ML17309A499

1992 Ginna Station Plume Exposure Emergency Preparedness Exercise 921008, Final Rev

ML17309A499
Person / Time
Site:	Ginna
Issue date:	10/08/1992
From:	BACKUS W H, POLFLEIT P S, WATTS R J ROCHESTER GAS & ELECTRIC CORP.
To:
References
NUDOCS 9210300061
Download: ML17309A499 (487)

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FORD 2 ri REGULAT INFORMATION DISTRIBUTION STEM (RIDS)ACCESSION NBR:9210300061 DOC.DATE: 92/10/08 NOTARIZED:

NO DOCKET FAClL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION POLFLEIT,P.S.

Rochester Gas 6 Electric Corp.BACKUS,W.H.

Rochester Gas&Electric Corp.WATTS,R.J.

Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

568/pe RECIPIENT COPIES ID CODE/NAME LTTR ENCL COPIES LTTR ENCL RECIPIENT ID CODE/NAME

SUBJECT:

"Rochester Gas a Electric Corp Ginna Station 1992 Plume Exposure Emergency Preparedness Exercise 921008." DISTRIBUTION CODE: DF01D COPIES RECEIVED:LTR ENCL SIZE: TITLE: Direct Flow Distribution:

50 Docket (PDR Avail)S/05000244 F-R INTERNAL: NUDOCS-ABSTRACT EXTERNAL: NRC PDR iC~c'dL t%q'g, REG FILE 01 NSIC YOTE TO ALL"RIDS" RECIPIENTS:

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)f V H 11 k ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION 1992 PLUIVIE EXPOSURE EIVIERGENCY 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 October, 1992 Emergency Preparedness Exercise.

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a>r lii,~'4-<, q~s4~M~Lw~4>il I~'!V I ILL h'IIJ~a, I~n THE ROCHESTER GAS AND ELECTRIC CORPORATION, GINNA STATION 1992 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 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" I ers" will n have rior knowled e of the na re of he im la ed in iden or an r hereof such as r diplo ical lume release informa ion includin times conten size and weather a rn 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.

1992 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE CENARIO" DEVELOPMENT COIVIIVIITTEE

" Wes Backus Richard Beldue Richard Biedenbach William Dillon Dan Hudnut James Knorr Frank Orienter Peter Polfleit Frank Puddu James Regan Richard Watts Terry White James Zulawski Dennis Behr (EEM)" As authorized by the Emergency Planning Milestone Committee 9flOfi', 5c!LO().

GINNA STATION 1992 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 INFORIVIATION 2.1 2.2 2.3 2.4 2.5 2.6 Exercise Participants Exercise Organization Emergency Response Facilities Exercise'Conduct Precautions and Limitations Evaluation and Critique 3.0 TRAVEL INFORMATION 3.1 Directions to Ginna Station 3.2 Directions to EOF, ESC and JENC 3.3 Accommodations

4.0 REFERENCES

ABBREVIATIONS-ACRONYIVIS 4.1 References 4.2 Abbreviations-Acronyms 5.0 CONTROLLER AND EVALUATOR INFORMATION 5.1 5.2 5.3 5.4 5,5 Controller Instructions Evaluation In'structions Personnel Assignments Evaluation Packages Public Information, Rumor Control 5 Spouse Questions Phone 6.0 SCHEDULE OF EVENTS GINNA STATION 1992 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 MESSAGE FORIVIS AND PLANT DATA SHEETS 9.0 ON-SITE RADIOLOGICAL AND CHEIVlISTRY DATA 9.1 Radiological Summary 9.2 In-Plant Radiation Data 9.3 Post-Accident Sampling Results 10.0 METEOROLOGICAL AND OFF-SITE RADIOLOGICAL DATA 10.1 Meteorological Data 10.2 Field Data and Maps 10.3 Field Air Isotopic Data GINNA STATION'1992 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 Assumed Source Term Air Ejector Concentrations 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)

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GINNA STATION 1992 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 Table 5.1 RG&E Onsite Controller Organization SECTION 7.0 Table 7.1 Simulator Set-up Data for Exercise Scenario Table 7.2 Simulator Set-up Data (Rad Monitor Readings)Table 7.3 Simulator Use Guidelines 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 (Gas)Post-Accident Reactor Coolant Samples (De-Gassed)

Boron, pH Continuous Air Monitor Readings (Auxiliary Bldg)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 Table 10.7 Forecast Information Plume Arrival/Departure Times Radiological Survey/Sampling Data (In Plume)Radiological Survey/Sampling Data (In Plume)Post-Plume Ground Survey Data (cpm)Post-Plume Micro-R/hr Data Air Sample Isotopic Analysis Data SECTION 1.0 SCOPE AND OBJECTIVES COPE AND NSITE OBJE TIVES-PLUME EXPOS RE PATHWAY$co~e The 1992 Emergency Preparedness Plume Exposuie Pathway Exercise 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 partial mobilization of state and local resources to adequately verify their capability to respond to an accident at the Ginna Nuclear Power Plant.Onsite Ob ec ives for the 19 2 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 (limited 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..Demonstrate the appropriate equipment and procedures for, the determination of ambient radiation levels.1-1 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 (i.e., 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.

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

1-2 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 preliminary short-term and long-term actions to support plant recovery.Demonstrate the proper use of back-up communications in the event of selected communications equipment malfunction.

Demonstrate the ability to mobilize principal portions of the licensee emergency organization on an off-hours, unannounced basis.~To b erformed s a mus erin drill durin November 1992.Demonstrate the ability to conduct a post-exercise critique which adequately characterizes licensee performance based upon controller and observer assessments.

Summar of Pro osed Ac ivities Table 1.1 provides a list of proposed RGRE activities.

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TABLE 1.1 1992 GINNA STATION EIVIERGENCY PREPAREDNESS EXERCISE PLUIVIE EXPOSURE PROPOSED ONSITE ACTIVITIES RGLE Notification of Agencies Call Up of Personnel Activate Organization Maintain Security Conduct Dose Assessment Protective Action Recommendations Operate Joint News Center Dispatch Field Survey Teams Obtain PASS Sample Actual Actual" Actual" Actual Actual Actual Actual Actual-3"" Actual Call up of personnel and facility activation will be performed in sequence.A separate, off-hours mustering drill will be conducted during the week of November 9, 1992.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.1-4 SI Nl ULATIONS 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 Actions involving ventilation of gas fumes from Screenhouse (e.g.breaking windows)shall be simulated.

o Security interrogation of suspected individuals shall be simulated.

No real employee or contractor names shall be communicated.

1-5 UMIVIARY F PR P SED F SITE ACTIVITIES It is anticipated that Wayne and Monroe Counties and New York State personnel will participate to perform the following minimum functions:

1.Command and Control 2.Dose Assessment 3.Joint New Center Staffing 4.Protective Action Decisionmaking 6.Communications 1-6 SECTION 2.0 EXERCISE INFORIVIATION 2.0 EXERCISE INFORMATION 2.1 Exerci e Par ici an s 2.1.1 The participants in the Exercise will include the following:

ROCHESTER GAS AND ELECTRIC CORPORATION A.Facili ies Mana emen and Su or 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.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 2-1 2.Monroe County 3.Other Supporting County Agencies 2-2 Exercise Or niza ion The organization for this Exercise will consist of the Exercise Coordinator, the Controllers, the Players and the Observers, as follows: The Exer is C r in r 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.lifidp I I d p t t 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 and motion aspects of the activity observed for post-Exercise use for implementing improvements.

2-3 n r llers will b i n ifie w rin r n I rin a in"C n r lier".wi h whi 2.2.3~PI~r 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 OilOs,~rv rs 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 iden ifi d b wearin arm bands r bad es.Federal a en ob rv rs will be iden ified b wearin arm bands or bad e wi h le erin statin"NRC" or"FEMA".Vi~Qiir 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.

Vi i ors will be identified b wearin arm bands or bad es sta in"Visi 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 RGRE Corporate Nuclear Emergency Planner (CNEP)no later than one week before the Exercise.2.3 Emer enc Res onse Facilities During the Exercise, special facilities must be activated to manage, assess and support emergency response.2-4

R 8cE FACILITIES The Rochester Gas and Electric Corporation Emergency R e s p o n s e Facilities are: A.Similator Control 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 Cen er 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.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.Join 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 RG5E 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 Exercise Conduct 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.

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 preve'nt 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.RGSE 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 Simulator Con rol Room OSC TEC ECF J C E~CEDC.0 lyL dd<<II 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 F I-dldl I<<I.T~d will acce he Exercise me s es as wri en.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 perso'nnel 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 an EOF rsonnel will c Exercise messa e s wri n.Th in nd r n i no o x lainwh asiuaionc uldno cc r or a t s hou h i 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 ers 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 1 i*i i i I d g y i<<.~lh n n n imrvmn h meohir nin rin h Ex r is n ubmi h m o the a ro riate Conr II r a he nclusion of he Exercise.2.5 Precau ions and Limlta ions 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.Sho Id n im rin h course of the on of hi Exercise n a al emer enc si uati n arise II ivi i s and communica ions related to he Ex reise 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.C.No pressurization of fire hoses, discharging of fire extinguishers, 2-10 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 exercise".

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.H.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.2.6 Evaluation and Criti ue The Exercise will be evaluated by Controllers/Observers who have 2-1 1 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 TRAVEL INFORMATION 3.0 TRAVEL INFORlVIATION This section of the Ginna Station Exercise Manual provides travel information to those individuals from RGSE, other u t i I i t i e s, local/State/Federal government, and/or other organizations who will participate/observe the Exercise.Permission for Visitors to observe the Exercise must be obtained from: Corporate Nuclear Emergency Planner Rochester Gas and Electric Corporation 49 East Avenue Rochester, NY 14649-0001.

3.1 Direc ions o GInna Nuclear Sta 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 Outer 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 Car 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 NOT TO SCALE 18 1b)Oa OH'I 0 Cldnk Rikb 35o~~Ne mZ Q g 0 ROCHESTER ROCHESTER-MONROE COUNTY AIRPORT 0 A 0 0 Z 10 N I ROCHESTER ANO VICINITY~~ewtasc>>~IOaaW

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4.0 REFERENCES

/ABBREVIATIONS

-ACRONYMS 4.1a.s.s References 10 CFR 50.47, 50.54, Appendix E 44 CFR 350.9 NUREG-0654/FEMA-REP-1, Rev.1, ri ria for Pr r i n n Evl in fRa iol i IEmren Re n Pin n Pr r ne in S o of Nuclear Power Pl n 4.1.10 4.1.11 RGRE 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 Wayne County Radiological Response Plan INPO Emergency Preparedness Drill and Exercise Manual 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 Abbreviation

-Acron ms C n'RC OSC OOS OOS PAG(s)PAR(s)PASS PIO PWR RCP RCS RHR RGRE 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 SECTION 5.0 CONTROLLER AND EVALUATOR INFORIVIATION 5.0 ONTROLLER AND EVAL ATOR INSTRU TIONS Each Controller and Evaluator should be familiar with the following:

a.The basic objectives of the Exercise.b.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 C n roller Ins ruc ions 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~n 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.'1.8 Some Players may insist that certain parts of the scenario are unrealistic.

The Lead Controllers have the sole authority to clarify any questions regarding scenario content.5.1 P9 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.5P2 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.

~gif-P I d lip g llyp f d expected.Any errors noted were not severe and could be corrected without undue labor or expense.~di-P I d dip g lly f ddl 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~~~Facili 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'ith 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 Eval ion P cka 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 News 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.1 The following personnel have been designated to act as Controllers during the 1992 Exercise activities (SEE ATTACHED LIST).5-6 POSITION CONTROLLER LIST Exercise Coordinator R.Beldue Control Room (Simulator)

D.Hudnut (Lead)J.O'oole T.White J.Zulawski Control Room (Real)D.Peterson Technical Support Center Lead T.Alexander Technical 8 Operations Assessment B.Zollner K.Masker Security R.Wood R.Teed Dose Assessment Health Physics 8 Chemistry P.Polfleit F.Puddu Communications 8 Data Flow S.Poulton Operations Support Center Lead J.Huff J.Knorr Fire D.Biedenbach M.Cavanaugh Operations W.Stiewe S.Carter POSITION.CONTROLLER LIST IBC T.Joachimczyk E.McGrattan Mechanical S.Meister E.Graus G.Gibaud J.Liese Electrical R.Yates R.Marriott Post Accident Sampling System M.Clifton TBD Survey Center Lead Red Team Blue Team Green Team Yellow Team Orange Team White Team Personnel Coordinator J.Schultz R.Mastrella J.Edler J.Mazzeo P.Phelan J.Grzybek D.Bryant M.E.Dangler Emergency Operations Facility Lead 8 Operations W.Backus Communications 8 Data Flow B.Stanfield POSITION CONTROLLER LIST Dose Assessment R.Watts N.Kiedrowski-Survey Team K.Hart M.Burgess-General Engineering Support Center J.Neis C.Anderson J.Bergstrom Joint Emergency News Center National Weather Service F.Orienter G.English 6-9 GINNA STATION 1992 EMERGENCY EXERCISE~PB~LI~l~FDRMATI~RII NOR CONTRDL ANO SPPEPH NE LLUUETIDHS FIIR 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 RG5E"Spouse Phone" will also be manned by the RGSE 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 ouu,~id 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~re~ed gggs~lon~wi h"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.5-10

~qh Ill Phil If<<l 2 I g llyf RGRE: h Elf C yR C<<IG~qh Il q I I I I dp<<p ldlld~Ah*Il 2 I I lg h"Rp Ph I h RGEEMdl Department.

5-11 GIN NA STATION 1992 EMERGENCY EXERCISE ATI ACHMENT 1 PU IID INFDNMIITIDN

~DUN Tl NN TIME 0930~This is from TV Station WWUV.We'e heard that there is an incident at the Ginna Nuclear Plant.Can you tell us what is happening?

~My husband's a Wayne County Sheriff's Deputy.He said he's heard that there's some sort of problem at the nuclear plant.~What is happening there?~How dangerous a situation is it?0915~This is from the Associated Press.I understand that you have an incident at the Ginna Nuclear Plant.What's going on up there?~How extensive is the problem?~Where did the trouble start in the plant?~Is it under control?~What's the status of the plant?~What kind of hazards are involved?~Have any workers been injured?~If so what is the extent of their injuries?~What are their names?~What are their job functions?

~Is the safety of the public threatened?

~At what time will you have a press conference?

~We'd like to send someone to the plant, for interviews and photos..Where do they go?5-12 0930~This is from TV Station WRRO.We have a report you have some serious problems at Ginna Station.Would you tell our listeners the story?~We heard the plant is reactor is no longer under control-is that true?~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?~Why are they in charge?~What emergency classification are you now under?~Was the reactor damaged?~Did you evacuate the site?~Why not?~Are you going to evacuate the public living by the plant?~Is the reactor under control?~Do you have a press conference scheduled?

~At what time?5-13 0945~What is happening at Ginna?~Is the plant still under your control?~Have the federal authorities been notified?~Which ones?~What will they be doing?~Has assistance been requested to deal with this crisis?~ls there any danger to the public?~What 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?

~I hear there is a toxic chemical spill, in addition to the radiation leak at the plant, what chemicals are leaking, what are the health effects of the chemicals and what impact will the spill have on the environment?

1000~I'e heard you declared an"Unusual Event" 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?5-14

~I work at the Fitzpatrick Plant.~I'm confused about what's going on at Ginna...is the leak a chemical or radiological leak to the atmosphere?

~Has the (chemical/radiation)leak stopped?~How much was released?~Do you need any help from us?1015~What is the significance of an"ALERT"?~How serious a problem is that?~Have government officials been called?~What will the Governor do?~What is RGRE doing?~What time did you declare the alert?~What conditions cause you to declare an alert?~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?~Is it poor management?

~Is it low quality aging equipment?

~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?

~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?5-1 5 1030~I heard that you declared a"Site Alert".~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?~ls the plant safe or in big trouble?1100~What does a"Site Area Emergency" mean?Doesn't that mean that no one can go near the plant for the next thousand years?~-Is this accident similar to the one you had in 1982?~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?

1115~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 tPe levels?~Are farmers supposed to take any action to protect their livestock?

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

1130~My father is in the Hill-Haven Nursing Home in Webster.~What will happen to him?~How long will this emergency last?5-16

~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?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?5-17

~This is from WRUS Radio in Syracuse.~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 toxic chemical spill and serious release of radiation, what can you tell us about how this came about?1230~I live in Webster on Schlegel Road.I'm worried about leaving my 3 dogs 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?~I'm Fred Ames from Perinton.I heard that radiation from Ginna might blow all the way down here.~What should I do about my vineyard and farm?~If my grapes and land get contaminated, who's going to pay me for my losses?5-18 1300~This is TV 25 in Toronto.Is it true that your G-e-e-na reactor is suffering a mishap and can you give us an update on 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?5-19 ATTA HMENT 2 ADMDS.DDSTEDL

~MESSAGE FOR INONROE COIONTY TIME 0930~Could you tell me about the problem at Ginna?I'm a Webster resident.~Is there a chemical or a radiation problem at Ginna?~Is the problem at Ginna or Nine Mile Unit II?~Is Ginna Station shut down because of an accident or something?

0945~I hear there's an emergency at the nuclear power plant.~What happened and how bad is it?~I'm of Radio Station WZZE.You'e on our"LIVE LINE" and could you tell our listeners what's happening 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 news?0950~Has any radiation or hazardous material 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?~Is there a release?~What's happening at the nuclear plant?5-20 1100~My son works at Xerox, he's there now.~How will he know about the Ginna problem?~Is he safe where he is?~Does RGRE 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?~Is there a security problem at Ginna?~Was there sabotage?~Is the plant under control?~What damage was done?~I heard there was an explosion and fire at Ginna which resulted in both a chemical release into the lake and a radioactive cloud being released over Webster and Penfield, what is really happening?

1110~I live on 22113 Salt Road in Webster.If there's an evacuation, I'm going to need help with my two infant twins.Can you help me?~How many nuclear plants are in the area?~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?

~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 5-21

~I live in Penfield, 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?1115~I live near the plant and heard there is an"ALERT", and then I heard it called something else...What's going on?~Are you checking the radiation levels outside?~Did Sad-Am Hussein's people do this?~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?~Is Cuomo or Bush sending help?~What's happening at the Ginna plant?~Is the plant burning out of control?~My neighbors are saying terrorists have blown up part of the Ginna plant.Is this true?~Has a State of Emergency been declared?~What should the public do to protect itself?1130~My wife and I are concerned because we haven't heard the sirens go off...we live over in Fairport.~Shouldn't we hear sirens now?~We don't think you county disaster people are being told everything by RGSE.I can't even get a straight answer on my monthly electric bill.What's really going on?~I don't trust the power plant people;they'd lie to save their own skins.~Do you have anybody checking on them?5-22

~Will the County Legislature look into this accident and stop Ginna from starting up again7~Who's going to pay for all the clean-up from this accident7~Should I close my restaurant due to the accident at Ginna Station?I'm over in Webster 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 evacuate7~I'm calling from California, I have family in Rochester....what's going on at your plant?~What's happening at Ginna?1200~I heard that at Ginna a disgruntled employee sabotaged the plant and that's what caused this accidentf Have they caught the person yet7~Has there been a radiation release7~What's happening to all the school kids in Webster 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 right7~What do I do7 I live on Dewitt Road near the Elementary School.~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?1230~I'm leaving now.Where do I go for temporary housing?I live on State Road near Route 250,~I'rn calling from Penfield.....has there been a release of radiation from Ginna7~I'm calling from Pennsylvania....l live 5 miles from Ginna.....can we return home tomorrow7~What's happening at Ginna?5-23

~I'm evacuating now.Which way is safe to travel7 We live next to the Wegman's on Holt Road.We need temporary housing.I'e got 4 kids with me.~I am supposed to leave but don't have a place to stay.Which school can I stay at?I live on Lake Road near Route 250.~How do I get there?~Who's going to pay my expenses7~Who do I call to get a check for my expenses7 1300~Is it true that the apples are now contaminated?

~Where are we supposed to get our groceries now?~We don't have any money or a car.How do we get away from the radiation 7~Where do we live and eat?~I live up on Five Mile Line Road by Plank Road.~I heard the accident at the Ginna Station is getting worse.~Are we gonna be moved out of our homes after this?~Why haven't you made the announcement on TV?~Are animals safe to be left outside.We live in Webster..~Can we leave the house?~Has there been an accident at Ginna7~What exactly has happened?~Does RG8cE have a plan for this kind of thing?~What about the County?5-24 GUMS~DETEDL~ME SAGE FOR WAYNE 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 Middle School in Ontario?~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 Wayne County declared a state of emergency?

~What is Wayne 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 Knickerbocker near the Ontario Water District plant....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 Ontario.~How are they going to be warned about the plant problem?~We live in Walworth...are we safe?~Are you going to block off the roads...my daughter needs to be able to drive back homel 5-25

~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 Ontario.~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?~We live in Marion...are we far enough away?~Is the plant under control now?~Will we lose our power because of the accident?~Is 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?~I'm calling from Consolidated Edison....could you give me some information about the event this morning at Ginna?1015~We'e lost our emergency information handbook and need one right away.Which Zone do we live in?~We live on Slocum Road near Kenyon Road-are we going to have to evacuate?We'e very close to Ginnal~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?5-26 1100~I have some milk goats out in our field...out on County Line Road by Berg 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 basementl~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 two miles east of the plant on Furnace Road.~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?~I figure with all the problems recently, some group's sabotaging all the nuke plants around here.~Have you captured the people involved?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?5-27

~How do we get checked for radiation?

My whole family is feeling nauseated and weak.~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 Freewill Elementary School.~Should I close my business due to the accident?Who will pay for the lost income?(The business is on Route 104 near County Line Road).1200~Are schools closing in Williamson...my kids are at the High School?~What are we supposed to do-we live on Route 21 in Williamson?

~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 Sodus?~Should Sodus residents leave their homes?~Is there a plan for nuclear emergencies?

~Is it finished?~Who wrote the plan and who approved it?~Is RG5E responsible for the accident that happened?5-28 j 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 Atana's Restaurant in Ontario.~I live in Macedon...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 Wayne ERPA Number 3 near the plant.~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.6 miles south 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?5-29 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 Lakeside 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 Boston Road.~I'm calling from Buffalo...l got my family out of our house in Ontario Center 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 east 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 willi~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?5-30 1400~How long will people who evacuate from Wayne 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 burn7~Are residents supposed to take potassium iodide7~If we can't get the potassium, can we take salt tablets7~What is happening at Ginna?~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?5-31 ATTACHMENT PRESS CORPS QUESTIONS~How bad a leak occurred?~What kind of leak was it-chemical or radiation?

~Where did it go?~Is the reactor stable and under control?~Is this plant similar Nine Mile Point?~Were any workers injured or contaminated?

~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?T~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 RGSE in terms of how decisions are made during this emergency.

For example 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?

5-32

~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?

~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?5-33

~After cleaning up the radioactive waste from this accident, where does it all get sent?Has RGRE significantly added to the State's low-level waste crisis?~Why doesn't RG&E distribute potassium iodide to the public?...do RGRE people get it?~How close have you come to a meltdown?~How do you know the extent of damage to the Ginna reactor?~What problems do you expect the contamination will cause with the apple farms in Wayne County?~What effect will the release of radioactivity have on Lake Ontario fish?~What is the difference between genetic effects of radiation and somatic effects?~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?5-34 ATTA HMENT 4"SPOUSE PHONE" QUESTIONS 0930 4 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?~Are the workers all okay?~Can I pick my wife up?If so, where do I meet her?0945~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.1015~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 a chemical accident at the plant, and that there's a security problem 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.1045~My father, Wesley Backus works in Operations at Ginna.~What's happening at the plant?~How bad is it?5-35

~Are the workers in danger?My father works around the back-up safety equipment.

~Are Ginna employees allowed to call home?~If he can, have Wesley Backus call home so I can stop worrying.1115~IVly.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?~How long will the emergency last?1130~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 Survey Center.Is everyone there now?~Will the workers have to stay at the plant?~I need to get through to the Technical Support Center to ask her what arrangements I should make concerning her kids at day care...since I'm at work.Her name is Barb Butler.1200~My father works at Ginna, and is there now, He works in the Training Center (Jim Huff).~Has there been a release?~Do they have the plant saboteur identified yet?~Can I drive to the plant and drop off some sandwiches for my father if he's got to stay overnight?

5-36 SECTION 6.0 SCHEDULE OF EVENTS EC ION 1 92 INNA PLUIVIE EXPOSURE PATHWAY EXER I E SCHED LE F EVENT DATE TIME PER ONNEL R P~ATIVITY 10/5 9-11 ALL (EOF)PLAYER BRIEFING 2-4 ALL (TSC)PLAYER BRIEFING 10/7 8-12 AS ASSIGNED CONTROLLER BRIEFING 1-4 NRC TEAIVl NRC TEAM , BADGING 5 BRIEFING 10/8 10/9 8-10 ALL CONTROLLERS 1992 EXERCISE PRE<RITIQUE MEETING 10-11 OPEN RGSE CORPORATE CRITIQUE 11-12 OPEN~CRmQUE 6-1 SECTION 7.0 EXERCISE SCENARIO GINNA STATION 1992 EMERGENCY PREPAREDNESS EXERCISE INITIAL CONDITIONS 1.The R.E.Ginna Nuclear Power Plant is operating at approximately 97%rated thermal power.The Plant has been operating at this power level continuously for approximately 150 days.2.The"A" Steam Generator (S/G)primary to secondary leak rate increased approximately 5 days ago to a calculated 60cc/min.At approximately 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> this morning the primary to secondary leak rate has again increased significantly as indicated by a substantial increase in radiation monitor R-15 (Air Ejector).Radiation monitor R-19 (S/G Blowdown)has also indicated an increase in activity.The Health Physics/Chemistry Department is in the process of analyzing samples to determine the calculated leak rate.3.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 /> (10/8/92 is provided in table 9.2 of scenario Section 9.3.Total activity is 2.56 microcuries/gram.

Chemistry Log Sheet, available from the Controller.

4.The Reactor Coolant System (RCS)total leakage is 0.361 GPM as of 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> this morning and has been increasing.

identified RCS Leakage is 0.073 GPM.5.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).6.The Primary Water Treatment Plant is secured for major maintenance that will take approximately 3 days.the 100,000 Gallon Outside Condensate Storage Tank is at 20%Level.A Demineralizer Trailer has been ordered and is scheduled to arrive at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> today.7.The House Heating Boiler is in service and Nuclear Steam is secured and held.7-2 GINNA STATION 1992 EMERGENCY PREPAREDNESS EXERCISE ONSITE SEQUENCE OF EVENTS APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION 0700 0715 0730 IJNUSUAL EVENT-00/1 5 00/00 00/1 5 Initial Conditions established Announcement to Commence Annual Emergency Exercise The Health Physics/Chemistry Department informs the Control Room that the"A" S/G calculated leak rate is approximately 450cc/min (i.e.,~0.125 gpm).ANTICIPATED RESULT Contr I R om Operators should begin performing the applicable actions of Operating Procedure 0-.6.10 (Plant Operations with Steam Generator Tube Leak Indication).

q,g~/g-Z.I)An orderly Plant shutdown should commence to be in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to be less than 350'F in the RCS within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> as required by Plant Technical Specification.

A~UI h Idh d I df d Ih E~PI 1-0,~Ginna Station Event Evaluation and Classification," EAL: Steam Generator Tube Rupture (SGTR);Steam Generator Tube Leakage).1 GPM as identified by sampling.Appropriate offsite notifications should be made per EPIP 1~5.If~UIE d I df pp*I Iffd minutes, a contingency message should be given out to declare it.7-3 APPROPRIATE SCENARIO TIME.TIME EVENT DE RIPTI N 0755 00/40 The"A" S/G ARV pops open and cannot be closed from the Control Room.ANTI IPATED RES LT~R'R Should send an Auxiliary Operator to the Steam Header Area to close the Isolation Valve on the"A" S/G ARV.Operators performing the applicable actions of 0-2.1.Tchnic ISu or C n r 0810 00/55 The Plant Manager, Operations Assessment Manager, and Duty Engineer should be manning the TSC for Offsite Communications Assistance per EPIP 1-5.The Auxiliary Operator sent to isolate the"A" S/G ARV reports to the Control Room that the LA-"-S/G ARV is Lisolated,abut he has noticed atsteam-leak on the"B" S/G t'ARV, between the ARV-and the ARV Isolation-Valve.--l ANTICIPATED RESULTS Con r I R om Should inform people manning the TSC of the"8" S/6 ARV Line steam leak.May request Auxiliary Operator to isolate the"B" S/G ARV.Operators performing the applicable actions of 0-2.1.Should inform the people manning the TSC of the"A" S/G ARV problem and isolation.

7-4 APPROPRIATE SCENARIO TIME TIME EVENT DES RIPTION T hni I n r 0815 May request that the"B" S/G ARV be isolated or may wait until Maintenance personnel have inspected it.May inform Control Room that they will take actions to have Maintenance personnel inspect for the"A" And"B" S/G ARV problems.01/00 Annunciator G-22 (ADFCS System Trouble)alarms.ANTICIPATED RESULT n rol Room Operators perform the applicable actions of AR-G.22.Operators should check the S/G levels to ensure proper level control.0840 Operators should inform the people manning the TSC and I 5 C Department of the ADFCS problem.01/25 The CCW Surge Tank Lo Level Alarm (AR-A-13)annunciates and the CCW level indicates it is decreasing.

ANTICIPATED RESULTS~R'R Operators perform the applicable actions of Alarm Response Procedure AR-A-13 (CCW Surge Tank Lo Level 41.2%).Operators should send an Auxiliary Operator into the Auxiliary Building to identify the CCW Leak.Should inform the people manning the TSC of the CCW leak.7-5 APPROPRIATE SCENARIO TIME TIME EVENT DE RIPTI N 0850 01/35 Auxiliary Operator checking the CCW leak in Auxiliary Building informs Control Room that the 1A CCW Pump Mechanical Seal is leaking and spraying on the pump motor.The running 1A CCW Pump trips out on overcurrent and annunciator (AR-A-17)alarms.The standby 1B CCW'ump starts automatically and deliverers required flow.ANTICIPATED RE LT Con rol Room Operators perform the applicable actions of abnormal procedure AP-CCW.2 (Loss of CCW during power operation).

Operators request the Auxiliary Operator sent to identify the CCW leak in the Auxiliary Building, to isolate the suction and discharge of the 1A CCW Pump and rack out its electrical breaker.0855 01/40 Operators should inform the people manning the TSC of the 1A CCW Pump problems.The ADFCS problem with the MFW Regulating Valves is repaired..

ANTICIPATED RESULTS C nrolR om 0905 01/45 Operators continue shutting Plant down per 0-2.1 Auxiliary Operator isolating the 1A CCW Pump informs Control Room that the Suction and Discharge Valves are closed and the electrical breaker is racked out.ANTICIPATED RESULTS nrlR m Operators should ensure that 1A CCW Pump Control Switch is in pull stop and CCW Surge Tank level has returned to normal.7-6 APPROPRIATE SCENARIO TIIVIE TIME EVENT DES RIPTI N 0915 02/00 The following events occur simultaneously:

ALERT~Pressurizer level and pressure decreases uncontrollably.

~A reactor trip occurs automatically from low pressurizer pressure gr is manually activated by the operator.~A safety injection occurs automatically from low pressurizer pressure gr is manually activated by the operator.~The"A" S/G water level increases uncontrollably.

~All safeguards equipment required is operating.

ANTICIPATED RESULTS C nr IR om Operators performing the immediate actions of E-0 (Reactor trip or safety injection).

~'l<)P An ALERT should be declared in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification," EAL: Steam Generator Tube Rupture (SGTR): SGTR)100 GPM.Appropriate onsite and offsite notifications should be made per EPIP 1-5~If and ALERT is not declared in approximately 15 minutes, a contingency message should be given out to declare it.Operators transition to E-3 (Steam Generator Tube Rupture)and start performing.its applicable actions.7-7 APPROPRIATE SCENARIO TIME TIME EVENT DE CRIPTION 0945 02/30 Accident Response and Evaluation continues.

ANTICIPATED RE ULT~RI R Operators performing the applicable actions of E-3 (Steam Generator Tube Rupture)to stabilize the Plant.Techni al S Cen r The TSC should be nearing operational readiness of the Emergency Response Organization.

The TSC, when operational, should send repair teams into the Auxiliary Building to evaluate the 1A CCW Pump and motor problems.The TSC, when operational should send repair teams out to evaluate the"A" and"B" S/G ARV problems if not already done.Emer nc 0 er i n F ili JENC EOF may be activating at this time due to Plant conditions.

JENC will be activating at this time, 1000 02/45 Accident response and evaluation continues and DI truck arrives at site.ANTICIPATED RESULTS nr IRo m Operators performing the applicable actions of E-3 (Steam Generator Tube Rupture)to stabilize the Plant.Technical Su or Cen er The TSC should be assuming command and control.7-8.

APPROPRIATE SCENARIO TIIVIE TIME EVENT DE RIPTI N 1015 03/00 Annunciator J-9 (Safeguard Breaker Trip)Alarms.ANTICIPATED RE LT ontrol Ro m When operators check the Board, the"A" SW Pump Switch indicates a white disagreement light and the"A" SW Pump indicates tripped.1030 SITE AREA EMERGEN Y 03/1 5 Operators/TSC should send an Auxiliary Operator to the Screen House to check on"A"'SW pump.Operators should inform the TSC of the"A" SW Pump problem.The Auxiliary Operator sent to the Screen House to check the"A" SW Pump reports to the Control Room/TSC that he can find nothing wrong with the"A" SW Pump but he has smelled the strong odor of gas through-out the building with the strongest odor in the Basement.ANTI IPATED RES LTS Con rol Room Should request that the Auxiliary Operator find the shutoff valves for the natural gas and propane gas to the Screen House and close them.Should inform the TSC of the gas problem in the Screen House.If not already isolated, should send an Axiliary Operator to isolate the"B" S/G ARV when requested to do.Te hnic I u o n r The TSC, after assessing Plant conditions, should: 7-9 APPROPRIATE SCENARIO TIME TIME EVENT DE RIPTI N Declare a SITE AREA EMER EN Y in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification," EAL: Hazards being experienced or projected; entry of uncontrolled flammable gases into vital areas.Appropriate notifications of offsite agencies should be made per EPIP 1-5.If a Site Area Emergency is not declared in approximately 15 minutes, a contingency message should be given to declare it.TSC should inform the EOF of Plant conditions and the Site Area Emergency Declaration.

A Site Evacuation should be commenced if it is determined necessary.

Re air Teams Repair team sent out to check the CCW Pump should report that the 1A CCW Pump Mechanical seal needs replacing and that the 1A CCW Pump motor needs to be cleaned and dried.They report this will take approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.They also report that the 1B CCW Pump Mechanical Seal is leaking a small amount.Repair Team sent out to check the"A" S/G ARV control problem should report that the ARV's Mercoid controller needs to be replaced.They report that it will take approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to do.1045 03/30 If not done earlier, the Repair Team sent out to check the"8" S/G ARV Steam leak request that it be isolated.Accident response and evaluation continues.

If not done earlier, the Auxiliary operator sent out to isolate the"B" S/G ARV steam leak reports back that it is isolated.7-10 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTI N ANTICIPATED RESULT on roi Room Operators performing the actions of E-3 (Steam Generator Tub Rupture)should have stabilized the Plant at approximately this time and be awaiting determination by the TSC as to what post SGTR cooldown procedure to use.If not done earlier, should inform the TSC of the"B" S/G ARV steam leak isolation.

T hni aIS r n r The TSC should be evaluating the flammable gas problem in the Screen House and be taking corrective actions required to return the Screen House to a safe condition (i.e., sending a Fire and Safety Team to evaluate and correct).TSC Dose Assessment performing offsite dose calculations as necessary.

TSC should inform CR to use ES-3.1 (POST-SGTR Cooldown using backfill).

R air Teams Repair Team sent out to check the"B" S/G ARV steam leak reports that it appears that the steam leak was from a 0.5-inch hole drilled almost through the pipe, and also that a flange is leaking.They report that it will take approximately one and a half hours to repair the leak.7-11 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTI N 1100 03/45 Condensate Storage Tank (CST)levels decrease to 5 feet.ANTI IPATED RE LT on rolR om Operators should refer to ER-AFW.1 (Alternate Water Supply to AFW Pumps)per foldout page of ES-3.1, Statement 4, which states,"If CST level decreases to less than 5 feet,~hn switch to alternate AFW supply (Refer to ER-AFW.1, Alternate Water Supply to AFW Pumps)and perform applicable actions.Should inform TSC of the low level in the CSTs.TECHNICAL SUPP RT CENTER TSC evaluating Plant conditions and taking action where required.TSC should inform security of the as found condition of the"B" S/G ARV steam leak.TSC Dose Assessment performing offsite dose calculations as required.TSC should be expediting the repair of the S/G ARVs because of their use during such events as loss of condenser and Plant cooldown.TSC should send a Repair Team to check out the"A" SW Pump problem when the Screen House is declared safe for entry.TSC should inform EOF of Plant status and problems.~S~uri y Should be evaluating the drilled hole in the"B" S/G ARV pipe.Emer enc 0 era ion F cili The EOF, after it is manned, should start assessing Plant conditions and take action as required.7-12 APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION 1115 04/00 Dl truck starts pumping to outside storage tank.1120 04/05 The"A" S/G ARV Mercoid is repaired and ready for return to service.ANTICIPATED RE LTS nr IRo m Operators performing applicable actions of ES-3.1 (Post-SGTR Cooldown using Backfill).

Operators performing applicable actions ER-AFW.1.Operators should return the"A" S/G ARV to service if requested by the TSC.T chni I S C nter TSC evaluating Plant conditions and taking actions where required.TSC Dose Assessment performing offsite dose calculations as required.TSC may request the Control Room to return the"A" S/G ARV to service.~Securi Should be evaluating the drilled hole in the"B" S/G ARV pipe.Em r enc r ion F cili The EOF, after it is manned, should start assessing Plant conditions and take action as required.EOF Dose Assessment should be performing offsite Dose Assessment, as required, in parallel with the TSC Dose Assessment.

The EOF should be assuming commanded and control at approximately this time.7-13 APPROPRIATE SCENARIO TIME TIME EVENT DES RIPTI N R irT Performing actions as required to return equipment to service as soon as possible.1145 04/30 Accident evaluation and response continues.

An individual arrives at the TSC and during frisking, finds contamination on his shoes and clothing.,The Rochester Telephone Corp.telephones in the EOF are suddenly found to be inoperable.

ANTICIPATED RESULTS~R'R Operators should be performing the applicable actions of the ES-3.1 (Post-SGTR Cooldown using Backfill).

T chnic I o Cner TSC evaluating Plant conditions and taking action as required.EOF evaluating Plant conditions and taking action as required.TSC should request Control Room to return the"B" S/G ARV to service.Health Physics technicians respond to the contaminated individual at the TSC entrance, perform further contamination monitoring, secure the TSC entrance and initiate appropriate decontamination and follow-up actions.Em r enc 0 er ion Fa ilit EOF personnel investigate nature of telephone system failure, and switch to alternate telephones for voice and fax communications.

7-14 APPROPRIATE SCENARIO TIME TIME EVENT DES RIPTION~1230 M 05/15 Recover/Re-entry discussions should commence.This should include preliminary discussions about short term and intermediate term concerns, including preliminary designation of the Recovery Organization.

State arid counties may also conduct parallel discussions.

Recovery/Re-entry interface between TSC/EOF and offsite agencies should be demonstrated as time allows.~1315~06/00 After all Exercise Objectives have been demonstrated, the Exercise will be terminated.

7-15 U

TABLE 7.1 SIMULATOR SET-UP DATA FOR EXERCISE SCENARIO RITI AL IM LAT R ET-P DATA F R 1 2 ME EN Y PLANNIN IM LAT R 1.At QQQ Equipment Set-up-See 0700 Plant Status sheet.2.At Q7QQ Reactor Core is in IVIOL (571 PPM Boron).3.At Q7QQ RCS Leak Rate is 0.361 GPM.4.At Q7QQ"A" S/G Primary to Secondary Leak Rate is approximately 450cc/min (0.125 gpm).5.At g)~7 R-15 on Alarm and Reading approximately 4.6 x 10'pm.6.At Q7QQ HP/Chemistry Reports to the Control Room that the"A" S/G calculated primary to secondary Leak Rate is 450cc/min (i.e., 0.125 GPM).7.At~Q7M Operators start shutting the Plant down in accordance with the 0-6.10 and 0-2.1 at 10%/hr for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and then at 20%/hr for the rest of the shutdown.8.A IL7&~IE h Id b d I d, IR G<<T b Leakage>0.1 GPIVI as identified by sampling).

9.At Q7~the"A" S/G ARV pops full open and cannot be closed from the Control Room.10.At Q5~1 the"A" S/G ARV Isolation Valve is closed.11.At QQ~the"B" S/G ARV is reported to have a steam leak.~N: Isolation of the"B" S/G ARV can occur at any time from now on.12.At Q9~1 Annunciator G-22 (ADFCS System Trouble)Alarms.13.At Qggg CCW System leak of 20 GPIVl starts.14.At Qg~the CCW Surge Tank Lo Level Alarm (A-13)annunciates and the CCW level indicates it is decreasing.

15.At QQ~the ADFCS Problem is Repaired.16.At 93~the 1A CCW Pump Suction and Discharge Valves are closed isolating the leak.The Electrical Breaker is racked out also.17.At Q91'j the"A" S/G sustains a tube rupture of approximately 700 GPM.7-/7 AL IM LAT R ET-P A F EMER EN Y PLANNIN IM LAT R R N (continued) 18.At~9939, an alert should be declared.(S/G Tube rupture>100 GPM)19.At~1QQ, Dl truck arrives on Site.20.At QQ1 the"A" SW Pump trips out-Annunciator (J-9)alarms.21.At~1', a natural gas leak in the Screen House is reported by Auxiliary Operator sent out to check the"A" SW Pump.22.At 1/1)Outside Storage Tank Empty as Reported by Auxiliary Operator.23.At~~1~4 a i Ar Em r n should be declared (entry of uncontrolled flammable gases into vital areas).~24, At 11QQ, the CST levels decrease below 5 feet.26.At~111 Mobile Dl truck starts pumping water to DST 26.At 112lt the"A" S/G ARV Mercoid is repaired.27.At~I14 the"B" S/G ARV steam leak is repaired.28.At~~1~1 the Exercise is terminated.

TABLE 7,2 SIMULATOR SET-UP DATA FOR EXERCISE SCENARIO RADIOLOGICAL AND METEOROLOGICAL DATA 92EX.XLS 0 SPEED 33 DIR 33 TEMP 33 SPEED 150 DIR 150 TEMP 150 DT150-33 SPEED 250 DIR 250 TEMP 250 DELTA TEMP 7'00 3.7 209 52.9 4.7 174 53.3 0.4 6.1 188 55.4 2.5 7:15 3.8 193 52.9 4.8 184 53.3 0.4 7.2~188 55.5 2.6 7:30 3.6 202 53 4.5 174 53.4 0.4 7.1 158 55.5 2.5 7:45 3.8 215 53.5 4.8 201 53.5 7.2 158 55.6 2.1 8:00 3.6 222 57.7 4.7 202 57.9 0.2 7.1 168 58 0.3 8:15 3.6 194 58.7 4.5 174 58.1-0.6 7.1 158 58-0.7 8:30 2.6 47 59.6 3.7 65 58.8-0.8 3.5 64 58.9-0.7 8:45 3.8 79 59.8 85 59.4-0.4 7.7 79 59-0.8 9:00 3.1 52 59.9 5.2 55 59.9 9.5 57 59.3-0.6 9:15 3.8 50 60.7 4.9 52 60.7 7.5 54 60.7 R02 R04 R07 R09 R15 R19 R34 R31 R32 R15A5 R15A6 R15A7 R15A9 6.40E+00 6.40E+00 6.40E+00 4.40E+00 4.40E+00 4.40E+00 6.40E+00 6.40E+00 6.40E+00 3.40E+01 3.40E+01 3.40E+01 4.66E+04 8.75E+04 1.25E+05 4.07E+03 4.07E+03 4.07E+03 9.90E-01 9.90E-01 9.90E-01 1.02E-02 1.02E-02 1.02E-02 1.01E-02 1.01E-02 1.01E-02 2.33E-03 4 40E-03 6.29E-03 4.32E-02 4.32E-02 4.32E-02 2.33E-03 4 40E-03 6.29E-03 2.33E-03 4.40E-03 6.29E-03 6.40E+00 4.40E+00 6.40E+00 3.40E+01 1.25E+05 4.07E+03 9.90E-01 1.02E-02 1.01E-02 6.29E-03 4.32E-02 6.29E-03 6.29E-03 6.40E+00 6.40E+00 4.40E+00 4.40E+00 6.40E+00 6.40E+00 3.40E+01 3.40E+01 1.25E+05 1.25E+05 4.07E+03 4.07E+03 9.90E-01 9.90E-01 1.02E-02 1.02E-02 1.01E-02 1.01E-02 6.29E-03 6.29E-03 4.32E-02 4.32E-02 6.29E-03 6.29E-03 6.29E-03 6.29E-03 6.40E+00 4.40E+00 6.40E+00 3.40E+01 1.25E+05 4.07E+03 9.90E-01 1.02E-02 1.01E-02 6.29E-03 4.32E-02 6.29E-03 6.29E-03.6.40E+00 6.40E+00 6.40E+00 4.40E+00 4.40E+00 2.30E+01 6.40E+00 6.40E+00 6.40E+00 3.40E+01 3.40E+01 1.48E+02 1.25E+05 1.25E+05 9.99E+06 4.07E+03 4.07E+03 1.57E+04 9.90E-01 9.90E-01 9.00E-01 1.02E-02 1.02E-02 3.02E+00 1.01E-02 1.01E-02 1.01E-02 6.29E-03 6.29E-03 9.99E43 4.32E-02 4.32E-02 8.00E-01 6.29E-03 6.29E-03 1.85E+00 6.29E-03 6.29E-03 1.85E+00 JOT, 5LOA=LOScym av 6 V'LOS=lV1 cpm 4 cV<1f Q ag.Page 1 92.XLS TIME SPEED 33 DIR 33 TEMP 33 SPEED 150 DIR 150 TEMP 150 DT 150-33 SPEED 250 DIR 250 TEMP 250 DELTA TEMP 9:35 9'45 4.9 49 61.3 4.8 55 62 0.7 6.9 54 61.3 9:55 10:00 55 61.3 5.2 61 62.5 1.2 6.1 69 61.4 0.1 10:15 4.9 80 61.3 4.8 72 62 0.7 6.6 77 63.3 10:30 4.8 80 61.3 7.9 86 62.2 0.9 7.8 89 63 1.7 10:45 5.2 79 61.4 5.5 79 62.5 5.1 77 63.5 2.1 11:00 4.8 79 62.4 2.8 79 63.3 0.9 5.1 77 64.9 2.5 11:15 80 62.5 5.1 81 62.5 6.8 69 2.4 11:30 5.6 79 62.7 79 63.9 1.2 6.5 78 2.1 R02 R04 R07 R09 R15 R19 R34 R31 R32 R15A5 R15A6 R15A7 R15A9 7.35E+00 2.30E+01 7.35E+00 1.48E+02 4.41E+06 9.00E-01 9.99E-03 2.00E-01 2.20E-01 2.20E-01 7.35E+00 7.35E+00 7.35E+00 2.30E+01 2.30E+01 2.30E+01 7.35E+00 7.35E+00 7.35E+00 1.48E+02 1.48E+02 1.48E+02 4.41E+06 1.58E+03 1.58E+03 1.57E+04 1.57E+04 1.57E+04 9.00E-01 9.00E-01 9.00E-01 3.02E+00 3.02E+00 3.02E+00 1.01E-02 1.01E-02 1.01E-02 9.99E-03 2.09E-07 2.09E-07 2.00E-01 2.00E-01 2.00E-01 2.20E-01 1.30E-05 1.30E-05 2.20E-01 1.27E-03 1.27E-03 7.35E+00 2.25E+01 7.35E+00 1.46E+02 1.58E+03 1.52E+04 9.00E-01 2.90E+00 1.01E-02 2.09E-07 2.00E-01 1.30E-05 1.27E-03 7.35E+00 7.35E+00 2.18E+01 2.13E+01 7.35E+00 7.35E+00 1.43E+02 1.41E+02 1.58E+03 1.58E+03 1.47E+04 1.42E+04 9.00E-01 9.00E-01 2.85E+00 2.72E+00 1.01E-02 1.01E-02 2.09E-07 2.09E-07 2.00E-01 2.00E-01 1.30E-05 1.30E-05 1.27E-03 1.27E-03 7.35E+00 7.35E+00 2.07E+01 2.01E+01 7.35E+00 7.35E+00 1.38E+02 1.36E+02 1.58E+03 1.58E+03 1.38E+04 1.32E+04 9.00E-01 9.00E-01 2.68E+00 2.50E+00 1.01E-02 1.01E-02 2.09E-07 2.09E-07 2.00E-01 2.00E-01 1.30E-05 1.30E-05 1.27E-03 1.27E-03 7.35E+00 1.95E+01 7.35E+00 1.34E+02 1.58E+03 1.28E+04 9.00E-01 2.50E+00 1.01E-02 2.09E-07 2.00E-01 1.30E-05 1.27E-03 Page 2 92.LS TIME SPEED 33 DIR 33 TEMP 33 SPEED 150 DIR 150 TEMP 150 DT 150-33 SPEED 250 DIR 250 TEMP 250 DELTA TEMP 11:45 6.2 76 65 6.6 77 65.3 0.3 7.2 70 66.8 1.8 12:00 6.1 77 65.1 6.5 78 65.3 0.2 71 66.8 1.7 12:15 6.5 77 66 6.7 79 66.3 0.3 7.4 79 67.8 1.8 12:30 8.5 67 69 7.7 69 66.3-2.7 7.4 69 67.8-1.2 12:45 8.7 65 66 7.9 62 66.3 0.3 7.9 66 67.8 1.8 1:00 1:15 1:30 1:45 2:00 R02 R04 R07 R09 R15 R19 R34 R31 R32 R15A5 R15A6 R15A7 R15A9 7.35E+00 1.89E+01 7.35E+00 1.32E+02 1.58E+03 1.28E+04 9.00E-01 2.42E+00 1.01E-02 2.09E-07 2.00E-01 1.30E-05 1.27E-03 7.35E+00 1.84E+01 7.35E+00 1.29E+02 1.58E+03 1.19E+04 9.00E-01 2.33E+00 1.01E-02 2.09E-07 2.00E-01 1.30E-05 1.27E-03 7.35E+00 7.35E+00 7.35E+00 1.78E+01 1.72E+01 1.65E+01 7.35E+00 7.35E+00 7.35E+00 1.27E+02 1.24E+02 1.22E+02 1.58E+03 1.58E+03 1.58E+03 1.14E+04 1.09E+04 1.02E+04 9.00E-01 9.00E-01 9.00E-01 2.25E+00 2.18E+00 2.16E+00 1.01E-02 1.01E-02 1.01E-02 2.09E-07 2.09E-07 2.09E-07 2.00E-01 2.00E-01 2.00E-01 1.30E-05 1.30E-05 1.30E-05 1.27E-03 1.27E-03 1.27E-03 7.35E+00 1.60E+01 7.35E+00 1.20E+02 1.58E+03 9.90E+03 9.00E-01 1.93E+00 1.01E-02 2.09E-07 2.00E-01 1.30E-05 1.27E-03'.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 1.58E+03 1.58E+03 1.58E+03 1.50E+04 1.50E+04 1.50E+04 9.00E-01 9.00E-01 9.00E-01 1.87E+00 1.01E-02 1.01E-02 1.01E-02 2.09E-07 2.09E-07 2.09E-07 2.00E-01 2.00E-01 2.00E-01 1.30E-05 1.30E-05 1.30E-05 1.27E-03 1.27E-03 1.27E-03 7.35E+00 7.35E+00 1.58E+03 1.50E+04 9.00E-01 1.01E-02 2.09E-07 2.00E-01 1.30E-05 1.27E-03 Page 3 TABLE 7.3 SIMULATOR USE GUIDELINES 7-2 3 TABLE 7.IM LAT R PREPARATI N AND E IDELINE 2 Days Prior Test Fax Check batteries in headsets TSC Sim Lead 1 Day Prior Check EPIP Attachment Supply in Procedure Cabinet Radios for Sim (5)Sim Lead Sim Lead/CNEP Exercise Day Turnover Transfer REGS, NRC phones Transfer page Check PPCS printer (ON)Disable load dispatch phone Switch over PPCS/SAS per EPIP 5-5 788 Prefix Load dispatch¹Sim OOC Equipment Operations Supervisor

/Present Operations Manager*/Present HP/STA location for notification Sim Lead Sim Lead Sim Lead Sim Lead TSC Sim Lead Sim Lead Sim Lead Sim Lead Sim Lead Sim Lead After Chain of custody of radios Switch back PPCS/SAS per EPIP 5-5 Transfer REGS, NRC phones Transfer page Enable load dispatcher phone Sim Lead/CNEP TSC Sim Lead Sim Lead Sim Lead SYSTEM PRESSURES Reactor Coolant System&Steam Generator PSIG 2500 2000 1500 1000 500 0 1 1 1 1 1 1.1 1 1 1 1 1 1 8 9 9 9 9 9 9 0 0 0 0 1 1 1 1 2 2 2 2 3 4 0 1 3 2 3 4 0 1 3 4 0 1 3 4 0 1 3 4 0 5 0 5 0 0 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 CLOCK TIME RCS~1A S/G~1B S/G LEVEL INDICATION TRENDS PRESSURIZER, S/8, RVLIS (%)100 80 60 40 20 0 1 8 8 8 8 9 9 9 9 9 9 0 0 1 3 4 0 1 1 2 3 4 0 0 5 0 5 0 5 7 0 0 5 0 CLOCK 1 1 1 1 1 1 1 1 1 1 0 0 0 1 1 1 1 2 2 2 I 1 3 4 0 1 3 4 0 1 3 5 0 5 0 5 0 5 0 5 0 TIME PRESSURIZER

~1A S/G LEVEL~18 S/G LEVEL~RVLIS TANK LEVEL TRENDS BAST, RWST (%)100 80 60 4Q 20 0 8 8 8 8 0 1 3 4 0 5 0 5 1 1 9 9 9 9 9 9 0 0 0 1 1 2 3 4 0 1 0 5 7 0 0 5 0 5 CLOCK TIME 1 1 0 0 3 0 5 1 1 1 1 1 1 I 0 1 3 0 5 0 1 1 1 2 Q 5 0 BAST~RWST SECTION 8.0 MESSAGE FORMS AND PLANT DATA SHEETS MESSAGE INDEX TIME 0700 0715 0730 0745 0750 0755 0755 0755 0800 0810 0815 0815 0815 0830 0840 0840 0845 0850 0850 0850 0855 0900 0905 0915 0917 0920 0930 0930 0945 1000 1000 1015 1015 1030 ME A E NO.I.C..1 2.3.4X.5.6.7.8.9.10.11.12.13.14.15.16.17 18.19.20.21.22.23.24.25.26.27X.28.28.1 29 30 31.32.MES AGE Initial Conditions Established Announcement to Commence Annual Exposure Exercise Notification of"A" S/G Leak Rate of 450cc/min Plant Status Unusual Event Contingency Message"A" S/G ARV Popping Open Mini-Scenario for"A" S/G ARV Isolation and"B" S/G ARV Leak Detection",A" S/G ARV Mercoid Control Problem Mini-Scenario Plant Status"B" S/G ARV Isolation Plant Status 8c ADFCS Trouble"B" S/G ARV Line Steam Leak Mini-Scenario MFW Regulating Valves (ADFCS)Trouble Mini-Scenario Plant Status CCW Surge Tank Lo Level Alarm 1A CCW Pump Leak Detection and Isolation Mini-Scenario Plant Status 1A CCW Pump Trip 1A CCW Pump Mechanical Seal Failure Mini-Scenario 1 A'CW Pump Motor Problem From Pump Seal Failure Mini-Scenario ADFCS Problem Repaired Plant Status 1A CCW Pump Isolated Plant Status 5 SGTR in"A" S/G Plant Status Plant Status Plant Status Alert Contingency Message Plant Status Mobile Dl Truck Mini-Scenario Plant Status and Mobile Dl Truck Arrives on Site Plant Status and"A" SW Pump Trip"A" SW Pump Inspection Mini-Scenario Natural Gas Leak Detection and Isolation Mini-MESSAGE INDEX (continued)

TIME~MEDEA E ED.IVIES AGE 1030 1045 1045 1045 1100 1100 1100 1115 1120 1120 1130 1145 1145 1145 1145 1145 1200 1215 1230 1245 1300 1315 33.34.35.36X.37.38 39 40.41.42.43.44.45.46.46.1 46.2 47.48.49.50.51.52.Plant Status Plant Status Air Evacuation of Screen House Mini-Scenario Site Area Emergency Contingency Message Plant Status"A" SW Pump Problem Mini-Scenario Security Investigation of"B" S/G ARV Drilled Hole Mini-Scenario Plant Status and Mobile Dl Truck Starts Pumping to OST."A" S/G ARV Mercoid Repair Complete Mini-Scenario for"A" S/G ARV Return to Service Plant Status The"B" S/G ARV Steam Leak Repair Completed"B" S/G Return to Service Mini-Scenario Plant Status Mini-Scenario for EOF Telephone System Failure Mini-Scenario for Contaminated IndividualArriving at TSC Plant Status Plant Status Plant Status Plant Status Plant Status Plant Status and Termination of Exercise MINI-SCENARIOS 1."A" S/G ARV Mercoid Control Problem~7tl IB 2."A" S/G ARV Isolation 7 H r A xilir ra r 3."B" S/G ARV Leak Detection 0810 Ho rs A xiliar 0 era or 4."B" S/G ARV Isolation 1 H r A xiliar 0 era or 5."B" S/G ARV Steam Leak Repair 81 H r n Pi fi r n Wl r 6.ADFCS Trouble~IH 1 a 7.1A CCW Pump Leak Inspection and Isolation 4 ur Auxiliar r r 8.1A CCW Pump Mechanical Seal Failure 5 Ho r M hanics 9.1A CCW Pump Motor Problem from Pump Seal Failure 0850 Hour Elec ricians 10.Mobile Dl Truck on Site, Hook up and Start Pumping, 1000 Auxiliar 0 era or Securi and Chemis 11.1A Service Water Pump Problem Inspection 1 1 H r A xiii r 0 eraor 12.Natural Gas Leak Detection in Screen House 10 H r A xiliar 0 er or 13.Natural Gas and Propane Gas Isolation to Screen House 1 Ho r A xiliar 0 era or 14.Air Evacuation of Screen House Air to Remove Natural Gas Concentration 1045 Hour Fire And Safe

15.Security Investigation of the"B" S/G Drilled Hole Steam Leak 11 H r e ri 16.17.1A Service Water Pump Problem (Breaker)11 r El ri i n"A" S/G ARV Return to Service 1120 o r A xiliar 0 era or 18."B" S/G ARV Return to Service 1145H r A xiii r 0 raor 19.Telephone System Failure in EOF 114 H r E F ff 20.Contaminated Individual Arrives at TSC 114 H ur Heal h Ph si s NTROLLERS F R MINI-SCENARI A.X LIARY PE AT R NTR LLER 1.2.3.4.5.6.7.8.9.10.QBM1 QBM1 Q)44 1000~1~1 F39.MIBQ~11 2~11 4"A" S/G ARV Isolation"B" S/G Leak Detection"B" S/G Isolation 1A CCW Pump Leak Inspection and Isolation Mobile DI Truck Operation 1A SW Pump Problem Inspection Natural Gas Leak Detection in Screen House Natural Gas and Propane Gas Isolation to Screen House"A" S/G ARV Return to Service"B" S/G ARV Return to Service B.ME HANIC ONTROLLER%88Q.1A CCW Pump Mechanical Seal Failure TRICIANS'.~ELE 1.2, 08gg~11 0 1A CCW Pump Motor Problem from Pump Seal Failure 1A Service Water Pump Problem (Breaker)D.PIPEFITTER AND WELDERS CONTROLLER 815"B" S/G ARV Steam Leak E.I 5 C CONTR LLERS 1.2.Q755 08'I 5"A" S/G ARV Mercoid Control Problem ADFCS Trouble F.FIRE AND AFETY C NTROLLER 1045 Air Evacuation of Screen house Air to Remove Natural Gas Concentration G.E RITY NTR LLER 1.11QQ Investigation of the"B" S/G Drilled Hole Steam Leak 2.1000 Escort Mobile Dl Truck on Site.il.~NTR LLER 1.~114 Failure of EOF Telephone System I.HEALTH PHY I ONTROLLER 1.~114 Contaminated Individual Arrives at TSC J.HEMI ST 0NTROLLER 1.~100 Hook-up Mobile Ol Truck and Start Pumping to OST.

RITI AL IMULATOR SET-UP DATA FOR 1 2 EMER EN Y PLANNING SIM LATOR R N 1.At Qgg)Equipment Set-up-See 0700 Plant Status sheet.2.At Q7gg Reactor Core is in MOL (571 PPM Boron).3.At Q7QQ RCS Leak Rate is 0.361 GPM.4.At Q7QO"A" S/G Primary to Secondary Leak Rate is approximately 450cc/min (0.125 gpm).5.At~07 0 R-15 on Alarm and Reading approximately 4.6 x 10'pm.6.At Q730 HP/Chemistry Reports to the Control Room that the"A" S/G calculated primary to secondary Leak Rate is 450cc/min (i.e., 0.125 GPM).7.At~Q745 Operators start shutting the Plant down in accordance with the 0-6,10 and 0-2.1 at 10%/hr for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and then at 20%/hr for the rest of the shutdown.8.A IL7v~l.h Idb d I d, 15 G<<Tb Leakage)0.1 GPM as identified by sampling).

9.At Q755 the"A" S/G ARV pops full open and cannot be closed from the Control Room.10.At 0810 the"A" S/G ARV Isolation Valve is closed.11.At Qg~1 the"B" S/G ARV is reported to have a steam leak.~N: Isolation of the"Bia S/G ARV can occur at any time from now on.12.At 0815 Annunciator G-22 (ADFCS System Trouble)Alarms.13.At 0830 CCW System leak of 20 GPM starts.14.At Q640 the CCW Surge Tank Lo Level Alarm lA-13l annunciates and the CCW level indicates it is decreasing.

'I 15.At~0!j5.the ADFCS Problem is Repaired.16.At~OQ5 the 1A CCW Pump Suction and Discharge Valves are closed isolating the leak.The Electrical Breaker is racked out also.17.At~015 the"A" S/G sustains a tube rupture of approximately 700 GPM.

RITI AL IM LAT R ET-P DATA F EIVIER ENCY PLANNING SllVI LAT R RUN (continued) 18.At~QQ;g, an alert should be declared.(S/G Tube rupture)100 GPM)19.At~1)Dl truck arrives on Site.20.At g1)~1 the"Ats SW Pump trips out-Annunciator (J-9)alarms.21.At~Q a natural gas leak in the Screen House is reported by Auxiliary Operator sent out to check the"A" SW Pump.22.At 1030 Outside Storage Tank Empty as Reported by Auxiliary Operator.23.At~~104 a i e Ar Em r n should be declared (entry of uncontrolled flammable gases into vital areas).24.At 11QQ, the CST levels decrease below 5 feet.25.At~111 Mobile Dl truck starts pumping water to OST 26.At 1120 the"Ars S/G ARV Mercoid is repaired.27.At 1145 the"B" S/G ARV steam leak is repaired.28.At~1315 the Exercise is terminated.

Time: egg Message: IC INN A TATI N 1 92 EVAL ATED EXER I E MESSAGE FORM MMM f: Si I 1:<<IR Simula e Plan Condi ion: See the Attached Sheets~Messe e: """THIS IS AN EXERCISE">>" FOR CONTROLLER USE ONLY~G'<<N 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 Results: 1)Participants should review conditions, Plant data, and other procedures as applicable.

GINNA STATION 1992 EMERGENCY PREPAREDNESS EXERCISE INITIAL CONDITIONS 1.The R.E.Ginna Nuclear Power Plant is operating at approximately 97%rated thermal power.The Plant has been operating at this power level continuously for approximately 150 days.2.The"A" Steam Generator (S/G)primary to secondary leak rate increased approximately five (5)days ago to a calculated 60cc/min.At approximately 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> this morning the primary to secondary leak rate has again increased significantly as indicated by a substantial increase in Radiation Monitor R-15 (Air Ejector).Radiation Monitor R-19 (S/G Blowdown)has also indicated an increase in activity.The Health Physics/Chemistry Department is in the process of analyzing samples to determine the calculated leak rate.3.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 /> (10/8/92)is provided in Table 9.2 of Scenario Section 9.3.Total activity is 2.56 microcuries/gram.

Chemistry data is provided on Exercise Chemistry Log Sheet, available from the Controller.

4.The Reactor Coolant System (RCS)total leakage is 0.361 gpm as of 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> this morning and has been increasing.

Identified RCS leakage is 0.073 gpm.5~General weather conditions are partly cloudy with no current precipitation.

For'urposes of the Exercise, additional meteorological information in the Simulator Control Room should be obtained from the Plant Process Computer System (PPCS)~6.The Primary Water Treatment Plant is secured for major maintenance that will take approximately three (3)days.The 100,000 gallon Outside Condensate Storage Tank is at 20%level.a demineralizer trailer has been ordered and is scheduled to arrive at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> today.7.The House Heating Boiler is in service and nuclear steam is secured and held.8.Provide general weather (clear conditions) 9.Provide initial conditions turnover paperwork.

199P EVALUATED EXERCISE Time:~7oo MAJOR PAEVLNETERS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FY-924~GPM FI-925 C7 GPM 1A.INSERV B OOS 1B.INSERV TB OOS 1C INSERV STB OOS BAST Level=Low Head S.I.Pum s FI-626 1A.INSERV TB OOS RECIRC , 1B.INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s FI-931A O GPM FI-931B 0 GPM 1A.INSERV TB 1B.INSERV TB NaOH Tank Level=OOS OOS Containme ecirc Fans 1A.SER STBY OOS 1B.NSE STB OOS 1C.INS RV B OOS 1D.NSER STBY OOS Post Acc ent Dampers OPEN LOSED Service Water Pum s 1A.SE STBY OOS 1B.R STBY OOS 1C.NS RV STB OOS 1D.INSERV STB OOS A&B Header Pressure/73 PSIG Com onent oolin Water Pum s DIESEL GENERATORS A.RUNNING UNLOADED B OOS B.RUNNING UNLOADED BY OOS TSC RUNNING UNLOADED 0 S Security RUNNING UNLOADED TB OOS Reactor Shutdown~YES N-3 1~CPS N-32 CPS N-35 AMPS N-36 AMPS Avg.Nuclear Power RCS Pressure ZzM PSIG PRZR Level A RCP NNI STOPPED B RCP UNNIN STOPPED 1A S/G Level~Z,.I 1B S/G Level 1A S/G Pressure/47 tz PSIG 1B S/G Pressure~SO PSIG Turbine/Generator LI OFFLINE 4 KV Buses NERGIZED DEENERGIZED 480V Buses NERGI DEENERGIZED DC Batteries A~5o VOLTS B/Sb VOLTS nmt Pressure PSTG nmt Sump A Level~FEET Cnmt Sump B Level INCHES A Loop Hot Leg~&A OF A Loop Cold Leg.S OF B Loop Hot Leg 7 OF B Loop Cold Leg oF RVLIS~'~e3*CET Q b~~e$OF S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow~GPM ENGINEERED SAFEGUARDS Aux.Feedwat um s 1A.INSERV OOS 1B.INSERV TB OOS Turb.Driven INSERV TB OOS ST Level~FEET 1A.NSE S OOS 1B.INSERV TB OOS Surge Tank Level=~2 Standb Aux.Fe ater Pum s 1C.INSERV OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples

8~1992 07'08 R.E.GINA SltKATOR 7REND GROUP ASSIG)ST SU)WARY PAGE 1 6ROUP: EVENT1 PROCEDURE:

EPIP 1-5 PLA)(7 STATUS POINT ID DESCRIPTION (IAL E.U.1 2 3 4 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 ATMS RXT N31 N32 N35 N36 NP PRCS LP2R FRCLA FRV B R)(T16 RXT17 TSUBTC LSGA LS69 PSGA PSGB GENBKRl GENBKR2 BUS11A BUS11B BUS12A BUS12B B11A12A B11B129 PCV LS(NPA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAVGBMID LRV TCCORE FAUXFMA FAUXFMB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT M/0 SCRAtt REACTOR TRIP BREAKER STATUS SO(mCE RANGE DETECTOR N-31 SO(HCE RA%E DETECTS N-32 INTERNEDIATE RANEE K7ECTOR tt-35 INTER)(EDIATE RANGE DETECTOR N-36 AVERAGE N(KLEAR POMER REfK:TOR CQOUNT SYSTEM AVG PRESS PRESSURIlER AVERAGE LEVEL REACTOR COOUNT LOOP A AVG FLOM REACTOR COOLANT LOOP B AVG FLOM RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP ItiCORE TC SUBCOOLED NRGIN STN GEN A NARROM RANGE AVG LEVEL STt(GEN B t(ARROM RANGE AVG LEVEL STt(GEN A AVERAGE PRESSURE STtt GEN B AVERAGE PRESSURE GE%MTOR ON LINE BREAKER 161T/2 GBGNTOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SUPPLY BREAKER NOT TERt(I)ITED Ott PPCS (7/19/91)NOT TERttINATED Otl PPCS (7/19/91)BUS 11A TO 12A TIE BREAKER BUS 11B To 12B TIE BREAKER CONTAIN)(ENT AVERAGE PRESSURE CONTAINtfENT SUt(P A AVERAGE LEVEL SSP B LEVEL 8 ItlCHES (TRAIN A)SUtP B LEVEL 8 INCHES (TRAIN B)SUtl'LEVEL 78 INCHES (TRAIN A)SUtP B LEVEL 78 INCHES (TRAIN B)SSP B LEVEL 113 INCHES(TRAIN A)SU%'LEVEL 113 INCHES(TRAIN B)SUtP B LEVEL 180 INCHES(TRAIN A)SU%'LEVEL 180 INCHES(TRAIN B)SSP B LEVEL 214 INCHES(TRAIN A)SUtF B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TEtPERATURE RCLB HOT LEG TEt(PERATURE RCLA COLD LEG TEt(PERATNE RCLB COLD LEG TEtiPERATNE RCLA TAVG (TNT/TCOLD MIDE RNG)RCLB TAVG (THOT/TCOLD MIOE RNG)REACTOR VESSEL AVERAGE LEVEL El~1 INCORE TC AVERAGE TEt(P S/G A TOTAL AUX FEEDMATER FLOM S/6 B TOTAL AUX FEEDMATER FLOM t(TR AUXILIARY FEEDMATER PUt(P A NTR AUXILIARY FEEDMATER PUt(P 9 AUX FM PUt(P STEAN Sl)PPLY VALVE A AUX FM PUt(P STEA)l SUPPLY VALVE B NO ATMS NOT TRIP 1.00000+00 1.00000+00 6.91829-04 6.42686M 97.15 2252.47.9 98.5 97.3 NOTTRIP NOT TRIP 45,4 52.1 52.1 692.6'90.NQT TRIP NOT TRIP t$7 TRIP NOT TRIP NOT TRIP NOT TRIP TRlPPED TRIPPED.17 1.6 LONER LONER LONER LONER LONER LONER LONER LONER LONER LOWER 600.7 600.7 543;3 544.6 572.0 572.7 99.3 604.5 0.0.OFF OFF CLOSED CLOSED 6009 6009 INHB CPS INHB CPS INHB le INHB NP GOOD X 6009 PSIG GOOD GOOD/6009/6009 6009 600~DEGF GOOD GOOD'/6009 PSIG GOOD PSIG GOOD Goon 6009 6009 DEL DEL 6009 6009 600D PSIG GOOD FEET 6009 Goon 6009 soon 6009 6009 6009 6009 6009 Goon 6009 DEGF 6009 DEGF 6009 DE6F GOOD DEGF 6009 KGF Goon DEGF 6009 Goo<DEGF 6009 GPH 6009 GPt(6009 Goon GOOD 6009 OCT 8~1992 07:08 R.E.GINA SI%LATOR TREND GROUP ASSIGOENT S1NNRY PAGE 26ROUP: EVENTi PROCEDURE:

EPIP 1-5 PLM'TATUS POINT ID DESCRIPTION VALUE QUAL E.U.53 FSIA SAFETY IN:ECTION LOCP A AVG FLOM 54 FSIB SAFETY INJECTION LOOP B AV6 FLOM 55 P2160 SERVICE MATER PlNPS A h B HEADER 56 P2161 SERVICE MATER PlNPS C 5 D HEADER 57 BKR041 SERVICE MATER PUNP A 58 BKR042 SERVICE MATER PlNP B 59 BKR043 SERVICE MATER PlNP C 60 BKR044 SERVICE MATER PUN'0.6000 0.600D 81.GOOD 73.GOOD GOOD 600D 6009 6009 PN 6PH PSI6 PSIG PROGRAM NAME:LRGTSZ.E RE E.GIHNA NUCLEAR POWER PLANT OCT 08,92 07 01 00 TREND GROUP ASSIGNMEHT

SUMMARY

GROUP NAHE EVENT 2 GROUP DESCRIPTION PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURREHT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 16 17 1e'19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15AS R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLIHG LOOP TOTAL FLW REFUELING WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEHPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOM AREA 2-CONTAINMENT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUHP AREA 35-PASS SAMPLE PANEL CONTAINMENT IODINE MONITOR R'IOA CONTAINMENT AIR PARTICULATE CONTAINHENT GAS MONITOR PLANT VENT IODINE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID WASTE DISPOSAL HONITOR STEAM GENERATOR SLOWDOWN DRAIN AREA 29-CONTAIHHENT HIGH RANGE AREA 30-CONTAINMENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5 LOW RANGE GAS CV VEHT CHAN 6-AREA GAMMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VEHT CHAN 5-LOW RAHGE GAS PLANT VENT CHAN 7-HID RANGE GAS PLANT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAN 9 Hl RANGE GAS AREA 3'I STEAM LINE A (SPING)AREA 32 STEAM LINE B (SPING)CV HYDROGEN CONCENTRATION CV BASEHENT LVL 6 FT TEHP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEHP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 3.7 209.52.9 55.4 2.5 9.02214-02 6.4067eioo 1.39946+00 3.40701+01 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 4.07174+03 5.05861-01 5'9440-01 4.66390+04 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 2.33589-03 2.33337-03 2.33436-03 1.02040.02 1.01048-02

.0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPH CPH CPM CPH CPH CPM CPH R/NR R/HR CPH UCI/CC MR/NR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR DEGF DEGF DEGF DEGF DEGF DEGF TIme:~715 Message: 1 INNA STATI N 19 2 EVAL ATED EXER I E MES AGE F RM>>>>>>ft:>>I C IR Si l Plan n i i n: See the Attached Sheets~essa<ee: """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 1992 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.

199K.EVALUATED EXERCISE Time: g 7/>MAZOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown~YES 0 N-3 1~CPS N-32 CPS N-35 AMPS N-36 AMPS Avg.Nuclear Power RCS Pressure PSIG PRZR Level A RCP UNNIN STOPPED B RCP UNNZN STOPPED lA S/G Level.I 1B S/G Level~a.1A S/G Pressure?PSIG 1B S/G Pressure 0 PSIG Turbine/Generator NLI OFFLINE 4 KV Buses NERGIZ DEENERGIZED 480V Buses RGZZ DEENERGIZED DC Batteries A/Sb VOLTS BISO VOLTS nmt Pressure~I PSIG nmt Sump A Level~FEET Cnmt Sump B Level INCHES A Loop Hot Leg~OF A Loop Cold Leg~g.S OF B Loop Hot Leg 0.'7 OF B Loop Cold Leg~59~OF RVLIS 1.9*CET OF S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow G GPM DIESEL GENERATORS A.RUNNING UNLOADED OOS.B RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB OOS ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.INSERV TB OOS 1B.INSERV OOS Turb.Driven INSERV TB OOS.ST Level~FEET Hi h Head S.I.Pum s FI-924 C7 GPM FI-925 C7 GPM 1A.INSERV T 1B.INSERV 1C.INSERV BAST Level=OOS OOS OOS Low Head S.I.Pum s FI-626 0 GPM 1A.INSERV TB OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s FI-931A O'PM FI-931B~GPM 1A.INSERV T 1B.INSERV TB NaOH Tank Level=OOS OOS Containment Recirc Fans 1A.NSER STBY OOS 1B.SERV STBY OOS 1C.INS V TB OOS 1D.SER STBY OOS Post Aces ent Dampers OPEN LOSED Service Wat Pum s 1A.S STBY OOS.1B.S STBY OOS 1C.NSE STBY OOS 1D.INSERV TB OOS A&B Header Pressure S PSIG Com onent Coolin Water Pum s 1A.SE STBY OOS 1B.INSERV B OOS Surge Tank Leve=~y Standb Aux.Fee ater Pum s 1C.INSERV TB OOS 1D.INSERV OOS*CET=Average of Selected Core Exit Thermocouples 0

07: 16 R.E.GINA Sit(ULATOR TREND GROUP ASSIGN)IENT SUI(tIARY PAGE 1 GROUP: EVENTl PROCEDURE:

EPIP 1-5 PLANT STATUS 1 2 3 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21.u 24 25 26 27 28 29 30 31 32 34 35 36 37 38 39 40 41 42 43 44 45 46 51 52 POINT ID ATMS RXT N31 N32 N35 N36 t(P PRCS LPZR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA'SGB PSGA PSGB GENBKRl GENBKR2 BUS11A BUSliB BUS12A BUS12B B11A12A B11B12B PCV LS(NPA L0942E L0943E L0942D L09439 L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAVGBMID LRV TCCORE FAUXFMA FAUXFMB BKR081 BKR082 V3504 DESCRIPTION ANTICIPATED TRANSIENT M/0 SCRAtI REACTOR TRIP BREAKER STATUS SMKE RANGE DETECTOR N-31 SOlRCE RA)IGE DETECTOR N-32 INTE)mEDIATE RANGE DETECTOR N-35 INTERI(EDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTE)(AVG PRESS PRESSURIZER AVERAGE LEVEL RHETOR COOLANT LOOP A AVG FLGM REACTGR COOLANT LOOP B AVG FLOM RCPA BREAKER CAUSE RX TRIP IKPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED t(ARGIN ST)I GEN A NARROM RANGE AVG LEVEL STI(GE)l B NARROM RANGE AVG LEVEL STN GEN A AVERAGE PRESSURE STtf GEtl B AVERAGE PRESSURE GBGQTOR ON LINE BREAKER!61372 GBERATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SL4'PLY BREAKER NOT TER)IINATED ON PPCS (7/19/91)NOT TER)IINATED ON PPCS (7/f9/91)BUS 11A TO 12A TIE BREAKER BUS 119 TO 12B TIE BRENER CONTAINIIENT AVERAGE PRESURE CoiWAINMEI(T SUI(P A AVERAGE LEVEL SU)P B LEVEL 8 ItlCHES (TRAIN A)SUtP B LEVEL 8 ItlCHES (TRAIN B)SSP B LEVEL 78 INCHES (TRAIN A)SUI(P B LEVEL 78 INCHES (TRAIN B)SSP B LE4l3.f13 INCHES(TRAIN A)SUtP B LEVEL 113 INCHES(TRAIN B)SU%'LEVEL 180 INCHES(TRAItl A)SUtF B LEVEL 180 INCHES(TRAIN B)SSP B LEVEL 214 INOKS(TRAIN A)SU%'LEVEL 214 INCHES(TRAIN B)IKLA HOT LEG TE)(PERATUfE RCLB HOT LEG TEt(PERATNK RCLA COLD LEG TPiPERATIRE RCLB CGI.D LEG TE)IPERATlRE RCLA TAVG (THQT/TCOLD WIDE RNG)RCLB TAVG (THOT/TCOLD MIDE RNG)REACTOR VESSEL AVERAGE LEVEL El~1 It/CORE TC AVERAGE TEtP S/6 A TOTAL AUX FEEDMATER FLGM S/G B TOTAL AUX FEEDMATER FLOW t(TR AUXILIARY FEEDMATER PU)IP A t(TR AUXILIARY FEEDMATER PUI(P 9 AUX FM PUI(P STEAN SUPPLY VALVE A AUX FM PUi"P STEAN SUPPLY VALVE B VALUE NO ATMS NOT TRIP 1.00000KO 1.0005&0 6.918Ã-04 6.42686M 97.16 2252.48.0 98.5 97.3 NOT TRIP NOT TRIP 45.4 52.1 52.1 692.690.NOT TRIP NOT TRIP NOT TRIP NOT TRIP NOT TRIP NQT TRIP TRIPPED TRIPPED.11 1.6 LONER LONER LOWER LOWER LONER LONER LONER LOWER LOWER LONER 600.7 600.7 543.3 544.6 572.0 572.7 99.3 604.5 0.0.OFF OFF CLOSED CLOSED 6009 6009 INHB INHB INHS INHH 6009 GOOD 6009 6009 GOOD 6009 Goon 600~6009 6009 GOOD GOOD GOOD GOOD 6009 Goon DEL DEL 6009 GOOD 6009 6009 6009 6009 Goon Goon 6009 6009 6009 Goon GOOD 6009 GOOD 6009 Goon 6009 soon 6009 GOOD 6008 6009 6009 Goon GOOD E.U.CPS CPS NP At(P PSIG X X X DEGF X/PSIG PSIG PSIG FEET DEGF DEGF DEGF DEGF DEGF DE6F X DE6F GPN GPI(8'-l 7 XT 8~1992 07!16 R.E.GINA SIHL&TOR TREND GROUP ASSIGNNEhT RNNRY PAGE 2 6ROUP: EVENT1 PROCEDURE!

EPIP 1-5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BKR042 5'P BKR043 60 BKR044 DESCRIPTION SAFETY IN.'ECTION LOOP A AVG FLOM SAFETY INJECTION LOOP B AVG FLOM SERVICE MATER PUFFS A h B HEADER SERVICE MATER PlDIPS C h D HEADER SERVICE MATER PUtF A SERVICE MATER PUNP B SERVICE MATER PIIP C SERVICE MATER PINP D ON ON ON OFF 0.GOOD 0.GOOD 81~GOOD 73.GOOD GOOD GOOD GOOD GOOD GPN PN PSI6 PSIG VALUE QUAL E.U.

~~~ROGRAM NAME:LRGTS2.E R.E.GIHHA NUCLEAR POWER PLANT OCT 08,92 07:15:00 TREND GROUP ASSIGHMEHT

SUMMARY

GROUP NAME EVENT 2 GROUP DESCRIPT ION PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPT ION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 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 4, F0619 LRWST WS033 WDO33 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R'l5 R12A5 R12A6 R12A7 R12A9 R14AS R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLW REFUELING WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-COHTAINHENT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PAHEL COHTAIHHEHT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE COHTAINMEHT GAS MONITOR PLANT VENT IODINE MONITOR R108 AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID WASTE DISPOSAL MONITOR STEAM GENERATOR BLOWDSS DRAIN AREA 29-COHTAIHMEHT HIGN RANGE AREA 30-CONTAINMENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6.AREA GAMMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9 HIGH RANGE GAS PLANT VENT CHAN 5-LOW RANGE GAS PLANT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 31 STEAH LINE A (SPIHG)AREA 32 STEAM LINE 8 (SPIHG)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEHP¹3 CV IHTERMEDIATE LVL 6 FT TEMP¹7 CV IHTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 3.8 193.52.9 55.5 2.6 9.02214-02 6.40678+00 1.39946+00 3.40701+01 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 4.07174+03 5.05861-01 5.09440-01 8.75390+04 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 4.39589-03 4.39337-03 4.39436-03 1.02040.02 1.01048-02

.0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPM CPM CPM CPM CPM CPM CPM R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR DEGF DEGF DEGF DEGF DEGF DEGF INNA STATION Time:~7'essage:

2 1 2 EVALUATED EXER I E~MEE AGE 3 RM~MI: G I<<G<<IR im la e Plan n I I n: See the Attached Sheets~IVI<<c~a: """THIS IS AN EXERCISE""" The"A" S/G calculated leak rate is approximately 450cc/min.

F R C NTR LLER USE ONLY 1)This message to be called into the Simulator Control Room by the Simulator operator acting as the HP technician.

Ani i R I 1)Operators should begin performing the Applicable Actions of Operating Procedure 0-6.10 (Plant Operation with Steam Generator Tube Leak Indication).

2)An orderly Plant shutdown should commence to be in Hot Shutdown within six (6)hours and to be less than 350'F in the RCS within the next six (6)hours as required by Plant Technical Specifications.

31 A~UI 3 Idd d I dI d IREPIPI.G."GI Station Event Evaluation and Classification," EAL: Steam Generator Tube Rupture (SGTR);Steam Generator Tube Leakage>.1gpm as identified by sampling or EAL: Reactor Coolant Leakage (RCS);Steam Generator Tube Leakage).1gpm as identified by sampling.Appropriate offsite notifications should be made per EPIP 1-5.4)Operators should also be performing the applicable actions of the following procedures:

a)EPIP 1-1 (Unusual Event)b)EPIP 5-7 (Emergency Organization) c)0-9.3 (NRC Immediate Notification).

199K'EVALUATED EXERCISE Time:~73+MAZOR PARAMETERS

'NGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 0 GPM FI-925 O GP 1A.INSERV B OOS 1B.INSERV TB OOS 1C.INSERV TB OOS BAST Level=Low Head S.X.Pum s FI-626 O GPM 1A.XNSERV T OOS RECIRC 1B.INSERV S B OOS RECIRC RWST Level=Containment S ra Pum s FI-931A O GPM FI-931B O GP 1A.INSERV TB OOS 1B.INSERV T OOS NaOH Tank Level=Containmen ecirc Fans 1A.NSERV STBY OOS 1B.NSE V STBY OOS 1C.IN ERV TB OOS 1D.NSE STBY OOS Post Accident Dampers OPEN CLOSED Service Water Pum s 1A NS STBY OOS 1B.NSE STBY OOS 1C.NSE STBY OOS 1D.INSERV OOS A&B Header Pressure PSIG Com onent oolin Water Pum s DIESEL GENERATORS A.*'RUNNING UNLOADED B OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED OOS Security RUNNING UNLOADED T OOS Reactor Shutdown YES 0 N-31~CPS N-32~CPS N-35~AMPS N-36 AMPS Avg.Nuclear Power RCS Pressure gg.~PSIG PRZR Level.I A RCP ING STOPPED B RCP UNNI STOPPED lA S/G Level 1B S/G Level 1A S/G Pressure~p PSIG 1B S/G Pressure O PSIG Turbine/Generator LXN OFFLINE 4 KV Buses RGIZE DEENERGIZED 480V Buses NERGXZE DEENERGXZED DC Batteries A)70 Bgg0 VOLTS Cnmt Pressure~~PSIG nmt Sump A Level FEET Cnmt Sump B Level INCHES A Loop Hot Leg 0.OF A Loop Cold Leg OF B Loop Hot Leg bOe OF B Loop Cold Leg OF RVLIS*CET~o~OF S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow M GPM ENGINEERED SAFEGUARDS Aux.Feedwater m s 1A.INSERV OOS 1B.INSERV TB OOS Turb.Driven INSERV B OOS~ST Level 2 FEET 1A.SER STB OOS 1B.INSERV TB OOS Surge Tank Leve Standb Aux.Feed ater Pum s 1C.INSERV TB OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples

OCT 8~1992 07:30 R.E.GINA SIMULATOR TREND GROUP ASSIGQBi7 SUt(MARY PAGE 1 GROl)P: EVENTl PROCEDURE'PIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E.U, 1 2 3 4 5 6 7 8 10 ll 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 AT%RXT N31 N32 N35 N36 NP PRCS LPIR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GENBKRl GENBKR2 BUS11A BUS118 BUS12A BUS128 811A12A 811812B PCV LSRFA L0942E L0943E L0942D L0943D L0942C L0943C L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TAKAMID TAVGBMID TCCGRE FAUXFMA FAUXFMB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT M/0 SCRAM REACTOR TRIP BREAKER STATUS SmSCE RANGE DETECTGR N-31 So(HCE RANGE DETECTOR N-32 INTERMEDIATE RANGE DETECTOR N-35 INTERMEDIATE RAN6E DETECTOR N-36 AVERAGE l(XLEAR POWER REACTOR COOLANT SYSTEM AVG PRESS PRESSURIZER AVERAGE LEVEL REACTOR CGOLN(T LOOP A AVG FLGM REACTOR COOLANT LOOP 8 AVG FLGM RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCGRE TC SUBCOOLED MAfFaIN STM GEN A NARROW RANGE AVG LEVEL STM GEN 8 NARROM RA%E AVG LEVEL STM GEN A AVERAGE PRESPJRE STtf GEN 8 AVERAGE PRESSURE GBGQTOR ON LINE BREAKER 1G1372 GEtGQTOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 118 SUPPLY BREAKER NOT TERMINATED OW PPCS (7/19/91)NOT TERMINATED OW PPCS (7/19/91)BUS 11A To 12A TIE BREAKER BUS 118 TO 128 TIE BRENER CONTAINMENT AVERAGE PRESSURE CONTAINMENT SUMP A AVERAGE LEVEL SUMP 8 LEVEL 8 INCHES (TRAIN A)SU%'LEVEL 8 INCHES (TRAIN B)SSP 8 LEVEL 78 INC)iES (TRAIN A)SU)P 8 LEVEL 78 INCHES (TRAIN 8)SSP 8 LEVEL 113 INCHES(TRAIN A)SU)P 8 LEVEL 113 INCHES(TRAIN 8)SUtP 8 LEVEL 180 INCHES(TRAIN A)SUtP 8 LEVEL 180 INCHES(TRAIN 8)SUMP 8 LEVEL 214 INCHES(TRAIN A)SUtP 8 LEVEL 214 INCHES(TRAIN 8)RCLA HOT LEG TEMPERATURE RCLB HOT LEG TEMPERATURE RCLA COLD LEG TEtfPERATlSE RCLB COLD LEG TE)fPERAT(SE RCLA TAVG (TNT/TCOLD WIDE RNG)RCLB TAVG (THOT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 INCORE TC AVERAGE TEMP S/G A TOTAL AUX FEEDMATER FLOW S/G 8 TOTAL AUX FEEDMATER FLOW MTR AUXILIARY FEEDMATER PUMP A MTR AUXILIARY FEEDMATER PUMP 8 AUX FM PUMP STEA)f SUPPLY VALVE A AUX FM PUt(P STEAM SUPPLY VALVE 8 No ATMS NOT TRIP 1.00000+00 1.00000%0 6.91829M 6.42686M 97.15 2252.48.1 98.5 97.3 NOT TRIP NOT TRIP 45.4 52.1 52.1 692.690.NOT TRIP NOT TRIP NOT TRIP NOT TRIP NOT TRIP NOT TRIP TRIPPED TRIPPED.08 1.7 LOWER LOWER LOWER LOWER LONER J.ONER LOWER LOWER LONER LONER 600.7 600.7 543.3 544.6 572.0 572.7 99.3 604.5 0.0.OFF OFF CLOSED CLOSED Goon Goon INHB INHB INHB INHB GOOD GOOD 600D 6008 GOOD GOOD Goon 6004 GOOD Goon Goon GOOD GOOD 6008 GOOD GOOD DEL DEL Goon GOOD Goon GOOD GOOD 600D GOOD GOOD GOOD Goon GOOD GOOD GOOD Goon 600D Goon GOOD Goon Goon GOOD GOOD 600~GOOD GOOD GOOD GOOD GOOD GOOD CPS CPS A!(P AMP 7, PSIG e/y./0 DEGF//PSIG PSIG PSIG FEET DE6F DEGF DEGF DEGF DEGF DEGF X DEGF GPM OCT 8~1992 07:30 R.E, GINA SINLATOR TREND GROUP ASSIGt4tlENT SUtNARY PAGE 2 6ROUP: EVEt4TI PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION 53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 SAFETY It43ECTION LOOP A AVG FLOM SAFETY IN.'tECTION LOOP 8 AVG FLOM SERVICE MATER PUtlPS A h B HEADER SERVICE MATER PUtlPS C h D HEADER SERVICE MATER PUtlP A SERVICE MATER PUtlP 8 SERVICE MATER PUtlP C SERVICE MATER PUtlP D ON ON ON OFF VALUE NAL 0.GOOD 0.GOOD 81.GOOD 73.GOOD GOOD 600D GOOD GOOD E.U.GPtl GPtl PSIG PSIG PROGRAM NAHE:LRGTSZ.E R.E.GINNA NUCLEAR POWER PLANT OCT 08,92 07:31:00 TREND GROUP ASSIGNHENT

SUMMARY

GROUP NAHE EVENT 2 GROUP DESCRIPTION PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURREHT VALUE DUALITY CODE ENGR UNITS 2 3 4 5 6 7 8 9 10 11 12 13 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13~R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAI.FLW REFUELING WATER STORAGE TANK LVL 33 FOOT LEVEL'WIND SPEED~33 FOOT LEVEL WIND DIRECTIOH 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOH AREA 2-CONTAINHENT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MOHITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAHPLE PANEL CONTAIHHEHT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE CONTAINMENT GAS MONITOR PLANT VENT 1001NE MONITOR R108 AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID WASTE DISPOSAL MONITOR STEAH GEHERATOR SLOWDOWN DRAIN AREA 29-CONTAINMENT HIGH RANGE AREA 30-CONTAINHENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-HID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VEHT CHAN 5 LOW RANGE GAS PLANT VENT CHAN 7-HID RANGE GAS PLANT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7 MID RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 31 STEAM LIHE A (SPING)AREA 32 STEAH LINE 8 (SPING)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEHP¹3 CV INTERMEDIATE LVL 6 FT TEHP'¹7 CV INTERHEDIATE LVL 6 FT TEHP¹8 CV INTERMEDIATE LVL 6 Fl'EHP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94'3.6 202.53.0 55.5 2.5 9.02214-02 6.40678+00 1.39946+00 3.40701+01 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543<01 8.58327+01 4.22831+01 2.78658+03 4.07174+03 5.05861-01 5.09440.01 1'5835+05 1.89699-07 2.53990.02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 6.29179-03 6.29392-03 6.29436.03 1.02040.02 1.01048-02

.0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOGO GOOD GOOD GOGO GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH HWRN GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM x HPH DEG.DEGF DEGF DEGF MR/H HR/H HR/H MR/H HR/H MR/H CPH CPH CPH CPH CPM CPM CPH CPM R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR HR/HR DEGF DEGF DEGF DEGF DEGF DEGF

'

Time: (L7~4 Message:~GINNA STATION 1 92 EVAL ATED EXER I E MESSAGE FORM~M: 8 I<<C IR Sirnula ed Plant Conditions:

See the Attached Sheets~essa<ee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: An ici ated Results: 1)Operators should be performing the applicable actions of the following procedures:

a)0-6.10 (Plant Operation With Steam Generator Tube Leak Indication).

b)0-2.1 (Normal Shutdown to Hot Shutdown).

c)S-3.3C (H, or 0, Removal From Primary System by Burping Volume Control Tank With N2}.d)S-3.3D (CVCS Cation Demineralizer BED Operations Using Deborating DI A Unit.

199K'EVALUATED EXERCISE Time: 07 t4 MAJOR PARAMETERS ENGINEERED SAFEGUARDS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED STB OOS TSC RUNNING UNLOADED OOS Security RUNNING UNLOA D B ENGINEERED SAFEGUARDS Aux.Feedwater m s 1A.INSERV TB OOS 1B.INSERV B OOS Turb.Driven INSERV TB OOS ST Level~g FE OOS Reactor Shutdown YES 0 N-3 1 CPS N-32 CPS N-35 AMPS N-36 f.'~CLAMPS Avg.Nuclear Power RCS Pressure V PSIG PRZR Level, A RCP UNNI STOPPED B RCP UNNIN STOPPED 1A S/G Level.Q.t.4 1B S/G Level 1A S/G Pressure~~PSIG 1B S/G Pressure PSIG Turbine/Generator NLIN OFFLINE 4 KV Buses ERGIZE DEENERGIZED 480V Buses NERGIZE DEENERGIZED DC Batteries A~Sa VOLTS B/ZO VOLTS nmt Pressure~GPSIG nmt Sump A Level FEET Cnmt Sump B Level INCHES A Loop Hot Leg dna f OF A Loop Cold Leg.~)~/OF B Loop Hot Leg dO.OF B Loop Cold Leg VS'.OF RVLIS'KX-.k~*CET OF 5/G A Total Aux FW Flow~GPM S/G B Total Aux FW Flow 0 GPM DIESEL GENERATORS Hi h Head S.I.Pum s FI-924 0 GPM FI-925~GPM 1A INSERV TB OOS 1B.INSERV TB OOS 1C INSERV STB OOS BAST Level=Low Head S.I.Pum s FI-626 GP 1A.INSERV B OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s FI-931A 0 GPM FI-931BGP 1A.INSERV OOS 1B.INSERV TB OOS NaOH Tank Level=Containme t ecirc Fans 1A.SER STBY OOS 1B.NSER STBY OOS 1C.INSERV TB OOS 1D.NSER ST Y OOS Post Accident Dampers OPEN Service Water Pum s 1A.STBY OOS 1B.STBY OOS 1C.ER STBY OOS 1D.INSERV TB OOS A&B Header Pressure LOSED PSIG Com onen olin Water Pum s 1A.E ST Y OOS 1B.INSERV TB OOS Surge Tank Level=~v Standb Aux.Fe dwater Pum s 1C.INSERV OOS 1D INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples 8i 1992 07:44 R.E.GINA SltmLATOR TREtfD GROUP ASSIG)IEt(T SU)L%8Y PAGE 16RQUP: EVENT1 PROCEDURES EPIP 1-5 PLANT 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 ATl6 RXT N31 N32 N35 N36 NP PRCS LPIR FRCLA FRCLB RX716 RXT17 TSUBTC LSGA LS6B PSGA PSGB GEtfBKR1 GENBKR2 BUSl IA BUS11B BUS12A BUS12B Bl 1A12A BiiB12B PCV LS(SPA L0942E L0943E L0942D L09430 L0942C L0943C L0942B L0943B L0942A L0943A 70409A 70410A 70450 70451 TAVGAMID TAVGBMID LRV TCCORE FAUXFMA FAUXFMB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT M/0 SCRN REACTOR TRIP BREAKER STATUS SO(ICE RAt(GE DETECTOR N-31 SINCE RAtiGE DETECTOR N-32 INTERtfEDIATE RAN6E DETECTOR N-35 INTER)(EDIATE RAN6E DETECTOR N-36 AVERAGE NUCLEAR PQMER REACTOR COOLANT SYSTEH AVG PRESS PRESSURIIER AVERAGE LEVEL RFAC70R CCQLANT LQQP A AVG FLOM RECTOR CQOLAtfT LOOP B AVG FLQM RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE 7C SUBCOQLED NRGIN STt(GEtf A NARROM RANGE AVG LEVEL STH GEN B NARROM RANGE AVG LEVEL STtf GEN A AVERAGE PRESSURE STH GEN B AVERAGE PRESSURE GEtGQTOR ON LINE BPEAKER 161372 GBERATOR ON LINE BREAKER 9X1372 BUS iiA SUPPLY BREAKER BUS 11B SLYLY BREAKER NOT TERMINATED ON PPCS (7/19/91)NOT TER)(INATED Otf PPCS (7/19/91)BUS llA To 12A TIE BRENER BUS 11B TQ 128 TIE BRENER CONTAltfMEt(7 AVERAGE PRESSURE CQNTAINtfEtlT SU)(P A AVERAGE LEVEL SEP 8 LEVEL 8 ItfCHES (TRAIN A)SU%'LEVEL 8 INCHES (TRAIN 8)SUNUP B LEVEL 78 INCHES (TRAIN A)SUNUP B LEVEL 78 INCf.:cS (TRAIN B)SU%'LEVEL 113 INCHES(TRAIN A)SU%'LEVEL 113 INCHES(TRAIN B)SUtP B LEVEL 180 INCHES(TRAIN A)SUt1'LEVEL 180 INCHES(TRAIN B)SUtp B LEVEL 214 INCHES(TRAIN A)-SU)P B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TEMPERATURE RCLB HOT LEG TEt(PERATUK RCLA COLD LEG TEtlPERATNE RCLB COLD LEG TEtfPERATNE RCLA TAVG (THOT/TCOLD MIDE RNG)RCLB TAVG (THOT/TCOLD MIDE RNG)RGtTOR VESSP AVERAGE LEVEL El.l IWCORE TC AVERAGE TEt(P S/G A TOTAl AUX FEETiMATER FLI{S/G B.OTAL AUX FEEDMATER FLOM N7R AUXILIARY FEEDMATER PU)(P A MTR AUXILIARY FEEDMA7ER PUHP B AUX FM PUt4P STEAtl SUPPLY VALVE A AUX Rl PUicP STEA)(SUPPLY VALVE B OFF OFF CLOSED CLOSED VALUE QUAL No ATMS GOOD NQT TRIP GOOD 1.00000+00 INHB 1.00000+00 INHB 6.85487M INHB 6.36793M INHB 96.19 6009 2280.HMRt(48.7 GQQD 98.4 6009 97.3 600D NOT TRIP 600D NOT TRIP 6000 47.2 Goo'2.2 6009 52.2 6000 7()0.GOOD 698.GOOD NQT TRIP GOOD NOT TRIP GOOD NOT TRIP 600D NQT TRIP 6009 NOT TRIP DEL NOT TRIP DEL TRIPPED GOOD TRIPPED GOOD~Oh GOOD 1.7 GQQD LONER GOOD LOMER 6009 LONER GOOD LOMER 600 D LOMER 600 D LONER 600D LONER GOOD LOWER GOOD LONER GOOD LOMER 6009 600.9 GOOD 600.9 GOOD 544.1 GOOD 545.4 GOOD 572.5 600D 573.1 GQQD 99.3 GOOD 604.6 Goo'.6000 0.6000 GOOD GOOD GOOD 600D E.U.CPS CPS Al(P At(P y.PSIG 7.X DEGFÃ/PSIG PS16 PSIG FKT DEGF KBF DEGF DE6F DEGF DEGF X DEGF Pt(GPt(

OCT 8~1992 07:44 R.E.GINA SIMULATOR TREND 6ROUP ASSIGNNEhT RNNARY PAGE 2 6ROUP: EVENTl PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P2ib0 5b P2ibi 57 BKR041 58 BKR042 5'9 BKRO43 b0 BKR044 E-0-J DESCRIPTION SAFE IN:ECTION LOOP A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SERVICE WATER PNFS A&B HEADER SERVICE WATER PlÃi'S C&D HEADER SERVICE WATER PUNP A SERVICE MATER PUP B SERVICE MATER PUtF C SERVICE WATER PtNP D I ON ON ON OFF VALUE QUAL 0.6009 0.6009 81.6009 73.GOOD 6000 GOOD GOOD GOOD E.U.9'N GPN PSIG PSIG

~~~GRAM NAME:LRGTSZ.E.E.GINNA NUCLEAR PSIER PLANT OCT 08,92 07:46:00 TREND GROUP ASSIGNMENT

SUMMARY

GROUP NAHE EVENT 2 GROUP DESCRIPTIOH PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43-F0619 I LRHST'NS033 l$033 NT033 MT250 lQT2 R01 R02 R05 R09 R34 R35 R10A R1'1 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R'l5A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPOHENT COOLING LOOP TOTAL FLll REFUELIHG HATER STORAGE TANK LVL 33 FOOT LEVEL IJIND SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-CONTAINMENT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PANEL CONTAINMENT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE CONTAINMENT GAS MONITOR PLANT VENT IODINE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID HASTE DISPOSAL MONITOR STEAH GEHERATOR BLSSOMN DRAIN AREA 29-COHTAINHEHT HIGH RANGE AREA 30-CONTAINMEHT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-HID RANGE GAS CV VENT CHAH 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOU RANGE GAS PLANT VENT CHAN 7-MID RANGE GAS PLAHT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOU RAHGE GAS AIR EJECTOR CHAN 7-HID RAHGE GAS AIR EJECTOR CHAN 9 HI RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE 8 (SPING)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERHEDIATE LVL 6 FT TEHP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEHP¹17 1485.94.5 3.8 215.53.5 55.6 2.1 9.02214-02 6.40678+00 1.39946+00 3.40701+01 9.09354-01 1.09283+00 9.58715401 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 4.07174+03 5.05861-01 5.09440.01 1.25835+05 1.89699.07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 6.29179-03 6.29392-03 6.29436-03 1.02040-02 1.01048-02

.0 95.1 106.0'106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH HEARN GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM MPH DEG.DEGF DEGF OEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPM CPM CPM CPM CPM CPH CPM R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/NR DEGF DEGF DEGF DEGF DEGF DEGF Time: 0759 Message: 4X~GI~NA TATIGN 1 2 EVAL ATED EXER I E MESSAGE FORM~MI: M I<<G<<IR RMI Pp Simula ed Plan Condi ions:~Messe e: """THIS IS AN EXERCISE">>" Declare an UNUSUAL EVENT in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification," EAL: Steam Generator Tube Rupture (SGTR);Steam Generator Tube Leakage).1 gpm as identified by sampling gr EAL: Reactor Coolant Leakage (RCS);Steam Generator Tube Leakage>.1 gpm as identified by sampling.FOR CONTROLLER USE ONLY Controller Notes: d li lyif G Id P P d I d.~ddli if Emer enc Cla ification dis ussions are in ro r s.An ici ated Re ult: 1)Deliver contingency message if Unusual Event not declared or is not being discussed.

Time:~75!j Message:~~l~NA Aff N 1992 EVALUATED EXER ISE MES A EF RM~MI: NI I N IN Sim la ed Plan Con i ions:~Messe e: """THIS IS AN EXERCISE>>"" The"A" S/G ARV has inadvertently opened.FOR CONTROLLER USE ONLY~NI I N 1)When operators try to manually close the"A" S/G ARV, it will not close.2)Controller to go with Auxiliary Operator sent to Steam Header with Mini-Scenarios for"A" 8c"B" S/G ARV problems.Antici ated Results: 1)Operator should shift the"A" S/G ARV Controller to manual and try to close it.2)Control Room should send an Auxiliary Operator to the Steam Header area to close the isolation valve on the"A" S/G ARV when it cannot be closed from the Control Board.

Time:~755 Message:~GINNA STATION 1992 EVALUATED EXER I E~ME SAGE FDRRI I: A III FDF<<I I<<R A SIGARV Sim la Plan C ndi ion: See the Attached Sheets~INesse e:<<>>>>THIS IS AN EXERCISE">>" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate actions are simulated or investigations are made by the Auxiliary Operators sent to isolate the"A" S/G ARV.Antici ated Results: 1)As per Mini-Scenario Anticipated Results.g-32

~GINN4 TATIDN J 1992 EVALUATED EXER I E MINI-SCENARIO Ac1~ivi y: Isolation of"A" S/G ARV and steam leak detection on the"B" S/G ARV.FOR CONTROLLER USE ONLY 1)Ensure Auxiliary Operator (AO)simulates closing manual valve 3507 ("A" S/G ARV Isolation Valve).After AO completes simulating the isolation of the"A" S/G ARV, but prior to informing the Control Room, Controller must notify Simulator Control Booth Operator at Ext.6641 that the valve is isolated.~lnf~r the AO that the"B" S/G ARV inlet steam line has a moderate leak on it between the ARV and the isolation valves (see attached sketch).2)Ensure AO simulates checking manual valve 3507A ("A" S/G ARV Isolation Valve, Bypass Valve)closed.3)4)If the Control Room requests the AO to isolate the"B" S/G ARV, after being informed of the leak, use the"Isolation of'8'/G ARV" Mini-Scenario.

ANTICIPATED RESULTS 1)AO should simulate isolating the"A" S/G ARV.2)AO, after simulating the isolation of the"A" S/G ARV and being informed of the"B" S/G ARV steam line leak, should inform Control Room of the isolation and leak.

ROCHESTER GAS ANO EI.ECTRIC CORPORATION GINNA STATION'OB:

SkmrC~c DATE'Zg@y 5(gg~g.gg~MADE BY: PAGE OF Time:~7~Message: 7 INNA TATION 1 2 EVALUATED EXER I E~ME ER E FORM MMfL: R F f T R Rf g d F ff g"R" E/GERT M fd problem.Sirnula d Plan C n i i n: See Attached Mini-Scenario

~IVlesse e: M<<MTHIS IS AN EXERCISE>>"" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate investigations are made by the Repair Team.Antici a ed Results: 1)As per Mini-Scenario Anticipated Results.

GINNA STATION 1992 EVALUATED EXERCISE MINI-SCENARIO Ac1~ivi y: Inadvertent Lifting of ARV-3411-"A" S/G ARV Mercoid Control Problem Repair Team (Checking Problem and Repair).Initial Conditions:

Method of Initiation:

Loud noise heard in Control Room and throughout plant.ARV-3411 open light lit;closed light extinguished.

Indications:

ARV-3411 1.Controller output level reads zero.2.Open light lit.3.Closed light extinguished.

4.Computer alarm.Expected Sequence of Actions: 1.Operations manually isolates ARV-3411.2.I/C will be called in to troubleshoot and repair.3.I/C should monitor the following:

-HC-468 output meter at zero,-ARV-3411 valve positioner:

Input signal at 2 psi Output pressure at 0 psi-Solenoid 3411S energized;

-PS-2092 has mercury in trip position.4.I/C should replace mercoid switch with spare.Final Condition; I/C replaces and calibrates PS-2092.Turns over to Operations for functional check.

Time: 0800 Message: 8 GINNA STATION 1992 EVALUATED EXERCISE MESSAGE FORM 8 I<<C IR Simulated Plan Conditions:

SEE ATTACHED SHEETS~essacee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1)Operators should be performing the applicable actions of the following procedures:

a)0-6.10 (Plant Operation with Steam Generator Tube Leak Indication).

b)0-2.1 (Normal shutdown to hot shutdown).

c)S-3.3C (H2 or 0, Removal from Primary System by Burping Volume Control Tank with N,)d)S-3.3D (CVCS Cation Demineralizer BED operations using Deborating Dl A Unit).2)The Plant Manager, Operations Assessment Manager and Duty Engineer should be manning the TSC for offsite Communications assistance per EPIP 1-5.8-36 199P'EVALUATED EXERCISE Time:~'bO MAZOR PAEVLHETERS Reactor Shutdown~YES~O N-3 1 O CPS N-32 O CPS N-35'I~OS AMPS N-36 CW-AMPS Avg.Nuclear Power RCS Pressure~2.S.C PSIG PRZR Level 9~7 A RCP'NNI G STOPPED B RCP RUNN G STOPPED 1A S/G Level 1B S/G Level~.I 0 lA S/G Pressure~'~PSIG 1B S/G Pressure PSIG Turbine/Generator N OFFLINE ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 O GPM FI-925 0 GPM 1A.INSERV B OOS 1B.INSERV TB OOS 1'NSERV TB OOS BAST Level=Low Head S.I.Pum s FI-626 O G M 1A.INSERV OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s 4 KV Buses RGIZED DEENERGIZED 48OV Buses NERGIZ DEENERGIZED DC Batteries A$54VOLTS B/SOVOLTS nmt Pressure~b lo PSIG nmt Sump A Level~FEET Cnmt Sump B Level INCHES A Loop Hot Leg~i+7 OF A Loop Cold Leg 53'4 7 OF B Loop Hot Leg 9 OF B Loop Cold Leg 9.OF RVLIS*CET~.3 OF S/G A Total Aux FW Flow O GPM 9/G B Total Aux FW Flow O GPM DIESEL GENERATORS A.RUNNING UNLOADED STB OOS B.RUNNING UNLOADED S B OOS TSC RUNNING UNLOADED STBY OOS Security RUNNING UNLOA D TB OOS FI-93 1A O GPM FI-931B 2)GP lA.INSERV TB OOS 1B.INSERV TB OOS NaOH Tank Level=Containment ecirc Fans 1A.SE STBY OOS 1B.NSER STBY OOS 1C.INSE V B OOS 1D.SE STBY OOS Post Accident Dampers OPEN LOSE Service Water Pum s 1A.SERV STBY OOS 1B.NSE STBY OOS 1C.NSERV ST Y OOS 1D.IN V STB OOS A&B Header Pressure 8 PSZG Com onent Co lin Water Pum s 1A.ST OOS 1B.INSERV T OOS Surge Tank Level=~'G ENGINEERED SAFEGUARDS Standb Aux.Feed ater Pum s 1C.INSERV TB OOS 1D.INSERV T Y OOS Aux.Feedwater Pum s 1A.INSERV TB OOS 1B.INSERV TB OOS Turb.Driven NSERV STB OOS ST Level~~FE*CET,=Average of Selected Core Exit, Thermocouples

'

OCT 8i 1992 07:59 R.E.GINA SINULATOR TREND GROUP ASSIGHNEI(T SUGARY PA6E 1 GROUP: EVENT1 PROCEDURE:

EPIP 1-5 POINT ID KSCRI TION PLANT STATUS E.U.1 2 3 5 6 7 8 9 10 ll 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 46 47 48 49 50 51 52 ATKi RXT N31 N32 N35 N36 NP PRCS LPZR FR(" A FRCLB RXT16 RXT17 TSUBTC LSBA LSBB PSBA PSGB GENBKRl GENBKR2 BUS11A BUS11B BUS 12A BUS12B B11A12A B11B12B PCV LS(IPA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVBAMID TAVBBWID LRV TCCORE FAUXF WA FAUXFMB BKR081 BKR082 V3505 V3504 ANTICIPATED TRAHSIEHT M/0 SCRAN REACTOR TRIP BREAKER STATUS SONCE RANGE DETECTOR N-31 SIKE RANGE DETECTOR N-32 INTERNEDIATE RANGE DETECTOR N-35 INTERNEDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEN AVG PRESS PRESSURIZER AVERAGE LEVEL REA"TOR COOLANT LOOP A AVG FLOW REACTOR COOLNT LOOP B AVG FLOW RCPA BREAKER CRUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED NARBIN STN GEN R NARROW RANGE AVG LEVEL STN GEH B NARROW RANGE AVG LEVEL STN GEN A AVERAGE PRESSURE STN GEN B AVERAGE PRESSURE GBERATOR ON LINE BREAKER lG1372 GENERATOR GN LINE BREAKER 9X1372 BUS liA SUPPLY BREAKER BUS 11B SUPPLY BREAKER NOT TERNINATED Ot(PPCS (7/19/91)NOT TERNIHATED ON PPCS (7/19/91)BUS 11A TO 12A TIE BRENER BUS 1lB To 12B TIE BRENER COHTAINNENT AVERAGE PRESSURE CONTAIN)(ENT SUNP A AVEImBE LEVEL SSP B LEVEL 8 INCHES (TRAIN A)SU)P B LEVEL 8 INCHES (TRAIN B)SU)P B LEVEL 78 INCHES (TRAIN A)SNP B LEVEL 78 INCHES (TRAIN B)SU@B LEVEL 113 INCHES(TRAIN A)SU%'LEVEL 113 INCHES(TRAIN B)SU%'LEVEL 180 INCHES(TRAIN A)SSP B LEVEL 180 INCHES(TRAIN B)SSP B LEVEL 214 INCHES(TRAIN A)SSP B LEVEL 214 INCHES(TRAIN B)RCLR HOT LEG TENPERATUlK'CLB HOT LEG TENPERATURE RCLA COLD LEG TEIIPERAT(SE RCLB COLD LEG TENPERAT(HE RCLA TAVG (THOT/TCOLD WIDE RHB)RCLB TAVG (THOT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 INCORE TC AVERA6E TENiP S/G A TOTAL AUX FEEDWATER FLOP S/6 B TOTAL AUX FEEDWAMa FLOW NTR AUXILIARY FEEDMRTER PU)IP A NTR AUXILIARY FEEDMATER PUNP B AUX FM PUIF STENI SUPPLY VALVE A AUX FM PUNP STEAN SUPPLY VALVE B NO ATMS HQT TRIP 1.00000+00 1.000NMO 7.01454-04 6.51626M 98.61 2263.44.7 98.9 97.8 NOT TRIP NOT TRIP 47.8 52.2 52.1 666.668.NOT TRIP NQT TRIP NOT TRIP HOT TRIP NOT TRIP NOT TRIP TRIPPED TRIPPED~06 1~8 Lo)IER LO)IER LG)E'ER LONER LOWER LONER LOWER LONER LONER LONER 598.7 598.7 539.9 541 F 6 569.3 570.2 99.5 602.3 0.0.OFF OFF CLOSED CLOSED GGGD 600D INHB IHHB INHB INHB 6009 HMRN GOOD 6009 600D GOOD 6009 600<<6009 6009 6009 GOOD GGQD GOOD GOOD 6009 DEL DEL 6009 6009 6009 GOOD GOOD GOOD GOOD 6009 6009 GOOD GOOD 6009 6009 6009 6009 GGGD GOOD 6009 6009 6009 GOOD 600<<6009 GQGD 6009 6009 GOOD 6009 CPS CPS ANP ANP/PSIG X I/X KGF>/7.PSIG PSIG KBF K6F KGF DE6F KGF KGF DEGF PN GPN 0

OCT Gs 1992 07:59 R.E.GINA SltiULATOR TREND GROUP ASSIGtttiENT SUtitiARY PAGE 2 53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 SAFETY INJECTION LOOP A AVG FLOM SAFETY INJECTION LOOP B AV6 FLOM SERVICE MATER PlIPS A h B HEADER SERVICE MATER PNPS C 5 D HEADER SERVICE MATER PNiP A SERVICE MATER PUtiP B SERVICE MATER PlIP C SERVICE MATER PUtiP D 6ROUP: EVEt)TI PROCEDURE:

EPIP 1-5 POINT ID DESCRIPTION PLAtlT STATUS VALLEY 0.0.81.73.ON ON ON OFF QUAL E.U.GOOD G.V GOOD IFN GOOD PS16 GOOD PSIG GOOD GOOD GOOD GOOD EMJ

~~~GRAM NAME:LRGTSZ.E.E.GlkkA NUCLEAR POWER PLANT OCT 08,92 08:00:00 TREND GROUP ASSIGNHEHT

SUMMARY

GROUP kAME EVENT 2 GROUP DESCR IPT ION PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURREHT VALUE QUALITY CODE EHGR UNITS 1 2 3 5 6 7 8 9 10 11 12 13 14 20 21 22 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43-F0619 LRWST WS033 W0033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COMPOHENT COOLING LOOP TOTAL FLW REFUELIHG WATER STORAGE TANK LVL 33 FOOT LEVEL WIHD SPEED 33 FOOT LEVEL WIND DIRECTIOH 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEHPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-CONTAINMENT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MOHITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAHPLE PANEL CONTAINMENT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE CONTAINMENT GAS MONITOR PLANT VENT IODIHE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID WASTE DISPOSAL MOHITOR STEAM GENERATOR SLOWDOWN DRAIN AREA 29-CONTAINHEHT HIGH RAHGE AREA 30-CONTAINHEHT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-HID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOW RAHGE GAS PLANT VENT CHAk 7-MID RANGE GAS PLANT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAN 9-'Hl RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE 8 (SPING)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEHP¹8 CV INTERHEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485~94.5 3.6 222.57.7 58.0 0.3 9.02214-02 6.40678+00 1.39946+00 3.40701+01 9.09354-01 1'9283+00 9.58719+01 5~18901+02 7.38002+02 4.30543t01 8.58327+01 4.22831+01 2.78658i03 4.07174+03 5.05861-01 5.09440-01 1.25835+05 1.89699.07 2.53990-02 3.57435-05 1.41261-03 4'0312-07 6.86543-05 3.72621-03 6.29179-03 6.29392-03 6.29436-03 1.02040.02 1.01048-02

.0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD HALH HWRN GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM MPH DEG.DEGF DEGF DEGF HR/H HR/H MR/H MR/H MR/H MR/H CPH CPM CPM CPH CPM CPM CPM CPM R/HR R/HR CPM UCI/CC HR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR HR/HR X DEGF DEGF DEGF DEGF DEGF DEGF Time:~~1 Message:~GINNA STATION 1 2 EVAL ATED EXER I E MESSAGE FORM f: A ill YOp<<i I 1'B" S/GARV Simula ed Pl n Condi ion: See Attached Mini-Scenario

~ll/lesss<<<<<<THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller No es: 1)Provide information verbally when appropriate actions are simulated by the Auxiliary Operator sent to isolate the"8" S/G ARV.An ici ated Results: 1)As per Mini-Scenario Anticipated Results.

GINNA STATION 1992 EVALUATED EXERCI E MINI-CENARI Act~ivi y: Isolation of"B" S/G ARV FOR CONTROLLER USE ONLY Controller Notes: 1)Ensure Auxiliary Operator (AO)simulates closing manual valve 3506 ("B" S/G ARV Isolation Valve).2)Ensure AO simulates checking manual Valve 3506A ("B" S/G ARV Isolation Valve, Bypass Valve)closed.3)The i ola i n of h"B" S G ARV mus e c nsid re done nd r Con rol Room S ri r 1045.Antici ated Results: 1)AO should simulate isolating the"B" S/G ARV.2)AO should inform the Control Room of the"B" S/G ARV isolation.

Time: 0815 Message:~1 GINNA STATION 19 2 EVALUATED EXERCISE MESSAGE FORM~f: 8 I<<R<<IR Simula ed Plant Conditi ns: See the Attached Sheets~Masse e: """THIS IS AN EXERCISE""" The following annunciators are received:~G-22 (ADFCS System Trouble)FOR CONTROLLER USE ONLY Controller Notes;1)When operators check the Control Board, inform them that the"MFW Reg Valves are controlling and all Control Board indications are normal.Antici ated Results: 1)Operators should perform the applicable actions of AR-G-22 and ER-INST.1.

2)Operators should check the S/G levels to ensure proper level control.3)Operators should simulate checking the ADFCS Printer for cause of failure (ADFCS printer read out on attached Mini-'Scenario).

4)Operators should inform the people manning the TSC and ISC Department of the ADFCS problem.5)Operators should inform people manning the TSC of the"B" S/G ARV line steam leak.

Time:~8~1 Message:~1 Qgn~in gg 6)Operators may request Auxiliary Operator to isolate the"B" S/G ARV.7)Operators should inform the people manning the TSC of the"A" S/G ARV problem and isolation.

8)Operators continue shutting the Plant down per 0-2.1.9)People manning the TSC may request the"B" S/G ARV be isolate gr may wait until Maintenance personnel have inspected it.10)People manning the TSC amy inform Control that they will take actions to have Maintenance personnel inspect for the"A" and"B" S/G ARV problems.

199<'VALUATED EXERCISE Time: 05'l5 MAJOR PAT%METERS ENGINEERED SAFEGUARDS Reactor Shutdown N-31 N-32 N-35 N-36 Avg.Nuclear Power RCS Pressure PRZR Level A RCP UNN B RCP UN 1A S/G Level 1B S/G Level lA S/G Pressure 1B S/G Pressure Turbine/Generator ONL 4 KV Buses ERGIZ 480V Buses RGIZ DC Batteries A~SaVOLTS Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level A Loop Hot Leg A Loop Cold Leg B Loop Hot Leg B Loop Cold Leg RVLIS*CET S/G A Total Aux FW Flow S/G B Total Aux FW Flow YES 0~CPS CPS AMPS AMPS PSIG ING STOPPED N STOPPED~e 3 PSIG.0 PSIG FFLINE DEENERGIZED DEENERGIZED B ($0 VOLTS.o6 PSIG~FEET~g INCHES~feZ OF~ST&OF OF mmkoF~1~0 GPM O'PM DIESEL GENERATORS OOS Aux.Feedwate m s 1A.INSERV OOS 1B.INSERV TB OOS Turb.Driven INSERV STB OOS CST Level~~F A.RUNNING UNLOADED T OOS B.RUNNING UNLOADED OOS TSC RUNNING UNLOADED T OOS Security RUNNING UNLOADED TB ENGINEERED SAFEGUARDS Hi h Head-S.I.Pum s FI-924GPM FZ-925~GPM 1A.INSERV T OOS 1B.INSERV TB OOS 1C.INSERV B OOS BAST Level=Low Head S.I.Pum s FI-626 0 GPM 1A.INSERV TB OOS RECIRC 1B.INSERV TBY OOS RECIRC RWST Level=Containment S ra Pum s FZ-931A~GPM FI-931B~GPM 1A.INSERV S B 1B.INSERV TB NaOH Tank Level=OOS OOS Contain Recirc Fans 1A.NSE STBY OOS 1B.NSE STBY OOS 1C.IN V TB OOS 1D.SER STBY OOS Post Accident Dampers OPEN LOS D Service Wate Pum s 1A.SE STBY OOS 1B.NSE STBY OOS 1C.NSE STBY OOS 1D.INSERV TB OOS A&B Header Pressure~PS1G Com onent Coolin Water Pum s 1A.SER STBY OOS 1B.INSERV TB OOS Surge Tank Level=~'o Standb Aux.Fee water Pum s 1C INSERV B OOS~1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples

Gi 1992 08:14 R.E.GINA SIMULATOR TREND GROUP ASSIGIST SUtIARY PAGE 1 GROUP: EVENT1 PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE E.U.1 2 3 4'5 6 7 8 9 10 il 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 ATt6 RXT N31 N32 N35 N36 NP PRCS LP2R FRCLA FRCLB RXT16 RXTD TSUBTC LSGA LS68 PSGA PSGB GENBKRl GENBKR2 BUSliA BUS118 BUS12A BUS128 811A12A 8118128 PCV LSNPA L0942E L0943E L0942D L0943D L0942C L0943C L09428 L09438 L0942A L0943A T0409A T0410A T0450 T0451 TAVGA MID TAVBBWID LRV TCCORE FAUXFMA FAUXFMB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT M/0 SCRAM REACTOR TRIP BREAKER STATUS SolSCE RANGE DETECTOR N-31 SO(SCE RAt(GE DETECTOR N-32 INTERMEDIATE RANGE DETECTOR N-3S INTERMEDIATE RANGE DETECTOR N-36 AVERAGE NUCLEN POWER REACTOR CGOUIT SYSTEM AVG PRESS PRESSURI 2ER AVERAGE LEVEL REACTOR COOLA%'OOP A AVG FLOW REACTOR COOLANT LOOP 8 AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCGRE TC SUIG)GLED NARiIN STM GEN A NARROW RANGE,AVG LEVEL STM GEN 8 NARROW RANGE AVG LEVEL STM GEN A AVERAGE PRESE)RE STM 6EN 8 AVERAGE PRESSURE GYRATOR ON LINE BREAKER 161372 GBERATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 118 SUPPLY BREAKER t<OT TERMINATED 0)I PPCS (7/19/91)NGT TERMII(ATED ON PPCS (7/19/91)BUS 11A TO 12A TIE BRENER BUS 118 TQ 128 TIE BRENER COt(TAINMENT AVERAGE PRESSURE CONTAINMENT SUMP A AVERAGE LEVEL SUIP 8 LEVEL 8 INCHES (TRAIN A)SUIP 8 LEVEL 8 INCHES (TRAIN 8)SUIP 8 LEVEL 78 INCHES (TRAIN A)SU)P 8 LEVEL 78 INCHES (TRAIN 8)SU)P 8 LEVEL 113 INCHES(TRAIN A)SUtP 8 LEVEL 113 INCHES(TRAIN 8)SU)P 8 LEVEL 180 INCHES(TRAIN A)SUtP 8 LEVEL 180 INCHES(TRAIN 8)SU)P 8 LEVEL 214 INCHES(TRAIN A)SIP 8 LEVEL 214 INCHES(TRAIN 8)RCLA HOT LEG TEMPERATUfK RCLB HOT LEG TEMPERATURE RCLA COLD LEG TE)IPERAT(HE RCLB COLD LEG TE)IPERAT(SE RCU)TAVG (THOT/TCOI.D WIDE RNG)RCLB TAVG (THGT/TCGLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL Ei.l INCORE TC AVERAGE TEMP S/6 A TOTAL AUX FEHIATER FLOM S/6 8 TOTAL AUX FEEDMATER FLOW MTR AUXILIARY FEEDNATER PlNP A MTR AUXILIARY FEEDMATER PlNP 8 AUX FM PU)P STEA)I SUPPLY VALVE A AUX FM PUI(P STEA)I SUPPLY VALVE 8 No ATN NOT TRIP 1.00000+00 1.00000+00 6.66807M 6.16593M 93.56 2264.47.9 98.4 97.3 NOT TRIP NOT TRIP 47.9 S2.0 52.1 703.701.NOT TRIP NGT TRIP NOT TRIP NOT TRIP NOT TRIP NOT TRIP TRIPPED TRIPPED.06 1.8 LONER LOWER LOWER LONER LONER LONER LOWER LOWER LONER LONER 599.2 599.2 543.5 544.8 571'572.0 99.3 602.6 0.0.OFF OFF CLOSED, CLOSED 600D GOOD INH8 CPS INHB CPS INHB AMP INHB AMP 6009 6000 PSIG Boon/6009 K GGGD/6000 6000 Gooe KGF Boon/6000 6009 psiG GOOD PSI6 6009 600D GOOD 6000 DEL DEL Goon GOOD 600 D PSIG 6009 FEET 6000 Goon Goon 6000 GOOD 6000 GOOD Goon 6000 BGGD 6009 DEGF 600D DEGF BGGD DE6F 6000 DEBF Boon 9 GF GOOD DEGF GOOD/Booe DEGF GOOD GPM 6000 6PM GOOD GGGD GGGD 6000 OCT 8~1992 08: 14 R.E.GINA S1%LATOR TREND GROUP ASSIGNMENT SUtDIRY PAGE 2 6ROUP: EVM'I PRXEDURE!EPIP 1-5 PLAftT STATUS POINT ID DESCRIPTION VALLEY DUAL E.U.53 FSIA 54 F GIB 55 P2 160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 SAFETY INJECTION LOOP A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SERVICE MATER PfIPS A h B HEADER SERVICE WATER PUffPS C 5 D HEADER SERVICE WATER PUffP A SERVICE MATER PUNP B SERVICE WATER PUtfP C SEfNICE MATER PUtfP D ON ON ON OFF 0.0.82.730 GOOD PN GOOD GPN GOOD PSIG GOOD PSIG GOOD GOOD 600D GOOD OGRAM NAHE:LRGTSZ.E R.ED GINNA NUCLEAR PONER PLANT OCT 08,92 08:15:00 TREND GROUP ASSIGHHENT SUHHARY GROUP NAME EVENT 2 GROUP DESCRIPT IOH PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 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-F0619 LRMST MS033 MD033 MT033 llT 250 lST2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLll REFUELIHG MATER STORAGE TANK LVL 33 FOOT LEVEL lllND SPEED 33 FOOT LEVEL MIND DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-CONTAINMENT AREA 5-SPENT FUEL PIT AREA 9-LETDSN LINE MONITOR AREA 34 AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PAHEL COHTAIHMENT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE CONTAINMENT GAS MOHI TOR PLAHT VENT IODINE MOHITOR R'IOB AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID IIASTE DISPOSAL MONITOR STEAM GENERATOR BLOSOMH DRAIN AREA 29-CONTAINMEHT HIGH RANGE AREA 30-COHTAINHEHT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAH 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOU RAHGE GAS PLANT VENT CHAN 7-MID RAHGE GAS PLANT VENT CHAN 9 HIGH RANGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 3'I STEAM LINE A (SPING)AREA 32 STEAM LINE B (SPING)CV HYDROGEN CONCENTRATION CV BASEMEHT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERHEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEHP¹17 1485.94.5 3.6 194.58.7 58.0.0.7 9.02214-02 6.40678+00 1.39946i00 3.40701+01 9.09354.01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658i03 4.07174+03 5.05861-01 5.09440.01 1.25835+05 1.89699.07 2.53990-02 3'7435-05 1.41261-03 4.40312-07 6.86543.05 3.72621-03 6.29179.03 6.29392-03 6.29436-03 1.02040.02 1.01048.02

.0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM HNRH GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPH MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPM CPM CPM CPM CPM CPM CPM'/HR R/NR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR x DEGF DEGF DEGF DEGF DEGF DEGF Time:~$15 Message: 11 GINNA STATI N 1 92 EVALUATED EXER I E~ME A EF RM~f: E'EIGAIIEM M k k~Ff T Simulated Plant Condi ions: See Attached Mini-Scenario

~Mess e:<<""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~GI I R 1)Provide information verbally when appropriate investigations are made by the"B" S/G ARV Line Steam Leak Repair Team.Antici a ed Results: 2)As per Mini-Scenario Anticipated Results.

GIN NA STATION 1992 EVALUATED EXERCISE MINI-SCENARIO Ac1~ivi y: "B" S/G ARV Line Steam Leak Investigation and Repair Initial Conditions:

Steam pressure at Main Steam Header per scenario.Method of Initiation:

Aux.Operator observing conditions in area, notifies Control Room of steam leak in the location of the"B" Steam Header.'ndications:

Large amount of steam at the flange area of"8" S/G ARV, Steam coming from hole drilled in weld and inlet flange leading to valve AOV-3410 (see attached sketch).Expected Sequence of Actions: 1.Notify TSC Maintenance support group, 2.Pipe Shop Planner/Welder notified.3.Pipe Shop Planner/Welder investigate for repairs.4.Initiate packages for repairs.5.Pipefitter/Welders crews sent out to make repairs.6.Repairs completed and service restored.Final Condition:

Notify TSC of completion of maintenance and remove holds for testing and return to service.

GINNA STATION: lOB: SA'&7GH o ROCHESTER GAS ANO ELECTRlC CORPORATlON DATE: MADE BY: 4%140 S PAGE OF Time:~~1 Message:~2 NINNA STATION 1 2 EVALUATED EXER I E MESSAGE FORM SSNNNLIAL:

MFFN N N I I II V I IADFNS T Sl I N S I T I P n i i: See attached Mini-Scenario

~Mesc e: """THIS IS AN EXERCISE""" FOR CONTROLLER U E NLY~CII N 1)Provide information verbally when appropriate investigations are made.2)Controller must notify Simulator Control Booth Operator at Ext.6641 to coordinate actions associated with this Mini-Scenario.

An ici e Re Its: 1)As per Mini-Scenario anticipated results.

ROCHESTER GAS AND ELECTRIC NIINNA T Tl N MINI SCENARIO TITLE: INITIAL CONDITIONS:

ADFCS Trouble G-22 In Alarm Graphics show that QAM on left block as"BACKUP ROLE" on a yellow background and QAM on the right block as"PRIMARY ROLE" on a green background.

METHOD OF INITIATION:

Program simulator to give annunciator 6-22.INDICATIONS:

At ADFCS Printer in the MUX Room will print out the following messages: 1)Date Time DIGITAL SCAN ALARM ADFCSTRB ADFCS SYSTEM TROUBLE ANNUNC.~2)Date Time DIGITAL SCAN ALARM K10FCVA RELAY K1 OPENED FCV A Graphics show that QAM on left block as"PRIMARY ROLE" on green background and QAM on right block as"BACKUP ROLE" on yellow background.

The following error messages will be seen on the graphics display: 7.Switchover defeated.(Switchover trigger is latched.Reset trigger when switchover demand has been cleared).11.Possible defective K1 relay or QCI input.Replace relay K1 when A/A logic=0.EXPECTED SEQUENCE OF ACTIONS:~Notify maintenance support group~ISC Planner receives T.R.~ISC Planner investigates T.R.~IRC Technicians go to Maintenance Training System to replace defective K1 relay~Clear all alarms FINAL CONDITIONS'otify Simulator Control Room that maintenance is complete.

Time:~39 Message:~1 Nll~NA NT Tl N 19 2 EVALUATED EXER I E MESSA E F RM Nle~f: Ni I<<C<<IN Simulated Plant Conditions:

See the Attached Sheets~Me ss e:<<<<<<THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~CI I N 1)A CCW System leak of 20 gpm starts at this time.The leak is on the 1A CCW Pump mechanical seal~Antici a ed Resul s: 1)Operators continue shutting the Plant down per 0-2,1, 199Z EVALUATED EXERCISE Time: 0 F3O ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s MAJOR P2Q&METERS FI-924 O GPM FI-925~GP 1A.INSERV TB OOS 1B INSERV TB OOS 1C.INSERV TB OOS BAST Level=Low Head S.I.Pum s FI-626 O G M 1A.INSERV TB OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s FI-931A 0 GPM FI-931B~GPM 1A.INSERV TB OOS 1B.INSERV TB OOS NaOH Tank Level=Containm ecirc Fans 1A.SE STBY OOS 1B.NSER STBY OOS 1C.INSERV B OOS 1D.S STBY OOS Post Accident Dampers OPEN LOSED Service ter Pum s 1A.NSE STBY OOS 1B.STBY OOS 1C.NSE STBY OOS 1D.INS RV B OOS A&B Header Pressure DIESEL GENERATORS A.RUNNING UNLOADED B OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB 8 PSIG Com onen Coolin Water Pum s 1A.NSER STBY OOS 1B.INSERV STB OOS Surge Tank Leve=S O OOS ENGINEERED SAFEGUARDS, Reactor Shutdown YES~@N-31 O CPS N-32 C7 CPS N-35 AMPS N-36 AMPS Avg.Nuclear Power RCS Pressure 2.X.LZ PSIG PRZR Level A RCP STOPPED B RCP UNNING STOPPED 1A S/G Level~z.I 1B S/G Level~..I 1A S/G Pressure PSIG 1B S/G Pressure o7 PSIG Turbine/Generator NLI OFFLINE 4 KV Buses ERGIZ DEENERGIZED 480V Buses ERGIZED DEENERGIZED DC Batteries A/SOVOLT BISO VOLTS Cnmt Pressure~<~PSIG Cnmt Sump A Level~FEET Cnmt Sump B Level INCHES A Loop Hot Leg 9 OF A Loop Cold Leg~$.OF B Loop Hot Leg OF B Loop Cold Leg OF RVLIS*CET 40.3 OF S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow 0 GPM Aux.Feedwate Pum s 1A.INSERV OOS 1B.INSERV T OOS Turb.Driven NSERV TB OOS CST Level 2.FE Standb Aux.Feed ater Pum s 1C.INSERV OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples 8~1992 08:30 R.E.GIM(A Sit(ULATOR TREND GROUP ASSIGNNENT SUt(MY PAGE 1 6ROUP: EVENT1 PROCEDURE'PIP 1-5 PLANT STATUS 1 2 3 4 6 7 8 9 10 if 12 13 14 15 16 17 18 f9 20 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 51 52 POINT ID ATMS RXT N31 N32 N35 N36 NP PRCS LPLR FRCLA FRCLB RXTI6 RXT17 TSUBTC LSGA LSGB PSGA PSGB GENBKR1 GENBKR2 BUS11A BUSflB BUS12A BUS12B BlfA12A B119129 PCV LSI(PA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAViiBWID TCCGRE FAUX FMA FAUXFWB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIEhT M/0 SCRAt(REACTOR TRIP BREAKER STATUS SONCE RANGE DETECTOR H-31 SGNCE RAt(GE DETECTOR N-32 INTER)(EDIATE RANGE DETECTOR N-35 INTER)(EDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR CGOUt(T SYSTBI AVG PRESS PRESSURI IER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOW REACTOR COOLANT LOOP B AVG FLQM RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOQLED HARBIN STt(GEt(A NARROW RANGE AVG LEVEL STN GEN B NARROW RANGE AVG LEVEL STN GEt(A AVERAGE PRESSURE STN GEH B AVERAGE PRESSURE GBGQTGR ON LINE BREAKER 161372 GYRATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SUPPLY BREAKER HOT TERt(INATED ON PPCS (7/19/91)NOT TERNlt(ATED ON PPCS (7/19/91)BUS llA To 12A TIE BREWER BUS 11B TO 12B TIE BREAKER COHTAINt(ENT AVERAGE PRESSURE CQNTAItNENT SUt(P A AVERAGE LEVEL SUtP B LEVEL 8 INCHES (TRAIN A)SU)P B LEVEL 8 INCHES (TRAIN B)SU(P B LEVEL 78 INCHES (TRAIN A)SU)P B LEVEL 78 INCHES (TRAIN B)SU)P B LEVEL 113 INCHES(TRAIN A)SUlP B LEVEL 113 INCOMES(TRAIN B)SU(P B LEVEL 180 INCfKS(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SUtP B LEVEL 214 INCHES(TRAIN A)SUtP B LEVEL 214 INCHES(TRAIN B)RCLA HQT LEG TE)(PERATUfK RCLB HOT LEG TEt(PERATSK RCLA COLD LEG TB(PERATNE RCLB COLD LEG TE)(PERATURE RCLA TAVG (THOT/TCOLD WIDE RNG)RCLB TAVG (THQT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 INCORE TC AVERAGE TEMP S/6 A TOTAL AUX FEEIIAPD FL(I S/G B TOTAL AUX FEEDWATER FLOW tm AUXILIARY FEEDMATER PUt(P A t(TR AUXILIARY FEEDMATER PUtP B AUX FM PUt(P STEAN SUPPLY VALVE A AUX FW PUt(P STEAN SUPPLY VALVE B VALUE NO ATWS NOT TRIP l.00000%0 1.005&00 6.48633M 6.02558-04 91.19 2262.46,7 98.5 97.3 NQT TRIP NGT TRIP 49.5 52.1 52.1 708.707.NOT TRIP NGT TRIP NOT TRIP NOT TRIP NQT TRIP NQT TRIP TRIPPED TRIPPED.N 1~9 LOVER LONER LOVER LONER LOVER LONER LOVER LONER LOWER LOVER 597.8 597.8 543.5 544.8 570.7 571.3 99.4 601.3 0.0.OFF OFF CLOSED CLOSED QUAL 6009 6009 INH9 INHB INHD INH8 6009 6009 6009 6009 6009 6009 6009 600~6009 6009 6009 6009 6009 GOOD 6009 GOOD DEL DEL 6009 6009 6009 6009 6009 6009 6009 GOOD 6009 6009 6009 GOOD 6009 6009 6009 GOOD 6009 6009 GOOD 6009 GOOD Goo>6009 6009 GGGD 6009 6009 6009 E.U.CPS CPS At)P At(P/I PSIG X y.7.KGF//I PSIG PSIG PSI6 Fry DEGF KGF KGF KGF DEGF K6F DE6F GPt(GPH OCT 8i 1992 08'30 R.E.GINA SItlULATOR TREND GROUP ASSIGtIENT SUNNARY PAGE 2 6ROUP: EVEtlT1 PRXEDURE: EPIP 1-5 PLAtlT STATUS POINT ID.DESCRIPTION VALLEY 11AL E.U.53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 SAFETY INJECTION LOOP A AVG FLOM SAFETY INJECTION LOOP B AVG FLOW SERVICE MATER PIIPS A h B HEADER SERVICE MATER PUtlPS C h D HEADER SERVICE WATER PlNP A SERVICE MATER PIP B SERVICE MATER PUtlP C SERVICE MATER PUtlP D ON ON ON OFF O.GOOD 0.GOOD 82.GOOD 73.GOOD GOOD GOOD GOOD GOOD GPtl GPtl PSIG PSIG

~~~ROGRAM NAME:LRGTS2.E R.E.GINNA NUCLEAR POWER PLANT OCT 08,92 08:31:00 TREND GROUP ASSIGNHENT SUHHARY GROUP NAME EVENT 2 GROUP DESCRIPTIOH PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 ROS R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLW REFUELING WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOH AREA 2-COHTAINMENT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUHP AREA 35-PASS SAHPLE PANEL CONTAIHMEHT IODINE MOHITOR R10A CONTAINMENT AIR PARTICULATE CONTAINHENT GAS MONITOR PLANT VENT IODINE HOHITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MOHITOR LIQUID WASTE DISPOSAL MONITOR STEAM GENERATOR BLOWDOWN DRAIN AREA 29-CONTAINHEHT HIGH RANGE AREA 30-CONTAIHHENT HIGH RANGE CONDEHSER AIR EJECTOR EXHAUST CV VENT CHAN 5 LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLAN'I VENT CHAN 5-LOW RANGE GAS PLANT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7-HID RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE B (SPING)CV HYDROGEN CONCENTRATIOH CV BASEHENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEHP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEHP¹17 1485.94.5 2.6 47.59.6 58.9.0.7 9.02214-02 6.40678+00 1.39946+00 3.40701+01 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 4.07174+03 5.05861.01 5.09440-01 1.25835+05 1.89699-07 2.53990.02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621.03 6.29179-03 6.29392-03

&.29436-03 1.02040-02 1.01048-02

.0 95.1 106.0 106.6'106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH HWRN GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM x MPH DEG.DEGF DEGF DEGF HR/H MR/H MR/H MR/H MR/H MR/H CPM CPM CPM CPM CPM CPM CPM CPM R/HR R/NR CPM UCI/CC KR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR X OEGF DEGF DEGF DEGF DEGF DEGF Time: 3@~4 Message: 14 INN A TATI N 1 2 EVAL ATED EXER I E IVIE A E F RIVI MMM f: 8 I<<1: tR Simvla d Plan Con i i n:~M~i~a"""THIS IS AN EXERCISE""" The following annunciator is received: A-13 (CCW Surge Tank Level 41.2%)FOR CONTROLLER USE ONLY Con roller No e: 1)When operators check the CCW Surge Tank level on Control Board, Inform them that it is approximately 41%and decreasing slowly.Antici a ed Results: 1)Operators should perform the applicable actions of AR-A-13.2)Operators should perform the applicable actions of AP-CCW.2.'I 3)Operators should send an Auxiliary Operator into the Auxiliary Building to identify the CCW System leak.4)Operators should inform the people manning the TSC of the CCW leak.

Time: Jg~4 Message:~5 INNA STATI N 1 2 EVALUA ED EXER E MESSAGE F RM~lli i: A iii YOI<<A ili~Bildig identify the CCW Leak.imula e Plan n i i n: See the Attached Mini-Scenario

~Maaa e: """THIS IS AN EXERCISE""" F R CONTROLLER USE ONLY N 1)Provide information verbally when appropriate actions are simulated or investigations are made by the Auxiliary Operator sent to the Auxiliary Building to identify the CCW leak.2)The Controller must notify the Simulator Control Booth Operator to coordinate all actions associated with this Mini-Scenario.

Ani i Rs I 1)As per Mini-Scenario Anticipated Results INNA TATI N 1 2 EVALUATED EXER ISE MINI-SCENARIO

~A~Ivl y: CCW Leak Identification and Isolation of the 1A CCW Pump F ONTROLLER USE ONLY~II N 1)W~hn Auxiliary Operator is within viewing distance of the 1A CCW Pump,~inf rm him that the 1A CCW Pump mechanical seal is leaking and spraying on the pump motor.2)~Wh n Auxiliary Operator is requested to isolate the 1A CCW Pump, answer the following: (a)Ensure Auxiliary Operator simulates closing manual valve 724A (CCW Pump A Discharge Block VLV).(b)Ensure Auxiliary Operator simulates closing manual valve 722A (CCW Suction Block VLV to CCW Pump A).(c)Ensure Auxiliary Operator simulates racking out the 1A CCW Pump electrical breaker (Bus'I4, Position 23A).3)When pump is isolated;.the Controller must notify the Simulator Control Booth Operator at Ext 6641 prior to allowing players to notify the Control Room/TSC.An ici a d Res I s: 1)Auxiliary Operator,~wh n informed of the 1A CCW Pump leak, should inform the Simulator Control Room.2)Auxiliary Operator,~wh n requested, should simulate isolating the 1A CCW Pump.3)Auxiliary Operator, after simulating the isolation of the 1A CCW Pump should inform Simulator Control Room of the isolation.

Time:~~4~j Message:~1 INNA TATI N 1 2 EVAL ATED EXER I E ME A E F RM~NI: N I<<C<<IR Sim la Plan Condi ion: See the Attached Sheets~Massa"""THIS IS AN EXERCISE""" F R CONTROLLER USE ONLY~CII N 1)When operators start filling the CCW Surge Tank with RMU water, inform them that the level is starting to increase slowly.Antici ated Results: 1)Operators continue performing applicable actions of AP-CCW.2.2)Operators continue shutting the Plant down per 0-2.1.8 199K'VALUATED EXERCISE Time:~OF MAZOR PARAMETERS ENGINEERED SAFEGUARDS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED ENGINEERED SAFEGUARDS OOS Reactor Shutdown YES 0 N-31~CPS N-32 CPS N-35 E AMPS N-36 AMPS Avg.Nuclear Power RCS Pressure aa Cr8 PSIG PRZR Level~9(e.A RCP N STOPPED B RCP UNNIN STOPPED 1A S/G Level~.I 1B S/G Level~./1A S/G Pressure PSZG 1B S/G Pressure 7/tr PSIG Turbine/Generator NLIN OFFLINE 4 KV Buses NERGI DEENERGIZED 480V Buses NERG ZE DEENERGZZED DC Batteries A ISo VOLTS BI8a VOLTS Cnmt Pressure~l PSIG Cnmt Sump A Level~9 FEET Cnmt Sump B Level INCHES A Loop'Hot Leg ZK2~oF A Loop Cold Leg Kf'V I OF B Loop Hot Leg.M OF B Loop Cold Leg OF RVLIS*CET t Oo.7 DF S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow C7 GPM DIESEL GENERATORS Hi h Head S.Z.Pum s FZ-924 GPM FI-925 O GPM 1A.INSERV TB OOS 1B.INSERV TB OOS 1C.INSERV TB OOS BAST Level=Low Head S.I.Pum s FI-626 0 G M 1A.INSERV T OOS RECIRC 1B.ZNSERV STB OOS RECIRC RWST Level=1.h 4 Containment S ra Pum s FI-931AGPM FI-931B E3 GPM 1A.INSERV T OOS 1B.INSERV TB OOS NaOH Tank Level=Containme t Recirc Fans 1A.SE STBY OOS 1B.SER STBY OOS 1C.INSERV TB OOS 1D.NSER STBY OOS Post Accident Dampers OPEN Service te Pum s 1A.I SE STBY OOS 1B.NSE STBY OOS 1C NSER STB OOS 1D.INSERV TB OOS A&B Header Pressure 78 PSIG Com onent C in Water Pum s 1A.NSE S BY OOS 1B.ZNSERV STB OOS Surge Tank Level=~204.SE Aux.Feedwater m s 1A.INSERV OOS 1B.INSERV T OOS Turb.Driven INSERV TB OOS CST Level 2.FEET*CET=Average of Selected Core Standb Aux.Fee ater Pum s 1C INSERV B OOS 1D.INSERV TB OOS Exit Thermocouples Gs 1992 08!45 R.E.GIMQ Sit(ULATOR TREND GIIP ASIGN)(E)IT SUt(tIARY PA6E 1 GROUP: EVENT1 PRXEDURE: EPIP 1-5 PLA)IT STATUS POINT ID DESCRIPTION E.U.1 2 3 5 6 7 8 9 10 11 12 13 14 15 16 17 18 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 ATMS RXT N31 N32 N35 N36 NP PRCS LPIR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LS68 PSGA PSBB GENBKRl GENBKR2 BUSiiA BUS11B BUS 12A BUS128 B11A12A 811B12B PCV LSIIPA L0942E L0943E L09429 L0943D L0942C L0943C L09428 L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVBAWID TAViiBMID LRV TCCORE FAUXFWA FAUXFMB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT M/0 SCfUN REACTOR TRIP BREAKER STATUS SMKE RANGE DETECTOR N-31 SINCE RANGE DETKTOR N-32 INTEf(t(EDIATE RANGE DETECTOR N-35 INTEftt(EDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEI(AVG PRESS PRESSURI ZER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOW REACTOR CGOLNT LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED t(ARGIN STI(GEN A NARROW RANGE AVG LEVEL STM GEN B t(ARROW RANGE AVG LEVEL STH BE)I A AVERAGE PRESSURE STtl GEN 8 AVERAGE PRESSURE GBGQTOR ON LINE BREAKER 161372 696QTOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SL'PPLY BREAKER NOT TERMINATED ON PPCS (7/19/91)NOT TERMINATED OM PPCS (7/19/91)BUS llA To 12A TIE BRENER BUS 11B To 128 TIE BREAKER CONTAIN)(ENT AVERAGE PRESSURE CONTAItl<IEI(T SUt(P A AVERAGE LEVEL SU)P B LEVEL 8 I)ICHES (TRAIN A)SUIP 8 LEVEL 8 INCHES (TRAIN 9)SU)P B LEVEL 78 INCHES (TRAIN A)SUIP B LEVEL 78 INCHES (TRAIN B)SUtP 8 LEVEL 113 INCHES(TRAIN A)SU)P 8 LEVEL 113 INCHES(TRAIN 8)SUtP B LEVEL 180 INCHES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SPiP 8 LEVEL 214 INCHES(TRAIN A)9PP B LE4l3.214 INCHES(TRAIN 8)RCLA HOT LEG TE)(PERATUR=

RCLB HOT LEG TE)IPERATURE RCLA COLD LEG TE)FERATNE RCLB COLD LEG TEIIPERATNE RCLA TAVB (THOT/TCOLD WIDE Rt(B)RCLB TAVG (THQT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 INCORE TC AVERAGE TEt(P S/6 A TOTAL AUX FEEDMATER FLOW S/G B TOTAL AUX FEEDMATER FLOW t(TR AUXILIARY FEEINATER PU)IP A HTR AUXILIARY FEEDMATER PU)IP B AUX FM PUI(P STEAN SUPPLY VALVE A AUX FW PlNP STEA)I SL'PPLY VALVE B NO ATMS NOT TRIP 1.0000800 1.0$N&00 6.3386AM 5.88842M 89.14 2263.46.5 98.4 97.3 NOT TRIP NOT TRIP 50.1 52.1 52.1 717.716.NOT TRIP NOT TRIP NOT TRIP NOT TRIP NOT TRIP NOT TRIP TRIPPED TRIPPED.11 1~9 LONER LONER.LONER LOMER LOMER LOMER LONER LONER LOMER LONER 597.2 597.2 544.1 545.4 570.6 571.3 99.3 600.7 OFF OFF CLOSED CLOSED 6009 GOOD INHB INHD INHB INHD 6009 600D Goon 6009 6009 6009 6009 Boos 6009 GOOD 6009 GOOD GOOD 6009 600D Boon DEL DEL GOOD 6009 GOOD 6009 Goon 6009 6009 6009 6009 6009 6009 6009 6009 Goon 6009 6009 6009 6009 6009 6009 600~Goon GOOD GOOD 6009.GOOD 6009 CPS 0%fM(P Al(P X PSIG X X X" DEBF X/PSIG PSIG DEBF DEBF DEGF DEBF DEGF DE6F DEGF GPtf GPtl OCT 8~1992 08:45 R.E.GINA SIMULATOR TREND 6ROUP ASSISNNENT SNINSY PA6E 2 6RGUP: EVENT1 PRXEDURE: EPIP 1-5 PLANT STARS POINT ID DESCRIPTION VALUE NAL E.U.53 FSIA 54 FSIB 55 P2 160 56 P2161 57 BKR041 58 IMR042 59 IIR043 60 IIR044 SAFETY INJECTION LOOP A AV6 FLOW SAFETY INJECTION LOOP B AVG FLN SERVICE@TER PNtPS A h B HEADER SERVICE NATER PLIPS C h D HEADER SERVICE NATER PNP A SERVICE NATER PIIP 8 SERVICE WATER PNrP C SERVICE NATER mP n 0.600D 6PN 0.600D GPN 82.600 D PSI6 73.6m PS16 600D 600D 600D 6009 EMJ

~~~OGRAM NAME:LRGTSZ.E.E.GINNA NUCLEAR PONER PLAHT OCT 08,92 08:45:00 TREND GROUP ASSIGNMEHT

SUMMARY

GROUP NAME EVENT 2 GROUP DESCRIPTION PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 0 J F0619 LRNST WS033 l$033 MT033 MT250 NDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R'l9 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH'CV03 , TCV07 TCVOB TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLll REFUELING llATER STORAGE TANK LVL 33 FOOT LEVEL 1JINO SPEED 33 FOOT LEVEL LIIND DIRECTION 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL TEHPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOH AREA 2-CONTAINHENT AREA 5-SPEHT FUEL PIT AREA 9-LETDONN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUHP AREA 35-PASS SAMPLE PANEL CONTAINHEHT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE CONTAINMENT GAS MOHITOR PLANT VENT IODINE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID llASTE DISPOSAL MONITOR STEAM GENERATOR BLOlSONN DRAIN AREA 29-CONTAINMENT HIGH RANGE AREA 30-COHTAINMENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LIN RANGE GAS CV VENT CHAN 6-AREA GAHMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLAHT VENT CHAN 5-LQI RAHGE GAS PLANT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAN 9 HIGH RANGE GAS AIR EJECTOR CHAN 5-LOFTI RANGE GAS.AIR EJECTOR CHAN 7-HID RANGE GAS AIR EJECTOR CHAN 9-Hl RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE 8 (SPING)CV HYDROGEH CONCENTRATION CV BASEMENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 3.8 79.59.8 59.0-0.8 9.02214.02 6.40678+00 1.39946+00 3.40701+01 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 4.07174+03 5.05861-01 5.09440.01 1.25835+05 1.89699-07 2.53990-02 3.57435.05 1.41261-03 4.40312.07 6.86543-05 3.72621-03 6.29179.03 6.29392-03 6.29436.03 1.02040-02 1.01048-02

.0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH HWRN GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM MPH DEG.DEGF DEGF DEGF MR/H KR/H MR/H MR/H MR/H MR/H CPH CPM CPM CPH CPH CPM CPH CPM R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF Time:~gg Message: 17 INNA TATI N 1 2 EVAL ATED EXER I E MESSA E F RM MMMf: Q t<<L<<IR imla dPln oniin:~Me gage: """THIS IS AN EXERCISE""" The following annunciator is received:~A-17 (Motor Off RCP CCWP)FOR CONTR LLER USE ONLY Controller Notes: 1)When operators check the Control Board, inform them that the 1A CCW Pump has tripped and the 1B CCW Pump has started automatically

~an is delivering required flow (i.e., There are no Control Board alarms that would indicate loss of CCW Flow).Antici ate Results: 1)Operators should perform the applicable actions of AR-A-17.2)Operators should perform the applicable actions of AP-CCW.2.3)Operators should request, that the Auxiliary Operator sent to the Auxiliary Building to identify the CCW leak, isolate the 1A CCW Pump and rack out its electrical breaker.4)Operators should inform the people manning the TSC of the 1A CCW Pump problems.

Time: Jg'jQ Message:~1~INNA TATI N 1 92 EVAL ATED EXER I E~ME EA EF R~MI: IACCWP PM R I IE IFII REIT Simula ed Plan Condi ions;See the Attached Mini-Scenario

~Mss~a"""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate investigations are made.Antici ated Results: 2)As per Mini-Scenario Anticipated Results.

NIINNII TATI N 2 EVAL ATED EXER I E~MINI-NNAIII SCENARIO: Failure of inboard mechanical seal on the 1A Component Cooling Water Pump.INITIAL CONDITIONS:

Plant Operating at 97%power with 1A Component Cooling Water Pump supplying the system.CONDITIONS:

The operator on tour finds water spraying from the inboard seal of 1A Component Cooing Water Pump, directly on the 1A motor.Caution;water contains potassium chromate which is toxic.ACTIONS REQUIRED: 1B CCW Pump Seal leaking a small amount.1A Component Cooling Water Pump secured.Pump isolated by A-1401.Procedures and package for corrective maintenance be prepared.Spare parts checked SWP request prepared Maintenance shop requested to clean up spill with aid of chemistry tech.Open Flame permit and Fire Watch obtained Pump uncoupled from motor and coupling removed.Seal water piping removed.Mechanical seal removed.Inboard bearing removed.Shaft and stuffing box inspected for damage after cleaning.New mechanical seal installed.

Bearing inspected and replaced as necessary.

Coupling installed and alignment accomplished.

Pump returned to service.EXPECTED RESULTS: 1A Component Cooling Water Pump returned to service.in eight hours after repairs started on unit.

Time:~5Q Message:~1 INN A TATI N 1 2 EVAL ATED EXER E~ME SA E F RM~f: IACCWP pM P Pl I P pS IFII RplT Simula e Plan Conditions:

See the Attached Mini-Scenario

~Messa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~CI I E 1)Provide information verbally when appropriate investigations are made.An ici a ed Resul s: 1)As per Mini-Scenario Anticipated Results.

gllNNil 74Tl N 1 2 EVAL ATED EXER I E~MINI-CENARI TITLE: 1A WP m M orPr bl mfromP m P kin F il r Expected scenario start time: 0850 INITIAL CONDITIONS:

Pump running.METHOD OF INITIATION:

Breaker trips, Operations calls for Electricians to investigate.

INDICATIONS:

CONTROL ROOM:~Alarm window: "A-17" MOTOR OFF: RCP/CCWP~White (disagreement) light: CCP1A BUS 14/POS 23A:~Amptector: "Instantaneous" Trip Indication CCWP1A MOTOR:~Smell of burnt insulation

~Water spray on motor case EXPECTED SEQUENCE OF ACTIONS: o Investigate Auxiliary Building for visible signs near breaker or motor.~Notice smell at motor~Notice Circuit Breaker Amptector target for"instantaneous" o Obtain holds, clearances, and test equipment.

o Simulate measuring resistance phase to phase 5 megger motor from Bus 14/Pos 23A readings: Megger readings: OMQ to ground Phase to phase resistance:

(1 Q 0 Simulate determ of motor and repeat tests to locate fault in motor windings.o Suggest replacing pump and motor with spare units.FINAL CONDITIONS:

Motor requires replacement due to shorted windings.Windings shorted due to water spray upon failure of pump seal.

Time:~~Message:~Q~INNA TATI N 1 2 EVAL ATED EXER E MES A E F RlVl~MI: N I<<C<<IR IINCRRI T imula e Plan Con i ion:~Nlessa e: """THIS IS AN EXERCISE""" The ADFCS problem with the MFW Regulating Valves is repaired.FOR CONTROLLER USE ONLY C~lN 1)The IRC Repair Team working on the ADFCS should report this message to the Simulator Control Room.Simula or Con rol Room Con roller and ISC Re air Team Controller to coordina e his re or a 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br />.Antici ated Resul s: 1)Operators continue shutting the Plant down per 0-2.1.

Time: 3)~Message: 21 lNNA TATION 1 2 EVAL ATED EXE I E IVIE A E F RM MMMf: 8 I C IR Simula ed Plan Condi ions: See the Attached Sheets~Messs e: FOR CONTROLLER USE ONLY Antici ated Results: 1)Operators continue shutting the Plant down per 0-2.1.

199Z'VALUATED EXERCISE Time: d'Fdb MAZOR PARAMETERS ENGINEERED SAFEGUARDS Hi h Head S.Z.Pum s FI-924 GPM FI-925~GP 1A.INSERV T OOS 1B.INSERV S B OOS 1C.'NSERV OOS BAST Level=Low Head S.I.Pum s FI-626 O M 1A.INSERV T OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s FI-931A O GPM Fl-931B~GP 1A.ZNSERV TBY OOS 1B~INSERV T OOS NaOH Tank Level=Containment ecirc Fans 1A.NSE STBY OOS 1B.SE STBY OOS 1C.INSERV T OOS 1D.SER STBY OOS Post Accident Dampers OPEN LOSED Service Wate Pum s 1A.STBY OOS 1B.INSE STBY OOS 1C.NSE V ST OOS 1D.INS V TB OOS A&B Header Pressure DIESEL GENERATORS A.RUNNING UNLOADED B OOS B.RUNNING UNLOADED OOS TSC RUNNING UNLOADED T OOS Security RUNNING UNLOADED OOS PSIG Com onent Coolin Wat r Pum s Reactor Shutdown~YES N-3 1 CPS N-32 CPS N-35 AMPS N-36 AMPS Avg.Nuclear Power RCS Pressure&2.fe2 PSZG PRZR Level 5r 7 A RCP IN STOPPED B RCP IN STOPPED 1A S/G Level~a.I 1B S/G Level 5a t 1A S/G Pressure PSIG 1B S/G Pressure 7s~PSIG Turbine/Generator ONLI OFFLINE 4 KV Buses NERG DEENERGIZED 480V Buses ER DEENERGIZED DC Batteries A~go VOLTS B ISOVOLTS Cnmt Pressure.IS PSIG Cnmt Sump A Level~OFEET Cnmt Sump B Level INCHES A Loop Hot Leg Xm.-L oF A Loop Cold Leg 899.I OF B Loop Hot Leg~C.I OF B Loop Cold Leg~,~iOF RVLIS*CET 91l OF S/G A Total Aux FW Flow GPM 5/G B Total Aux FW Flow 0 GPM ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.INSERV T OOS 1B.INSERV TB OOS Turb.Driven INSERV TB OOS CST Level~FEET*CET=Average of Selected Core Exit 1A.STBY 1B.NSER STBY OOS Surge Tank Level=Standb Aux.Fe water Pum s 1C.INSERV OOS 1D.INSERV STB OOS Thermocouples 8>1992 09:00 R.E.GINA SIWLATOR TREND GROUP ASSIGNNENT SUNNARY PAGE 1 GROUP: EVENT1 PROCEDURE!

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E.U.1 2 3 5 6 7 8 r 9 10 11 12 13 14 15 16 f7 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 51 ATMS RXT N31 N32 N35 N36 NP PRCS LPIR FRM FR(u RXT16 RXT17 TSUBTC LSGA LSBB PSGA PSGB GENBKR1 BENBKR2 BUSffA BUS11B BUS12A BUS12B B11A12A B11B12B PCV LSUNPA L0942E L0943E LO'942D L0943D L0942C L0943C L0942B , L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAVGBMID LRV 7CCORE FAUXFWA FAUXFMB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIEhT M/0 SCRAN REACTOR TRIP BREAKER STATUS SMCE RANGE DETECTOR N-31 SMKE RANGE DETECTOR N-32 INIERNEDIATE RANGE DETECTOR N-35 INTERNEDIATE RANGE DETECTOR N-36 AVERAGE NIKLEAR POWER REACTOR COOLANT SYSTEN AVG PRESS PRESSURI IER AVERAGE LEVEL RECTOR COOLANT LOOP A AV6 FLIN REACTOR COOLNT LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED NAPKIN STN GEt(A NARROW RANGE AVG LEVEL STN GEN B NARROW RANGE AVG LEVEL STN BEt(A AVERAGE PRESSURE STN 6EN B AVERAGE PRESSURE GENERATOR ON LINE BREAKER 161372 GBERATOR ON LINE BREAKER 9X1372 BUS 11A SlFPLY BREAKER BUS 11B SUPPLY BREAKER NOT TERNINATED ON PPCS (7/19/91)t(OT TERNINATED ON PPCS (7/19/91)BUS 11A To f2A TIE BREA'(ER BUS 11B TO 12B TIE BRENER CONTAINHENT AVENGE PRESSURE CONTAINNENT RJNP A AVERAGE LEVEL SUtP B LEAL'8 It(CHES (TRAIN A)SU)P B LBtEL 8 It/CHES (TRAIN 8)SUtP B LEVEL 78 INCHES (TRAIN A)SUtP B LEVEL 78 INCHES (TRAIN B)SU)P B LEVEL 113 INCHES(TRAIN A)SUtP B LEVEL 113 INCHES(TRAIN B)SU)P B LBr'EL 180 INCHES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SUlP B LEVEL 214 INCHES(TRAIN A)SUtP B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TENPERATUiK RCLB HOT LE6 TBPERATSK RCLA COLD LEG TE)IPERATlBE RCLB COLD LEG TENPERATNE RCLA TAVG (THOT/TCOLD WIDE RNG)RCLB TAVG (THOT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.l INCORE TC AVERAGE TENP S/6 A TOTAj AUX FEECAIATER FLOW S/G B TOTAL AUX FEEDMAWD FLOW NTR AUXILIARY FEEDMATER PUNP A NTR AUXILIARY FEEDMATER PUNP 9 AUX FW PUNP STEA)I SUPPLY VALVE A AUX FM PINP STEAJI SUPPLY VALVE 8 OFF OFF CLOSED CLOSED gr 75 No ATMS GOOD NOT TRIP GOOD 1.000008M INHH 1.00000+00 INHB 6.19439M INHB 5,727~INHB 86.94 GOOD 2262.6009 45.7 6009 98.4 6009 97.3 6009 NOT TRIP 6009 NOT TRIP 6009 51.8 600~52.1 GOOD 52.1 6009 723.6009 722.BOOB NOT TRIP 6009 NOT TRir SOOn NOT TRIP 6009 NOT TRIP 6009 NOT TRIP DEL NOT TRIP DEL TRIPPED 6009 TRIPPED 6009.13 6009 2.0 6009 LOWER 6009 LOWER 6009 LOWER 6009 LOWER 6009 LOWER 6009 LONER 6009 LONER 6009 LOWER 6009 LOWER 6009 LOWER 6009 596.1 6009 596.1 6009 544.1 6009 545.2 G009 570.1 6009 570.6 6009 99.4 6009 599.1 600~0.6009 0.6009 6009 6909 6009 GOOD CPS CPS ANP ANP X PSIB X X DEBF X X PSIG PSI6 PSI6 FEET DE6F DEGF DE6F DEBF KBF DEBF X KBF PN GPN OCT 8~1992 09:00 R.E.GIMjfA SIffULATOR TREND GfOUP ASSIGNffENT SNIARY PA6E 2 6ROUP'VENTI PfNlEDURE'PIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE.QUAL E,', 53 FSIA 54 FSIB 5S P2160 56 P2I61 57 BffR04i 58 Bff R042 59 BffR043 60 BKR044 SAFETY INJECTION.

LOOP A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SERVICE WATER PNfPS A h B HEADER SERVICE WATER PNFS C 5 0 HEADER SERVICE WATER PNfP A SERVICE WATER PUNP 8 SERVICE WATER PNfP C SEfIICE WATER PNfP D 0.0.82.73, ON ON ON OFF 600D PN 600 D GPN 600D PSIG GOOD PSIG GOOD 600D GOOD GOOD EMJ

~l~IOGRAM NAME: LRGTSZ.E.E.GIHNA NUCLEAR PONER PLANT OCT 08,92 09:00:00 TREND GROUP ASSIGNMENT SUHHARY GROUP HAME EVENT 2 GROUP DESCRIPT ION PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURREHT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 2'1 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 0-F0619 LRNST IIS033 l$033 IIT 033 NT250 M)T2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLU REFUELING llATER STORAGE TANK LVL 33 FOOT LEVEL llIND SPEED 33 FOOT LEVEL IIIND DIRECTIOH 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOH AREA 2-CONTAINMEHT AREA 5-SPEHT FUEL PIT AREA 9-LETDONN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUHP AREA 35-PASS SAHPLE PANEL CONTAINMENT IODINE MONITOR R10A CONTAIHHEHT AIR PARTICULATE CONTAINMENT GAS HOHITOR PLANT VENT IODINE HOHITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID'HASTE DISPOSAL MONITOR STEAM GENERATOR BLONDONH DRAIN AREA 29-CONTAINMEHT HIGH RANGE AREA 30-CONTAINMEHT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOU RANGE GAS CV VENT CKAH 6-AREA GAMMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RAHGE GAS PLANT VENT CHAN 5-LOI RANGE GAS PLANT VENT CHAM 7-MID RANGE GAS PLANT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOU RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 31 STEAM LINE A (SPIHG)AREA 32 STEAM LINE B (SPING)CV HYDROGEN CONCEHTRATION CV BASEMEHT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEHP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 3.1 52.59.9 59.3-0.6 9.02214-02 6.40678i00 1.39946+00 3.40701+01 9.09354-01 1.09283+00 9.5871&01 5.18901+02 7.38002+02 4.30543>01 8.58327+01 4.22831+01 2.78658t03 4.07174+03 5.05861-01 5.09440-01 1.25835+05 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 6.29179.03 6.29392-03 6.29436.03 1.02040-02 1.01048-02

.0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM HNRN GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPM CPM CPM CPH CPH CPM CPH R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC HR/HR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF g-77 Time:~)~Message: 22~INNA TATI N 2EV L TEDE ER I E MES A E F RIVI~MI:M I N<<IR IA IIINRA<100gpm.3)Operators should also be performing the applicable actions of the following procedures:

a)EPIP 1-2 (ALERT)b)EPIP 1-5 (Notifications) c)0-9.3 (NRC Immediate Notification).

199Z'EVALUATED EXERCISE TIme: G'Ill MAZOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown ES NO N-31~CPS N-32 CPS N-35 e AMPS N-36-t AMPS Avg.Nuclear Power e RCS Pressure I 7 PSIG PRZR Level 0 A RCP STOPPED B RCP UNNI STOPPED 1A S/G Level~lO.1B S/G Level~l 1A S/G Pressure~(S PSIG 1B S/G Pressure t3 PSIG Turbine/Generator OFFLINE 4 KV Buses NERGIZE DEENERGIZED 480V Buses N RGIZE DEENERGIZED DC Batteries A~TOVOL S BlSOVOLTS Cnmt Pressure~(PSZG Cnmt Sump A Level FEET Cnmt Sump B Level INCHES A Loop Hot Leg~~eOF A Loop Cold Leg~G~Z OF B Loop Hot Leg OF B Loop Cold Leg~5 OF RVLZS*CET~~.S OF.S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow GPM DIESEL GENERATORS A.NING UNLOADE STBY OOS B.UNNING UN DE STB OOS TSC RUNN ED TB OOS Security RUNNING UNLOAD D TB OOS ENGINEERED SAFEGUARDS Aux.Feedw ter Pum s 1A.SE STBY OOS 1B.N ER STBY S Turb.Driven SER STBY OOS CST Level g~~h FEET*CET=Average of Selected Core Exit Hi h Head S.I.Pum s FI-924 0.GPM FZ-925 0 GPM 1A SE STBY OOS 1B STBY OOS 1C.INSERV STBY OOS BAST Leve=~7 Low Head S.Z.Pum s FI-62 GPM 1A.SER STBY OOS RECIRC 1B.SERV STBY OOS RECIRC RWST Level=V.Containment S ra Pum s FZ-931A O GPM FI-931B O GP 1A.INSERV ST 1B.INSERV NaOH Tank Level=OOS OOS Service W te Pum s 1A.SE STBY OOS 1B.SE STBY OOS 1C.STBY OOS 1D.INSER STBY OOS A&B Hea er ressure PSIG Com onent Coolin Water Pum s 1A.IN STBY 0 1B.NSERV STBY OOS Surge Tan Level=Containment Recirc Fans 1A.NS STBY OOS 1B.INSE STBY OOS 1C.STBY OOS 1D.INSE STBY OOS Post Acct ent Dampers OPEN CLOSED Standb Aux.Fe ater Pum s 1C.INSERV T OOS 1D.ZNSERV TB OOS Thermocouples 8)1992 09'17 R.E.GINA SitmLATOR'REN9 GROUP ASSIGNMEt(T SUt(MARY PAGE 1 6ROUP: EVEHT1 PROCEDURES EPIP 1-5 PLANT STATUS1 2 3 4 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 ATWS RXT N31 N32 N35 H36 NP PRCS LPIR FRCLA FRCLB R)(T16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GENBKRl GENBKR2 BUS11A BUS11B BUS12A BUS12B B11A12A B11B12B PCV LSUMPA L0942E L0943E L0942D L0943D L0942C L0943C l.0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAWID TAVGBMID LRV TCCORE FAUXFWA FAUXFWB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT W/0 SCRAM REACTOR TRIP BREAKER STATUS SmSCE RANGE DETECTOR N-31 SRSCE RANGE DETECTOR H-32 INTERMEDIATE RANGE DETECTOR N-35 IHTERt(EDIATE RAN6E DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEN AVG PRESS PRESSURIIER AVERAGE LEVEL REACTOR COOLNT LOOP A AVG FLOW REACTOR COOLANT LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUKOOLED MARIN STtl GEN A NARROW RANGE AVG LEVEL STM GB(B NARROW RANGE AVG LEVEL ST)(GEN A AVERAGE PRESSURE STtl GEN B AVERAGE PRESSURE GBERATOR ON LINE BREAKER 161372 GE%MTOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SUPPLY BREAKER NOT TERMINATED ON PPCS (7/19/91)NOT TERMINATED ON PPCS (7/19/91)BUS 11A To 12A TIE BRENER BUS 11B To 129 TIE BREAKER CONTAINMENT AVERAGE PRESSURE CONTAIt(t~

SUt(P A AVERAGE LEVEL SU)P B LEVEL 8 INCHES (TRAIN A)SUtP B LEVEL 8 INCHES (TRAIN 9)SU)P B LEVEL 78 iNCHES (TRAIN A)SUtP B LEVEL 78 INOZS (TRAIN B)SUIP B LBtEL 113 INCHES(TRAIN A)SUIP B LEVEL 113 INCHES(TRAIN B)SUtP B LEVEL 180 INCHES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SUtP B LEVEL 214 INCHES(TRAIN A)SU)P B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TBIPERATUK RCLB HOT LE6 TBIPERATNK RCLA COLD LEG TE)IPERAT(RE RCLB COLD LEG TE)IPERAT(SE RCLA TAVG (THOT/TC(LD WIDE RNG)RCLB TAVG (THOT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 It(CORE TC AVERAGE TBIP S/G A TOTAL A'JX FEEDWATER FLOW S/G B TOTAL A)JX FEEDMATER FLOW t(TR AUXILIARY FEEDWATER PUMP A tITR AUXILIARY FEEDMATER PUMP 9 AUX FW PUMP STEA)I SUPPLY VALVE A AUX FM PUMP STEA)I SUPPLY VALVE B GUAL OH ON OPEN OPEN AIMS ALRt(RX TRIPPED ALRII 1.00000+(e INHB 1.00000I00 INHS 4.20726-06 6009 3.59748M 6009.59 600D 1474.LAB.0 LALI(98.9 GOOD 98.0 600D NOT TRIP 600D NOT TRIP 6009 51.7 600~10.8 LALM 7.1 LALN 913.6009 913.6009 NOT TRIP 6009 NOT TRIP 6009 NOT TRIP 6009 NOT TRIP 6009 NOT TRIP DEL HOT TRIP DEL TRIPPED 6009 TRIPPED GOOD.11 GOOD 2.0 6009 LOWER 6009 LOWER 6009 LONER 6009 LOWER 6009 LOWER 6009 LOWER 6009 LOWER 6009 LOWER 6009 LOWER 6009 LOWER 6009 543.6 6009 543.6 6009 536.2 6009 537.3 6009 539.9 6009 540.2 6000 99.5 6009 539.3 Goo'78.GOOD 484.6009 6009 Gm ALRtf ALRtl E.U.CPS CPS At(P AMP X PSIG X, X X KGF X X PSI6 PSIG PSI6 FK DE6F KGF DEGF DEGF DEGF DEGF X DFGF PN GPN

OCT&s 1992 09'17 R.E.GINA SIWLATOR TREND 6ROUP ASSI6NENT RNHARY PAGE 2 GROUP: EVENT1 PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 DESCRIPTION SAFiiY INJECTION LOOP A AVG FLOW SAFETY INJECTION l.OOP B AVG FLOW SERVICE WATER PIIPS A 5 B HEADER SERVICE WATER PNPS C h D HEADER SERVICE WATER PlNP A SERVICE WATER PUNP B SERVICE WATER PlmP C SERVICE WATER PUMP D ON ON ON ON VALUE OUAL E.U.101.600 D 6Ptl 101.GOOD GPH 85.GOOD PSIG 85.GOOD PSI6 600D 600D GOOD GOOD EMJ

~~~Q IOGRAM HAME:LRGTSZNE.E.GINNA NUCLEAR POMER PLANT OCT 08,92 09:17:00 TREND GROUP ASSIGMHEHT SUHMARY GROUP NAME EVENT 2 GROUP DESCRIPT IOH PROCEDURE:

EPIP 1-5 PLANT STATUS POINT IO DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43-F0619 LRlIST MS033 l$033 MT033 MT250 MDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLlI REFUELING MATER STORAGE TANK LVL 33 FOOT LEVEL IIIND SPEED 33 FOOT LEVEL lIIND DIRECTION 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-COHTAINHENT AREA S.SPENT FUEL PIT AREA 9.LETDOMN LINE MOHITOR AREA 34-AUX BLDG CV SPRAY PUHP AREA 35-PASS SAMPLE PANEL COHTAINHENT IODINE MONITOR R10A CONTAINMEHT AIR PARTICULATE CONTAINMEHT GAS MONITOR PLANT VENT IOOIHE MOHITOR R108 AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXNAUST GAS MONITOR LIQUID MASTE DISPOSAL MONITOR STEAM GENERATOR BLOleOllH DRAIN AREA 29-COHTAINMEMT HIGH RANGE AREA 30-CONTAIHMENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LNI RAHGE GAS CV VENT CHAN 6 AREA GAMMA CV VENT CHAM 7-HID RANGE GAS CV VENT CHAN 9-HIGH RAHGE GAS PLANT VENT CHAN 5-LNI RANGE GAS PLANT VENT CHAN 7-HID RAHGE GAS PLANT VENT CHAM 9-HIGH RANGE GAS AIR EJECTOR CHAH 5-LOU RANGE GAS AIR EJECTOR CHAN 7-MID RAHGE GAS AIR EJECTOR CHAN 9-Hl RANGE GAS AREA 31 STEAM LINE A (SPIMG)AREA 32 STEAM LIHE 8 (SPING)CV HYDROGEN CONCENTRATION CV BASEMEHT LVL 6 FT TEHP¹3 CV INTERMEDIATE LVL 6 FT TEHP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEHP¹9 CV INI'ERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 3.8 50.60.7 60.7 0.0 9.02214.02 7.35678+00 1.3994&00 1.47701+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.57174+04 5.05861.01 5.09440-01 9.~06 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 9.99999.03 1.85392+00 1.85436+00 3.02040+00 1.01048-02

~0 95.1 106.0 106.6 106.7 106.2 117.5 6(XO 6000 QXX)GOOD 6000 GOOD GOOD GOOD GOOD 6000 GOOD GOOD GOOD GOOD 6000 6000 GOOD GOOD GOOD GOOD~HALM GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH HALM HMRH MALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPH X MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPM CPM CPM CPM CPM CPM CPM R/HR R/HR CPM UCI/CC HR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR DEGF DEGF DEGF DEGF DEGF DEGF Time:~20 Message:~2 Sl~NA STATION 2 EV L TED EXER E ME A E F RIVI~MN: SI I<<N IN Simulated Plan Condi ions: See the Attached Sheets~Massa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~NI I N Antici a ed Results: 1)Operators performing the applicable actions of E-O.2)Operators should be transitioning to E-3 (Steam Generator Tube Rupture).

199P EVALUATED EXERCISE Time: 0 92.O MAZOR PAE&METERS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s Fl-924 I 5 GPM FI-925 GPM 1A.NSE STBY OOS 1B.NSER STBY OOS 1C.INSERV STBY OOS BAST Leve Low Head S.I.Pum s FI-626 O GPM 1A.NSE STBY OOS RECIRC 1B.NSE STBY OOS RECIRC RWST Level=Containment S ra Pum s FI-931A O GPM FI-93 1B 0 GPM 1A.INSERV B OOS 1B.INSERV B OOS NaOH Tank Level=Containment Recirc Fans 1A.NSER STBY OOS 1B.NSE STBY OOS 1C.SERV STBY OOS 1D.NSE V STBY OOS Post Aces ent Dampers OPE CLOSED Service Water Pum s 1A SE STBY OOS 1B.E STBY OOS 1C.SER STBY OOS 1D.NSER STBY OOS A&B Header ressure ggP8 PSIG Com onent Coolin Water Pum s DIESEL GENERATORS A.UNNING UNLOADE STBY OOS B.RUNNING UNLOADED STBY OOS TSC RU G LO DED STB OOS Security RUNNING UNLOADED TB OOS Reactor Shutdown ES NO N-31~CPS N-32 CPS N-35 AMPS N-36 Q+-AMP S Avg.Nuclear Power o RCS Pressure~s&7 PSIG PRZR Level A RCP UNNI STOPPED B RCP UNNING STOPPED 1A S/G Level so.t a 1B S/G Level.1 1A S/G Pressure PSIG 1B S/G Pressure PSIG Turbine/Generator FFLINE 4 KV Buses NERGIZ DEENERGIZED 480V Buses N ED DEENERGIZED DC Batteries AI'SbVO S B~3oVOLTS Cumt Pressure~dPSIG Cnmt Sump A Level.0 FEET Cnmt Sump B Level INCHES A Loop Hot Leg'f043 OF A Loop Cold Leg M4LX oF B Loop Hot Leg OF B Loop Cold Leg OF RVLIS f3*CET Oa OF S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow~g GPM ENGINEERED SAFEGUARDS 1A.INSERV STBY 1B.SER STBY OOS Surge Tank Level=~2-Aux.Feedwater Pum s 1A.SE STBY OOS Standb Aux.Feedwater Pum s 1B.INSERV STBY OOS 1C.INSERV TB OOS Turb.Driven INSERV TB OOS 1D.INSERV TB OOS CST Level~f F*CET=Average of Selected Core Exit Thermocouples 8-fo 8, 1992 09:21 R.E.GINA Sit(ULATOR TREND GROUP ASSIGN)(ENT SUl(NARY PAGE 1 GROUP!EVENTi PROCEDURE(EPIP 1-5 POINT ID DESCRIPTION PLANT STATUS E.U.1 2 3 4 5 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 ATMS RXT N31 N32 N35 N36'NP PRCS LPLR FRM FRCLB RXT16 RXT17 TSUBTC LSSA LSSB PSGA PSGB GENBKR1 GENBKR2 BUSIIA BUS11B BUS12A BUS12B 811A12A B11812B PCV LSI(PA L0942E L0943E L0942D L09439 L0942C L0943C L0942B L0943B L0942A t 0943A T0409A T0410A T0450 T0451 TAVGA MID TAVSBWID LRV TCCORE FAUXFWA FAUXFWB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT W/0 SCRI(REACTOR TRIP BREAKER STATUS SMKE RANGE DETECTOR N-31 SIIKE RANGE DETECTOR N-32.INTERt(EDIATE RANGE DETECTOR N-35 INTERt(EDIATE RANGE DHECTOR N"36 AVERAGE NXLEAR POWER REACTOR COOLANT SYSTEt(AVG PRESS PRESSURIIER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOW REACTOR COOLNT LOOP B AV6 FLN RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCQRE TC SUBCOOLED t(ARSIN STt(GEt(A NARRN RANGE AVG LEVEL STt(BEN B NARROW RANGE AVG LEVEL STt(SEt(A AVERAGE PRESS(EE STH GEN B AVERAGE PRESSURE 6BERATOR ON LltK BREAKER 161372 aaeuTOR oN LINE BREAKER 9ra372 BUS 11A SUPPLY BREAKER BUS iiB SUPPLY BREAKER NOT TERt(INATED Ot(PPCS (7/19/91)NOT TERNINATED ON PPCS (7/19/91)BUS 11A TQ 12A TIE BREWER BUS 11B TQ 12B TIE BREWER CONTAIttt(ENT AVERAGE PRESSURE CONTAINt(ENT RIP A AVERAGE LEVEL SU)P B LEVEL 8 INCHES (TRAIN A)SU)P B LEVEL 8 INCHES (TRAIN B)SU)P B LEVEL 78 INCHES (TRAIN A)SU)P B LEVEL 78 INCHES (TRAIN B)SUtP B LEVEL 113 INCHES(TRAIN A)SU)P B LEVEL 113 INCHES(TRAIN B)SU)P B LEVEL 180 INCHES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SUtP B LEVEL 214 INCHES(TRAIN A)SUtP B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TEt(PERATURE RCLB HOT LE6 TEt(PERATURE RC(A COLD LEG TEt(PERAT(SE RCLB COLD LEG TEt(PERATlRE RCLA TAVG (THOT/TCOLD WIDE RNG)RCLB TAVG (THQT/TCOLD MIDE RNG)REACTOR VESSEL AVERAGE LEVEL E1.1 INCORE TC AVERAGE TEt(P S/6 A TOTAL AUX FEEDMATER FLN S/G B TOTAL AUX FEEDWATER FLN t(TR AUXILIARY FEEDMATER PUt(P A HTR AUXILIARY FEEDWATER PUlP B AUX FM PUtP STEA)l SUPPLY VALVE A AUX FM PUt(P STENi SL%'PLY VALVE B ATWS RX TRIPPED 1.0000(MO 1.00000+00 6.79204M 5.80759M.02 1267..0 98.1 97.3 NOT TRIP NOT TRIP 35.0 30.8 28.7 941.941-.TRiPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NQT TRIP NOT TRIP.08 2.0 LOWER LONER LONER LONER LNER l.OWER LNER LNER LNER LONER 540.3 540.3 538.8 538.4 539.7 539.4 99.3 540.5 0.198.ON ON CLOSED CLOSED ALRt(ALRt(INHB INHB 6009 6009 6009 LALN LALN 6009 6009 GOOD 6009 600~GOOD LWRt(6009 6009 ALRt(ALRt(ALRt(ALRN DEL DEL ALRt(ALRt(6009 GOOD soon GOOD 6009 6009 Goon 6009 6009 6009 6009 GOOD 6009 6009 6009 6009 6009 SOQD 6009 Goo<6009 GOOD 6009 GOOD 6009 6009 CPS CPS At(P At(P y.PSIG'l 7l DEGF X y.PSIG PSIG DEGF DEBF DEGF DE6F DEGF DESF K DE6F 6PN 6Pt(

OCT 8)1%2 N:21 R.E.GINA SIILATOR PAGE 2 TREND 6ROUP ASSIMENT SUNRY 6ROUP: EVENT1 PRXEOUREl EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION QUAL E.U.53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 IIR042 59 INR043 60 IIR044 SAFETY INJECTION.

LOOP A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SERVICE WATER PNPS A h B HEADER SERVICE WATER PNFS C h D HEADER SERVICE WATER PNF A SERVICE WATER PlIP B SERVICE WATER PIIP C SERVICE WATER PNP D 145.145.85.85.600D PN GOOD GPN SOOn PSIG 6009 PSIG GOOD GOOD GOOD GOOD EMJ Time:~3g Message: 26 INNA TATI N 2 EV L ATED XER E ME A E F RM~lli i: 'i i<<L<<iR Simula e Plan n i ions: See the Attached Sheets~INesse e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: Antici ated Results: 1)Operators performing the Applicable Actions of E-3.2)The Ruptured Steam Generator should be isolated at approximately this time, ti.e., secondary side).8 6 199K'VALUATED EXERCISE Time: 00'50 ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s MAJOR PARAMETERS FI-924 GPM FI-925 2'j~GPM 1A.SE STBY OOS 1B SE STBY OOS 1C NSER STBY OOS BAST Lave=~O Low Head S.I.Pum s FI-626 O G M 1A.INSERV TB OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s FI-931A Q GPM Fl-931B D GPM 1A.INSERV TB OOS 1B.INSERV TB OOS NaOH Tank Level=~4 Containm nt ecirc Fans 1A.NSERV STBY OOS 1B.N ERV STBY OOS 1C.S STBY OOS 1D.NSER STBY OOS Post Accident Dampers OPE CLOSED Service Wa er Pum s 1A.NSERV STBY OOS 1B.'SER STBY OOS 1C.SER STBY OOS 1D.NSER STBY OOS A&B Header ressure~APSIG Com onent Coolin Water Pum s DIESEL GENERATORS A.UNNING UNLOAD STBY OOS B.ED STBY OOS TSC D TB OOS Security RUNNING UNLOA D B OOS Reactor Shutdown ES NO N-31 CPS N-32~CPS N-35!-II AMPS N-3 6~~wl AMPS Avg.Nuclear Power o RCS Pressure PSIG PRZR Level A RCP STOPPED B RCP UNNIN STOPPED 1A S/G Level 1B S/G Level~o&1A S/G Pressure~5 PSIG 1B S/G Pressure 0 PSIG Turbine/Generator NE FFLIN 4 KV Buses RGIZE DEENERGIZED 480V.Buses NERGIZ DEENERGIZED DC Batteries A~5o VOLTS B/Sb VOLTS Cnmt Pressure.oa PSIG-Cnmt Sump A Level~3.FEET Cnmt Sump B Level INCHES A Loop Hot Leg~OF A Loop Cold Leg Zi OF B Loop Hot Leg~OF B Loop Cold Leg~4 OF RVLIS i+i~*CET~92,3 OF'/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow~IG GPM 1A.INSERV STBY 00 1B.NSE V STBY OOS Surge Tan vel=5~4 ENGINEERED.

SAFEGUARDS Aux.Feedwater Pum s 1A.INSERV TB OOS 1B.SER STBY OOS Turb.Driven INSERV B OOS CST Level/FEET*CET=Average of Selected Core Exit Thermocouples Standb Aux.Fee ater Pum s 1C.INSERV TB OOS 1D.INSERV TB OOS 8s 1992 09!30 R.E.GINA SI)ILATOR PAGE 1 TREND GROUP ASSIGN%AT SUt(t(ARYDESCRIPTION GROUP'VENT1 PROCEDURE'PIP f<POINT ID PLANT STATUS E.U.1 2 3 4 5 6 7 8 9 f0 11 12 13 14 15 16 17 18 f9 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 46 47 48 49 50 51 52 ATiS RXT N31'32 ta5 N36 NP PRCS LPLR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PS6B GENBKRf GENBKR2 BUS11A BUS11B BUS12A BUS12B 811A12A B11812B PCV LSI(PA L0942E L0943E LO'942D L0943D L0942C L0943C L09428 L0943B L0942A L0943A T0409A T0410A T0450 TO451 TAVGAWID TAVGBWID LRV TCCORE FAUXFWA FAUXFWB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT W/0 SCRAt(REACTOR TRIP BRENER STATUS SMCE RANGE DETECTOR N-31 SONCE RI(GE DETECTOR N-32 INTER)(EDIATE RANGE DETECTOR N-35 INIEt(t(EDIATE RAN6E DETKTOR N-36 AVERA6E NUCLEAR POWER REACTOR COOLANT SYSTEt(AVG PRESS PRESSURI lER AVERAGE LEVEL REACTOR COOLNT LOOP A AVG FLOW REACTOR COOLANT LOOP B AVG FLOW RCPA BRENER CAUSE RX TRIP RCPB BRENER CAUSE RX TRIP INCORE TC SUBCOOLED t)ARGIN STtl GB(A NARROW RANGE AVG LEVEL STN GEN B NARROW RANGE AVG LEVEL STtt GEN A AVERAGE PRESSURE STt(GEN 8 AVERA6E PRESSURE GBGQTOR ON LINE BRENER 161372 GamATOR ON~INE BREAKER 9X1372 BUS f1A SUPPLY BRENER BUS 11B SLPPLY BRENER NOT TERNINATED Ott PPCS (7/19/91)NOT TERt(INATED OW PPCS (7/19/91)BUS 11A TO 12A TIE BRENER BUS 11B TO 128 TIE BRENER CONTAIN)(ENT AVERAGE PRESSURE CONTAINEhT PJt(P A AVcCAGE LE4l3.SUtP 8 LEVEL 8 INCHES (TRAIN A)SUtP 8 LEVEL 8 INCHES (TRAIN B)SUtP 8 LEVEL 78 INCHES (TRAIN A)SUtP 8 LEVEL 78 INCHES (TRAIN 8)SUtP B LEVEL 113 INCHES(TRAIN A)SSP B LEVEL 113 INCHES(TRAiN 8)SUtP B LEVEL 180 INES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SUtP B LEVEL 214 INCHES(TRAIN A)SUtf B LEVl3.214 INCHES(TRAIN B)RCL4 HOT LEG TB(PERATUK RCLB HOT LEG TB(PERATNK RCLA COLD LEG TB(PERAT(mE RCLB COLD LE6 TB(PERATIRE RCLA TAVG (TNT/TCOLD WIDE RN6)RCLB TAVG (THOT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL Ei.f INCORE TC AVERAGE TB(P S/G A TOTAL AUX FEEDWATER FLOW S/6 B TOTAL AUX FEEDWATBt FLOW t(TR AUXILIARY FEEDWATER PlNP A ttTR AU)(ILIARY FEEDWATER PU)(P B AUX FW PUt(P STEA)t SUPP(.Y VALVE A AUX FW PlNP STEA)(SUPPLY VALVE 8 ATWS RX TRIPPED i.00000+00 1.0000&0 6.13757"1 1 5.34561-11

.00 934..0 103.3 103.0 NOT TRIP NOT TRIP 45.9 49.6.0 1053.580.TRIPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NOT TRIP NOT TRIP.02 2.1 LO)tER LONER LO)tER LOI(ER LO)tER LONER LOWER LOWER LONER LONER 494.6 494.6 495.5 487.6 494.8 491.0 100.8 492.2 0.182.OFF ON CLOSED CLOSED ALN ALN INH)t CPS INH8 CPS GOOD At(P GOOD At(P GDOD X LALt(PSIG LAL)(X 600D X 600D X GOOD GOOD 600'EGF GOOD X LAL)(X GOOD PSIG LWR)(PSI6 ALRtl ALRt(ALRtl ALR)(DEL DEL ALRt(AUI GOOD PSIG 6009 FAT GOOD GOOD 6009 6000 GOOD 6009 600D GOOD 6009 GOOD GOOD DEGF 600D DEGF GOOD DE6F 600D DE6F 6000 KGF 6000 DEGF 600D X 600~DEGF 600 D GPtt GOOD GPt(6009 GBQD 600D 6009 OCr 8, 1992 R.E.GINA SINlLATOR TREND GROI'SSIGQKNT RNNARY PA6E 2POINT ID 53 FSIA 54 F GIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 DESCRIPTION SAFETY INJECTION.LOOP A AVG FLOM SAFETY IN JECTION LOOP B AVG FLOM SERVICE MATER PIPS A h B HEADER SERVICE MATER PIIPS C h D HEADER SERVICE MATER PtIP A SERVICE MATER PlmP B SERVICE MATER PlIP C SERVICE MATER PUNP D VALUE NIL E.U.257.GOOD GPtl 256.GOOD GPN 85.GOOD PSIG 85.6008 PSIG GOOD GOOD GOOD GOOD GROUP: EVENTi PROCEDURE:

EPIP 1-5 PLANT STATUS E+J ROGRAM NAME:LRGTSZ.E R.E.GINNA NUCLEAR POlER PLANT OCT 08,92 09:30:00 TREND GROUP ASSIGNHEHT

SUMMARY

GROUP HAME EVENT 2 GROUP DESCRIPTION PROCEDURE:

EPIP 1-5 PLANT STATUS POINT m DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 0 J F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14AS R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FL'W REFUELIHG WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL TEHPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-CONTAIKMEHT AREA 5-SPENT FUEL PIT AREA 9 LETDOWN LINE MONITOR AREA 34 AUX BLDG CV SPRAY PUMP AREA 35 PASS SAMPLE PANEL CONTAINMENT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE CONTAIHMEHT GAS MOHITOR PLANT VENT IOOIHE MONITOR R108 AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID WASTE DISPOSAL MONITOR STEAM GEHERATOR BLOWDOWN DRAIN AREA 29-COHTAINMENT HIGH RANGE AREA 30-CONTAINHENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VEHT CHAN 5-LOW RANGE GAS PLANT VENT CHAN 7-MID RAHGE GAS PLANI'ENT CHAN 9 HIGH RANGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAN 9-Hl RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LIHE B (SPIKG)CV HYDROGEN COHCEHTRATION CV BASEMENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEHP¹9 CV INTERMEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 4.1 50.60.7 60.6-0.1 9.02214-02 7.35678+00 1.39946+00 1.47701+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002i02 4.30543>01 8.58327+01 4.22831+01 2.78658t03 1.57174+04 5.05861-01 5.09440-01 9.99999+06

~1.89699-07 2.53990-02 3.57435.05 1.41261.03 4.40312-07 6.86543-05 3.72621-03 9.99999.03 1.85392+00 1.85436+00 3.02040+00 1.01048.02

.0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD BALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD BALM HALM HWRN HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM X MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPM CPM CPM CPM CPM CPM CPH R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/NR X DEGF DEGF DEGF DEGF DEGF OEGF Time: Jg~)Message:~~X INN A TATI N 1 2 EVAL ATED EXER I E MESSA E F RM~f: RI I<<C<<IR RPII Rp I I Emergency Coordinator Simula ed Plan Conditions:

~Massa e: """THIS IS AN EXERCISE""" Declare an~LERT in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification," EAL: Steam Generator Tube Rupture (SGTR);SGTR)100 gpm.FOR CONTROLLER USE ONLY~C"'l R 1)Deliver only if an ALERT has not been declared.Do no Deliver if Emer en Classifica ion di cussions ar in ro r Antici ated Resul s: 1)Deliver contingency message if ALERT not declared or is not being discussed.

Time: g)~4'j Message:~2~IMNA TATI~1 2 EVAL ATED EXER E ME A E F RM~Mf: Si I<<C<<IR Simula ed Plan Condi ions: See the Attached Sheets Messa<ee: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller No es: An ici a ed Resvl s;1)Operators performing Applicable Actions of E-3.2)The RCS should be depressurized to ruptured S/G pressure and the High Head Safety Injection Pumps taken out at approximately this time.3)The TSC should be nearing operational readiness of the Emergency Response Organization.

4)The TSC, when operational, should send repair teams into the Auxiliary Building to evaluate the 1A CCW Pump and motor problems.5)The TSC, when operational, should send repair teams out to evaluate the"A" and"B" S/G ARV problems, if not already done.6)The EOF may be activating at this time due to Plant conditions.

199K'EVALUATED EXERCISE Time: QVVg MAZOR PAEULMETERS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FZ-924~GPM FI-925 O GPM 1A.INSERV TB OOS 1B.INSERV TB OOS 1C.INSERV TB OOS BAST Level=~OS Low Head S.I.Pum s FI-626 O GPM 1A.INSERV OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=S.Containment S ra Pum s FI-931A GPM FZ-93IB~GPM 1A.INSERV STB OOS 1B.INSERV TB OOS NaOH Tank Level=Containment Recirc Fans 1A.NSE V STBY OOS 1B.NSERV STBY OOS 1C.INS STBY OOS 1D.IN STBY OOS Post Accident Dampers PE CLOSED Service Water Pum s 1A.SE STBY OOS 1B.NSE V STBY OOS 1C.NSER STBY OOS 1D.NS STBY OOS A&B Header Pressure S 5 PSIG DIESEL GENERATORS A.NING UNLOADE STBY OOS B.RUNNIN ADED STBY OOS TSC RUNN NG ADED TB OOS Security RUNNING UNLOA D Com onent Coolin Water Pum s 1A.IN E V STBY 00 1B NSERV STBY OOS Surge Tan vel=~2 OOS ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.INSERV B OOS 1B.NSE V STBY OOS Turb.Driven ERV STBY OOS CST Level FEET*CET=Average of Selected Core Standb Aux.Feedwater Pum s 1C.INSERV TB OOS 1D.INSERV B OOS Exit Thermocouples Reactor Shutdown YES NO N-31 CPS N-32 CPS N-35/.os-I AMPS N-36'-//AMPS Avg.Nuclear Power RCS Pressure~FPSIG PRZR Level ye 2.4 A RCP STOPPED B RCP RUNNIN STOPPED lA S/G Level 2.1B S/G Level'1A S/G Pressure/0/PSIG 1B S/G Pressure 2.Z PSIG Turbine/Generator INE/4 KV Buses N RGIZ DEENERGIZED 480VBuses ENERGIZ DEENERGIZED DC Batteries A/SOVOLTS B(3OVOLTS Cnmt Pressure~~~FO G PSIG Cnmt Sump A Level~/FEET Cnmt Sump B Level INCHES A Loop Hot Leg 1.OF A Loop Cold Leg/1 OF B Loop Hot Leg 817.OF B Loop Cold Leg OF RVLIS/oo.S'*CET~97.9 OF.S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow~~SGPM 8)1992 09:45 R.E.GINA SIILATOR PA6E 1 TREND GROUP ASSIGHNEHT SUttt(ARY6ROUP: EVENT1 PROCEDURE:

EPIP 1-5 POINT ID DESCRIPTION PLA)(T STATUS E.U.1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 f7 18 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 t(P PRCS LPZR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSBB PSBA PSBB GENBKR1 GEHBKR2 BUS11A BUS11B BUSf2A BUS12B B11A12A B11B12B PCV LSI(PA LO942E LO943E LO942D LO943D LO942C LO943C LO942B LO943B LO942A LO943A TO409A T041OA TO450 T0451 TAVBA MID TAVBBWID LRV TCCORE FAUXFWA FAUXFWB BKRO81 BKR082 V3505 V3504 ANTICIPATED TRANSIENT M/0 SCRAtt REACTOR TRIP BS(ER STATUS SISCE RANGE DETECTOR N-31 So(ICE RANGE DETECTOR N-32 INTERt(EDIATE RANGE DETECTOR N-35 INTERt(EDIATE RAN6E DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEt(AVG PRESS PRESSURIZER AVERAGE LEVEL REI:TOR COOLNT LOOP A AVG FLOW REACTOR COOLANT LOOP B AVB FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED t)ARGIN STtt GEN A NARROW RAHGE AVG LEVEL STt(GEN B NA)SOW RANGE AVG LEVEL STH GEtt A AVERAGE PRESSURE STH GEN B AVERAGE PRESSURE GBHQTOR ON LINE BREAKER 16f372 GBGQTOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SUPPLY BREAKER NOT TERNIHATED OH PPCS (7/19/91)HOT TERNIHATED OH PPCS (7/19/91)BUS 11A TO 12A TIE BRENER BUS ifB To 128 TIE BRENER CONTAIN)(EHT AVERAGE PRESSURE CONTAItlt(EHT S)t(P A AVEIWBE i&EL SU)P B LEVEL 8 INCHES (TRAIN A)SUtP B LEVEL 8 INCHES (TRAIN 9)SUtP 8 LEVEL 78 INCHES (TRAIN A)SUtP B LEVEL 78 INCHES (TRAIN B)SUtP B L&EL 113 INCHES(TRAIN A)SUtP B LEVEL 113 INCHES(TRAIN B)SU)P B LEVEL 180 INDUS(TRAIN A)SUtP B LB(EL 180 INCHES(TRAIN B)SUtP B LEVEL 214 INCHES(TRAIN A)SUtP B LElr'EL 214 INCHES(TRAIN B)RCLA HOT LEG TEtlPERATSK RCLB HOT LE6 TEtiPERATUliE RCLA COLD LEB TE)PERAT(BE RCLB COLD LEG TEt(PERAT(SE RCLA TAVG (THOT/TCOLD WIDE RNG)RCLB TAVB (THOT/TCOLD WIDE RHB)REACTOR VESSEL AVERAGE LEVEL E1.1 IHCOPE TC AVERAGE TEt)P S/G A TOTAL AUX FEEDWATER FLOW S/6 B TOTAL AUX FEENAlrB FLOW t(TR AUXILIARY FEEDWATER PlNP A t(TR AUXILIARY FEEDWATER PUt(P B AUX FW PIN'TEA)t RFPLY VALVE A AUX FM PlNP STEAN SUPPLY VALVE B ATWS RX TRIPPED 8.46249+01 8.75988+01 1.01391-11 1.01391-11

.00 1085 50 0 2 103.1 102.5 NOT TRIP HOT TRIP 58.9 62.6 33.4 1081.622.TRIPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NOT TRIP NOT TRIP".O9 2.1 LO)tER Lo)(ER LOWER LONER LOWER LOWER LOWER LO))ER LONER LOWER 497.4 497.4 497.9 494.6 497.7 496.0 100.5 497.4 O.364.OFF ON CLOSED OPEN ALRN ALIN GOOD 6009 6009 6009 6009 Lu Goon 6009 Goon 6009 6009 Boo<HWRH Goon 6009 6009 ALfN ALR)(ALRt(AUN DEL DEL ALR)(ALRt(6009 GOOD 6009 Boon 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 6009 Gooe GOOD 6009 6009 6009 6009 AUN PSIG PSIG PSIG FKf DEGF KGF DEBF DEGF DEGF DEGF X DEBF GN BPN OCT Bi 1992 09:45 R.E.GINA SINKATOR TREND GROUP ASSIGNNENT SIOIRY PA6E 2 6ROUP!EVENT1 PRXEDUREl EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE NNL E.U.53 54 55 56 57 58 59 60 FSIA SAFETY INJECTION.

LOOP A AVG FLOM FSIB SAFETY INJECTION LOOP B AV6 FLOW P2160 SERVICE MATER PNPS A 5 B HEADER P2161 SERVICE MATER PIIPS C 5 D HEADER BER041 SERVICE MATER PlIP A INR042 SERVICE MATER PlIP B BER043 SERVICE MATER PNP C BKR044 SERVICE MATER P1IP D 0.600D PN 0.GOOD GPtl 85.600D PSI6 85.GOOD PSIG GOOD GOOD 600D 600D 0

~~I~OGRAM NAME:LRGTSZ.E.E.GIHNA NUCLEAR POWER PLANT OCT 08,92 09:44:00 TREND GROUP ASSIGHHENT

SUMMARY

GROUP NAME EVENT 2 GROUP DESCRIPTION PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 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 F0619 LRWST'WS033 WD033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14AS R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COHPONEHT COOLING LOOP TOTAL FLW REFUELING WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL, TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-CONTAINMEHT AREA 5-SPENT FUEL PIT AREA 9.LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAHPLE PANEL CONTAINMENT IODINE MONITOR R10A CONTAINHENT AIR PARTICULATE CONTAINMENT GAS MONITOR PLANT VEHT IODINE HONITOR R108 AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS'MONITOR LIQUID WASTE DISPOSAL MONITOR STEAM GENERATOR BLOWDOWN DRAIN AREA 29-CONTAINMEHT HIGH RANGE AREA 30-CONTAIHMEHT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5 LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAH 7-MID RANGE GAS CV VENT CHAN 9 HIGH RANGE GAS PLANT VENT CHAN 5-LOW RANGE GAS PLAHT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAH 5-LOW'RAHGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAH 9-HI RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LIHE 8 (SPIHG)CV HYDROGEN CONCENTRATION CV BASEMEHI'VL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV IHTERHEDIATE LVL 6 FT TEHP¹8 CV INTERMEDIATE LVL 6 FT TEHP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEHP¹17 1485.94.5 4.9 49.61.3 61.3 0.0 9.02214-02 7.35678i00 1.3994&00 1.47701+02 9.09354.01 1.09283+00 9.58719+01

.5'8901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.57174+04 5.05861.01 5'9440.01 4.40835i06 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312.07 6.86543-05 3.72621-03 9.99999-03 2.20392-01 2.20436-01 3.02040100 1~01048-02~0 95.1 106.0 106.6 106.7 106.2 117.5 G(a)GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD BALM GOOD QXO HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM BALM GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM X MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPH CPM CPH CPM CPM CPM CPM R/HR R/HR CPM UCI/CC HR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF$-/03 Time:~1QQ Message:~2)~IN NA TATION 1 2 VAL EDEXE I E ME A EF RM~i: 8*iiylA iliWDi<<ICh i i i d ii h iiiiiii site, connection and operation of IVlobile Dl Unit.im I Pl n n i i n: See Attached Mini-Scenarios

~M~a: "'THIS IS AN EXERCISE"'

R NT LLER E NLY N 1)Provide information verbally when appropriate actions are simulated or investigations are made by the appropriate players.E 1)As per attached IVlini-Scenarios F-/o33 INN A TATI N 1 2EVAL A EDE E E MINI-CENARI~A~ivi y: Bringing Mobile Dl Unit On Site (Security)

FOR ONTR LLER SE ONLY N 1)At 1000 Security Controller will inform Guard House personnel that there is a Simulated Mobile Dl Unit Trailer out front of Guard House and it needs to come on Site,~Ai E 1)Security personnel should inform TSC and Simulate processing the Dl Truck on Site Expeditiously.

NA ATI 1 2 EVAL ATED EXER I E MINI-CENARIO hg~ivi y: Connection and Operation of Mobile Dl Unit (Auxiliary Operator and Chemist).F R NTROLLER SE ONLY on roller N 1)Auxiliary Operator and Chemist should be notified by the TSC/CR that the Mobile DI Unit has arrived and needs to be connected and put in operation.

2l Inform Auxiliary Operator~AT 103 that he is to Simulate stop pumping from outside storage tank to inside storage tank because outside storage tank is empty.Also the Mobile Dl'nit should be ready to operate in about an hour.3)Inform Auxiliary Operator just prio'r to 1120 that he is to Simulate pumping water h 1 kd<<g k~Agkkg A ions Ex 1)'uxiliary Operator and Chemist should Simulate connecting the Mobile Dl Unit per procedure T-6.13.To be Simulated pumping to outside storage tank~T~111 hr.2)Auxiliary Operator should inform TSC/CR that the outside storage tank is empty and he has stopped pumping.Also that the Mobile Dl Unit will be in operation in about an hour.3)Auxiliary Operator should simulate starting to transfer water from the outside storage tank to the inside storage tanks per procedure T-6.12 at~112 hr.4)Auxiliary Operator should notify TSC/CR that he is starting to fill the inside Condensate Storage tanks.

Time:~1QQ Message:~2 INNA TATI N 2 EVAL ATED EXE I E ME AGE F RM C I<<C IC im la Pl n n i i n: See the Attached Sheets~Mesa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE NLY~C"'C 1)The Dl truck arrives on Site Anici ae R suls: 1)Operators performing the Applicable Actions of E-3.2)The TSC should be assuming command and control at approximately this time.

199'VALUATED EXERCISE Time:~/GG MAZOR PAEVLMETERS

'NGINEERED SAFEGUARDS Reactor Shutdown Q~ES)NO N-31~~CPS N-32 CPS N-35 i.oe-I AMPS N-36-ll AMPS Avg.Nuclear Power o RCS Pressure 073 PSIG PRZR Level A RCP RUNNING TOP B RCP STOPPED 1A S/G Level 1B S/G Level~'8 4 1A S/G Pressure~d7 PSIG 1B S/G Pressure 2.~PSIG Turbine/Generator ONLINE/FLIN 4 KV Buses NERGIZ DEENERGIZED 480V Buses NERGIZE DEENERGIZED DC Batteries A tSO VOLTS B/BO VOLTS Cnmt Pressure/7 PSIG nmt Sump A Level 2.I FEET Cnmt Sump B Level INCHES A Loop Hot Leg OF A Loop Cold Leg OF B Loop Hot Leg f4.I OF B Loop Cold Leg~2 OF RVLIS*CET f V4.24F 3/G A Total Aux FW Flow~GPM S/G B Total Aux FW Flow~13.GPM Hi h Head S.I.Pum s FI-924.GPM FI-925 Q GP 1A.INSERV OOS 1B INSERV TB OOS 1C INSERV TB OOS BAST Level=~p OOS OOS Containme Recirc Fans 1A.INSER STBY OOS 1B.S STBY OOS 1C.NSER STBY OOS 1D.NSER STBY OOS Post Accident Dampers PE Service Water Pum s 1A.NSER STBY OOS Low Head S.I.Pum s FI-626 Cl GPM 1A.INSERV T OOS RECIRC 1B INSERV TB OOS RECIRC RWST Level=~E.Containment S ra Pum s FI-931A 0 GPM FI-931B 0 GPM 1A.INSERV B 1B.INSERV TB NaOH Tank Level=CLOSED DIESEL GENERATORS A.RUNNING UNLOADED T OOS B.RUNNING UNLOADED B OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.INSERV TB OOS 1B.NSER STBY OOS Turb.Driven INSERV TB OOS CST Level FEET OOS 1B.S R STBY OOS 1C.NSE STBY OOS 1D.SE V STBY OOS A&B Header ressure fh PSIG Com onent Coolin Water Pum s 1A.INSERV STBY 0 1B.NSER STBY OOS Surge Tan vel=~L-Standb Aux.Fe ater Pum s 1C.INSERV TB OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples Bs 1992 10:00 R.E.GINA Sit(ULATOR TREND GIP ASSIGI(Et(T SUt(t(ARY PAGE 11 2 3 4 5 6 7 8 10 11 12 13 IS 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 6ROUP: EVENTi PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID ATMS RXT N31 N32 N35 N36 NP PRCS LPIR FRCLA FRCLB RXT16 RXT17 TSUBTC LSBA LSBB PSBA PSGB GENBKRl GENBKR2 BUS11A BUS11B BUS12A BUS12B B11A12A BIIB129 PCV LS(NPA L0942E L0943E L0942D L0943D L0942C L0943C L09428 L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAVGBMID LRV TCCORE FAUXFWA FAUXFWB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT W/0 SCRAtt REACTOR TRIP BREAKER STATUS SolSCE RANGE DETECTOR N-31 SISCE RANGE DETECTOR N-32 INTEf(t(EDIATE RANGE DETECTOR N-3S INTER)(EDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTE)(AVG PRESS PRESSURIIER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOW REACTOR COOLANT LOOP 8 AVG FLOW RCPA BREAKER CAUSE Rr TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED t(ARGIN STt(GEN A NARROW RANGE AV6 LEVEL ST)(GEN B NARROW RANGE AVG LEVEL STt(GEN A AVERAGE PRESSURE STH GEN B AVERAGE PRESSURE GBERATOR ON LINE BREAKER 161372 BBGQTOR ON LINE BREAKER 9)(1372 BUS 11A SUPPLY BREAKER BUS 11B SIPPLY BREAKER NOT TERt(I@ATED ON PPCS (7/19/91)NOT TERt(INATED ON PPCS (7/19/91)BUS 11A TO 12A TIE BREA(ER BUS 11B TO 128 TIE BREIER CONTAIN)(ENT AVERAGE PRESURE CONTAINt(ENT SUt(P A AVE)mGE LEVEL SU)P 8 LEVEL 8 INCHES (TRAIN A)SU)P B LEVEL 8 It/CHES (TRAIN B)SU)P B LEVEL 78 INCHES (TRAIN A)SUtP B LEVEL 78 INCHES (TRAIN B)SUtP B LEVEL 113 INCHES(TRAIN A)SUtP B LEVEL 113 INCHES(TRAIN B)SUtP B LEVEL 180 INCHES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SU)P B LEVEL 214 INCHES(TRAIN A)SUtP B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TEt(PERATURE RCLB HOT LEG TBlPERATURE RCL4 COLD LEG TEt(PERAT(BE

'RCLB COLD LEG TEt(PERAT(RE RCLA TAVG (THOT/TCOLD WIDE RNG)RCLB TAVG (THOT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 INCORE TC AVERAGE TEt(P S/G A:OTAL AUX FEEDMATW FLOW S/6 9 TOTAL AUX FEEDVAm FLOW t(TR AU)(ILIARY FEEDMATER PUtF A t(TR AU)(ILIARY FEEDMATER PU)(P B AUX FW PUt(P STEAtl SUPPLY VALVE A AUX FW PlIP STEA)t SLR'LY VALVE B ATNS RX TRIPPED 8.52117+01 8.8206801 1.01391"Ii 1.01391-11

.00 1073.51.5 12.3 106.9 TRIPPED NOT TRIP 58.7 60.4 49.3 1067.622.TRIPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NOT TRIP NOT TRIP-.17 2.1 LONER LONER LONER LONER LONER.LONER LONER LONER LONER LONER 493.9 496.1 O'.2 494.2 494.1 495.2 99.6 496.2 0.129.OFF CLOSED CLOSED ALRN ALRt(6009 6009 6009 6009 6009 LALt(6009 INHB 600D ALR)(6009 Booe HNRt(6009 6009 GOOD ALRl ALRt(ALRt(ALRt(DEL DEL AUI ALRt(6009 6009 6009 6009 6009 6009 6009 BOOB 6009 6009 6009 6009 6009 6009 6009 6009 6009 GOOD BM9 6009 6009 6009 E.U.CPS CPS At(P X PSIG X X X DEGF X'X PSIG PSIG KGF DEBF DEGF DEGF KGF DE6F DEGF GPt(9%

OCT 8~892 10:00 R.E.GINA SitSLATN TREND 6IIP ASSIGNMENT QNNRY PAGE 2 6ROUP: EVENTi PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION NLUE QNL 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 SERVICE WATER HIPS A h B HEADER SERVICE WATER PNPS C 5 D HEADER SERVICE WATER PNP A SERVICE WATER PIIP B SERVICE WATER PllP C SERVICE WATER PlIP 9 0.6009 Ptl 0.6009 GPN 85.6009 PSI6 85.600D PSI6 6009 6009 600D 6009

~~I~ROGRAM NAME:LRGTSZ.E.E.GIKHA NUCLEAR POWER PLANT OCT 08,92 10:00:00 TREND GROUP ASSIGKHENT SUMHARY GROUP NAHE EVENT 2 GROUP DESCRIPTION PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 0 J F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R'I4A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVN TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLW REFUELING WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WINO DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-CONTAINMENT, AREA 5 SPENT FUEL PIT AREA 9-LETDOWN LINE MOHITOR AREA 34-AUX BLDG CV SPRAY PUHP AREA 35-PASS SAMPLE PANEL COHTAINMEHT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE CONTAINHENT GAS MONITOR PLANT VENT IODINE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIDUID'WASTE DISPOSAL MONITOR STEAM GENERATOR BLOWDDWN DRAIN AREA 29-CONTAINMENT HIGH RANGE AREA 30-CONTAINHENT HIGH RAHGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMHA CV VENT CHAN 7-HID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VEHT CHAN 5-LOW RANGE GAS PLANt VENT CHAN 7 MID RANGE GAS PLAN'I VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CNAH 9-Hl RANGE GAS AREA 31 STEAH LIHE A (SPING)AREA 32 STEAM LINE 8 (SPING)CV HYDROGEN CONCENTRATION CV BASEHENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 Ft TEHP¹7 CV INTERMEDIATE'LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEHP¹9 CV IHTERMEDIATE LVL 6 Ft TEMP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 5.0 55.61.3 61 4 0.1 9.02214-02 7.35678+00 1.39946+00 1 47701+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.57174+04 5.05861.01 5.09440-01 1.57835+03 1.89699.07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 2.09411-07 1.34492 05 1.27941-03 3.02040+00 1.01048-02

~0 95~1 106.0 106.6 106.7 106.2 117.5 G(XS GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD BALM GOOD GOOD.GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD NALH GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD.GPM MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H HR/H MR/M MR/H CPH CPH CPM CPM CPM CPM CPH CPM R/HR R/HR CPH UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/NR DEGF DEGF DEGF DEGF DEGF DEGF Time:~1~1 Message:~g~INNA TATIRN 1 2 EVAL ATED EXER I E~MES A EF RM~III I: M I<<R IR Simula ed Plant Condition:

See the Attached Sheets~Messe e: """THIS IS AN EXERCISE""" The following annunciator is received:~J-9 (Safeguard Breaker Trip)FOR CONTROLLER USE ONLY Controller Notes: 1)When operators check the Control Board, inform them that the"A" SW Pump switch indicates a white light and the"A" SW Pump indicates tripped.lf operators try to restart pump because of Sl, it will not restart.An ici a ed Re ul s: 1)Operators perform the Applicable Actions of AR-J.9.2)Operators should inform TSC of"A" SW Pump problem.3)Operators/TSC should send an Auxiliary Operator to the Screenhouse to check on the"A" SW Pump.4)Operators performing the Applicable Actions of E-3.

199K EVALUATED EXERCISE Time:~biS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s MAJOR PAEULMETERS

.'eactor 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 DC Batteries A PO Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level A 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 ES NO FI-924~GPM FI-925~GPM 1A.INSERV TB OOS 1B.INSERV B OOS 1C.ZNSERV TB OOS BAST Level=/O C PS.E-s AMPS.~oI-AM PS 0 OP<7 PSIG>4 l g RUNNING TOPPE UNNING STOPPED S.~4~IO7 PS IG 2.~PSIG 0 LIN ERGIZE DEENERGIZED ERGIZE DEENERGIZED

~VOLTS B/3O VOLTS-o I 0 PSIG~2.~e FEET INCHES'fge OF~1'i~OF~6~40 F OF Flow~GPM Flow~~GPM Low Head S.Z.Pum s FZ-626 GPM 1A.INSERV TB OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=~~4 Containment S ra Pum s FZ-931A 0 GPM FI-931B C9 GPM 1A.INSERV TB OOS 1B.INSERV T OOS NaOH Tank Level=Containment Recirc Fans 1A.NSER STBY OOS 1B.NS STBY OOS 1C.INSE STBY OOS 1D.NSE STBY OOS Post Acci ent Dampers PE CLOSED Service Water Pum s 1A.INSERV STBY 0 1B.S STBY OOS 1C.ER STBY OOS 1D.NSER STBY OOS A&B Header Pressure 7 0 PSIG Com onent Coolin Water Pum s DIESEL GENERATORS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED OOS Security RUNNING UNLOADED TB OOS 1A.INSERV STBY OS 1B.ERV STBY OOS Surge Tan vel=ENGINEERED SAFEGUARDS Standb Aux.Feedwater Pum s 1C.INSERV TBY OOS 1D.INSERV OOS Aux.Feedwater Pum s 1A.INSERV T OOS 1B.NSER STBY OOS Turb.Driven INSERV TB OOS CST Level FEET*CET=Average of Selected Core Exit Thermocouples 8i 1992 10: 14 R.E.GINA SINULATOR PAGE 1 TREND GROUP ASSIGNNE)(T SUNNARY GROUP: EVENT1 PROCEDURE:

EPIP 1-5 PLANT 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 ATWS RXT N31 N32 N35 N36 NP PRCS LPZR FRCLA FRCLB RXT16 RXT17 TSUBTC LSBA LSGB PSGA PSGB GENBKR1 GENBKR2 BUS11A BUS118 BUS12A BUS128 811AI2A 8118128 PCV LSlNPA 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 SCRAN REACTOR TRIP BREAKER STATUS SIKE RANGE DETECTOR N-31 SMCE RANGE DETECTOR N-32 INTERNEDIATE RANBE DETECTOR N-35 INIERNEDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEN AVG PRESS PRESSURILER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOW REACTOR COOLANT LOOP 8 AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED t%5IN STN GEN A NARROW RANGE AVG LEVEL STN GEN 8 NARROW RANGE AVG LEVEL STN 6EN A AVERAGE PRESSURE STN GEN 8 AVERAGE PRESSURE GBGQTOR ON LINE BREAKER 161372 BBGQTOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 118 SUPPLY BREAKER NOT TERNINATED ON PPCS (7/19/91)NOT TERNINATED Ott PPCS (7/19/91)BUS liA TO 12A TIE BREAKER BUS 118 To 128 TIE BRENER CONTA It(NENT AVERAGE PRESSURE CONTAINNENT PJNP A AVERAGE LEVEL SUtP 8 LEVEL 8 INCHES (TRAIN A)SUtP B LEVEL 8 It(CHES (TRAIN 8)SUtP'LEVEL 78 It<CHES (TRAIN A)SSP 8 LEVEL 78 INQ!ES (TRAIN 8)SUNUP 8 LEVEL 113 INCHES(TRAIN A)SUti'LEVEL 113 INCHES(TRAIN 8)SUtP 8 LEVEL 180 INCHES(TRAIN A)SUtP 8 LEVEL 180 INCHES(TRAIN 8)SUtl-'LE'<re 214 INCHES(TRAIN A)SUtP 8 LEVEL 214 INCHES(TRAIN 8)RC(A HOT LEG TENPERATSK RCLB HOT LEG TENPERATURE RCLA COLD LEG TENPERATlBE RCLB COLD LEG TE)(PERAT(BE RCLA TAVG (THOT/TCOLD WIDE RNG)RCLB TAVG (THOT/TCOLD WIDE RNB)REACTOR VESSEL AVERAGE LEVEL E1.1 It'CORE TC AVERAGE TENP S/6 A TOTAL AUX FEEDMATER FLOW S/G 8 TOTAL AUX FEEDWATER FLOW NTR AUXILIARY FEEDWATER PUt(P A NTR AUXILIARY FEEDMATER PUNP 8 AUX FW PlIP STEAN SUPPLY VALVE A AUX FW PU5'TEAN SUPPLY VALVE 8 ATWS AUI RX TRIPPED ALRN 8.91247%1 600D 9.00531401 6009 1.01391-11 6009 1.01391-11 6009.00 6009 1084.LALN 42.7 6009 12.3 INHB 106.9 6009 TRIPPED ALRtl NOT TRIP 6009 60.5 600'3.2 HWRt(48.1 GO09 1078.6009 622.6009 TRIPPED AUI TRIPPED ALRN TRIPPED ALRtf TRIPPED AUI NOT TRIP DEL NOT TRIP DEL NOT TRIP ALRtf NOT TRIP ALRN".19 6009 2.2 6009 LOWER G009 LONER 6009 LOWER GOOD LOMER 6009 LOWER 6009 LOMER 6009 LOWER 6009 LOWER 6009 LOWER 6009 LOMER 6009 493.5 GOOD 495.7 6009 493.8 6009 494.0 6009 493.7 6009 494.8 6009 99.6 6009 495.7 600e 0.6009 197.6009 OFF G009 ON 6(I9 CLOSED 6009 CLOSED 6009 g-'/I/E.U.CPS CPS ANP ANP X PSIG X X X DEGF X PSI6 PSIG DE6F KGF DEBF DE6F DE6F DEBF DEGF PN 6PN XT Gs 1992 10: 14 R.E.GIN@SIRLATOR TREND Gm'SSIGlST RNNSY PAGE 2 GROUPS EVENT1 PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E.U.53 FSIA 54 FSIB 55 P21b0 5b P21bi BKR041 58 BKR042 59 BKR043 b0 BKR044 SAFETY INJECTION LOOP A AVG FLN SAFETY INJECTION LOOP 8 AVG FLON SERVICE@TER PlNPS A 5 8 HEADER SERVICE NTER PIWPS C h D HEADER SERVICE HATER PNP A SERVICE HATER PNP 8 SERVICE WTER PuP C SERVICE WTER PNP 0 OFF ON ON ON 0.600 D GPM 0.600 D GPN 72.600D PSI6 80.GOOD PSIG 6009 600D Gm GOOD E+J

~~~ROGRAM KAME:LRGTSZ.E.E.GINNA KUCLEAR POKER PLANT OCT 08,92 10:16:00 TREND GROUP ASSIGNMEHT SUHHARY GROUP NAHE EVENT 2 GROUP DESCRIPTIOH PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPT ION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43-F0619 LRIIST IIS033 M0033 MT033 lIT250 IIDT2 R01 R02 R05 R09 R34 R35'10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R15 R12AS R12A6 R12A7 R12A9 R14AS R14A7 R14A9 R15AS R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLU REFUELING iIATER STORAGE TANK LVL 33 FOOT LEVEL NIKD SPEED 33 FOOT LEVEL KIND DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEHPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-COHTROL ROOM AREA 2-CONTAINHENT AREA 5-SPENT FUEL PIT AREA 9-LETOOMN LINE HOHITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAHPLE PANEL CONTAINMENT 1001HE MONITOR R'10A CONTAIHHENT AIR PARTICULATE COHTAINHENT GAS MOHITOR PLANT VENT IOOIKE HOHITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS HONITOR LIQUID UASTE DISPOSAL MONITOR STEAM GENERATOR BLOMDOMN DRAIN AREA 29-CONTAINHENT HIGH RANGE AREA 30-CONTAINMENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOU RAHGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-HID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CHAN 5-LO1I RANGE GAS PLANT VENT CHAN 7 MID RANGE GAS PLANT VENT CNAH 9-HIGH RANGE GAS'IR EJECTOR CHAN 5-LOM RANGE GAS AIR EJECTOR CHAN 7-HID RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 31 STEAH LINE A (SPING)AREA 32 STEAM LINE 8 (SPIKG)CV HYDROGEN COHCENTRATION CV BASEHEHT LVL 6 FT TEMP¹3 CV INTERHEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEHP¹10 CV OPERATIHG LVL 6 FT TEHP¹17 1485.94.5 4.9 80.61.3 63.3 2.0 9.02214-02 7.35678+00 1.39946+00 1.46701+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.52174+04 5.05861-01 5.09440-01 1'7835+03 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543.05 3.72621-03 2.09411-07 1.34492-05 1.27941-03 2.90040+00 1.01048.02

.0 95.1 106.0 106.6 106.7 106.2 117.5 6000 6000 6000 GOOD GOOD GOOD GOQO GOOD GOOD 6000 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD 6000 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM 6000 GOOD GOOD GOOD GOOD GOOD GOOD GPM X MPH DEG.DEGF DEGF DEGF MR/H MR/H HR/H MR/H MR/H MR/H CPM CPM CPH CPM CPM CPM CPH CPM R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF Time:~1~1 Message:~1~l~NA TATI N 2 EVAL ATED EXER I E ME A E F RM~Mf:A SNAP<<S ANSI'AS Water Pump trip problem.Sim la d Plan Condi i ns: 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 are made by the Auxiliary Operator sent to the Screenhouse to check the"A" SW Pump trip problem.Antici a ed Results: 1)As per Mini-Scenario Anticipated Results.

I NA TATI N 1 2 EVALUATED EXER ISE MINI-ENARI Ac1~ivi y: "A" Service Water Pump tripping out problem check out.FOR CONTROLLER USE ONLY Controller Notes: ti When Auxiliary Operator checks the"A" SW Pump,~inf rm the pump appears normal.2i If Auxiliary Operator checks the"A" SW Pump Electrical Breaker,~inf rm him that it appears normal.3)Go directly to the Gas Leak Detection IVlini-Scenario.

Antici a ed Re ul s: 1)Auxiliary Operator should check the"A" SW Pump motor for heat (i.e., by touching motor)and for odor (i.e., by smelling).

2)Auxiliary Operator should inform Control Room/TSC of results of the"A" SW Pump inspection.

Time:~1'essage:

~2 INN A TATI N TED E E E ME A E F RIVI~Mt: A ill~Op i E t,d i di I i t Natural Gas leak.Simula ed Pl n Condi ions: See the Attached Mini-Scenario

~Messs e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Note: 1 j Provide information verbally when appropriate actions are simulated or investigations are made by the Auxiliary Operator sent to the Screenhouse to check the"A" SW Pump trip problem.An ici ated Results: 1)As per Mini-Scenario Anticipated Results.

INNA TATI N 1 2 EVALUATED EXER I E ININI-CENARI~A~Ivi if: Screenhouse Flammable Gas Leak Detection and Isolation FOR CONTROLLER USE ONLY 1)~Wh n Auxiliary Operator enters the Screenhouse and checks the"A" SW Pump motor,~inf rm him that there is a very strong odor of gas where he is standing.2)~Wh n the Auxiliary Operator checks the Basement of the Screenhouse,~inf rm him that there is a hissing sound coming from the ceiling.An ici ated Results: 1)Auxiliary Operator should inform Control Room/TSC of the strong odor of gas by the"A" SW Pump and the stronger odor of gas and the hissing sound in the Basement of the Screenhouse.

2)~Wh n requested by Control Room/TSC to isolate Natural Gas and propane gas to Screenhouse, Auxiliary Operator will simulate the following:

a)Closing the Gas Shutoff for Natural Gas to the Screenhouse (V7229A)located just outside of Screenhouse, southeast corner.b)Closing the Gas Shutoffs on top of the propane tanks supplying the Screenhouse located west of Screenhouse.

3)Auxiliary Operator should inform Control Room/TSC of isolation of gas to the Screenhouse.

Time:~1'essage:

~3 INN A TATI N 1 2 EVAL TED E E E ME A E F RM MMM f: 8 I 1.'<<IR Simula ed Plan Condi ions: See the Attached Sheets~Mssss"""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Antici ated Results: 1)Operators performing the Applicable Actions of E-3.2)Control Room/TSC, when informed of the gas leak in the Screenhouse, should request the Auxiliary Operator to isolate all sources of gas to the Screenhouse.

3)Control Room should communicate with the TSC on the gas problem in the Screenhouse.

4)If not already isolated, the Control Room/TSC should send an Auxiliary Operator to isolate the"B" S/G ARV when requested to do so.(continued on the next page) 5)TSC, afterassessing Plantconditions,should declare a ITE A EA EMER EN Y in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification," EAL: Hazards Being Experienced or Projected; Entry of Uncontrolled Flammable Gases into Vital Areas.Appropriate notification should be made per EPIP 1-5 (Notifications) and 0-9.3 (NRC, State and Counties Immediate Notification).

6)TSC should inform the EOF of Plant Conditions and the SITE AREA EMERGENCY declaration.

7)A Site Evacuation should be commenced if it is determined necessary.

8)Repair team sent out to check the CCW Pump, should report the 1A CCW Pump Mechanical Seal needs replacing and that the I A CCW Pump motor needs to be cleaned and dried or replaced.They report these repairs will take approximately eight (8)hours.They also report that the 1B CCW Pump Mechanical Seal is leaking a small amount.9)Repair team sent out to check the"A" S/G ARV control problem should report that the ARVs Mercoid Controller needs to be replaced, They report that it will take approximately one (1)hour to repair it.10)If not already done, the Repair Team sent out to check the"B" S/G ARV steam leak should request that it be isolated.

1992'VALUATED EXERCISE Time: 10 3>MAZOR PAEULMETERS ENGINEERED SAFEGUARDS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB ENGINEERED SAFEGUARDS OOS Aux.Feedwater Pum s 1A.INSERV TB OOS 1B.SE STBY OOS Turb.Driven INSERV TB OOS CST Level~FEET*CET=Average of Selected Core Reactor Shutdown YES NO N-31 2.CPS N-32~CPS N-35 I.es (I A-MPS N-36 II A-MPS Avg.Nuclear Power o RCS Pressure O7O7 PSTG PRZR Level 3 A RCP RUNNING TOPPED B RCP UNNZN STOPPED 1A S/G Level t'e~4 1B S/G Level~sv lA S/G Pressure 07/PSIG 1B S/G Pressure PSIG Turbine/Generator ONLINE FFLI 4 KV Buses NERGIZ DEENERGZZED 480V Buses RG D DEENERGIZED

'DC Batteries A~OVOLTS BIMVOLTS Cnmt Pressure~Ll PSIG Cnmt Sump A Level FEET Cnmt Sump B Level INCHES A Loop Hot Leg~iMQ OF A Loop Cold Leg VVF B Loop Hot Leg~HiS: OF B Loop Cold Leg'fsI 0 OF RVLIS~V.*CET M9'S;7 OF S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow~AF GPM DIESEL GENERATORS Hi h Head S.I.Pum s FI-924 O GPM FI-925 C)GPM 1A.INSERV T 1B.INSERV 1C.INSERV BAST Level=OOS OOS B OOS Low Head S.I.Pum s FZ-626GPM 1A.INSERV TB OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=3.Containment S ra Pum s FI-931A&GPM FI-931B C)GPM 1A.INSERV T OOS 1B.INSERV S B OOS NaOH Tank Level=Containment Recirc Fans 1A.NSE STBY OOS 1B.SE STBY OOS 1C.SE STBY OOS 1D.SER STBY OOS Post Accident Dampers OPE CLOSED Service Water Pum s 1A.INS V STBY 0 1B.S STBY OOS 1C.NSER STBY OOS 1D.NSER STBY OOS A&B Header ressure~~b PSZG Com onent Coolin Water Pum s 1A.INSERV STBY 0 1B.NSER STBY OOS Surge Tank Level=~'f Standb Aux.Feedwater Pum s 1C.INSERV ST OOS 1D.INSERV STB OOS Exit Thermocouples 8i 1992 10:30 R.E.GINA SIWLATOR TREND GRI)P ASSIGN)(ENT SU)tt(ARY PAGE 1 6ROUP: EVENT1 PROCEDURE'PIP I<PLANT STATUS 1 2 3 5 6 7 8 9 10 11 12 13 14 15 16 17 18 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 ATKi RXT N31 N32 N35 N36 NP PRCS LPLR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PS6B GENBKRl GENBKR2 BUSllA BUS11B BUS12A BUS128 Bi 1A12A B11B12B PCV LSRlPA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAVGBMID LRV TCCORE FAUXFMA FAUXFMB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT M/0 SCRAt(REACTOR TRIP BRENER STATUS SMICE RA)(GE DETECTOR N-31 SONCE RAN6E DETECTOR N-32 INTER)(EDIATE RANGE DETECTOR N-35 INTER)(EDIATE RANK DETECTOR N"36 AVERAGE NUCLEAR POMER REACTOR COOLANT SYSTE)f AVG PRESS PRESSURIZER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOM REACTOR COOLANT LOOP 8 AVG FLOM RCPA BREAKER CAUSE RX TRIP RCPB BRENER CAUSE RX TRIP INCORE TC SUBCOOLED HAIN STt(GEN A NARROM RANGE AVG LEVEL STt(6EN 8 NARROM RANGE AV6 LEVEL STt(GE)t A AVERAGE PRESSURE STtt GEN 8 AVERAGE PRESSURE 696&OR ON LINE BRENER 161372 GBGNTOR ON LINE BRENER 9X1372 BUS 11A SUPPLY BRENER BUS 11B SL'PPLY BREAKER NOT TER)(It(ATED Ot(PPCS (7/19/91)NOT TERHINATED 0)t PPCS (7/19/91)BUS 1lA TO 12A TIE ERENER BUS 11B TO 128 TIE BRENER CONTAIN)(Et(T AVERAGE PRESSURE CONMINMEtiT StJ5'AVERAGE LEVEL SU%'LEVEL 8 It(CHES (TRAIN A)SUtP B LEVEL 8 It(CPS (TRAIN B)SUlF'LEVEL 78 It<CHES (TRAIN A)SU%'LEVEL 78 INCHES (TRAIN 8)SUtI'LEVEL 113 INCHES(TRAIN A)SUtP 8 LEVEL 113 INCHES(TRAIN 8)SU!I'LEVEL 180 INCHES(TRAIN A)SUtF'LEVEL 180 INCHES(TRAIN 8)SSP 8 LEVEL 214 INCHES(TRAIN A)SUtP B LEVEL 214 INCHES(TRAIN 8)RCLA HOT LEG TE)(PERATURE RCLB HOT LEG TEt(PERATURE RCLA COLD LEG TEt(PERATNE RCLB COLD LEG TEt(PERATNE R(u TAVG (THOT/TCOLD MIDE RNG)RCLB TAVG (THOT/TCOLD MIDE RN6)REACTOR VESSEL AVERAGE LEVEL El.1 INCOPE TC AVERAGE TEttP S/G A TOTP AUX FEEDMATER FLOM S/6 B TOTAL AUX FEEDMATlJt FLOW t(TR AUXILIARY FEEDMATER PU)(P A t(TR AUXILIARY FEEDMATER PU)(P B AUX FM PUtP'STEAt(SUPPLY VALVE A AUX FM PUt'iP STEA)l SUPPLY VALVE 8 I VALUE ATMS RX TRIPPED 8.20350IOI 8.79019401 1.01391-11 1.01391"li

.00 1076.43.0 12.3 106.9 TRIPPED NOT TRIP 59.6 62.2 57.1 1071.622.TRIPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NOT TRIP NOT TRIP-.21 2.2 LOWER LOWER LOWER LOWER LOWER LOWER LOWER LOWER LOWER LOWER 493.5 495.5 493.8 494.0 493.7 494.7 99.6 495.7 0.158.OFF ON CLOSED I)AL ALRt(ALR)(600D 600D 6009 600D GOOD LAL)t 600D INH3 600D ALR)t 6009 600~HMR)(GOOD GOOD GOOD ALRt(ALR)(ALRtf ALR)(DEL DEL ALRtt ALRtt GOOD GOOD GOOD 6009 6000 6009 6XD 6000 6000 600))GOOD GOOD 6000 GOOD GOOD GOOD GOOD GOOD 6000 6009 600D GOOD GDOD 600D E.U.DE6F y.y.PSIG PSIG DEGF KGF DEGF lKGF DE6F DEGF)(DEGF PN GPt(p-/2/

XT 8s 1992 10:30 R.E" GINA SINILATOR'TREND GROUP ASSIMENT SNNARY PAGE 2 GROUP: EVENT1 PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E.U.53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BNR042 59 INR043 60 INR044 SAFETY IN:ECTION:LOOP A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SERVICE MATER PINPS A&B HEADER SERVICE MATER PNIPS C&D HEADER SERVICE WATER PNP A SERVICE MATER PlNP B SERVICE MATER PNIP C SERVICE MATER PNIP 0 0.600 D GPtI 0.GOOD GPN 72.600D PSI6 80.GOOD PSI6 600D GOOD GOOD Gm EMJ

~~ROGRAM NAHE:LRGTSZ.E R.E.GINNA NUCLEAR PSJER PLANT OCT 08,92 10:32:00 TREND GROUP ASSIGNHENT

SUMMARY

GROUP NAHE EVENT 2 GROUP DESCRIPTIOH PROCEDURE:

EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE EHGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 0 J F0619 LRNST NS033 IID 033 llT 033 MT250 IST2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12AS R'l2A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COHPONENT COOI.IHG LOOP TOTAL FLII REFUELING'MATER STORAGE TANK LVL 33 FOOT LEVEL MIND SPEED 33 FOOT LEVEL IJIND DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-CONTAINHENT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUHP AREA 35-PASS SAMPLE PANEL CONTAINHENT IODINE HONITOR R10A CONTAINHENT AIR PARTICULATE CONTAINMENT GAS HONITOR PLANT VENT IODINE HONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID HASTE DISPOSAL HONITOR STEAH GENERATOR BLDNDDNN DRAIN AREA 29-CONTAINHEHT HIGH RANGE AREA 30-COHTAINHEHT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LRI RANGE GAS CV VENT CHAN 6 AREA GAMMA CV VENT CHAN 7-HID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CNAH 5-Lml RANGE GAS PLANT VENT CHAN 7-HID RANGE GAS PLANT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LQI RANGE GAS AIR EJECTOR CHAM 7-MID RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 31 STEAH LINE A (SPING)AREA 32 STEAH LINE 8 (SPING)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEHP¹3 CV INTERHEDIATE LVL 6 FT TEHP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEHP¹9 CV IHTERHEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94'4.8 80.61.3'3.0 1.7 9.02214-02 7.35678+00 1.39946+00 1.43501+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7 38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.47174+04 5.05861.01 5.09440-01 1.57835+03 1.89699.07 2.53990.02 3.57435-05 1.41261-03 4.40312.07 6.86543.05 3.72621-03 2.09411-07 1.34492-05 1.27941-03 2.85040+00 1.01048.02

.0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD G(XX)GOOD GOOD GOOD GOOD HALH GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD NALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPH X MPH DEG.DEGF DEGF DEGF MR/H HR/H MR/H HR/H MR/H MR/H CPM CPH CPH CPM CPH CPM CPH CPH R/HR R/HR CPM UCI/CC HR/NR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF Time:~~4 Message:~4 INN A TATI N 1 2 EVAL ATED EXER E lVIES A E FORM~MI: M I<<C IR Simula ed Plan Condi ions: See the Attached Sheets~Masse e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~CI R 1)Accident response and evaluation continue.2)If not done earlier, the Auxiliary Operator sent out to isolate the"B" S/G ARV steam leak, reports to Control Room/TSC that it is isolated.Antici a ed Resul s: 1)Operators performing the actions of E-3/Steam Generator Tube Ruptures)should have stabilized the Plant at approximately this time and be awaiting determination by the TSC as to what post SGTR Cooldown procedure to use.2)If not done earlier, Control Room should inform the TSC of the"B" S/6 ARV steam leak isolation.

3)The TSC should be evaluating the flammable gas problem in the Screenhouse and be taking corrective actions required to return the Screenhouse to a safe condition.

's (continued on the next page) 4)The TSC Dose Assessment should be calculating and quantifying any release paths to the environment.

5)TSC should have determined and informed the Control Room to use ES-3.1 (Post-SGTR Cooldown Using Backfill).

6)Repair Team sent out to check the"B" S/G ARV steam leak should have reported back that it appears that the steam leak was from a hole drilled almost through the pipe.They report that it will take approximately one and one-half hours to repair the leak.

199EVALUATED EXERCISE Time:/0'/b MAZOR PAEUQIETERS ENGINEERED SAFEGUARDS Reactor Shutdown ES NO N-31~CPS N-32 CPS N-35 I.o a-I AMFS N-36~/AMP S Avg.Nuclear Power RCS Pressure O7 PSIG PRZR Level A RCP RUNNING TOPPE B RCP UNNI STOPPED 1A S/G Level~ls&1B S/G Level AVE lA S/G Pressure 4 PSZG 1B S/G Pressure R~PSIG Turbine/Generator ONLINE/F 4 KV Buses NERGIZ DEENERGIZED 480V Buses NERGIZ DEENERGIZED DC Batteries A~lo VOLTS B ISOVOLTS Cnmt Pressure~~2a.PSTG Cnmt Sump A Level 24 3 FEET Cnmt Sump B Level INCHES A Loop.Hot Leg OF A Loop Cold Leg f73 P OF B Loop Hot Leg 8.K 0F B Loop Cold Leg 97.o 0F RVLIS%&*CET~9.7 OF S/G A Total Aux FW Flow O GPM 5/G B Total Aux FW Flow~SGPM DIESEL GENERATORS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB OOS ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.INSERV B OOS 1B.NSE STBY OOS Turb.Driven INSERV TB OOS CST Level~FEET Hi h Head S.I.Pum s F1-924~GPM Fl-925~GPM 1A INSERV TB OOS 1B.INSERV B OOS 1C.INSERV TB OOS BAST Level=/O Low Head S.I.Pum s FI-626 O GPM 1A.INSERV TB OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=S.Containment S ra Pum s FI-931A C7 GPM FI-931B~GP 1A.INSERV T OOS 1B.INSERV TB OOS NaOH Tank Level=Containment Recirc Fans 1A.SERV STBY OOS 1B.NSE STBY OOS 1C.R STBY OOS 1D.INSERV STBY OOS Post Aces ent Dampers OPE CLOSED Service Water Pum s 1A.INSERV STBY OS 1B.S STBY OOS 1C.SE STBY OOS 1D.NSER STBY OOS A&B Header Pressure~7 0 PSTG Com onent Coolin Water Pum s 1A.INSERV STBY OS 1B.NSE V STBY OOS Surge Tau vel=~5 Standb Aux.Fe water Pum s 1C.INSERV TB OOS 1D.INSERV TB OOS*CET=Average of Selected Core Exit Thermocouples

,8~1992 10'44 R.E.GMA SINULATOR-TREND GROUP ASSIBNNENT SUNNARY PA6E 1 6ROUP: EVENT}PROCEDURE}

EPIP 1-5 PLANT STATUS 1 2 3'5 6 7 8 10 ii 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'D ATMS RXT N31 N32 N35 N36 NP PRCS LP2R FR%A FRCLB RXT}6 RXT}7 TSUBTC LSBA LSBB PSBA PSBB GENBKR}GENBKR2'BUSA BUS}1B BUS12A BUS}2B B}1A}2A Bi}B12B PCV LS(@PA L0942i L0943E L0942D L0943D L0942C LO943C L0942B L09439 L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAVGBMID LRV TCCORE FAUXFWA FAUXFMB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT M/0 SCRAN REACTOR TRIP BREAKER STATUS SO(jKE RANGE DETECTOR N-31 SMCE RANGE DETECTOR N-32 INTERNEDIATE RANGE DETECTOR N-35 INTEI(NEDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEN AVG PRESS PRESSURI2ER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOW REACTOR COOLANT LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED NARBIN STN GEN A NARROM RANGE AVG LEVEL STN GEN B NARROM RANGE AVG LEVEL STN GEN A AVERAGE PRESSURE STN BEN B AVERAGE PRESSURE GENERATOR ON LINE BREAKFR 161372 GsSRATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SUPPLY BREAKER NOT TERNINATED ON PPCS (7/19/91)NOT TERNlhATED Ott PPCS (7/19/91)BUS ilA TQ 12A TIE BRENER BUS 1}B TO 128 TIE BREAKER CONTAINNENT AVERAGE PRESSURE CONTAINNENT SUNP A AVERAGE LEVEL SU)4'LEVEL 8 INCHES (TRAIN A)~SU%'LEVEL 8 INCHES (TRAIN 9)SSP B LEVEL 78 INCHES (TRAIN A)SUtP B LEVEL 78 INQSS (TRAIN B)SUtP B LEVEL 113 INCHES(TRAIN A)SUN'LEVEL 113 INCHES(TRAIN B)SU%'LEItcL 180 INCHES(TRAIN A)SUtP B LEVEL}80 INCHES(TRAIN B)SUt}B LEVEL 214 INCHES(TRAlt< A)SUtP B LEVEL 214 INCHES(TRAIN B)RCL/)HOT LEG TENPERATUFE RCLB HOT LEG TENPERATURE RCLA COLD LEG TE)IPERATNE 'RCLB COLD LEG TE)IPERATNE RCLA TAVG (THQT/TCOLD WIDE RNB)RCLB TAVB (THOT/TCOLD WIDE RNB)REACTOR VESSEL AVERAGE LEVEL El.l INCORE TC AVERAGE TENP S/6 A TOTAL AUX FEEDMATER FLOW S/G B TOTAL AUX FEEDMATER FLOW NTR AUXILIARY FEEDMATER PU)(P A NTR AUXILIARY FEEDMATER PUNP B AUX FM PUt(P STEAN SUPPLY VALVE A AUX FM PUt(P STEA)I SUPPLY VALVE B ATM S ALRfi RX TRIPPED ALR)(8.6397}%}6009 8.8206M)i 6009 1.01391-11 6009 1.01391-11 6009.00 6009 1071.LAL)(43.4 6009 12.3 INHB 106.9 6009 TRIPPED ALRN NOT TRIP 6009 59,0 600t 6}.5 HMRt(64.3 HMR)(1065.6009 622.GOOD TRIPPED ALRt(TRIPPED ALRt(TRIPPED ALRt(TRIPPED ALRt(NOT TRIP DEL NOT TRIP DEL N)T TRIP ALRN NOT TRIP ALRt(-.21 GOOD 2.3 HMRt(LONER GOOD LOltER 6009 LOWER 6009 LOWER 6009 LOWER 6009 LOWER 6009 LONER 6009 LOWER GOOD LOWER 6009 LOWER 6009 493.5 600D 495.5 6009 493.8 6009 494.0 6009 493.7 G009 494.7 6009 99.6 6009 495.7 600~0.6009 158.6009 OFF GOOD ON GOOD CLOSED 6009 CLOSED GOOD F-12'.U.CPS CPS ANP X PSIB X X X DEGF X X PSIG PSIG DEBF KGF DEGF DEGF DEBF DEBF/DE6F PN GPN

OCT Hs 1992 10:44 R.E.6INA SINLATOR'REND 6ROUP ASSISINENT SUSARY PASE 2 6ROUP: EVBIT1 PRXEDURE'PIP 1-5 PLANT STATUS POINT IO DESCRIPTION VALUE NNL E.U.53 FSIA 54 FSIB 55 P2160 56 P2161 57 INR041 58 BIIR042 59 BKR043 60 BIIR044 SAFETY INJECTION LOOP A AV6 FLOW SAFETY INJECTION LOOP B AV6 FLOM SERVICE MATER PNIPS A h B HEADER SERVICE MATER PNIPS C 5 0 HEADER SERVICE MATER PNIP A SEINICE WATER PNIP B SEINICE WATER PINP C SEINICE WATER PUIIP D 0.0.72.80.600D 6Pll 600D 6PII 600D PSI6 6000 PSI6 600D 600D 600D 600D ~~~OGRAM HAME:LRGTSZ.E.E.GINNA NUCLEAR PONER PLANT OCT 08,92 10:49:00 TREND GROUP ASSIGNHENT

SUMMARY

GROUP NAHE EVEHT 2 GROUP DESCRIPTION PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTIOH CURRENT VALUE QUALITY CODE ENGR UNITS 2 3 4 5 6 7 8 9 10 12 13 14 20 21 22 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 0-F0619 LRIIST WS033 M)033 MT033 WT250 IST2 R01 R02 R05 R09 R34 R35 R10A R11 R'12 R10B R'13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLll REFUELIHG IIATER STORAGE TANK LVL 33 FOOT LEVEL HIND SPEED 33 FOOT LEVEL MIND DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOM AREA 2-CONTAIHHEHT AREA 5.SPENT FUEL PIT AREA 9-LETDONN LIHE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PANEL CONTAINMENT IODINE HONITOR R10A CONTAINMEHT AIR PARTICULATE CONTAINMENT GAS HONITOR PLANT VEHT IODINE MONITOR R108 AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID IIASTE DISPOSAL MOHITOR STEAM GEHERATOR BLONDONN DRAIN AREA 29-CONTAINMENT HIGH RANGE AREA 30 CONTAINMENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VEHT CHAN 5-LDN RANGE GAS CV VENT CHAN 6-AREA GAHHA CV VENT CHAH 7-MID RANGE GAS CV VENT CHAH 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOLI RANGE GAS PLANT VENT CHAN 7 HID RANGE GAS PLANT VENT CNAH 9-HIGH RANGE GAS AIR EJECTOR CHAM 5-LOW'RANGE GAS AIR EJECTOR CHAN 7-HID RANGE GAS AIR EJECTOR CHAN 9-Hl RAHGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE B (SPING)CV HYDROGEN COHCEHTRATIOH CV BASEMEHT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEHP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEHP¹17 1485.94.5 5.2 79.61.4 63.5 2.1 9.02214-02 7.35678i00 1.3994&00 1.41701+02 9.09354-01 1.09283+00 9.58715401 5.18901+02 7.38002+02 4.30543i01 8.58327+01 4.22831+01 2.78658t03 1.42174i04 5.05861-01 5.09440.01 1.57835+03 1.89699.07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 2.09411.07 1.34492-05 1.27941-03 2.72040t00 1.01048-02 .0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GO(e GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPH)I MPH DEG.DEGF DEGF DEGF MR/H HR/H MR/H MR/H MR/H MR/H CPM CPH CPM CPH CPM CPM CPM CPH R/HR R/HR CPH UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/NR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF Time:~1~4 IVlessage: ~l~NA TATI~2 EV L ATED E ER I E ME A E F RM~f: R R N<<IG R IN GRIITT Simulated Plan Conditions: See the Attached IVlini-Scenario ~Messe e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY GGGI 1)Provide information verbally when appropriate investigations and actions are made by the Screenhouse Natural Gas Removal Fire and Safety Team.An ici ated Results: 1)As per Mini-Scenario Anticipated Results. ~GINNN NT Tl N 1992 EVALUATED EXERCISE MINI-SCENARIO ~Actitrl Screenhouse Natural Gas Removal FOR CONTROLLER USE ONLY Controller Notes: 1i if Fire and Safety Team checks gas concentration,~inf rm them that the gas concentration is not within the flammable range of the combustible gas indicator used.Antici ated Resul s: 1)Fire and Safety Team should evaluate wind direction to determine best utilization for natural ventilation and prepare hose lines for fire suppression activities. 2)Fire and Safety Team should~im ala establishing natural ventilation via breaking grade level Screen House windows on South side first and breaking glass windows in Northwest section.Master stream fog lines should be activated on the South side in the area of the broken windows to enhance air movement and promote rapid ventilation of the area.g-(3o Time:~1)~4 Message:~QX~NNA TATi N 1 2 EVAL ATED EXER I E ME A E F RM~Mf: Tggg g Tg gi Sim la ed Plan Conditions; Messac~:<<""THIS IS AN EXERCISE"">> Declare a SITE AREA EMERGENCY in accordance with EPIP 1-0,"Ginna Station Event Evaluation and Classification," EAL: Hazards Being Experienced or Projected; Entry of Uncontrolled Flammable Gases into Vital Areas.FOR CONTROLLER USE ONLY Controller Notes: 1)Deliver only if ITE AREA EMERGENCY has not been declared.D no d liver if Emer enc Cl ssifica ion discu sions are in ro ress.Antici ated Resul s: 1)Deliver contingency message if SITE AREA EMERGENCY is not declared or is not being discussed. Time: 11QQ Message:~7 GINNA STATION 1992 EVALUATED EXERCISE MESSAGE FORM Ei I<<C<<IR Simulated Plant Conditions: See the Attached Sheets Messa<ee: """THIS IS AN EXERCISE""" The Condensate Storage Tanks are at five (5)feet.FOR CONTROLLER USE ONLY Controller Notes: An ici a ed Res I s: 1)Operators should refer to ER-AFW.1 (Alternate Water Supply to AFW Pumps)per foldout page of ES-3.1, Statement 4, which states,"If CST level decreases to, less than five (5)feet, then switch to alternate AFW supply (refer to ER-AFW.1, Alternate Water Supply to AFW Pumps)" and perform applicable actions.2)Control Room should inform TSC.of low level in the CSTs.3)Cohtrol Room should be performing the applicable actions of ES-3,1 (post-SGTR Cooldown Using Backfill). 4)TSC should be evaluating Plant conditions and taking action where required, 5)TSC should inform security of the as found conditions of the"B" S/G ARV steam leak.(continued on next page) 6)TSC Dose Assessment performing offsite dose calculations as required.7)TSC should be expediting the repair of the S/G ARVs because of their use during such events as loss of condenser and Plant cooldown.8)TSC should send a repair team to check out the"A" SW Pump problem when Screenhouse is declared safe for entry.9)TSC should inform EOF of Plant status and problems.10)Security should be evaluating the drilled hole in the"B" S/G ARV pipe.11)The EOF, after it is manned, should start assessing Plant conditions and take action as required. 199P'VALUATED EXERCISE Time:~/DO MAJOR PAE%METERS ENGINEERED SAFEGUARDS A.RUNNING UNLOADED T Y OOS B.RUNNING UNLOADED B OOS TSC RUNNING UNLOADED OOS Security RUNNING UNLOADED T ENGINEERED.SAFEGUARDS OOS Reactor Shutdown YES NO N-31 CPS N-32~~CPS N-35~=-//AMPS N-36 IMPS Avg.Nuclear Power 0 RCS Pressure oÃei psIG PRZR Level 93~A RCP R NG/TOPPED B RCP UNNIN STOPPED lA S/G Level~'L 4 1B S/G Level 1A S/G Pressure~o~PSIG 1B S/G Pressure 85 PSIG Turbine/Generator NLINE FFLI 4 KV Buses NERGIZED DEENERGIZED 480V Buses ERGIZE DEENERGIZED DC Batteries Af So VOLTS B/So VOLTS Cnmt Pressure-em I PSIG Cnmt Sump A Level Z.3 FEET Cnmt Sump B Level INCHES A Loop Hot Leg 9d.OF A Loop Cold Leg OF B Loop Hot Leg l~n.2 OF B Loop Cold Leg~gZ-OF RVLIS c~7*CET 9JL'5~~OF'/G A Total Aux FW Flow o GPM S/G B Total Aux FW Flow V2 GPM DIESEL GENERATORS Hi h Head S.I.Pum s FI-924 CO GPM FI-925~GPM 1A INSERV OOS 1B.INSERV B OOS 1C.INSERV TB OOS BAST Level=~g Low Head S.I.Pum s FI-626 N GPM 1A.INSERV OOS RECIRC 1B~INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s FI-931A GPM FI-93 IB~GPM 1A.INSERV TB OOS 1B.INSERV TB OOS NaOH Tank Level=Containment Recirc Fans 1A SE STBY OOS 1B.INSE STBY OOS 1C.R STBY OOS 1D.INSER STBY OOS Post Aces ent Dampers PEN CLOSED Service Water Pum s 1A.INS STBY 0 1B.SE STBY OOS 1C.SE STBY OOS 1D.SE STBY OOS A&B Header Pressure~V~PSIG Com onent Coolin Water Pum s 1A.INS V STBY 00 1B.NSERV STBY OOS Surge Tan Level=~/Aux.Feedwater Pum s 1A.INS RV TB OOS 1B.NSER STBY OOS Turb.Driven INSERV STB OOS CST Level FEET*CET=Average of Selected Core Standb Aux.Fe ater Pum s 1C.INSERV T OOS 1D.INSERV TB OOS Exit Thermocouples OCT Gi 1992 II:(O R.E.BIWA SltaLATOR TREND 6ROUP AKIGtmENT SUt(NARY PAGE 1 6ROUP: EVENT1 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID 1 ATNS 2 RXT 3 N31 4 N32 5 N35 6 N36 7 NP 8 PRK 9 LPIR 10 FRCLA 11 FRCLB 12 R)(T16 13 RXT17 14 TSUBTC 15 LSGA 16 LSGB!7 PSGA 18 PSGB 19 GENBKRI 20 GENBKR2 21 BUS11A 22 BUS11B 23 BUS12A 24 BUS12B 25 BIIA12A 26 B110129 27 PCV 28 LS(NPA 29 L0942E 30 L0943E 31 L09429 32 L0943D 33 L0942C 34 L0943C 35 L09420 36 L0943B 37 L0942A 38 L0943A 39 T0409A 40 T0410A 41 T0450 42 T0451 43 TAVBAWID 44 TAVBBWID 45 LRV 46 TCCORE 47 FAUXFWA 48 FAUXFWB 49 BKFQBI 50 BKR082 51 V3505 52 V3504 DESCRIPTION ANTICIPATED TRANSIENT N/0 SCRA)(REACTOR TRIP BREAKER STATUS SMICE RANGE DETECTOR N-31 So(SCE RA%E DETECTOR N-32 INTERMEDIATE RANGE DETECTOR N"35 INIERt(EDNTE RANGE DETECTOR,N-36 AVERAGE NLGSAR POWER REACTOR COOLANT SYSTEt(AVG PRESS PRESSURIIER AVERAGE LEVEL REACTOR COOLANT LOOP A AVG FLOW REACTOR COOLANT LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUKOOLED tmRBIN STN GEN.A NARRON RAhBE AVG LEVEL STtl GEN B NARROW RANGE AVG LEVEL STN GEN A AVERAGE PRESSURE STtt GEtt B AVERAGE PRESSURE GBGQTOR ON LINE BREAKER 161372 GENERATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SUPPLY BREAKER NOT TERHlt(ATED ON PPCS (7/19/91)t<OT TERHINATED ON PPCS (7/19/91)BUS 11A TO 12A T[E BREWER BUS 11B TO 12B TIE BREAKER CONTAIOENT AVERAGE PRESURE CONTAIN)(ENT SUt(P A AVERAGE LEVEL SUtP B LEVEL 8 INCHES (TRAIN A)SUtP B LEVEL 8 INCHES (TRAIN 0)SUtP B LEVEL 78 INCHES (TRAIN A)SUtP B LEVEL 78 INCHES (TRAIN B)SUtP B LEAL 113 INCHES(TRAIN A)SUtP B LEVEL 113 INCHES(TRAIN B)SUIP B LEVEL 180 INCHES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SUtP B LEVEL 214 It(CHES(TRAIN A)SUNUP B LEVEL 214 INCHES(TRAIN B)BC'OT LEG TEt(PERATLK RRB HOT LEG TEIIPERATUlt= RCLA COLD LEG TEtFERATNE RCLB COLD LEB TEtPERATNE RCLA TAVG (TKIT/TCOLD WIDE RNB)RCLB TAVG (TtK)T/TCOLD WIDE RNB)REACTOR VESSEL AVERAGE LEVEL El.1 INCORE TC AVERAGE TEt(P S/G A TOTAL AUX FEEDMATER FLOM S/G B TOTAl.AUX FEEDMATER FLOW t(TR AUXILIARY FEEDMATER PUt(P A tITR AU)(ILIARY FEEDNATER PIWP 0 AU)(FW PUI(P STEAN SIFPLY VALVE A AUX FM PULE'TEA)I SL4'PLY VALVE B ATWS ALRI(RX TRIPPED ALRII 8.46249+01 600D 8.28893+01 600D 1.01391-11 6000 1.01391-11 GOOD.00 6000 1056.LALII 43.1 600D 12.3 INHH 107.5 GOOD TRIPPED ALRI(NOT TRIP Goon 63.1 Gooe 59.6 HNRN 50.5 6000 1053.6009 585.LNRt(TRIPPED ALRI(TRIPPED ALRI(TRIPPED ALR(NOT TRIP DEL NOT TRIP DEL NOT TRIP ALRI(NOT TRIP ALRI(-.21 6000 2.3 HWRt(LOWER GOOD LONER Boon LOWER 6000 LOWER 6000 LOWER 6000 LONER 6000 LOWER 6000 LOWER 6000 LOWER 6000 LOWER 6000 490.4 600D 490.2 6009 488.4 6000 488.2 6000 489.4 6000 489.2 GOOD 99.7 6000 489.9 Boot 0.6009 72.6000 OFF GOOD ON 6600 cLOBED.Boon CLOSED 6000 p E.U, CPS CPS NP At(P X PSIG X X KGF X'X PSIG PSIG DE6F KGF DEGF DEGF KGF DEGF X DEBF GPtl GPtl OCT Gi 1992 11:00 R.E.GINA SINKATOR TREND 6ROUP ASSIGNEttT RNtNRY PAGE 2 GROUP: EVENT1 PRXEDURE'PIP 1-5 PLAttT STATUS POINT ID'DESCRIPTION VALUE QUAL E.U.53 FSIA 54 F GIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 SAFETY INJECTION'LOOP A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SERVICE WATER PUtrPS A h B HEADER SERVICE MATER PNPS C 5 D HEADER SERVICE WATER PUtIP A SERVICE WATER PNP B SERVICE WATER PNP C SERVICE WATER PINP D 0.600D PN 0.GOOD 6PN 72.600D PSI6 80.GOOD PSI6 GOOD GOOD GOOD GOOD ~~~OGRAM NAME:LRGTSZ.E R.E.GINNA NUCLEAR POUER PLANT OCT 08,92 11:01:00 TREHD GROUP ASSIGNHENT

SUMMARY

GROUP NAME EVENT 2 GROUP DESCRIPTIOH PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43-~F0619 LR'IIST WS033 IJD 033 IIT 033 MT250 NDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R'13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03.TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLII REFUELIMG IIATER STORAGE TANK LVL 33 FOOT LEVEL IIIND SPEED 33 FOOT LEVEL MIND DIRECTION 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOH AREA 2-CONTAINMEHT AREA 5-SPENT FUEL PIT AREA 9-LETDONM LINE MONITOR AREA 34 AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PANEL CONTAINMEHT IODINE HOHITOR R10A CONTAINMENT AIR PARTICULATE COHTAIHHEHT GAS MONITOR PLANT VEHT IOOIHE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID IIASTE DISPOSAL HONITOR STEAM GEHERATOR BLOMDONN DRAIH AREA 29-CONTAINHENT HIGH RANGE AREA 30-CONTAINMENT HIGH RANGE COHDEHSER AIR EJECTOR EXHAUST CV VENT CHAM 5-LOII RANGE GAS CV VENT CHAH 6-AREA GAMMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOM RAMGE GAS PLANT VEHT CHAN 7.MID RANGE GAS PLANT VEHT CHAN 9 HIGH RANGE GAS AIR EJECTOR CHAN 5 LOU RANGE GAS AIR EJECTOR CHAN 7-HID RANGE GAS AIR EJECTOR CHAN 9 Hl RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAH LINE B (SPIKG)CV HYDROGEH CONCENTRATION CV BASEMENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEHP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 4.8 79.62.4 64.9 2.5 9.02214-02 7.35678+00 1.3994&00 1.38701+02 9.09354-01 1.09283+00 9.58719101 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.38174+04 5.05861-01 5.09440.0'I 1.57835+03 1.89699-07 2.53990-02 3.57435-05 1.41261.03 4'0312.07 6.865C3-05 3.72621-03 2.09411-07 1.34492-05 1.27941-03 2.680CO+00 1.01048-02 .0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD 6000 GOOD 6000 6000 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD 6000 HALH GOOD GOOD GOOD 6000 GOOD GOOD GOOD GOOD GOOD GOOD GOOD 6000 GOOD BALM GOOD GOOD GOOD GOOD GOOD GOOD 6(XN GOOD GPH X MPH DEG.DEGF DEGF DEGF HR/H MR/H MR/H MR/H MR/H MR/H CPH CPM CPM CPM CPH CPM CPM CPM R/NR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF Time: 11QQ Message:~Q INNA TAT N 1 2 EVAL ATED EXER E IVIE SA E F RIVI~WP: PARWP pTfpP Pf Rpf T Simula ed Pl n Conditions: See the Attached Mini-Scenario ~Me s~e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate investigations and actions are made by the 1A SW Pump Trip Problem Repair Team.Antici ated Results: 1)As per Mini-Scenario Anticipated results. NINNII NTIITINN 2 EVALUATED EXER I E MINI-S ENARI TITLE'A rvi W rP m Br k rTri Expected scenario start time: 1015 INITIAL CONDITIONS: Pump running METHOD OF INITIATION: Breaker trips, Operations calls for Electricians to investigate. INDICATIONS'ONTROL ROOM:~Aiarm Window: "J-9" Safeguard Breaker Trip~White idiaagreementi light: SWP1A BUS 18/POS 29C:~Amptector: No indication of Amptector~Alarm switch contacts not activated SWP1A MOTOR:~No indication of trouble LOCAL CTRL STA.:~No indication of trouble o MCB Control Switch to"Trip" clears white light and Alarm.o Attempts to close breaker from Control Room do not succeed;indications as above.o When Local Control Panel Transfer Switch is turned to"Local," breaker can be closed electrically. Transfer to"Remote" (MCB)Trips Breaker with above indications again.EXPECTED SEQUENCE OF ACTIONS: o Investigate Screenhouse for visible signs near breaker or motor.~No indications noticed o Obtain holds, clearances, and test equipment. o Simulate measuring resistance phase to phase 5 megger motor from Bus 18/Pos 29C readings: Megger,readings: )100 MQ to ground Phase to phase resistance: good (continue on next page) o Take Local/Remote Switch to Local and close breaker.o Test and confirm shorted Red Light.FINAL CONDITIONS: Service Water Pump operated from Local Control Panel.Locate shorted Red Light in Main Control Board, and replace, Return Breaker to service. Time: 11QQ Message:~9 INN A TATI N 2 EVAL ATED EXER E MES AGE F RM~Mf: S lfl lp l fd'S'Sfdldddlp Plltddl T Simula ed Plan Condi ions: See the Attached Mini-Scenario ~Messa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate investigations are made by the Security Investigation Team investigating the"B" S/G ARV Pipe Drilled Hole.Antici ated Results: 1)As per Mini-Scenario Anticipated Results. INNA STATI N 1 2 EVALUATED EXERCISE NIINI-SCENARIO ~A1~IVI g: Security Investigation of the"B" S/G ARV Pipe Drilled Hole F R CONTROLLER USE ONLY N 1)Security should follow their normal procedures for apparent tampering with equipment. 2)See attached sketch on Steam Leak.An ici a ed Resul s: 1)Security should check the door entries to Steam Header area for a selected time block.2)Based upon the entries into the area, a profile should be performed on selected individuals. 3)Based upon results of the above profiles, security may~im~la a interrogation of selected individuals. 4)Inform TSC and EOF of any findings from above. GINNA STATION: ROCHKSTKI GAS AND KLECTltC COIttOltATION DATE: mrna s PAGE OF sOB: Sks'rcpt o'>g AtV$78~~LEAL MADE BY: Time:~111 Message:~4~INNA TATI~1 2 EVALUATED EXER I E ME A EF RM I: R I<<R IR im la e Pl n ndi I n: See the Attached Sheets~Messe e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY 1)Dl Truck starts pumping to outside storage tank.Antici ated Resul s: 1)Operators performing the Applicable Actions of ES-3.1 (Post-SGTR Cooldown Using Backfill). 2)Operators performing the Applicable Actions of ER-AFW.1 (Alternate Water Supply to the AFW Pumps). 199P EVALUATED EXERCISE Tlate:///5 MAZOR PAEKMETERS ENGINEERED SAFEGUARDS A.RUNNING UNLOADED OOS B.RUNNING UNLOADED STB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED STB ENGINEERED SAFEGUARDS OOS Reactor Shutdown E NO N-3 1 3 CPS N-32~~CPS N-35 t,~I I AMPS N-36 g,@~AMPS Avg.Nuclear Power RCS Pressure 025 PSIG PRZR Level A RCP R TOPPE B RCP UNN N STOPPED 1A S/G Level 1B S/G Level.I lA S/G Pressure PSIG 1B S/G Pressure PSIG Turbine/Generator ONLINE FL NE 4 KV Buses NERGIZE DEENERGIZED 480V Buses NERGIZE DEENERGIZED DC Batteries A~OVOLTS B/So VOLTS Cnmt Pressure-~2.PSIG Cnmt Sump A Level FEET Cnmt Sump B Level INCHES A Loop'Hot Leg 7z.OF A Loop Cold Leg Qadi~OF B Loop Hot Leg 7~OF B Loop Cold Leg OF RVLIS*CET e OF S/G A Total Aux FW Flow O GPM S/G B Total Aux FH Flow~&GPM DIESEL GENERATORS Hi h Head S.I.Pum s FI-924 O GPM FI-925&GPM 1A.INSERV T OOS 1B.INSERV TB OOS 1C.INSERV TB OOS BAST Level=0 Low Head S.I.Pum s FI-626 GPM 1A INSERV B OOS RECIRC 1B.INSERV B OOS RECIRC RWST Level=3.Containment S ra Pum s FI-931A 0 GPM Fi-931B~GPM 1A.INSERV B OOS 1B.INSERV TB OOS NaOH Tank Level=Containment Recirc Fans 1A.NSE STBY OOS 1B.NSER STBY OOS 1C.NSE STBY OOS 1D.NSE STBY OOS Post Accident Dampers PE CLOSED Service Water Pum s 1A.INSERV STBY 0 1B.NSE STBY OOS 1C.ER STBY OOS 1D.SERV STBY OOS A&B Header Pressure~0 PSXG Com onent Coolin Water Pum s 1A.INSER STBY 1B.NSER STBY OOS Surge Tank Level~7 Aux.Feedwater Pum s 1A.INSERV TB OOS 1B.NS R STBY OOS Turb.Driven INSERV B OOS a CST Level FEET*CET=Average of Selected Core Standb Aux.Feedwater Pum s 1C.INSERV TB OOS 1D.INSERV TB OOS Exit Thermocouples F-~W 8s 1992 11: 15 R.E.GINA SIMULATOR TRB(D GROUP ASSIGHMEHT

SUMMARY

PA6E 1 GROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E.U.1 2 3 5 6 7 8 9 10 11 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 AT%RXT N31 N32 N35 H36 t(P PRCS LPIR FRCLA FRCLB RXT16 RXTij TSUBTC LSGA LSGB PSGA PSGB GEHBKR!GENBKR2 BUS11A BUS11B BUS12A BUS12B B11A12A BllB12B PCV LSWPA L0942E L0943E L0942D L09439 L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAKBWID LRV TCCORE FAUXFMA FAUXFMB BKR081 BKR082 V3505<<V3504 ANTICIPATED TRANSIENT M/0 SCRAM REACTOR TRIP BRENER STATUS SMKE RANGE DETECTOR H-31 SONCE RA%E DETECTOR N-32 INIEfIEDIATE RANGE DETECTOR N-35 INTERMEDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEM AVG PRESS PRESSURIIER AVERAGE LEVB.REACTOR COOLANT LOOP A AVG FLOW REACTOR COOLANT 1.00P B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BRENER CAUSE RX TRIP INCORE TC SUBCOOLED MARGIN STM GEH A NARROW RANGE AVG LEVEL STM GB(B NARROW RANGE AVG LEVEL STM GEH A AVERAGE PRESSURE STM 6Ett B AVERAGE PRESSURE GEtGMTOR.ON LINE BREAKER 1G1372 GsJRRATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BRENER BUS llB SUPPLY BRENER HOT TERMINATED OH PPCS (7/19/91)NOT TERMINATED OH PPCS (7/19/91)BUS 11A TG 12A TIE BRENER BUS 11B TG 12B TIE BRENER CONTAINMEHT AVERAGE PRESSURE CGNTAIHMEt(T SUMP A AVERAGE LEVEL SSP B LEVEL 8 INCHES (TRAIN A)SUtP B LEVEL 8 INCHES (TRAIN 9)SUtF'LEVEL 78 ItKHES (TRAIN A)SUtP B LEVEL 78 IHC)'.cS (TRAIN B)SUtP B LEVFL 113 INCHES(TRAIN A)SUN'LEVEL 113 INCHES(TRAIN B)SUtP B LE(tcL 180 INCHES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SU%'LEVcL 214 INCHES(TRAIN A)SUP B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TEMPERATURE RCLB HOT LEG TEMPERATURE RCLA COLD LEG TE)(PERATIEE RCLB COLD LEG TE)(PERATNE RCLA TAVG (THDT/TCOLD WIDE RNG)RCLB TAVG (T)OT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 INCORE TC AVERAGE TEMP S/G A:OTAL AUX FEEI'4(ATcD FLOW S/6 B TOTAL AUX FEECSNW FLOW MTR AUXILIARY FEEINATER PUlP A'TR AUXILIARY FEEOMATER PUt(P B AUX FM PUtt STEAtl SUPPLY VALVE A AUX FM PU!F STEAN SUPPLY VALVE B ATMS ALRt(RX TRIPPED ALII 8.31763K)I 6009 8.66958~01 6009 1.01391-11 6009 1.01391-11 6009.00 6009 1025.LALt(41.6 600D 12.6 INHB 109,4 6009 TRIPPED ALfi NOT TRIP 6009 77.9 600~53.5 6009 36.1 6009 1024.6009 469.LALM TRIPPED ALRt(TRIPPED ALII TRIPPED ALRt(TRIPPED ALII NOT TRIP DEL NOT TRIP DEL NOT TRIP ALRt(NOT TRIP ALRt(-.21 GOOD 2.4 HWRN LO)(ER 6009 LONER G009 LONER 6009 LONER 6009 LONER 6009 LO))ER 6009 LO)tER 6009 LO)tER GOOD LO)tER 6009 LO))ER 6009 472.7 6009 471.8 GOOD 469.6 6009 469.4 6009 471.2 GOOD 470.6 6009 99.9 6009 471.5 600~0.6009 196.6009 OFF 6009 ON 6109 CLOSED GOOD CLOSED 6009 CPS CPS AMP AMP'/PSIG X//KGF X PSIG PSI6 PSIG DE6F DEGF OE6F DEGF DEGF DE6F X DE6F PN GPM OCT 8>1992 11: 15 R.E.GINA SINULATOR TREND GROUP ASSIGNNENT RNMY PA6E 2POINT ID 53 FSIA 54 F GIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 DESCRIPTION SAFETY INJECTION:LOOP A AV6 FLON SAFETY INJECTION LOOP B AVG FLON SERVICE NATER PUIIPS A h B HEADER SERVICE HATER PNPS C h D HEADER SERVICE NTER PUIIP A SERVICE NATER PlIP B SERVICE NTER PIIP C SERVICE HATER PUIIP D VALUE QUAL E.U.0.GOOD 0.Goon 72.600 D 80.Goon Goon ON 600D ON 600 D ON GOOD GPt1 GPtl PSI6 PSIG GROUP: EVENT1 PRXEDURE: EPIP 1-5 PLANT STATUS ~~ROGRAM NAME:LRGTSZ.E R.E.GIHNA NUCLEAR POWER PLANT OCT 08,92 11:15:00 TREND GROUP ASSIGNHEHT

SUMMARY

GROUP NAME EVENT 2 GROUP DESCRIPT ION PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 F0619 LRWST WS033 WD033 WT033 WT250 WOT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15AS R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COMPOHENT COOLING LOOP TOTAL FLW REFUELING WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TEKPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-COHTROL ROOK AREA 2-CONTAINMENT AREA 5-SPENT FUEL PIT AREA 9 LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUHP AREA 35-PASS SAMPLE PAHEL CONTAINMENT IOOIHE MONITOR R10A CONTAINMENT AIR PARTICULATE COHTAINKEHT GAS MONITOR PLANT VENT IOOIHE MOHITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS KONITOR LIQUID WASTE DISPOSAL MONITOR STEAM GENERATOR SLOWDOWN DRAIN AREA 29-CONTAINMEHT HIGH RANGE AREA 30-CONTAIHMEHT NIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOW RAHGE GAS PLANT VENT CHAN 7-MID RAHGE GAS PLANT VEHT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAN 5'OW RANGE GAS AIR EJECTOR CHAN 7-MID RAHGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE 8 (SPING)CV HYDROGEN CONCEHTRATIOH CV BASEMENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 5.6 80.62.5 64.9 2.4 9.02214-02 7.35678+00 1.3994&00 1.36701+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543t01 8.58327+01 4.22831+01 2.78658+03 1.32174+04 5.05861.01 5.09440-01 1.57835+03 1.89699-07 2.53990.02 3.57435-05 1.41261-03 4.40312.07 6.86543-05 3.72621-03 2.09411-07 1.34492-05 1.27941-03 2.50040+00 1.01048-02.0 95.1 106.0 106.6 106.7 106.2 117.5 Gmm GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD NALK GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM X KPH DEG.DEGF DEGF DEGF KR/H MR/H MR/H MR/H KR/H MR/H CPH CPK CPK CPM CPM CPK CPK CPM R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC KR/HR MR/HR DEGF DEGF DEGF DEGF DEGF DEGF Time: 1120 Message: 41 INNA STATION'I9 2 EVALUATED EXERCI E MESSAGE FORM~MI: T P I IR pp<<C<<IIPCR p I T Simula ed Plan Condi ions:~Messe e: """THIS IS AN EXERCISE""" The"A" S/G ARV mercoid is repaired and ready for return for service.FOR CONTROLLER USE ONLY Controller Notes: 1)The IRC Repair Team working on the"A" S/G ARV Mercoid should report this message to the TSC.TSC C n roller and ISC Re air Team Con roller o coordinate this re or at 1120 hours.Antici ated Results;1)Operators performing Applicable Actions of ES-3.1 (Post SGTR Cooldown Using Backfill). 2)Operators performing Applicable Actions of ER-AFW.1, 3)Operators should return the"A" S/G ARV to service if requested by the TSC.4)TSC evaluating Plant conditions and taking action where required.5)TSC may request Control Room to return the"A" S/G ARV to service.(continued on next page) 6)Security should be evaluating the Drilled Hole in the"B" S/G ARV Pipe.7)EOF should be assessing Plant conditions and taking action as required.8)EOF Dose Assessment should be performing offsite Dose Assessment as required, in parallel with the TSC Dose Assessment. 9)The EOF should be assuming command and control at approximately this time.10)Repair teams performing actions as required to return equipment to service as soon as possible.11)The Mobile Dl Unit should be connected and in operation and the inside condensate storage tanks should be being filled. Time:~12 Message: 42 INNA STATION 1 2E AL TEDEXE I E~MEE A E F RM~MI: A III M RF<<<<R'A'IR ARE Simula ed Plant Condi ions: See the Attached Mini-Scenario ~Me ee e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~CII E 1)Provide information verbally when appropriate actions are simulated by the Auxiliary Operator sent to return the"A" S/G ARV to service.An ici ated Results: 1)As per Mini-Scenario Anticipated Results. ~INN II TN N 1 2 EVALUATED EXER ISE M~ININ NNNIII~A~ivi y: Return to service of the"A" S/G ARV FOR CONTROLLER USE ONLY 1)Ensure Auxiliary Operator simulates opening Manual Valve 3507 ("A" S/G ARV Isolation Valve).2)Ensure Auxiliary Operator simulates checking Manual Valve 3507A ("A" S/G ARV Isolation Valve, Bypass Valve)closed.3)Controller must notify the Simulator Control Booth Operator at Ext.6641 to coordinate actions on this Mini-Scenario. N 1)Auxiliary Operator should simulate returning to Service (i.e.unisolating) the"A" S/G ARV.2)Auxiliary Operator, after simulating return to service of the"A" S/G ARV, should inform Control Room/TSC.3)Control Room may place"A" S/G ARV to Automatic Control. Time: 11'essage: ~4 INN A TATI N 1 2EV L ATEDEXE I E MESSAGE FORM I: RI I<<R IR Sim la e Plan C ndi ion: See the Attached Sheets~Massa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller N tes: An ici ated Results: 1)Operators performing the Applicable Actions of ES-3.1 (Post-SGTR Cooldown Using Backfill). 199EVALUATED EXERCISE Time://3O MOOR PARAMETERS "'NGINEERED SAFEGUARDS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED STBY OOS TSC RUNNING UNLOADED OOS Security RUNNING UNLOADED TB ENGINEERED SAFEGUARDS OOS Aux.Feedwate m s 1A.INSERV B OOS 1B.NSER STBY OOS Turb.Driven INSERV TB OOS CST Level FEET" Reactor Shutdown ES NO N-31~~CPS N-32 CPS N-35&I AMPS N-36 g l/AMPS Avg.Nuclear Power RCS Pressure~b Z PSIG PRZR Level&7 A RCP RUNNING TOPPE B RCP RUNNIN STOPPED 1A S/G Level.C a 1B S/G Level MV 1A S/G Pressure oO PSIG 1B S/G Pressure 0 PSIG Turbine/Generator ONLINE FFLIN 4 KV Buses NERGZZ DEENERGIZED 480V Buses ERGZZE DEENERGIZED DC Batteries A~So VOLTS B/3OVOLTS Cnmt Pressure PSIG Cnmt Sump A Level~a<+FEET Cnmt Sump B Level INCHES A Loop Hot Leg S7 OF A Loop Cold Leg.0 OF B Loop Hot Leg Q~O OF B Loop Cold Leg%XKZ oF RVLIS*CET~.b OF S/G A Total Aux FW Flow~GPM S/G B Total Aux FW Flow Z.o2 GPM DIESEL GENERATORS Hi h Head S.I.Pum s FI-924 O GPM F1-925~GPM 1A.INSERV B OOS 1B.INSERV B OOS 1C.INSERV OOS BAST Level=/O Low Head S.I.Pum s FI-626 N G M 1A.INSERV OOS RECIRC 1B.INSERV T OOS RECIRC RWST Level=S.Containment S ra Pum s FI-931A&GPM FI-931B lD GP 1A.INSERV 1B.INSERV T NaOH Tank Level=OOS OOS Containment Recirc Fans 1A.NSERV STBY OOS 1B.SE STBY OOS 1C.SER STBY OOS 1D.NSER STBY OOS Post Acc dent Dampers PE CLOSED Service Water-Pum s 1A.INSERV STBY 0 1B.NSE STBY OOS 1C.NSE STBY OOS 1D.NSER STBY OOS A&B Header Pressure~PSZG Com onent Coolin Water Pum s 1A.I ERV STBY 1B.NSER STBY OOS Surge Tan vel Standb Aux.Feedwater Pum s 1C.INSERV TB OOS 1D.INSERV STB OOS*CET=Average of Selected Core Exit Thermocouples 8i 1992 11:30 R.E.6INA SINLATOR TREND GROUP ASSIGN)(ENT SUt(t(ARY PA6E 1 6ROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE E.U.1 2 3 4 5 b 7 8 9 10 11 12 13 14 15 ib 17 18 19 20 21 22 23 24 25 2b 27')8 29 30 31 32 33 34 35 3b 37 38 39 40 41 42 43 45 4b 47 48 49 50 51 52 ATI6 RXT N31 N32 N35 N3b i"(P PRCS LPIR FRCLA FRCLB RXT1b RXT17 TSUBTC LSGA LS6B PSGA PSGB GENBKR1 GENBKR2 BUS11A BUS118 BUS12A BUS12B Bi IA12A B11B12B PCV LSNPA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAVGBMID LRV TCCORE FAUXFMA FAUXFWB BKR081 BKR082 V3505 V3504 ANTICIPATED TRAt(6IENT W/0 SCRAt(REACTOR TRIP BREAKER STATUS SSSCE RANGE DETECTOR N-31 SONCE RANGE DETECTOR N-32 INTERt(EDIATE RANGE DETECTOR N-35 INTERt(EDIATE RANGE DETECTOR N-3b AVERAGE NUCLEAR POWER REKTOR COOLANT SYSTEtl AVG PRESS PRESSURIlER AVERAGE LEVEL REACTOR CCEA(T LOOP A AVG FLOW REACTOR COOLANT LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUP3NLED t(ARGIN STN GEN A NARROW RANGE AVG LEVEL STN GEN B t(ARROW RAKE AVG LEVEL STt(GEtt A AVERAGE PRESSURE STN GEN B AVERAGE PRESRJRE GENERATOR ON LINE%FAKER 161372 GENERATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS liB SUPPLY BREAKER t(QT TERNlhATED OM PPCS (7/19/91)NOT TERtlit(ATED OM PPCS (7/19/91)BUS 11A TO 12A TIE BREAKER BUS iiB TO 12B TIE BREAKER COl(TAINl"iENT AVERAGE PRESSURE CQNTAItit(Et(T SUMP A AVERAGE LEVEL SM'LEVEL 8 INCHES (TRAIN A)SM B LEVEL 8 INCHES (TRAIN B)SUt(P B LEVEL 78 INCHES (TRAIN A)SU@'LEVEL 78 INCHES (TRAIN B)SUN'LEVEL 113 INCHES(TRAIN A)SM~B LEVEL 113 INCH.=S(TRAIN B)SU%B LEVEL 180 INCHES(TRAIN A)SUtP B LEVEL 180 INCHES(TRAIN B)SU%'LEVEL 214 INCHES(TRAIN A)S"tP B LEVEL 214 It/CHES(TRAIN B)RCLA HOT LEG TEt(PERATUP= RCLB HOT LEG TEt(PERATUK RCLA CP D LEG TE)PERATURE RCLB COLD LEG TEt(PERATNE RCLA TAVG (THQT/TCOLD WIDE RNG)RCLB TAVG (TNT/TCOLD WIDE RNG)REACTOR VESSEL A'FRAGE LEVEL E1.1 INCOFE TC AVERAGE TEt(P S/G A TOTAL AUX FEEDWATER FLO((S/G B TOTAL AUX FEEDMATER FLOW t(TR AUXILIARY FEEDMATER PUt(P A MTR AUXILIARY FEEDMATER PUt(P B AUX FM PUP STEAN SUPPLY VALVE A AUX FM PU5'TEAN SUPPLY VALVE B ATMS RX TRIPPED 8.75988+01 7.92501+01 1.01391-11 1.01391-11 .00 1002.41.7 12.8 110.8 TRIPPED NOT TRIP 90.1 48.b 34.9 1000.401.TRIPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NOT TRIP NOT TRIP-.24 LONER LOMER LOWER LONER lONER ,LONER LOWER LOWER LONER LONER 457.8 457.0 455i0 454.8 45b.4 455.9 99.9 45b.b 0.202.OFF ON CLOSED CLOSED ALRt(ALRt(6(mD GOOD GOOD GOOD GOOD GOOD GOOD INHB GOOD ALRt(GOOD 600~600D GOOD GOOD LALN ALRt(ALRt(ALRtl ALRt(DEL DEL ALRt(ALR)(GOOD SlRt(GOOD 600D GQOD GOOD 6009 GOOD GOOD 600D 600D 600D GOOD GOOD GOOD GOOD GOOD GOOD GOOD 600~GOOD GOOD 600D GOOD GOOD GOOD CPS CPS At(P At(P y.PSIG//DEGF/7.PSIG PSIG PS16 FM DEGF DEGF DE6F DE6F DEGF DEGF 7.D-"GF 6PN GPt( OCT 8i 1992 11:30 R.E.GINA SINLATOR PAGE 2 TREND GROUP ASSIGNMENT 9NMY 6ROUP: EVBP1 PROCEDURES EPIP 1-5 PLNIT STATUS POINT ID DESCRIPTION VALUE QUAL E.U.53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 NR044 SAFETY INJECTION LOOP A AV6 FLOW SAFETY INJECTION LOOP B AV6 FLOM SERVICE MATER PlmPS A h B HEADER SERVICE WATER PNPS C 5 9 HEADER SERVICE MATER PINP A SERVICE MATER PUNP B SERVICE WATER PUNP C SERVICE WATER PUe D 0.Gxa m 0.GOOD GPN 72.GOOD PSIG 80.600D PSIG GOOD GOOD 6OOD GOOD ~~~ROGRAH KAME:LRGTSZ.E R.E.GIKHA NUCLEAR POWER PLANT OCT 08,92 11:31:00 TREND GROUP ASSIGNMENT

SUMMARY

GROUP NAME EVENT 2 GROUP DESCRIPTION PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS l.2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43-F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 RDS R09 R34 R35 R10A R11 R12 R108 R13 R14~R18 R19 R29 R30 R15 R12AS R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15AS R15A7 R15A9 R31 R32 CVH TCV03 TCV07 Tcvoe TCV09 TCV10 TCV17 COMPOHENT COOLING LOOP TOTAL FLW REFUELING WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WIHD DIRECTION 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL TEHPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOM AREA 2-COHTAINHEHT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LIHE MOHITOR AREA 34 AUX BLDG CV SPRAY PUHP AREA 35-PASS SAHPLE PANEL CONTAINMENT IODINE MONITOR R10A CONTAINHEHT AIR PARTICULATE CONTAINMEHT GAS MONITOR PLANT VENT IODINE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MOHITOR LIQUID WASTE DISPOSAL MONITOR STEAM GEKERATOR BLOWDOWN DRAIN AREA 29-CONTAINMENT HIGH RANGE AREA 30.CONTAINMEHT HIGH RANGE COKDEHSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VEN'I CHAN 7-MID RAHGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOW RANGE GAS PLAHT VENT CHAN 7-MID RANGE GAS PLANT VENT CKAN 9-HIGH RAHGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAN 9 Hl RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE 8 (SPING)CV HYDROGEN CONCEHTRATIOH CV BASEHENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATIKG LVL 6 FT TEMP¹17 1485.94.5 5.6 79.62.7 64.8 2.1 9.02214-02 7.35678+00 1.39946+00 1.34701+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.28174+04 5.05861-01 5.09440-01 1.57835+03 1.89699.07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 2'9411-07 1.34492-05 1.27941-03 2.50040+00 1.01048.02 .0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOGO QXX)GOOD 0000 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD BALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPH X MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPH CPH CPH CPM CPH CPM CPM CPM R/HR R/HR CPH UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/NR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF Time:~114 Message: '44 I NNA TATI N 1 92 EVALUATED EXER ISE ME SA EF RM~hl f:Thl fhppp lPlpfl PWldhplT imulae Pl n n ii n:~lVI s~sa e: """THIS IS AN EXERCISE"""'he"B" S/G ARV steam leak is repaired and ready for return to service.FOR CONTROLLER USE ONLY C~fl 1)The Pipefitter 5.Welder Repair Team working on the"B" S/G ARV steam leak should report this message to the TSC.T C on r II r n Pi fi r 5 W I r Re irT m Conroll r r in hi r a 114 h r.'An ici a ed Re I s: 1)TSC should request Control Room to return the"B" S/G ARV to service.2)Operators should return the".B" S/G ARV to service, Time:~114 Message:~4 INNA TATIO 2EV L ATD XE I E MESSAGE F RM t: A iti yDp<<<<<<1"B" SIGARV t mul e Pl n n i i n: See the Attached Mini-Scenario ~Massa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Provide information verbally when appropriate actions are simulated by the Auxiliary Operator sent to return the"B" S/G ARV to service.2)Controller must notify the Simulator Control Booth Operator at Ext 6641 to coordinate actions on this Mini-Scenario. Anici ae Re Is: 1)As per Mini-Scenario Anticipated Results. INNA STATION 1 92 EVALUATED EXERCISE MINI-E MARI~A1~Ivi y: Return to service of the"B" S/G ARV F R CONTROLLER USE ONLY 1)Ensure Auxiliary Operator simulates opening Manual Valve 3506 ("B" S/G ARV Isolation Valve).2)Ensure Auxiliary Operator simulates checking Manual Valve 3506A ("B" S/G ARV Isolation Valve, Bypass Valve)closed.Antici a ed Resul s: 1)Auxiliary Operator should simulate returning to service (i.e., unisolating) the"B" S/G ARV.2)Auxiliary Operator, after simulating return to service of the"B" S/G ARV, should inform Control Room/TSC.3)Control Room should place"B" S/G ARV to automatic control~ Time:~114 Message:~4 INN A TATI N 1 2 EVAL ATED EXER E~ME A E FORM~MI: M I<<C<<IR Simula ed Plan Condi ion: See the Attached Sheets~Massa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Antici ated Res its: 1)Operators performing the Applicable Actions of ES-3.1 (Post-SGTR Cooldown Using Backfill). 2)TSC evaluating Plant conditions and taking action as required.3)TSC should request Control Room to return the"B" S/G ARV to service.4)EOF evaluating Plant conditions and taking action as required. 199P EVALUATED EXERCISE TXme://'/5 MAZOR PAMMETERS ENGINEERED SAFEGUARDS Hi h Head S.Z.Pum s FI-924 C7 GPM FI-925&GPM INSERV TB OOS 1B.ZNSERV B OOS 1C~INSERV TB OOS BAST Level=/O Low Head S.I.Pum s FZ-626 O GPM 1A INSERV TB OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=Containment S ra Pum s FZ-931A&GPM FI-931B&GPM 1A.INSERV T OOS 1B.INSERV TB OOS NaOH Tank Level=Containment ecirc Fans lA.S STBY OOS 1B.NS STBY OOS 1C.SE STBY OOS 1D.NSE STBY OOS Post Accident Dampers OPE CLOSED Service Water Pum s 1A.INSE STBY OOS 1B.NSERV STBY OOS 1C.SER STBY OOS 1D.NSER STBY OOS A&B Header Pressure 7&&70 PSZG DIESEL GENERATORS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TBY OOS Security RUNNING UNLOADED B Com onent Coolin Water Pum s 1A.I V STBY 1B.NSE V STBY OOS Surge Tank Level=~/Standb Aux.Fe water Pum s 1C.INSERV T OOS 1D.INSERV TB OOS OOS ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.INSERV OOS 1B.INSERV TB OOS Turb.Driven INSERV B OOS CST Level~g FEET*CET=Average of Selected Core Exit Thermocouples Reactor Shutdown YES NO N-31~~CPS N-32 CPS N-35~0-II AHPS N-36~-I/AMPS Avg.Nuclear Power RCS Pressure'f7 PSIG PRZR Level~&.3 A RCP RUNNING OPP B RCP RUNNIN STOPPED 1A S/G Level~sd&1B S/G Level~)a7 1A S/G Pressure~~PSIG 1B S/G Pressure PSIG Turbine/Generator ONLINE FF I 4 KV Buses NERGIZE DEENERGIZED 480V Buses NERGIZE DEENERGIZED DC Batteries A~VOLTS B/30VOLTS Cnmt Pressure~ZCa PSZG Cnmt Sump A Level FEET Cnmt Sump B Level INCHES A Loop Hot Leg~3.Z.OF A Loop Cold Leg Wla 7 OF B Loop Hot Leg~~3.OF B Loop Cold Leg'~l.h OF RVLIS*CET.3 OF.S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow O GPM Gi 1992 11:45 R.E.GINA Slt(ULATOR TREND 6ROUP ASSIG)NENT SUt)t(ARY PAGE 1 6ROUP: EVENTl PROCEDURE: EPIP 1-5 PLANT STATUS1 2 3 4 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 HP PRCS LPLR FRCLA FRCLB RXT16 R)(T17 TSUBTC LSGA LSBB PSBA PSBB GENBKRl GENBKR2 BUS11A BUS11B BUS12A BUS12B Bl lA12A 811B12B PCV LSI(PA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVBAMID TAVBBMID LRV TCCQRE FAUXFMA FAUXFMB BKR081 BKR082 V3505 V3504 DESCRIPTION ANTICIPATED TRANSIENT W/0 SCRAtt REACTOR TRIP BRENER STATUS SISCE RANGE DETECTOR N-31 SISCE RANGE DETECTOR N-32 INTEI(t(EDIATE RANBE DETECTOR N-35 INTER)(EDIATE RANBE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEtt AVG PRESS PRESSURI IER AVERA6E LEVEL REKTOR CQOUNf LOOP A AVB FLOW REACTOR COOLAt(T LOOP 8 AVB FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED MARIN STtt GEH A HARROM RANGE AVG LEVEL STM GEN B t(ARROW RA%E AVG LEVEL STM GEN A AVERAGE PRESSURE STt(GEN B AVERAGE PRESSURE CBERATOR ON LINE BRENER 161372 GENERATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BRENER BUS 118 SUPPLY BRENER NOT TERNINATED ON PPCS (7/19/91)NOT TERHINATED Qt(PPCS (7/19/91)BUS llA TO 12A TIE BREAKER BUS 119 TO 12B TIE BREAKER CQNTAINtiENT AVERAGE PRESSURE CONTAltitlEhT S)iP A AVERAGE LEVEL SUtP B LEVEL 8 INCHES (TRAIt(A)SUtP B LEVEL 8 INCHES (TRAIN 9)SUtP 8 LE4S.78 INCHES (TRAIN A)SU)P B LEVEL 78 INCHES (TRAIN B)SUtP B LEVEL 113 It(CHES(TRAIN A)SUtP B LDH, 113 It(CHES(TRAIN B)SUtP B LEVEL 180 INCHES(TRAIN A)SUtP B LE4S.180 INCHES(TRAIN B)SUtP B LEVEL 214 INCHES(TRAIN A)SUtP B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TFt1PER4T()K RCEB HOT LEG TE5'ERATURE RCLA COLD LEG TEt(PERAT(SE RCLB COLD LEG TEt)PERATURE RCLA TAVB (THOT/TCQLD WIDE RNB)RCLB TAVG (THAT/TCOLD WIDE RNB)REACTOR VESSEL AVERAGE LEVEL El.l IHCORE TC AVERAGE TEt(P S/G A TOTAL AiJX FEEDMATER FLOW S/6 B TOTAL AUX FEEDMATER FLS(t(TR AUXILIARY FEEDMAmi.Put(P 4 t)TR AUXILIARY FEEDMATER PUt)P 9 AUX FW PU)(P STEA)t SL4'PLY VALVE A AUX FW PU5'TEAt)SL'PPLY VALVE B OFF OFF CLOSED CLOSED VALUE QUAL ATMS ALII RX TRIPPED ALR)(7.87043+01 6009 8.34639%1 6009 1.01391-11 6009 1.01391-11 6009.00 6009 976.6009 46.3 6009 12.9 INHB 111.9 6009 TRIPPED ALRtt NQT TRIP 6009 100.1 600e 42.5 6009 40.7 6009 973.6009 350.LALN TRIPPED ALQf TRIPPED ALR)(TRIPPED ALRN TRIPPED AUI NQT TRIP DEL NOT TRIP DEL NOT TRIP ALRt(NOT TRIP ALRtf-.26 6009 2.4 tIRt(LONER G009 LOMER GOOD LOMER GOOD LOMER GOOD LOMER GOOD LOMcR GOOD LOMER 6009 LOMER GOOD LOMER 6009 LOMER 6009 443.2 6009 443.4 6009 441.7 6009 441.5 6009 442.4 GOOD 44'.5 GOOD 99.8 6009 443.3 600e 0.6009 1.6009 GOOD 6909 6009 GOOD E.U.CPS CPS At(P y.PSIG X 7.z DEGF X X PSIG PSIG PSIG FcCT DEBF I)EGF t)EGF DEGF KGF 066F y.DEGF GP)(GPt( OCT Bi 1992 il:45 R.E.GINA SINLATOR TREND GSP AKIGNENT RNNRY PAGE 2.6ROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID 53 FSIA 54 FSIB 55 P21b0 56 P2161 57 BKR041 58 BKR042 59 BKR043 h0 BKR044 DESCRIPTION SAFETY INACTION'LOCH A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SERVICE WATER PtNPS A h B HEADER SERVICE WATER PNPS C h D HEADER SERVICE WATER PUNP A SERVICE WATER PUNP B SERVICE WATER PUNP C SERVICE WATER PUNP D OFF ON ON ON 0.0.72.80.QUAL E.U.6009 GPN 600 D GPN GOOD PSI6 600D PSIG GOOD GOOD GOOD GOOD E+3 ROGRAM HAME:LRGTSZ.E R.E.GINHA NUCLEAR PSIER PLANT OCT 08,92 11 47 00 TREND CROUP ASSIGNMENT

SUMMARY

GROUP NAME EVENT 2 GROUP DESCRIPTION PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY GX)E ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 F0619 LRMST US033 40033 l6033 lIT250 lOT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R'19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 C(NPONEHT COOLING LOOP TOTAL FLII REFUELIMG lIATER STORAGE TANK LVL 33 FOOT LEVEL lIIHD SPEED 33 FOOT LEVEL IIIHD DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOH AREA 2-CONTAINHENT AREA 5-SPENT FUEL PIT AREA 9-LETDSIN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUHP AREA 35-PASS SAHPLE PANEL CONTAINMEHT IODINE HOHITOR R10A CONTAINMENT AIR PARTICULATE CONTAINHENT GAS MONITOR PLANT VENT IODINE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID IIASTE DISPOSAL MONITOR STEAH GENERATOR BLSNSIM DRAIN AREA 29-CONTAIMHENT HIGH RANGE AREA 30-CONTAINMEHT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LSI RANGE GAS CV VENT CHAN 6 AREA GAHMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOlI RANGE GAS PLANT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAN 9-HIGH RAMGE GAS AIR EJECTOR CHAN 5-LSI RANGE GAS AIR EJECTOR CHAN 7-HID RANCE GAS AIR EJECTOR CHAN 9-MI RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE 8 (SPING)CV NYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEHP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL.6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 6.2 76.65.0 66.8 1.8 9.02214.02 7.35678+00 1.39946+00 1.32701+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.28174+04 5.05861-01 5.09440.01 1.57835+03 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 2.09411-07 1.34492-05 1.27941-03 2.42040100 1.01048-02 .0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD 60(O GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD QXO GOOD GOOD 6000 BALM GOOD GOCD GOOD GOOD GOOD GOOD 6000 GOOD GOOD GOOD GOOD MALH 6000 6000 CODD CODD GOOD GOOD COOD COCO GPM X MPM DEG.DEGF DEGF DEGF MR/N HR/H MR/H HR/H MR/H MR/M CPM CPM CPH CPH CPM CPM CPM CPM R/HR R/MR CPH UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC HR/MR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF 0-J Time:~114 Message:~4l~INN A TATI N 1 2EVAL E E ER I E MESSA E FORM MMMf: ICFF ffff dg IM F,V I C Support Staff, Engineering Support Center Staff im l P I i: See the Attached Mini-Scenario ~IVle s~a"""THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~gl g 1)Provide information verbally that several Rochester Telephone phone sets are inoperable due to an unspecified cause.Antici ated Results: 1)As per Mini-Scenario Anticipated Results. GINNA STATION 19 2 EVALUATED EXERCISE IVIINI-SCENARIO TITLE: EOF Tel hone S s em F il re Expected scenario start time: 1145 INITIAL CONDITIONS: Centrex, Rochester Telephone and New York Telephone extensions operable.METHOD OF INITIATION: EOF and ESC Controllers inform EOF and ESC Staff that several Rochester Telephone extensions are not working.INDICATIONS: Controllers should have tags ready to place on phone sets indicating they are not functional. EXPECTED SEQUENCE OF ACTIONS: 2.Voice communications staff to initiate investigation on cause of telephone system malfunction. 1 Appropriate announcements made to EOF and ESC staffs.Voice and fax communications should be transferred to alternate telephone systems.EOF Dose Assessment may need to obtain weather tower data through alternate telephone extension. FINAL CONDITIONS: Players will be given credit for actions taken.Telephones will not be restored before the end of the exercise.8-/66 Time:~114 Message:~42~INNA TATI N 2 EVAL ATED XER I E ME A E FORM NNNNNLIAL: N Ihdhd I T h I I<<I CI h TNC.im la d Plan C nditions: See the Attached Mini-Scenario ~Me~a"""THIS IS AN EXERCISE""" F R ONTROLLER USE ONLY~CN 1)Health Physics controller may alarm the frisker probe with a check source to simulate contamination found on his shoes and clothing.An ici a ed Resul 1)As per Mini-Scenario Anticipated Results. INNA TATI N 1 2 EVAL ATED EXER I E MINI-S ENARI TITLE: in In'v I rivin h Expected scenario start time: 1145 INITIAL CONDITIONS'risking stations and step-off pads set up at TSC entrances. METHOD OF INITIATION: Health Physics controller alarms the frisker probe with a check source to simulate contamination on his shoes and clothing.INDICATIONS: Controller should provide simulated readings to HP technician responding to frisker alarm.Bottoms of shoes: 2000 cpm Socks and pant cuffs: 500 cpm Floor areas at TSC entrance: 200-1000 cpm EXPECTED SEQUENCE OF ACTIONS: 2.3.4.5.HP technician responds and conducts monitoring of contaminated individual. HP/Chemistry Manager is informed.TSC entrance secured to prevent further spread of contamination. Follow-up actions required by HP-6,3 are initiated for documentation and decontamination. Technicians should investigate and survey for extent of contamination spread within TSC and areas outside of TSC.(Controller will provide readings to players as requested). FINAL CONDITIONS: Health Physics Controller to give credit for decontamination and contamination control actions taken.Readings to be reduced as appropriate, depending on actions taken. Time:~QQ Message: 47~INNA TATI~19 2 EVAL ATED EXER I E~MESSA R F RM~IM I: M I<<F<<IR Simulated Plan Conditi ns: See the Attached Sheets~Messs e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Con roller No es: An ici a ed Resul s: 1)Operators performing the Applicable Actions of ES-3.1 (Post-SGTR Cooldown Using Backfill), 2)TSC evaluating Plant conditions and taking action as required.3)EOF Plant conditions and taking action as required. 199K EVALUATED EXERCISE Time:/2OO ENGINEERED SAFEGUARDS Hi h Head S.Z.Pum s MAZOR PAE&METERS FI-924 O GPM FI-925 0 GP 1A INSERV TB OOS 1B.INSERV TBY OOS 1C INSERV OOS BAST Level=Low Head S.I.Pum s FZ-626 O G M 1A.INSERV B OOS RECIRC 1B.INSERV OOS RECIRC RWST Level=3.Containment S ra Pum s FI-931A D GPM Fl-93 1B C7 GP 1A.INSERV B OOS 1B.INSERV B OOS NaOH Tank Level=9'ontainment Recirc Fans 1A.NS STBY OOS 1B.SER STBY OOS 1C.SE STBY OOS 1D.NSE STBY OOS Post Accident Dampers OPEN CLOSED Service Water Pum s 1A.I STBY OO 1B.SER STBY OOS 1C.STBY OOS 1D.NSER STBY OOS A&B Header Pressure v~f'0 PSIG DIESEL GENERATORS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED OOS TSC RUNNING UNIADADED TB OOS Security RUNNING UNLOADED TB Com onent Coolin Water Pum s OOS Reactor Shutdown ES NO N-31 CPS N-32~CPS N-35~O~AAMPS N-36=Wf AMPS Avg.Nuclear Power 0 RCS Pressure+@LPSZG PRZR Level/A RCP R NG TOPP B RCP UNNIN STOPPED 1A S/G Level ga2 1B S/G Level e.1A S/G Pressure PSIG 1B S/G Pressure 2 4 PSZG Turbine/Generator ONLIN FFLIN 4 KV Buses ERGIZE DEENERGZZED 480V Buses NERGZZE DEENERGZZED DC Batteries Ange VO B/BOVOLTS Cnmt Pressure~2.PSIG Cnmt Sump A Level~i,~FEET Cnmt Sump B Level@~i INCHES A Loop Hot Leg~>~70 F A Loop Cold Leg OF B Loop Hot Leg~BA.Q OF B Loop Cold Leg OF RVLIS~g*CET OF , S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FN Flow~a.GPM ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.INSE V TB OOS 1B.NS R STBY OOS Turb.Driven INSERV TB OOS CST Level F*CET=Average of Selected Core 1A.ZNSE V STBY OOS 1B.NSERV STBY OOS Surge Tank Level=~/Standb Aux.Feedwater Pum s 1C.INSERV TB OOS 1D.ZNSERV TB OOS Exit Thermocouples Gi 1992 12'00 R.E.GINA Sit((LATOR TREND GROUP ASSIBNt(Et(T SUtft(ARY PAGE 1 GROUP: EVENTI PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E.U.2 3 5 6 7 8 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 46 a7 48 49 50 51 52 ATI6 RXT N31 N32 N35 N36 NP PRCS LPLR FRCLA FRCLB RXT16 RXT17 TSUBTC LSBA LSGB PS6A PSGB GENBKRI GB(BKR2 BUS11A BUS 118 BUS12A BUS128 811A12A 8118128 PCV LBNPA L0942E L0943E L09429 L0943D L0942C L0943C L09428 L09438 L09a2A L0943A T0409A T0410A T0450 T0451 TAVGAW!9 TAVGBMID LRV TCCORE FAUXFWA FAUXFWB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT M/0 SCRuf REACTOR TRIP BREAKER STATUS SONCE RANGE DETECTOR N-31 SOlRCE RAhGE DETECTOR N-32 It(TERt(EDIATE RANGE DETECTOR N-35INTEfNEDI ATE RANGE KTECTOR N-36 AVERAGE N(GER POWER REACTOR COOLufT SYSTEtf AVG PRESS PRESSURIIER AVERAGE LEVEL REKTOR COOLANT(T LOOP A AVG FLOW REACTOR COOLANT LOOP 8 AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED t(ARGIN STff GEtf A NARROW RANGE AVG LEVEL STtf GEN 8 t(ARROW RANGE AVG LEVEL STt(GEtf A AVERAGE PRESSURE STt(GEN 8 AVERAGE PRESSURE GENERATOR ON LINE BREAKER 1G1372 GEhERATOR ON LINE BREAKER'9X1372 BUS 11A SUPPLY BREAKER BUS 118 SlFPLY BREAKER NOT TERMINATED Off PPCS (7/19/91)NOT TERt(INATED ON PPCS (7/19/91)BUS 11A TO 12A TIE BRENER BUS 118 TO 128 TIE BRE(CER CONTAItft(ENT AVERAGE PRESSURE C0%'Aiht(ENT PJt(P A AVEfmGE LEVEL SUtf'LEVS.8 It(CHES (TRAIN A)SUtP 8 LEVEL 8 INCHES (TRAIN 8)SUtf'LEVEL 78 JNCHES (TRAIN A)SU%'LESS 78 INCI:ES (TRAIN 8)SU@8 LEVEL 113 INCHES(TRAIN A)SUtP 8 LESS.113 INCHES(TRAIN 8)SUtf'LEVEL 180 INCHES(TRAIN A)SUtP 8 LEVEL 180 INCHES(TRAIN 8)PJtf'LEVS.214 IhGfES(TRAIN A)SLtiP 8 LEVEL 214 INCHES(TRAIN 8)RCuf HOT LEG TEf(PERATUR= RCLB HOT LEG TEt(PERATUK RCLA COLD LEG TEtfPERATNE PCLB CO'LEG TEtiPERATURE PCLA TAVG (Tf(OT/TCOLD WIDE RNG)R".U3 TAVG (THDT/TCOLD WIDE RNG)PEACTOR VESS<<AVERAGE LEVEL Ei.'t'COPE TC AVcBAGE TEt'i~S!C A TOTAL AUX FEEDMAlS(FLOW S/G 8 TOTAL AJX FEEDMATER FLOW t(TR AUXILIARY FEEBLER PUt(P A tfTR AUXILIARY FEEDMATER PU)fP 8 AUX FM PUt(P STEAtf SUPPLY VALVE A AUX FM PUN'TEA)f SUPPLY VALVE 8 ATNS RX TRIPPED 8.11894%1 8.09093%1 1.01391-11 1.01391-11 .00 958.51.8 12.9 112.5 TRIPPED NOT TRIP 105.4 38.2 40.8 953.326, TRIPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NOT TRIP NOT TRIP~28 2.5 LONER LONER LONER LONER LONER LONER LONER LONER LONER LONER 434.7 436.0 434.6 434.6 434.6 435.3 99.7 435.9 0.42, OFF ON CLOSED CLOSED ALII ALfm 6009 600D 6009 GXD 6009 6009 6009 INHB 600D ALRtf 6009 600~600D 6009 6009 LALN ALRtj ALRtf ALRt(ALRtf DEL DEL ALRtf ALRff 6009 HWRtf 6009 GOOD 6009 600D 6009 6009 GOOD 6009 6009 6009 6009 6009 6009 GOOD 6009 6009 GOOD 600~6009 600D 600D 6()09 GOOD 6009 CPS CPS At(P At(P X PSIG X X'X K6F X X PSI6 PSIG PSI6 FEET DEGF DEGF DEBF KGF DE6F K6F X KBF GPtf XT Gs 1992 12'00 R.E.GINA SINULATOR TREND GROUP ASSIGNENT SUNQRY PAGE 2 GROUPS EVENTi PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E.U.53 FSIA 54 FSIB 55 P2160 5b P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 SAFETY INJECTION.'LOOP A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SERVICE WATER PNPS A 5 B HEADER SERVICE WATER PmfPS C h D HEADER SERVICE WATER PtNP A SERVICE HATER PUffP B SERVICE WATER PlNP C SERVICE WATER PUtfP D 0.0.72.80.OFF ON ON ON 600 D GPtf GOOD GPN 6XD PSI6 GOOD PSIG GOOD GOOD 600D 600D ~~ROGRAM NAME:LRGTSZ.E R.E.GINNA KUCLEAR POWER PLANT OCT 08,92 12:01:00 TREND GROUP ASSIGNMEHT

SUMMARY

GROUP HAHE EVENT 2 GROUP DESCRIPTION PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 20 21 22 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 0 J F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R15 R12AS R12A6 R12A7 R12A9 R14AS R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLW REFUELING WATER STORAGE lANK LVL 33 FOOT LEVEL WIKD SPEED 33 FOOT LEVEL WIKD DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOM AREA 2-CONTAIHHEHT AREA 5-SPENT FUEL PIT AREA 9.LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PANEL CONTAINHEHT IODINE MONITOR R10A CONTAINMEHT AIR PARTICULATE CONTAINMEHT GAS MOHITOR PLANT VENT 1OOIHE MONITOR R108 AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID WASTE DISPOSAL MOHITOR STEAM GENERATOR SLOWDOWN DRAIN AREA 29-CONTAINMENT HIGH RANGE AREA 30-CONTAINMENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7 MID RANGE GAS CV VENT CNAH 9-HIGH RANGE GAS PLAHT VENT CHAN 5-LOW RANGE GAS PLAHT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAN 9-HIGH RAKGE GAS AIR EJECTOR CHAN 5-LOW RAHGE GAS AIR EJECTOR CHAN 7 HID RAKGE GAS AIR EJECTOR CHAN 9-Hl RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE B (SPIHG)CV HYDROGEN CONCENTRATION CV BASEHEHT LVL 6 FT TENP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERHEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 6.1 77.65.1 66.8 1.7 9.02214-02 7.35678+00 1.3994&00 1.29701+02 9.09354-01 1.09283i00 9.58719+01 5.18901+02 7.38002+02 4.30543t01 8.58327+01 4.22831+01 2.78658+03 1.19174+04 5.05861-01 5'9440.01 1.57835+03 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 2.09411-07 1.34492-05 1.27941-03 2.33040+00 1.01048-02 .0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD G(XS GOOD GOOD GOtX)G(XX)GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM X MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/M MR/H MR/H MR/H CPM CPH CPM CPM CPM CPH CPH CPH R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR X DEGF DEGF DEGF DEGF DEGF DEGF Time:~121 Message:~4~INN A TATI N 1 2 EVAL ATED EXER I E MESSA E FORM T: N I N IN Simula e Plan Condition: See the Attached Sheets~Messs e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~CI N Antici a ed Resul s: 1)Operators performing the Applicable Actions of ES-3.1 (Post-SGTR Cooldown Using Backfill). 2)TSC evaluating Plant conditions and taking action as required.3)EOF evaluating Plant conditions and taking action as required. 199K'VALUATED EXERCISE MAJOR PARAMETERS ENGINEERED SAFEGUARDS A.RUNNING UNLOADED T OOS B.RUNNING UNLOADED STB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB ENGINEERED SAFEGUARDS OOS Aux.Feedwater Pum s 1A.INSERV TB OOS 1B.S R STBY OOS Turb.riven INSERV B OOS CST Level/2 F*CET=Average of Selected Core Reactor Shutdown ES NO N-31 CPS N-32~OCPS N-35 NH/AMPS N-36 AMPS Avg.Nuclear Power 0 RCS Pressure PSIG PRZR Level A RCP R G OP PE B RCP UNNIN STOPPED 1A S/G Level 1B S/G Level~E~to 1A S/G Pressure PSIG 1B S/G Pressure PSIG Turbine/Generator ONLINE FL 4 KV Buses ERGIZE DEENERGIZED 480V Buses NERGIZED DEENERGIZED DC Batteries A~SOVOLTS B~VOLTS Cnmt Pressure-~R.PSZG Cnmt Sump A Level?.FEET Cnmt Sump B Level INCHES A Loop Hot Leg~Qg.dLOF A Loop Cold Leg OF B Loop Hot Leg I.OF B Loop Cold Leg~i.O OF RVLIS~K>~*CET oF'/G A Total Aux FW Flow~GPM S/G B Total Aux FW Flow~fGPM DIESEL GENERATORS Hi h Head S.Z.Pum s FI-924 C)GPM FZ-925 N GPM 1A INSERV TB OOS 1B.INSERV TB OOS 1C INSERV TB OOS BAST Level=/C7 Low Head S.Z.Pum s FI-626 O GPM 1A.INSERV OOS RECIRC 1'NSERV OOS RECIRC RWST Level=VS-Containment S ra Pum s FZ-931A GPM FI-931B C)GP 1A.INSERV T OOS 1B.INSERV OOS NaOH Tank Level=Containment ecirc Fans 1A.E STBY OOS 1B.SE STBY OOS 1C.SE STBY OOS 1D.STBY OOS Post Accident Dampers EN CLOSED Service Water Pum s 1A.INSE V STBY OS 1B.SE STBY OOS 1C~SER STBY OOS 1D.N R STBY OOS A&B Header ressure~PSIG Com onent Coolin Water Pum s 1A.I ERV STBY OOS 1B.INSERV STBY OOS Surge Tan vel=Standb Aux.Feedwater Pum s 1C.INSERV T OOS 1D.INSERV TB OOS Exit Thermocouples Gr 1992 12:15 R.E.GINA Sft(ULATOR TREND GROUP ASSIG)ST SUM)IRY PA6E 1 GROUP: EVENTi PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E.U.1 2 3 5 6 7 8~9 10 11 12 13 14 15 16 17 18 f9 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 ATMS R)(T N31 N32 N35 N36 NP PRCS LPLR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGR LS6B PSGA PSGB GEtlBKRl GENBKR2 BUS11R BUS11B BUS12A BUS12B B11A12R B11812B PCV LSlNPA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409R T0410R T0450 T0451 TAVGAMID TR'LGBMID LRV TCCORE FAUXFMR FRUXFMB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT M/0 SCRAM REACTOR TRIP BREAKER STATUS SMKE RANGE DETECTOR N-31 SISCE RRt(GE DETECTOR N-32 INTERMEDIATE RAN6E DETECTOR N-35 INTERMEDIATE RANGE DETECTOR N-36 AVERA6E NUCLEAR POWER RECTOR COOLANT SYSTEM AVG PRESS PRESSURIZER AVERAGE LEVEL REACTOR COOLW(T LOOP A AVG FLOW REACTOR COOLANT LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED MARGIN STM GEN A NARROM RANGE AVG LEVEL STM GEN B NARROW RAKE AVG LEVEL STM GEN A AVERAGE PRESSURE STM GEN B AVERAGE PRESSURE GENERATOR ON LINE BREAKER 161372 GYRATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B SUPPLY BREAKER NOT TERMIt(ATED ON PPCS (7/19/91)NOT TERMINATED ON PPCS (7/19/91)BUS 11A TO 12A TIE BREAKER BUS 11B TO 128 TfE BREAKER CONTAINMENT AVERAGE PRESSURE CO)1TAIt(MENT SUMP A AVERAGE LEVEL SU)A'LEVEL 6 INCHES (TRAIN A)SUB'LEVEL 8 INCHES (TRAIN B)SUtf'LEVEL 78 INOKS (TRAIN A)SUtf'LEVEL 78 fNCHES (TRAIN B)SUMP B LEVEL 113 INCHES(TRAIN A)SrJYP 8 LEVEL 113 INCHES(TRAIN B)SUMP B LEVEL 180 It(CHES(TRAIN A)SUtf'LEVEL 180 INCHES(TRRIN B)SUtf B LEVEL 214 INCHES(TRAIN A)SUtP B LEVEL 214 INCHES(TRAIN B)RCLR HOT LEG TEMPERATURE RCLB HOT LEG TEMPERATURE RCLR COLD LEG TEMPERAT(RE RCLB COLD LEG TEMPERRTNE RCLR TAVG (THOT!TCOLD WIDE RNG)RCLB TAVG (T)GT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.l ft, ORE TC AVERAGE TEMP S/G R TOT&'UX FEEBtA7rZ FLOW S/G B TOTAL AUX FEENATER FLOW MTR AUXILIARY FEEDMATER PUMP A MTR AUXILIARY FEEDMRTER PUMP B AUX FM PUt(P STER)(SUPPLY VALVE A RUX FM PUN'TEAN SUPPLY VALVE B ATMS RX TRIPPED 8.55064+01 7.95241+01 1.01391"11 1~01391-11.00 899.58.9 13.0 114.0 TRIPPED NOT TRIP 115.7 29.4 36.0 919.268.TRfPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NOT TRIP NOT TRIP-28 2.5 LONER l.ONER LONER LONER LONER LONER LONER LONER LONER LONER 418.9 418.0 416.2 416.0 417.5 417.0 99.6 417.7 0.189.OFF ON CLOSED CLOSED RLRt(ALII GOOD 6000 GOOD 600D GOOD GOOD GOOD INHB GOOD ALRt(600D 600~LMRN GOOD GOOD LALt(RUI ALR)(ALRtf AUI DEL DEL RLRt(AUI 600D HMRN GOOD GOOD GOOD GOOD 600D 6000 6009 600D 6000 600D GOOD GOOD GOOD GOOD GOOD 6000 GOOD 600>GOOD 600D 600D 680D GOOD GOOD CPS CPS AMP AMP X PSIG X X X DEGF PSI6 PSIG PSIG FKT DEGF KGF KGF KGF KGF K6F X KGF GPtf PM 8'76 OCT 8~1992 12:15 R.E.GIWA SINULATOR TREND GROUP ASSIGNNENT SUNNARY PAGE 2 6ROUP: EVENT1 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QlAL E.U.53 54 55 56'57 58 59 60 EMJ FSIA SAFETY INJECTION:LOOP A FSIB SAFETY INJECTION LOOP B P2160 SERVICE MATER PIIPS A h P2161 SERVICE MATER PNPS C h INR041 SERVICE WATER PNP A IIR042 SERVICE WATER PlNP B INR043 SERVICE MATER PIIP C BKR044 SERVICE MATER PNF 0 AVG FLOW AVG FLOW B HEADER D HEADER 0.GOOD 0.GOOD 72.GOOD 80.600 D GOOD 600D 6009 GOOD GPN 6PN PSIG PSIG ~~OGRAK NAHE:LRGTSZ.E R.E.GINNA NUCLEAR POWER PLANT OCT 08,92 12:15:00 TREND GROUP ASSIGNHEHT SUHHARY GROUP NAME EVENT 2 GROUP DESCRIPTIOH PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE EHGR UNITS 1 2'4 5 6 7 8 9 10 11 12 13 14 20 21 22 23 24 25 26 27 28 29 ,30 31 32 33 34 35 36 37 38 39 40 41 42 43 0'0619 LRWST WS033 WD033 WT033 WT250 WOT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15AS R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COKPONEHT COOLING LOOP TOTAL FLW REFUELIHG WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEHPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOM AREA 2-CONTAINMENT AREA 5-SPENT FUEL PIT AREA 9.LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PANEL CONTAINMENT IODINE MONITOR R10A CONTAINHENT AIR PARTICULATE COHTAINKENT GAS MONITOR PLANT VENT IODIHE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS KOHITOR LIQUID WASTE DISPOSAL MONITOR STEAM GENERATOR BLOWDOWN DRAIN AREA 29 CONTAINHENT HIGH RANGE AREA 30-COHTAINHEHT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5 LOW RANGE GAS CV VENT CHAN 6-AREA GAHHA CV VENT CHAH 7 MID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOW RANGE GAS PLANT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHANS-LOW RANGE GAS AIR EJECTOR CHAN 7-HID RANGE GAS AIR EJECTOR CHAN 9-Hl RANGE GAS AREA 31 STEAK LIHE A (SPING)AREA 32 STEAH LINE 8 (SPING)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEHP¹3 CV IHTERMEDIATE LVL 6 FT TEMP¹7 CV INTERHEDIATE LVL 6 FT TEHP¹8 CV INTERHEOIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 6.5 77.66.0 67.8 1.8 9.02214-02 7.35678+00 1.39946+00 1.27501+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658i03 1.14174+04 5.05861.01 5.09440.01 1.57835+03 1.89699-07 2.53990-02 3.57435-05 1 41261-03 4.40312.07 6.86543-05 3.?2621-03 2.09411-07 1.34492-05 1.27941-03 2.25040t00 1.01048.02 .0 95~1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPK X KPH OEG.DEGF DEGF DEGF MR/H MR/H KR/H KR/H KR/H KR/H CPH CPM CPM CPM CPM CPH CPK CPM R/NR R/HR CPH UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC KR/HR MR/HR DEGF DEGF DEGF DEGF DEGF DEGF Time:~12 Q Message:~4 GINNA STATION 1 92 EVAL ATED EXERCISE~MERE E ERRM~M: M I E<<IR Simulated Plant Conditions: See the Attached Sheets~IVlesss e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY Controller Notes: 1)Accident evaluation and response continues. Antici ated Resul s: 1)Recovery/Re-entry and Declassification discussions should commence per the guidance provided in EPIP 3-4,"Emergency Declassification and Recovery." Discussions should also include but not be limited to the following: a)Preliminary discussions between the EOF and the TSC on the following: ~Short Term Plant concerns such as: 1.2.3.4.5.Cooldown and depressurization of the Plant.Repair and return to service of the"A" CCW Pump to ensure a redundant pump for decay heat removal.Repair and return to service of the"A" Service Water Pump.Repair and return to service of the Natural Gas line to the Screenhouse. Continued evaluation of the drilled hole in the"B" S/G ARV.(continued on the next page)

~Intermediate Term Plant concerns such as: 1."A" S/G Tube inspection and repair.2.Possible"B" S/G Tube inspection. 3.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. 199'VALUATED EXERCISE Time:~23G'AJOR PARAMETERS ENGINEERED SAFEGUARDS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED T ENGINEERED SAFEGUARDS OOS Aux.Feedwater Pum s 1A.INSERV T OOS 1B.SE STBY OOS Turb.Driven INSERV TB OOS CST Level~1 FEET Reactor Shutdown (YYE NO N-31~CI CPS N-32~~CPS N-35 z~/AMPS N-36~-s/AMPS Avg.Nuclear Power C7 RCS Pressure~FE-PSTG PRZR Level b~~l.A RCP RUNNING TOPPED B RCP~RUNNIN STOPPED 1A S/G Level 1B S/G Level S7.7 1A S/G Pressure PSIG 1B S/G Pressure 2.93 PSIG Turbine/Generator ONLINE FFLI 4 KV Buses NERGIZE DEENERGIZED 480V Buses R DEENERGIZED DC Batteries A/BO VOLTS B/30 VOLTS Cnmt Pressure~~30 PSIG Cnmt Sump A Level 2,ek FEET Cnmt Sump B Level~~INCHES A Loop Hot Leg Bm.~oF A Loop Cold Leg~ax a OF B Loop Hot Leg.2 OF B Loop Cold Leg~oa.OF RVLIS g5 4*CET~OS~0 F S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow Ia.a GPM DIESEL GENERATORS Hi h Head S.X.Pum s FI-924 0 GPM FI-925&GPM 1A.INSERV TB OOS 1B.INSERV TB OOS 1C.INSERV TB OOS BAST Level=Io Low Head S.I.Pum s FI-626 O GPM 1A.INSERV OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=~E.V Containment S ra Pum s FI-931A&GPM FI-931B O GPM 1A.INSERV TB OOS 1B.INSERV TB OOS NaOH Tank Level=Containment Recirc Fans 1A.NSE V STBY OOS 1B.SER STBY OOS 1C.SE STBY OOS 1D.NSER STBY OOS Post Accident Dampers E CLOSED Service Water Pum s 1A.XNSERV STBY 0 1B.SE STBY OOS 1C.NSER STBY OOS 1D~NSER STBY OOS A&B Header Pressure~7'0 PSIG Com onent Coolin Water Pum s 1A.INSERV STBY 00 1B.NSE STBY OOS Surge Tan evel=M/Standb Aux.Feedwater Pum s 1C.INSERV TB OOS 1D.INSERV STB OOS*CET=Average of Selected Core Exit.Thermocouples 8s f992 12:30 R.E.GINA SIMULATOR PAGE 1=-TREND GROUP-ASSIGNMENT

SUMMARY

6ROUP: EVENT1 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE ()UAL E.U.1 2 3 6 7 8 9 10 11 12 13 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 45 46 47 48 49 50 51 52 ATMS RXT N31 N32 N35 N36 NP PRCS LP2R FRY FRM RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GENBKRI GEt(BKR2 BUS11A BUS11B BUS12A BUS12B BiiA12A B11812B PCV LQNPA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAVGBMID LRV TCCORE FAUXFMA FAUXFWB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT W/0 SCRAM REACTOR TRIP BREAKER STATUS SOlRCE RANGE DETECTOR N-31 SmSCE RA)IGE DETECTOR N-32 INTERMEDIATE RANEE DETECTOR N-35 INTERMEDIATE RANGE DETECTOR N-36 AVERAGE NLQZ8 POWER REACTOR COOLANT SYSTEM AVG PRESS PRESSURI2ER AVERAGE LEVEL REKTOR COOLANT LOOP A AVG FLOW REKTOR COOLANT LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBC(mLED MARGIN STM GEN A NARROW RANGE AVG LEVEL STM GBI B NARROW RA%E AVG LEVEL STM GEN A AVERAGE PRESSURE STM GEN 8 AVERAGE PRESSURE GBHNTOR ON LINE BREAKER 161372 GBERATOR ON LINE BREAKER 9X1372 BUS 1fA SUPPLY BREAKER BUS 11B SlFPLY BREAKER NOT TERMIt(ATED Ott PPCS (7/f9/91)NOT TERMIt(ATED ON PPCS (7/19/91)BUS ifA To 12A TfE BREAKER BUS 11B To 128 TIE BRENER CONMINMEt(T AVERAGE PRESSURE CONTAINMENT SUMP A AVERAGE LEVEL SU)P B LEVEL 8 INCHES (TRAIN A)SU)P B LEVEL 8 INCHES (TRAIt4 B)SU)P B LEVEL 78 INCIIES (TRAIN A)SU)P B LEVEL 78 INQKS (TRAIN B)SU)P B LEVEL 113 INCHES(TRAIN A)SU)P B LEVEL 113 INCHES(TRAIN B)SU)P B LEVEL 180 INCHES(TRAIN A)SUIP B LEVEL 180 INCHES(TRAIN B)SU)P B LEVEL 214 INCHES(TRAIN A)SU)P B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TEMPERATURE RCLB HOT LEG TEMPERATUR" RCLA COLD LEG TEtIPERATURE RCLB COLD LEG TBIPERATNE RCLA TAVG (THOT/TCOLD WIDE RNG)RCLB TAVG (THOT/TCOI.D WIDE RNG)REACTOR VESSEL AVERAGE LEVEL Ei~1 INCORE TC AVERAGE TEMP S/G A TOTAL AUX FEEDMATER FLOW S/G B TOTAL AUX FEEDMATER FLOW MTR AUXILIARY FEEDMATER PUMP A MTR AUXILIARY FEEDMATER PUMP B AUX FM PUMP STEAN SUPPLY VALVE A AUX FW PUMP STEAN SUPPLY VALVE B ATWS R)(TRIPPED 7.95241+01 8.46249+01 1.01391-11 1.01391-11 .00 892.61.8 13.2 115.2 TRIPPED NOT TRIP 128.6 21.7 51.7 891.233.TRIPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NOT TRIP t40T TRIP-.30 2.6 LONER LONER LONER LONER LONER Lo)IER Lo)4ER LOWER LOWER LONER 403.8 404.2 402.5 402.5 403.2 403.4 99.5 403.6 0.125.OFF ON CLOSED CLOSED ALRN ALRN 6009 CPS GOOD CPS 6009 AMP 6009 AMP GOOD X GOOD PSIG HMRN X INHB X 6009 X ALRN GOOD 600~DEGF LMRN X GOOD X 6009 PSIG LALM PSIG ALRN ALRN ALRN ALRN DEL DEL ALRN ALRN 6009 PSIG HMRN FKf 6009 6009 6009 6009 6009 6009 6009 G009 6009 GOOD 6009 DEGF 6009 DEGF 6009 DEGF GOOD DEGF 6009 DE6F 600D DEGF GOOD X 600~DEGF 6009 GPM GOOD GPM 6009 GOOD 6009 GOOD OCT 8~1992, 12!30 R.E.GIt5A SIIIULATOR TREND GROUP ASSIGIDIENT SINNRY PAGE 2 53 FSIA 54 FSIB 55 P2160 56 P2161 57 BKR041 58 BKR042 59 BKR043 60 BKR044 SAFETY INJECTION'LOOP A SAFETY INJECTION LOOP B SERVICE WATER PINPS A h SERVICE MATER PNIPS C 5 SEINICE WATER PINP A SERVICE WATER PUlIP B SERVICE WATER PINP C SERVICE MATER PNP 0 GROUP: EVEIIT1 PROCEDURE: POINT ID DESCRIPTION EPIP 1-5 PLNT STATUS VALUE AVG FLOW 0.AV6 FLOW 0.B HEADER 72.D HEADER 80.QUAL E.U.GOOD 6PtI GOOD 6PN GOOD PSIG 600D PSIG GOOD 600D GOOD 600D ROGRAM NAME:LRGTSZ.E~~~R.E.GIHHA NUCLEAR POWER PLANT OCT 08,92 12:30:00 TREHD GROUP ASSIGNMEHT

SUMMARY

GROUP NAME EVENT 2 GROUP DESCRIPTION PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 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 0 J F0619 LRWST WS033 WD033 WT033, WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15AS R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLW REFUELIHG WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL'WIHD DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-CONTAIHMENT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35 PASS SAMPLE PANEL CONTAINMENT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE CONTAINMEHT GAS MOHITOR PLANT VENT IODINE MOHITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID WASTE DISPOSAL MONITOR STEAM GENERATOR BLOWDOWH DRAIN AREA 29-COHTAIHHEHT HIGH RANGE AREA 30-CONTAINMEHT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CHAH 5-LOW RANGE GAS PLANT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAH 9-HIGH RANGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAN 9 HI RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE 8 (SPIHG)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹'IO CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 8.5 67.69.0 67.8 1.8 9.02214-02 7.35678+00 1.39946+00 1.24701+02 9.09354-01 1.09283+00 9.58719+01 5'8901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.09474+04 5.05861-01 5.09440.01 1'7835+03 1.89699.07 2.53990-02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 2.09411-07 1.34492-05 1.27941-03 2.18040t00 1.01048-02 .0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM x MPH BEGS DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPM CPM CPM CPM CPM CPM CPM R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR MR/HR x DEGF DEGF DEGF DEGF DEGF DEGF Time:~124 Message:~g INN A TATI N 1 92 EVALUATED EXER ISE~MEBBAGE F~MI: BI I G<<IR Simulated Plant Conditions: See the Attached Sheets~IN ssa e: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY C nr llrN 1)Accident evaluation and response continues. Antici ated Results: 1)Recovery/Re-entry and Declassification discussions should commence per the guidance provided in EPIP 3-4,"Emergency Declassification and Recovery." Discussions should also include but not be limited to the following: a)Preliminary discussion between the EOF and the TSC on the following: ~Short term Plant concerns such as: 1.2.3.Cooldown and depressurization of the Plant.Repair and return to.service of the"A" CCW Pump to ensure a redundant pump for decay heat removal~Repair and return to service of the"A" Service Water Pump.Repair and return to service of the Natural Gas line to the Screenhouse. Note: An evaluation of this may lead to a discussion not to return Natural Gas to the Screenhouse.(continued on the next page) ~Intermediate term Plant conditions such as: 1.2.3.4,"A" S/G Tube inspection and repair.Possible"B" S/G Tube inspection."A" S/G Tube rupture evaluation for root cause.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. 199K EVALUATED EXERCISE Time: 1~/~MAJOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YE NO N-31 0 CPS N-32 g CPS N-35 feb'-If AMPS N-36 gl AMPS Avg.Nuclear Power RCS Pressure 4 7 PSIG PRZR Level dO A RCP RUNNING TOPPE B RCP RUNNING STOPPED 1A S/G Level 1B S/G Level~.2 1A S/G Pressure~~~PSIG 1B S/G Pressure woz PSIG Turbine/Generator ONLINE FFLIN 4 KV Buses RG DEENERGIZED 480V Buses ENERGIZE DEENERGIZED DC Batteries A~VOLTS B/30 VOLTS Cnmt Pressure~~~aS S PSIG Cnmt Sump A Level 2.~Ce FEET.Cnmt Sump B Level~(INCHES A Loop Hot Leg>9m.r7 OF A Loop Cold Leg~Et.s.OF B Loop Hot Leg~i.ELOF B Loop Cold Leg~.I OF RVLIS*CET OF S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow~GPM DIESEL GENERATORS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED T OOS Security RUNNING UNLOADED TB OOS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 0 GPM FI-925GPM 1A.INSERV TB OOS 1B.INSERV T OOS 1C INSERV TB OOS BAST Level=/Low Head S.I.Pum s FI-626 O GPM 1A.INSERV T OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=~3.Containment S ra Pum s FI-931A GPM FI-931B O GPM 1A.INSERV 1B.INSERV T NaOH Tank Level=OOS OOS Containment ecirc Fans 1A.NSER STBY OOS 1B.SER STBY OOS 1C.SER STBY OOS 1D.NSE STBY OOS Post Accident Dampers PEN CLOSED Service Water Pum s 1A.INSERV STBY 1B.NSER STBY OOS 1C.SERV STBY OOS 1D.NS STBY OOS A&B Header ressure~0 PSIG Com onent Coolin Water Pum s 1A.INSERV STBY 00 1B.NSERV STBY OOS Surge Tan Level=~%Standb Aux.Fee ater Pum s 1C.INSERV TB OOS 1D.INSERV TB OOS Aux.Feedwater Pum s 1A.INSERV TB OOS 1B.SER STBY OOS Turb.Driven INSERV T OOS CST Level~iFEET*CET=Average of Selected Core Exit Thermocouples 8~1992 12:45 R.E.Glt5A SIMULATOR TREND GROUP ASSIG)MENT SUM)(ARY PA6E 1 GROUP: EVENT1 PROCEDURES EPIP 1-5 PLA)IT STATUS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 1S 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 46 47 48 49 50 51 52 POINT ID ATWS RXT N31 N32 N35 N36 t(P PRCS LPZR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GENBKR1 GENBKR2 BUS11A BUS11B BUS12A BUS12B B11A12A BiiB12B PCV LSINPA LO942E LO943E LO942D LO943D LO942C LO943C LO942B LO9438 LO942A LO943A TO409A TO41OA TO450 TO451 TAVGAWID TAVGBMID LRV TCCGRE FAUXFWA FAUXFWB BKRO81 BKR082 V35OS V3504 DESCRIPTION ANTICIPATED TRANSIENT W/0 SCRAM REACTOR TRIP BREAKER STATUS SmSCE RANGE DETECTOR N-31 SolSCE RWGE DETECTOR N-32 INIEI(MEDIATE RANGE DETECTOR N"35 INTERMEDIATE RANGE DETECTOR N-36 AVERAGE NIKLEAR PONER REACTOR COOLANT SYSTEM AVG PRESS PRESSURIIER AVERAGE LEVEL REACTOR CGOL@T LOOP A AVG FLOW REACTOR COOLANT LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCGRE TC SUBCOOLED MARGIN STM GEN A tQRROM RAt(GE AVG LEVEL STM GEt(B NARROW RANGE AVG LEVEL STM GEN A AVERAGE PRESSURE STM GEN B AVERAGE PRESS)RE GEtGQTOR ON LINE BREAKER 161372 GESITOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BREAKER BUS 11B RFPLY BREAKER NGT TERMINATED Ott PPCS (7/19/91)NOT TERMINATED ON PPCS (7/19/91)BUS iiA TO 12A TIE BREAKER BUS 11B TO 12B TIE BREAKER CONTAIeENT AVERAGE PRESSURE CONTAINMENT SUt(P A AVERAGE LE4EL SU)P B LEVEL 8 INCHES (TRAIN A)SUtP B LEVEL 8 INCHES (TRAIN B)SU)P B LEVEL 78 IN&KG (TRAIN A)SU)P B LEVEL 78 INCHES (TRAIN B)SU)P B LEVEL 113 INCHES(TRAIN A)SUtP B LEVEL 113 INCHES(TRAIN B)SU)P B LEVEL 180 INCHES(TRAIN A)SUtP 0 LEVEL 180 INCHES(TRAIN B)SU)P B LEVEL 214 INCHES(TRAIt< A)SU)P 0 LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TEMPERATURE RCLB HGT LEG TEMPERATURE RCLA Col.D LEG TE)IPERATlRE RCLB COLD LEG TE)IPERATISE RCU)TAVG (THOT/TCOLD WIDE RNG)RCLB TAVG (THOT/TCOLD WIDE RNG)RECTOR VESSP AVERAGE LEVEL Ei.i INCORE TC AVERAGE TEMP S/6 A TOTAL AUX FEEDWATER FLW S/G 8 TOTAL AUX FEEDWATR FLOW MTR AUXILIARY FEEDWATER PU)IP A t(TR AUXILIARY FEEDWATER PUt(P 0 AUX FW PUIIP STEA)I SUPPLY VALVE A AUX FM PUI(P STEA)l Sl)PPLY VALVE B VALUE ATNS RX TRIPPED 7.95241+01 8.5802M)1 1.01391-11 1~01391-11.00 767.60.0 13.3 116.0 TRIPPED NOT TRIP 122.9 18.8 S6.2 768, 202.TRIPPED TRIPPED TRIPPED TRIPPED NGT TRIP NOT TRIP NOT TRIP NOT TRIP-.34 2.6 LONER LONER LONER LONER LONER LONER LONER LONER LONER LONER 392.7 392.9 391.2 391.1 392.0 392.0 99.3 392.7 O.86.OFF ON CLOSED CLOSED ALRII ALR)(GOOD 6000 6000 6000 GOOD 6000 HWRN INHB 6000 ALRN 6000 600i LMRtl 6000 6009 LAL)I ALRN ALRI(ALRt(ALRN DEL DEL ALRN ALRtf 6009 HWRI(6000 GOOD 6000 6000 GOOD 6000 6000 6000 6009 6000 GOOD 6000 GOOD 6000 GOOD 6000 6000 Goo'009 6000 6009 6000 GOOD 6000 E.U.CPS CPS AMP At(P/PSI6 I/y.DEGF X X PSIG PSIG PSI6 FKT DEGF KGF DEGF DE6F DEGF KGF KGF IPM GPM OCT 8~1992 12:45 R.E.GINA SIRLATOR TREND GROUP ASSIGNNENT RNNRY PA6E 2 GROUP!EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION 53 FSIA SAFETY INJECTION'LKP A AVG FLOW 54 FSIB SAFETY INJECTION LOOP B AVG FLIN 55 P2160 SERVICE MATER PlIPS A h B HEADER 56 P2161 SERVICE MATER PIIPS C h 9 HEADER 57 BKR041 SERVICE MATER PlmP A 58 BKR042 SERVICE WATER PSF B 59 BKR043 SERVICE MATER PNP C 60 BKR044 SERVICE MATER PlIP D OFF ON ON ON 0.0.72.80.OVAL E.U.GOOD GPN GOOD IF'00 D PSIG GOOD PSIG GOOD GOOD 600D GOOD ROGRAM NAME:LRGTSZ~E~~R.E.GIHNA NUCLEAR POWER PLANT OCT 08,92 12 45 00 TREND GROUP ASSIGNMENT

SUMMARY

GROUP NAME EVENT 2 GROUP DESCRIPT ION PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 12 13 14 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 0-F0619 LRWST WS033 WD033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R15 R12A5 R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLIHG LOOP TOTAL FLW REFUELING'WATER STORAGE TANK LVL 33 FOOT LEVEL WIND SPEED 33 FOOT LEVEL WIHD DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEMPERATURE 250 TO 33 FOOT LEVEL DELTA TEMP AREA 1-CONTROL ROOM AREA 2-COHTAINMEHT AREA 5-SPEHT FUEL PIT AREA 9-LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PAHEL CONTAINMEHT IODINE MONITOR R10A CONTAINMENT AIR PARTICULATE CONTAINMENT GAS MONITOR PLANT VENT IODINE MONITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID WASTE DISPOSAL MONITOR STEAM GENERATOR SLOWDOWN DRAIN AREA 29-COHTAINMEHT HIGH RANGE AREA 30-CONTAINMENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMHA CV VENT CHAN 7-MID RANGE GAS CV VENT CHAN 9-HIGH RAHGE GAS PLANT VENT CHAN 5-LOW RAHGE GAS PLANI'ENT CHAN 7 MID RAHGE GAS=PLANT VEHT CHAN 9-HIGH RANGE GAS AIR EJECTOR CHAH 5-LOW RANGE GAS AIR EJECTOR CHAN 7-MID RAHGE GAS AIR EJECTOR CHAN 9-Ml RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE B (SPING)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEMP¹10 CV OPERATING LVL 6 FT TEHP¹17 1485~94.5 8.7 65.66.0 67.8 1.8 9.02214-02 7.35678+00 1.39946+00 1~22501+02 9.09354-01 1.09283i00 9.58719+01 5'8901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 1.02474+04 5.05861-01 5.09440.01 1.57835+03 1.89699-07 2'3990.02 3.57435-05 1.41261-03 4.40312-07 6.86543-05 3.72621-03 2.09411-07 1.34492-05 1.27941.03 2.16040+00 1.01048-02 ~0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD BALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM x MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H MR/H CPM CPM CPM CPM CPM CPM CPM CPM R/HR R/HR CPM UCI/CC MR/NR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/NR MR/NR X DEGF DEGF DEGF DEGF DEGF DEGF Time:~1QQ Message:~1 INNA TATION 1 2 EVALUATED EXER I E IVIE SA E F RM I: C I<<C<<IR Simulated Plan Conditions: See the Attached Sheets M~e sacaS: """THIS IS AN EXERCISE""" FOR CONTROLLER USE ONLY~CI I R 1)Accident evaluation and response continues. Antici a ed Results;1)Recovery/Re-entry and declassification discussions should commence per the guidance provided in EPIP 3-4,"Emergency Declassification and Recovery." Discussions should also include but not be limited to the following; a)Preliminary discussions between the EOF and the TSC on the following: ~Short term Plant concerns such as: 1.2.3.4.Cooldown and depressurization of the Plant.Repair and-return to service of the"A" CCW Pump to ensure a redundant pump for decay heat removal.Repair and return to service of the" A" Service Water Pump.Repair and return to service of the Natural Gas line to the Screenhouse. Note: An evaluation of this event may lead to a discussion not to return Natural Gas to the Screenhouse, (continued on next page) 5.Continued evaluation of the drilled hole in the"B" S/G ARV.~Intermediate term Plant conditions such as: 1.2.3.4."A" S/G Tube inspection and repair.Possible"B" S/G Tube inspection."A" S/G Tube rupture evaluation for root cause.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 EOF/TSC and offsite agencies should be demonstrated as time allows. 199P EVALUATED EXERCISE Time: ISO'AZOR P20&METERS ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 N GPM FI-925~GPM 1A INSERV TB OOS 1B.INSERV B OOS 1C INSERV TB OOS BAST Level=~1 Low Head S.I.Pum s FI-626 O GPM 1A.INSERV TB OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=3.Containment S ra Pum s FI-931A O GPM FI-931B&GPM 1A.INSERV T OOS 1B.INSERV TB OOS NaOH Tank Level='F Containment Recirc Fans lA.SE STBY OOS 1B.SE STBY OOS 1C.NSE STBY OOS 1D.NSER STBY OOS Post Accident Dampers PEN CLOSED Service Water Pum s 1A.IN RV STBY 0 1B.NSE STBY OOS 1C.ER STBY OOS 1D.NSERV STBY OOS A&B Header Pressure 7~'0 PSIG DIESEL GENERATORS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s Reactor Shutdown E NO N-31 CPS N-32~CPS N-35-s(AMPS N-36 AMPS Avg.Nuclear Power 0 RCS Pressure~@i PSIG PRZR Level 3).a A RCP RUNNING TOPP B RCP UNNIN STOPPED 1A S/G Level 27.1 1B S/G Level 1A S/G Pressure PSIG 1B S/G Pressure l7 PSIG Turbine/Generator ONLINE FFLI 4 KV Buses NERGIZED DEE RGIZED 480V Buses NERGI E DEENERGIZED DC Batteries AI3o VOLTS BI30 VOLTS Cnmt Pressure 3'SIG Cnmt Sump A Level 2.7 FEET Cnmt Sump B Level~(INCHES A Loop Hot Leg~SPOOF A Loop Cold Leg~3I 70F.B Loop Hot Leg OF B Loop Cold Leg 3t/.s OF RVLIS'~/*CET~~..9'F S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow a GPM ENGINEERED SAFEGUARDS Aux.Feedwater Pum s 1A.NSE STBY OOS 1B.NSER STBY OOS Turb.Driven INSERV TB OOS 1A.INS STBY 0 1B.NSER STBY OOS Surge Tan Level=~i~4 Standb Aux.Fe water Pum s 1C.INSERV STB OOS 1D.INSERV STB OOS CST Level~/F*CET=Average of Selected Core Exit Thermocouples Gs 1992 13:00 R.E.GINA SltmLATOR PAGE 1 TREND GROUP*ASSIGN)(Et(T SU)IARY GROUP!EVENT1 PRXED(IE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E.U.1 2 3 4 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 ATl6 RXT N31 N32 N35 N36 NP PRCS LPLR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB GENBKRl GBIKR2 BUSllA BUS11B BUS12A BUS12B Bl lA12A B11B129 PCV LS(IPA L0942E L0943E L0942D L0943D L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAMID TAVGBWID LRV TCCORE FAUXFMA FAUXFMB BKR081 BKR082 V3505 V3504 ANTICIPATED TRANSIENT M/0 SCRN REACTOR TRIP BREAKER STATUS SmmCE RANGE DETECTOR N-31 SmnCE RA%E DETECTOR N-32 INTERNEDIATE RANGE KfECTOR N-35 INTERNEDIATE RANGE DETECTOR N-36 AVERAGE NLQZ8 POMER REACTOR COOLANT SYSTB(AVG PRESS PRESSURIlER AVERAGE LEVEL REACTOR COOLNT LOOP A AVG FLOM REACTOR COOLNI'OOP B AVG FLOM RCPA BRENER CAUSE RX TRIP RCPB BREAKER CAUSE RX TRIP INCORE TC SUBCOOLED t(ARGIN STtt 6Bl A NARROM RA%E AVG LEVEL STN GEN B NARROM RAtlGE AVG LEVEL STt(GB(A AVERAGE PRESSURE STN GEN B AVERAGE PRESSURE GEtGQTOR ON LINE BREAKER 161372 GENERATOR ON LINE BRENER 9Xf372 BUS 11A SLPPLY BREAKER BUS 11B SUPPLY BREAKER NOT TERNINATED Ott PPCS (7/19/91)tloT TERt(lt(ATED ON PPCS (7/19/91)BUS 11A TO 12A TIE BREAKER BUS 11B To 12B TIE BREAKER CONTAINtiENT AVERAGE PRESSURE CONTAItlt(B(T PJt(P A AVERAGE LEVEL SIP B LEVEL 8 INCHES (TRAIN A)SUtP B LEVEL 8 It(CHES (TRAIN 9)SU)P B LEVEL 78 INCHES (TRAIN A)SU)P B LEVEL 78 IN&KG (TRAIN B)SUtP B LEVEL 113 INCHES(TRAIN A)SU)P B LEVEL 113 INCHES(TRAIN B)SU)P B LEVEL 180 INCHES(TRAIN A)SU)P 8 LEVEL 180 INCHES(TRAIN B)SUtP B LEAL 214 INCHES(TRAIN A)SU)P B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TB(PERATUfK RCLB HOT LEG TEt(PERATURE RCLA COLD LEG TB(PERATNE RCLB COLD LEG TB(PERAT(RE RCLA TAVG (THOT/TCOLD MIDE RNG)RCLB TAVG (THOT/TCOLD MIDE RNG)REI:TOR VESSEL AVERAGE LEVEL El~1 INCORE TC AVERAGE TBP S/6 A TOTAL AUX FEEDMATER FLOM S/G B TOTAL AUX FEEDMATER FLON NTR AUXILIARY FEEDMATER PUt(P A t(TR AUXILIARY FEEDMATER PUlP B AUX FM PUttP STEAN SUPPLY VALVE A AUX FM PU!P STBI SUPPLY VALVE B'I RX TRIPPED 8.40424+01 8.60992+01 1.01391-11 1.01391-11 F 00 646, 31.5 13.5 116.7 TRIPPED NOT TRIP 113.2 28.7 55.4 615.174.TRIPPED TRIPPED TRIPPED TRIPPED NOT TRIP NOT TRIP NOT TRIP NOT TRIP-.36 2.7 LONER LONER LONER LONER LONER LONER LONER LONER LONER LONER 385.9 383.7 381.7 381.5 383.8 382.6 99.1'382.9 53 I 24.ON ON CLOSED CLOSED Goon 6009 6009 600D 6009 GOOD 6009 INHH 6009 ALRt(6009 600~LMRtt Goon 6009 LALN AUI ALRt(6009 GOOD 6009 6009 GOOD 6009 Goon GOOD GOOD GOOD 600D Goon 6009 6009 6009 6009 GOOD 600~6009 GOOD 6009 6009 Goon CPS CPS I(P Al(P 0/PSIG X y.7 DEGF X/PSIG PSIG DEGF D""BF DEGF DEGF IEGF DEGF X DE6F GPt(GPt(w-AD%3 OCT 8~1992 13l00 R.E.GINA SIMULATOR TREND GROUP ASSIGNMENT

SUMMARY

PAGE 2 6ROUP: EVENTI PROCEDURE: EPIP 1-5 PLAtIT STATUS POINT ID DESCRIPTION VALUE QUAL E.U.53 FSIA 54 FSIB 55 P2160 56 P2 161 57 BNR041 58 ImR042 59 BKR043 60 IIR044 E+J SAFETY INJECTION'LOOP A AVG FLOW SAFETY INJECTION LOOP B AVG FLOW SERVICE WATER PNFS A h B HEADER SERVICE WATER PNFS C h D HEADER SERVICE WATER PNF A SERVICE WATER PNF B SERVICE WATER PNF C SERVICE WATER PNF D OFF ON ON ON 0.0.72.80.GOOD GPM GOOD GPM 600D PSIG GOOD PSI6 GOOD GOOD 600D GOOD ROGRAH NAHE:LRGTSZ.E R.E.GINNA NUCLEAR POWER PLANT OCT 08,92 13:01:00 TREND GROUP ASSIGNHENT SUMHARY GROUP NAHE EVEHT 2 GROUP DESCRIPTION PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 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 0 J F0619 LRWST WS033 W0033 WT033 WT250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R108 R13 R14 R18 R19 R29 R30 R15 R12AS R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCV08 TCV09 TCV10 TCV17 COMPONENT COOLING LOOP TOTAL FLW REFUELING'WATER STORAGE TANK LVL 33 FOOT LEVEL WIHD SPEED 33 FOOT LEVEL WIND DIRECTION 33 FOOT LEVEL TEHPERATURE 250 FOOT LEVEL TEHPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1-CONTROL ROOM AREA 2-COHTAINHENT AREA 5-SPENT FUEL PIT AREA 9-LETDOWN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PANEL CONTAINMENT IODINE MONITOR R10A COHTAINHENT AIR PARTICULATE CONTAINHENT GAS MONITOR PLANT VENI'OOIHE MOHITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS MONITOR LIQUID WASTE DISPOSAL HONITOR STEAM GENERATOR BLOWDOWN DRAIN AREA'9.CONTAINHEHT HIGH RANGE AREA 30-CONTAINHENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOW RANGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-HID RANGE GAS CV VENT CHAN 9-HIGH RANGE GAS PLANT VENT CHAN 5-LOW RANGE GAS PLANT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAN 9.HIGH RAHGE GAS AIR EJECTOR CHAN 5-LOW RANGE GAS AIR EJECTOR CHAN 7.MID RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 31 STEAM LINE A (SPING)AREA 32 STEAM LINE B (SPING)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEHP¹3 CV INTERHEDIATE LVL 6 FT TEHP¹7 CV INTERMEDIATE LVL 6 FT TEHP¹8 CV INTERMEDIATE LVL 6 FT TEMP¹9 CV INTERMEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEHP¹17 1485.94.5 8.7 65.66.0 67.8 1.8 9.02214-02 7.35678+00 1.3994&00 1.20701+02 9.09354-01 1.09283+00 9.58719+01 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658+03 9.90174+03 5'5861-01 5.09440-01 1.57835+03 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312.07 6.86543.05 3.72621-03 2.09411-07 1.34492-05 1.27941-03 1.93040+00 1.01048.02 .0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOGO KALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALH GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPH x MPH DEG.DEGF DEGF DEGF MR/H MR/H MR/H MR/H MR/H HR/H CPM CPH CPH CPM CPH CPH CPM CPM R/HR R/HR CPM UCI/CC MR/HR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/HR HR/HR DEGF DEGF DEGF DEGF DEGF DEGF Time:~1~1 Message:~2 SIINNA ATATI~1992 EVALUATED EXERCI E MESSAGE FORM~NI: 8 I<<N NA Simula ed Plan Condi ions: See the Attached Sheets~Messs e: """THIS IS AN EXERCISE""" The Exercise is Terminated. FOR CONTROLLER USE ONLY Controller Notes: 1)Deliver when all Exercise objectives have been demonstrated. Antici ated Results: 1)Close out by making an announcement to all facilities (including REGS)that the Exercise is terminated. 199P EVALUATED EXERCISE Time: I 3 l~MAJOR PARAMETERS ENGINEERED SAFEGUARDS 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 DC Batteries A/Sb Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level A 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 ES NO~~CPS~OCPS g.OE-II AMPS Ass'->I AMPs$3O PSIG&RUNNING TOPP UNNIN STOPPED~s.o&~~PSIG/z.(r PSIG ONLINE FFLIN ERGIZE DEENERGIZED ERGIZE DEENERGIZED VOLTS B/B~'VOLTS -.3g PSIG 2..7 FEET~(INCHES OF SS 2.OF 3'F/ST'F OF V$" 9'F Flow 88 GPM Flow 2-9 GPM OOS A.RUNNING UNLOADED TB OOS B.RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED ENGINEERED SAFEGUARDS Hi h Head S.I.Pum s FI-924 O GPM FI-925 C)GPM 1A.INSERV T OOS 1B.INSERV T OOS 1C.INSERV B OOS BAST Level=/O Low Head S.I.Pum s FI-626 GPM 1A.INSERV OOS RECIRC 1B.INSERV TB OOS RECIRC RWST Level=9'3.Containment S ra Pum s FI-931A GPM FI-931B N GPM 1A.INSERV T OOS 1B.INSERV TB OOS NaOH Tank Level=Containme ecirc Fans 1A.SERV STBY OOS ost Accident Dampers Service Water Pum s 1A.INSE V STBY OS 1B.NS R STBY OOS 1C.NSERV STBY OOS 1D.NSER STBY OOS A&B Header Pressure V~0 PSIG Com onent Coolin Water Pum s 1A.INSERV STBY 0 1B.NSERV STBY OOS Surge Tau Level=~d 1B.SERV STBY OOS lc.SE STBY OOS 1D.NSERV STBY OOS P OPE CLOSED Standb Aux.Feedwater Pum s 1C.INSERV STB OOS 1D.INSERV TB OOS Aux.Feedwater Pum s 1A.SE STBY OOS 1B.NSE STBY OOS Turb.Driven INSERV TB OOS CST Level~FE T*CET=Average of Selected Core Exit Thermocouples

81 1992 13:16 R.E.GINA Sft(ULATOR TREND GROUP ASSIGN>(Et(T SUI(ARY PAGE 1 GROUP: EVENT1 PROCEDURE: EPIP 1"5 PLANT STATUS POINT ID DESCRIPTION E.U.1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 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 tG6 NP PRCS LPLR FRCLA FRCLB RXT16 RXT17 TSUBTC LSGA LSGB PSGA PSGB BBSKRI GBSKR2 BUS11A BUS118 BUS12A BUS12B B11A12A B11B12B PCV LSiNPA L0942E L0943E L0942D L09439 L0942C L0943C L0942B L0943B L0942A L0943A T0409A T0410A T0450 T0451 TAVGAWID TAVGBWfD LRV TCCORE FAUXFWA FAUXFWB BKRO81 BKR082 V3505 V3504 ANTICIPATED TRANSIENT W/0 SCRN REACTOR TRIP BREAKER STATUS SolsCE RANGE DETECTOR N-31 So(ICE RANGE DETECTOR N-32 INTERt(EDIATE RANGE DETECTOR N-35 It(TER>(EDIATE RANGE DETECTOR N-36 AVERAGE NUCLEAR POWER REACTOR COOLANT SYSTEtl AVG PRESS PRESSURIIER AVERAGE LEVEL RECTOR COKAVT LOOP A AVG FLOW REI:TOR COOLW(T LOOP B AVG FLOW RCPA BREAKER CAUSE RX TRIP RCPB BREAKER CAUSE RX'IHIP INCORE TC SUBCOOLED t(ARGIN STt(GEtt A NARROW RANGE AVG LEVEL STN GEN B NARROW RANGE AVG LEVEL STt(GEt(A AVERAGE PRESSURE STt(GEN B AVERAGE PRESSURE GBERATOR ON LINE BREAKER 161372 GBERATOR ON LINE BREAKER 9X1372 BUS 11A SUPPLY BS(ER BUS liB SliPPLY BREAKER t(OT TERt)lt(ATED ON PPCS (7/19/91)NOT TERNINATED ON PPCS (7/19/91)BUS 11A TO 12A TIE BRENER BUS 11B TO 12B TfE BREA((ER CONTAIN)(ENT AVERAGE PRESSURE Cot(TAIttt(EtIT SUt(P A AVERAGE LEVEL SiRP B LEVEL 8 INCHES (TRAIN A)SUtP B LEVEL 8 INCHES (TRAIN 9)SU>P B LEVEL 78 INCHES (TRAIN A)SU)P B LEVEL 78 INC)XS (TRAIN B>SU>P B LEVEL 113 INCHES(TRAIN A)SU)P B LEVEL 113 INCHES(TRAIN B)SU)P B LEVEL 180 INCHES(TRAIN A>SU)P B LEVEL 180 INCHES(TRAIN B)SIP B LEVEL 214 INCHES(TRAIN A)SU>P B LEVEL 214 INCHES(TRAIN B)RCLA HOT LEG TEt)PERATUR= RCLB HOT LEG TEt(PERATUfK RCLA COLD LEG TPiPERAT(HE RCLB COLD LEG TEt(PERAT(SE RCLA TAVG (THOT/TCOLD WIDE RNG)RCLB TAVG (THOT/TCOLD WIDE RNG)REACTOR VESSEL AVERAGE LEVEL El.1 INCORE TC AVERAGE TEt(P S/G A TOTAL AUX FEEDWATER FL(I S/G B TOTAL AUX FEENA7R FLOW t(TR AUXILIARY FEEDWATER PUt(P A t(TR AUXILIARY FEEDWATER PUt(P 9 AUX FN PlNP STEA)f SUPPLY VALVE A AUX FW PUt(P STEAtf SUPPLY VALVE B ATWS RX TRIPPED 8.40424+01 8.03523+01 I.Oi39f-ff 1.01391"ii .00 530.32.4 13,6 118.6 TRIPPED NOT TRIP 116.5 30.0 34.4 525.126.TRIPPED TRfPPED TRIPPED TRfPPED NOT TRIP NOT TRIP NOT TRIP NOT TRIP-.38 2.7 LONER LONER LONER LONER LONER/ONER LONER LONER LONER LONER 360.3 359.8 358.2 357.9 359.3 358.9 98.9 359.4 55.23.ON ON CLOSED CLOSED ALfm ALRt(6009 6009 6009 GOOD 6009 6009 6009 INHB 6009 ALR)(6009 600~LWRN Goon LWfi LALN ALRt(ALRtj ALRtl ALRt(DEL DEL ALfm ALRt{6009 HWRt(Goon 6009 6009 6009 6009 Goon 6009 Goon 6009 6009 6009 6009 Goon 6009 GOOD 6009 Goo>GOOD 6009 6009 6009 6009 CPS CPS NP At(P PSIG X X DEGF X PSIG PSIG PSIG FFEf DEGF KGF DEGF DEGF DEGF DEGF X DEGF GP>(8't( XT 8~1992 13:ib R.E.GINA SINULATOR---TREND GMlUP ASSIGNBtT StNMY PAGE 2 6tm'VENTi PROCES'PIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE NNL E.U.53 FSIA 54 FSIB 55 P2160 56 P2161'57 Bt<R041 58 IaR042 59 BttR043 60 BttR044 SAFETY INJECTION LOOP A SAFETY INJECTION LOOP B SERVICE WATER PtNPS A 5 SERVICE WATER PtNPS C h SERVICE WATER PtNP A SERVICE WATER PUtP B SERVICE WATER PtNP C SERVICE WATER PtNP 0 AV6 FLOW AVG FLOW B HEADER D HEAXR OFF ON ON ON 0.600 D 0.600D 72.600D So.GOOD 600D 600D 600D 600D fPtt GPN PSIG PSIG E+J ROGRAM NAME:LRGTSZ.E R.E.GINHA NUCLEAR PONER PLANT OCT 08,92 13:14:00 TREND GROUP ASSIGNHENT

SUMMARY

GROUP HAME EVENT 2 GROUP DESCRIPTION PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 2 3 4 5 6 7 8 9 10 11 12 13 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 3 F0619 LRNST WS033 ll0 033 UT033 IH250 WDT2 R01 R02 R05 R09 R34 R35 R10A R11 R12 R10B R13 R14 R18 R19 R29 R30 R15 R12AS R12A6 R12A7 R12A9 R14A5 R14A7 R14A9 R15A5 R15A7 R15A9 R31 R32 CVH TCV03 TCV07 TCVOB TCV09 TCV10 TCV17 COMPOHEHT COOLING LOOP TOTAL FLIJ REFUELING MATER STORAGE TANK LVL 33 FOOT LEVEL llIND SPEED 33 FOOT LEVEL MIND DIRECTION 33 FOOT LEVEL TEMPERATURE 250 FOOT LEVEL TEHPERATURE 250 TO 33 FOOT LEVEL DELTA TEHP AREA 1 CONTROL ROOM AREA 2-CONTAINHENT AREA 5-SPENT FUEL PIT AREA 9-LETDONN LINE MONITOR AREA 34-AUX BLDG CV SPRAY PUMP AREA 35-PASS SAMPLE PANEL CONTAINMEHT IODINE MONITOR R10A CONTAINMEHT AIR PARTICULATE COHTAINHENT GAS MONITOR PLANT VENI'ODINE MOHITOR R10B AUX BLDG EXHAUST AIR PARTICULATE AUX BLDG EXHAUST GAS HONITOR LIQUID lJASTE DISPOSAL HONITOR STEAM GENERATOR BLONDOWN DRAIN AREA 29-CONTAINMEHT HIGH RANGE AREA 30-CONTAINMENT HIGH RANGE CONDENSER AIR EJECTOR EXHAUST CV VENT CHAN 5-LOU RAHGE GAS CV VENT CHAN 6-AREA GAMMA CV VENT CHAN 7-MID RAHGE GAS CV VENT CHAN 9-HIGH RAHGE GAS PLANT VENT CHAH 5 LOU RANGE GAS PLANT VENT CHAN 7-MID RANGE GAS PLANT VENT CHAN 9 HIGH RANGE GAS AIR EJECTOR CHAN 5-LOU RANGE GAS AIR EJECTOR CHAN 7-MID RANGE GAS AIR EJECTOR CHAN 9-HI RANGE GAS AREA 31 STEAM LINE A (SPIHG)AREA 32 STEAM LINE B (SPING)CV HYDROGEN CONCENTRATION CV BASEMENT LVL 6 FT TEMP¹3 CV INTERMEDIATE LVL 6 FT TEMP¹7 CV INTERMEDIATE LVL 6 FT TEMP¹8 CV INTERMEDIATE LVL 6 F'I TEHP¹9 CV INTERHEDIATE LVL 6 FT TEHP¹10 CV OPERATING LVL 6 FT TEMP¹17 1485.94.5 8.7 65'6.0 67.8 1.8 9.02214-02 6.40678+00 1.39946+00 '1.47701+02 9.09354-01 1.09283+00 9.58719101 5.18901+02 7.38002+02 4.30543+01 8.58327+01 4.22831+01 2.78658>03 1.57174+04 5.05861-01 5.09440.01 1.57835+03 1.89699-07 2.53990-02 3.57435-05 1.41261-03 4.40312.07 6.86543-05 3.72621-03 2.09411-07 1.34492-05 1.27941-03 1.87040+00 1.01048.02 .0 95.1 106.0 106.6 106.7 106.2 117.5 GOOD GOOD GOOD GOOD GOOD GOGO GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD BALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD HALM GOOD GOOD GOOD GOOD GOOD GOOD GOOD GOOD GPM x MPH DEG.DEGF DEGF DEGF MR/H MR/H HR/M HR/H MR/H MR/H CPM CPM CPH CPM CPM CPH CPM CPM R/HR R/HR CPM UCI/CC MR/NR UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC MR/MR MR/NR x DEGF DEGF DEGF DEGF DEGF DEGF SECTION 9.0 ONSITE RADIOLOGICAL AND CHEMISTRY DATA

SECTION 9.1 RADIOLOGICAL

SUMMARY

0 9.1 Radiolo ical Summa 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 accident scenario.Protective action recommendations i.e., sheltering or evacuation for certain Emergency Response Planning Areas (ERPAs)will not be required based upon the anticipated declaration of a Site Area Emergency and plant conditions. As a result of accident release rates, the projected whole body and thyroid doses will not 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 two release points which is from the Air Ejector and the"A" Atmospheric Relief Valve (ARV).This occurs as follows: Pre-Steam Generator Tube Rupture Time 0700-0915 Release Point Air Ejector Release Rate Ci/sec 1.77 E-3 (Noble Gas)*2.24 E-8 (Radioiodine)

• The noble gas-to-radioiodine ratio assumed in this scenario is 7.89E4:1 during the period of release.Time Release Point Release Rate Ci/sec 0755-0810 ARV 8.32 E-3 (Noble Gas)*1.05 E-7 (Radioiodine)
• The noble gas-to-radioiodine ratio assumed in this scenario is 7.89 E4:1 during the period of release.Steam Generator Tube Rupture Time 0915-0935 Release Point Air Ejector'elease Rate Ci/sec 5.24 E-1 (Noble Gas)*2.62 E-4 (Radioiodine)
• The noble gas-to-radioiodine ratio assumed in this scenario is 2000:1 during the period of release.Isotopic breakdowns of assumed noble gas, radioiodine and particulate release quantities are provided in Table 9.1.

Time Release Point Release Rate Ci/sec 0935-0955 Air Ejector 6.23 E-2 (Noble Gas)*.3.12 E-5 (Radioiodine)

• The noble gas-to-radioiodine ratio assumed in this scenario is 2000:1 during the 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 from the scenario release are as follows: Time Release Point lnte rated Dose Rem 0700-0915 0755-0810 0915-0935 0936-0955 Air Ejector ARV Air Ejector Air Ejector 1.25 E-4 (Whole Body)8.75 E-7 (Child Thyroid)6.52 E-5 (Whole Body)4.56 E-7 (Child Thyroid)5.34 E-3 (Whole Body)1 48 E-3 (Child Thyroid)6.51 E-4 (Whole Body)1.81 E-4 (Child Thyroid)Total Whole Body Dose (at Site Boundary)=6.18 E-3 Rem Total Child Thyroid Dose (at Site Boundary)=1.66 E-3 Rem C.Princi al Plant Radiolo ical Indications Figures 9.1 through 9.3 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: Nuclide Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Total Noble Gas Time: 0915-0935 hr Curie/Sec 4.0 E-04 1.3 E-02 1.8 E-02 2.1 E-02 4.9 E-03 3.3 E-01 4.9 E-02 4.9 E-02 1.6 E-02 6.3 E-02 5.2 E-01 Total Curies Released 4.8 E-01 1.7 E+01 2.3 E+01 2.5 E+01 5.9 E+00 4.0 E+02 5.9 E+01 5.9 E+01 1.9 E+01 7.6 E+01 6.3 E+02 I-131 1-1 32 I-1 33 l-1 34 1-1 35 7.8 E-05 1.3 E-05 5.4 E-05 8.6 E-05 3.1 E-05 9.3 E-02 1.5 E-02 6.3 E-02 1.0 E-01 3.7 E-02 Total Radioiodine 2.6 E-04 3.1 E-01 Long-Lived Particulate 1.2 E-09 1.5 E-06 TABLE 9.1 (continued) The assumed release quantities for the Ginna Exercise Scenario are summarized as follows: Time: 0936-0955 hr Nuclide Curie/Sec Total Curies Released Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-1 35 Xe-135m Xe-138 Total Noble Gas 4.8 E-05 1.5 E-03 2.1 E-03 2.5 E-03 5.8 E-04 3.9 E-02 5.8 E-03 5.8 E-03 1.9 E-03 7.5 E-03 6.2 E-02 5.8 E-02 1.8 E+00 2.5 E+00 3.0 E+00 7.0 E-01 4.7 E+01 7.0 E+00 7.0 E+00 2.3 E+00 9.0 E+00 7.5 E+01 l-1 31 l-1 32 l-1 33 1-1 34 I-1 35 6.3 E-06 1.5 E-06 6.5 E-06 1.0 E-05 3.7 E-06 1.1 E-02 1.8 E-03 7.8 E-03 1.2 E-02 4.4 E-03 Total Radioiodine 3.1 E-05 3.7 E-02 Long-Lived Particulate 1.4 E-10 1.7 E-07

FIGURE 9.1 ASSUMED SOURCE TERMS C 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 1.0E-10 1.0E-11 I/SEC 1 1 1 1 1 1 1 1 7 7 7 888889999990000 1 1 1 1 3450113401334501340134 0 5 5 0 0 5 0 5 0 5 0 6 5 6 0 5 0 5 0 5 0 5 CLOCK TIME 1 1 1 1 2 2 2 2 0 1 3 4 0505~NOBLE GAS CI/SEC~RADIOIODINE CI/SEC FIGURE 9.2 AIR EJECTOR VENT CONCENTRATIONS UCI/CC 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 1.0E-10 1.0E-1 1 1.0E-12 1 1 1 1 1 1 1'I 1 1 1 1 7 7 8 8 8 8 9 9 9 9 9 9 0 0 0 0 1 1 1 1 2 2 2 2 3 4 0 1 3 4 0 1 3 3 4 5'0 1 3 4 0 1 3 4 0 1 3 4 0 5 0 5 0 5 0 5 0 5 5 5 0 5 0 5 0 5 0 5 0 5 0 5 CLOCK TIME NOBLE GAS~RADIOIODINE FIGURE 9.3'CS CONCENTRATIONS VS TIME 1.0E+02 UCI/GM 1.0E+01 1.0E+00 1.0E-01 1 1 1 1 1 1 1 1 1 1 1 1 7 7 8 8 8 8 9 9 9 9 0 0 0 0 1 1 1 1 2 2 2 2 I 3 4 0 1 3 4 0 1 3 4 0 1 3 4 0 1 3 4 0 1 3 4 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 CLOCK TIME TOTAL GAS~TOTAL IOOINE

SECTION 9.2 IN-PLANT RADIOLOGICAL DATA MAPS 4)\ 0 0 D Ooor 25 ROCHESTER GAS AHD ELEC R'ZNNA STATZOH Servtea Budding DATE:~Kith TZME: 0 OO SURVEYED BY: SURVEY INST: SERZAL NUMBER: COUNTZNG ZHST: SERZAL NUMBER!(ONER:\(, D: g o A p~)'0~n-I~I A/9 0."'a 0 me~A~Door 24 0 Cl CI g C3 0 MR REMARKS: A=0.01 mR/hr (500 dpm/100cm> ALL READZHCS ZN MR/HR UNLESS OTMERHZSE NOTED

~...,~~-:mOO- ~<OO~SURVEY ZNSTRUNENT: SERIAL NUMBER: REMARKS: AREA SURVEYED: ROCHESTER GAS AND ELECTRIC GINNA STATION SERVICE BUILDING NORTH SURVEYED BY: COUNTING ZNSTRUMENT I SERZAL NUMBER POWER: LLD: RWP/SWP NUMBER: hXZ~I I C I eYS Wc~C.O YW I C-I'g.'II Gk.klhc.L. A=0.01 mR/hr<500 dpm/100cm2 ~Sj'3.IJ 4 J I'X J eII I eJ IE"Ar ff t i OR.Elbe,k. 2 J 2 IJ 2 0 I cC eJ Q 2 IJ e J I'l.I 2 X 2'2 2 4'2 CI 2 4J I eEI cj cd~READINGS ZN MRII'HR UNLESS OTlKRIIISI NOTED 9-/o

GG GC Q660 8 ROCHESTER GAS&ELECTR)C CORP GlNNA STAT)ON SERVICE BUILDING p~~yp Qt G A Surveyed By: Survey Meter: Serial Number: A=0.01 mR/hr<500 dpm/100cm2 Da~e:~i~i~W Time: k Power: SMEAR INFORMATlON Instrument: Serial Number: LLD: Smear¹d m/100cm2 I 5gi 0 h.-I o A I l I I I Remarks: 'Vv.9.'.(l;,;~~(C:(rh C f Z>)n-i'(.i)(~;x 'I (~-I.4+401 9'-//All readings are in mrlhr unless otherwise noted

~~'I I~~I I a I I I~~I I I I Ilail 1lm ill LllL~ ~~'~I I t Ig a I~~es l Ill balll Ill Ill l

I I I~~I I I I I~~stt tK I Ill'l l<m Lllllll 0 RG&E G INNA STATION TURBINE BUILDING MEZZANINE FLOOR SURVEY NAP 0700'-DATE: lCClR-TLHE: HDRTHlI ll Il il II A I I I oeee o ae4 A=0.01 mR/hr (500 dpm/100cm2 B=0.02 mR/hr~500 dpm/100cm2 C=0.02 mR/hr 850 dpm/100cm2 (on countertop of sample sink)DPA~I e en~5&lQlLSs II II~~LL ll g C 0 !IORTH tT il II Il il A RC&E CINNA STATION TURBINE BUILDING AEZ2ANINE 9'LOOR SURVEY NAP I I I eeee o eel CR5 DATE: L;IqE:~~)A=0.01 mR/hr<500 dpm/100cm2 8=0.80 mR/hr<500 dpm/100cm2 C=0.80 mR/hr 5000 dpm/100cm2 'on countertop of sample sink)uPNI avv A~~I II~A IILL Ll g CH'R C RC&E C INNA STATION TURBINE BUILDING AEZZANENE":LOOR SURVEY NhP NORTH I l II II I I I eeet o eeet A=0.01 mR/hr<500 dpm/100cm2 B=0.02 mR/hr<500 dpm/100cm2 C=0.02 mR/hr 5000 dpm/100cm2 (on countertop of sample sink)B Q 0 GPN/I.QQ Ci%A~~I I I II II~II II~I

NORTH RC6 E CINNh SThTION TURBI.iE BUILDINC BhSEHENT FLOOR SURVEY KKP A=0.05 mR/hr<500 dpm/$00cm2 B=0.02 mR/hr<500 dpm/100cm2 a ada 0 0 OOl~o ot~~~~~~~~~I~~o~~~~~~~oo~~~~~I~~~o OO G ,o B io Ip i a.a I I I A i os DhTEi 8 ll-Tm:~~~POVER i BY: INSTRUMENT: SERIhL I: SNEARS D?i~i/ICC Gn~4 8 NORTH RC&E CINNh STATION TVRBINE BUILDING BhSEMENT FLOOR, SVRVKY EXP A=0.01 mR/hr<500 dpm/100cm2 B=0.02 mR/hr<500 dpm/100cm2 4444 OOOO~Q E~~~~~~~~~~~'~g~~~~~~~1~t'~~O~~~~OO Q I I iO I io I-La.a cW(-QATE)(0 RX TIME'~lOO POMR!BY: INSTRUMENT: SERIAL 1: SMEARS DPMI'ICQ m 2 i CfrEE'~Au' NORTH RC6E GINNh SThTION TURBINE BUILDING BhSEMENT FLOOR SURVEY NAP A=0.01 mR/hr<500 dpm/100cm2 B=0.80 mR/hr<600 dpm/100cm2 oassa OO OO OO I I~t Q~~~~~~0~~~~~~~~~~y~O qt~~A DhTEs IOQ Q POWERs INSTRUMENT: SERIhL ft CA ib TTHR:~CR 0 BY: D?M/LCC Gn 2 I'rr.ir~j%i~~I'~lA)wd>"--l!>a r a OW p-go RENANCSs

R.E.GINNA STATION~~TEc vo>cat Suwena i C e eT~R SMEARS DPM/LOO cm;<K v DATE:~0 4~L TIME: GOO-CA(S POWER: BY: INSTRUMENT: ALL READINGS IN MR/HR UNLESS OTHERWISE NOTED A=0.01 mR/hr<500 dpm/100cm2 R.E.GINNA STATION'j'.Conderisati". Pcdhhln9;:;; BU!nBdinQ::,.:Contrcg 'pano'eI'rea ~'!il'!': u.s.t',ll,'Technician: Date: tb Time:~01 6-Gott/o Inst.Type:/Serial¹'s:/Power: LLD: Note: All readings are in mr/hr unless otherwise noted.II AtI A=0.01 mR/hr<500 dpm/100cm2 B=0.02 mR/hr<500 dpm/100cm2 C=0.02 mR/hr 850 dpm/100cm2 (on countertop of sample sink)No.etpmi100cm2 NaQH Tank H2S04 Tank To AVT Dl Room.Sample Sink B Ano/rrsr Rod tlonitor A 6 AVT Control Panel H20 Heater Desk Door 28 Door 67 Door 19!¹=Smear Location Radiation Level'=Contact Reading echnician Remarks: BrQA:ew'.(t.-\'t-x-x-=Rad/Cont.Barrier Neutron Radiation Level I-I ("GA r k/-.-I~V.'o a'*~i ed t.~!r').~-Q'.<<t~~tO 0 0=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad..Area . LLD: R.E.GINNA'TATION ';"Co'nderisate'.,'.,:..l,'oils>In9,"-.'Bulldin'O.-'-"'.Contre'8,'; Paneal:A'rea','echnician: Date: 0 ('RW Time: CA&-'l 450 Inst.Type:-/Serial¹'s:/Power;Note: All readings are in mr/hr unless otherwise noted.A=0.01 mR/hr<500 dpm/100cm2 B=0.30 mR/hr No.dpm/100cm2 (AII (A II 5000 dpm/100cm2 (on countertop of sample sink)NoQH Tonk H2S04 Tonk To AVT Dl Room Sample Sink Ror trN'tet-~A 6 AVT Control Panel H20 Heater Door 28 Door 67 Door 19¹=Smear Location Radiation Level c=Contact Reading echnician Remarks:!\M-"r~=-x-x-=Rad/Cont.Barrier Neutron Radiation Level I g.'ur.')g t~v m t r.c.)C*i'.)ri Cont.Area High Cont.Area!Radiation Area High Rad.Area Locked High Rad.;Area

R.E.GINNA STATION:RCOn4eS'at8'",.FP'IIShfA'g,':,;Bulfdjig':,;"'>>"'"",Dem'jneraaljiear.'raea.' Technician: Date: RL Time: Q7~-OQ lS Inst.Type:/Serial¹'s: I Power: LLD: Note: All readings are in mr/hr unless otherwise noted.High Condensate Waste Tank Low Condensate Waste Tank ellfelt'oof 27 No.dpm/100cm2 B 0 D Demin Dilute NH4QH 0 0 Mixed C Demin Dilute NaQH Anion Regen B Demin Dilute H2SQ4 Cation Regen A Demin A=0.01 mR/hr<500 dpm/100cm2 B=0.02 mR/hr<500 dpm/100cm2 Smear Location Radiation Level r~c=Contact Reading echnician Remarks:<lime:~1k-.l rDD Inst.Type:/Serial¹'e: I Power: Li.o: Note: All readings are in mr/hr unless otherwise noted.High Condensate Waste Tank Low Condensote Waste Tank I>>I el'oor 27 I No.t dpm/100cm2 I 0 D Demin Dilute NH40H Mixed C Demin Dilute NaQH A Anion Regen 8 Demin Dilute H2S04 Cation Regen A Demin A=0.01 mR/hr<500 dpm/100cm2 B=0.80 mR/hr<500 dpm/100cm2 O¹=Smear Location Radiation Level c=Contact Reading echnician Remarks:-x-x-=Rad/Cont.Barrier Neutron Radiation Level Ar(r r Y~J2)tc 0-l~-t Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area

R.E.GINNA STATlON Technician: Date: Io I ll.Time:61co-A3t)inst.Type: Note: All readings are ln mr/hr unless ottterwise noted.-.i: QOOVI'$-'o dpm/100cm2 0 0 0 0 cv'Purge--->(---N A=0.01 mR/hr<500 dPm/1 00cm2 Containment R10A,11,12 CV Vent-->Plant Vent--->----R10B,13,14 0 0 0 0 0 0 A Purge Exhaust Fan o A o 8 Purge Exhaust Fan¹=Smear Location Radiation Level c=Contact Reading Technician Remarks: (tP-x-x-=Rad/Cont.Barrier Neutron Radiation Level>+i(ut=C IŽ(0 Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area

R.EeGINNA STATION.2%5:c'"jt <tglS'att@c~p'.g~+":ri~i~Lt:j~~e:

i."'~Cer;~~.y

i~@';%%Jr'Ya t t r:"~"Sq::tlag>,~'; Technician: Ttme:~000-IIO C)Inst.Type: I Power: LLD: Note: All readings are In mr/hr unless otherwise noted.No.dPm/100cmg A=0.0 t mR/hr<600 dpm/100cm2 A<---N Corltoinment A Purqe t:xhoust Fan 8 L 0 W 0 L R 0 A utjn 4 Sleon 8 Purge shousT rtst Ooar 57 ChernisTrT L<O OJ.Woler-sloroge Tonk 0 0¹=Smear Location Radiation Level c~Contact Reading echnician Remarks:-x-x-=Rad/Cont.Barrier~~Neutron Radiation Level J,;~&un 4'-.,;ri-(.)~C(C~h~Pic-i(.t)rr-k -~'t2-t Cont.Area High Cont.Area i Radiation Area High Rad.Area Locked High Bad..Area R.E.GINNA STATlON'~~rdglottINSSW" STottkg~RTa'aa'iiiT)~::::L'at'rtal-,-:.". Technician: Cate:~Ttma: 67CO-Cert~ inst.Type:/Serial¹'a: l pc~et.Note: All readings are in mr/hr unless otherwise noted.dpm/100cm2 B Main Steam--'>A Oi A=0.01 mR/hr<500 dpm/100cm2 8=0.05 mR/hr<500 dpm/100cm2 (--N Containment A Q 0 A Main Steam-->r W I I I I I I HHB Racttim Tonk 0 I I I I I I I A Ooor 45 A go Q¹=Smear Location Radiation Level c=Contact Reading , echnician Remarks: 't'Q'9;u~~t I (".(~I-->0-x-x-=Rad/Cont.Barrier Neutron Radiation Level Cont.Area r Q>>High Cont.Area+=Radiation Area Q High Rad.Area O Locked High Rad.Area R.EeGINNA STATlON Technician: Date: l0'Kl I'L Tirae:gil6-0<< Q Inst.Type:/Serial¹'a: i pew: LLD Note: All readings are ln mr/hr unless otherwise noted.No.dpm/100cm2 8 Main Steam-->l A I A=0.01 mR/hr<500 dpm/100cm2 B=3.0 mR/hr<500 dpm/100cm2 (--N Containment B A Main Steam-->0 I B c HHB Reottartt fora 0 I I I I A 000 f 45 go¹=Smear Location Radiation Level c=Contact Reading echnician Remarks:-x-x-=Rad/Cont.Barrier Neutron Radiation Level\4(>>'>>'k>l (r~(p(-'ic.uh(~i =~i E-tb Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad..Area R.E.GINNA STATION'<<A<<"'~>>(+;<<>>~+~>>'re>>>>')i';:<',re'>>>>r>> gz'dye 4jtt",*>>'~rr";t".V>>+% Technician: Date: I l1-Time:~-QOO Inst.Type:/Serial¹e l po: LLD: Note: All readings are in mr/hr unless otherwise noted.No.dpm1100cm2 B Main Steam-->I I A rlr r~C~r P I>>A=0.01 mR/hr<500 dpm/100cm2 B=0.3 mR/hr I<500 dpm/100cm2 (--N Containment A Main Steam-->I NS Rectorn 1onh 0 I I I I I I I I I I I A Door 45 A Ho Q¹=Smear Location Radiation Level c=Contact Reading echnician Remarks: (t;-i-x-x-~Rad/Cont.Barrier Neutron Radiation Level Cont.Area 0>>High Cont.Area+=Radiation Area Q>>High Bad.Area O Locked High Rad.Area R.E.GINNA STATlON::.'"'~~~Q~4%%~"P>%<~pa)'~~..<p4<+m~..:jm"".-+'.:: 'MOc'.":~<to,e.'-'~~a."kw~'~"'35F<t<'<e<'<'j)v Technician: pate: 0 l-Time:CQX)"MLS inst.Type: Note: Ail readings are in mr/hr unless otherwise noted.Cable--->Tunnel Entry 0 A=0.01 mR/hr<600 dpm/100cm2 B=0.05 mR/hr<600 dpm/100cm2 (--N No, dpm/100cm2 Door 36 Containment Turbine 0 Driven Aux.FW~<Pump---0 Door 37 Turbine Aux.PW-Pump Oil Tank)~ljlj A r-i D A So~o8 Chillers 0 Motor Driven Aux.FW Pumps-----"" 0 0 0 Q¹=Smear Location Radiation Level c=Contact Reading echnician Remarks:~lr=-(<-x-x-~Rad/Cont.Barrier~Neutron Radiation Level'~c Qt~u(~"i<=tC-'lie Cont.Area High Cont.Area!Radiation Area High Rad.Area Locked High Rad.Area R.E.GINNA STATlON Technician: i): u~2%'pb.>'e.;:,. ',.T Q~,"'>>p,>+'N~:+>: A,gj~ej+i>> ';>e'>'>r~9?~i~i~+<>>>>T>>>$ >>%~)'~'tntmtedfko. -":g~'-.IIt aeNat"k4vof fnst.Type:/Serial¹'s: Note: Ail readings are in mr/hr unless othertlvise noted.Power: Cable---)Tunnel Entry 0 O 0 A=0.01 mR/hr (500 dpm/100cm2 B=2.0 mR/hr<500 dpm/100cm2 d pm/100cm2 Door 36 A Containment Turbine Driven Aux.FW Pump---Door 37 0~~B)O 0 OO 0~c+>".,".'7w->~DO A~D So 3 o8 C hitters 0 Motor Driven Aux FW Pumps------- 0 0 0¹=Smear Location!Radiation Level c~Contact Reading echnician Remarks: k)c',i: s=-x-x-~Rad/Cont.Barrier Neutron Radiation Level A>M'l9 t'<-..i'r v vG Cc.C'i F-to I Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area R.E.GINNA STATKRI A=0.01 mRlhr<500 dpm/100cm2 Note: All readings are in ,hitarinadhte-: BiiMa9:.:: South;"-MezxeHns k.evel oats: tCIst t'L Time:~aCr-t/tao Serial¹'s:/Power: LLO: mr/hr unless otherwise noted.Door 46 Door 45 No.dpm/100cm2 Door 65 Control Point/Sign-in Desk Containment Passbos Nuclear j Sample j Room I Nuclear Sample Shed HEPA Fitters Door 503 echniclan Remarks: 'two"-(C.-'l ,Q¹=Smear Location Radiation Level I¹'c=Contact Reading T t4 v~t'tv'-Aha (C4 i r-.r,a.=C l~-l 0-x-x-=Rad/Cont.Barrier Neutron Radiation Level s Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area A=0.1 mR/hr<500 dpm/100cm2 B=10'-'R/hr<500 dpm/100cm2 ",;fnrtefinadfati'-',BiiMiij.'.,S{iuth;:= Mezz~I Lese}.'Rl i%Time: 455 lul roc to+Date: l0 Serial¹'s:/Power: LLD: (hr unless otherwise noted.Crol((Ooor 46 Ooor 45 ND.dpm/100cm2 Ooor 65 Control Point/Sign-in Oesk Containment Passbox Nuclear l Somple l'oom r I Nucleor Sample Shed HEPA Fillers Ooor 503;Qar=Smear Location Radiation Level'¹c=Contact Reading Technician Remarks: 8>"-Lt t'g'Ag (ut~t>G cc=((~-tO-x-x-=Rad/Cont.Barrier Neutron Radiation Level!0 Q>>+8=+Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Bad.Area R.E.GINNA STATION'ntermidiats SiRdln9 South',-Basement'evei A=0.01 IR/hr<500 dpm/100cm2 Date: lb I L Time:~b~oO l/00 Serial¹'s:/Power: LLD: Note: A/I readings are m mr/hr unless otherwise noted.Q Quot tgVt Ooor 38 No.dpm/100cm2 To Hot Shop<---Laundry Tanks 1A Hydrogen Recombiner Panels Containment Chemical Drain Tank H PA Chas cad/Spenl Fuel Pil, Skimmer Filler 8 Conlrolled Access Fans i e 0 I ,(Q¹=Smear Location l~=Radiation Level c=Contact Reading echnician Remarks: c-x-x-=Rad/Cont.Barrier Neutron Radiation Level I<<t r lr<<w(u+i t'~c'.Z=Zt-'tb 4 0=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area A=0.1 mR/hr<500 dpm/1 00cm2 B=100 mR/hr<600 dpm/100t:m2 A." fntermediati; Rdh8ns-South.-Basernera'evel Date: lO l~Time:~ASS IA opRr~rort Serial¹'s:/Ihr unless otherwise noted.Ooor 38 No.dpm/100cm2 To Hot Shop<---l.aundry Tanks lA A IB Hydrogen Recombiner Panels Containment Chemical Orain Tank H PA A iilrr sop Spent Fuel Pit Skimmer Filler Controlled Access Fans I A 6 ,V+¹=Smear Location!=Radiation Level Contact Reading echnician Remarks: 4t F-(t,-x-x-=Rad/Cont.Barrier Neutron Radiation Level (.~uc ice hc=(tC-t 4 0=+0=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area e R.E.GINNA STATION min'ated;Storage BuBdine Technician: Date: 9'L Time:QlQQ-4tDI-I inst.Type: Serial¹'s:/Power: LLD: Note: All readings are in mr/hr unless otherwise noted.A=0.05 mR/hr<500 dpm/100cm2 No.dpm/100cm2 Door 6l0 Slorage Racks Art>>stoa I SA LSA Slorage Racks RCP Molor R~0 I L v l P 0 0 R-X---X---X I o I I X Oecon Areo Slorage Racks I I Smear Location Radiation Level'c=Contact Reading echnician Remarks:-.x=()-:-'t'i-x-x-=Rad/Cont.Sarrier Neutron Radiation Level~Ci cc Pr t>tC.<hD>-~l Cr 3~4 0=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area 0 ..:.:;~:.8P'int;.'Fiiet"'M any" i)econ ptt Technician: Date: 'lolS RL Tiote:~~0-tWOQ inst.Type:/Serial rr'e: I Power: LLD: Note: All readings are in mr/hr unless otherwise noted.A=0.10 mR/hr<500 dpm/100cm2 No.dpm/100cm2 R-18 8----x--x----r--r---I X Oecon Pit X I X I I Drain X Q X X I X C A T W A K I X Spent Fuel Pit I X I X I X I X I X I X~Bridqe I X I X I r I X I X I X I X I X I X x CRS HEPA Filters I I'ro sre.m I~sor i-..--.-..Transfer Canal~sop New rvet Storaqe Areo chnlcian Remarks.Ct I Smear Location l Radiation Level¹c=Contact Reading'e-x-x-=Rad/Cont.Barrier Neutron Radiation Level h,~4-c;.0=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area 9-3B R.E.GINNA STATlON A=0.50 mR/hr<500 dpm/100cm2 .;:.:..Ru88ary Sultry,,OPerat@g,'k;ever -Nest End Date: lO 8 L Time: CQCO-(400 Serial¹'e: I Power: LLD: Note: All readings are in mr/hr unless otherwise noted.No.'pm/100crnR New Fuel Storage Door 29 A Og-CV Penetrolion ron 0 0 C C W H 0 0 0 RWST o OO Smear Location Radiation Level¹c=Contact Reading Technician Remarks: t f~'Cr C'ri'D ,'~C (c~h C>~-tG-x-x-=Rad/Cont.Barrier Neutron Radiation Level 0=+6=+Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area R.E.GINNA STATION':".'AuxIII&~~.'aiilfdInjp)itteimodfato. Legal:-.'-. infest End A=0.10 mR/hr<500 dpm/100cm2 Date: le'8 l Time:e7ee-gee Serial¹'a:/Power: LLD, Note: All readings are in mr/hr unless otherwise noted.A CVCS qQ hler No.~dpm/100cm2 A 8 CVCS~>~i~>~>C CVCS X X X X X i~~x I I X RWST A wGC Room An:Q>=Smear Location Radiation Level¹c=Contact Reading Technician Remarks: 'k':z=Z't~-t, k-x-x-=Rad/Cont.Barrier Neutron Radiation Level 00=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area I R.E'GINNA STATlON-A=0.10 mR/hr<500 dpm/100cm2

,';AUXIN~

BUffcQAQ.88$8ntent: LevEA'.@fest-End Date: 1't>K Time:gQd-IGLOO Serial¹'s:/Power: LLD: Note: All readings are in mr/hr unless otherwise noted.Art(B SFP PUMPS Na..dpm/100cm2 A CVCS--Ad(B RHR Fans X X e e te.I 8 CVCS QA 8 E A x Qa C CVCS RWST R E E ter C A Xt Lx-x-GS PIIP FK i~;(¹+=Smear Location Radiation Level I¹c=Contact Reading Technician Remarks:-x-x-=Rad/Cont.Barrier Neutron Radiation Level~/r A'crxv Ar siv ir<<C'e%Ql tA&t (v.<<tt-t l-IrQ Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area R.E.GINNA STATION'QxN~."',BUIding;'t Operating; L'eve(,t Date: Ct'tti(l>Ti tne:Q7gD t+DO A=0.10 IR/hl'500 dpm/100cm2 Serial¹'s:/Power: LLD: Note: All readings are in mr/hr unless otherwise noted.A Monitor Tonk~VV I A x I B I I I;g)xlot li';0 ggQ 0 RWST Bus 14 Door 26 1 ttpm/100cm2 B Monitor Tonk A Aux.Bldg.Supply A/H Unit RMWT ooooo~erettte 0 riroeesstno 0 Q Resin liner p p A BAST 8 8A BAST rater g ner 0 Door 28 Door 27 B A rretisems p~0'~+¹=Smear Location Radiation Level i¹c=Contact Reading , Technician Remarks: 'I, Zll--ttt c Mt(/>~iK rM&C l CC.-x-x-=Rad/Cont.Barrier Neutron Radiation Level cJ=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area R E.GINNA STATtON A=0.10 mR/hr (500 dpmI100cm2 Note: All readings are in AuxiHary::.SiiHdlrTS'fat8rmetHate,.Levd: -past aid Date: 'IQl 6 C.Ttrne:~QQOQ-(QOQ Serial¹'s:/Power: LLD.mr/hr unless otherwise noted.RWST No.'pm/100cm2 A GPT Bus 16 44 A I B GPT~oo A.'0 G Charcaaf/HERA riller C GPT , SDP p GOT 0 A ooOo RC filler Pl Vault VCT CHT Lo A O r I";¹)=Smear Location Radiation Level c=Contact Reading Fechnician Remarks: Ktwa.=~lE-lK<~>>((<r t=(l f=-lo-x-x-=Rad/Cont.Barrier Neutron Radiation l.evel Ah~C;1c~t Cont.Area High Cont.Area Radiation Area High Rad.Area l.ocked High Rad,:.Area R.E.GIKNA STATloN'Auxlli~" BQQdjnQ>'. 80$8Ntnf, Levg-A=0.10 mR/hr 4500 dpm1100cm2 Date: LO.L Time: CQ~-b5(5'erial ¹'s:/Power: LLp, Note: All readings are in mr/hr unless otherwise noted.N p dpm/100cm2 WHUr Pomp A a St Pumps~~~~~~e~e~~eee~~e~~~CS Pumps e gQQA Waste Holdup Tank miami, I X I X I=., Xjoe't-0 0 0 BR Ec WO A+9 Chorging Pump Cooling Fans A Non-regen Hx Sepr Retien t WEFT Oo rn~4 8~L R~t:0 rr 0~ou T.R Spent Resin Tank Room Sur e Tank~4 Chorging Pump Room Cl;~l NaoH'I e~e chntctan Remarks.~Dire=i'.¹~Smear Location Radiation Level'¹c=Contact Reading Te-x-x-=Rad/Cont.Barrier Neutron Radiation Level 7~!0 c<hit 5 VG/CCh I-Z iC-tO 0 00=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area 0 R.E.GINNA STATION A=0.1 mR/hr<500 dpm/100cm2 B=100 mR/hr<500 dpm/100cm2 Date: (0 Time: O'QQ--.',f ggg Serial¹'s:/r/hr unless otherwise noted.Power: LLQ.-':.Auxlllacy~ ByQdfii9;.':BiWfliBAf LeveIr dpml1OOcm2 Waste Holdup Tonk GA wHUT p Run O 0 X j BR Imii c wp xt'X I X WE XI 4'l 0 0 0 A A ArttIT Charging Pump Cooling Fans Sl Pumps~~~~~~~~~~~~~~~~>>~~~~~~~>>~~~~~8 A CS Pumps~A Non-regen Hx gJ Alc Q~Sect Return Oo Xt~~~B 8 8~t R~t:0 N a 4pu E R Spent Resin Tank Room Sur e Tank Charging Pump Room NOOH chntctan Remarks.'ve=(ll=-((.I~'t~¹=Smear Location Radiation Level~~~'¹c=Contact Reading Te t(t.)t cX'a tr--x-x-=Rad/Cont.Barrier~~Neutron Radiation Level r Y&wrrr&Alibi fr>>Ci r Ch Q>>+0=Cont.Area High Cont.Area Radiation Area High Rad.Area Locked High Rad.Area SECTION 9.3 IN.-PLANT AND POST-ACCIDENT SAMPLING RESULTS TABLE 9.2A Nuclide Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 Rb-88 REACTOR COOLANT SYSTEM Radioactive Gasses and lodines (Collection between 07:00-09:15)Concentration (pCi/gm)Corrected to time of Shutdown 2.88E-02 4.02E-02 4.66E-02'.51E-01 1.10E-01 3.72E-02 1.43E-01 2.62E-02 Gas Total 1.16E+00 1-1 31 1-1 32 l-1 33 l-134 1-135 3.20E-02 1.05E-01 4.18E-02 1.51E-01 7.55E-02 iodine Total 4.05E1 I-131 Dose Equivalent 4.7E-02 TABLE 9.2B RCS Gas Sample Nuclide Kr-85m Kr-87 Kr-88 Xe-133 Xe-135 Xe-135m Xe-138 Rb-88 REACTOR COOLANT SYSTEM Radioactive Gasses and lodines (Collection between 09:16-14:00)Concentration (pCi/gm)Corrected to time of Shutdown 2.88E-01 4.02E-01 4.66E-01 7.51E+00 1.10E+00 3.72E-01 1.43E+00 2.62E-01 Gas Total 1.16E+01 RCS Gas Sample Dose Rate (based on 35cc sample)1 meter=0.195 mR/hr 1 foot=2.44 mR/hr On contact=1.95 R/hr RCS Liquid Sample Nuclide I-1 31 I-1 32 I-1 33 1-134 I-135 Concentration (pCi/gm)Corrected to time of Shutdown 2.72E-01 1.76E-01 1.65E-01 1.51E-01 1.53E-01 Iodine Total 9.17E-01 I-131 Dose Equiv 3.10E-01 RCS Liquid Sample Dose Rate (based on 12cc sample)1 meter=<0.01 mR/hr 1 foot=0.06 mR/hr On contact=52.8 mR/hr TABLE 9.3A Nuclide I-131 I-132 l-133 I-134 I-135 Cs-134 Cs-137 STEAM GENERATOR (Collection between 07:00-09:15)Concentration (pCi/gm)Corrected to time of Shutdown eIAee~I Bee 3.78E-05 1.62E-07 1.35E-05 6.33E-07 4.65E-05 1.03E-06 1.56E-04 5.85E-07 8.73E-05 1.22E-06 3.27E-06 4.64E-08 2.96E-06 7.20E-08 TOTAL ACTIVITY 3.47E-04 3.75E-06 Sample Dose Rates (based upon 3500cc sample)I IAI I 1 meter<0.01 mR/hr 1 foot<0.01 mR/hr On contact 5.83 mR/hr I I 8 I I<0.01 mR/hr<0.01 mR/hr<0.01 mR/hr TABLE 9.3B Nuclide I-131 I-132 I-134 I-1 35 Cs-1 34 Cs-1 37 STEAM GENERATOR (Collection between 09:16-13:00)Concentration (pCi/gm)Corrected to time of Shutdown~I All 2.8E-02 1.8E-02 1.7E-02 1.5E-02 1.5E-02 2.9E-04 Il Bl~5.93E-05 5.38E-06 2.56E-05 3.13E-06 1.87E-05 TOTAL ACTIVITY 9.33E<2 1.12E-04 Sample Dose Rates (based upon 1000cc sample)I IAI I 1 meter 0.045 mR/hr 1 foot 0.56 mR/hr On contact 449 mR/hr IIBII<0.01 mR/hr<0.01 mR/hr 0.538 mR/hr TABLE 9.4A AIR EJECTOR (Sample collection between 07:00-09:15)Nuclide Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Concentration (pCi/gm)Corrected to time of Shutdown 5.59E-03 5.26E-03 9.21E-03 1.38E-02 9.87E-02 2.40E-03 3.95E-02 6.25E-03 2.67E-02 TOTAL GAS 2.07E-01 35cc Sample Dose Rate on contact=35 mR/hr Dose Rate at 1 foot=0.04 mR/hr Dose Rate at 1 meter=<0.01 mR/hr Flowrate=0.21 cfm TABLE 9.4B AIR EJECTOR (Sample collection between 09:16-09:35)Nuclide Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Concentration (pCi/gm)Corrected to time of Shutdown 3.72E-02 1.18E+00 5.06E-01 1.91E+00 4.53E-01 3.96E+01 4.76E+00 4.73E+00'I.73E+00 5.97E+00 TOTAL GAS 5.65E+01 Dose Rate on contact=1.0E+04 mR/hr*Dose Rate at 1 foot=11 mR/hr*Dose Rate at 1 meter=1 mR/hr**assumes a 35 cc sample TABLE 9.4C AIR EJECTOR (Sample collection between 09:36-09:55)Nuclide Kr-85'r-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Concentration (pCi/gm)Corrected to time of Shutdown 4.87E-03 1.55E-01 6.62E-02 2.50E-01.5.93E-02 4.03E+00 5.97E-01 5.93E-01 2.00E-01 7.68E-01 TOTAL GAS 6.72E+00 Dose Rate on contact=1.1E+03 mR/hr Dose Rate at 1 foot=1.2 mR/hr Dose Rate at 1 meter=0.1 mR/hr TABLE 9.4D AIR EJECTOR (Sample collection between 09:56-14:00)Nuclide Kr-85'r-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Concentration (pCi/gm)Corrected to time of Shutdown 1.92E-09 6.10E-08 2.61E-08 9.85E-08 2.34E-08 1.59E-06 2.35E-07 2.34E-07 2.20E-07 3.03E-07 TOTAL GAS 2.79E-06 Dose Rate on contact=<0.01 mR/hr Dose Rate at 1 foot=<0.01 mR/hr Dose Rate at 1 meter=<0.01 mR/hr TABLE 9.5A COMPONENT COOLING WATER (CCW)SYSTEM (Collection between 08:30-14:00)Activity=2.51 K-05 pCi/gm Chromates=154 ppm pH=8.0 TABLE 9.6B WASTE HOLD UP TANK (WHUT)(Collection between 08:30-14:00)Activity=2.3E-05 pCi/gm Chromates=20 ppm pH=6.7 TABLE 9.6 CONTAINNlENT HYDROGEN CONCENTRATION Time 06:30-1 4:00 H dro en VOL.%0.0 TABLE 9.7 Reactor Cooiant S stem RCS and Containment Sum Boron/H Data~Sam le RCS RCS RCS Sump Time 06:45-09:15 09:16-09:30 09:31-14:00 06:45-1 4:00 m Boron 571 2097 2207<10.pH 6.8 5.1 4.7 7.5 TABLE 9.8 CONTINUOUS AIR MONITOR READINGS IN AUXILIARY BUILDING (READINGS IN COUNTS.PER MINUTE)0630-1130 hrs: TOP FLOOR INTERMEDIATE FLOOR BASEMENT FLOOR GAS 50 50 100 IODINE 100 100 200 PARTICULATE 100 100 200 09:16-10:00 hrs: TOP FLOOR INTERMEDIATE FLOOR BASEMENT FLOOR 100 50 100 200 100 200 200 100 200 10:01-14:00 hrs: TOP FLOOR INTERMEDIATE FLOOR BASEMENT FLOOR 50 50 100 200 100 200 200 100 200 TABLE 9.9AIR SAMPLE RESULTS IN TSC AND CONTROL ROOM (Readings in Counts per Minute)07:00-09:15 hrs: TSC CONTROL ROOM IODINE 50 50 PARTICULATE 50 50 BACKGROUND 50 50 09:16-10:00 hrs: TSC CONTROL ROOM 80 80 50 50 50 50 10:01-14:00 hrs: TSC CONTROL ROOM 50 50 50 50 50 50 METEOROLOGICAL ASSUMPTIO SECTION 10.0 METEOROLOGICAL AND OFFSITE RADIOLOGICAL DATA SECTION 10.1 METEOROLOGICAL DATA PLUME DIRECTION WEATHER FORECASTS AND TOWER DATA FIGURE$0,.4 D)RECTION OF THE PI.UMK-t., I~~'ai I~)j'o ifs.I'e~/'.7'I I I, a I.'e94!22:-'=We Webster.-J I ir I o~~Vice<<~Woioe Ioao OooehaO I e'i/I>>oc'aa 75~e r"-1 t!t i/~/.~./.~'/5e Ooe i/I j~~~ii I'~".-EIIOt/" Roc hesce~r'O I ala erI~eillfO$oea/" V/-~r Aaeoa Foa$rl~Wiia taro~~g/i I'T I" I Wm Wolaooolh aooi'I;SroCOdoei Wahoael oora>>ihl mS airaai C~o F I iree./o rooi I>.-r+IF oohoea Ia Aal,~.'i I"5 ZS go'00 2'5 SCALE 1:Ipp ppp I CO O I CQ WS'Ch M&2 H/OI/OOOO/oiS I k+OICI(h Ileo Iloe COO$0 15 iaam Coeaii ONrhfgo~ia I'oeeoaaoooea i I/eaaaa>>I/~i leeeaaat//Og lOCO O25 ICO IO CO Ila INOO~~20 ON 15I 225 I I ON%UZI'0 CO M orolo ic I ndi i n A.~Ba is The meteorological conditions for this scenario were based upon historical meteorological data recorded by the Ginna primary weather tower and the National Weather Service on Au s 22 1988.Minor editting was performed on 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.Scnri A m in The scenario begins with light, southerly winds which shift and become northeasterly by mid-morning. During the period of release due to the Steam Generator Tube Rupture (0915-0955 hr), the average meteorological conditions are as follows: Wind Speed=5 mph (at 33 ft)Wind Direction=50 degrees (at 33 ft;wind from)Pasquill Stability=E 10-4. TABLE 10.1 WEATHER FORECAST INFORMATI N OCTOBER 8, 1992 7:30 AM-3:00 PM LAKE ONTARIO FORECAST: TODAY: SOUTHERLY WINDS WILL BE SHIFTING NORTHEASTERLY BY MID-MORNING.TEMPERATURES EXPECTED IN THE MID-TO UPPER 60'S.WINDS WILL REMAIN FROM THE NORTHEAST AT 5 MPH THROUGHOUT THE REMAINDER OF THE AFTERNOON. NOTE'UPPLEMENTAL FORE AST INFORMATI N T BE PROVIDED BY NATIONAL WEATHER SERVICE CONTROLLER AT THE FOLLOWING TELEPHONE NUMBER: 716 2-7633 OR BY DESIGNATED NYS CONTROLLER IN ALBANY.10-5. PRINTO TS FR IVI INNA PRIMARY MET.T WER (15-MINUTE AVERAGES)10-6. PRINTOUT PROM GINNA PRIMARY METe TOWER IBM PC TERMINAL AV 10/8/92 06: 45 RECORD NUMBER 3974 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250"ER 33A 57.1 MPH 7'MPH 197.0 DEG 196.0 DEG 174.0 DEG 56.0 DEG 198.0 DEG 48.8 AVERAGE UNIT 3.6 MPH 3'MPH 4.5 MPH CODE STDDEV 0.9 0.8 0.9 0.0 0.4 9.0 9.0 3.0 0.0 10.0 MIN 2.8 7.0 2-3 2'6.8 6.9 57.0 13'57.2 15.1 178.0 232.0 179.0 225.0 166.0 183.0 55.0 57.0 174.0 230.0 TER 33B TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 48.7 49.2 51.4 55.2 2.6 2.4 6.5 6.0 PRECIPITATION 1.08 F/F/F/F/0 INCH 0 0.00 0.00 0.00 PRINTOUT FROM GINNA PRIMARY MET TORE BM PC TERMINAL AV 10/8/92 07: 00 RECORD NUMBER 3975 RG&E GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV M~I SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A i'ER 33B 57.1 6.1 209.0 195.0 174.0 56.0 188.0 52.9 53.3 MPH 0 MPH 0 MPH DEG 0 DEG DEG 0 DEG 0 DEG 0 0 MPH MPH 0 0.9 0.8~0.0.0 p~4 11.0 7.0 3.0 0.0 9.0 2.8 7.0 2-3 6.8 2'57.0 13-2 183.0 197.0 6.9 57.2 15.1 247.0 295.0 55.0 184.0 57.0 230.0 166.0 183.0 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 53.6 55.4 5.0 3.0 2.5"2.0 PRECIPITATION 1.08 F F/F/F/p F/0 INCH 0 0.00 0.00 0.00 PRINTOUT PROM G1'NNA PRIMARY MET TOWER IBM PC TERMINAL%V 10/8/92 07:15 RECORD NUMBER 3976 RGS(E GINNA PLANT'ENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 ER 33A TER 33B TER150A TER150B TER250A 3.8 3.9 4;8 57.1 7'193.0 197.0 184.0 56.0 188.0 52.9 53.3 53.3 53.6 55.5 MPH MPH MPH MPH MPH DEG DEG DEG DEG DEG CODE STDDEV 0.9 0.8 0.9 0.0 0.4 9.0 7.0 3.0 0.0 1.0 MIN 2.8 7.0 2'6.8 2'57.0 13-2 172.0 6.9 57.2 15.1 229.0 197.0 295.0 55.0 57.0 154.0 160.0 166.0 183.0 DT150-33A DT150-33B DT250-33A DT250-33B 0.4 0.3 2.5 2-3 PRECIPITATION 1.08 F/F/F/0 F/0 INCH 0 0.00 0.00 0.00 PRINTOUT FROM GINNA PRIMARY MET TONER IBM PC TERMINAL WV 10/8/92~0: 30 RECORD NUMBER 3977 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A'DIR 33B DIR150A DIR150B DIR250 ZER 33A AVERAGE 3'3'4.5 57.1 7'202.0 195.0 174.0 56.0 158.0 53.0 MPH MPH MPH MPH MPH DEG DEG DEG DEG'DEG CODE STDDEV 0.8 0.9 0.0 0.4 9.0 7.0 3.0 0.0 1.0 MIN 2.8 7.0 2-3 6.8 2'57.0 13-2 6.9 57.2 15.1 172.0 229.0 197.0 166.0 295.0 183.0 55.0 57.0 154.0 160.0 TER 33B TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 53.1 53.4 53.5 55.5 0.4 0.5 2.5 2'PRECIPITATION 1.08 0 F/F/F/0 F/0 INCH 0 0.00 0.00 0.00 PRINTOUT PROM GINNA PRIMARY MET TOWER IBM PC TERMINAL XV 10/8/92 07: 45 RECORD NUMBER 3978 RG&E GINNA PLANT SENSOR NAME SPD 33A.SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 x'ER 33A TER 33B TER150A TER150B TER250A 57 F 1 MPH 7'MPH 215'198.0 DEG DEG 201.0 DEG 56.0 DEG 158.0 53.5 DEG 53.7 53.5 53.6 55.6 AVERAGE UNIT MPH MPH MPH CODE 0 STDDEV 0.9 0.8 0.9 0.0 0.4 11.0 11.0 13.0 0.0 1.0 MIN 2.8 2-3 2'57.0 13'184.0 197.0 175.0 55.0 154.0 7.0 6.8 6.9 57.2 15.1 242.0 255.0 238.0 57.0 160.0 DT150-33A DT150-33B DT250-33A DT250-33B 0.0 0.0 2-1 1.9 PRECIPITATION 1.08 F/F/F/0 F/0 INCH 0 0.00 0.00 0.00 PRZNTOUT PROM OZNNA PRIMARY MET TOWER ZBM PC TERMINAL AV.10/8/92 08: 00 RECORD NUMBER 3979 RG&E GINNA PLANT SENSOR NAME UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A 3.6 3.5 4.7 57'F 1 222.0 230.0 202.0 56.0 168.0 57.7 MPH MPH MPH MPH MPH DEG DEG DEG DEG DEG 0 0 0 0 0 0 0.9 0.8 0.9 0.0 0.4 13.0 7.0 3.0 0.0 3.0 2.8 7.0 2'2'6.8 6.9 57.0 13.2 186.0 57.2 15.1 268.0 197.0 295.0 55.0 154.0 57.0 180.0 179.0 230.0 ER 33B 57.7 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 57.9 57.9 58.0 0.2 0.2 0.3 0.1 F/F/F/F/0 0 0 0 PRECIPITATION 1.08 INCH 0 0.00 0.00 0.00 PRINTOUT PROM GINNA PRIMARY MET TONER IBM PC TERMINAL AV 10/8/92 08015 RECORD NUMBER 3980 RG&E GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250'ER 33A 3.6 3'4.5 57'F 1 194.0 195.0 174.0 56.0 158.0 58.7 MPH MPH MPH MPH MPH DEG DEG DEG DEG DEG 0.9 0.8 0.9 0.0 0.4 9.0 7.0 3.0 0.0 1.0 2.8 7.0 2-3 2-7 57.0 13'172.0 197.0 6.8 6.9 57.2 15.1 229.0 295.0 55.0 57.0 154.0 160.0 166.0 183.0 TER 33B TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 58.7 57.9 58.1 58.0 0.8 0.8-0.7-0.7 PRECIPITATION 1.08 F/F/F/0 F/0 INCH 0 0.00 0.00 0.00 \PRINTOUT FROM GINNA PRIMARY MET TOWER IBM PC TERMINAL%V 10/8/92 08:30 RECORD NUMBER 3981 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 AVERAGE 2'2.5 3'57.2 3.5 47.0 42.0 65.0 55.0 64.0 MPH MPH MPH MPH-MPH DEG DEG DEG DEG DEG CODE STDDEV 0.9 2.0 0.0 3.0 3.0 8.0 14.0 0.0 3.0 MIN 3.0 3-7 3.0 57.1 12'~08.0 110.0 5.0 54.0 15.0 9.7 8.7 11.0 57.2 14.4 312.0 300.0 153.0 56.0 141.0 z'ER 33A TER 33B TER150A TER150B TER250A 59.6 59.6 58.8 58.8 58.9 DT150-33A DT150-33B DT250-33A DT250-33B 0.8 0.8-0.7-0.7 F/F/F/F/PRECIPITATION 1.08 INCH'0.00 0.00 0.00 PRINTOUT PRO GINNA PRIMARY MET4 TOWE BM PC ERMI L AV 10/8/92 08:45 RECORD NUMBER 3982 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A AVERAGE UNIT 3.8 MPH MPH MPH CODE STDDEV 0.8 0;9 1.0 MIN 2-3 2.6 2'7-7 7'7.5 SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A ZER 33B 57.2 7'79.0 82.0 85.0 56.0 79.0 59.8 59.8 MPH MPH DEG DEG DEG DEG DEG 0.0 0.9 15.0 14.0 6.0"0.0 3.0 57.1 8.6 44.0 40.0 57.3 13.6 118.0 128.0 55.0 56.0 144~0 167.0 145.0 178.0 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 59.4 59.4 59.0-0.4-0.4-0.8-0.8 PRECIPITATION 1.08 F/F/F/F/0'INCH 0 0.00 0.00 0.00 'I PRINTOUT PRO CINNA PRIMARY MET i TONE IBM PC TERMINAL AV 10/8/92 09: 00 RECORD NUMBER 3983 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A F 1 3'5.2 57'9.5 52.0 54~0 55.0 56.5 57.0 59.9 MPH MPH MPH MPH DEG DEG DEG DEG DEG CODE STDDEV 0.9 0.7 0.7 0.0 1.0 3.0 4.0 3.0 0.0 5.0 MIN 2.9 3.4 3.4 57.2~6.35.0 30.0 36.0 54.0 35.0 MAX 7'6.8 6.9 57.4 11-1 126.0 130.0 121.0 56.0 129.0 j.'ER 33B 59.9 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 59.9 59.9 59.3 0.0 0.0'0.6 0.6 F/F/F/F/0 0 PRECIPITATION 1.08 INCH 0 0.00 0.00 0.00 PRINTOUT PROM GINNA PRIMARY MET.TOWER IBM PC TERMINAL.AV 10/8/92 09:15 RECORD NUMBER 3984 RG&E GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 3.8 3.8 4.9 57.3 7'50.0 51.4 52.0 53.0 54.0 MPH 0 MPH 0 MPH 0 MPH 0 MPH DEG DEG DEG DEG DEG 1.0 1.0 1.0 0.0 1~1 19.0 18.0 10.0 0.0 8.0 2.0 7'2'7-1 2-2 57.2 7'57.4 4.5 10.0 9.8 96.0 10.0 93.0 11.0 54.0 90.0 56.0 135.0 178.0'VER 33A TER 33B 60.7 61.2 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 60.7 60.7 60.7 0.0 0.0 0.0 0.5 PRECIPITATION 1.08 F/F/,~0 F/F/0 INCH 0 0.00 0.00 0.00 PRINTOUT PROM GINNA PRIMARY MET.TOWER IBM PC TERMINAL AV, 10/8/92 09:30 RECORD NUMBER 3985 RG&E GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250'PER 33A ER 33B 4.1 4.2 5.1 57.0 7.4 50.4 51.0 49.0 52.0 55.0 60.7 60.7 MPH MPH MPH MPH MPH DEG DEG DEG DEG DEG 0 0 0 0 1'1~1 1~3 0.4 1.5 9.0 14.0 14.0 5.0 16.0 2-2 7.6 2'7'2'7.5 56.3 3'55.0 57.4 10.7 291.0 35.0 319.0 174.0 311.0 54.0 69.0 166.0 282.0 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 60.3 60.3 60.6 0.4 0.4 0.0 0.1 PRECIPITATION 1.08 0 F/F/0 F/0 F/0 INCH 0 0.00 0.00 , 0.00 PRINTOUT PROM GINNA PRIMARY MET TOlifER 1BM PC TERMINAL AV 10/8/92 09:45 RECORD NUMBER 3986 RG&E GINNA PLANT 8EN80R NAME SPD 33A SPD 33B SPD 150A AVERAGE 4.9 4.8 4.8 UNIT MPH MPH MPH CODE 0, 8TDDEV 1~3 1-2 1'MIN 0.6 2.0 1.9 8.3 8.2 8.3 SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 5.7 6.9 49.0 49.9 55.0 56.0 54.0 MPH'PH DEG DEG DEG.DEG DEG 0.1 1-2 17.0 14.0 11.0 3.0 10.0 56.3 3.6 97.0 52.0 68.0 57.0 56.9 9.5 334.0 333.0 8.0 68.0 163.0 355.0~ER 33A TER 33B 61.3 61.6 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 62.0 62.0 61.3 0.7 0.7 0.0 0.4 F/F/F/F/PRECIPITATION 1.08 INCH 0 0.00 0.00 0.00 AV RG&E GINNA PLANT 10/8/92 10:00 RECORD NUMBER 3987 STDDEV,~MI CODE AVERAGE SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 9.1 2.5 5.0 1.4 0 2.4 2.5 56.9 11.0 5~1 1.5 9.0 0 5.2 1.5 9.1 MPH 57.0 0.0 57.1 96.0 MPH 0 MPH 6.1 2.0 55.0 40.0 DEG 0 13.0 14.0 13.0 135.0 58.0 35.0 146.0 DEG 61'42.0 137.0 DEG 65.0 DEG 0.53.0 1.0 57.0 46.0 134.0 0 69.0 DEG 12.0 61.3 TER 33A TER 33B 0 61.7 0 62.5 TER150A TER150B TER250A 62.6 61.4 F/DT150-33A 1'DT150-33B 1-3 DT250-33A 0.1 F/0 F/DT250-33B-0.4 F/PRECIPITATION 1.08 INCH 0 0;00 0.00 0.00 PR1NTOUT PROM GINNA PRIMARY MET+TOWER IBM PC TERMINAL PRXNTOUT PRO GINNA PRIMARY MET.TONER BM PC ERMXNAL AV 10/8/92 10 15 RECORD NUMBER 3988 RG&E GINNA PLANT SENSOR NAME AVERAGE CODE STDDEV MIN SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B'DIR250 TER 33A ER 33B 4.9 4'4.8 51.1 6.6 80.0 81.0 72.0 54.0 77.0 61.3 61.3 MPH MPH MPH MPH DEG DEG DEG DEG DEG 0 1.4~4 1'0.0 1.8 14.0 13.0 12.0 0.0 10.0 0.6 0.5 0.6 57.0 1.0 30.0 31.0 32.0 53.0 54.0 6.9 6.6 6.4 57.1 9.1 141.0 146.0 139.0 55.0 128.0 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B PRECIPITATION 62.0 62.3 63.3 0.7 2.0 2.0 2-1 1.08 F F/F/F/F/0 INCH 0 0.00 0.00 0.00 PRZNTOUT PROM GZNNA PRZMARY MET~TOWER ZBM PC TERMZNAL AV 10/8/92 10: 30 RECORD NUMBER 3989 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A AVERAGE 4.8 4.9 7.9 57.+7.8 81.0 79.0 86.0 53.0 89.0 61.3 MPH MPH MPH MPH DEG DEG DEG DEG DEG CODE 1-3 1 3 1'0.0 0.5 12.0 1.4 5.0 57.0 0.8 41.0 6.9 7.9 9.0 57.2 9.2 140.0 13.0 16.0 0.0 37.0.148.0 39.0 53.0 162.0 54.0 14.0 27.0 156.0 r STDDEV MZN'AX x'ER 33B TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 61.3 62.2 62.2 63.0 1.0 1~1 2'2'F/F/F/F/PRECIPITATION 1.08 INCH 0 0.00, 0.00 0.00 PRINTOUT PROM GINNA PRIMARY MET TOWER IBM PC TERMINAL.AV 10/8/92 10: 45 RECORD NUMBER 3990 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A ZER 33B AVERAGE 5.2 6.2 5.5 57.2 5.1 79.0 77.0 79.0 53.0 77.0 61.4 61.4 UNIT MPH MPH MPH MPH MPH DEG DEG DEG DEG DEG CODE 0 STDDRV 1.0 1'1'0.0 1'14.0 12.0 9.0 0.0 11.0 MIN 2.8 8.5 F 1 9'2.5 9.0 57.1 57.2 2.4 8.2 35.0 139.0 48.0 52.0 32.0 122.0 54.0 144.0 36.0 127.0 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 62.5 62.4 63.5 1.0 F 1 2-1 PRECIPITATION 1.08 F/F/F/0 F/0 INCH 0 0.00 0.00 0.00 PRINTOUT FROM GINNA PRIMARY MET4 TOWER IBM PC TERMINAL AV 10/8/92 11000 RECORD NUMBER 3991 RGGE GINNA PLANT SENSOR NAME AVERAGE UNIT CODE 8TDDEV MIN SPD 33A SPD 33B 4.8 5'MPH MPH 0 0 1.4 1.4 1'1.5 7.4 7.6 SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A 2.8 57.2 5.1 79'80.0 79.0 33.0 77.0 62.4 MPH MPH MPH DEG DEG DEG DEG DEG 0 0 0 0 0 1.6 0.0 1'14.0 14.0 0.0 11.0 1.6 6.0 57.1 57.2 2.4 8.2 28.0 39.0 130.0 153.0 26.0 111.0 32.0 144.0 52.0 54.0 ER 33B 62.4 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 63.3 63.3 64.9 0.9 0.9 2.4 2.5 F/F/F/F/0 0 0 0 PRECIPITATION ,1.08 INCH 0 0.00 0.00 0.00 PRINTOUT FROM GINNA PRIMARY MET>>TOWER IBM PC TERMINAL AV 10/8/92 11:15 RECORD NUMBER 3992 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A 57'MPH 6.8 MPH 80.0 DEG 82.0 DEG 81.0 DEG 78.0 DEG 69.0 DEG 62.5 AVERAGE UNIT MPH MPH MPH CODE STDDEV 1~3 1-3 0.0 1~1 14.0 13.0 13.0 0.0 11.0 MIN 2.4 F 1 MAX 10.0 9.4 2-2 9.5 57.1 57.3 3.8 9.3 37.0 144.0 39.0 133.0 42.0 32.0 134.0 129.0 41.0 120.0'R 33B TER150A TER150B TER250A 62.5 63.6 63.7 64.9 DT150-33A DT150-33B DT250-33A DT250-33B F 1 1~2 2.4 2.5 PRECIPITATION 1.08 F/F/F/0 F/0 INCH 0 0.00 0.00 0.00 PRINTOUT FROM GZNNA PRIMARY MET i TONE IBM PC TERMINAL AV 10/8/92 11:30 RECORD NUMBER 3993 RG&E GINNA PLANT SENSOR NAME SPD 33A-SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B 5.6 5.7 8.0 57.2 6.5 79.0 80.0 79.0 54.0 UNZT MPH MPH MPH MPH MPH DEG DEG DEG DEG CODE 0 STDDEV-3 1-2 2.0 0.0 1~3 11.0 11.0 6.0 0.0 MZN 2.6 2.6 3.0 57.2 4.3 36.0 37.0 53.7 53.0 8.1 8.0 11.0 57.3 9.7 129.0 138.0 116.0 55.0 DIR250 TER 33A l'ER 33B 78.0 62.7 62.7 DEG 0 8.0 20.0 125.0 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 63.9 63.9 64.8 1'1'2.5 2.4 F/F/F/F/0 PRECIPITATION 1.08 INCH 0.00 0.00 0.00 RINTOUT FROM QINNA PRIMARY MET TOWER IBM PC TERMINAL AV 10/8/92 11 45 RECORD NUMBER 3994 RG&E GINNA PLANT 8EN8OR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A i'ER 33B 6.2 6.4 6.6 57.2 7-2 76.0 81.0 77.0 53.0 70.0 65.0 65.0 MPH MPH MPH MPH MPH DEG DEG DEG DEG DEG CODE STDDEV 1.5~4 1~3 0.0~1.15.0 15.0 17.0 0.0 9.0 MIN 2'2.0 2.5 57.1 3.6 15.0 16.0 21.0 52.0 20.0 MAX 9.8 9.7 9.5 57.3 10.3 115.0 114.0 125.0 55.0 114.0 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 65.3 65.5 66.8 0.3 0.5 1.8 1.9 F/F/F/F/0, PRECIPITATION 1.08 INCH 0 0.00 0.00 0.00 PRINTOUT FROM GINNA PRIMARY MET TOWER IBM PC TERMINAL AV 10/8/92 12:00 RECORD NUMBER.3995 RG&E GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A 6.1 6'6.5 57.2 7'77.0 80.0 78.0 53.0~7~0 65.1 MPH MPH MPH MPH DEG DEG DEG DEG DEG 0 1.5 1.4 1-3 0.0 1.4 15.0 15.0 17.0 0.0 9.0 2-2 2.0 2.5 57.1 3.6 15.0 16.0 21.0 52.0 20.0 9.8 9.7 9.5 57.3 10.3 115.0 114.0 125.0 55.0 14.0 ER 33B TER150A 65.0 65.3 TER150B TER250A 65.5 66.8 DT150-33A DT150-33B DT250-33A DT250-33B PRECIPITATION 0.3 0.5 1.8 1.9 1.08 F/0 F/0 F/0 F/0 INCH 0 0.00 0.00 0.00 PRINTOUT PROM GINNA PRIMARY MET~TOWER IBM PC TERMINAL AV 10/8/92 12:15 RECORD NUMBER 3996 RGErE GINNA PLANT SENSOR NAME SPD 33A SPD 33B.SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A 6.5'.6 MPH MPH 1.5 1.4 6.7 MPH 0 1~3 57.2 MPH 0.0 7.4 MPH 1.4 77.0 85.0 79.0 DEG DEG DEG 15.0 15.0 17.0 53 0 DEG 0.0 79.0 DEG 9.0 66.0 AVERAGE UNIT CODE STDDEV MIN 2'2.0 2.5 57.1 3.6 15.0 16.0 21.0 52.0 20.0 9.8 9.7 9.5 57.3 10.3 115.0 114.0 125.0 55.0 114.0 ER 33B 66.0 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A 66.3 66.5 67.8 0.4 0.5 1.9 F/F/F/DT250-33B 1.8 PRECIPITATION 1.08 F/.0 INCH 0 0.00 0.00 0.00 PRINTOUT>ROM GZNNA XRZMARV MET.TOWZR IBM PC TERMZNAZ, AV 10/8/92 12: 30 RECORD NUMBER 3997 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 TER 33A ER 33B AVERAGE 8.5 8'7'57'7.4 67.0 65.0 69.0 53.0 69.0 66.0 66.0 MPH 0 MPH 0 MPH 0 MPH 0 1.4 1'0.0 MPH 1.4 DEG 0.15.0 DEG DEG 0 14.0 15.0 DEG 0.0 DEG F'9.0 F UNXT CODE STDDEV MIN 2'3.0 MAX 12.8 12'2.5 9.5 57.1 3.6 11.0 57.3 10.3 104.0 12.0 115.0 52.0 20.0 55.0 100.0 11.0 103.0 TER150A TER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 66.3 66.5 67.8 0.4 0.5 1.9 1.8 F/F/F/F/0 0 0 PRECIPITATION 1.08 INCH 0 0.00 0.00 0.00 PRZNTOUT PROM GZNNA PRZMARY MET TOWER ZBM PC TERMZNAL AV 10/8/92 12: 45 RECORD NUMBER 3998 RG&E GINNA PLANT SENSOR NAME SPD 33A SPD 33B SPD 150A SPD 150B SPD 250 DIR 33A DIR 33B DIR150A DIR150B DIR250 8'8 7 ,7~9 57'7.9 65.0 MPH MPH 0'.4 MPH 0 1'MPH 0 0.0 MPH 0 1.4 DEG 0 15.0 63.0 DEG , 0 14.0 62.0 DEG 0 15.0 53.0 66.0 DEG DEG 0.0 9.0 AVERAGE UNIT CODE STDDEV MZN 2'12.8 3.0 12~7 2.5 9.5 57.1 3.6 57.3 10.3 11.0 104.0 52.0 55.0 20.0 100.0 11.0 103.0'2.'0 115.0 TER 33A ER 33B TER150A'ER150B TER250A DT150-33A DT150-33B DT250-33A DT250-33B 66.0 66.0 66.3 66.5 67.8 0.4 0.5 1.9 1.8 F/F/F/F/0 PRECIPITATION 1.08 INCH 0 0.00 0.00 0.00 0 SECTlON 10.2 F!ELD DATA AND MAPS TABLE'10.2 PLUME-ARRIVAL DEPARTURE TIMES DISTANCE IVII 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 1 2.0 TABLE 10.3 09:21 09:27 09:39 09:51 10:03 10:15 10:27 10:39 10:51 11'03 11:15 11:27 11:39 TABLE 10.4 09'42 09:48 10:00 10:12 10:24 10:36 10:48 11:00 11:12 11:24 11:36 11:48 12:00 10:01 10:07 10:19 10:31 10:43 10:55 11:07 11:19 11:31 11:43 11:55 12:07 12:19 NOTES: " After indicated arrival time, refer to offsite radiological data shown on Tables 10.3 and 10.4 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 10.5 and 10.6. TABLE 10.3-A RADIOLOGICAL SURVEY/SAMPLING DATA (RG8cE FIELD TEAMS)CLOSE WINDOW OPEN WINDOW DOSIMETRY GROSS (mr/hr)(mr/br)INCREMENT IODINE EXPOSURE CARTRIDGE ZONE 3 FEET CONTACT 3 FEET CONTACT (mREM)(CPM)GROSS PARTIC.FILTER (CPM)A 7.3 3.4 1.5 0.7 0.4 0.3 0.2 0.1 0.1 7.3 3.4 1.5 0.7 0.4 0.3 0.2 0.1 0.1 9.5 4.5 2.0 0.9 0.6 0.4 0.2 0.2 0.1 9.5 4.5 2.0 0.9 0.6 0.4 0.2 0.2 0.1 70 50 45 BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG NOTES: 1.Dose rate readings apply to Victoreen 450 dose rate instrument or equivalent. Ensure that readings provided do not exceed range of survey instrument being used.Provide only those readings being requested, or in accordance with Controller instructions. 2.Dosimeter incremental exposure assumes a 15-minute stay-time in the particular zone of interest.Incremental values may be scaled up or down as appropriate. Provide cumulative dosimeter reading only when requested. 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.BKG=Use actual back round readin of surve instrument bein used.lo-3Y I~I J l'%g'4 TABLE 10.3-B RADlOLOGICAL SURVEY/SAMPL(NG:DATA (COUNTY TEAMS)CLOSE WINDOW OPEN WINDOW DOSIMETRY GROSS (mr/hr)(mr/hr)INCREMENT IODINE EXPOSURE CARTRIDGE ZONE 3 FEET CONTACT 3 FEET CONTACT (mREM)(CPM)GROSS PARTIC.FILTER (CPM)7.3 3.4 7.3 3.4 9.5 4.5 9.5 4.5 90 60 BKG BKG 1.5 0.7 0.4 1.5 0.7 0.4 2.0 2.0 0.9" 0.9 0.6 0.6 50 BKG BKG BKG BKG BKG 0.3 0.2 0.1 0.1 0.3 0.2 0.1 0.1 0.4 0.2 0.2 0.1 0.4 0.2 0.2 0.1 BKG BKG BKG BKG BKG BKG BKG BKG NOTES: 1.Dose rate readings apply to Victoreen 450, CDV-715, RO-2 dose rate instrument or equivalent. Ensure that readings provided do not exceed range of survey instrument being used.Provide only those readings being requested, or in accordance with Controller instructions. 2.Dosimeter incremental exposure assumes a 15-minute stay-time in the particular zone of interest.Incremental values may be scaled up or down as appropriate. Provide cumulative dosimeter reading only when requested. 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 or equivalent. 4.BKG=Use actual back round readin of surve instrumen bein used. ~P%P t I.via'4 t 4,'f>)t c",~s"M TABL'E 10.4-A RADIOLOGICAL SURVEY/SAMPLING DATA (RGEEE SURVEY TEAMS)CLOSE WINDOW OPEN WINDOW DOSIMETRY GROSS (mr/hr)'mr/hr) INCREMENT IODINE EXPOSURE CARTRIDGE ZONE 3 FEET CONTACT 3 FEET CONTACT (mREM)(CPM)GROSS PARTIC.FILTER (CPM)0.9 0.9 BKG BKG 0.4 0.4 0.2 0.2 0.5 0.2 0.5 0.2 BKG BKG BKG BKG 0.1 0.1 0.1 0.1 BKG BKG BKG BKG BKG BKG 0 BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG-BKG BKG BKG BKG NOTES: 1.:Dose rate readings apply to Victoreen 450 dose rate instrument or equivalent. Ensure that readings provided do not exceed range of survey instrument being used.Provide only those readings being requested, or in accordance with Controller instructions. 2.Dosimeter incremental exposure assumes a 15-minute stay-time in the particular zone of interest.Incremental values may be scaled up or down as appropriate. Provide cumulative dosimeter reading only when requested. 3.Air samples assume use of RADECO H-809C air sampler or equivalent. Volume assumed is approximately 180 liters (30 lpm for 6 minutes), and field reading is with HP-260.4.BKG=Use ac ual back round readin of surve instrumen bein used. J')II r<<~'I f I TABLE 10.4-B RADIOLOGICAL SURVEY/SAMPLING DATA (COUNTY TEAMS)CLOSE WINDOW OPEN WINDOW DOSIMETRY GROSS (mr/hr)(mr/br)INCREMENT IODINE EXPOSURE CARTRIDGE ZONE 3 FEET CONTACT 3 FEET CONTACT (mREM)(CPM)GROSS PARTIC.FILTER (CPM)0,9 0.4 0.2 0.1 BKG BKG BKG BKG BKG 0.9 0.4 0.2 0.1 BKG BKG BKG BKG BKG 0.5 0.2 0.1 BKG BKG BKG BKG BKG 0.5 0.2 0.1 BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG NOTES: 1.Dose rate readings apply to Victoreen 450, CDV-715, RO-2 dose rate instrument or equivalent. Ensure that readings provided do not exceed range of survey instrument being used.Provide only those readings being requested, or in accordance with Controller instructions. 2~Dosimeter incremental exposure assumes a 15-minute stay-time in the particular zone of interest.Incremental values may be scaled up or down as appropriate. Provide cumulative dosimeter reading only when requested. 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 or equivalent. 4.BKG=Use actual back round readin of surve instrument bein sed. I 1! TABLE 10.5 POST-PLUME SURVEY DATA (FOR PANCAKE PROBES AND RM-14 METER)ZONE A PANCAKE PROBE (GROSS CPM)1 METER BKG BKG BKG BKG BKG BKG BKG BKG BKG 1 CM BKG BKG BKG BKG BKG BKG BKG BKG BKG NOTE: BKG=Use ac ual back round readin of surve ins rurnen bein used. ~l~ TABLE 10.6 POST-PLUME SURVEY DATA (GAMMA MICRO-R/HOUR READINGS)ZONE GROSS GROSS MICRO-R/HOUR MICRO-R/HOUR @1 METER 91 CM A D G BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG NOTE: BKG=Use actual back round readin of surve instrumen bein sed.Io-3g r i-~e 4I~a><t SECTION 10.3 FIELD AIR SAIVIPLE ISOTOPIC DATA S r'I, i P~i h j I)~l+>,"'I 1,.l II li ,I~~t f 0 i, i~~a~)'l r ('A~!,-I TABLE 10.7-A AIR PARTICULATE FILTER ISOTOPIC ACTIVITY SAHPLE COLLECTION DURING PLUHE PHASE COUNTY TEAHS.10 CUBIC FT SAHPLE TOTAL FIELD I-131 I-133 I-135 CS-134 20NE ACTIVITY READING UCI/CC (CPH)UCI/CC UCI/CC UCI/CC UCI/CC CS-137 BA-140 LA-140 UCI/CC UCI/CC UC I/CC 6.71E-11 2.98E-11 1.33E-11 6.23E-12 3.83E-12 2.52E-12 1.61E-12 1.15E-12 9.10E-13 4.6E+01 4.2E+01 4.1E+01 4.1E+01 4.DE+01 4.DE+01 4'E+01 4.DE+01 4.0E+01 1.99E-11 8.85E-12 3.96E-12 1.85E-12 1.14E-12 7.47E-13 4.77E-13 3.42E-13 2.70E-13 1.39E.11 6.20E-12 2.77E-12 1.29E-12 7.95E-13 5.23E-13 3.34E-13 2.40E-13 1.89E-13 7.96E-12 3.54E-'l2 1.58E-12 7.39E-13 4.55E-13 2.99E-13 1.91E-13 1.37E-13 1.08E-13 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.OOE+00 O.DOE+00 O.DOE+00 O.OOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 0.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 TABLE 10.7-BSILVER 2EDLITE CARTRIDGE RADIOIODINE I SOTOP I C ACTIVITY SAHPLE COLLECTION DURING PLUHE PHASE COUNTY TEAHS-10 CUBIC Fl'AHPLE TOTAL F I ELD I-131 I-132 I-133 I-134 I-135 ZONE ACTIVITY READING UC I/CC (CPH)UCI/CC UC I/CC UC I/CC UCI/CC UCI/CC 6.71E-09 2.98E-09 1.33E-09 6.23E-10 3.83E-10 2.52E-10 1.61E 10 1.15E-10 9.10E.11 8.5E+01 6.DE+01 4.9E+01 4.4E+01 4.3E+01 4.2E+01 4.1E+01 4.1E+01 4.1E+01 1.99E-09 8.85E-10 3.96E-10 1.85E-10 1.14E-10 7.47E-11 4.77E-11 3.42E-11 2.70E-11 3.39E-10 1.50E-10 6.73E-11 3.14E-11 1.93E-11 1.27E-11 8.10E-12 5.82E-12 4.59E-12 1.39E-09 6.20E-10 2.77E-10 1.29E-10 7.95E-11 5.23E-11 3.34E-11 2.40E-11 1.89E-11 2.19E-09 9.74E-10 4.35E-10 2.03E-10 1.25E-10 8.21E-11 5~24E-11 3.76E-11 2.97E-11 7.96E-10 3.54E-10 1.58E-10 7.39E-11 4.55E-11 2.99E-11 1.91E-11 1.37E-11 1.08E-11 ~C lP V]p 4.1 r I l4 44~ll~ll 4 4~M~44 OAT ,;!'1'e-t~~l~l~~~~M~~~)r" r4'4!i'4V,~,~~l ftV p r".,(4 I~4 l I l I,~c~~t,J'I't,.;J (ly'44ll, I~.<<~lf~4 I t 44~4'4 rf',C 1 y 4"-~~~l W ly~l yl FIGURE 40.2 PLUME MAP.(0" O'!LE)R C.CL~tLAÃ2 SAX 0~~pl~~SCCQSI5V TDCC~1 aaaL aaa suaaTATION 154 I 0 R I R~W V O C.a D O.S NllR g I l pf--l,<~';=.:.-~...: ..;4).-,.' 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