR)I TRIPPED ALR)I TRIPPED ALR)I TRIPPED AUW NOT TRIP DEL NOT TRIP DEL NOT TRIP ALRt(NOT TRIP ALRI(.66 6009 31.2 HENS HIGHER INHD HI6HER Ita)HIGHER INHD HIGHER INHD HI6HER ALRI(HI6HER ALR)(LOWER 600D Gm LOWER 6009 L(WER 6009 124.2 6009 124.2-6009 124.4 6009 124.1 6009 124.3 GOOD 124.2 6009 90e4 GXD 128,2 600e 0.GOM 0.6009 OFF 6009 OFF GOOD CLOSED 6009 CLOSED GOOD E.U.CPS CPS At(P At(P X PSIG X X X DEGF X X PSIG PSI6 NOV 17'993 15:29 0 R.E.GINA SIILATOR TREND 6ROUP ASSIMENT SUNNRY PA6E 2 6ROUP: EVENTi PRXEDURE: EPIP 1-5 PUOT STATUS VALUE QUAL E.U.DESCRIPTION POINT ID SAFETY INJECTION LOOP A AVG FLOM SAFETY INJECTION LOOP B AV6 FLOM SERVICE MATER PtIPS A h B HEADER SERVICE MATER PNPS C h D fEADER SERVICE MATER PNP A SERVICE MATER PNP B SERVICE MATER PNP C SERVICE MATER PNP D 0.6009 GPN 0.6009 GPN 87.6009 PSIG Bb.600D PSIG GOOD 6009 6009 6009 53 FSIA 54 FSIB 55 P21b0 Sb P21b1 57 NR041 58 NR042 59 NR043 b0 NR044 NOV 17~1993 15:30 R.E.GINA SINU)TOR TREND 6ROUP ASSIS)ST SUtmARY GROUP: EVENT2 PROCEDURES EPIP 1-5 PLANT STATUS P01NT ID 1 F0619 2 LR)ST 3 NS033 4 N$33 5 NT033 6 NT250 7 NDT2 8 Roi 9 R02 10 R05 11 R09 12 R34 13 R35 14 R10A 15 R11 16 R12 17 RiOB 18 R13 19 RI4 20 R18 21 R19 22 R29 23 R30 24 R15 25 R12A5 26 R12Ah 27 R12A7 28 R12A9 29 R14A5 30 R14A7 31 R14A9 32 R15A5 33 R15A7 34 R15A9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 DESCRIPTION COtPONENT COOLING LOOP TOTAL FLN REFUELINB NATER STORAGE TAN LVL 33 FOOT LEVEL NIND SPEED 33 FOOT LEVEL ilIND DIRECTION 33 FOOT LEVEL TE)tPERAIURE 250 FOOT LEVEL TE)lPERATURE 250 TD 33 FOOT LEVEL DELTA TE)tP AREA HXNTROL ROOtl AREA 2~AINtK)tT AREA 5-SPENT FUEL PIT AREA 9~0@LINE ttONITOR AREA 34-AUX BLOB CV SPRAY PUtlP AREA ZrPASS SANPLE PA)KL CONTAINtKNT IODINE NNITOR R10A CONTAIN)KNT AIR PARTIMATE CONTAIN)KNT GAS t)ONITOR PLANT VENT IODINE NNITDR R109 AUX BLDG EXHAUST AIR PARTIMATE AUX BLDG EXHAUST BAS mlTOR LIQUID MASTE DISPOSAL NNITOR SIGN GENERATOR SLSiDOO DRAIN AREA 29~AIN)KNT HI6H RANGE AREA 30-COMTAINNENT HI6H RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN MN RAN6E GAS CV VENT CS)N h~GAIN CV VENT CHAN 7+ID RAN6E GAS CV VENT CHAN 9+IGH RA%E BAS PLANT VENT CHAN MON RANGE GAS PLANT VENT CHAN 7+ID RANGE 6AS PLANT VENT CHAN MIBH RANGE GAS AIR EJECTOR CHAN~RANGE GAS AIR EJECTOR CHAN 7+ID RAN6E BAS AIR EJECTOR CHAN 9+I RAN6E 6AS AREA 31 STEA)t LINE A lSPING)AREA 32 STEAtl LINE B lSPING)CV HYDROGEN CONCENTRATION CV BASE)KttT LEVEL 6FT TENP t)3 CV INTERNEDIATE LVL 6FT TBP t)7 CV INTERtlEDIATE LVL hFT TE)tP t)8 CV INTE)MEDIATE LVL 6FT TEttP f9 CV INTERtKDIATE LVL 6FT TE)tP 010 CV OPERATINB LEVL 6FT TEttP CI7 6493.600 D 14.6 LNRtt 5.2 600D 64.6009 49.1 6009 49.0 GOOD-.1 600D 9.22572M 6009 2.90067M HAUl 1.00577+00 6009 2.88402+01 6009 9.8852@01 6009 1.09648+00 6009 9.78647+06 HAUl 9.744ZHOb.HAUl 1.01303%7 HENS 9.63272+05 HAUf 2.6039M2 GOM 5.27077+01 600D 1.0321&t03 6009 2.10438+03 GOOD 2.99398+02 HALN 2,99398+02 HALN 1.39035>03 600D 4.2051H5 GOOD 2,00000k00 GOOD 4.2051M5 600D 9.99987-04 6009 2.30991M 600D 9.98974M 6009 2.20996M 6009 6.2298~GOOD 1.80975-05 6009 1.52999M GOOD 3.61997M 6009 3.61997-03 6009.0 6009 72.1 600D 70.0 6009 7O.O-.6009 70.0 600D 70.0 6009 68.1 GOOD E.U.GPN AH IKB.DE6F IHF DE6F N/HR N/HR N/HR tS/HR N/N N/HR CP)t CPN CPN CPN CPN CPtl CPtl CPtl R/HR R/HR CPtl XI/CC N/HR UCI/CC XI/CC UCI/CC Xl/CC UCI/CC UCI/CC XI/CC UCI/CC tS/HR N/HR X DEGF DEGF IKGF DE6F DE6F XGF

NGV 17~1993 15;44 R.E.GINA SIN(!LATOR TREND MUP ASSIBNNENT SUNDRY GROUP: iMNf PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE I)AL E.U.1 2 3 5 6 7 8 9 10 li 12 f3 14 f5 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 ATWS RXT N31 N32 N35 N36 NP PRCS LPIR FRCLA FRCLB RXT16 Rxjij TSUBTC LSBA LSGB PSBA PSEB BE)IKRl GENBKR2 BUS11A BUS118 BUS 12A BUS128 811A12A 8118128 PCV LSI(PA L0942E L0943E L09429 L0943D L0942C L0943C L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TAVBAWID TAVGBWID LRV TCCGRE FAUXFWA FAUX RI BKR081 BKRO82 V3505 V3504 ANTICIPATED TRANSIENT W/0 SCRAN REACTOR TRIP BREAKER STATUS SO(ICE RANGE DETECTOR N-31 SG(ICE RA%E DETECTOR N-32 INTERNEDIATE RANEE DETECTOR N-35 INTERNEDIATE RANEE DETECTOR N"36 AVERAGE NUCLEAR POWER REW:TGR COOLANT SYSTEN AVB PRESS PRESSURILER AVERAGE LEVEL REACTOR COOlANT LOOP A AVG FLOW REACTOR COOLANT LOOP 8 AVB FLOW RCPA BREAKER CAUSE RX 1RIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED NARBIN STN BE)i A NARROW RA%E AV6 LEVEL STN BEN 8 NARROW RANGE AVB LEVEL STN GEN A AVERAGE PRESSURE STN 6EN 8 AVERAGE PRESSU!(E GEtHIATOR ON LINE BREAKER 161372 EE%RATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 118 SUPPLY BREAKER NGT TERNINATED ON PPCS (7/19/91)NOT TERNINATED Gt(PPCS (7/19/91)BUS 11A TG 12A TIE BREAKER BUS 118 TG 128 TIE BRENER CONTAINNENT AVERAGE PRESSURE CONTAINNENT SUNP A AVERAGE LEVEL SU)P 8 LEVEL 8 INCHES (TRAIN A)SUtP 8 LEVEL 8 INCHES (TRAIN 8)SU)P B LEVEL 78 INCHES (TRAIN A)SU)P 8 LEVEL 78 INCHES (TRAIN 8)SUtP 8 LEVEL if3 INCHES(TRAIN A)SUtP 8 i&EL 113 INCHES(TRAIN 8)SUtP 8 LEVEL 180 INCHES(TRAIN A)SU)P 8 LEVEL 180 INCHES(TRAIN 8)SUtP 8 LEVEL 214 INCHES(TRAIN A)SUtP 8 LEVEL 214 INCHES(TRAIN 8)RCLA HOT LEG TENPERATURE RCLB HOT LEG TEt(PERAlUK RCLA COLD LEB TENPERAT(IE RCLB COLD LE6 TENPERAT(IE RCLA TAVE (THOT/TCOLD WIDE RNE)RCLB TAVE (THOT/TCOLD WIDE RN6)REACTOR VESSEL AVERAGE LEVEL El.l INCGRE TC AVERAGE TENP S/6 A TOTAL AUX FEEDWATER FUN S/6 8 TOTAL AUX FEEDWATER FLOW t(TR AUXILIARY FEEDWATER PUNP A NTR AUXILIARY FEEDWATER PUNP 8 AUX FM PUtP STEAN SUPPLY VALVE A AUX FW PU)F STEAN SUPPLY VALVE 8 ATWS ALRN RX TRIPPED AUI 3.56860101 6009 3.29609%1 6009 1.00461-11 GOM 1.00461-11 6009.00 6009 6.LALN.0 LALN.0 INHS.0 INH8 TRIPPED AUI TRIPPED ALRN 95.0 600>83.5 HALN 100.0 HENS 0.LALN 0.LALN TRIPPED ALRN TRIPPED ALRN TRIPPED ALN TRIPPED AUI NOT TRIP DEL NOT TRIP DEL NOT TRIP ALRN NOT TRIP ALN.66 6009 31.2 HENS HIGHER IN)I H16HER INHB HIGHER INHH HIGHER INHB HIGHER ALRN HI6HER ALI L(IER 6009 LOWER 6009 LG)(ER 6009 LOWER 6009 123.4 6009 123.4-.6009 122.7'-6(ID 122.4 6009 123.1 60(m 122.9 6009 90.5 6009 127.9 600~0.6009 0.6009 OFF, 6009 OFF 6009 CLOSED 6009 CLOSED 6009 CPS CPS ANP QP PSIG X BEEF X PSIG PSIG NOV 17~1993 15:44 R.E.GINA SINLATOR TREND GROUP ASSIGNNENT SUNARY PAGE 2 GROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P2160 56 P2161 57 NR041 58 NR042 59 iNR043 60 NR044 DESCRIPTION SAFETY INACTION LOOP A AVG FLN SAFETY INECTION LOOP B AV6 FLON SERVICE NATER PlNPS A 5 B HEADER SERVICE NATER PINPS C h D HHKR SERVICE NATER PlNP A SERVICE NATER PINP B SERVICE NATER PtNP C SERVICE NATER PINP D 0.0.87.86.QN.E.U.GOOD GPN 600D GPN 600D PSI6 600D PSI6 GOOD 6009 GOOD 600D HOV 17~1993 15:45 R.E.GINA SINLATOR TREND 6ROUP ASSIMENT SUt(t(ARY GROUP: EVENT2 PROCEMKl EPIP 1-5 PLANT STATUSPOINT ID I F0619 2 LRMST 3 MS033 4¹9033 5¹T033 6 MT250 7 MDT2 8 ROI 9 R02 10 R05 11 R09 12 R34 13 R35 14 RIOA 15 Rl1 16 R12 17 RIOB 18 ,R13 1'9 R14 20 R18 21 R19 22 R29 23 R30 24 R15 25 R12AS 26 R12A6 27 R12A7 28 R12A9 R14AS 30 R14A7 31 R14A9 32 R15A5 33 RISA7 34 RISA9 35 R31 36 R32 37 CVH 38 TCV03 39 TCV07 40 TCV08 41 TCV09 42 TCV10 43 TCV17 DESCRIPTION C05%NENT COOLINB LOOP TOTAL FLM REFUELINB MATER STORAGE TANK LVL 33 FOOT LEVEL MIND SPEED 33 FOOT LEVEL MIND DIRECTION 33 FOOT LEVEL TEISATURE 250 FOOT LEVEL TBPERATURE 2SO TO 33 FOOT LEVEL DELTA TEIF AREA I<Ot(TII(X ROOt(AREA 2~AIQKNT AREA 5-SPENT FUEL PIT AREA 9-LETDO¹N LIHE t(ONITOR AREA 34-AUX BLDG CV SPRAY PUNP AREA~ASS SNPLE PQ8.CONTAINNEhT IODINE NNITOR RIOA COHTAINI(ENT AIR PARTICIIATE CONTAIN((ENT BAS NNITOR PLANT VENT IODINE!SNITDR RIOB AUX BLOB EXHAUST AIR PARTICULATE AUX BLDG EXHAUST NS NNITOR LIOUID MASTE DISPOSAL tSNITOR STEAt(GENERATOR BLMSO DRAIN AREA 29~AINI(ENT HIGH RAN6E ARE'A 30<ONTAItST HI%RANGE CONDEHSER AIR EJECTOR E(HAUST CV VENT CHAN MOM RANK GAS CV VENT CHAN h~6ANA CV VENT CHAN 7+ID RANK 6AS CV VENT CSN 9+IBH RA%E BAS PLANT VENT CHAN MOM RANGE NS PLNT VENT CHAN 7+ID RANGE 6AS PLANT VENT CHAN MIGH RANGE NS AIR EJECTOR CHAN MO¹RANGE NS AIR EJECTOR CHAN 7+ID RANGE NS AIR EJECTOR CHAN 9+I RANGE BAS AREA 31 STEAtI LINE A (SPIHB)AREA 32 STEAN LINE 8 (SPINB)CV HYDROGEN CONCENTRATION CV BASEtIENT LB%1 6FT TEt(P<<3 CV INTERI(EDIATE LVL 6FT TEI(P<<7 CV INTERHEDIATE LVL 6FT TEt(P<<8 CV INTHNEDIATE LVL 6FT TBP<<9 CV INTERt(EDIATE LVL 6FT TEMP<<10 CV OPERATIHB LEVL 6FT TEt(P<<17 6493.6009 14.6 LMRN 3.7 GOOD 67.6009 49.5 6009 49.6 6009.1 GOOD 9.22572M 6009 3.14411+05 HALI(1.0232960 BOX 2.75423+01 6009 9.44062<1 6009 1.09648M 6009 1~00432+07 HEHB 1.01741+07 %NB 1.04864M fENB 9.84289+05 HALII 2.55932+02 6009 5.69671+01 6009 1.05925+03 6009 2.06835KK3 6009 2.99398+02 HALt(2.99398%2 HALI(1.46428+03 6009 4.2051 1M 6009 2.000MOO 6009 4.20511M 6009 9.99987M 6009 2.30991M 6009 9.98974M 6009 2.20996M 6009 6.22985-06 6009 1.80975-05 6009 1.52999<3 6009 3.61997M 6009 3.61997M 6009.0 6009 72.4 6009 70.3 6009 70.3.6009 70.3'6009 70.3 6009 68.2 6009 E.U.6PN X le DEG.DE6F IKBF IKGF t8/HR t8/HR t8/HR l8/HR t8/HR t8/HR CPt(CPN CPt(CPN CPtI CPtl CPtl CPt(R/HR R/HR CPN XI/CC I8/HR UCI/CC XI/CC XI/CC Xl/CC Xl/CC UCI/CC UCI/CC UCI/CC t8/HR t8/HR X IK6F DEGF IKGF DEGF IKBF IKGF R E GINNA STATION Intermediate Buifding North-Basement Leve Technician: Date: Time: Inst.Type: Serial er'e:/Power: LLO Note: All readings are in mr/hr unless otherwise noted.rrerelrrraa eaP No.Opmr lQOamg p C'rp inc."riven Su X FIN"A;9 rOO('i rO 0~~~~~~Ip~0 (--N Containment 07:3049:10 All Areas (Clean)Radiation Levels 0.01 mR/hr Smears 250(j pm Airborne Activi iodine=1 E-11 uCi/cc Part.=1E-10 uCl/cc u(Orn0 aux FW-Pumo Qil IOrx w weCAhl ,~00 553r 0 0 0"hrilerq 0@0 Oa VOtO(9riven Aux, r"W PurnpS OO¹=Smear Location Radiation Level.¹c=Contact Reading Technician Remarks:-x-.x-=Rad/Cont.Barrier¹',=Neutron Radiation Level 4 i~I;I+.I~+i'Cont.Area High Cont Area Radiation Area High Rad.Area Locked High Rad. R.E.GINNA STATION Intermediate Buifding North-Basement Level Technician: Date Time: Inst.Type:/Serial¹'a: I Power: Ll 0: Note: All readings are in mr/hr unless otherwise noted.~ra(tart(as aep tr rQ)~r(B/No.a pmr l Oocm2 B B 0 A.ro(nS pneen Aux FW-ump 0 0 poor 36~~~t~t L~A', Ip~0 Oo 0 Containment 09:10-10:30 Radiation Levels A=3m R/hr 8=0.6mR/hr Smears 250dpm t~MII iodine=1 E-11 uCi/cc Part.=1E-10 uCi/cc poor'7 Turbine Aux FW->urrtp Pil it 0o((((Q 0 0 0 0 n((((t r et 0 A ,~gQ B 5 5 3 rS B@0 o S r MOIOr Onven AuxP((r Pumps 00 0 0 Smear Location-x-.x-=Rad/Cont.Barrier Radiation Level¹',=Neutron Radiation Level¹c=Contact Reading Technician Remarks: 'l (,e r'i)(:I+Il~+Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad. R.E.GlNNA STATlON intermediate Building North-Basement Level Technician: Date: Time;Inst.Type:/Serial¹'a:/Power: LLD: Note: All readings are in mr/hr unless otherwise noted.Irrrrartrss eap B g A No.4pmr 1oocm2 0 10:30-1 5:00 0'roinS Lnr,von Aux rR-mo Ooor eo B~~~~~~I Q g)o Containment Radiation Levels A=37m R/hr B=17mR/hr Smears 2504pttl~Aia a ti i iodine=1E-11 uCi/cc Part.=1 E-10 uCi/cc Ooar Tur0tns>ux FW-?ump Qtl Tang.httlqrea 0 O O B ,~OG B i:i r 0'o8 0 tAofor Driven Aug.FW Pumps OO¹=Smear Location-x-.x-=Rad/Cont.Barrier Radiation Level~¹'Neutron Radiation Level¹c=Contact Reading Technician Remarks: f r%l ,i.'I+:f.~"+Cont Area High Cont.Area Radiation Area High Rad.Area Locked High Rad. I%I.ONNA STATlON Technician: Dare: Time: lorn.~re: Mote: AN readl ate in wtlttf 4~140 o&orwiio not IINSI$0gh-Tyy~Jamt$7~100orn j ter Containment 07:3049:10 All Areas (Clean)Radiation Leve)s 0.01mR/hr.Smears 260dpm a~id a~i iodine=1E-11 uCi/cc Part=1E-10 uCi/cc refers 0:Qt a Smsm Looedon.a-x.~nedlConL Sardsr~Sereelon Level~~Nernron Ihreeeon Level'A!~Concecc AaicÃnoWsohnlrdmr nsmenrs:~e Cut.Atia Qe~leon QNff.Area~~geagon Aroi Qi~lnyn use.Area~Leh&'High Rad.Atee

R.E.QINNA STATlON Technician: Date: 'Hme: Inst.Typo: I Seri~I<<'e: I Pevrer.Note: All readinQO are in mr/hr unleaa otgerwlee not~$7 I (A fq l frat atn a B 0 Containment Ne.4Sml100crn2 I 09:40-10:30 Radiation Levels A=3m R/hr B=0.5mR/hr Smears 250dpm~ill h II ti I iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc Ethetlst , FDR Atla C;QN~Smear Locathn-x-x-a Rad/Cont.Barrier!g.~Radlatlen Level~~Meutran Sad!ation Level'Ne~Contact Realng~Teehlllelen Rameftte: Qe Qo~R Cont.Area Ngh Cont.Area Radladon Area Ngh Rad.Area L,ochod High Aad.Area R.e.elNNA ITATlON Technician: Data: lime: lnit.Ty: Ser/el g'e:/Power'.LLD: Note: All FeatHAOO ere ln mr/hr unleaa otherwlle nota!.Fdo.dnttt/100ont2 I r Fe arm A a Bl (A l g Containment 10:30-10:50 Radiation Levels A=37m R/hr B=17mR/hr Smears 250dpm Airborne Activi Iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc B l a Fe arm I B 0 FCR At/I C Q+dmem Looadon.a-a.Rad/Cont.earner~Radladon Lar/al~~lr/atman Ra@aden Larrel 40~Corltaot Rainy.~chnkQan Ramarkae~~Com.Area Qe w Hdtl Cont.Area a gacga50tl Area Q~~Nyn Rad.Area~~Locked High Rad.Arae 8,8.0!NNA ITATlON Ittilg Ious)-Top Lewl Technician: Dace: Time: lnit.Type: I Serial s': I Power.LLD: Nato: All reecllnNN ere in fnrlhr unteee atherwiie nated.(CAN C I Ho.dhrccs100errc1 I I 10:50-12:50 A Containment Radiation Levels A=6R/br B=1R/hr C=500mh/hr 0=37mR/hr Smears 5,000dpm Airborne Activi iodine=3E-9 uCi/cc Part.=9E-9 uCi/cc D Kcleuct FCR ACS C~QN e Smear Location-x-x-e Ihd/Cert.Barrier~Rsrhsdon Level+a Mscnron Radiadon Level e'A e Contaot lteatlnl peahnlcden Rsmarhs:~e Cont.Area Q~~Ngh Conc.Area a gNIation Aree Q~~RhNc Rsd.Area Q~Lashed High Rad.Area 8,5.6WNA STATION Technician: Date: Yama: Inst.Type: Serial a': I Pawan l.LD: Note: All res~are in mr/hr unless otherwise noted.3aet$7 Ne.t!Rrrtl1OOarrt2 !bhse re ate btaa re ats B Containment 12:50-15:00 Radiation Levels A-37m R/hr B=50mR/hr~ears A=3000dpm B=5000dpm me Activi locI~2E-9 ulcc Part~2E-9 uCI/cc B (,x~~ron Atra Qt~Smas Laaattan.a-a.a WCant earrlar..'.W~Ratiatlan Latrel~~Matnran Raatattan Lawl'W~Contaot Raasnl.Pe:ltnlalan Ramartta: Cont.Area Nyh Cont.Area Itsa5on Area Nyh Ral.Area Locetod High Rad..Araa 8, j.QNIA ITATlON Date: ttme: fnet.TV': Sar(el a': I Power: LLD: pote: All reedl~eM in rnrlhr unieae otherwiee noted.3oor a6 Ooor 45 d yrttr 1 OOarn2 I L(OOr Control Point/Sigh wrh Oestt Possttoa Httcteor l Somttte l Room I ttuctettr Somttte Shed Contoittmettt 07:309 l0 All Areas (Clean)Radiation Levels 0.01m R/hr Smeara 250(I pm~ale a ti I iodine=1E-11 uGilcc.Part.=1 E-10 uCi/cc<Pa r;tt~.NJ~Smear Local-x<<x-a IbcUCorn.Iarriw w nadtadon Level~z w rtaotron ttadtadon La(rat ,Ne~Contact Baaing ,7eehnician ltemarhs:~~Can.Area Q~w Nyh Cont.Area~Satiation Area Q w Neh ttad.Area Locit&High Red.Area ll.f.tINNA STATION Tachyon: Cats'rillo! tnat.Ty~: I OerISI a'e Note: All reedll>ate ln Qf/Q Mggygg+++meow-+am'~00r)~6 toe.Setter tOOsnng, ioot (5f Cottttot Poet/Sett-In Oesh Posseoa l4eleor t Satek t toots I t A Continment 09:10-10:30 Radiation Levels A=3m R/hr B=0.5mR/hr 'nrears 2500PITI l~liH A*ti i iodine=1E-11 uCi/cc'art.=1E-10 uCi/cc A tQ e em'ocation-x-x-e Had/Cona Senior g.~Wsihsnon Least+i~Nsntron hsrhsoon Lsvd 4e~Coetect AeaNni tWachnklln Itemarle: 'a Ccet.AN O~m Noh Cont.Ares e ga5gion Area Om Ngh SNL Ares~m 4ggg4 High Red.area R.I.ON%A SYATlOH TecttlllcQfli limo: inane.Type: I OoaaI a': I aoww: Motl,'ll PIOOI~ere ill nlr]ill Mggggg O~~~OOI<d ioo<(o COIItrOI Poet/Sign iII Oem POSSOoo~g Noes I)A ContainmM 10:30-15:00 Radiation Levels A=37m R/hr B=17mR/hr/meara 250dpm irborne Activi iodine=1E-11 uGi/cc', Part.=1E-10 uci/cc+gJ a eggs LOgg+0-I a.a RSdlCNt hAt j w goISoooo~~l w NAIIIIoll OAIlolloo Lily',4e~Contact hoedlnO ,WOehniC{an Itemarha~m CeeL A%a Qo w~OOOI.Ataa~~RQSRSodl ArII Q+w IOgII NNI.Afoa~ed Hlgn Had sew R.B.QINNA STATlON+'IQ Ioutft-Iasesnent Level Technicisn: pete: Time: inst.Type: Seri~I<<'e: r Power: pote;fA)(res4ing ere in mr/hr unless otherwise noted Ooof 3b Nt.4nmf100em1 'o-o{Shoo<---I I f I.a{fndfy an{is i I IA re Hydfagtn 4{Teaamarntr oane{S CI{emrcaI Ofaln Tant i.ontginment 07:3049:10 All Areas (Clean)Radiation Levels 0.01mRlhr smears 250dpm Airborne Activi odine~1E-11 u ilcc.Part.-"1E-10 uCilcc Saent Ftft{TfiI Sirrmmtr Fii{tr-->C--traIItd Aaatss Fons 0 Smear I eeet{all-x x>Ilail/aollt. terr{el~RaHatkm Level~Neutron RaNstkn Level c~Contact Reading Techrldan Rlnsrlts:~Corlt.Area Qo w Nth aoot.Area~Ralathn Ares Q~w Hit{1 gat.Arel~Lociteci High Rsd.Area R.K.QINNA STATIC~Tochnfclan: Inst.Type: Seri~I<<'a: I sower: I I 1: Note: All reidlnge ere In mr/hr unites otherwlae noted.O"Ol ShOO<---I I iaunarg CnsS I I 1:homrcct Qrarn lane I l~~e f A p 4 rrIraroqen Coccmorner oan etc Containment Ne.Ehrttr 100ortt1 09:10-10:30 Radiation Levels A=3m R/hr B=0.5mR/hr /meara 250dpm Irbome Activi odine~1E-11 uQ/cc Part"-1E-10 uci/cc A~sar SOent Fuet>it 5trrmmtr Filttr--)Qw i c-aA4 Aeeoes;Fons 0 ,Qo~Smear Loostlon.x-x.e ltert/Cont. center~I4dlatlon Level~Neutron Radiation Level~Contact Reading T~nidan Remarita:~m Cont.Area Qa n Noh ContAree.e ga¹atlon Area Q~Ntth rtsrt.Ares 0 Looted High Rad Ane h.5.0lNNA STATEN Technician: Inst.Ty pe: serrel a'e: I power: r.Ln: Note: All reedlngO ere fn mr/hr unleae othe~le noted.dyrsM100orn j o ol>rroD I".aundty dna'l)I 1>8 wy410gdn QdCom0rndf owners COhtalhmeht Chdmrdcl OIOln fane o~~e f (A 10:I'-15:I Radiation Levels A=37m R/hr B=17mR/hr/meara 250dpm irbame Activi odine<1E-11 uCi/cc Part~1E-10 uCi/cc A S~t F.df Ot 5irrmmdf Filfyr Qres i--roNN Access Fee Qt w S.maar LOaadsn-X-X.w nadiCOiir. larder~haclelon Level~Neut en hacgalon~~Contact loa4ny 7whnicSen Ranee:~~ConL Argo Q>>w Ngh COIIL ursa~Itsation Aru Q~nsd.Area m~4 High Rid Atw

R.K.QINNA STATION Technician: Inat.Ty pe: Note: All readings're in Dsts!Tllll~: Serial<<'s: r power: LLD: mr/hr unleaa otherwiso noted.O"Ol SIIOO (---Oooc 38 SSSMIOOsnlg I I 1.OIIndnr OnNS I I 8 B IA 18 IIrO copen oeoonISIner Den eIS t:hemrool Qcoln Tonk B Containment 10:30-15:00 DURING PA$$OPERATION Radiation Levels A=3R/hr B=500mR/hr C=50mR/hr Smears All Areas=250dpm ale'A t'R Iodine=1E-9 uCi/cc Part.=5E-9 uCi/cc So+i f.~r t S1IImmer filter--)C-W kCcea'FOIS 0 Qt~Sms,w Locaoon-x-x.~SadlOonI.Sarrlsc~Re~n Lewi~Meueon Radletlon Level~Contacc leedlno TechWten Romaine:~m ConL Atee Oe~ISSS OanI.Area e Iticlatlon Arel Q a IQSS l4S.Area a Looite4 High Rtd.Arw R.E.GINNA STATION ,":trautrr~"Hotehop .Technician: Date: Time: Inst.Type: I Power: LLD: Note: All readlnQI are ln mr/hr unless otherwise noted.tao xaHop M rrnae No.4pm1100cm2 Ooor 41 Ooor 40 Laundry Monitor X X t t I X I I s x 0 P X I Oecon Table X X I P I X Id/'A I I X I I I t B X X X X X I s x 0 i P P A S S 0 0 0 4 0 0 0 0 PASS FLOW 07:30-1 5:00 Radiation Levels A=50mR/hr'=25mr/hr.Smears 250dpm a~Ma~i Iodine=1 E-11 uCi/c Part=1E-10 uCi/cc~R.35 Ch 3R/hr*1*NOTE 111 CALL TSC (506)BEFORE STARTING SANIPLE FLOW ate~e Snk~Smear Location-x-x-a Rad/Cont.Barrier Radlatlon Level.+~Neutron Radiation Level~'c~Contact Reading Technician Remarks:~~Cont.Area l Qi m High Cont.Area~Radiation Area Qim High Rad.Area O~Locked High Rad..Area Technician: Date: Tints: inst.Typo: Serial S'a: I Power: LLD: Note: AII readlnge are ln mr/hr unleee otherwlae noted.4Rttt1100etttg Ooar 4t Ooor 40'a X>>>>X>>Laundry Monitor x x t~I I X I1 t a (P X I Ocean Table'X X>>>>'a'>>>>R I X I X I I'X I X>>X X I-5 X 0 NO PASS FLOW 07:30-1 5:00 All Areas (Clean)Radiation Levels 0.01m R/hi Smears 250dpm Ai&A tt ttt iodine=1 E-11 uCi/cc Part.=1E-10 uCi/cc~t535 0.01 mR/hr***NOTE'"" CALL TSC (506)BEFORE STARTING SAMPLE FLOW>>grocer l.ocadon-x-x->>RadlCont Bards.r>>Radlsdon Level+>>Neutron Radiation Level 4'c~Contact Reading Technician Remarka: Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad..Area R.E.GINNA STAT10N::,~Pf@+4,,, n..~~~~~Hotsho'p;:.:. Technician: Date: Time: Inst.Type: Serial¹'e: I Power: LLD: Note: AII reading are In mr/hr unless otherwise noted.fritaer No.4pntl10acrng Ooor 41 I Ooar 40 Laundry Monitor I I I I I I I I1 I a I'Oecon Table P I I g I Id'A I I I I I I l I I Shop P A S S 0 0 A 0 0 0 Sink~Sink I I X'I'I B 5 I a PASS FLOW 07:30-15:00 Radiation Levels A=50m R/hr B=25mrlhr Smears 250dpm Airborne Activi Iodine=1 E-11 uCi/c Part.=1E-10 uCI/cc~ll-35 di 3R/hr***NOTE***CALL TSC (506)BEFORE STARTING SAMPLE FLOW~Smear Location-x-x-~Rad/Cont.Barrier a Radiation Level g Neutron Radiation Level¹c~Contact Reading Technician Remarks: Qo+Qo Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.'.Area R.E.GINNA STATlON Technician: Date: Time: RWP/SWP¹: inst.Type:/Serial¹'a:/Power: LLD: ote: All readings are in mr/hr unless otherwise noted.Ct(ST~1.P¹P No.dpm/100cm2 DDD-x---x---x I l X I I I X l 07:30-1 5:00 All Areas (Clean)Radiation Levels 0.01mR/hr Smears 250dpm Airborne Activi iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc O¹=Smear Location-x-x-=Rad/Cont.Barrier Radiation Level+=Neutron Radiation Level Contact Reading~~Technician Remarks:+Q++Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area I.I.ONNA STAY<~TechrKclan: DeN: Tllne: fnat.Type: Sar/el e';/power: Nate:+>rieti I~'n Cnr/hr unleaa OtgICWiII nOt<<.No.dhnt/10Oo/n4 I r R-I8 I Oecon~it I I t I Oren'r t I t I Spent Fuel Pit C A!I T I W I A g I I r I HEPA Filttn 07t30-09:10 All Areas Radiation Levels 0.02mR/hr Smears 250dpm Airborne Activi iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc'roetrr.~I SOP (.transfer Cgeg Nder<t/RI SI~RrRO Qo~Srnsa Looatlon.a-a.e Rad/Cont harder~~Ra/Radon Level~~Neutron Radlatlon Level P Ne e Contact laatlnl.Technician lhmaclta: I~a Cont.Atia pe~Nyh ConL Area gatiatlon Acoa P'RRh Rad.Area~Local HIQh R<<Ana R.I.OWSA STATNlti e Technl64n: Date!Tl Ill~: Inst.Type:/Senal 4 s: I powet: Note: Atl rea4m in mr/hr unlasa otherwilo noted.Me.SSRII100ontg I I R-I8 0 C I Oecpn t'it c I W B', A Oren c l I B I c I I I l SPent F'Llel Pit I'f I I I B I f I 09:10-10:30 Radiation Levels A=3 mR/hr B=0.5mR/hr Smears 250dpm Airborne Activi iodine=1E-11 uCi/r, Part.=1E-10 uci/cc"ontte~I SOIS (--frORtf>>r CONS A M IIScr MINI SlOr>>g>>Iree ,Qt~Smsa Loostlon-x-s.a Ran/Cent.Satnar g.~Sedation Level+~Rsunon Ranlanon Level Ne~Coeact leonl.7echnicien Ranatka:~e Cont.Aru 0'~NSh Cont.Ates a NaNadon Area Qi a NSh Ran.A(aa 0~Locke4 High Red.Ane R.E.QINNA STATlaN Technician: Date: lime: fnat.Type: Serial d e'Po r'LD: Note: All readiISa ere in mr/hr unleia otherwise noted.lgn.4 Rmr100omg R-18 OrCrn CJ I Deco'it t I 8 t I t I'I I t B I'5 Spent Fuel Pit C A I't I W A 2 I B Bridge HEPA Filtca 10:30-10:50 Radiation Levels A=37m R/hr B=17mR/hr Smears , 250dpm Ai&A tl IIX iodine=1 E-11 uCi/cc Part.=1E-10 uCi/cc'rostra.onto I SOP l.Trangfgt COnal A Hgtr<ugl Slot Argg Qd~Smear Location-x-x-e Rad/Cont.Barrier L.~Retgadon Level~~Metrtron Radiation Level Ne~Contact Raalno.Tochrtician Remarlta: I m CoAt.Area Qe m Hlgll Cont.Area~Radiation Area Qi a High Rad.Area Q L,ocltad High Rad Area e Tao hniclll: Data: Time: Inat.Typo: Sarr~I e'al/Pewar: Nota: All raadfele are in mr]hr unlaaa otharlIlriaa noted.No.dhrrtr 1 COerrtg I It'-I8 0 I t Oecpn~it t I l I l I prdrn'r r I C A T A C.I 2 Spent F'ueI Pit I 2 I 2 I 2 I I l I HKPA Rlten 10:50-12:50 All Areas Radiation Levels 62R/h Smears 200,000dpm Airborne Activi iodine=4E-1 uCi/cc Part.=3E+0 uCi/cc"~e.~I SOP I lrCIISIRP Q~~<uel Slat090 AtRO Qt~Smam Laesden-a-x.~Rad/Cant.Ssrrter W~Rsrdadan Lmrel's Neutron Radladen Lmrel 4e~Contact SoaNnl.Veehnlrdsn Rsmarla:~~Cont.Ates Qe s Ndh Cent.Ares~a Is¹edon Area 0 Ndh Rad.Area~L~ed Nigh Rad Aces R.f.QINNA STATION Technician: Oate: Time: Inst.Type:/Seri~i a'e: I Power: Note: All reec&%ere in mr/br unless otherwise noted.No.ddrrrr100crng e-I8 Ordrn a e o o I Oecon Pit e I 8 l I x I I S I 1 Spent Fuel Pit C A I T N I A g I x 8 8ndqe A HKPA Filters'l2:50-15:00 Radiation Levels A=37mR/hr B=17mR/hr Smears.000,000dpm i~lid II ti iodine=SE-7 uCi/cc Part=2ER uCi/cc c'rind<<.~I SOP l--B Trongfet Conal aIder p<RI Sin woo Qg a Sme<<i.ooadon-x-x-w Rad/Cone.Rani<<Rardadan garrai~m aiarnron Radladon Larval Ne~Contact ReaNng.TechrNciin Nemarita Qe 0-Cont.Area Ngh Cont.Area~tion Area Ngh I4ci.Area L,~el Htgh Rad.Area

~~~'~~<<4 RR=~1 W~~I s~e~~~0 0~S K%I~~~:~~~~~0 ~~Qe I.0 0~I~~~~I~~~ R.E.QINNA STATION NhR: TechnlcIIn: Date: Time: Inst.Type: Nots: All res~s~ln mr/hr oolsss otherwise noted.d~100deng New Fuel Sioroge 10 30-10:60 Oocr 29 Radiation Levels A=37mRIhf B=10mR/hf Smears.250dprn Aifbofne Activi iodine=1E-11 uCilcc Part.=1E-10 uGilcc Penebothn. F'm 0 0 0 s 0 RH5T y'~Smear Locatke.-x-x-a Rad/Cont..Barrier w Radlatlon Level+w Natrtron Radiation Level~Contact Reading Technician Remarks:~~Cont.Arel Ps w tRgh Cont.Area a gaciatioll Area P~w Rtgh Rad.Area a l.odored High Rad Area ~~.N~~~if Itt~~~~'pW~~: Qa I~~I I~~~I~~I~~~ R.E.QINNA STATION a r c n c Acmic'j cc<<e ,>ccccnccncrc <<acne censce".Ac"c cn ccc" w'ccc".ecn a'-cc f Ir Technician: Date: Ttclcs: Inst.Type: I Seri sr 4's: I power: LLD: Note: All raadlnle are ln mrihr unleaa otherwise noted.r..S dftml100ertta 5 f f I 0 New Fuel Storage~~a~a~~~OOCC 29 12:50-15:g Radiation Levels 0 0 C C W~~~~Og (aagf Pffnetrotion Fr+17mRlhr~meara 500,000dpm a~64 c I iodine=6E-7 uCMcc Part~2EA uCllcc s 0 0 oc5 a Smear Location-x-x-a Rad/Cont.Barrier~Radiation level~Neutron Radiation i.evei~Contact Reading echniclan Remarks: Cont, Area Oe~Hlffh Cont.Area a Radiation Area Q~a HIIh Rarf.Area O~Locked High Rad.Area a~~')0 e~e~I 0~O~~I~~~~~~~~K>s~~.gl)r~'~~~0~~ 0 ~~~~~~~~s~Q~t a 0 I I I I~~~~~~~~~K>I gag t~%$~'~;~~~~~~I~ s~~~~~St~~W RR e~~e~~~O~1 II fit~~~~~~e~0 a K5s Sg~~~~~~~~~~~~~~~ ~~~~~I~'I~~~~s~k~a~a s~smAN w~~>>~~RR~W~W~~W I'I~I I I I III III'~~~~~~~E>I~~.gP, La: 5~;~~~~,~~~~~ R.E.GINNA STATlON:"".:."Aoidltiiijgsr'rgdin'@l~0g +4~%" Technician: o te: Tiara.inst.Type: Serial¹'a: I power, LLD ote: Ail readings are in mrIhri Auttgtrg.~ o.8 RWST It oo dlrttt/100cittg A CDT Bus 16 sar 8 CDT C CDT D CDT RC 4 Filter~e MCC 1M C Charcoal/HEPA Filler OOQ O Dl Vault 0 Q 07:30 gp 5p All Areas (Clean)Radlatton Levels 0.1mRIhr Smears 250dpm l~liH il i;4 iodine=<E-'1 0 uCilcc Part 1E 10 uCt/cc VCT Co OOQO~Smear Location-x-x-~RadICont.Barrier Radiation Level¹~Neutron Radiation Level¹c~Contact Reading Technic/an Remarks:~~Cont.Area 0~High Cont Area.~Radiation Area Q'High Rad;Area~Locked High Rad.Ares, 0-R.E.GINNA STATION Technician: Cate: 'Rme: Inst.Type:/Serial¹'e: I Power: LLD Note: All readings are in mr/hr unle oth Autorr'.gyes A GOT RWST 0'us 16 tt0 0 tlptttl 10Octttg B GOT C GOT 0 GOT~ee MCC tM G Charcoal/HEpA Filter 10:50-12:go All Areas Radiation Levels 62R/h Smears 500,000dpm ~Nd II ti I iodine=4E-1 uCi/cc Part.=3E+0 uCi/cc sar VCT RC Filter CHT po ooOo Ol Vault ooOo 0 I S mear Location-x'-x-a Rad/Cont.Barrier Radiation Level Q¹~Neutron Radiation Level¹c~Contact Reading Technician Remarks:~~Cont.Area 0 w High Cont.Area+Radiation Area Q~w High Rad, Area~Locked High Rad. R.E.GINNA STATIONi!'Auxlllagfi; BVBdinQ';ql+er'meditet"'eevgr"'j E't'ttst'i~jpj jg'?'.Technician: Date: Time: Inst.Type:/Serial¹'e: I Power: LLD: Note: All readings are in mr/hr unless otherwise noted.AUNTS.~No.dpml100cm2 RtNST 0'us 16 oo A GDT C GDT B GDT D GDT 1M G Chorcool/HEPA Filter 12'50-15:00 Radiation Levels 17m R/hr Smears 1,000,000d pm Airborne Activi iodine=6E-7 uCi/cc Part.=2EW uCi/cc sop VCT Voice Hlcy RC Filter CHT Qo ooOo Dt Vault ooOo'tt I 0 I Smear Location Radiation Level¹c=Contact Reading Technician Remarks:-x-x-=Rad/Cont.Barrier¹~Neutron Radiation Level 0-e g 8-Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.h y'nn R.<.CIRCA STATION Technician: Date: Time:/Inst.Type: SerlU<<'s: I Power.lsote: All res<<loss sre In mrlhr unless otherwise noted.No.d Rtttt1QOomi I Containment Veisel 10:00-1 0:50 f(K r I g I 7 I Sump Q Pft Sump Tank 4, Pumps AII Areas Radiatiop Levels 1 R/hr Smears 50,000dpm Ai*A r IV Iodine=3E-9 uCi/cc Part.=9E-9 uCi/cc*nnNOTEe*nn AT THIS TIIIE PLAYERS IN THIS AREA WILL BE FORCED TO LEAVE DUE TO HIGH DOSE RATES e Smut LOCadnn-X-X-a Rad/Cnl>>.Sarrler:g.e Ratdadon l.oval~~Neutron Radladon Level ga~Contact RoaNno TechnicIan Remarks: Pe 0 pe a Cont.Area Ngh Cont.Area RacNation Area High Red.Area Lockecl High Rid.Area -N,I.ORNA ITATlON AcmdINV~+4%act secK~-yggNg Ind Technician: Dote: Tlee:-/Inst.Type: Serial S':>rrowar: LI,C: Mote;All ree4 gI are in mrlhr unieae otherwiae noted, 4t8"aFIa Cg~'yrnl1COorng 4=vCS C~AQ RHQ SCREE 9 CVCS C CVCS x Qe 07:309:10 All Areas (Clean)Radiation Levels 0.8mR/hr Smears 250dpm Ale A ti itK iodine=1 E-11 uCi/cc Part.=1E-10 uCilcc RWST R(Cv A , Smear Looadon x x w RadlConr.Senior JL w llardadon losel~w Iaautron Radladon I.assi da w Canraar Reading~!Helen ltemaAa~Cont.Atom O~w Ngh Com.Area IlSQlSOtl Area Q'w NSh Rad.Ares baked High Rad.Atw e.i.a+ca ITATlo~Techrdcian: Dere: Tlllle: inst.TyPe: Serial e': r power: LLD: Mott: All rIN~~ln mr/hr gnlogg oNIFwjg4 A4C~adc9 ltrIS op~4hettl SCOerng;4:PCS (aa lg IIIIR deny~I e~09:10-10:00 9 CVCS C CVCS Qac E x Qe Radiation Levels A=3mR/hr.B=O.SmR/hr , Smears 260 dpm~ill*a~i iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc RWQ A RE K v A L 0 o QO a Seem Loosens-e-x.~lied/Cont. Settler'~~gargstmn Losel~~Weotron hadlat4n Losel A~Contact ReeOny ,7eehnlo4n hemsraa~~Cont.Atria Qs~Ngh Cont.Area a QI+A Acii Q~s Ihgh had.Area~yg'Qgh Rid.arw IM.QNhfA ITATlON~~~%~anent LevN.~~~Tocll flic)ll: DIte;Time:.I inst.Tyyo: S4rlil 4" 0;Power: I.l.g,"~'/"<<nliaa otherwiso noted.dh>>OO A VCS RltR FCRS 9 CPS C CVCS~I~~0 8 f N r Qr sgw a OS:10-10:00 Radiation Levels A=3mR/hr.8=0.5mR/hr Smeam 250dpm~AW II Bi iodine=1E-11 uCi/cc Part.=1 E-10 uCi/cc RWQ A R f Ev w Smear I.deaden-a-x-a RadlCont.Sant<<'~w Radladen I.mrel'~w Ieetnren Radladen Larral~Ccetact RoaNng~chnkSan ltanaAa:~e Cont.Ataa Qe w ISSh Com.Area~~ftaNt5on Arei Q w ISSh Rad.Area m Locked High Rid.Arao ft.I.QINNA STATION TechrHclan: Oate: Time:./fflefr T~r'l a e: I rrower LLD"r ur(II44 othirwiao noted.ada SFP Dg~4Rcccl 1OOerccg:PCS 4 a+Q RHR geng 9 CVCS C CVCS RE g V A~~e (~Qr~Q f x Qc RWST 10:00-40:50 All Areas Radiation Levels 600mR/hr Smears 6,000dpm~aw a t'ai ledine=1E-9 uCi/cc.Part.=3E-9 uCi/cc n*nNQTE e*ee AT THIS TIME PLAYERS IN THIS AREA WILL BE FORCED TO LEAVE DUE TO HIGH DOSE RATES ,Qt w Smear Loeaoon.x-a.w RaUConc.Senior g.w RarRaC(on Level~w Mecnron Radlaoon Lerlel A~Contact looting 7echrdclan lanate:~~Can.~Qo w CCCC(CC CenC.Area~gst540 ArII Q~w R(C(CC Rao.Area o~~yd HIOh Rad.Ane Qelgg4 QC~Wl-~I~II I I I~~~~~~~4KZZEl~y I.~t~4~~~*0~~I 0 P ~~geiger-~QO~W-~I~III~~I I I~Kill 0~(o)~I I I I I I~~~~o~~~l~~~~e~~~4 I~I~ R.EsGINNA STATION r<<'r/tran'.r.'. <<cc;;, Technician: Date: Time: Inst.Type: ger/al/r's:/Power: LLD: Note: All readings are in mr/hr unless otherwise noted.AUXOPg.M I M No, dpnt/100ttrn2 A Monitor Tank~a 0 Bus 14 Ooor 26 B Monitor Tank A Aux.Bldg.Supply A/H Unit~~~~a<I 07:30-10:50 All Areas (Clean)Radiation Levels 0.1mR/tir.Smears 250dpm Airborne Activi iodine=1 E-11 uCi/cc Part=1E-10 uCi/cc ooooo~Prooeasing 0 0 I s X 0 g a~X Ooor 28 Ooor 27 6 A~O Pogtharg<<¹~Smear Location-x-x-a Rad/Cont.Barrier W~Radiation Level+I Neutron Radiation Level¹c~Contact Reading Technician Remarks:~~Cont.Area Qs m High Cont.Area+~Radiation Area Qc m High Rad-.Area O Locked High Rad.Area R.E.GINNA STATlON""'je84"" 8@.."Wfaa3rSndti Technician: Date: Tlm e: tnst.Type:/Serial¹'s: I Power: LLD: Note: All readlnge-are ln mr/hr unless otherwise noted.AUxops~I M No, dpm/100cm2 A Monitor Tank Bus 14 Ooor 26 B Monitor Tank A Aux.Bldg, Supply A/H Unit~~10:50-12:50 All Areas Radiation Levels 62R/h Smears 200,000dpm Airborne Activi iodine=4E-1 uCi/cc part.=3E+0 uC!/cc OOOOO~O.0 s x P B A Posahara Ooor 28~Smear Location-x-x-~Rad/Cont.Barrier OjF~Radiation Level+~Neutron Radiation Level¹c~Contact Reading Technician Remarks: Qo+Qi Cont.Area High Cont.Area Radiation Area High Rad-.Area Locked High Rad.Area I R.E.GINNA STATlON Technician: Date: Time: inst.Type: Sedal¹'e: I power: LLD.Note: Ail readlnga are in mr/hr unless otherwise noted.+mott.se I M No.ttpml100oma A Monitor Tank 8us 14 Ooor 26 8 Monitor Tank A AUx.B(4g SUPPiy A/H Unit tat 0 1:50-1: Radiation Leyele~~17m R/hr smears 500.000dpm Airborne Actin locNAOWE-7 tIQl/cc Part~2EA ulcc OOOOO~itrooeaaina 0 0 I s x P S~X 8 A Ooor 28 Door 27~0~Smear Location-x-x-a Rad/Cont.Barrier Radiation Level+~Neutron Radiation Level¹c~Contact Reading Technician Remarks: 0-6-Cont.Area High Cont.Area Radiation Area High Rad-.Area Locked High Red.Area SECTION 9.0 ONSITE RADIOCOGICAL AND CHEM/STRY DA TA 9.1 Radiolo ical Summar A.Source Term The radiological source term assumed for this scenario was selected to include appropriate quantities of noble gas and radioiodine resulting from the postulated 3%fuel melt accident scenario.Protective action recommendations i.e., sheltering or evacuation for certain Emergency Response Planning Areas (ERPAs)-will be required based upon the anticipated declaration of a General Emergency and plant conditions. As a result of accident release rates, the projected whole body and thyroid doses will exceed EPA Protective Action Guides beyond the Site Boundary.The assumed noble gas and radioiodine release quantities are shown in Figure 9.1 as a function of time.The scenario involves one release point which is from the Plant Vent.This occurs as follows: Time Release Poin Release Rate Ci sec 10:50-12:50 Plant Vent 3.21 E+2 (Noble Gas)3.21 E-2 (Radioiodine) The noble gas-to-radioiodine ratio assumed is 10 000:1 during this period of release.Isotopic breakdowns of assumed noble gas, radioiodine and particulate release quantities are provided in Table 9.1.B.Inte rated Offsite Doses Due to Plume Ex osure The downwind integrated doses at 3.5 miles, based upon a 2.0 hour actual release duration are: Time 10:50-12:50 Release Poin Plant Vent Inte ra ed Dose Rem 1.50E+0 (Whole Body)2.63E-1 (Child Thyroid)Princi al Plant Radiolo ical Indications Figures 9.1 through 9.5 provide trend plots for key plant radiological indications, including plant vent concentration, letdown monitor level, containment radiation level and reactor coolant concentration. TABLE 9.1 The assumed release quantities for the Ginna Exercise Scenario are summarized as follows: Time: 10:50-12:50 hr Nuclide K Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138~curie Sec 1.6 E+01 5.0 E-01 2.9 E+01 4.3 E+01 4.6 E-01 1.5 E+02 2.1 E+01 2.8 E+01 7.1 E+00 2.8 E+01 Total Curies Released 1.2 E+05 3.6 E+03 2.1 E+05 3.1 E+05 3.3 E+03 1.1 E+06 1.5 E+05 2.0 E+05 5;1 E+04 2.0 E+05 Total Noble Gas 3.2 E+02 2.3 E+06 l-1 31 I-1 32 I-1 33 l-1 34 I-1 35 4.7 E-03 6.7 E-03 9.5 E-03 2.6 E-03 8.6 E-03 3.4 E+01 4.8 E+01 6.9 E+01 1.9 E+01 6.2 E+01 Total Radioiodine 3.2 E-02 2.3 E+02 Long-Lived Particulate 1.2 E-09 1.5 E-06 Figure 9.1 Assumed Source Terms CI/SEC 1.0E+03..1;OE+02 1.0E+01 1.0E+00:: 1.0E-01 1.0E-02 1.0E-03 1.0E-04-,- 1.0E-05:5 1.0E-06 1.0E-07,-1.0E-08: 1.0E-09~09 00 i 5!i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I~I I-I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I~~f f f f f t 1 5 I 5 I I 5 I 5 5~~5 l f l l f l!t 5 5 I!l l l I f!!f-l l 1!l l l f l l 5 5 I 5~~l l!l*f l l l l f l!!!i!!!!!!!! ~~!if l l l f!!l l l f!f f t I 5 5 It!it I I I I I I I I I t I I I t I I I I I I I I I I I!I I I I I I l f l f f l l f l l l!!!I!!5~f~~f l I I I l l f l l l l l I!.!f l 5 I~f~5 I l l l l l f l l f l!I f l l l!I!l f l l f l l l l l!!l!!l l I I I I li I I I I I I I I I t I I I I I I I I I I I I I I I I I I I I t 1 5~5 5 5 I~ill!!f l l l!if l l l I l l l fill!fill!!f!all!I!!!l l l!I l l l I l I f l l f!!!!l I l l l 5 5 5~5~5 I 5 5 5~5~5 1 t 5 5~5 1 1~I I I I I I I I I t Ill I t I I I.k I I!11!I I I I I!11 t I!I!!I I!I I!!I!LO 0 4 0 00 0)LOOOQOLOOLOO r 09 0~C9 0 0~C9$00000~v v-LO 0 LO 0 4 0~0~~09 4 0~~CVOl CVOl09 T T T T T 4 0 4 0 LO~C9'ct'0~090909 rt N T I!I I I I I I I I I I I I I I I I!I I I I I I I I I I I I I I I I I I I I CLOCK TIME~NOBLE GAB Cl/SEC RADIOIODINE Cl/SEC Figure 9.2 Plant Vent Concentrations uci/cc a 00 1.0E+01.1.0E+00:, 1.0E-01 1.0E-02.1.0E-03.1.0E-04 1.0E-05=1.0E-06-, 1.0E-07-: 1.0E-08: 1.0E-09,: 1.OE-1 0&a~~a a a a a a a a a a~I I I I I I I I I)t)I I I I I I I-I)~I I I I I I I I I I~~a I)a~~~~~~~~~I~~~~a a I=')I I I I I I I~I I II I I I!II)I I I I I I I I I 5 I!!I I I I I I I I~!}}I!~)~~)~I~a I~a~I~~~~~a a~~~~~~~~I a})1 I I I I I I I!!!!I I I)I I}I!I I I I I I I I I I~I I I I I!I I I I I~~~~~I I~I I I~I I I I I~I I I I I I t I I I I t I I I I I I I I I~~I t~I I.I I I I I I I I I I I I I I I I I I I~~!I I I I I I I I I I~I I I I I I I I I I I I I I I I I I I I I I I I I I~~I I I I I I I I~I I I I I I I I I I I I I I I I I I I I I I I I~I I I I~f I I)II I~I I I I I~~I}I f I I I}I!I I~!I I I I I I I I I I I~I I~~~I~I I I I I I I 4 0 rl 0 00 0)Q O O LO O~80r C9%OOOO LAO LO cf Ov-~~~~~~Owe 0 4 0 LO 0 COCO~C9 v-~AC))l N LO Ol T OLOO 0 v-CO 09 09 09 404%Or 09%%I I I I~I~~I I I I I I I I I I I I I I I I I I I I I I I I I I I I~I I I I I CLOCK TIME NOBLE GAS~RADIOIODINE Figure 9.3 Letdown (R-9)Readings 1.0E+05 MREM/HR 1.0E+04 1.0E+03 1.0E+02 1.0E+01 1.0E+00 0 LO 0 LO 0 0 N'cf'Or 090 LOOOOLOOLO r 09 rf'r 09 4~~~~~~~~~~~~~~~~~~~~~~~~~~00 CO 0 8 0 0 0 0 0 r r r r rrrrr rr O Q O LO O Q O LO O LO Or C940r0940r OlOlOl CV09e9COC9% W r r r r r r r r r 1 CLOCK TIME~LETDOWN Figure 9.4 Containment Radiation M 1.0E+07 REM/HR 1.0E+06 1.0E+05 1.0E+04 I.OE+03::,-.-1.0E+02-:-.: 1.0E+01 1.0E+00~09 LOOOOOLOO Ct'Ot-COOr 09 OOSSSOOO 4 0 lO 0 ct 0~09 0 v v 4 0 LO 0 LO'ct'~09'cf'N N Ol Ol 0 4 0 LO 0 Lfl 0 r 09 4 0 v-09C90909%N T V T T CLOCK TIME~CV RADIATION Figu e 9.5 RCS Activity 1.0E+06 uci/cc 1.DE+04 1.0E+03 1.0E+02 1.0E+01 1.0E+00 0 LO 0 LO 0 0 COVO~COO 00 00 0)0)0)0 LO 0 4 0 0 09'ct'w 000'-~T T T T 0404 09%0~~~~~~~~~~~AN O LO O Q O LO O LO C9 cf'~v-09 4 O~v-OlOl09090949% W T L l l T CLOCK TIME RCS Activity 9.2 IN-PLANT RADIOLOGICAL DA TA ROCHESTER GAS AND ELECTRZC GZNNA STATZOM SERVICE BUILDING NORTH DATE:Ž!~!SURVEY YRSYRUREST'ERZAZs NUMbER: REMARKS'REA SURVEYED!~I I SURVEYED bY!COUHTZNO ZNSTRUMENZ. SERZAZ NUMbER!POWER!~I RNZ'/SMP NUMbER: L?dKhXZ~~I Sg J~J SU z eJ ul I 07:30-15:00 All Areas (Clean)Radiation Levels 0.01mR/hr Smears 250dpm Airborne Activi iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc~Q 2 CI I'S1 fj I (1 QU IQB CsI~U 0]2 2~RELDZNlssd ZN MR/MR UlGL5d~RRÃZSR llOTfD R.E.GINNA STATION tact rtrxtrt.rht Technician: Date: Tlnte: Inst.Type:/Serial g'a: I Power: LLO: Note: All readinga are in mr/hr unless otherwise noted.No.dpm/100clrt2 Ooor 65 Ooor 46 0 Oressing Area S El 0 W E R Mens Room L 0 C K E R 07:30-1 5:00 All Areas (Clean)Radiation Levels 0.01 mR/hr Smears 250dpm Airborne Activi Iodine=1E-11 uCi/c Part.=1E-10 uCi/cc (--To Turbine Buddln LctNtty Smear Location-x-x-=Rad/Cont.Barrier Radiation Level¹=Neutron Radiation Level¹c=Contact Reading Technician Remarks: Cont.Area 0=High Cont.Area+=Radiation Area Q=High Bad.Area O Locked High Rad.I Area R.E.GINNA STATION r<<'p" t,.Ql i<<petti~'t<<ina<<it<<<<<<<<<<u<<. <<<<<t<<<<>>'A<<>><<ante>d>>>Q

  • Technician:

Date: Tlute: Inst.Type:/Serial er'e: I Power: LLD: Note: All readings'are in mr/hr unless otherwise noted.Door 8 Carpenters No.dpm/100cm2 OA Stoiat3e Planners Pipe Shop Stock Room Mechanic Shop Weld Shop Uens Room 07:30-15:00 All Areas (Glean)Radiation Levels 0.01mR/hr Smears 250dpm Airborne Activi Iodine=1E-11 uCi/cc Part.=1 E-10 uCi/cc Kot Shop Bectrtc Shop O Smear Location-x-x-=Rad/Cont.Barrier Radiation Level+=Neutron Radiation Level¹c=Contact Reading Technician Remarks: Cont.Area High Cont.Area Radiation Area High Rad.Area Locked Migh Red.Area R.E.GINNA STATION>>:'r: j~i50ff@A 50uth~~q-'.oufhm !K~"i ii%r!re'r,",,+N~KNifr:,z!!,4N!fH>fffr'r!44>>'eq~'jgf:; ~'~',>i;R':<4: Technician: Date: Time: Inst.Type:/Serial 0': I Power: Note: All readings'are in mr/hr unless otherwise noted.LLD: sVC44.Rrr Qlj Q X~"0~[]R>>r g GOO'lj 0 L i)Cf No.dpm/100cm2 0 0 0 0 Ij g CDC3DC3+O OO O~O~0 OO 0 Pff 0 p HP/Chem.Qdf Offices p~Pa~ff aa ff.O lj Q~~ll a~np 07:30-15:00 All-Areas (Clean)Radiation Levels 0.01m R/hr Smears 250dpIH>>~lid il Iodine=1E-11 uCi/cc Part.=1 E-10 uCi/cc C.R.C3 Rises Office Door 74 O Smear Location-x-x-=Rad/Cont.Barrier=.Radiation Level¹=Neutron Radiation Level¹c=Contact Reading Technician Remarks: p>>+0=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.';Area R.E,GINNA STATION::,"Ail" VolaNe Treatment Building.-Control Panel Area Technician: pate: Time: Inst.Type: Serial (('s: I Power: LLp: Note All readings are in mr/hr unless otherwise noted.AVTCP Fr(P No.dpm1100cm2 NaOH Tank Ro(t Uonrior H2S04 Tank To AYT Dl Room AVT Control Panel Sample Sink Anotyter)07:30-1 6:00 All Areas (Clean)Radiation Levels 0.01mR/hr Smears 250d pITI Airborne Activi Iodine=1 E-11 uCi/cc Part.=1E-10 uCi/cc Door 67 H20 Heater Desk Door I9 f Door 28 I'(¹~=Smear Location-x--x-=Rad/Cont.Barrier~~~Radiation Level.<4,=Neutron Radiation Level ,¹c=Contact Reading f Technician Remarks: Cont.Area 0=High Cont.Area+=Radiation Area High Rad.Area Locked High Rad. R,E.GINNA STATlON::,."All"'.Vofatfte':":.::Treatment,:l ,BuBdinQ:": -Oemtnerafizer Area Technician: Date: Time: inst.Type: I rieriat¹'s: I Power: LLD: Note: At(readings are in mr/hr unless otherwise noted High Conductivity Waste Tank Low Conductivity Waste Tank Door 27 No.dpm1100em2 0 Dilute NH40H Dilute NaOH 0 Mixed Anion Regen 0 Oemin C Demin B Demin 07:30-15:00 All Areas (C)ean)Radtat>on Levels 0.01mR/hr Smears 250dpm~air II r'iodine=1E-11 uCi/cc Part.=1E-10 uCl/cc ilute H2S04 Cation Regen A Demin¹=Smear Location-x-x-=Rad/Cont.Barrier Radiation Level¹=Neutron Radiation Level¹c=Contact Reading Technician Remarks: Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area R.E.GlNNA STATlON're423gj~fiji Technician: Date: Time: Inst.Type: I Serlel rr'e: I Power: LLD: Note: All readlnga are ln mrlhr unless otherwise noted.NRC Office Kitchen wo IZM Mens Room Womens Room)3~32 dpm/toocm2 dpm/toocm2 rtc 07:30-15:00 All Areas (Clean)Radiation Levels 0.01m Rlhr Smears 260dpm Airborne Activi iodine=1E-11 uCilcc Part.=1E-10 uCilcc oocm2 d pm/1 oocm2 No.d pm/100cn/ee Smear Location g ee Radiation Level gg, m Contact Reading m Neutron Radfatfon Level-x-x-ee Radlcont.Serrier Technician Aernarfta: ~w Cont.Aroo Qi~teett Cont.Ares+o Aocaotfon Ares+o fee/2 Aod.Aron+a LOCksd Heh Aed.Arse R.E.GINNA STATiON tstteaII~A~~ I'RY>IR~m RB"RrrRuvernr-u<0' Nt Technician: Date: Time: Inst.Type:/Serial¹'0: I Power: LLD: Note: All readings;-are in mr/hr unless otherwise noted.8 Iheset-GerL k 0 eset-Gen.32 26 Svc.Air Comp.0000 0000 Air lonks Condensote Borrtter Pumps tI pret/100crts2 Heoter I I Bran fk I i~0~0~~OO~~~0 0~~0~0~~~0~~~0~0~0~0~~~0~~~0~0 Bottle Storooe Door 8 Q~0~000000 Bottle~0~St9~0~Chem.Add Ptanps lCondensate Pumps LR Condenser s See.Oil System 07:30-1 5:00 All Areas (Clean)Radiation Levels 0.01mR/hr'mears 250dpm Airborne Activi iodine=1E-11 uCi/cc part.=1 E-10 uCi/cc r r~~RO 01RRR, Btoedoen lank train feed Pumpt rrre water rLRl A'r Onrer O¹=Smear Location-x-x-=Rad/Cont.Barrier Radiation Level+=Neutron Radiation Level¹c=Contact Reading Technician Remarks: Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.tI Area R.E.GINNA STATION Technician: Date: Time: Inst.Type:/Serial ttr'a:/'ower: Note: All readings are in mr/hr unless otherwise noted.LLD: TVIWHCZL~se Reloy Room No.dpm/100cm2 feed Wirier Crane Bgtr Condenser 22 07:30-1 5:00 All Areas (Clean)Radiation Levels 0.01mR/hr Smears 250dpm A~Nb II ti I iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc 0 0 a lube Oig Res, Sfs QQn Qm0~Chem.tanhs C ta, Mon feed See CN.~C=-~O¹=Smear Location Radiation Level¹c=Contact Reading Technician Remarks:-x-x-=Rad/Cont.Barrier Neutron Radiation Level Cont.Area 0=High Cont.Area+='adiation Area O=High Rad.Area c Lockeu high Red.Area R.g.GINNA STATlON P tt(tIIIPtttt,ItttthttttttttttItN Technician: Date: Time: inst.Type:./Serial¹'s: I Power: Note: All readings are ln mr/hr unless otherwise noted.LLD: dpm1100cm2 I I I I L J I I I I I I I I L Control Room K=V I I 8=k CV 07:30-15:00 All Areas (Clean)RadIatIon Levels 0.01mR/hr Smears 250dpm Airborne Activi iodine=1 E-11 uCi/cc Part.=l E-10 uCi/cc O¹=Smear Location-x-x-=Rad/Cont.Barrier Radiation Level=Neutron Radiation Level¹c=Contact Reading Technician Remarks: Qs Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.l Area R Q.GiNNA STATiON~<>,'gcK.><~~>Kj <>?)wtpQp'F<,"~A<+Pt.<rt~N<'+;,c'<+ $%<.tp~+>'~'>wq++pz>w'>;<p< ',-'Li>iggh,.'.~>34;..<a is+w>r<,y v';~<>'Ster<",~"",'S:>>"e'j;3; L>".h>>'3r<,j<:.iv a+>a'.;:<<.>Technician: Date: Time inst.Type:/Serial¹'e: I Power: Npte: All readings are ln mr/hr unless otherwise noted.'iet,i'3" 5$>i, LLD: No.dpm1100cm2 CV Purge--->R10A,11,12 CV Vent-->Plant Vent--->0 0 0 0 0 3;~'---N----R108 13 14 Containment 07:309'10 All Areas (Clean)Radiation'eve(8 0.01m R/hr smears 250dpm~<l<<~I iodine=1E-11 uCi/cc Part=1 E-10 uCi/cc 0 0 0 0 0 A Purge Exhaust Fan il::<>>3[i I::~tr;, 8 Purge fxhoust fon O Smear Location-x-x-~Rad/Cont.Barrier Radiation Level~~Neutron Radiation Level 4'c=Contact Reading Technician Remarks:~~Cont, Area Q~~High Cont.Area+~Radiation Area Q'High Rad.Area Q Locked High Rad Area R f.GINNA STATION~c4k+N~Mc+apNjc(', RYc r'tres~+4&g s.a'Ã~a q%c<gcrv r'wNQM e cw~'g t;<r'piary j;c,',:e~'<'rw rj"+%i'j"x'"+~l,.'71 r,i'np Technician: Date: Time: Inst.Type:/'erial¹'e: I Power: LLD: N p pe;AII rea ding I are in mr/hr unless otherwise noted.~r ll tl No.dpm/100cm2 0 0 0 0;r~r 09:10-10:30 CV Purge--->R IOA,11,12 CV Vent-->Plant Vent--->0 0 0 0 0 A Purge Exhaust Fan Containment A----R10B 13 14 U Cl Radiation Levels A=3m R/hr B=0.5mR/hr Smears 250dpITI~ale ii ii i Iodine=1 E-11 uCI/cc Part=1 E-10 uCI/cc B Purge Exhaust Fun=Smear Location-x-x-~Rad/Cont.Barrier~Radiation Level'Neutron Radiation Level¹c=Contact Reading Technician Remarks:~Cont.Area Q+m High Cont.Area+~Radiation Area Q'High Rad.Area O~Locked High Rad Area C~~~-I wr wary ao.iv h~;a'v~'vi~mQ a~~~~~~I I I Qo~~I~~~~~~~>~~~~~I~~.I~~',~~~~~~~~~ R.E.GINNA STATION Technician: Date: Time: Inst.Type:/Serial rrr'e: I Power: LLD: Note: All readings are ln mr/hr unless otherwise noted.dpm/100ctn2 CV Purge--->R10A,11,12 CV Vent-->Plant Vent--->0 0 0 0 c 0 B CL 0 0 A Purge Exhaust Fan c Containment

R10B,13,14 10:50-12:50 All Areas Radiation Levels A=6 R/hr 8=1 000mR/hr C=500m R/hr 0=37mR/hr Smears As 8=600dpm C&0=2000dpm Ai~A ti itK lod<ne=1EW uC>/cc Part=1E-7 uCi/cc 8 Purge Exhaust fan O~Smear Location-x-x-~Rad/Cont.Barrier~Radiation Level.~Neutron Radiation Level¹c=Contact Reading Technician Remarks:~Cont.Area Q'High Cont.Area+=Radiation'Area Q High Rad.Area O~Locked High Rad.Area R.E.GINNA STATION Technician:

Date: Time: Inst.Type:/Serial<<'a: I Power: LLD: gate: All readings are ln mr/hr unless otherwise noted.No.dpm/100cm2 ~\0 0 0~I CV 8 Purge--->~.Q Containment 12:50-1 5:00 R10A,11,12 Plant Vent--->0[]0 0----R10B,13,14 Radiation Levels A-37m R/hr B=50mR/hr smears A=3000dpm B=5000dpm Airborne Activl Iodine=2E-9 uCl/cc Part.=2E-S uCI/cc 0 0 0 lint Purge Exhaust Fan B Purge Exhoust Fan O¹=Smear Location-x-x-~Rad/Cont.Barrier~Radiation Level~Neutron Radiation Level¹c=Contact Reading Technician Remarks: Cont.Area Oe~High Cont.Area+~Radiation Area Q+~High Bad.Area O~Locked High Rad.Area R.E.GINNA STATION Intermediate'uilding North-Operad Technician: Date: Time: Inst.Type:/Serial¹'e: I Power: Note: All readings are in mr/hr unless otherwise noted.Wert THOP aetP N4.dpm(1aacm2 0 (---N Purge Exhaust Fan~R-i/A 8 L a W 0 R Containment 07:3049:10 All Areas (Clean)Radtat>on Levels 0.01mR/hr Smears 260dpm A~id Il r.iodine=1 E-11 uCi/cc Part.=1 E-10 uCi/cc Cl a Uon 4 Steexn 8 purqe ettoust f Nt Oaae 57 Chateau Leer O.l.etoter-Stortxye lank'¹)=Smear Location Radiation Level.'¹c=Contact Reading , Technician Remarks: t-x-x-=Rad/Cont.Barrier+i=Neutron Radiation Level Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.A I'ne R.E.GlNNA STATlON Intermediate Building North-Operating Leve Technician: Date: Time: Inst.Type:/Serial¹'e: I Power: Note: All readings are in mr/hr unless otherwise noted.WtrrIHO¹frrrp N4.dpmr1000mg I t<---N 09:10-1 0:30~R-l2A Containment Radiation Levels A=3m R/hr B=0.5mR/hr Smears 250dpm I~IN 4 ri iodine=1E-11 uCi/cc Part.=1 E-10 uCi/cc A t Urge Exhaust fan W 0 R I I 0 A taon 4 St¹4 8 pr¹rta rrxaxrt F4e Oaor 57 Chemistry l(Xt 0J.Weter-Sloreta fantr'¹;=Smear Location Radiation Level ,'¹c=Contact Reading;Technician Remarks:-x-x-~Rad/Cont.Barrier Neutron Radiation Level Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad, Area R.E.GINNA STATION intermediate Building North-Operating Level Technician: Date: Time: Inst.Type:/Serial¹'e:/Power: Note: All readings are in mr/hr unless otherwise noted.No.d pmi t Oacm2 0 y A/I t R-irk I R 1%A o (---N Containment 'I 0:30-1 0:50 Radiation Levels A=37m R/hr B=17mR/hr Smears 250dpm~ee Il el iodine=1E-11 uCi/cc Part=1 E-10 uCi/cc A Purqe Exhaust Fan 8 a W 0 t R 0 Auon 4 Stars 8 piece aiaaarl fa¹r Ooor 57.B Cieenestry t OJ.Wder-Skarote tank I¹}=Smear Location Radiation Level',.¹c=Contact Reading , Technician Remarks:-x-x-=Rad/Cont.Barrier/=Neutron Radiation Level 4 0=+0=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area~ R.E.GINNA STATION intermediate Building North Operating Le Technician: Date: Time: Inst.Type:/Serial¹'a: I Power: LLD;Note: All readings are in mr/hr unless otherwise noted.trrartTttop atttr D N4, dpm/100Cm2 D 10:50-12:50 C B QA IBt c A Purqe ExhtJusl Fan--8-8 L 0 W 0 R Containment All Areas Radtation Levels A=6 R/hr B=1000mR/hr C=500mR/hr D=37mR/hr Smears A&B=600dpm C&D=2000dpm >>~ik>>iodine=1 EW uCi/cc Part=1 E-7 uCi/cc 0 Alon 4 Stet¹n C PttrtJ¹t F4t D OOor 57 Ckrrvatry Lett OJ.Wotar-Storoga fry'¹)=Smear Location-x-x-=Rad/Cont.Barrier Radiation Level+=Neutron Radiation Level ,¹c=Contact Reading , Technician Remarks: 0 Q>>+Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area R.EeGINNA STATION Intermediate Building North-Operating Level Technician: Date: Time: Inst.Type:/Serial¹'s: I Power: LL4: Note: All readings are in mr/hr unless otherwise noted.WTrr Tstaa Sat¹Na.dpmlloocm2 8 it4n c (---N 12:50-15:00 A Purqe Exhoust Foll~R i/A C 8 0 w 0 R Containment Radiation Levels A=50mR/hr B=37mR/hr C=2mR/hr smears A=5000dpm B=3000dpm C=3000dpm Airborne Activi Iodine=2E-9 uCi/cc Part.=2E-9 uCi/cc 0 A@On 4 irlcssn e Pt¹qe shauai Fan Ooor 57 C Chamrslry ltgt Ol, SASer tllaaqe lank¹)=Smear Location-x-x-=Rad/Cont.Barrier Radiation Level,'I=Neutron Radiation Level',¹c=Contact Reading ,.Technician Remarks: Cont.Area=High Cont.Area Radiation Area High Rad.Area Locked High Rad. R.E.GlNNA STATlON intermediate Building North-Mezzanine Level Technician: Oate: Time: Inst.Type:/Serial¹'a: I power: LLD;Note: All readings are in mr/hr unless otherwise noted.wTtt Ttteeg earp No., dPml1OOr.trial S;carr.0 ,0 Containment 07:30%9:10 All Areas (Clean)Radiation Levels 0.01mR/hr Smears 250dpm Airborne Activi iodine=1 E-11 uCi/cc Part.~1E-10 uCi/cc 4 Mein S)earn--)0 0 IIIte Rcetortt r~I I I I I I I I I Door 45'¹=Smear Location-x-;x-=Rad/Cont.Barrier~~~Radiation Level'4";=Neutron Radiation Level¹c=Contact Reading Technician Remarks: Cont.Area High Cont.Area Radiat>on Area High Rad.Area Locked High Rad.Area ~i~~~.~~~~='='=-'"'-IIL!Pdi)till

=llllll5i~aaHMFll I o~~~~P'IC~I'I I~~~~a I 0~~~~~~ygO o~~~I+~I~~~0 t'~)4~~~~~~~~I~~~~~~~

R.E.GINNA STATION Intermediate Building North-Mezzanine Level Technician, Date: Time: Inst.Type:/Serial¹'a: I power: Note: All readings are in mr/hr unless otherwise noted.WTrerrree2 pap No.dpm(100cm2 pica&-)0 (--N 10:30-15:00 I B Containment Radiation Levels A=37mR/hr B=17mR/hr Smears 260dpm a~le ari iodine=1E-11 uCi/cc Part.=1E-10 uCi/cc A Main Steam--)HHS Raced 1 I I I I I I I I I I Door 45'¹=Smear Location-x-.-x-=Rad/Cont.Barrier~~~~~~Radiation Level'¹~~=Neutron Radiation Level¹c=Contact Reading Technician Remarks: 0 0=+I+~Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area 9.3 POST-ACClOENT SAMPL!NG RESULTS TABLE 9-2A Chemistry Data Equilbrium Activity Reactor Coolant System"B" Loop Sample Sample time: November 17, 1993 O 04:30 Nuclide Ar-41=Kr-85m=Kr-87=Kr-88=Xe-133=Xe-135=Xe-135m=Xe-138=Total Gas Activity=Activit Ci/cc 3.25E-02 4.02E-02 5.41E-02 6.59E-02 2.13E-01 2.03E-01 9.19E-02 3.06E-01 1.01E+00 Total Degassed Activity=1.55E+00 Total Activity=2.56E+00 Boron=345ppm pH=7.0 For more detailed chemistry information see HP/Chemistry turnover sheet. TABLE 9-3A Chemistry Data Post-Accident Samples Reactor Coolant System"B" Loop Sample Sample time: November 17, 1993 O 09:30-1 0:29 Nuclide Ar-41=Kr-85m=Kr-87=Kr-88=Xe-1 33=Xe-135=Xe-135m=Xe-138=Total Gas Activity=Activi*Ci/cc 2.27E-02 2.81E-02 3.78E-02 4.61E-02 1.49E-01 1.42E-01 6.42E-02 2.14E-01 7.04E-01 Total Degassed Activity=1.08E+00 Total Activity=1.79E+00 I-1 31=l-1 32=l-1 33=l-134=1-135=1.11E-02 2.14E-01 1.09E-01 4.60E-01 2.25E-01 Boron=2150ppm pH=5.0*=Activity Corrected to Time of Shutdown 1.62 mR/hr on contact, Sam le Dose Rates: Gas'Undiluted 35cc gas bulb=2.9 mR/hr on contact, Liquid-Undiluted sample= TABLE 9-3B Chemistry Data Post-Accident Samples Reactor Coolant System"B" Loop Sample Sample time: November 17, 1993 O 10:30-15:00 Nuclide.Kr-85=Kr-85m=Kr-87=Kr-88=Xe-131m=Xe-133=Xe-135=Xe-135m=Total Gas Activity=Activi*Ci/cc 1.34E+01 4.36E+02 7.94E+02 1.17E+03 1.24E+01 3.97E+03 7.61E+02 1.93E+02 7.93E+03 Nuclide I-1 31=l-1 32=l-1 33=I-134=I-135=Total Radioiodine Activity=Activit*Ci/cc 4.51E+03 6.50E+03 9.17E+03 2.52E+03 8.28E+03 3.10E+04 Ba-140=8.09E+03 La-140=8.43E+03 Cs-134=1.10E+03 Cs-137=5.00E+02*=Activity Corrected to Time of Shutdown Boron=2150ppm pH=5.0 Sam le Dose Rates: Gas-Undiluted 35cc gas bulb=19.5 R/hr on contact, 111 mR/hr at 1 meter.-Diluted 35cc gas bulb=107 mR/hr on contact, 0.07 mR/hr at 1 meter.Liquid-Undiluted sample=-Diluted sample=804 R/hr on contact, 1.3 R/hr at 1 meter.804 mR/hr on contact, 1.3 mR/hr at 1 meter. TABLE 94A Chemistry Data Equilibrium Activity Containment Atmosphere Sample time: November 17, 1993 O 04:30 N Iid acti ittCi/*I Ar-41=Xe-133=Xe-133m=Xe-135=1.42E-06'.83E-05 1.99E-07 3.39E-07 TABLE 9MB Chemistry Data Post-Accident Samples Containment Atmosphere Sample time: November 17, 1993 I 09:30-10:29 Nuclide Ar-41=Kr-85m=Kr-87=Kr-88=Xe-133=Xe-135=Xe-135m=Xe-138=Total Gas Activity=I-131=I-132=I-133=I-134=1-1 35=Activit*Ci/cc 1.09E-04 1.35E-04 1.82E-04 2.21E-04 7.17E-04 6.82E-04 3.09E-04 1.03E-03 3.38E-03 3.30E-08 6.34E-07 3.24E-07 1.36E-06 6.67E-7*=Activity Corrected to Time of Shutdown Sam le Dose Rates: Gas-Undiluted 3500cc marinelli=0.58 mR/hr on contact 0.01 R/hr at 1 meter-Undiluted 35cc gas bulb=0.01 mR/hr on contact, 0.01 mR/hr at 1 meter.-Diluted 35cc gas bulb=0.01 mR/hr on contact, 0.01 mR/hr at 1 meter. TABLE 94C Chemistry Data Post-Accident Samples Containment Atmosphere Sample time: November 17, 1993 O 10:30-15:00 Nuclide Kr-85=Kr-85m=Kr-87=Kr-88=Xe-131m=Xe-133=Xe-135=Xe-135m=Total Gas Activity=Nuclide 1-1 31=1-1 32=I-1 33=l-1 34=l-1 35=Total Radioiodine Activity=Activi*Ci/cc 2.09E-01 6.78E+00 1.24E+01 1.82E+01 1.94E-01 6.19E+01 1.19E+01 3.01E+00 1.24E+02 Activit*Ci/cc 4.33E-02 6.23E-02 8.82E-02 2.42E-02 7.96E-02 2.98E-01 Ba-1 40=7.61E-02 La-140=7.96E-02 Cs-1 34=1.04E-02 Cs-1 37=4.71E-03*=Activity Corrected to Time of Shutdown Sam le Dose Rates: Gas-Undiluted 3500cc marinelli=12.9 R/hr on contact 137 mR/hr at 1 meter-Undiluted 35cc gas bulb=306 mR/hr on contact, 1.75 mR/hr at 1 meter.-Diluted 35cc gas bulb=0.18 mR/hr on contact, 0.01 mR/hr at 1 meter. TABLE 9-5A Chemistry Data.Equilibrium Activity Containment Sump Sample time: November 17, 1993 I 04:30 Boron=210ppm pH=6.8 Nuclide Cr-51=Mn-54=Co-58=Co-60=Nb-95=Mo-99=Sb-124=I-1 31=1-1 33=Xe-133=Cs-134=Cs-137=Activi Ci/cc 6.52E-05 1.22E-05 1.78E-04 3.25E-05 1.60E-05 1.64E-05 1.66E-05 6.43E-04 1.95E-04 1.21E-04 1.01E-04 2.49E-04 TABLE 9-5B Chemistry Data Post-Accident Samples Containment Sump Sample time: November 17, 1993 O 09:30-10:29 Nuclide Ar-41=Kr-85m=Kr-87=Kr-88=Xe-133=Xe-135=Xe-135m=Xe-138=Total Gas Activity=Activi*Ci/cc 1.13E-03 1.40E-03 1.89E-03 2.30E-03 7.44E-03 7.07E-03 3.21E-03 1.07E-02 3.51E-02 Total Degassed Activity=5.42E-02 Total Activity=8.93E-02 I-1 31=l-132=I-1 33=I-1 34=l-135=4.19E-03 8.06E-02 4.13E-02 1.73E-01 8.48E-02 Boron=2150ppm pH=8.8 Sam le Dose Rates: Liquid-Undiluted sample=-Diluted sample=*=Activity Corrected to Time of Shutdown 11.8 mR/hr on contact, 0.02 mR/hr at 1 meter.0.01 mR/hr on contact, 0.01 mR/hr at 1 meter. TABLE 9-SC Chemistry Data Post-Accident Samples Containment Sump Sample time: November 17, 1993 O 10:30-15:00 Nuclide Kr-85=Kr-85m=Kr-87=Kr-88=Xe-131m=Xe-133=Xe-133m=Xe-1 35=Xe-135m=Total Gas Activity=Activi*Ci/cc 1.72E+00 5.60E+01 1.02E+02 1.50E+02 1.60E+00 5.10E+02 7.40E+01 9.80E+01 1.96E+02 1.19E+03 1-1 31=4.38E+03 I-1 32=6.30E+03 I-1 33=8.93E+03 I-1 34=2.45E+03 1-1 35=8.05E+03 Boron=2150ppm pH=8.8 Sam le Dose Rates: Liquid-Undiluted sample=-Diluted sample=Ba-140=7.70E+03 La-140=8.05E+03 Cs-134=1.05E+03 Cs-137=4.76E+02*=Activity Corrected to Time of Shutdown 781 R/hr on contact, 1.28 R/hr at 1 meter.781 mR/hr on contact, 1.28 mR/hr at 1 meter.

TABLE 9-6 Continuous Air Monitors (CAMS)(Auxiliary Bldg&TSC)Auxiliary Building Top Floor Time Noble Gas Radioiodine Particulate Alarmin?07:00-09:10 09:10-10:00 50 50 50 50 50 50 No No 10:00-10:50 10:50-12:50 100 To ofScale 50 50 To ofScale To of Scale No Yes 12:50-15:00 50 To ofScale 100 Yes Auxiliary Building Intermediate Floor TIIYle 07:00-09:10 09:10-10:00 50 50 50 50 Noble Gas Radioiodine Particulate 50 50 Alarmin?No 10:00-10:50 150 50 50 No 10:50-12:50 To of Scale To of Scale To of Scale Yes 12:50-15:00 50 To of Scale 100 Yes Auxiliary Building Basement Floor Time 07:00-09:10 Noble Gas 50 Radioiodine 50 Particulate Alarmin?50 09:10-10:00 10:00-10:50 50 300 50 125 50 70 No Yes 12:50-15:00 50 10:50-12:50 To of Scale To ofScale To ofScale To ofScale 100 Yes Yes Time 07:00-09:10 50 50.50 Technical Support Center Noble Gas Radioiodine Particulate Alarmin?No 09:10-10:00 10:00-10:50 10:50-12:50 12:50-15:00 50 50 50 50 50 50 50 50 50 50 50 50 No No No No 07:30-15:00 TABLE 9-7 Air Sample Results in TSC and Control Room Particulate Filter=60 cpm iodine cartridge=60 cpm SECTION 10.0 METEOROLOGICAL AND OFFSITE RADIOLOGICAL DA TA N.I.QIANA STATlON maaiaV Iii ice aetna~-sr~~TechrHcfan: Date: Time:.I fnto Tfp.aerial a': r power: LLQ: Note: 4ll'ee~a~in mr/br unleie otherwise notect.A88 SrO Oq~dRnM1OOeng ', 4:VCS (aa RHR Fond 10:50-12:50 9 CVCS C CVCS x Qa All Areas Radiation Levels 62R/h Smears 1,000,000dpm Airborne Activi iodine=4E-1 uCi/cc Part.=3E+0 uCi/cc RWST R f f V A 4 0 ,Qt w Smear Looadon.x-a.w MConr.Banier'W w RerNaden LeVel~w Nemine Radladan LeVel A~Contlct Holing..Technician ltemuha:~~Can.Area Qe inSR Corn.Area~gggt15on Area Q~w Ngn Rad Area~~gd High Rad. R.R.QtNNA STATlON Technician: Date: Time:./lnat.Typo: Seri~I<<'e:/Power LLQ/tote: An reed/nRa are in mr/hr un/eee otnerwiea noted A@a SrO CuM~S 0 Rett/1000/tent A PCS (ww Ag RHR FCnS 0 te 4~J~S CVCS C CVCS x Qe A l 12:50-1 5:00 Radiation Levels A=37mR/br B=17mR/hr Smears 2,000,000dpm Airborne Activi iodine=6E-7 uCi/cc Part.=2EA uCi/cc RWSTi RE K tI A cled.Qd w Smear Loosdon-x-x-w Rad/Cont Ra/der i'~w Ra/Radon LN/et~w Net/tron Red/aden LN/al lc~Contact ReaNng Tochnhhn Romarkl:~a Cont.Area Qe w NRh Cont.Area e Raglan Area Q w NSh Rad.Ares l.o:lied High Rad.Area R.E.QfNNA STATfos~<<k Technician: Ca<<: 'Itrne: Setlel 0'a:/po<<er Mote: All readlno~ln Tnr/hr unlace othiWs noted.demr100ttm2 Sl Pumps CS Pum WcNe Holdup Tonk e 0 0 lo~ace~Aks Charging Pump Cootinq Fons Non-reqen Hs"0 07:30-10:50 All Areas (Clean}, Radiation Levels 0.8mR/hr Smears 250dpm Airborne Activi iodine=1E-11 uCi/cc Part.=1 E-1 0 uCi/cc Oo Spent Resin Tonk Room Sur Tank~~~Le EO o HO~4 I E~a I CtHt~i'ump Room~Smear Locatfon-x-x-e Rad/Cont.Barrfer~Radfatfon Level~Neutron Radlatlon Level Nc~Contact Readfng Technfcfan Remarka:~~Cont.Area 0~High Cont.Area~Radfatfon Area Q~~High Rad.Area 0~Locked High Rad, Area 10.1 METEOROLOGICAl DATA ROUTE M 1.M.3, M.S,M 8 To Greece Olymp>a H,S.: M8~K fern Ad, At.ROUTE M I, M-3.M.S.404~M.S.M9 pV D rc<><v Z Vl a C o.hh3 D Vl 0 Cl 0 O C 0 M I Tg M.3,M6 04 RO (f 000 Ad.~~p>rt':(I I 0, I Nl.>l.Ihl g-.Ma Z Vl I'L>I>Ir I rh Lake Rd.(S OOSIOI>Bd<v 4<r<I.Whinlev Rd Plank Ad.0 0 ul C 0 0 0>.DD o(c wi,r 40104~PNfhfilir'0<c I>1 Irttttryat tt 11 0 00(<v At 101 loAI.88 1 I I pin itvln<A<I rlsl lrvl Iv lhi~~<>m'1 I I~, I>~I I IIVI 5 W>If<an>son town I ne~pad<ter ftn Le~rl~cc l>r>>>fve>I I;<>>>l<v B<l~~'lr I-S-Allanhc Avo."W7 0 C<v C 0 C C 0 C 0 C (vv>S(>>>f\I~e~e b+0 O To Rt.390S and Lehi9h Stat>on Rd.and 4>>sh.Henrfeita H.S.r-~BOO~Rt.64 To Pg Piltsford. Mendon H.S.D IL'X I O IIII>PIIT Garnsey 4'>ulrlrLO Penf>eld Rd./AI.44~~Penfield Walwonh Rd.~ee ee~~~ee~~~~~~~ee~~~~e~~WALWI)AIII PAI I.IYBA MACAROON Patmyra/Macedon H.S.~Mal<i'<l I l H(deSv<e<I\d I lr>tinv.vrk H I>FIGURE 10.1-DIRECTION OF THE PLUME Meteorolo ical Conditions A.Basis The meteorological conditions for this scenario were based upon historical meteorological data recorded by the Ginna primary weather tower and the N tt I IN th 9 I~97 1993.Ilt dtd 9 9 I d the data to provide the wind direction and atmospheric stability conditions required by the scenario during the period of release.National Weather Service and other Exercise controllers will provide Exercise participants weather forecast summaries based on the meteorological data and other supporting information available from the historical record.The goal of this approach is to provide participants with more realistic forecast information. B.Scenario Assum tions The scenario begins with light, southerly winds which shift and become northeasterly by mid-morning. During the period of release (10:50-12:50 hr), the average meteorological conditions are as follows: Wind Speed=3mph(at33ft) Wind Direction=45 degrees (at 33 ft;wind from)Pasquill Stability=E TABLE 10.1 WEATHER FORECAST INFORMATION NOVEMBER 17, 1993 07:30 AM-3:00 PM LAKE ONTARIO FORECAST'ODAY:,SOUTHERLY WINDS WILL BE SHIFTING NORTHEASTERLY BY MID-MORNING. TEMPERATURES ARE EXPECTED IN THE MID 40'S.WINDS WILL REMAIN FROIVI THE NORTHEAST AT 5 MPH THROUGHOUT THE REMAINDER OF THE AFTERNOON. NOTE: SUPPLEMENTAL FORECAST INFORMATION TO BE PROVIDED BY NATIONAL WEATHER SERVICE CONTROLLER AT THE FOLLOWING TELEPHONE NUMBER.(716)328-7633 OR BY DESIGNATED NYS CONTROLLER IN ALBANY 11/17/93 07:00 RECORD NUMBER 1336 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A~TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN~3.5 MPH 2.9 MPH 4.4 MPH 4.8 MPH 5.6 MPH 321 DEG 321~DEG 323 DEG 325 DEG 322 DEG 44.4 F 44.3 F 44.0 F 43.8 F 43.8 F 43.7 F-0.6 F/-0.8 F/-0.6 F/-0.6 F/49.7 F 0.00 INCH 0.9 1.3 1.2 1.2 0.9 122 122 61 0.5 0.8 3.4 4,4 264 278 300 6.1 6.0 6.8 8.0 8.5 40 55 85 308 96 320 25 0 1.02 1.02 0.00 11/17/93 07:15 RECORD NUMBER 1337 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 5.0 MPH 4.8 MPH 6.3 MPH 7.8 MPH 7.4 MPH 320 DEG 313 DEG 311 DEG 312 DEG 322 DEG 44.2 F 44.2 F 43.6 F 43.6 F 43.4 F 43.3 F-0.8 F/F/-0.8 F/-1.2 F/49.7 F 0.00 INCH 0.8 3.5 6.8 0.9 0.6 2.8 4.0 6.7 7.4 0.6 6.3 10.2 0.4 6.4 8.0 287 328 8 284 5 300 4 306 335 328 325 4 315 333.0 0 0 1.02 1.02 0.00 11/17/93 07:30 RECORD NUMBER 1338 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 5.1 MPH 4.7 MPH 6.2 MPH 7.6 MPH 7.1 MPH 317 DEG 309 DEG 305 DEG 306 DEG 322 DEG 43.8 F 43.9 F 43.4 F 43.0 F 43.1 F 42.9 F-0.8 F/F/-0.7 F/-1.2 F/49.6 F 0.00 INCH 0.9 0.4 3.2 2.5 4.9 7.1 7.3 7.0 0.3 7.0-8.3 0.4 6.1 8.2 6 280 324 7 293 328 4 293 314 3 299 313 3 314 329 0 1.02 1.02 0.00 11/17/93 07:45 RECORD NUMBER 1339 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 5.0 MPH 4.7 MPH 6.1 MPH 7.3 MPH 7.6 MPH 322 DEG 321 DEG 312 DEG 312 DEG 330 DEG 44.0 F 43.9 F 43.2 F 42.8 F 43.0 F 42.9 F-1.2 F/-1.4 F/-1.0 F/-1.4 F/49.4 F 0.00 INCH 0.9 1.0 3.3 2.5 7.2 6.9 0.6 0.6 4.8 7.3 5.9~9.2 0.5 6.1 8.5 9 281 326 9 282 297 6 299 5 319 331 333 331 341 0 0 1.02 1.02 0.00 11/17/93 08:00 RECORD NUMBER 1340 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 5.7 MPH 5.3 MPH 6.9 MPH 8.1 MPH 8.8 MPH 339 DEG 320 DEG 320 DEG 320 DEG 333 DEG 43.5 F 43.6 F 42.6 F 42.3 F 42.4 F 42.4 F-1.2 F/-1.5 F/F/-1.6 F/49.2 F 0.00 INCH 1.0 1.2 1.0 2.8 2.4 4.4 7.7 7.4 9.7 0.9 14 67 5.9 10.3 6.8 11.1 286 356 290 10 8 299 339 302 309 334 354 0 0 0 1.02 1.02 0.00 11/17/93 08:15 RECORD NUMBER 1341 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A.l""'ER 33B,."~4 Y ERl5'OA':--'-'-. ,"..-;,.'TER'150B TER250A 7.1 MPH 6.7 MPH 8.4 MPH 9.8 MPH 9.5 MPH 321 DEG 320 DEG.315 DEG 315 DEG 327 DEG 42.9 F 42.9 F 41.8 F 42.0 F'2.0 F 0 0 0 0 0 0-"0" 0 0 1.4 1.5 3.1 2.0 9.5 9.3 1.2 1.2 1.0 25 47 5.7 11.3 6.9 12.9 7.2 11.8 93 344 288 18 293 346 295 349 13 298 358 TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 41.9 F F/-1.4 F/-0.9 F/-1.4 F/48.9 F 0.00 INCH 0 0 0 0 1.02 1.02 0.00 11/17/93 08:30 RECORD NUMBER 1342 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 6.4 MPH 6.1 MPH 7.3 MPH 8.5 MPH 10.1 MPH 343 DEG 342 DEG 321 DEG 320 DEG 342 DEG 42.6 F 42.7 F 42.2 F 41.9 F 42.7 F 42.6 F-0.8 F/-1.1 F/0.1 F/-0.5 F/48.6 F 0.00 INCH 1.2 3.5 2.0 8.9 8.7 1.2 1.3 1.0 13 12 13 12 4.7 10.7 6.0 12.6 7.7 12.1 285 346 291 347 293 348 300 346 9 320 358 0 1.02 1.02 0.00 11/17/93 08:45 RECORD NUMBER 1343 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 5.7 MPH 5.0 MPH 8.1 MPH 9.1 MPH 11.5 MPH 342 DEG 336 DEG 341 DEG 340 DEG 355 DEG 42.6 F 42.7 F 42.3 F 41.9 F 42.9 F 42.7 F-0.8 F/F/0.3 F/-0.4 F/48.4 F 0.00 INCH 1.2 2.3 9.0 1.6 1.5 1.3 1.3 0.9 8.0 4.4 11.4 6.1 12.3 8.7 13.6 77 288 17 98 10 37 184 303 308 311 330 358 0 1.02 1.02 0.00 11/17/93 09:00 RECORD NUMBER 1344 , GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 4.2 MPH 3.9 MPH 8.8 MPH 9.9 MPH 14.2 MPH 346 DEG 338 DEG 345 DEG 343 DEG 1 DEG 43.1 F 43.1 F 42.4 F 42.1 F 44.0 F 44.0 F-1.0 F/F/0.9 F/0.5 F/48.9 F 0.00 INCH 1.2 1.4 1.4 7.0 7.4 1.2 5.7 10.7 1.2 6.6 12.0 0.8 11.5 15.4 68 289, 36'48 284 47 6 330 5 323 356 351 192 352 0 1.02 1.02 0.00 GINNA PLANT 11/17/93 09:15 RECORD NUMBER 1345 SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT 4.2 MPH 4.0 MPH 9.2 MPH 10.1 MPH 5.3 MPH 356 DEG 344 DEG 340 DEG 338 DEG 357 DEG 43.3 F 43.4 F 43.5 F 42.3 F 43.9 F 43.9 F F/-1.4 F/0.6 F/0.1 F/48.9 F 0 1.3 3.5 9.2 1.5 1.3 1.3 1.7 2.1'.2 6.2 12.4 7.4 13.6 2.1 10.0 37 241 322 0 333 6 49 288 6 69 296 8 8 321 359 RAIN 0.00 INCH 0 1.02 1.02 0.00 11/17/93 09:30 RECORD NUMBER 1346 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 4.2 MPH 4.3 MPH 9.5 MPH 10.5 MPH 11.5 MPH 357 DEG 358 DEG 347 DEG 345 DEG 359 DEG 43.3 F 43.4 F 43.6 F 42.5 F 43.7 F 43.6 F-0.9 F/-1.2 F/0.4 F/0.1 F/49.3 F 0.00 INCH 1.5 1.7 1.3 1.3 1.2 2.8 11.3 2.1 10.0 6.7 11.9 7.3 12.8 8.1 13.4 100 305 144 37 37 313 323 325 20 280 332 0 1.02 1.02 0.00 11/17/93 09:45 RECORD NUMBER 1347 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A=-TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN I 3.7 MPH 4.3 MPH 10.4 MPH 11.2 MPH 12.4 MPH 8 DEG 4 DEG 356 DEG 354 DEG 9 DEG 43.5 F 43.6 F 43.9 F 42.7 F 44.0 F 44.0 F-1.2 F/-0.9 F/0.5 F/0.9 F/49.6 F 0.00 INCH 1.2 1.4 2.8 2.2 9.0 8.9 1.2 7.0 12.7 7.8 12.9 8 10.5 14.4 173 311 33 202 328 41 187 163 338 344 0 1.02 1.02 0.00 11/17/93 10:00 RECORD NUMBER 1348 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.5 MPH 3.6 MPH 6.2 MPH 6.4 MPH 5.9 MPH 17 DEG 7 DEG ll DEG 10 DEG 19 DEG 43.5 F 43.3 F 43.9 F 43.6 F 44.7 F 45.0 F 0.2 F/0.0 F/1.2 F/1.7 F/50.1 F 0.00 INCH 1.3 1.4 0.9 2.5 3.2 4.8 9.6 9.4 7.1 0.8 4.8 7.1 0.6 5.2 6.6 257 303 32 166 292 30 0~74 356 21 357 19 13 27 0 0 1.02 1.02 0.00 11/17/93 10:15 RECORD NUMBER 1349 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.3 MPH 3.5 MPH 3.5 MPH 3.7 MPH 3.6 MPH 24 DEG 27 DEG 31 DEG 30 DEG 29 DEG 43.1 F 42.9 F 43.2 F 43.7 F 45.0 F 45.0 F 0.8 F/0.5 F/F/1.6 F/50.2 F 0.00 INCH 0 1.2 0.9 1.0 1.0 0.5 257 2.4 2.7 3.0 3.3 3.3 303 4.8 4.5 6.4 6.6 6.2 32 166 292 64 356 74 357 4 13 30 41 39 37 0 1.02 1.02 0.00 11/17/93 10:30 RECORD NUMBER 1350 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.0 MPH 3.0 MPH 3-.0 MPH 3.2 MPH 3.2 MPH 41 DEG 42 DEG 40 DEG 42 DEG 40 DEG 42.8 F 42.6 F 43.2 F 43.8 F 43.3 F 43.1 F 0.3 F/0.3 F/0.5 F/0.5 F/50.4 F 0.00 INCH 1.2 0.6 0.4 0.6 2.7 2.5 2.7 2.7 2.7 5.2 4.7 6.6 6.8 7.0 90 355 36 358 15 23 31 51 52 51 51 50 0 0 1.02 1.02 0.00 11/17/93 10:45 RECORD NUMBER 1351 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.0 MPH 3.0 MPH 3.5 MPH 3.6 MPH 3.9 MPH 39 DEG 40 DEG 41 DEG 42 DEG 43 DEG 42.6 F 42.6 F 42.8 F 42.7 F 43.1 F 43.0 F 0.3 F/0.3 F/0.5 F/0.5 F/50.3 F 0.00 INCH 0.7 2.7 4.7 0.7 0.7 0.7 0.4 10 2.7 3.0 2.7 3.1 27 19 22 26 37 6.1 6.3 6.0 50 48 52 51 49 0 1.02 1.02 0.00 11/17/93 11:00 RECORD NUMBER 1352 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B.DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.0 MPH 3.0 MPH 3.0 MPH 3.1 MPH 3.3 MPH 38 DEG 39 DEG 39 DEG 41 DEG 38 DEG 42.9 F 42.8 F 42.8 F 42.5 F 44.0 F 43.8 F 0.7 F/0.7 F/F/1.1 F/50.3 F 0.00 INCH 0.5 0.4 0.6 0.4 0.3 2.3 2.2 2.0 2.8 2.9 23 20 27 33 4.5 4.6 6.1 6.2 5.6 47 49 53 54 41 0 1.02 1.02 0.00 11/17/93 11:15 RECORD NUMBER 1353 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.1 MPH 2.9 MPH 3.1 MPH 3.2 MPH 3.1 MPH 44 DEG 45 DEG 42 DEG 38 DEG 43 DEG 43.2 F 42.8 F 43.1 F 43.2 F 44.0 F 43.8 F 0.4 F/0.4 F/0.8 F/0.8 F/50.3 F 0.00 INCH 0 1.0 0.7 0.4 0.5 0.4 37 12 2.5 2.6 2.6 2.7 2.7 359 12 31 30 31 4.7 4.3 5.7 5.7 4.7 52 51 46 48 53 1.02 1.02 0.00 11/17/93 11:30 RECORD NUMBER 1354 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.0 MPH 2.9 MPH 3.5 MPH 3.6 MPH 3.4 MPH 38 DEG 39 DEG 39 DEG 42 DEG 38 DEG 43.1 F 43.2 F 42.9 F 42.8 F 43.8 F 43.8 F 0.3 F/0.3 F/0.7 F/0.7 F/50.5 F 0.00 INCH.0 0 0 1.0 1.7 4.0 1.0 1.8 3.6 0.8 0.7 1.5 2.6 2.0 3.2 356 37 34 28 5.2 5.2 5.5 49 48 58 58 66 1.02 1.02 0.00

11/17/93 11:45 RECORD NUMBER 1355 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.1 MPH 2.8 MPH 2.7 MPH 3.0 MPH 2.6 MPH 37 DEG 38 DEG 51 DEG 53 DEG 65 DEG 43.6 F 43.4 F 44.0 F 44.1 F 44.9 F 44.9 F 0.6 F/0.6 F/F/1.2 F/50.9 F 0.00 INCH 0.6 0.5 0.6 0.6 0.5 2.3 1.5 1.5 2.8 1.6 5.5 4.9 8.1 8.3 8.0 71 341 36 358 5 39 4 44 2 59 46 63 60 69 1.02 1.02 0.00 11/17/93 12:00 RECORD NUMBER 1356 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.1 MPH 3.1 MPH 3.2 MPH 3.4 MPH 3.3 MPH 35 DEG 35 DEG 54 DEG 54 DEG 67 DEG 43.9 F 43.6 F 44.3 F 43.9 F 45.2 F 45.8 F 0.8 F/0.7 F/F/1.4 F/51.6 F 0.00 INCH 0.5 0.5 2.2 1.7 4.7 4.0 0.5 0.5 0.6 101 2.0 2.1 2.1 324 6.4 6.8 6.5 36 353 42 45 62 46 61 71 0 0 1.02 1.02 0.00 11/17/93 12:15 RECORD NUMBER 1357 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.3 MPH 2.9 MPH 2.7 MPH 3.0 MPH 3.3 MPH 43 DEG 42 DEG 64 DEG 64 DEG 67 DEG 44.2 F 44.0 F 44.9 F 44.4 F 45.2 F 45.7 F 0.6 F/0.7 F/1.0 F/F/51.8 F 0.00 INCH 0 0.6 0.6 0.9 0.6 0.5 10, 1.9 1.5 2.3 2..6 2.0 13 45 43 4.5 3.9 6.4 6.5 5.7 51 57 78 77 75 0 1.02 1.02 0.00 11/17/93 12:30 RECORD NUMBER 1358 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B.DIR250 3.3 MPH 2.9 MPH 3.8 MPH 3.4 MPH 2.8 MPH 43 DEG 48 DEG 45 DEG 44 DEG 45 DEG 0 0.6 0.6 0.8 0.3 0.5 14 12 1.5 4.5 1.3 4.0 3.9 1.7 33 35 39 7.0 4.5 85 72 79 77 81 1.6'.1 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 44.6 F 44.6 F 45.3 F 45.7 F 45.5 F 45.5 F 0.5 F/0.6 F/0.9 F/1.0 F/52.3 F 0.00 INCH 0 0 1.02 1.02 0.00 11/17/93 12:45 RECORD NUMBER 1359 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.2 MPH 3.0 MPH 3.1 MPH 4.7 MPH 4.0 MPH 39 DEG 37 DEG 40 DEG 38 DEG 44 DEG 44.1 F 44.2 F 44.4 F 44.4 F 45.3 F 45.2 F 0.6 F/0.6 F/F/F/51.9 F 0.00 INCH 0 0 0.6-2.2 5.5 0.6 2.7 2.3 5.0 7.1 0.5 3.6'7.8 0.5 2.9 5.0 22 34 32 36 68 81 76 82 1.02 1.02 0.00 11/17/93 13:00 RECORD NUMBER 1360 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.2 MPH 2.7 MPH 3.6 MPH 3.7 MPH 3.0 MPH 40 DEG 37 DEG 78 DEG 78 DEG 81 DEG 44.8 F 44.9 F 45.5 F 45.5 F 45.7 F 45.7 F 0.6 F/0.5 F/0.9 F/1.0 F/52.3 F 0.00 INCH 0.4 1.9 4.0 0.4 1.7'.0 0 0 0.8 0.6 1.2 51 12 1.7 2.9 2.7 357 60 61 71 5.7 6.8 6.5 65 92 91 90 0 0 1.02 1.02 0.00 11/17/93 13:15 RECORD NUMBER 1361 GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD150A SPD150B SPD250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A TER 33B TER150A TER150B TER250A TER250B DT150-33A DT150-33B DT250-33A DT250-33B DEWPOINT RAIN 3.3 MPH 3.0 MPH 3.1 MPH 3.2 MPH 3.8 MPH 35 DEG 32 DEG 81 DEG 80 DEG 77 DEG 45.4 F 45.4 F 45.3 F 45.4 F 46.1 F 46.2 F 0.4 F/0.5 F/0.7 F/0.8 F/51.7 F 0.00 INCH 0

II q 1 s h 4 K'l 1)I'\C. TABLE 10.2 Plume Arrival&Departure Times Distance miles 0.5 1.0 2.0 3.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 12.0 Arrival 11:00 11:20 11:40 12:00 12:20 12:40 13:00 13:20 13:40 14:00 14:20 14:40 15:00~De arture 13:00 13:20 13:40 14:00 14:20 14:40 15:00 15:20 15:40 16:00 16:20 16:40 17:00 NOTES: " After indicated arrival time, refer to offsite radiological data shown on Table 10.3 as appropriate for zone of interest.'" After indicated departure time, all dose rates (mR/hr)will be background. For ground deposition readings, refer to post-plume radiological data shown on Tables 10.4 and 10.5 ~1 TABLE 10.3 RADIOLOGICAL SURVEY DATA (RG&E SURVEY TEAMS)CLOSED OPEN DOSIMETRY CLOSED WINDOW ON OPEN WINDOW ON INCREMENT IODINE PARTICULATE WINDOW, AT CONTACT WINDOW AT CONTACT EXPOSURE CARTRIDGE FILTER ZONE 3 FEET mR/hr mR/hr 3 FEET mR/hr mR/hr mREM CPM CPM A G 4.8E+03 2.2E+03 1.0E+03 4.7E+02 2.9E+02 1.9E+02 1.2E+02 8.6E+01 6.8E+01 4.8E+03 2.2E+03 1.0E+03 4.7E+02 2.9E+02 1.9E+02 1.2E+02.8.6E+01 6.8E+01 7.1E+03 3.3E+03 1.5E+03 6.9E+02 4.3E+02 2.8E+02 1.8E+02 1.3E+02 1.0E+02 7.1E+03 3.3E+03 1.5E+03 6.9E+02 4.3E+02 2.8E+02 1.8E+02 1.3E+02 1.0E+02 1.2E+03 5.6E+02 2.5E+02 1.2E+02 7.2E+01 4.7E+01 3.0E+01 2.2E+01 1.7E+01 6.1E+03 2.6E+03 1.2E+03 5.8E+02 3.7E+02 2.6E+02 1.8E+02 1.4E+02 1.2E+02 7.6E+02 3.6E+02 1.8E+02 1.1E+02 8.1E+01 6.7E+01 5.7E+01 5.2E+01 5.0E+01 NOTES: 1)Dose rate readings apply to Victoreen 450 dose rate instrument or equivalent. 2)Dosimeter incremental exposure assumes a 15-minute stay-time in the particular zone of interest.3)Air samples assume use of RADECO H-809C air sampler or equivalent. Volume assumed is approximately 180 liters (30 Ipm for 6 minutes), and field reading is with HP-260. 4 I 4 4 I 4~hW h h 4 4 4 I 1 4 4 4 4 4 TABLE 10.3 RADIOLOGICAL SURVEY DATA (COUNTY SURVEY TEAMS)CLOSED OPEN DOSIMETRY CLOSED WINDOW ON OPEN WINDOW ON INCREMENT IODINE PARTICULATE WINDOW AT CONTACT WINDOW AT CONTACT EXPOSURE CARTRIDGE FILTER ZONE 3 FEET mR/hr mR/hr 3 FEET mR/hr mR/hr mREM CPM CPM G 4.8E+03 2.2E+03 1.0E+03 4.7E+02 2.9E+02 1.9E+02 1.2E+02 8.6E+01 6.8E+01 4.8E+03 2.2E+03 1.0E+03 4.7E+02 2.9E+02 1.9E+02 1.2E+02 8.6E+01 6.8E+01 7.1E+03 3.3E+03 1.5E+03 6.9E+02 4.3E+02 2.8E+02 1.8E+02 1.3E+02 1.0E+02 7.1E+03 3.3E+03 1.5E+03 6.9E+02 4.3E+02 2.8E+02 1.8E+02 1.3E+02 1.0E+02 1.2E+03 5.6E+02 2.5E+02 1.2E+02 7.2E+01 4.7E+01 3.0E+01 2.2E+01 1.7E+01 9.6E+03 4.1E+03 1.9E+03 8.9E+02 5.6E+02 3.8E+02 2.6E+02 2.0E+02 1.6E+02 1.2E+03 5.5E+02 2.7E+02 1.5E+02 1.1E+02 8.3E+01 6.7E+01 6.0E+01 5.6E+01 NOTES: 1)Dose rate readings apply to Victoreen 450 dose rate instrument or equivalent. 2)Dosimeter incremental exposure assumes a 15-minute stay-time in the particular zone of interest.3)Air samples assume use of RADECO H-809C air sampler or equivalent. Volume assumed is approximately 10 cubic feet and field reading is with HP-260. Il"'7~'i@7'V 1'4'I 9)4 1 ('I TABLE 10.4 POST-PLUME RADIOLOGICAL SURVEY/SAMPLING DATA (FOR END WINDOW AND PANCAKE PROBES)POST-PLUME DECAY TIME=1.0 HOURS ZONE A B C D E F G H I 1 METER 2.3E+03 1.1E+03 4.9E+02 2.3E+02 1.4E+02 9.2E+01 5.9E+01 4.2E+01 3.3E+01 END WINDOW PROBE (CPM)1 CM 3.3E+04 1.5E+04 6.9E+03 3.2E+03 2.0E+03 1.3E+03 8.3E+02 6.0E+02 4.7E+02 1 METER 3.BE+03 1.BE+03 8.0E+02 3.7E+02 2.3E+02 1.5E+02 9.6E+01 6.9E+01 5.5E+01 PANCAKE PROBE (CPM)1 CM 5.0E+04 3.9E+04 1.7E+04 8.1E+03 5.0E+03 3.3E+03 2.1E+03 1.5E+03 1.2E+03 t 1 g I r I 1 4h l A n~w 1 t TABLE 10.5 GAMMA MICRO-R/HR READINGS DUE TO GROUND DEPOSITION POST-PLUME DECAY TIME=1.0 HOURS ZONE A B C D E F G H I@1 METER MICRO-R/HR 1.1E+03 5.0E+02 2.2E+02 1.0E+02 6.4E+01 4.2E+01 2.7E+01 1.9E+01 1.5E+01@1 CM MICRO-R/HR 1.8E+03 8.5E+02 3.8E+02 1.8E+02 1.1E+02 7.1E+01 4.6E+01 3.3E+01 2.6E+01 t'la gI/44 s<M P'k'4~I~~, q~)pe I 0"k<<")/t k j":.-)V)e b z bi~~t 5 i a$=Ot'l..k C~l f I jJ 4&<mW" gi~4 p VGV>>f/);i l sl I.V l 1,\.fl f~W,"" r-~i~Q l~g aj (K~k sg 4" I r 4 I. 'FlGURE 10.2 PLUME MAP.(0-0'll E)t t,CI~t~pffft~ted@~~~~t~lTT FDCt r--I~a LAat aoA l tttt suss TATIOH 104 Cl 0 R~I I R W Ct O R I a 0.S Slip. ~R I~t I'I II I+t~I g;.gcjt;:. s="" N I I E I I l/r Je J;I'.J I I~tt I I-~.~I>>'I t It'I t IN I~I 2fj/iE r/I E r t I J r r-'I'I r I I IŽ'I I I 15 MII~c.~N Rlyctee 8hrN I Figure 10.3 Plume Map 0-10 Mile 1 0.lVII ic cc III rcrc I~cccrteppeKcrc utah mrc'r iec Sttch Vee berth hnl hticli Feet re Le+et p'Llehcecc ~8etch/I)I../c h~<P Ccc P'Ki.'C/I wt I~c'I.c Pc n I:/I': U ro n n ee 8ren t.j;:,.I+~ev~tel~cce Ctnn per let/cclcclt We Web(~I IKK~tl~(P cf I/4.g reA<<I'//'QO IF%I Ice I I P/~I r"'-'//'.I hv I R Jl'v/~~I~~~~~ljce,~Well WII I AI Wlfcerct.Ihhhc I I~r'/rF c'eer ICP J rwr~Pnthh Qi(ct I h recto 0 M Ceccn htKO I\/(C COIPIPh/'V 5 heir~~1 I IQQ/I;MPP 0/I~0 i f r II r K OIPI 0 CI IJ Wl'CI~'Ih P, P i P.C.F)~'9,.x'-"A fik'AR S.'Q'~ 10.3 A/R SAMPLING DATA t p hh~r~Pt,I O'I~(s Q'J'I I J(A" f f.r-3R:.5 Ir i'l'IC!(h f 3Gt" PIC'(h.)0>>fi)~)fi3c." f-3'-o>ff 3~t'r'!Bi'..'"~&'.t!t h\Al'di ht ,h..'~~0'a8 Of->>'-'.>C i.->>-'IG~Ih f A/I"i r r".Jti t'.340.: 6 d Or 3.!GA'">GIRT%A) 3rUQ3>>if3V.IIH 5 l Ivt I'l-!<()"'!~Al GOfi'IGAR C'I Q j~.>>i'<~36t>'-.0.~'C:I)8 uJ 3V i*"..."6:: .'.'(!-3.o.0 P.O'"(4 2 h')0-"P'r I i(<,"r'l>Q P>I>>-';l.i>hfdf>'..r'I zhhl~i, y VO h-30',C.if~3vO,~;K'3C0.O J~lhri i tIC""~~-'n.3.".P~i'6(!-3f t"..Z~I,)'3 I Q 69,'V>>t CV 3r3o.'C'.>Q 3 g{' TABLE 10.6-A AIR PARTICULATE FILTER ISOTOPIC ACTIVITY SAMPLE COLLECTION DURING PLUME PHAS COUNTY TEAMS-10 CUBIC FT SAMPLE ZONE l-131 UCI/CC I-133 UCI/CC" I-135 UCI/CC CS-134 UCI/CC CS-137 UCI/CC BA-140 LA-140 UCI/CC UCI/CC A B C D E F G H I 2.23E-09 9.90E-10 4.43E-10 2.07E-10 1.27E-10 8.35E-1 1 5.33E-11 3.83E-11 3.02E-11 4.45E-09 1.98E-09 8.85E-10 4.13E-10 2.54E-10 1.67E-10 1.07E-10 7.66E-11 6.04E-11 4.03E-09 1.79E-09 8.01E-10 3.74E-10 2.30E-10 1.51E-10 9.65E-11 6.93E-11 5.47E-11 5.34E-10-2.45E-10 2.38E-10 1.09E-10 1;06E-10 4.87E-11 4.96E-1 1 2.27E-1 1 3.05E-11 1AOE-11 2.00E-11 9.18E-12 1.28E-11 5.86E-12 9.19E-12 4.21E-12 7.25E-12 3.32E-12 1.25E-11 5.54E-'I 2 2.48E-12 1.1 6E-'1 2 7.12E-13 4.68E-13 2.98E-13 2.14E-13 1.69E-13 1.25E-11 5.54E-12 2.48E-12 1.16E-12 7.12E-13 4.68E-13 2.98E-13 2.14E-13 1.69E-13 TABLE 10.6-8 SILVER ZEOLITE CARTRIDGE RADIOIODINE ISOTOPIC ACTIVITY SAMPLE COLLECTION DURING PLUME PHAS COUNTY TEAMS-10 CUBIC FT SAMPLE: ZONE I-131 I-132 I-133 I-134 I-135 UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC A B C D E F H S I 2.23E-07 9.90E-08 4.43E-OS 2.07E-08 1.27E-OS 8.35E-09 5.33E-09 3.83E-09 3.02E-09 3.21E-07 1.43E-07 6.37E-OS 2.98E-OS 1.83E-OS 1.20E-OS 7.67E-09 5.51E-09 4.35E-09 4.45E-07 1.98E.07 8.85E-08 4.13E-OS 2.54E-OS 1.67E-OS 1.07E-OS 7.66E-09 6.04E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.03E-07 1.79E-07 8.01E-OS 3.74E-OS 2.30E-OS 1.51E-OS 9.65E-09 6.93E-09 5.47E-09 i}}

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