ML17309A499
| ML17309A499 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/08/1992 |
| From: | Backus W, Polfleit P, Watts R ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| References | |
| NUDOCS 9210300061 | |
| Download: ML17309A499 (487) | |
Text
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
SUBJECT:
"Rochester Gas a Electric Corp Ginna Station 1992 Plume Exposure Emergency Preparedness Exercise 921008."
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THE ROCHESTER GAS AND ELECTRIC-CORPORATION GINNA STATION EIVIERGENCY PREPAREDNESS EXERCISE MANUAL I 1 I
1992 PLUIVIE EXPOSURE EMERGENCY PREPAREDNESS EjKERCISE '
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(FINAL REVISION)
October 8, 1992 Prepared By:
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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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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
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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 Scope 1.2 Onsite Objectives 1.3 Summary of Proposed Activities 1.4 Offsite Proposed Activities 2.0 EXERCISE INFORIVIATION 2.1 Exercise Participants 2.2 Exercise Organization 2.3 Emergency Response Facilities 2.4 Exercise 'Conduct 2.5 Precautions and Limitations 2.6 Evaluation and Critique 3.0 TRAVEL 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 Controller Instructions 5.2 Evaluation In'structions 5.3 Personnel Assignments 5.4 Evaluation Packages 5,5 Public Information, Rumor Control 5 Spouse Phone Questions 6.0 SCHEDULE OF EVENTS
GINNA STATION 1992 PLUME EXPOSURE EIVIERGENCY PREPAREDNESS EXERCISE TABLE OF CONTENTS (Cont'd) 7.0 EXERCISE SCENARIO 7.1 Initial Conditions 7.2 Onsite Sequence of Events 7.3 Simulator Set Up Instructions 7.4 Simulator Use Guidelines 8.0 MESSAGE FORIVIS AND PLANT DATA SHEETS 9.0 ON-SITE RADIOLOGICALAND 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 Directions to Ginna Station Figure 3.2 Map of Rochester and Vicinity Figure 3.3 Map of Rochester Central Business District Figure 3.4 Directions to State Emergency Operations Center, Albany Figure 3.5 Map of State Office Building Campus, Albany SECTION 9.0 Figure 9,1 Assumed Source Term Figure 9.2 Air Ejector Concentrations Vs Time Figure 9.3 RCS Concentrations Vs Time SECTION 10.0 Figure 10.1 Direction of Plume Figure 10.2 Plume Map (0-1 Mile)
Figure 10.3 Large Plume Map (0-10 Mile)
GINNA STATION 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 Assumed Release Quantities Table 9.2 Equilibrium Reactor Coolant Activity Table 9.3 Post-Accident Reactor Coolant Samples (Gas)
Table 9.4 Post-Accident Reactor Coolant Samples (De-Gassed)
Table 9 5
~ Boron, pH Table 9.6 Continuous Air Monitor Readings (Auxiliary Bldg)
Table 9.7 Air Sample Results in TSC and Control Room SECTION 10.0 Table 10.1 Forecast Information Table 10.2 Plume Arrival/Departure Times Table 10.3 Radiological Survey/Sampling Data (In Plume)
Table 10.4 Radiological Survey/Sampling Data (In Plume)
Table 10.5 Post-Plume Ground Survey Data (cpm)
Table 10.6 Post-Plume Micro-R/hr Data Table 10.7 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.
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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.
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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 Actual Call Up of Personnel Actual" Activate Organization Actual" Maintain Security Actual Conduct Dose Assessment Actual Protective Action Recommendations Actual Operate Joint News Center Actual Dispatch Field Survey Teams Actual-3""
Obtain PASS Sample 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.
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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.
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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 The participants in the Exercise will include the following:
2.1.1 ROCHESTER GAS AND ELECTRIC CORPORATION A. Facili ies Mana emen and Su or Personnel
- 1. Simulator Control Room
- 3. Operations Support Center (OSC)
- 4. Survey Center (SC)
- 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.
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n r llers will b i n ifie w rin r n wi h whi I rin a in "C n r lier".
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.
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R 8cE FACILITIES The Rochester Gas and Electric Corporation Emergency Res p onse 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.
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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.
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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.
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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.
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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
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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.
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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 n
1 i* i n n i i imrvmn I d h
g y meohir i<<.~lh Electric Corporation personnel to practice coordinating with outside 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 (716) 381-9900 Marriott Hotel, Greece (716) 225-6880 Red Roof Inn, Henrietta (716) 359-1100 Brookwood Inn, Pittsford (716) 248-9000 Woodcliff Lodge, Perinton (716) 248-4810 3-2
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SECTION
4.0 REFERENCES
/ABBREVIATIONS - ACRONYMS
4.1 References a.s.s 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 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 4.1.10 Wayne County Radiological Response Plan 4.1.11 INPO Emergency Preparedness Drill and Exercise Manual
4.2 Abbreviations - Acron ms A/E Architect Engineer ALARA As Low As Reasonably Achievable AOV Air-Operated Valve ARMS Area Radiation Monitor(s)
ARV Atmospheric Relief Valve ATWS Anticipated Transient Without Scram BAST Boric Acid Storage Tank CD Civil Defense CFR Code of Federal Regulations CV Containment CR Control Room DOE Department of Energy DOE-IRAP DOE Interagency Radiological Assistance Plan EAL(s) Emergency Action Level(s)
EBS Emergency Broadcast System EC Emergency Coordinator ECL(s) Emergency Classification Level(s)
ENS Emergency Notification System (NRC)
EOC Emergency Operations Center EOF Emergency Operations Facility EPA Environmental Protection Agency EPC Emergency Planning Coordinator EPIP(s) Emergency Plan Implementation Procedure(s)
EPZ Emergency Planning Zone ERF(s) Emergency Response Facility(s)
ERPA Emergency Response Planning Area ESC Engineering Support Center FEMA Federal Emergency Management Agency FRERP Federal Radiological Emergency Response Plan GS Ginna Station HALM High Alarm HP Health Physicist HPN Health Physics Network HVAC Heating Ventilation Air Conditioning INHB Inhibited (Alarm Suppressed)
INPO Institute of Nuclear Power Operations JENC Joint Emergency News Center Kl Potassium Iodide LALM Low Alarm LCO Limited Condition of Operation LOCA Loss of Coolant Accident LWR Light Water Reactor MOV Motor-Operated Valve MPC Maximum Permissible Concentration NERP Nuclear Emergency Response Plan 4-2
4.2 Abbreviation - Acron ms C n
'RC Nuclear Regulatory Commission OSC Operational Support Center OOS Out of Service (on site)
OOS Out of Sequence (off site)
PAG(s) Protective Action Guide(s)
PAR(s) Protective Action Recommendation(s)
PASS Post Accident Sampling System PIO Public Information Officer PWR Pressurized Water Reactor RCP Reactor Coolant Pump RCS Reactor Coolant System RHR Residual Heat Removal RGRE Rochester Gas and Electric Corporation RST Radiation Survey Team SC Site Contingency (or Survey Center)
Sl Safety Injection SPING High Range Effluent Monitor TSC 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.
5.1.3 All Controllers will comply with instructions from the Lead Controller.
5.1.4 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
CONTROLLER LIST POSITION Exercise R. Beldue Coordinator Control Room D. Hudnut (Lead)
(Simulator) J. O'oole T. White J. Zulawski Control Room D. Peterson (Real)
Technical Support Center Lead T. Alexander Technical 8 B. Zollner Operations K. Masker Assessment Security R. Wood R. Teed Dose Assessment P. Polfleit Health Physics F. Puddu 8 Chemistry Communications S. Poulton 8 Data Flow Operations Support Center Lead J. Huff J. Knorr Fire D. Biedenbach M. Cavanaugh Operations W. Stiewe S. Carter
CONTROLLER LIST POSITION .
IBC T. Joachimczyk E. McGrattan Mechanical S. Meister E. Graus G. Gibaud J. Liese Electrical R. Yates R. Marriott Post Accident M. Clifton Sampling System TBD Survey Center Lead J. Schultz Red Team R. Mastrella Blue Team J. Edler Green Team J. Mazzeo Yellow Team P. Phelan Orange Team J. Grzybek White Team D. Bryant Personnel M.E. Dangler Coordinator Emergency Operations Facility Lead 8 W. Backus Operations Communications B. Stanfield 8 Data Flow
CONTROLLER LIST POSITION Dose Assessment R. Watts N. Kiedrowski-Survey Team K. Hart M. Burgess-General J. Neis Engineering Support Center C. Anderson J. Bergstrom Joint Emergency News Center F. Orienter National Weather Service 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
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5-11
GIN NA STATION 1992 EMERGENCY EXERCISE ATIACHMENT 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 ALL 1992 EXERCISE 10/9 8-10 CONTROLLERS 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 INITIALCONDITIONS
- 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 -00/1 5 Initial Conditions established 0715 00/00 Announcement to Commence Annual Emergency Exercise 0730 00/1 5 The Health Physics/Chemistry Department informs the Control Room that the "A" S/G calculated leak rate is IJNUSUAL approximately 450cc/min EVENT (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 1-0,~ Ginna Station Event d I df d Ih E~PI 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 The Plant Manager, Operations Assessment Manager, and Duty Engineer should be manning the TSC for Offsite Communications Assistance per EPIP 1-5.
0810 00/55 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 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.
0815 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.
Operators should inform the people manning the TSC and I 5 C Department of the ADFCS problem.
0840 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.
Operators should inform the people manning the TSC of the 1A CCW Pump problems.
0855 01/40 The ADFCS problem with the MFW Regulating Valves is repaired..
ANTICIPATED RESULTS C nrolR om Operators continue shutting Plant down per 0-2.1 0905 01/45 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:
~ Pressurizer level and pressure decreases ALERT 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).
An ALERT should be declared in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification,"
EAL: Steam Generator Tube Rupture (SGTR): SGTR )
~'l<)P 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.
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.
1030 03/1 5 The Auxiliary Operator sent to the Screen House to check the "A" SW Pump reports to the Control Room/TSC that SITE AREA he can find nothing wrong with the "A" SW Pump but he EMERGEN Y 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.
- 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 Leakage > 0.1 GPIVI as identified by sampling).
I d, IR G <<T b
- 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 AF 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
- 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
7'00 7:15 7:30 7:45 8:00 8:15 8:30 8:45 9:00 9:15 SPEED 33 3.7 3.8 3.6 3.8 3.6 3.6 2.6 3.8 3.1 3.8 DIR 33 209 193 202 215 222 194 47 79 52 50 TEMP 33 52.9 52.9 53 53.5 57.7 58.7 59.6 59.8 59.9 60.7 SPEED 150 4.7 4.8 4.5 4.8 4.7 4.5 3.7 5.2 4.9 DIR 150 174 184 174 201 202 174 65 85 55 52 TEMP 150 53.3 53.3 53.4 53.5 57.9 58.1 58.8 59.4 59.9 60.7 DT150-33 0.4 0.4 0.4 0.2 -0.6 -0.8 -0.4 SPEED 250 6.1 7.2 7.1 7.2 7.1 7.1 3.5 7.7 9.5 7.5 DIR 250 188 ~
188 158 158 168 158 64 79 57 54 TEMP 250 55.4 55.5 55.5 55.6 58 58 58.9 59 59.3 60.7 DELTA TEMP 2.5 2.6 2.5 2.1 0.3 -0.7 -0.7 -0.8 -0.6 R02 6.40E+00 6.40E+00 6.40E+00 6.40E+00 6.40E+00 6.40E+00 6.40E+00 . 6.40E+00 6.40E+00 6.40E+00 R04 4.40E+00 4.40E+00 4.40E+00 4.40E+00 4.40E+00 4.40E+00 4.40E+00 4.40E+00 4.40E+00 2.30E+01 R07 6.40E+00 6.40E+00 6.40E+00 6.40E+00 6.40E+00 6.40E+00 6.40E+00 6.40E+00 6.40E+00 6.40E+00 R09 3.40E+01 3.40E+01 3.40E+01 3.40E+01 3.40E+01 3.40E+01 3.40E+01 3.40E+01 3.40E+01 1.48E+02 R15 4.66E+04 8.75E+04 1.25E+05 1.25E+05 1.25E+05 1.25E+05 1.25E+05 1.25E+05 1.25E+05 9.99E+06 R19 4.07E+03 4.07E+03 4.07E+03 4.07E+03 4.07E+03 4.07E+03 4.07E+03 4.07E+03 4.07E+03 1.57E+04 R34 9.90E-01 9.90E-01 9.90E-01 9.90E-01 9.90E-01 9.90E-01 9.90E-01 9.90E-01 9.90E-01 9.00E-01 R31 1.02E-02 1.02E-02 1.02E-02 1.02E-02 1.02E-02 1.02E-02 1.02E-02 1.02E-02 1.02E-02 3.02E+00 R32 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 R15A5 2.33E-03 4 40E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 9.99E43 R15A6 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 4.32E-02 8.00E-01 R15A7 2.33E-03 4 40E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 1.85E+00 R15A9 2.33E-03 4.40E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 6.29E-03 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 9:35 9'45 9:55 10:00 10:15 10:30 10:45 11:00 11:15 11:30 SPEED 33 4.9 4.9 4.8 5.2 4.8 5.6 DIR 33 49 55 80 80 79 79 80 79 TEMP 33 61.3 61.3 61.3 61.3 61.4 62.4 62.5 62.7 SPEED 150 4.8 5.2 4.8 7.9 5.5 2.8 5.1 DIR 150 55 61 72 86 79 79 81 79 TEMP 150 62 62.5 62 62.2 62.5 63.3 62.5 63.9 DT 150 -33 0.7 1.2 0.7 0.9 0.9 1.2 SPEED 250 6.9 6.1 6.6 7.8 5.1 5.1 6.8 6.5 DIR 250 54 69 77 89 77 77 69 78 TEMP 250 61.3 61.4 63.3 63 63.5 64.9 DELTA TEMP 0.1 1.7 2.1 2.5 2.4 2.1 R02 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 R04 2.30E+01 2.30E+01 2.30E+01 2.30E+01 2.25E+01 2.18E+01 2.13E+01 2.07E+01 2.01E+01 1.95E+01 R07 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 R09 1.48E+02 1.48E+02 1.48E+02 1.48E+02 1.46E+02 1.43E+02 1.41E+02 1.38E+02 1.36E+02 1.34E+02 R15 4.41E+06 4.41E+06 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 R19 1.57E+04 1.57E+04 1.57E+04 1.52E+04 1.47E+04 1.42E+04 1.38E+04 1.32E+04 1.28E+04 R34 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 R31 3.02E+00 3.02E+00 3.02E+00 2.90E+00 2.85E+00 2.72E+00 2.68E+00 2.50E+00 2.50E+00 R32 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 R15A5 9.99E-03 9.99E-03 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 R15A6 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 R15A7 2.20E-01 2.20E-01 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 R15A9 2.20E-01 2.20E-01 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 Page 2
92 . LS TIME 11:45 12:00 12:15 12:30 12:45 1:00 1:15 1:30 1:45 2:00 SPEED 33 6.2 6.1 6.5 8.5 8.7 DIR 33 76 77 77 67 65 TEMP 33 65 65.1 66 69 66 SPEED 150 6.6 6.5 6.7 7.7 7.9 DIR 150 77 78 79 69 62 TEMP 150 65.3 65.3 66.3 66.3 66.3 DT 150 - 33 0.3 0.2 0.3 -2.7 0.3 SPEED 250 7.2 7.4 7.4 7.9 DIR 250 70 71 79 69 66 TEMP 250 66.8 66.8 67.8 67.8 67.8 DELTA TEMP 1.8 1.7 1.8 -1.2 1.8 R02 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 '.35E+00 7.35E+00 7.35E+00 7.35E+00 R04 1.89E+01 1.84E+01 1.78E+01 1.72E+01 1.65E+01 1.60E+01 R07 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 7.35E+00 R09 1.32E+02 1.29E+02 1.27E+02 1.24E+02 1.22E+02 1.20E+02 R15 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 R19 1.28E+04 1.19E+04 1.14E+04 1.09E+04 1.02E+04 9.90E+03 1.50E+04 1.50E+04 1.50E+04 1.50E+04 R34 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 9.00E-01 R31 2.42E+00 2.33E+00 2.25E+00 2.18E+00 2.16E+00 1.93E+00 1.87E+00 R32 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 R15A5 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 2.09E-07 R15A6 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 2.00E-01 R15A7 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 R15A9 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 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 TSC Check batteries in headsets Sim Lead 1 Day Prior Check EPIP Attachment Supply in Sim Lead Procedure Cabinet Radios for Sim (5) Sim Lead/CNEP Exercise Day Transfer REGS, NRC phones Sim Lead Transfer page Sim Lead Check PPCS printer (ON) Sim Lead Disable load dispatch phone Sim Lead Switch over PPCS/SAS per EPIP 5-5 TSC Turnover 788 Prefix Sim Lead Load dispatch ¹ Sim Lead Sim OOC Equipment Sim Lead Operations Supervisor / Present Sim Lead Operations Manager / Present Sim Lead HP / STA location for notification Sim Lead After Chain of custody of radios Sim Lead/CNEP Switch back PPCS/SAS per EPIP 5-5 TSC Transfer REGS, NRC phones Sim Lead Transfer page Sim Lead Enable load dispatcher phone 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 1 1 1 1 1 1 1 1 1 1 8 8 8 8 9 9 9 9 9 9 0 0 0 0 1 1 1 1 2 2 2 I
0 1 3 4 0 1 1 2 3 4 0 1 3 4 0 1 3 4 0 1 3 0 5 0 5 0 5 7 0 0 5 0 5 0 5 0 5 0 5 0 5 0 CLOCK TIME PRESSURIZER ~ 1A S/G LEVEL ~ 18 S/G LEVEL ~ RVLIS
TANK LEVEL TRENDS BAST, RWST (%)
100 80 60 4Q 20 0
1 1 1 1 1 1 1 1 1 8 8 8 8 9 9 9 9 9 9 0 0 0 0 1 1 1 I
1 2 0 1 3 4 0 1 1 2 3 4 0 1 3 0 1 3 Q 0 5 0 5 0 5 7 0 0 5 0 5 0 5 0 5 0 5 0 CLOCK TIME BAST ~ RWST
SECTION 8.0 MESSAGE FORMS AND PLANT DATA SHEETS
MESSAGE INDEX TIME ME A E NO. MES AGE 0700 I.C. Initial Conditions Established 0715 .1 Announcement to Commence Annual Exposure Exercise 0730 2. Notification of "A" S/G Leak Rate of 450cc/min 0745 3. Plant Status 0750 4X. Unusual Event Contingency Message 0755 5. "A" S/G ARV Popping Open 0755 6. Mini-Scenario for "A" S/G ARV Isolation and "B" S/G ARV Leak Detection 0755 7. ",A" S/G ARV Mercoid Control Problem Mini-Scenario 0800 8. Plant Status 0810 9. "B" S/G ARV Isolation 0815 10. Plant Status 8c ADFCS Trouble 0815 11. "B" S/G ARV Line Steam Leak Mini-Scenario 0815 12. MFW Regulating Valves (ADFCS) Trouble Mini-Scenario 0830 13. Plant Status 0840 14. CCW Surge Tank Lo Level Alarm 0840 15. 1A CCW Pump Leak Detection and Isolation Mini-Scenario 0845 16. Plant Status 0850 17 1A CCW Pump Trip 0850 18. 1A CCW Pump Mechanical Seal Failure Mini-Scenario 0850 19. 1 A'CW Pump Motor Problem From Pump Seal Failure Mini-Scenario 0855 20. ADFCS Problem Repaired 0900 21. Plant Status 0905 22. 1A CCW Pump Isolated 0915 23. Plant Status 5 SGTR in "A" S/G 0917 24. Plant Status 0920 25. Plant Status 0930 26. Plant Status 0930 27X. Alert Contingency Message 0945 28. Plant Status 1000 28.1 Mobile Dl Truck Mini-Scenario 1000 29 Plant Status and Mobile Dl Truck Arrives on Site 1015 30 Plant Status and "A" SW Pump Trip 1015 31. "A" SW Pump Inspection Mini-Scenario 1030 32. Natural Gas Leak Detection and Isolation Mini-
MESSAGE INDEX (continued)
TIME ~MEDEA E ED. IVIES AGE 1030 33. Plant Status 1045 34. Plant Status 1045 35. Air Evacuation of Screen House Mini-Scenario 1045 36X. Site Area Emergency Contingency Message 1100 37. Plant Status 1100 38 "A" SW Pump Problem Mini-Scenario 1100 39 Security Investigation of "B" S/G ARV Drilled Hole Mini-Scenario 1115 40. Plant Status and Mobile Dl Truck Starts Pumping to OST.
1120 41. "A" S/G ARV Mercoid Repair Complete 1120 42. Mini-Scenario for "A" S/G ARV Return to Service 1130 43. Plant Status 1145 44. The "B" S/G ARV Steam Leak Repair Completed 1145 45. "B" S/G Return to Service Mini-Scenario 1145 46. Plant Status 1145 46.1 Mini-Scenario for EOF Telephone System Failure 1145 46.2 Mini-Scenario for Contaminated IndividualArriving at TSC 1200 47. Plant Status 1215 48. Plant Status 1230 49. Plant Status 1245 50. Plant Status 1300 51. Plant Status 1315 52. Plant Status and Termination of Exercise
MINI-SCENARIOS
~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. 1A Service Water Pump Problem (Breaker) 11 r El ri i n
- 17. "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. "A" S/G ARV Isolation
- 2. QBM1 "B" S/G Leak Detection
- 3. QBM1 "B" S/G Isolation
- 4. Q)44 1A CCW Pump Leak Inspection and Isolation
- 5. 1000 Mobile DI Truck Operation
- 6. ~1~1 1A SW Pump Problem Inspection
- 7. F39. Natural Gas Leak Detection in Screen House
- 8. MIBQ Natural Gas and Propane Gas Isolation to Screen House
- 9. ~11 2 "A" S/G ARV Return to Service
- 10. ~11 4 "B" S/G ARV Return to Service B. ME HANIC ONTROLLER
%88Q. 1A CCW Pump Mechanical Seal Failure
~ELE TRICIANS '.
- 1. 08gg 1A CCW Pump Motor Problem from Pump Seal Failure 2, ~11 0 1A Service Water Pump Problem (Breaker)
D. PIPEFITTER AND WELDERS CONTROLLER 815 "B" S/G ARV Steam Leak E. I 5 C CONTR LLERS
- 2. 08'I 5 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. HEMIST 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.
- 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 0-8.
9.
A shutdown.
Leakage IL7v
)
~l.
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 h Idb d 0.1 GPM as identified by sampling).
I d, 15 G <<Tb 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
- 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 INITIALCONDITIONS
- 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 Reactor Shutdown ~YES Hi h Head S.I. Pum s N-3 1 N-32
~CPS CPS FY-924 ~GPM FI-925 C7 GPM N-35 AMPS 1A. INSERV B OOS N-36 AMPS 1B. INSERV TB OOS Avg. Nuclear Power 1C INSERV STB OOS RCS Pressure ZzM PSIG BAST Level =
PRZR Level A RCP NNI STOPPED Low Head S.I. Pum s B RCP UNNIN STOPPED FI-626 1A S/G Level ~Z,. I 1A. INSERV TB OOS RECIRC 1B S/G Level , 1B. INSERV TB OOS RECIRC 1A S/G Pressure /47 tz PSIG RWST Level =
1B S/G Pressure ~SO PSIG Turbine/Generator LI OFFLINE Containment S ra Pum s 4 KV Buses NERGIZED DEENERGIZED FI-931A O GPM 480V Buses DC Batteries NERGI DEENERGIZED FI-931B 0 GPM A~5o VOLTS B/Sb VOLTS 1A. INSERV TB OOS nmt Pressure PSTG 1B. INSERV TB OOS nmt Sump A Level ~ FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg ~&A OF Containme ecirc Fans A Loop Cold Leg .S OF 1A. SER STBY OOS B Loop Hot Leg 7 OF 1B. NSE STB OOS B Loop Cold Leg oF 1C. INS RV B OOS RVLIS ~'~e3 1D. NSER STBY OOS
- CET Q b~~e$ OF Post Acc ent Dampers OPEN LOSED S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow ~GPM Service Water 1A.
Pum s SE STBY OOS DIESEL GENERATORS 1B. R STBY OOS 1C. NS RV STB OOS A. RUNNING UNLOADED B OOS 1D. INSERV STB OOS B. RUNNING UNLOADED TSC RUNNING UNLOADED BY OOS A&B Header Pressure / 73 PSIG 0 S Security RUNNING UNLOADED TB OOS Com onent oolin Water Pum s 1A. NSE S
~2 OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Surge Tank Level =
Aux. Feedwat um s 1A. INSERV OOS Standb Aux. Fe ater Pum s 1B. INSERV TB OOS 1C. INSERV OOS Turb. Driven ST Level ~INSERV TB FEET OOS 1D. INSERV TB OOS
- CET = Average of Selected Core Exit Thermocouples
8~ 1992 07'08 R. E. GINA SltKATOR PAGE 1 7REND GROUP ASSIG)ST SU)WARY 6ROUP: EVENT1 PROCEDURE: EPIP 1-5 PLA)(7 STATUS POINT ID DESCRIPTION (IAL E. U.
1 ATMS ANTICIPATED TRANSIENT M/0 SCRAtt NO ATMS 6009 2 RXT REACTOR TRIP BREAKER STATUS NOT TRIP 6009 3 N31 SO(mCE RANGE DETECTOR N-31 1.00000+00 INHB CPS 4 N32 SO(HCE RA%E DETECTS N-32 1.00000+00 INHB CPS 5 N35 INTERNEDIATE RANEE K7ECTOR tt-35 6.91829-04 INHB le 6 N36 INTER)(EDIATE RANGE DETECTOR N-36 6.42686M INHB NP 7 NP AVERAGE N(KLEAR POMER 97.15 GOOD X 8 PRCS REfK:TOR CQOUNT SYSTEM AVG PRESS 2252. 6009 PSIG 9 LP2R PRESSURIlER AVERAGE LEVEL 47.9 GOOD 10 FRCLA REACTOR COOUNT LOOP A AVG FLOM 98.5 GOOD /
11 FRV B REACTOR COOLANT LOOP B AVG FLOM 97.3 6009 /
12 R)(T16 RCPA BREAKER CAUSE RX TRIP NOTTRIP 6009 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC ItiCORE TC SUBCOOLED NRCIN 45,4 600~ DEGF 15 LSGA STN GEN A NARROM RANGE AVG LEVEL 52.1 GOOD 16 LS69 STt( GEN B t(ARROM RANGE AVG LEVEL 52.1 GOOD '/
17 PSGA STt( GEN A AVERAGE PRESSURE 692. 6009 PSIG 18 PSGB STtt GEN B AVERAGE PRESSURE 6'90. GOOD PSIG 19 GENBKRl GE%MTOR ON LINE BREAKER 161T/2 NQT TRIP GOOD 20 GENBKR2 GBGNTOR ON LINE BREAKER 9X1372 NOT TRIP Goon 21 BUS11A BUS 11A SUPPLY BREAKER t$ 7 TRIP 6009 22 BUS11B BUS 11B SUPPLY BREAKER NOT TRIP 6009 23 BUS12A NOT TERt(I)ITED Ott PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERttINATED Otl PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS 11A TO 12A TIE BREAKER TRlPPED 6009 26 B11B129 BUS 11B To 12B TIE BREAKER TRIPPED 6009 27 PCV CONTAIN)(ENT AVERAGE PRESSURE .17 600D PSIG 28 LS(NPA CONTAINtfENT SUt(P A AVERAGE LEVEL 1.6 GOOD FEET 29 L0942E SSP B LEVEL 8 ItlCHES (TRAIN A) LONER 6009 30 L0943E SUtP B LEVEL 8 INCHES (TRAIN B) LONER Goon 31 L0942D SUtl' LEVEL 78 INCHES (TRAIN A) LONER 6009 32 L0943D SUtP B LEVEL 78 INCHES (TRAIN B) LONER soon 33 L0942C SSP B LEVEL 113 INCHES(TRAIN A) LONER 6009 34 L0943C SU%' LEVEL 113 INCHES(TRAIN B) LONER 6009 35 L0942B SUtP B LEVEL 180 INCHES(TRAIN A) LONER 6009 36 L0943B SU%' LEVEL 180 INCHES(TRAIN B) LONER 6009 37 L0942A SSP B LEVEL 214 INCHES(TRAIN A) LONER 6009 38 L0943A SUtF B LEVEL 214 INCHES(TRAIN B) LOWER Goon 39 T0409A RCLA HOT LEG TEtPERATURE 600.7 6009 DEGF 40 T0410A RCLB HOT LEG TEt(PERATURE 600.7 6009 DEGF 41 T0450 RCLA COLD LEG TEt(PERATNE 543;3 6009 DE6F 42 T0451 RCLB COLD LEG TEtiPERATNE 544.6 GOOD DEGF 43 TAVGAMID RCLA TAVG (TNT/TCOLD MIDE RNG) 572.0 6009 KGF 44 TAVGBMID RCLB TAVG (THOT/TCOLD MIOE RNG) 572.7 Goon DEGF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.3 6009 46 TCCORE El ~ 1 INCORE TC AVERAGE TEt(P 604.5 Goo< DEGF 47 FAUXFMA S/G A TOTAL AUX FEEDMATER FLOM 0. 6009 GPH 48 FAUXFMB S/6 B TOTAL AUX FEEDMATER FLOM 0. 6009 GPt(
49 BKR081 t(TR AUXILIARYFEEDMATER PUt(P A OFF 6009 50 BKR082 NTR AUXILIARYFEEDMATER PUt(P 9 OFF Goon 51 V3505 AUX FM PUt(P STEAN Sl)PPLY VALVE A CLOSED GOOD 52 V3504 AUX FM PUt(P STEA)l SUPPLY VALVE B CLOSED 6009
OCT 8~ 1992 07:08 R. E. GINA SI%LATOR PAGE 2 TREND GROUP ASSIGOENT S1NNRY 6ROUP: EVENTi PROCEDURE: EPIP 1-5 PLM'TATUS POINT ID DESCRIPTION VALUE QUAL E. U.
53 FSIA SAFETY IN:ECTION LOCP A AVG FLOM 0. 6000 PN 54 FSIB SAFETY INJECTION LOOP B AV6 FLOM 0. 600D 6PH 55 P2160 SERVICE MATER PlNPS A h B HEADER 81. GOOD PSI6 56 P2161 SERVICE MATER PlNPS C 5 D HEADER 73. GOOD PSIG 57 BKR041 SERVICE MATER PUNP A GOOD 58 BKR042 SERVICE MATER PlNP B 600D 59 BKR043 SERVICE MATER PlNP C 6009 60 BKR044 SERVICE MATER PUN' 6009
PROGRAM NAME :LRGTSZ.E OCT 08,92 RE E. GIHNA NUCLEAR POWER PLANT 07 01 00 TREND GROUP ASSIGNMEHT
SUMMARY
GROUP NAHE GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURREHT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLIHG LOOP TOTAL FLW 1485. GOOD GPM 2 LRWST REFUELING WATER STORAGE TANK LVL 94.5 GOOD 3 WS033 33 FOOT LEVEL WIND SPEED 3.7 GOOD MPH 4 WD033 33 FOOT LEVEL WIND DIRECTION 209. GOOD DEG.
5 WT033 33 FOOT LEVEL TEMPERATURE 52.9 GOOD DEGF 6 WT250 250 FOOT LEVEL TEHPERATURE 55.4 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEHP 2.5 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINMENT 6.4067eioo GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDOWN LINE MONITOR 3.40701+01 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD MR/H R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD MR/H R10A CONTAINMENT IODINE MONITOR R'IOA 9.58719+01 GOOD CPM R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPH 16 R12 CONTAINHENT GAS MONITOR 7.38002+02 GOOD CPH 17 R10B PLANT VENT IODINE MONITOR R10B 4.30543+01 GOOD CPM 1e R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPH
'19 R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPH 20 R18 LIQUID WASTE DISPOSAL HONITOR 2.78658+03 GOOD CPM 21 R19 STEAM GENERATOR SLOWDOWN DRAIN 4.07174+03 GOOD CPH 22 R29 AREA 29-CONTAIHHENT HIGH RANGE 5.05861-01 GOOD R/NR 23 R30 AREA 30-CONTAINMENT HIGH RANGE 5 '9440-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 4.66390+04 HALM CPH 25 R12A5 CV VENT CHAN 5 LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VEHT CHAN 6-AREA GAMMA 2.53990-02 GOOD MR/NR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VEHT CHAN 5-LOW RAHGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-HID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15AS AIR EJECTOR CHAN 5-LOW RANGE GAS 2.33589-03 HALM UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 2.33337-03 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9 Hl RANGE GAS 2.33436-03 GOOD UCI/CC 35 R31 AREA 3'I STEAM LINE A (SPING) 1.02040.02 GOOD MR/HR 36 R32 AREA 32 STEAM LINE B (SPING) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD 38 TCV03 CV BASEHENT LVL 6 FT TEHP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCV08 CV INTERMEDIATE LVL 6 FT TEHP ¹8 106.6 GOOD DEGF TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF TCV10 CV INTERMEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD 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 0 Hi h Head S.I. Pum s N-3 1 N-32
~CPS
~YES CPS FI-924 FI-925 C7 C7 GPM GPM N-35 AMPS 1A. INSERV T OOS N-36 AMPS 1B. INSERV OOS Avg. Nuclear Power 1C. INSERV OOS RCS Pressure PSIG BAST Level =
PRZR Level A RCP UNNIN STOPPED Low Head S.I. Pum s B RCP UNNZN STOPPED FI-626 0 GPM lA S/G Level .I 1A. INSERV TB OOS RECIRC 1B S/G Level ~a. 1B. INSERV TB OOS RECIRC 1A S/G Pressure ? PSIG RWST Level =
1B S/G Pressure 0 PSIG Turbine/Generator NLI OFFLINE Containment S ra Pum s 4 KV Buses NERGIZ DEENERGIZED FI-931A O'PM 480V Buses RGZZ DEENERGIZED FI-931B~GPM DC Batteries A/Sb VOLTS BISO VOLTS 1A. INSERV T OOS nmt Pressure ~ I PSIG 1B. INSERV TB OOS nmt Sump A Level ~ FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg ~ OF Containment Recirc Fans A Loop Cold Leg ~g.S OF 1A. NSER STBY OOS B Loop Hot Leg 0.'7 OF 1B. SERV STBY OOS B Loop Cold Leg ~59 ~ OF 1C. INS V TB OOS RVLIS 1.9 1D. SER STBY OOS
- CET OF Post Aces ent Dampers OPEN LOSED S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow G GPM Service Wat Pum s 1A. S STBY OOS .
DIESEL GENERATORS 1B. S STBY OOS 1C. NSE STBY OOS A. RUNNING UNLOADED OOS. 1D. INSERV TB OOS B RUNNING UNLOADED TB OOS A&B Header Pressure S PSIG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. SE STBY OOS ENGINEERED SAFEGUARDS 1B. INSERV B OOS Aux. Feedwater Pum s Surge Tank Leve = ~y 1A. INSERV TB OOS Standb Aux. Fee ater Pum s 1B. INSERV OOS 1C. INSERV TB OOS Turb. Driven INSERV TB OOS 1D. INSERV OOS
.ST Level ~FEET
- CET = Average of Selected Core Exit Thermocouples
0 07: 16 R. E. GINA Sit(ULATOR PAGE 1 TREND GROUP ASSIGN)IENT SUI(tIARY GROUP: EVENTl PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE E. U.
1 ATMS ANTICIPATED TRANSIENT M/0 SCRAtI NO ATMS 6009 2 RXT REACTOR TRIP BREAKER STATUS NOT TRIP 6009 3 N31 SMKE RANGE DETECTOR N-31 1. 00000KO INHB CPS N32 SOlRCE RA)IGE DETECTOR N-32 1.0005&0 INHB CPS 5 N35 INTE)mEDIATE RANGE DETECTOR N-35 6.918Ã-04 INHS NP 6 N36 INTERI(EDIATE RANGE DETECTOR N-36 6.42686M INHH At(P 7 t(P AVERAGE NUCLEAR POWER 97.16 6009 8 PRCS REACTOR COOLANT SYSTE)( AVG PRESS 2252. GOOD PSIG 9 LPZR PRESSURIZER AVERAGE LEVEL 48.0 6009 X 10 FRCLA RHETOR COOLANT LOOP A AVG FLGM 98.5 6009 X 11 FRCLB REACTGR COOLANT LOOP B AVG FLOM 97.3 GOOD X 12 RXT16 RCPA BREAKER CAUSE RX TRIP NOT TRIP 6009 13 RXT17 IKPB BREAKER CAUSE RX TRIP NOT TRIP Goon 14 TSUBTC INCORE TC SUBCOOLED t(ARGIN 45.4 600~ DEGF 15 LSGA ST)I GEN A NARROM RANGE AVG LEVEL 52.1 6009 X 16
'SGB STI( GE)l B NARROM RANGE AVG LEVEL 52.1 6009 /
17 PSGA STN GEN A AVERAGE PRESSURE 692. GOOD PSIG 18 PSGB STtf GEtl B AVERAGE PRESSURE 690. GOOD PSIG 19 GENBKRl GBGQTOR ON LINE BREAKER ! 61372 NOT TRIP GOOD 20 GENBKR2 GBERATOR ON LINE BREAKER 9X1372 NOT TRIP GOOD 21 BUS11A BUS 11A SUPPLY BREAKER NOT TRIP 6009
.u 24 BUSliB BUS12A BUS12B BUS 11B SL4'PLY BREAKER NOT TER)IINATED ON PPCS NOT TER)IINATED ON PPCS (7/19/91)
(7/f9/91)
NOT NOT NQT TRIP TRIP TRIP Goon DEL DEL 25 B11A12A BUS 11A TO 12A TIE BREAKER TRIPPED 6009 26 B11B12B BUS 119 TO 12B TIE BRENER TRIPPED GOOD 27 PCV CONTAINIIENT AVERAGE PRESURE .11 6009 PSIG 28 LS(NPA CoiWAINMEI(T SUI(P A AVERAGE LEVEL 1.6 6009 FEET 29 L0942E SU)P B LEVEL 8 ItlCHES (TRAIN A) LONER 6009 30 L0943E SUtP B LEVEL 8 ItlCHES (TRAIN B) LONER 6009 31 L0942D SSP B LEVEL 78 INCHES (TRAIN A) LOWER Goon 32 L09439 SUI(P B LEVEL 78 INCHES (TRAIN B) LOWER Goon L0942C SSP B LE4l3. f13 INCHES(TRAIN A) LONER 6009 34 L0943C SUtP B LEVEL 113 INCHES(TRAIN B) LONER 6009 35 L0942B SU%' LEVEL 180 INCHES(TRAItl A) LONER 6009 36 L0943B SUtF B LEVEL 180 INCHES(TRAIN B) LOWER Goon 37 L0942A SSP B LEVEL 214 INOKS(TRAIN A) LOWER GOOD 38 L0943A SU%' LEVEL 214 INCHES(TRAIN B) LONER 6009 39 T0409A IKLA HOT LEG TE)(PERATUfE 600.7 GOOD DEGF 40 T0410A RCLB HOT LEG TEt(PERATNK 600.7 6009 DEGF 41 T0450 RCLA COLD LEG TPiPERATIRE 543.3 Goon DEGF 42 T0451 RCLB CGI.D LEG TE)IPERATlRE 544.6 6009 DEGF 43 TAVGAMID RCLA TAVG (THQT/TCOLD WIDE RNG) 572.0 soon DEGF 44 TAVGBMID RCLB TAVG (THOT/TCOLD MIDE RNG) 572.7 6009 DE6F 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.3 GOOD X 46 TCCORE El 1 It/CORE
~ TC AVERAGE TEtP 604.5 6008 DE6F FAUXFMA S/6 A TOTAL AUX FEEDMATER FLGM 0. 6009 GPN FAUXFMB S/G B TOTAL AUX FEEDMATER FLOW 0. 6009 GPI(
BKR081 t(TR AUXILIARYFEEDMATER PU)IP A OFF Goon BKR082 t(TR AUXILIARYFEEDMATER PUI(P 9 OFF 51 AUX FM PUI(P STEAN SUPPLY VALVE A CLOSED GOOD 52 V3504 AUX FM PUi"P STEAN SUPPLY VALVE B CLOSED 8'-l 7
XT 8~ 1992 07! 16 R. E. GINA SIHL&TOR PAGE 2 TREND GROUP ASSIGNNEhT RNNRY 6ROUP: EVENT1 PROCEDURE! EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U.
53 FSIA SAFETY IN.'ECTION LOOP A AVG FLOM 0. GOOD GPN 54 FSIB SAFETY INJECTION LOOP B AVG FLOM 0. GOOD PN 55 P2160 SERVICE MATER PUFFS A h B HEADER 81 ~ GOOD PSI6 56 P2161 SERVICE MATER PlDIPS C h D HEADER 73. GOOD PSIG 57 BKR041 SERVICE MATER PUtF A ON GOOD 58 BKR042 SERVICE MATER PUNP B ON GOOD 5'P BKR043 SERVICE MATER PIIP C ON GOOD 60 BKR044 SERVICE MATER PINP D OFF GOOD
ROGRAM NAME :LRGTS2.E
~ OCT 08,92 R.E.
~ ~ GIHHA NUCLEAR POWER PLANT 07:15:00 TREND GROUP ASSIGHMEHT
SUMMARY
GROUP NAME GROUP DESCRIPT ION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPT ION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLW 1485. GOOD GPM 2 LRWST REFUELING WATER STORAGE TANK LVL 94.5 GOOD 3 WS033 33 FOOT LEVEL WIND SPEED 3.8 GOOD MPH 4 WDO33 33 FOOT LEVEL WIND DIRECTION 193. GOOD DEG.
5 WT033 33 FOOT LEVEL TEMPERATURE 52.9 GOOD DEGF 6 WT250 250 FOOT LEVEL TEMPERATURE 55.5 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEMP 2.6 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-COHTAINHENT 6.40678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDOWN LINE MONITOR 3.40701+01 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PAHEL 1.09283+00 GOOD MR/H 14 R10A COHTAIHHEHT IODINE MONITOR R10A 9.58719+01 GOOD CPM R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPM R12 COHTAINMEHT GAS MONITOR 7.38002+02 GOOD CPM R108 PLANT VENT IODINE MONITOR R108 4.30543+01 GOOD CPM 18 R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM 19 R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658+03 GOOD CPM 21 R19 STEAM GENERATOR BLOWDSS DRAIN 4.07174+03 GOOD CPM 22 R29 AREA 29-COHTAIHMEHT HIGN RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINMENT HIGH RANGE 5.09440-01 GOOD R/HR 24 R'l5 CONDENSER AIR EJECTOR EXHAUST 8.75390+04 HALM CPM 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6.AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9 HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14AS PLANT VENT CHAN 5-LOW RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOW RANGE GAS 4.39589-03 HALM UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 4.39337-03 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 4.39436-03 GOOD UCI/CC 35 R31 AREA 31 STEAH LINE A (SPIHG) 1.02040.02 GOOD MR/HR 36 R32 AREA 32 STEAM LINE 8 (SPIHG) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD 38 TCV03 CV BASEMENT LVL 6 FT TEHP ¹3 95.1 GOOD DEGF 39 TCV07 CV IHTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCV08 CV IHTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 4,
TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD DEGF
Time:
~7'essage:
2 INNA STATION 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 Station Event 3 Idd d I dI d IREPIPI.G."GI 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 Reactor Shutdown YES 0 Hi h Head S.I. Pum s N-31 N-32
~CPS
~CPS FI-924 FI-925 0 GPM O GP N-35 ~ AMPS 1A. INSERV B OOS N-36 AMPS 1B. INSERV TB OOS Avg. Nuclear Power 1C. INSERV TB OOS RCS Pressure gg.~PSIG BAST Level =
PRZR Level .I A RCP ING STOPPED Low Head S.X. Pum s B RCP UNNI STOPPED FI-626 O GPM lA S/G Level 1A. XNSERV T OOS RECIRC 1B S/G Level 1B. INSERV S B OOS RECIRC 1A S/G 1B S/G Pressure Pressure
Turbine/Generator LXN OFFLINE Containment S ra Pum s 4 KV Buses RGIZE DEENERGIZED FI-931A O GPM 480V Buses NERGXZE DEENERGXZED FI-931B O GP DC Batteries A)70 Bgg0 VOLTS 1A. INSERV TB OOS Cnmt Pressure nmt Sump A Level
~~PSIG 1B. INSERV T OOS FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg A Loop Cold Leg
- 0. OF Containmen ecirc Fans OF 1A. NSERV STBY OOS B Loop Hot Leg bOe OF 1B. NSE V STBY OOS B Loop Cold Leg OF 1C. IN ERV TB OOS RVLIS 1D. NSE STBY OOS
- CET Total Aux
~o~OF Post Accident Dampers OPEN CLOSED S/G A FW Flow O GPM S/G B Total Aux FW Flow M GPM Service Water Pum s 1A NS STBY OOS DIESEL GENERATORS 1B. NSE STBY OOS 1C. NSE STBY OOS A. *'RUNNING UNLOADED B OOS 1D. INSERV OOS B. RUNNING UNLOADED TB OOS A&B Header Pressure PSIG TSC RUNNING UNLOADED OOS Security RUNNING UNLOADED T OOS Com onent oolin Water Pum s 1A. SER STB OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Surge Tank Leve Aux. Feedwater m s 1A. INSERV OOS Standb Aux. Feed ater Pum s 1B. INSERV TB OOS 1C. INSERV TB OOS Turb. Driven INSERV B OOS 1D. INSERV TB OOS
~ST Level 2 FEET
- CET = Average of Selected Core Exit Thermocouples
OCT 8~ 1992 07:30 R. E. GINA SIMULATOR PAGE 1 TREND GROUP ASSIGQBi7 SUt(MARY GROl)P: EVENTl PROCEDURE'PIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U, 1 AT% ANTICIPATED TRANSIENT M/0 SCRAM No ATMS Goon 2 RXT REACTOR TRIP BREAKER STATUS NOT TRIP Goon 3 N31 SmSCE RANGE DETECTGR N-31 1. 00000+00 INHB CPS 4 N32 So(HCE RANGE DETECTOR N-32 1.00000%0 INHB CPS 5 N35 INTERMEDIATE RANGE DETECTOR N-35 6.91829M INHB A!(P 6 N36 INTERMEDIATE RAN6E DETECTOR N-36 6.42686M INHB AMP 7 NP AVERAGE l(XLEAR POWER 97.15 GOOD 7, 8 PRCS REACTOR COOLANT SYSTEM AVG PRESS 2252. GOOD PSIG LPIR PRESSURIZER AVERAGE LEVEL 48.1 600D e/
10 FRCLA REACTOR CGOLN(T LOOP A AVG FLGM 98.5 6008 y.
ll FRCLB REACTOR COOLANT LOOP 8 AVG FLGM 97.3 GOOD /0 12 RXT16 RCPA BREAKER CAUSE RX TRIP NOT TRIP GOOD 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP Goon 14 TSUBTC INCGRE TC SUBCOOLED MAfFaIN 45.4 6004 DEGF 15 LSGA STM GEN A NARROW RANGE AVG LEVEL 52.1 GOOD /
16 LSGB STM GEN 8 NARROM RA%E AVG LEVEL 52.1 Goon /
17 PSGA STM GEN A AVERAGE PRESPJRE 692. Goon PSIG 18 PSGB STtf GEN 8 AVERAGE PRESSURE 690. GOOD PSIG 19 GENBKRl GBGQTOR ON LINE BREAKER 1G1372 NOT TRIP GOOD 20 GENBKR2 GEtGQTOR ON LINE BREAKER 9X1372 NOT TRIP 6008 21 BUS11A BUS 11A SUPPLY BREAKER NOT TRIP GOOD 22 BUS118 BUS 118 SUPPLY BREAKER NOT TRIP GOOD 23 BUS12A NOT TERMINATED OW PPCS (7/19/91) NOT TRIP DEL 24 BUS128 NOT TERMINATED OW PPCS (7/19/91) NOT TRIP DEL 25 811A12A BUS 11A To 12A TIE BREAKER TRIPPED Goon 26 811812B BUS 118 TO 128 TIE BRENER TRIPPED GOOD 27 PCV CONTAINMENT AVERAGE PRESSURE .08 Goon PSIG 28 LSRFA CONTAINMENT SUMP A AVERAGE LEVEL 1.7 GOOD FEET 29 L0942E SUMP 8 LEVEL 8 INCHES (TRAIN A) LOWER GOOD 30 L0943E SU%' LEVEL 8 INCHES (TRAIN B) LOWER 600D 31 L0942D SSP 8 LEVEL 78 INC)iES (TRAIN A) LOWER GOOD 32 L0943D SU)P 8 LEVEL 78 INCHES (TRAIN 8) LOWER GOOD 33 L0942C SSP 8 LEVEL 113 INCHES(TRAIN A) LONER GOOD 34 L0943C SU)P 8 LEVEL 113 INCHES(TRAIN 8) J.ONER Goon 35 L09428 SUtP 8 LEVEL 180 INCHES(TRAIN A) LOWER GOOD 36 L09438 SUtP 8 LEVEL 180 INCHES(TRAIN 8) LOWER GOOD 37 L0942A SUMP 8 LEVEL 214 INCHES(TRAIN A) LONER GOOD 38 L0943A SUtP 8 LEVEL 214 INCHES(TRAIN 8) LONER Goon 39 T0409A RCLA HOT LEG TEMPERATURE 600.7 600D DE6F 40 T0410A RCLB HOT LEG TEMPERATURE 600.7 Goon DEGF 41 T0450 RCLA COLD LEG TEtfPERATlSE 543.3 GOOD DEGF 42 T0451 RCLB COLD LEG TE)fPERAT(SE 544.6 Goon DEGF 43 TAKAMID RCLA TAVG (TNT/TCOLD WIDE RNG) 572.0 Goon DEGF 44 TAVGBMID RCLB TAVG (THOT/TCOLD WIDE RNG) 572.7 GOOD DEGF 45 REACTOR VESSEL AVERAGE LEVEL 99.3 GOOD X 46 TCCGRE El. 1 INCORE TC AVERAGE TEMP 604.5 600~ DEGF 47 FAUXFMA S/G A TOTAL AUX FEEDMATER FLOW 0. GOOD GPM 48 FAUXFMB S/G 8 TOTAL AUX FEEDMATER FLOW 0. GOOD 49 BKR081 MTR AUXILIARYFEEDMATER PUMP A OFF GOOD 50 BKR082 MTR AUXILIARYFEEDMATER PUMP 8 OFF GOOD 51 V3505 AUX FM PUMP STEA)f SUPPLY VALVE A CLOSED GOOD 52 V3504 AUX FM PUt(P STEAM SUPPLY VALVE 8 CLOSED GOOD
OCT 8~ 1992 07:30 R. E, GINA SINLATOR PAGE 2 TREND GROUP ASSIGt4tlENT SUtNARY 6ROUP: EVEt4TI PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE NAL E. U.
53 FSIA SAFETY It43ECTION LOOP A AVG FLOM 0. GOOD GPtl 54 FSIB SAFETY IN.'tECTION LOOP 8 AVG FLOM 0. GOOD GPtl 55 P2160 SERVICE MATER PUtlPS A h B HEADER 81. GOOD PSIG 56 P2161 SERVICE MATER PUtlPS C h D HEADER 73. GOOD PSIG 57 BKR041 SERVICE MATER PUtlP A ON GOOD 58 BKR042 SERVICE MATER PUtlP 8 ON 600D 59 BKR043 SERVICE MATER PUtlP C ON GOOD 60 BKR044 SERVICE MATER PUtlP D OFF GOOD
PROGRAM NAHE :LRGTSZ.E OCT 08,92 R.E. GINNA NUCLEAR POWER PLANT 07:31:00 TREND GROUP ASSIGNHENT
SUMMARY
GROUP NAHE GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURREHT VALUE DUALITY CODE ENGR UNITS F0619 COMPONENT COOLING LOOP TOTAI. FLW 1485. GOOD GPM 2 LRWST REFUELING WATER STORAGE TANK LVL 94 ' GOOD x 3 WS033 33 FOOT LEVEL 'WIND SPEED ~ 3.6 GOOD HPH 4 WD033 33 FOOT LEVEL WIND DIRECTIOH 202. GOOD DEG.
5 WT033 33 FOOT LEVEL TEHPERATURE 53.0 GOOD DEGF 6 WT250 250 FOOT LEVEL TEMPERATURE 55.5 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEHP 2.5 GOOD DEGF 8 R01 AREA 1-CONTROL ROOH 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINHENT 6.40678+00 GOOD HR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD HR/H 11 R09 AREA 9-LETDOWN LINE MOHITOR 3.40701+01 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOGO HR/H 13 R35 AREA 35-PASS SAHPLE PANEL 1.09283+00 GOOD MR/H R10A CONTAIHHEHT IODINE MONITOR R10A 9.58719+01 GOOD CPH R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOGO CPH R12 CONTAINMENT GAS MONITOR 7.38002+02 GOOD CPH R108 PLANT VENT 1001NE MONITOR R108 4.30543<01 GOOD CPH R13 ~ AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM 19 R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658+03 GOOD CPH 21 R19 STEAH GEHERATOR SLOWDOWN DRAIN 4.07174+03 GOOD CPM 22 R29 AREA 29-CONTAINMENT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINHENT HIGH RANGE 5.09440.01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1 '5835+05 HALH CPM 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990.02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-HID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VEHT CHAN 5 LOW RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-HID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOW RANGE GAS 6.29179-03 HALH UCI/CC 33 R15A7 AIR EJECTOR CHAN 7 MID RANGE GAS 6.29392-03 HWRN UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 6.29436.03 GOOD UCI/CC 35 R31 AREA 31 STEAM LIHE A (SPING) 1.02040.02 GOOD MR/HR 36 R32 AREA 32 STEAH LINE 8 (SPING) 1.01048-02 GOOD HR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD 38 TCV03 CV BASEMENT LVL 6 FT TEHP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEHP'¹7 106.0 GOOD DEGF 40 TCV08 CV INTERHEDIATE LVL 6 FT TEHP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 Fl'EHP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD DEGF
Time:
Message: ~
(L7~4 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 Reactor Shutdown YES 0 Hi h Head S.I. Pum s N-3 1 CPS FI-924 0 GPM N-32 CPS FI-925 ~GPM N-35 AMPS 1A INSERV TB OOS N-36 f .'~CLAMPS 1B. INSERV TB OOS Avg. Nuclear Power 1C INSERV STB OOS RCS Pressure V PSIG BAST Level =
PRZR Level, A RCP UNNI STOPPED Low Head S.I. Pum s B RCP UNNIN STOPPED FI-626 GP 1A S/G Level .Q.t. 4 1A. INSERV B OOS RECIRC 1B S/G Level 1B. INSERV TB OOS RECIRC 1A 1B S/G S/G Pressure Pressure
~~PSIG RWST Level =
PSIG Turbine/Generator NLIN OFFLINE Containment S ra Pum s 4 KV Buses ERGIZE DEENERGIZED FI-931A 0 GPM 480V Buses NERGIZE DEENERGIZED FI-931B GP DC Batteries A~Sa VOLTS B/ZO VOLTS 1A. INSERV OOS nmt Pressure ~GPSIG 1B. INSERV TB OOS nmt Sump A Level FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg A Loop Cold Leg .
dna
~)~/OF f OF Containme 1A.
t SER ecirc STBY Fans OOS B Loop Hot Leg dO. OF 1B. NSER STBY OOS B Loop Cold Leg VS'. OF 1C. INSERV TB OOS RVLIS 'KX-.k ~ 1D. NSER ST Y OOS
~GPM 0 GPM Service Water Pum s 1A. STBY OOS DIESEL GENERATORS 1B. STBY OOS 1C. ER STBY OOS A. RUNNING UNLOADED TB OOS 1D. INSERV TB OOS B. RUNNING UNLOADED STB OOS A&B Header Pressure PSIG TSC RUNNING UNLOADED OOS Security RUNNING UNLOA D B OOS Com onen olin Water Pum s 1A. E ST Y OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Aux. Feedwater m s Surge Tank Level = ~v 1A. INSERV TB OOS Standb Aux. Fe dwater Pum s 1B. INSERV B OOS 1C. INSERV OOS Turb. Driven INSERV TB OOS 1D INSERV TB OOS ST Level ~g FE
- CET = Average of Selected Core Exit Thermocouples
8i 1992 07:44 R. E. GINA SltmLATOR PAGE 1 TREtfD GROUP ASSIG)IEt(T SU)L%8Y 6RQUP: EVENT1 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U.
1 ATl6 ANTICIPATED TRANSIENT M/0 SCRN No ATMS GOOD 2 RXT REACTOR TRIP BREAKER STATUS NQT TRIP GOOD 3 N31 SO(ICE RAt(GE DETECTOR N-31 1.00000+00 INHB CPS N32 SINCE RAtiGE DETECTOR N-32 1.00000+00 INHB CPS 5 N35 INTERtfEDIATE RAN6E DETECTOR N-35 6.85487M INHB Al(P 6 N36 INTER)(EDIATE RAN6E DETECTOR N-36 6.36793M INHB At(P 7 NP AVERAGE NUCLEAR PQMER 96.19 6009 y.
8 PRCS REACTOR COOLANT SYSTEH AVG PRESS 2280. HMRt( PSIG 9 LPIR PRESSURIIER AVERAGE LEVEL 48.7 GQQD 7.
10 FRCLA RFAC70R CCQLANT LQQP A AVG FLOM 98.4 6009 11 FRCLB RECTOR CQOLAtfT LOOP B AVG FLQM 97.3 600D X 12 RX716 RCPA BREAKER CAUSE RX TRIP NOT TRIP 600D 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6000 14 TSUBTC INCORE 7C SUBCOQLED NRCIN 47.2 DEGF Goo'2.2 15 LSGA STt( GEtf A NARROM RANGE AVG LEVEL 6009 Ã 16 LS6B STH GEN B NARROM RANGE AVG LEVEL 52.2 6000 /
17 PSGA STtf GEN A AVERAGE PRESSURE 7()0. GOOD PSIG 18 PSGB STH GEN B AVERAGE PRESSURE 698. GOOD PS16 19 GEtfBKR1 GEtGQTOR ON LINE BPEAKER 161372 NQT TRIP GOOD 20 GENBKR2 GBERATOR ON LINE BREAKER 9X1372 NOT TRIP GOOD 21 BUSl IA BUS iiA SUPPLY BREAKER NOT TRIP 600D 22 BUS11B BUS 11B SLYLY BREAKER NQT TRIP 6009 23 BUS12A NOT TERMINATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TER)(INATED Otf PPCS (7/19/91) NOT TRIP DEL 25 Bl 1A12A BUS llA To 12A TIE BRENER TRIPPED GOOD 26 BiiB12B BUS 11B TQ 128 TIE BRENER TRIPPED GOOD 27 PCV CONTAltfMEt(7 AVERAGE PRESSURE ~ Oh GOOD PSIG 28 LS(SPA CQNTAINtfEtlT SU)(P A AVERAGE LEVEL 1.7 GQQD FKT 29 L0942E SEP 8 LEVEL 8 ItfCHES (TRAIN A) LONER GOOD 30 L0943E SU%' LEVEL 8 INCHES (TRAIN 8) LOMER 6009 31 L0942D SUNUP B LEVEL 78 INCHES (TRAIN A) LONER GOOD 32 L09430 SUNUP B LEVEL 78 INCf.:cS (TRAIN B) LOMER 600 D 33 L0942C SU%' LEVEL 113 INCHES(TRAIN A) LOMER 600 D 34 L0943C SU%' LEVEL 113 INCHES(TRAIN B) LONER 600D
- 35. L0942B SUtP B LEVEL 180 INCHES(TRAIN A) LONER GOOD 36 L0943B SUt1' LEVEL 180 INCHES(TRAIN B) LOWER GOOD 37 L0942A SUtp B LEVEL 214 INCHES(TRAIN A) LONER GOOD 38 L0943A - SU)P B LEVEL 214 INCHES(TRAIN B) LOMER 6009 39 70409A RCLA HOT LEG TEMPERATURE 600.9 GOOD DEGF 40 70410A RCLB HOT LEG TEt(PERATUK 600.9 GOOD KBF 41 70450 RCLA COLD LEG TEtlPERATNE 544.1 GOOD DEGF 42 70451 RCLB COLD LEG TEtfPERATNE 545.4 GOOD DE6F 43 TAVGAMID RCLA TAVG (THOT/TCOLD MIDE RNG) 572.5 600D DEGF 44 TAVGBMID RCLB TAVG (THOT/TCOLD MIDE RNG) 573.1 GQQD DEGF 45 LRV RGtTOR VESSP AVERAGE LEVEL 99.3 GOOD X 46 TCCORE El.l IWCORE TC AVERAGE TEt(P 604.6 Goo'.
DEGF 47 FAUXFMA S/G A TOTAl AUX FEETiMATER FLI{ 6000 Pt(
48 FAUXFMB S/G B .OTAL AUX FEEDMATER FLOM 0. 6000 GPt(
49 BKR081 N7R AUXILIARYFEEDMATER PU)(P A OFF GOOD 50 BKR082 MTR AUXILIARYFEEDMA7ER PUHP B OFF GOOD 51 V3505 AUX FM PUt4P STEAtl SUPPLY VALVE A CLOSED GOOD 52 V3504 AUX Rl PUicP STEA)( SUPPLY VALVE B CLOSED 600D
OCT 8~ 1992 07:44 R. E. GINA SIMULATOR PAGE 2 TREND 6ROUP ASSIGNNEhT RNNARY 6ROUP: EVENTl PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U.
53 FSIA SAFE IN:ECTION LOOP A AVG FLOW 0. 6009 9'N 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. 6009 GPN 55 P2ib0 SERVICE WATER PNFS A & B HEADER 81. 6009 PSIG 5b P2ibi SERVICE WATER PlÃi'S C & D HEADER 73. GOOD PSIG 57 BKR041 SERVICE WATER PUNP A ON 6000 58 BKR042 SERVICE MATER PUP B ON GOOD 5'9 BKRO43 SERVICE MATER PUtF C ON GOOD b0 BKR044 SERVICE WATER PtNP D OFF GOOD I
E-0-J
GRAM NAME :LRGTSZ.E
~ OCT 08,92
.E.
~ ~ GINNA NUCLEAR PSIER PLANT 07:46:00 TREND GROUP ASSIGNMENT
SUMMARY
GROUP NAHE GROUP DESCRIPTIOH EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPOHENT COOLING LOOP TOTAL FLll 1485. GOOD GPM 2 I LRHST REFUELIHG HATER STORAGE TANK LVL 94.5 GOOD 3 'NS033 33 FOOT LEVEL IJIND SPEED 3.8 GOOD MPH 4 l$ 033 33 FOOT LEVEL WIND DIRECTION 215. GOOD DEG.
5 NT033 33 FOOT LEVEL TEMPERATURE 53.5 GOOD DEGF 6 MT250 250 FOOT LEVEL TEMPERATURE 55.6 GOOD DEGF 7 lQT2 250 TO 33 FOOT LEVEL DELTA TEMP 2.1 GOOD OEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINMENT 6.40678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDOWN LINE MONITOR 3.40701+01 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINMENT IODINE MONITOR R10A 9.58715401 GOOD CPM R1'1 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPM R12 CONTAINMENT GAS MONITOR 7.38002+02 GOOD CPM R10B PLANT VENT IODINE MONITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID HASTE DISPOSAL MONITOR 2.78658+03 GOOD CPH 21 R19 STEAH GEHERATOR BLSSOMN DRAIN 4.07174+03 GOOD CPM 22 R29 AREA 29-COHTAINHEHT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINMEHT HIGH RANGE 5.09440.01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.25835+05 HALH CPM 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS 1.89699.07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-HID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAH 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOU RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLAHT VENT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOU RAHGE GAS 6.29179-03 HALH UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-HID RAHGE GAS 6.29392-03 HEARN UCI/CC 34 R'l5A9 AIR EJECTOR CHAN 9 HI RANGE GAS 6.29436-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 1.02040-02 GOOD MR/HR 36 R32 AREA 32 STEAM LINE 8 (SPING) 1.01048-02 GOOD MR/NR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD 38 TCV03 CV BASEMENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCV08 CV INTERHEDIATE LVL 6 FT TEHP ¹8 '106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEHP ¹17 117.5 GOOD 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 Emer enc lyif Cla G Id P P ification dis ussions are in ro r s.
d I d. ~ddli if 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).
- 2) Ensure AO simulates checking manual valve 3507A ("A" S/G ARV Isolation Valve, Bypass Valve) closed.
- 3) 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).
- 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
- 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 DATE' PAGE OF STATION'OB:
SkmrC~ c Zg @y 5(gg~ g.gg~ MADE BY:
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 ii 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 ENGINEERED SAFEGUARDS Reactor Shutdown ~YES ~O Hi h Head S.I. Pum s N-3 1 O CPS FI-924 O GPM N-32 O CPS FI-925 0 GPM N-35 'I~OS AMPS 1A. INSERV B OOS N-36 CW - AMPS 1B. INSERV TB OOS Avg. Nuclear Power Pressure 1'NSERV =
TB OOS RCS PSIG BAST Level RCP'NNI
~2.S.C PRZR Level 9 7 ~
A G STOPPED Low Head S.I. Pum s B RCP RUNN G STOPPED FI-626 O G M 1A S/G Level 1B S/G Level lA S/G Pressure
~. I
~'~PSIG 0
1A. INSERV 1B. INSERV RWST Level =
TB OOS RECIRC OOS RECIRC 1B S/G Pressure PSIG Turbine/Generator N OFFLINE Containment S ra Pum s 4 KV Buses RGIZED DEENERGIZED FI-93 1A O GPM 48OV Buses NERGIZ DEENERGIZED FI-931B 2) GP DC Batteries A$ 54VOLTS B/SOVOLTS lA. INSERV TB OOS nmt Pressure ~ b lo PSIG 1B. INSERV TB OOS nmt Sump A Level ~ FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop A Loop Hot Leg Cold Leg
~i+
53'4 7 OF Containment ecirc Fans 7 OF 1A. SE STBY OOS B Loop Hot Leg 9 OF 1B. NSER STBY OOS B Loop Cold Leg 9. OF 1C. INSE V B OOS RVLIS 1D. SE STBY OOS
- CET S/G A Total Aux FW Flow
~.3 O OF GPM Post Accident Dampers OPEN LOSE 9/G B Total Aux FW Flow O GPM Service Water Pum s 1A. SERV STBY OOS DIESEL GENERATORS 1B. NSE STBY OOS 1C. NSERV ST Y OOS A. RUNNING UNLOADED STB OOS 1D. IN V STB OOS B. RUNNING UNLOADED S B OOS A&B Header Pressure 8 PSZG TSC RUNNING UNLOADED STBY OOS Security RUNNING UNLOA D TB OOS Com onent Co lin Water Pum s 1A. ST OOS ENGINEERED SAFEGUARDS 1B. INSERV T OOS Aux. Feedwater Pum s Surge Tank Level = ~'G 1A. INSERV TB OOS Standb Aux. Feed ater Pum s 1B. INSERV TB OOS 1C. INSERV TB OOS Turb. Driven NSERV STB OOS 1D. INSERV T Y OOS ST Level ~~FE
- CET, = Average of Selected Core Exit, Thermocouples
OCT 8i 1992 07:59 R. E. GINA SINULATOR PA6E 1 TREND GROUP ASSIGHNEI(T SUGARY GROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID KSCRI TION E. U.
1 ATKi ANTICIPATED TRAHSIEHT M/0 SCRAN NO ATMS GGGD 2 RXT REACTOR TRIP BREAKER STATUS HQT TRIP 600D 3 N31 SONCE RANGE DETECTOR N-31 1.00000+00 INHB CPS N32 SIKE RANGE DETECTOR N-32 1.000NMO IHHB CPS 5 N35 INTERNEDIATE RANGE DETECTOR N-35 7.01454-04 INHB ANP 6 N36 INTERNEDIATE RANGE DETECTOR N-36 6.51626M INHB ANP 7 NP AVERAGE NUCLEAR POWER 98.61 6009 /
8 PRCS REACTOR COOLANT SYSTEN AVG PRESS 2263. HMRN PSIG 9 LPZR PRESSURIZER AVERAGE LEVEL 44.7 GOOD X 10 FR(" A REA"TOR COOLANT LOOP A AVG FLOW 98.9 6009 I/
ll FRCLB REACTOR COOLNT LOOP B AVG FLOW 97.8 600D X 12 RXT16 RCPA BREAKER CRUSE RX TRIP NOT TRIP GOOD 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED NARBIN 47.8 600<< KGF 15 LSBA STN GEN R NARROW RANGE AVG LEVEL 52.2 6009 >/
16 LSBB STN GEH B NARROW RANGE AVG LEVEL 52.1 6009 7.
17 PSBA STN GEN A AVERAGE PRESSURE 666. 6009 PSIG 18 PSGB STN GEN B AVERAGE PRESSURE 668. GOOD PSIG 19 GENBKRl GBERATOR ON LINE BREAKER lG1372 NOT TRIP GGQD 20 GENBKR2 GENERATOR GN LINE BREAKER 9X1372 NQT TRIP GOOD 21 BUS11A BUS liA SUPPLY BREAKER NOT TRIP GOOD 22 BUS11B BUS 11B SUPPLY BREAKER HOT TRIP 6009 23 BUS 12A NOT TERNINATED Ot( PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERNIHATED ON PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS 11A TO 12A TIE BRENER TRIPPED 6009 26 B11B12B BUS 1lB To 12B TIE BRENER TRIPPED 6009 27 PCV COHTAINNENT AVERAGE PRESSURE ~ 06 6009 28 LS(IPA CONTAIN)(ENT SUNP A AVEImBE LEVEL 1 ~ 8 GOOD 29 L0942E SSP B LEVEL 8 INCHES (TRAIN A) Lo)IER GOOD 30 L0943E SU)P B LEVEL 8 INCHES (TRAIN B) LO)IER GOOD 31 L0942D SU)P B LEVEL 78 INCHES (TRAIN A) LG)E'ER GOOD 32 L0943D SNP B LEVEL 78 INCHES (TRAIN B) LONER 6009 33 L0942C SU@ B LEVEL 113 INCHES(TRAIN A) LOWER 6009 34 L0943C SU%' LEVEL 113 INCHES(TRAIN B) LONER GOOD 35 L0942B SU%' LEVEL 180 INCHES(TRAIN A) LOWER GOOD 36 L0943B SSP B LEVEL 180 INCHES(TRAIN B) LONER 6009 37 L0942A SSP B LEVEL 214 INCHES(TRAIN A) LONER 6009 38 L0943A SSP B LEVEL 214 INCHES(TRAIN B) LONER 6009 39 T0409A RCLR HOT LEG TENPERATUlK'CLB 598.7 6009 KBF 40 T0410A HOT LEG TENPERATURE 598.7 GGGD K6F 41 T0450 RCLA COLD LEG TEIIPERAT(SE 539.9 GOOD KGF 42 T0451 RCLB COLD LEG TENPERAT(HE 541 F 6 6009 DE6F 43 TAVBAMID RCLA TAVG (THOT/TCOLD WIDE RHB) 569.3 6009 KGF 44 TAVBBWID RCLB TAVG (THOT/TCOLD WIDE RNG) 570.2 6009 KGF LRV REACTOR VESSEL AVERAGE LEVEL 99.5 GOOD 46 TCCORE El. 1 INCORE TC AVERA6E TENiP 602.3 600<< DEGF 47 FAUXFWA S/G A TOTAL AUX FEEDWATER FLOP 0. 6009 PN 48 FAUXFMB S/6 B TOTAL AUX FEEDWAMa FLOW 0. GQGD GPN 49 BKR081 NTR AUXILIARYFEEDMRTER PU)IP A OFF 6009 50 BKR082 NTR AUXILIARYFEEDMATER PUNP B OFF 6009 51 V3505 AUX FM PUIF STENI SUPPLY VALVE A CLOSED GOOD 52 V3504 AUX FM PUNP STEAN SUPPLY VALVE B CLOSED 6009
0 OCT Gs 1992 07:59 R. E. GINA SltiULATOR PAGE 2 TREND GROUP ASSIGtttiENT SUtitiARY 6ROUP: EVEt)TI PROCEDURE: EPIP 1-5 PLAtlT STATUS POINT ID DESCRIPTION VALLEY QUAL E. U.
53 FSIA SAFETY INJECTION LOOP A AVG FLOM 0. GOOD G.V 54 FSIB SAFETY INJECTION LOOP B AV6 FLOM 0. GOOD IFN 55 P2160 SERVICE MATER PlIPS A h B HEADER 81. GOOD PS16 56 P2161 SERVICE MATER PNPS C 5 D HEADER 73. GOOD PSIG 57 BKR041 SERVICE MATER PNiP A ON GOOD 58 BKR042 SERVICE MATER PUtiP B ON GOOD 59 BKR043 SERVICE MATER PlIP C ON GOOD 60 BKR044 SERVICE MATER PUtiP D OFF GOOD EMJ
GRAM NAME :LRGTSZ.E
~ OCT 08,92
.E.
~ ~ GlkkA NUCLEAR POWER PLANT 08:00:00 TREND GROUP ASSIGNHEHT
SUMMARY
GROUP kAME GROUP DESCR IPT ION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURREHT VALUE QUALITY CODE EHGR UNITS 1 F0619 COMPOHENT COOLING LOOP TOTAL FLW 1485 ~ GOOD GPM 2 LRWST REFUELIHG WATER STORAGE TANK LVL 94.5 GOOD 3 WS033 33 FOOT LEVEL WIHD SPEED 3.6 GOOD MPH W0033 33 FOOT LEVEL WIND DIRECTIOH 222. GOOD DEG.
5 WT033 33 FOOT LEVEL TEMPERATURE 57.7 DEGF 6 WT250 250 FOOT LEVEL TEHPERATURE 58.0 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEMP 0.3 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD HR/H 9 R02 AREA 2-CONTAINMENT 6.40678+00 GOOD HR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDOWN LINE MOHITOR 3.40701+01 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAHPLE PANEL 1 '9283+00 GOOD MR/H 14 R10A CONTAINMENT IODINE MONITOR R10A 9.58719+01 GOOD CPH R11 CONTAINMENT AIR PARTICULATE 5 ~ 18901+02 GOOD CPM R12 CONTAINMENT GAS MONITOR 7.38002+02 GOOD CPM R10B PLANT VENT IODIHE MONITOR R10B 4.30543t01 GOOD CPH R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID WASTE DISPOSAL MOHITOR 2.78658i03 GOOD CPM 21 R19 STEAM GENERATOR SLOWDOWN DRAIN 4.07174+03 GOOD CPM 22 R29 AREA 29-CONTAINHEHT HIGH RAHGE 5.05861-01 GOOD R/HR R30 AREA 30-CONTAINHEHT HIGH RANGE 5.09440-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.25835+05 HALM CPM 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS 1.89699.07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD HR/HR 27 R12A7 CV VENT CHAN 7-HID RANGE GAS 3.57435-05 UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOW RAHGE GAS 4 '0312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAk 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOW RANGE GAS 6.29179-03 HALH UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 6.29392-03 HWRN UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-'Hl RANGE GAS 6.29436-03 UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 1.02040.02 GOOD MR/HR 36 R32 AREA 32 STEAM LINE 8 (SPING) 1.01048-02 GOOD HR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD X 38 TCV03 CV BASEMENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEHP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERHEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 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:
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).
Time: ~8~1 Message: ~1 Qgn~in gg
- 6) Operators may request Auxiliary Operator to isolate the "B" S/G ARV.
- 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 YES 0 Hi h Head -S.I. Pum s N-31 N-32
~CPS CPS FI-924 FZ-925 ~GPM GPM N-35 AMPS 1A. INSERV T OOS N-36 AMPS 1B. INSERV TB OOS Avg. Nuclear Power 1C. INSERV B OOS RCS Pressure PSIG BAST Level =
PRZR Level A RCP UNNING STOPPED Low Head S.I. Pum s B RCP UN N STOPPED FI-626 0 GPM 1A S/G 1B S/G Level Level lA S/G Pressure
~e 1A. INSERV 1B. INSERV TB OOS RECIRC TBY OOS RECIRC 3 PSIG RWST Level =
1B S/G Pressure .0 PSIG Turbine/Generator ONL FFLINE Containment S ra Pum s 4 KV Buses ERGIZ DEENERGIZED FZ-931A~GPM 480V Buses RGIZ DEENERGIZED FI-931B~GPM DC Batteries A~SaVOLTS B ($ 0 VOLTS 1A. INSERV S B OOS Cnmt Pressure . o6 PSIG 1B. INSERV TB OOS Cnmt Sump A Level ~FEET NaOH Tank Level =
Cnmt Sump B Level A Loop Hot Leg
~g
~feZ INCHES OF Contain Recirc Fans A Loop Cold Leg ~ST&OF 1A. NSE STBY OOS B Loop Hot Leg OF 1B. NSE STBY OOS B Loop Cold Leg mmkoF 1C. IN V TB OOS RVLIS ~ 1D. SER STBY OOS
- CET ~1 Post Accident Dampers OPEN LOS D S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow O'PM Service Wate Pum s 1A. SE STBY OOS DIESEL GENERATORS 1B. NSE STBY OOS 1C. NSE STBY OOS A. RUNNING UNLOADED T OOS 1D. INSERV TB OOS B. RUNNING UNLOADED TSC RUNNING UNLOADED T OOS OOS A&B Header Pressure ~PS1G Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. SER STBY OOS ENGINEERED SAFEGUARDS 1B. INSERV TB OOS Aux. Feedwate m s Surge Tank Level = ~'o 1A. INSERV OOS Standb Aux. Fee water Pum s 1B. INSERV TB OOS 1C INSERV B OOS ~
Turb. Driven INSERV STB 1D. INSERV TB CST Level ~~F OOS OOS
- CET = Average of Selected Core Exit Thermocouples
Gi 1992 08:14 R. E. GINA SIMULATOR PAGE 1 TREND GROUP ASSIGIST SUtIARY GROUP: EVENT1 PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE E. U.
1 ATt6 ANTICIPATED TRANSIENT M/0 SCRAM No ATN 600D 2 RXT REACTOR TRIP BREAKER STATUS NOT TRIP GOOD 3 N31 SolSCE RANGE DETECTOR N-31 1.00000+00 INH8 CPS 4 N32 SO(SCE RAt(GE DETECTOR N-32 1.00000+00 INHB CPS
'5 N35 INTERMEDIATE RANGE DETECTOR N-3S 6.66807M INHB AMP 6 N36 INTERMEDIATE RANGE DETECTOR N-36 6. 16593M INHB AMP 7 NP AVERAGE NUCLEN POWER 93.56 6009 8 PRCS REACTOR CGOUIT SYSTEM AVG PRESS 2264. 6000 PSIG 9 LP2R PRESSURI 2ER AVERAGE LEVEL 47.9 Boon /
10 FRCLA REACTOR COOLA%'OOP A AVG FLOW 98.4 6009 K il FRCLB REACTOR COOLANT LOOP 8 AVG FLOW 97.3 GGGD /
12 RXT16 RCPA BREAKER CAUSE RX TRIP NOT TRIP 6000 13 RXTD RCPB BREAKER CAUSE RX TRIP NOT TRIP 6000 14 TSUBTC INCGRE TC SUIG)GLED NARiIN 47.9 Gooe KGF 15 LSGA STM GEN A NARROW RANGE,AVG LEVEL S2.0 Boon /
16 LS68 STM GEN 8 NARROW RANGE AVG LEVEL 52.1 6000 17 PSGA STM GEN A AVERAGE PRESE)RE 703. 6009 psiG 18 PSGB STM 6EN 8 AVERAGE PRESSURE 701. GOOD PSI6 19 GENBKRl GYRATOR ON LINE BREAKER 161372 NOT TRIP 6009 20 GENBKR2 GBERATOR ON LINE BREAKER 9X1372 NGT TRIP 600D 21 BUSliA BUS 11A SUPPLY BREAKER NOT TRIP GOOD 22 BUS118 BUS 118 SUPPLY BREAKER NOT TRIP 6000 23 BUS12A t<OT TERMINATED 0)I PPCS (7/19/91) NOT TRIP DEL 24 BUS128 NGT TERMII(ATED ON PPCS (7/19/91) NOT TRIP DEL 25 811A12A BUS 11A TO 12A TIE BRENER TRIPPED Goon 26 8118128 BUS 118 TQ 128 TIE BRENER TRIPPED GOOD 27 PCV COt(TAINMENT AVERAGE PRESSURE .06 600 D PSIG 28 LSNPA CONTAINMENT SUMP A AVERAGE LEVEL 1.8 6009 FEET 29 L0942E SUIP 8 LEVEL 8 INCHES (TRAIN A) LONER 6000 30 L0943E SUIP 8 LEVEL 8 INCHES (TRAIN 8) LOWER Goon 31 L0942D SUIP 8 LEVEL 78 INCHES (TRAIN A) LOWER Goon 32 L0943D SU)P 8 LEVEL 78 INCHES (TRAIN 8) LONER 6000 33 L0942C SU)P 8 LEVEL 113 INCHES(TRAIN A) LONER GOOD 34 L0943C SUtP 8 LEVEL 113 INCHES(TRAIN 8) LONER 6000 35 L09428 SU)P 8 LEVEL 180 INCHES(TRAIN A) LOWER GOOD 36 L09438 SUtP 8 LEVEL 180 INCHES(TRAIN 8) LOWER Goon 37 L0942A SU)P 8 LEVEL 214 INCHES(TRAIN A) LONER 6000 38 L0943A SIP 8 LEVEL 214 INCHES(TRAIN 8) LONER BGGD 39 T0409A RCLA HOT LEG TEMPERATUfK 599.2 6009 DEGF 40 T0410A RCLB HOT LEG TEMPERATURE 599.2 600D DEGF 41 T0450 RCLA COLD LEG TE)IPERAT(HE 543.5 BGGD DE6F 42 T0451 RCLB COLD LEG TE)IPERAT(SE 544.8 6000 DEBF 43 TAVGAMID RCU) TAVG (THOT/TCOI.D WIDE RNG) 571 ' Boon 9 GF 44 TAVBBWID RCLB TAVG (THGT/TCGLD WIDE RNG) 572.0 GOOD DEGF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.3 GOOD /
46 TCCORE Ei.l INCORE TC AVERAGE TEMP 602.6 Booe DEGF 47 FAUXFMA S/6 A TOTAL AUX FEHIATER FLOM 0. GOOD GPM 48 FAUXFMB S/6 8 TOTAL AUX FEEDMATER FLOW 0. 6000 6PM 49 BKR081 MTR AUXILIARYFEEDNATER PlNP A OFF GOOD 50 BKR082 MTR AUXILIARYFEEDMATER PlNP 8 OFF GGGD 51 V3505 AUX FM PU)P STEA)I SUPPLY VALVE A CLOSED, GGGD 52 V3504 AUX FM PUI(P STEA)I SUPPLY VALVE 8 CLOSED 6000
OCT 8~ 1992 08: 14 R. E. GINA S1%LATOR PAGE 2 TREND GROUP ASSIGNMENT SUtDIRY 6ROUP: EVM'I PRXEDURE! EPIP 1-5 PLAftT STATUS POINT ID DESCRIPTION VALLEY DUAL E. U.
53 FSIA SAFETY INJECTION LOOP A AVG FLOW 0. GOOD PN 54 F GIB SAFETY INJECTION LOOP B AVG FLOW 0. GOOD GPN 55 P2 160 SERVICE MATER PfIPS A h B HEADER 82. GOOD PSIG 56 P2161 SERVICE WATER PUffPS C 5 D HEADER 730 GOOD PSIG 57 BKR041 SERVICE WATER PUffP A ON GOOD 58 BKR042 SERVICE MATER PUNP B ON GOOD 59 BKR043 SERVICE WATER PUtfP C ON 600D 60 BKR044 SEfNICE MATER PUtfP D OFF GOOD
OGRAM NAHE :LRGTSZ.E OCT 08,92 R.ED GINNA NUCLEAR PONER PLANT 08:15:00 TREND GROUP ASSIGHHENT SUHHARY GROUP NAME GROUP DESCRIPT IOH EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLll 1485. GOOD GPH 2 LRMST REFUELIHG MATER STORAGE TANK LVL 94.5 GOOD 3 MS033 33 FOOT LEVEL lllND SPEED 3.6 GOOD MPH 4 MD033 33 FOOT LEVEL MIND DIRECTION 194. GOOD DEG.
5 MT033 33 FOOT LEVEL TEMPERATURE 58.7 GOOD DEGF 6 llT250 250 FOOT LEVEL TEMPERATURE 58.0 GOOD DEGF 7 lST2 250 TO 33 FOOT LEVEL DELTA TEMP .0.7 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINMENT 6.40678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946i00 GOOD MR/H 11 R09 AREA 9-LETDSN LINE MONITOR 3.40701+01 GOOD MR/H 12 R34 AREA 34 AUX BLDG CV SPRAY PUMP 9.09354.01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PAHEL 1.09283+00 GOOD MR/H 14 R10A COHTAIHMENT IODINE MONITOR R10A 9.58719+01 GOOD CPM 15 R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPM R12 CONTAINMENT GAS MOHI TOR 7.38002+02 GOOD CPM R108 PLAHT VENT IODINE MOHITOR R'IOB 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM 19 R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID IIASTE DISPOSAL MONITOR 2.78658i03 GOOD CPM 21 R19 STEAM GENERATOR BLOSOMH DRAIN 4.07174+03 GOOD CPM'/HR 22 R29 AREA 29-CONTAINMEHT HIGH RANGE 5.05861-01 GOOD 23 R30 AREA 30-COHTAINHEHT HIGH RANGE 5.09440.01 GOOD R/NR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.25835+05 HALM CPM 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS 1.89699.07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3 '7435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAH 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOU RAHGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RAHGE GAS 6.86543.05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9 HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOW RANGE GAS 6.29179.03 HALM UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 6.29392-03 HNRH UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 6.29436-03 GOOD UCI/CC 35 R31 AREA 3'I STEAM LINE A (SPING) 1.02040.02 GOOD MR/HR 36 R32 AREA 32 STEAM LINE B (SPING) 1.01048.02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD x 38 TCV03 CV BASEMEHT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERHEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEHP ¹17 117.5 GOOD 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 Simulated Plant Condi ions: See Attached Mini-Scenario T
~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.
ROCHESTER GAS ANO ELECTRlC CORPORATlON 4% 140 S GINNA STATION: DATE: PAGE OF lOB: SA'&7GH o MADE BY:
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: ADFCS Trouble G-22 In Alarm INITIALCONDITIONS: 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 DIGITALSCAN 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 Nll Message: ~1
~ NA NT Tl N 19 2 EVALUATED EXER I E MESSA E F RM
~f:
Nle 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 MAJOR P2Q&METERS ENGINEERED SAFEGUARDS Reactor Shutdown YES~@ Hi h Head S.I. Pum s N-31 FI-924 N-32 N-35 O
C7 CPS CPS AMPS FI-925 1A.
~GP O GPM INSERV TB OOS N-36 AMPS 1B INSERV TB OOS Avg. Nuclear Power 1C. INSERV TB OOS RCS Pressure 2.X.LZ PSIG BAST Level =
PRZR Level A RCP STOPPED Low Head S.I. Pum s B RCP UNNING STOPPED FI-626 O G M 1A S/G Level ~z. I 1A. INSERV TB OOS RECIRC 1B 1A S/G S/G Level Pressure
~.. I PSIG 1B. INSERV RWST Level =
TB OOS RECIRC 1B S/G Pressure o7 PSIG Turbine/Generator NLI OFFLINE Containment S ra Pum s 4 KV Buses ERGIZ DEENERGIZED FI-931A 0 GPM 480V Buses ERGIZED DEENERGIZED FI-931B~GPM DC Batteries A/SOVOLT BISO VOLTS 1A. INSERV TB OOS Cnmt Pressure ~< ~PSIG 1B. INSERV TB OOS Cnmt Sump A Level ~ FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg 9 OF Containm ecirc Fans A Loop Cold Leg ~$ . OF 1A. SE STBY OOS B Loop Hot Leg OF 1B. NSER STBY OOS B Loop Cold Leg OF 1C. INSERV B OOS RVLIS 1D. S STBY OOS
- CET 40 .3 OF Post Accident Dampers OPEN LOSED S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow 0 GPM Service ter Pum s 1A. NSE STBY OOS DIESEL GENERATORS 1B. STBY OOS 1C. NSE STBY OOS A. RUNNING UNLOADED B OOS 1D. INS RV B OOS B. RUNNING UNLOADED TB OOS A&B Header Pressure 8 PSIG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB OOS Com onen Coolin Water Pum s 1A. NSER STBY OOS ENGINEERED SAFEGUARDS, 1B. INSERV STB OOS Surge Tank Leve = SO Aux. Feedwate Pum s 1A. INSERV OOS Standb Aux. Feed ater Pum s 1B. INSERV T OOS 1C. INSERV OOS Turb. Driven NSERV TB OOS 1D. INSERV TB OOS CST Level 2. FE
- CET = Average of Selected Core Exit Thermocouples
8~ 1992 08:30 R. E. GIM(A Sit(ULATOR PAGE 1 TREND GROUP ASSIGNNENT SUt(MY 6ROUP: EVENT1 PROCEDURE'PIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U.
1 ATMS ANTICIPATED TRANSIEhT M/0 SCRAt( NO ATWS 6009 2 RXT REACTOR TRIP BREAKER STATUS NOT TRIP 6009 3 N31 SONCE RANGE DETECTOR H-31 l. 00000%0 INH9 CPS 4 N32 SGNCE RAt(GE DETECTOR N-32 1.005&00 INHB CPS N35 INTER)(EDIATE RANGE DETECTOR N-35 6.48633M INHD At)P 6 N36 INTER)(EDIATE RANGE DETECTOR N-36 6.02558-04 INH8 At(P 7 NP AVERAGE NUCLEAR POWER 91.19 6009 /I 8 PRCS REACTOR CGOUt(T SYSTBI AVG PRESS 2262. 6009 PSIG 9 LPLR PRESSURI IER AVERAGE LEVEL 46,7 6009 X 10 FRCLA REACTOR COOLANT LOOP A AVG FLOW 98.5 6009 y.
if FRCLB REACTOR COOLANT LOOP B AVG FLQM 97.3 6009 7.
12 RXTI6 RCPA BREAKER CAUSE RX TRIP NQT TRIP 6009 13 RXT17 RCPB BREAKER CAUSE RX TRIP NGT TRIP 6009 14 TSUBTC INCORE TC SUBCOQLED HARBIN 49.5 600~ KGF 15 LSGA STt( GEt( A NARROW RANGE AVG LEVEL 52.1 6009 /
16 LSGB STN GEN B NARROW RANGE AVG LEVEL 52.1 6009 /I 17 PSGA STN GEt( A AVERAGE PRESSURE 708. 6009 PSIG 18 PSGB STN GEH B AVERAGE PRESSURE 707. 6009 PSIG f9 GENBKR1 GBGQTGR ON LINE BREAKER 161372 NOT TRIP 6009 20 GENBKR2 GYRATOR ON LINE BREAKER 9X1372 NGT TRIP GOOD BUS11A BUS 11A SUPPLY BREAKER NOT TRIP 6009 BUSflB BUS 11B SUPPLY BREAKER NOT TRIP GOOD BUS12A HOT TERt(INATED ON PPCS (7/19/91) NQT TRIP DEL BUS12B NOT TERNlt(ATED ON PPCS (7/19/91) NQT TRIP DEL 25 BlfA12A BUS llA To 12A TIE BREWER TRIPPED 6009 26 B119129 BUS 11B TO 12B TIE BREAKER TRIPPED 6009 27 PCV COHTAINt(ENT AVERAGE PRESSURE .N 6009 PSI6 28 LSI(PA CQNTAItNENT SUt(P A AVERAGE LEVEL 1~9 6009 Fry 29 L0942E SUtP B LEVEL 8 INCHES (TRAIN A) LOVER 6009 30 L0943E SU)P B LEVEL 8 INCHES (TRAIN B) LONER 6009 31 L0942D SU(P B LEVEL 78 INCHES (TRAIN A) LOVER 6009 32 L0943D SU)P B LEVEL 78 INCHES (TRAIN B) LONER GOOD 33 L0942C SU)P B LEVEL 113 INCHES(TRAIN A) LOVER 6009 34 L0943C SUlP B LEVEL 113 INCOMES(TRAIN B) LONER 6009 35 L0942B SU(P B LEVEL 180 INCfKS(TRAIN A) LOVER 6009 36 L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LONER GOOD 37 L0942A SUtP B LEVEL 214 INCHES(TRAIN A) LOWER 6009 38 L0943A SUtP B LEVEL 214 INCHES(TRAIN B) LOVER 6009 39 T0409A RCLA HQT LEG TE)(PERATUfK 597.8 6009 DEGF 40 T0410A RCLB HOT LEG TEt(PERATSK 597.8 GOOD KGF 41 T0450 RCLA COLD LEG TB(PERATNE 543.5 6009 KGF 42 T0451 RCLB COLD LEG TE)(PERATURE 544.8 6009 KGF 43 TAVGAMID RCLA TAVG (THOT/TCOLD WIDE RNG) 570.7 GOOD DEGF 44 TAViiBWID RCLB TAVG (THQT/TCOLD WIDE RNG) 571.3 6009 K6F 45 REACTOR VESSEL AVERAGE LEVEL 99.4 GOOD 46 TCCGRE El. 1 INCORE TC AVERAGE TEMP 601.3 Goo> DE6F FAUXFMA S/6 A TOTAL AUX FEEIIAPD FL(I 0. 6009 GPt(
FAUXFWB S/G B TOTAL AUX FEEDWATER FLOW 0. 6009 GPH BKR081 tm AUXILIARYFEEDMATER PUt(P A OFF GGGD BKR082 t(TR AUXILIARY FEEDMATER PUtP B OFF 6009 51 V3505 AUX FM PUt(P STEAN SUPPLY VALVE A CLOSED 6009 52 V3504 AUX FW PUt(P STEAN SUPPLY VALVE B CLOSED 6009
OCT 8i 1992 08'30 R. E. GINA SItlULATOR PAGE 2 TREND GROUP ASSIGtIENT SUNNARY 6ROUP: EVEtlT1 PRXEDURE: EPIP 1-5 PLAtlT STATUS POINT ID . DESCRIPTION VALLEY 11AL E. U.
53 FSIA SAFETY INJECTION LOOP A AVG FLOM O. GOOD GPtl 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. GOOD GPtl 55 P2160 SERVICE MATER PIIPS A h B HEADER 82. GOOD PSIG 56 P2161 SERVICE MATER PUtlPS C h D HEADER 73. GOOD PSIG 57 BKR041 SERVICE WATER PlNP A ON GOOD 58 BKR042 SERVICE MATER PIP B ON GOOD 59 BKR043 SERVICE MATER PUtlP C ON GOOD 60 BKR044 SERVICE MATER PUtlP D OFF GOOD
ROGRAM NAME :LRGTS2.E
~ OCT 08,92 R.E.
~ ~ GINNA NUCLEAR POWER PLANT 08:31:00 TREND GROUP ASSIGNHENT SUHHARY GROUP NAME GROUP DESCRIPTIOH EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLW 1485. GOOD GPM 2 LRWST REFUELING WATER STORAGE TANK LVL 94.5 GOOD x 3 WS033 33 FOOT LEVEL WIND SPEED 2.6 GOOD MPH 4 WD033 33 FOOT LEVEL WIND DIRECTION 47. GOOD DEG.
5 WT033 33 FOOT LEVEL TEHPERATURE 59.6 GOOD DEGF 6 WT250 250 FOOT LEVEL TEMPERATURE 58.9 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEHP .0.7 GOOD DEGF 8 R01 AREA 1-CONTROL ROOH 9.02214-02 GOOD HR/H 9 R02 AREA 2-COHTAINMENT 6.40678+00 GOOD MR/H 10 ROS AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDOWN LINE MONITOR 3.40701+01 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAHPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAIHMEHT IODINE MOHITOR R10A 9.58719+01 GOOD CPM R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPM R12 CONTAINHENT GAS MONITOR 7.38002+02 GOOD CPM R108 PLANT VENT IODINE HOHITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS MOHITOR 4.22831+01 GOOD CPM 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658+03 GOOD CPM 21 R19 STEAM GENERATOR BLOWDOWN DRAIN 4.07174+03 GOOD CPM 22 R29 AREA 29-CONTAINHEHT HIGH RANGE 5.05861.01 GOOD R/HR 23 R30 AREA 30-CONTAIHHENT HIGH RANGE 5.09440-01 GOOD R/NR 24 R15 CONDEHSER AIR EJECTOR EXHAUST 1.25835+05 HALM CPM 25 R12A5 CV VENT CHAN 5 LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990.02 GOOD KR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLAN'I VENT CHAN 5-LOW RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RANGE GAS 3.72621.03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOW RANGE GAS 6.29179-03 HALH UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-HID RANGE GAS 6.29392-03 HWRN UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS &.29436-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 1.02040-02 GOOD MR/HR 36 R32 AREA 32 STEAM LINE B (SPING) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATIOH .0 GOOD X 38 TCV03 CV BASEHENT LVL 6 FT TEMP ¹3 95.1 GOOD OEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEHP ¹7 106.0 GOOD DEGF 40 TCV08 CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 '106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEHP ¹17 117.5 GOOD DEGF
Time: 3@~4 Message: 14 INNA 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.
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 Reactor Shutdown YES 0 Hi h Head S.Z. Pum s N-31 N-32
~CPS CPS FZ-924 FI-925 O GPM GPM N-35 E AMPS 1A. INSERV TB OOS N-36 AMPS 1B. INSERV TB OOS Avg. Nuclear Power 1C. INSERV TB OOS RCS Pressure aa Cr8 PSIG BAST Level =
PRZR Level ~9(e.
A RCP N STOPPED Low Head S.I. Pum s B RCP UNNIN STOPPED FI-626 0 G M 1A 1B S/G S/G Level Level
~. I
~./ 1A. INSERV T OOS RECIRC 1B. ZNSERV STB OOS RECIRC 1A S/G Pressure PSZG RWST Level = 1 .h 4 1B S/G Pressure 7/tr PSIG Turbine/Generator NLIN OFFLINE Containment S ra Pum s 4 KV Buses NERGI DEENERGIZED FI-931A GPM 480V Buses NERG ZE DEENERGZZED FI-931B E3 GPM DC Batteries A ISo VOLTS BI8a VOLTS 1A. INSERV T OOS Cnmt Pressure Cnmt Sump A Level
~l ~ 9 PSIG FEET 1B. INSERV TB NaOH Tank Level =
OOS Cnmt Sump B Level INCHES A Loop 'Hot Leg A Loop Cold Leg ZK2~oF Kf'V I OF Containme 1A.
t Recirc SE STBY Fans OOS B Loop Hot Leg .M OF 1B. SER STBY OOS B Loop Cold Leg OF 1C. INSERV TB OOS RVLIS 1D. NSER STBY OOS
- CET t Oo.7 DF Post Accident Dampers OPEN SE S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow C7 GPM Service te Pum s 1A. I SE STBY OOS DIESEL GENERATORS 1B. NSE STBY OOS 1C NSER STB OOS A. RUNNING UNLOADED TB OOS 1D. INSERV TB OOS B. RUNNING UNLOADED TB OOS A&B Header Pressure 78 PSIG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED OOS Com onent C in Water Pum s 1A. NSE S BY OOS ENGINEERED SAFEGUARDS Aux. Feedwater m s 1B. ZNSERV STB OOS Surge Tank Level = ~204.
1A. INSERV OOS Standb Aux. Fee ater Pum s 1B. INSERV T OOS 1C INSERV B OOS Turb. Driven INSERV TB OOS 1D. INSERV TB OOS CST Level 2. FEET
- CET = Average of Selected Core Exit Thermocouples
Gs 1992 08!45 R. E. GIMQ Sit(ULATOR PA6E 1 TREND GIIP ASIGN)(E)IT SUt(tIARY GROUP: EVENT1 PRXEDURE: EPIP 1-5 PLA)IT STATUS POINT ID DESCRIPTION E. U.
1 ATMS ANTICIPATED TRANSIENT M/0 SCfUN NO ATMS 6009 2 RXT REACTOR TRIP BREAKER STATUS NOT TRIP GOOD 3 N31 SMKE RANGE DETECTOR N-31 1. 0000800 INHB CPS N32 SINCE RANGE DETKTOR N-32 1.0$ N&00 INHD 0%
5 N35 INTEf(t(EDIATE RANGE DETECTOR N-35 6.3386AM INHB fM(P 6 N36 INTEftt(EDIATE RANGE DETECTOR N-36 5.88842M INHD Al(P 7 NP AVERAGE NUCLEAR POWER 89. 14 6009 X 8 PRCS REACTOR COOLANT SYSTEI( AVG PRESS 2263. 600D PSIG 9 LPIR PRESSURI ZER AVERAGE LEVEL 46.5 Goon X 10 FRCLA REACTOR COOLANT LOOP A AVG FLOW 98.4 6009 X 11 FRCLB REACTOR CGOLNT LOOP B AVG FLOW 97.3 6009 X" 12 RXT16 RCPA BREAKER CAUSE RX TRIP NOT TRIP 6009 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED t(ARGIN 50.1 Boos DEBF 15 LSGA STI( GEN A NARROW RANGE AVG LEVEL 52.1 6009 X 16 LS68 STM GEN B t(ARROW RANGE AVG LEVEL 52.1 GOOD /
17 PSGA STH BE)I A AVERAGE PRESSURE 717. 6009 PSIG 18 PSBB STtl GEN 8 AVERAGE PRESSURE 716. GOOD PSIG GENBKRl GBGQTOR ON LINE BREAKER 161372 NOT TRIP GOOD 20 GENBKR2 696QTOR ON LINE BREAKER 9X1372 NOT TRIP 6009 21 BUSiiA BUS 11A SUPPLY BREAKER NOT TRIP 600D 22 BUS11B BUS 11B SL'PPLY BREAKER NOT TRIP Boon 23 BUS 12A NOT TERMINATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS128 NOT TERMINATED OM PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS llA To 12A TIE BRENER TRIPPED GOOD 26 811B12B BUS 11B To 128 TIE BREAKER TRIPPED 6009 27 PCV CONTAIN)(ENT AVERAGE PRESSURE .11 GOOD 28 LSIIPA CONTAItl<IEI(T SUt(P A AVERAGE LEVEL 1~9 6009 29 L0942E SU)P B LEVEL 8 I)ICHES (TRAIN A) LONER Goon 30 L0943E SUIP 8 LEVEL 8 INCHES (TRAIN 9) LONER. 6009 31 L09429 SU)P B LEVEL 78 INCHES (TRAIN A) LONER 6009 32 L0943D SUIP B LEVEL 78 INCHES (TRAIN B) LOMER 6009 33 L0942C SUtP 8 LEVEL 113 INCHES(TRAIN A) LOMER 6009 34 L0943C SU)P 8 LEVEL 113 INCHES(TRAIN 8) LOMER 6009 35 L09428 SUtP B LEVEL 180 INCHES(TRAIN A) LONER 6009 36 L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LONER 6009 37 L0942A SPiP 8 LEVEL 214 INCHES(TRAIN A) LOMER 6009 38 L0943A 9PP B LE4l3. 214 INCHES(TRAIN 8) LONER Goon 39 T0409A RCLA HOT LEG TE)(PERATUR= 597.2 6009 DEBF 40 T0410A RCLB HOT LEG TE)IPERATURE 597.2 6009 DEBF 41 T0450 RCLA COLD LEG TE)FERATNE 544.1 6009 DEGF 42 T0451 RCLB COLD LEG TEIIPERATNE 545.4 6009 DEBF 43 TAVBAWID RCLA TAVB (THOT/TCOLD WIDE Rt(B) 570.6 6009 DEGF 44 TAViiBMID RCLB TAVG (THQT/TCOLD WIDE RNG) 571.3 6009 DE6F 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.3 46 TCCORE El. 1 INCORE TC AVERAGE TEt(P 600.7 600~ DEGF 47 FAUXFWA S/6 A TOTAL AUX FEEDMATER FLOW Goon GPtf 48 FAUXFMB S/G B TOTAL AUX FEEDMATER FLOW GOOD GPtl 49 BKR081 t(TR AUXILIARYFEEINATER PU)IP A OFF GOOD 50 BKR082 HTR AUXILIARYFEEDMATER PU)IP B OFF 6009 51 V3505 AUX FM PUI(P STEAN SUPPLY VALVE A CLOSED . GOOD 52 V3504 AUX FW PlNP STEA)I SL'PPLY VALVE B CLOSED 6009
OCT 8~ 1992 08:45 R. E. GINA SIMULATOR PA6E 2 TREND 6ROUP ASSISNNENT SNINSY 6RGUP: EVENT1 PRXEDURE: EPIP 1-5 PLANT STARS POINT ID DESCRIPTION VALUE NAL E. U.
53 FSIA SAFETY INJECTION LOOP A AV6 FLOW 0. 600D 6PN 54 FSIB SAFETY INJECTION LOOP B AVG FLN 0. 600D GPN 55 P2 160 SERVICE @TER PNtPS A h B HEADER 82. 600 D PSI6 56 P2161 SERVICE NATER PLIPS C h D HEADER 73. 6m PS16 57 BKR041 SERVICE NATER PNP A 600D 58 IMR042 SERVICE NATER PIIP 8 600D 59 IIR043 SERVICE WATER PNrP C 600D 60 IIR044 SERVICE NATER mP n 6009 EMJ
OGRAM NAME:LRGTSZ.E
~ OCT 08,92
.E.
~ ~ GINNA NUCLEAR PONER PLAHT 08:45:00 TREND GROUP ASSIGNMEHT
SUMMARY
GROUP NAME GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLll 1485. GOOD GPM 2 LRNST REFUELING llATER STORAGE TANK LVL 94.5 GOOD 3 WS033 33 FOOT LEVEL 1JINO SPEED 3.8 GOOD MPH 4 l$ 033 33 FOOT LEVEL LIIND DIRECTION 79. GOOD DEG.
5 MT033 33 FOOT LEVEL TEHPERATURE 59.8 GOOD DEGF 6 MT250 250 FOOT LEVEL TEHPERATURE 59.0 GOOD DEGF 7 NDT2 250 TO 33 FOOT LEVEL DELTA TEHP -0.8 GOOD DEGF 8 R01 AREA 1-CONTROL ROOH 9.02214.02 GOOD MR/H 9 R02 AREA 2-CONTAINHENT 6.40678+00 GOOD KR/H 10 R05 AREA 5-SPEHT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDONN LINE MONITOR 3.40701+01 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINHEHT IODINE MONITOR R10A 9.58719+01 GOOD CPH R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPM R12 CONTAINMENT GAS MOHITOR 7.38002+02 GOOD CPM R108 PLANT VENT IODINE MONITOR R10B 4.30543+01 GOOD CPH R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPH R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID llASTE DISPOSAL MONITOR 2.78658+03 GOOD CPH 21 R'l9 STEAM GENERATOR BLOlSONN DRAIN 4.07174+03 GOOD CPM 22 R29 AREA 29-CONTAINMENT HIGH RANGE 5.05861-01 GOOD R/HR R30 AREA 30-COHTAINMENT HIGH RANGE 5.09440.01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.25835+05 HALM CPM 25 R12A5 CV VENT CHAN 5-LIN RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAHMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435.05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLAHT VENT CHAN 5-LQI RAHGE GAS 4.40312.07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9 HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOFTI RANGE GAS. 6.29179.03 HALH UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-HID RANGE GAS 6.29392-03 HWRN UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-Hl RANGE GAS 6.29436.03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 1.02040-02 GOOD MR/HR 36 R32 AREA 32 STEAM LINE 8 (SPING) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEH CONCENTRATION .0 GOOD X 38 'CV03 CV BASEMENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 , TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD DEGF 0 J
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.
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.
INITIALCONDITIONS:
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 INNA TATI N 1 2 EVAL ATED EXER E
~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 INITIALCONDITIONS: 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 0
Phase to phase resistance: ( 1 Q 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:
Message:
3)~
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 Reactor Shutdown ~YES Hi h Head S.Z. Pum s N-3 1 FI-924 N-32 N-35 CPS CPS AMPS FI-925 1A.
~GP INSERV T GPM OOS N-36 AMPS 1B. INSERV S B OOS Avg. Nuclear Power 1C.'NSERV OOS RCS Pressure &2.fe2 PSZG BAST Level =
PRZR Level 5r 7 A RCP IN STOPPED Low Head S.I. Pum s B RCP IN STOPPED FI-626 O M 1A S/G Level ~a. I 1A. INSERV T OOS RECIRC 1B S/G Level 5a t 1B. INSERV TB OOS RECIRC 1A S/G Pressure PSIG RWST Level =
1B S/G Pressure 7s ~ PSIG Turbine/Generator ONLI OFFLINE Containment S ra Pum s 4 KV Buses NERG DEENERGIZED FI-931A O GPM 480V Buses ER DEENERGIZED Fl-931B~GP DC Batteries A~go VOLTS B ISOVOLTS 1A. ZNSERV TBY OOS Cnmt Pressure .IS PSIG 1B ~ INSERV T OOS Cnmt Sump A Level ~OFEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg Xm.-L oF Containment ecirc Fans A Loop Cold Leg 899. I OF 1A. NSE STBY OOS B Loop Hot Leg ~C. I OF 1B. SE STBY OOS B Loop Cold Leg RVLIS
~,~iOF 1C. INSERV T OOS 1D. SER STBY OOS
- CET 91l OF Post Accident Dampers OPEN LOSED S/G A Total Aux FW Flow GPM 5/G B Total Aux FW Flow 0 GPM Service Wate Pum s 1A. STBY OOS DIESEL GENERATORS 1B. INSE STBY OOS 1C. NSE V ST OOS A. RUNNING UNLOADED B OOS 1D. INS V TB OOS B. RUNNING UNLOADED OOS A&B Header Pressure PSIG TSC RUNNING UNLOADED T OOS Security RUNNING UNLOADED OOS Com onent Coolin Wat r Pum s 1A. STBY ENGINEERED SAFEGUARDS 1B. NSER STBY OOS Surge Tank Level =
Aux. Feedwater Pum s 1A. INSERV T OOS Standb Aux. Fe water Pum s 1B. INSERV TB OOS 1C. INSERV OOS Turb. Driven INSERV TB 1D. INSERV STB CST Level ~ FEET OOS OOS
- CET = Average of Selected Core Exit Thermocouples
8> 1992 09:00 R. E. GINA SIWLATOR PAGE 1 TREND GROUP ASSIGNNENT SUNNARY GROUP: EVENT1 PROCEDURE! EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E. U.
1 ATMS ANTICIPATED TRANSIEhT M/0 SCRAN No ATMS GOOD 2 RXT REACTOR TRIP BREAKER STATUS NOT TRIP GOOD 3 N31 SMCE RANGE DETECTOR N-31 1.000008M INHH CPS N32 SMKE RANGE DETECTOR N-32 1.00000+00 INHB CPS 5 N35 INIERNEDIATE RANGE DETECTOR N-35 6.19439M INHB ANP 6 N36 INTERNEDIATE RANGE DETECTOR N-36 5,727~ INHB ANP 7 NP AVERAGE NIKLEAR POWER 86.94 GOOD X 8 PRCS REACTOR COOLANT SYSTEN AVG PRESS 2262. 6009 PSIB r
9 LPIR PRESSURI IER AVERAGE LEVEL 45.7 6009 X 10 FRM RECTOR COOLANT LOOP A AV6 FLIN 98.4 6009 11 FR(u REACTOR COOLNT LOOP B AVG FLOW 97.3 6009 X 12 RXT16 RCPA BREAKER CAUSE RX TRIP NOT TRIP 6009 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED NAPKIN 51.8 600~ DEBF 15 LSGA STN GEt( A NARROW RANGE AVG LEVEL 52.1 GOOD X 16 LSBB STN GEN B NARROW RANGE AVG LEVEL 52.1 6009 X f7 PSGA STN BEt( A AVERAGE PRESSURE 723. 6009 PSIG 18 PSGB STN 6EN B AVERAGE PRESSURE 722. BOOB PSI6 19 GENBKR1 GENERATOR ON LINE BREAKER 161372 NOT TRIP 6009 20 BENBKR2 GBERATOR ON LINE BREAKER 9X1372 NOT TRir SOOn 21 BUSffA BUS 11A SlFPLY BREAKER NOT TRIP 6009 22 BUS11B BUS 11B SUPPLY BREAKER NOT TRIP 6009 23 BUS12A NOT TERNINATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS12B t(OT TERNINATED ON PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS 11A To f2A TIE BREA'(ER TRIPPED 6009 26 B11B12B BUS 11B TO 12B TIE BRENER TRIPPED 6009 27 PCV CONTAINHENT AVENGE PRESSURE . 13 6009 PSI6 28 LSUNPA CONTAINNENT RJNP A AVERAGE LEVEL 2.0 6009 FEET 29 L0942E SUtP B LEAL'8 It(CHES (TRAIN A) LOWER 6009 30 L0943E SU)P B LBtEL 8 It/CHES (TRAIN 8) LOWER 6009 31 LO'942D SUtP B LEVEL 78 INCHES (TRAIN A) LOWER 6009 32 L0943D SUtP B LEVEL 78 INCHES (TRAIN B) LOWER 6009 33 L0942C SU)P B LEVEL 113 INCHES(TRAIN A) LOWER 6009 L0943C SUtP B LEVEL 113 INCHES(TRAIN B) LONER 6009 35 L0942B SU)P B LBr'EL 180 INCHES(TRAIN A) LONER 6009 36 , L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LOWER 6009 37 L0942A SUlP B LEVEL 214 INCHES(TRAIN A) LOWER 6009 38 L0943A SUtP B LEVEL 214 INCHES(TRAIN B) LOWER 6009 39 T0409A RCLA HOT LEG TENPERATUiK 596.1 6009 DE6F 40 T0410A RCLB HOT LE6 TBPERATSK 596.1 6009 DEGF 41 T0450 RCLA COLD LEG TE)IPERATlBE 544.1 6009 DE6F 42 T0451 RCLB COLD LEG TENPERATNE 545.2 G009 DEBF 43 TAVGAMID RCLA TAVG (THOT/TCOLD WIDE RNG) 570.1 6009 KBF 44 TAVGBMID RCLB TAVG (THOT/TCOLD WIDE RNG) 570.6 6009 DEBF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.4 6009 X 46 7CCORE El.l INCORE TC AVERAGE TENP 599.1 600~ KBF 47 FAUXFWA S/6 A TOTAj AUX FEECAIATER FLOW 0. 6009 PN 48 FAUXFMB S/G B TOTAL AUX FEEDMAWD FLOW 0. 6009 GPN 49 BKR081 NTR AUXILIARYFEEDMATER PUNP A OFF 6009 BKR082 NTR AUXILIARYFEEDMATER PUNP 9 OFF 6909 51 V3505 AUX FW PUNP STEA)I SUPPLY VALVE A CLOSED 6009 V3504 AUX FM PINP STEAJI SUPPLY VALVE 8 CLOSED GOOD gr 75
OCT 8~ 1992 09:00 R. E. GIMjfA SIffULATOR PA6E 2 TREND GfOUP ASSIGNffENT SNIARY 6ROUP'VENTI PfNlEDURE'PIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE . QUAL E,',
53 FSIA SAFETY INJECTION. LOOP A AVG FLOW 0. 600D PN 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. 600 D GPN 5S P2160 SERVICE WATER PNfPS A h B HEADER 82. 600D PSIG 56 P2I61 SERVICE WATER PNFS C 5 0 HEADER 73, GOOD PSIG 57 BffR04i SERVICE WATER PNfP A ON GOOD 58 BffR042 SERVICE WATER PUNP 8 ON 600D 59 BffR043 SERVICE WATER PNfP C ON GOOD 60 BKR044 SEfIICE WATER PNfP D OFF GOOD EMJ
IOGRAM NAME:l LRGTSZ.E
~
OCT 08,92
.E.
~ GIHNA NUCLEAR PONER PLANT 09:00:00 TREND GROUP ASSIGNMENT SUHHARY GROUP HAME GROUP DESCRIPT ION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURREHT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLU 1485. GOOD GPM 2 LRNST REFUELING llATER STORAGE TANK LVL 94.5 GOOD 3 IIS033 33 FOOT LEVEL llIND SPEED 3.1 GOOD MPH 4 l$ 033 33 FOOT LEVEL IIIND DIRECTIOH 52. GOOD DEG.
5 IIT033 33 FOOT LEVEL TEHPERATURE 59.9 GOOD DEGF 6 NT250 250 FOOT LEVEL TEMPERATURE 59.3 GOOD DEGF 7 M)T2 250 TO 33 FOOT LEVEL DELTA TEHP -0.6 GOOD DEGF 8 R01 AREA 1-CONTROL ROOH 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINMEHT 6.40678i00 GOOD MR/H 10 R05 AREA 5-SPEHT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDONN LINE MONITOR 3.40701+01 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAHPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINMENT IODINE MONITOR R10A 9.5871&01 GOOD CPM R11 CONTAIHHEHT AIR PARTICULATE 5.18901+02 GOOD CPM R12 CONTAINMENT GAS HOHITOR 7.38002+02 GOOD CPM R10B PLANT VENT IODINE HOHITOR R10B 4.30543>01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPH R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPH 20 R18 LIQUID 'HASTE DISPOSAL MONITOR 2.78658t03 GOOD CPM 2'1 R19 STEAM GENERATOR BLONDONH DRAIN 4.07174+03 GOOD CPH 22 R29 AREA 29-CONTAINMEHT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINMEHT HIGH RANGE 5.09440-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.25835+05 HALM CPM 25 R12A5 CV VENT CHAN 5-LOU RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CKAH 6-AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RAHGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOI RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAM 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOU RANGE GAS 6.29179.03 HALM UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 6.29392-03 HNRN UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 6.29436.03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPIHG) 1.02040-02 GOOD HR/HR 36 R32 AREA 32 STEAM LINE B (SPING) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEN CONCEHTRATION .0 GOOD X 38 TCV03 CV BASEMEHT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCV08 CV INTERMEDIATE LVL 6 FT TEHP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD DEGF 0-g -77
Time:
Message:
~)~
22
~INNA TATI N 2EV L TEDE ER I E MES A E F RIVI
~MI:M I N<<IR 1A CCW Pump 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 Hi h Head S.I. Pum s N-31 N-32
~CPS CPS FI-924 0 FZ-925 0
. GPM GPM N-35 e AMPS 1A SE STBY OOS N-36 -t AMPS 1B STBY OOS Avg. Nuclear Power e 1C. INSERV STBY OOS RCS Pressure PRZR Level I 7 0
PSIG BAST Leve = ~7 A RCP STOPPED Low Head S.Z. Pum s B RCP UNNI STOPPED FI-62 GPM 1A 1B 1A S/G S/G S/G Level Level Pressure
~l
~lO.
~(S PSIG 1A.
1B.
SER STBY OOS RECIRC SERV STBY OOS RECIRC RWST Level = V .
1B S/G Pressure t3 PSIG Turbine/Generator OFFLINE Containment S ra Pum s 4 KV Buses NERGIZE DEENERGIZED FZ-931A O GPM 480V Buses N RGIZE DEENERGIZED FI-931B O GP DC Batteries A~TOVOL S BlSOVOLTS 1A. INSERV ST OOS Cnmt Pressure ~ ( PSZG 1B. INSERV OOS Cnmt Sump A Level FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg ~~eOF Containment Recirc Fans A Loop Cold Leg Loop Hot Leg
~G Z OF ~ 1A. NS STBY OOS B OF 1B. INSE STBY OOS B Loop Cold Leg ~ 5 OF 1C. STBY OOS RVLZS 1D. INSE STBY OOS
- CET ~~.S OF . Post Acct ent Dampers OPEN CLOSED S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow GPM Service W te Pum s 1A. SE STBY OOS DIESEL GENERATORS 1B. SE STBY OOS 1C. STBY OOS A. NING UNLOADE STBY OOS 1D. INSER STBY OOS B. UNNING UN DE STB OOS A&B Hea er ressure PSIG TSC RUNN ED TB OOS Security RUNNING UNLOAD D TB OOS Com onent Coolin Water Pum s 1A. IN STBY 0 ENGINEERED SAFEGUARDS 1B. NSERV STBY OOS Surge Tan Level =
Aux. Feedw ter Pum s 1A. SE STBY OOS Standb Aux. Fe ater Pum s 1B. N ER STBY S 1C. INSERV T OOS Turb. Driven SER STBY OOS 1D. ZNSERV TB OOS CST Level g~~h FEET
- CET = Average of Selected Core Exit Thermocouples
- 8) 1992 09'17 R. E. GINA SitmLATOR PAGE 1
'REN9 GROUP ASSIGNMEt(T SUt(MARY 6ROUP: EVEHT1 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION GUAL E. U.
1 ATWS ANTICIPATED TRANSIENT W/0 SCRAM AIMS ALRt(
2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRII 3 N31 SmSCE RANGE DETECTOR N-31 1.00000+(e INHB CPS 4 N32 SRSCE RANGE DETECTOR H-32 1.00000I00 INHS CPS 5 N35 INTERMEDIATE RANGE DETECTOR N-35 4.20726-06 6009 At(P 6 H36 IHTERt(EDIATE RAN6E DETECTOR N-36 3.59748M 6009 AMP 7 NP AVERAGE NUCLEAR POWER .59 600D X 8 PRCS REACTOR COOLANT SYSTEN AVG PRESS 1474. LAB PSIG 9 LPIR PRESSURIIER AVERAGE LEVEL .0 LALI( X, 10 FRCLA REACTOR COOLNT LOOP A AVG FLOW 98.9 GOOD X 11 FRCLB REACTOR COOLANT LOOP B AVG FLOW 98.0 600D X 12 R)(T16 RCPA BREAKER CAUSE RX TRIP NOT TRIP 600D 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUKOOLED MARIN 51.7 600~ KGF 15 LSGA STtl GEN A NARROW RANGE AVG LEVEL 10.8 LALM X 16 LSGB STM GB( B NARROW RANGE AVG LEVEL 7.1 LALN X 17 PSGA ST)( GEN A AVERAGE PRESSURE 913. 6009 PSI6 18 PSGB STtl GEN B AVERAGE PRESSURE 913. 6009 PSIG 19 GENBKRl GBERATOR ON LINE BREAKER 161372 NOT TRIP 6009 20 GENBKR2 GE%MTOR ON LINE BREAKER 9X1372 NOT TRIP 6009 21 BUS11A BUS 11A SUPPLY BREAKER NOT TRIP 6009 22 BUS11B BUS 11B SUPPLY BREAKER NOT TRIP 6009 23 BUS12A NOT TERMINATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERMINATED ON PPCS (7/19/91) HOT TRIP DEL 25 B11A12A BUS 11A To 12A TIE BRENER TRIPPED 6009 26 B11B12B BUS 11B To 129 TIE BREAKER TRIPPED GOOD 27 PCV CONTAINMENT AVERAGE PRESSURE .11 GOOD PSI6 28 LSUMPA CONTAIt(t~ SUt(P A AVERAGE LEVEL 2.0 6009 FK 29 L0942E SU)P B LEVEL 8 INCHES (TRAIN A) LOWER 6009 30 L0943E SUtP B LEVEL 8 INCHES (TRAIN 9) LOWER 6009 31 L0942D SU)P B LEVEL 78 iNCHES (TRAIN A) LONER 6009 32 L0943D SUtP B LEVEL 78 INOZS (TRAIN B) LOWER 6009 33 L0942C SUIP B LBtEL 113 INCHES(TRAIN A) LOWER 6009 34 L0943C SUIP B LEVEL 113 INCHES(TRAIN B) LOWER 6009 35 l.0942B SUtP B LEVEL 180 INCHES(TRAIN A) LOWER 6009 36 L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LOWER 6009 37 L0942A SUtP B LEVEL 214 INCHES(TRAIN A) LOWER 6009 38 L0943A SU)P B LEVEL 214 INCHES(TRAIN B) LOWER 6009 39 T0409A RCLA HOT LEG TBIPERATUK 543.6 6009 DE6F 40 T0410A RCLB HOT LE6 TBIPERATNK 543.6 6009 KGF 41 T0450 RCLA COLD LEG TE)IPERAT(RE 536.2 6009 DEGF 42 T0451 RCLB COLD LEG TE)IPERAT(SE 537.3 6009 DEGF 43 TAVGAWID RCLA TAVG (THOT/TC(LD WIDE RNG) 539.9 6009 DEGF 44 TAVGBMID RCLB TAVG (THOT/TCOLD WIDE RNG) 540.2 6000 DEGF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.5 6009 X 46 TCCORE El. 1 It(CORE TC AVERAGE TBIP 539.3 DFGF Goo'78.
47 FAUXFWA S/G A TOTAL A'JX FEEDWATER FLOW GOOD PN 48 FAUXFWB S/G B TOTAL A)JX FEEDMATER FLOW 484. 6009 GPN 49 BKR081 t(TR AUXILIARYFEEDWATER PUMP A OH 6009 50 BKR082 tITR AUXILIARYFEEDMATER PUMP 9 ON Gm 51 V3505 AUX FW PUMP STEA)I SUPPLY VALVE A OPEN ALRtf 52 V3504 AUX FM PUMP STEA)I SUPPLY VALVE B OPEN ALRtl
OCT &s 1992 09'17 R. E. GINA SIWLATOR PAGE 2 TREND 6ROUP ASSI6NENT RNHARY GROUP: EVENT1 PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE OUAL E. U.
53 FSIA SAFiiY INJECTION LOOP A AVG FLOW 101. 600 D 6Ptl 54 FSIB SAFETY INJECTION l.OOP B AVG FLOW 101. GOOD GPH 55 P2160 SERVICE WATER PIIPS A 5 B HEADER 85. GOOD PSIG 56 P2161 SERVICE WATER PNPS C h D HEADER 85. GOOD PSI6 57 BKR041 SERVICE WATER PlNP A ON 600D 58 BKR042 SERVICE WATER PUNP B ON 600D 59 BKR043 SERVICE WATER PlmP C ON GOOD 60 BKR044 SERVICE WATER PUMP D ON GOOD EMJ
Q IOGRAM HAME:LRGTSZNE~ OCT 08,92
.E.
~ ~ GINNA NUCLEAR POMER PLANT 09:17:00 TREND GROUP ASSIGMHEHT SUHMARY GROUP NAME GROUP DESCRIPT IOH EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT IO DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLlI 1485. 6(XO GPH 2 LRlIST REFUELING MATER STORAGE TANK LVL 94.5 6000 X 3 MS033 33 FOOT LEVEL IIIND SPEED 3.8 QXX) MPH l$ 033 33 FOOT LEVEL lIIND DIRECTION 50. GOOD DEG.
5 MT033 33 FOOT LEVEL TEHPERATURE 60.7 6000 DEGF 6 MT250 250 FOOT LEVEL TEMPERATURE 60.7 GOOD DEGF 7 MDT2 250 TO 33 FOOT LEVEL DELTA TEMP 0.0 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214.02 GOOD MR/H 9 R02 AREA 2-COHTAINHENT 7.35678+00 GOOD MR/H 10 R05 AREA S.SPENT FUEL PIT 1.3994& 00 6000 MR/H 11 R09 AREA 9.LETDOMN LINE MOHITOR 1.47701+02 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD MR/H 14 R10A COHTAINHENT IODINE MONITOR R10A 9.58719+01 GOOD CPM R11 CONTAINMEHT AIR PARTICULATE 5.18901+02 6000 CPM R12 CONTAINMEHT GAS MONITOR 7.38002+02 6000 CPM R108 PLANT VENT IOOIHE MOHITOR R108 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXNAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID MASTE DISPOSAL MONITOR 2.78658+03 GOOD ~
CPM 21 R19 STEAM GENERATOR BLOleOllH DRAIN 1.57174+04 HALM CPM 22 R29 AREA 29-COHTAINMEMT HIGH RANGE 5.05861.01 GOOD R/HR 23 R30 AREA 30-CONTAIHMENT HIGH RANGE 5.09440-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 9.~06 HALM CPM 25 R12A5 CV VENT CHAN 5-LNI RAHGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6 AREA GAMMA 2.53990-02 GOOD HR/HR 27 R12A7 CV VENT CHAM 7-HID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RAHGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LNI RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-HID RAHGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAM 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAH 5-LOU RANGE GAS 9.99999.03 HALH UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RAHGE GAS 1.85392+00 HALM UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-Hl RANGE GAS 1.85436+00 HMRH UCI/CC 35 R31 AREA 31 STEAM LINE A (SPIMG) 3.02040+00 MALM MR/HR 36 R32 AREA 32 STEAM LIHE 8 (SPING) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION ~ 0 GOOD 38 TCV03 CV BASEMEHT LVL 6 FT TEHP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEHP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEHP ¹9 106.7 GOOD DEGF 42 TCV10 CV INI'ERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD 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 Reactor Shutdown ES NO Hi h Head S.I. Pum s N-31 N-32
~CPS CPS Fl-924 I 5 GPM FI-925 GPM N-35 AMPS 1A. NSE STBY OOS N-36 Q+- AMPS 1B. NSER STBY OOS Avg. Nuclear Power o 1C. INSERV STBY OOS RCS Pressure ~s& 7 PSIG BAST Leve PRZR Level A RCP UNNI STOPPED Low Head S.I. Pum s B RCP UNNING STOPPED FI-626 O GPM 1A S/G Level so.t a 1A. NSE STBY OOS RECIRC 1B S/G Level .1 1B. NSE STBY OOS RECIRC 1A S/G Pressure PSIG RWST Level =
1B S/G Pressure PSIG Turbine/Generator FFLINE Containment S ra Pum s 4 KV Buses NERGIZ DEENERGIZED FI-931A O GPM 480V Buses N ED DEENERGIZED FI-93 1B 0 GPM DC Batteries AI'SbVO S B~3oVOLTS 1A. INSERV B OOS Cumt Pressure Cnmt Sump A Level
~dPSIG 1B. INSERV B OOS
. 0 FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg 'f043 OF Containment Recirc Fans A Loop Cold Leg M4LX oF 1A. NSER STBY OOS B Loop Hot Leg OF 1B. NSE STBY OOS B Loop Cold Leg OF 1C. SERV STBY OOS RVLIS f3 1D. NSE V STBY OOS
- CET Oa OF Post Aces ent Dampers OPE CLOSED S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow ~g GPM Service Water 1A SE Pum STBY s
OOS DIESEL GENERATORS 1B. E STBY OOS 1C. SER STBY OOS A. UNNING UNLOADE STBY OOS 1D. NSER STBY OOS B. RUNNING UNLOADED STBY OOS A&B Header ressure ggP8 PSIG TSC RU G LO DED STB OOS Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. INSERV STBY ENGINEERED SAFEGUARDS 1B. SER STBY OOS Aux. Feedwater Pum s Surge Tank Level = ~2-1A. SE STBY OOS Standb Aux. Feedwater Pum s 1B. INSERV STBY OOS 1C. INSERV TB OOS Turb. Driven INSERV TB CST Level ~f F OOS 1D. INSERV TB OOS
- CET = Average of Selected Core Exit Thermocouples 8-fo
8, 1992 09:21 R. E. GINA Sit(ULATOR PAGE 1 TREND GROUP ASSIGN)(ENT SUl(NARY GROUP! EVENTi PROCEDURE( EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E. U.
1 ATMS ANTICIPATED TRANSIENT W/0 SCRI( ATWS ALRt(
2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRt(
3 N31 SMKE RANGE DETECTOR N-31 1. 0000(MO INHB CPS 4 N32 SIIKE RANGE DETECTOR N-32. 1.00000+00 INHB CPS 5 N35 INTERt(EDIATE RANGE DETECTOR N-35 6.79204M 6009 At(P N36 INTERt(EDIATE RANGE DHECTOR N"36 5.80759M 6009 At(P 7 'NP AVERAGE NXLEAR POWER .02 6009 y.
8 PRCS REACTOR COOLANT SYSTEt( AVG PRESS 1267. LALN PSIG 9 LPLR PRESSURIIER AVERAGE LEVEL .0 LALN 'l 10 FRM REACTOR COOLANT LOOP A AVG FLOW 98.1 6009 7l 11 FRCLB REACTOR COOLNT LOOP B AV6 FLN 97.3 6009 12 RXT16 RCPA BREAKER CAUSE RX TRIP NOT TRIP GOOD 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCQRE TC SUBCOOLED t(ARSIN 35.0 600~ DEGF 15 LSSA STt( GEt( A NARRN RANGE AVG LEVEL 30.8 GOOD X 16 LSSB STt( BEN B NARROW RANGE AVG LEVEL 28.7 LWRt( y.
17 PSGA STt( SEt( A AVERAGE PRESS(EE 941. 6009 PSIG 18 PSGB STH GEN B AVERAGE PRESSURE 941-. 6009 PSIG 19 GENBKR1 6BERATOR ON LltK BREAKER 161372 TRiPPED ALRt(
20 GENBKR2 aaeuTOR oN LINE BREAKER 9ra372 TRIPPED ALRt(
21 BUSIIA BUS 11A SUPPLY BREAKER TRIPPED ALRt(
22 BUS11B BUS iiB SUPPLY BREAKER TRIPPED ALRN 23 BUS12A NOT TERt(INATED Ot( PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERNINATED ON PPCS (7/19/91) NOT TRIP DEL 25 811A12A BUS 11A TQ 12A TIE BREWER NQT TRIP ALRt(
26 B11812B BUS 11B TQ 12B TIE BREWER NOT TRIP ALRt(
27 PCV CONTAIttt(ENT AVERAGE PRESSURE .08 6009 28 LSI(PA CONTAINt(ENT RIP A AVERAGE LEVEL 2.0 GOOD 29 L0942E SU)P B LEVEL 8 INCHES (TRAIN A) LOWER soon 30 L0943E SU)P B LEVEL 8 INCHES (TRAIN B) LONER GOOD 31 L0942D SU)P B LEVEL 78 INCHES (TRAIN A) LONER 6009 32 L09439 SU)P B LEVEL 78 INCHES (TRAIN B) LONER 6009 33 L0942C SUtP B LEVEL 113 INCHES(TRAIN A) LNER Goon 34 L0943C SU)P B LEVEL 113 INCHES(TRAIN B) l.OWER 6009 35 L0942B SU)P B LEVEL 180 INCHES(TRAIN A) LNER 6009 36 L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LNER 6009 37 L0942A SUtP B LEVEL 214 INCHES(TRAIN A) LNER 6009 38 t 0943A SUtP B LEVEL 214 INCHES(TRAIN B) LONER GOOD 39 T0409A RCLA HOT LEG TEt(PERATURE 540.3 6009 DEGF 40 T0410A RCLB HOT LE6 TEt(PERATURE 540.3 6009 DEBF 41 T0450 RC(A COLD LEG TEt(PERAT(SE 538.8 6009 DEGF 42 T0451 RCLB COLD LEG TEt(PERATlRE 538.4 6009 DE6F 43 TAVGAMID RCLA TAVG (THOT/TCOLD WIDE RNG) 539.7 6009 DEGF 44 TAVSBWID RCLB TAVG (THQT/TCOLD MIDE RNG) 539.4 SOQD DESF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.3 6009 K 46 TCCORE E1.1 INCORE TC AVERAGE TEt(P 540.5 Goo< DE6F 47 FAUXFWA S/6 A TOTAL AUX FEEDMATER FLN 0. 6009 6PN 48 FAUXFWB S/G B TOTAL AUX FEEDWATER FLN 198. GOOD 6Pt(
49 BKR081 t(TR AUXILIARYFEEDMATER PUt(P A ON 6009 50 BKR082 HTR AUXILIARY FEEDWATER PUlP B ON GOOD 51 V3505 AUX FM PUtP STEA)l SUPPLY VALVE A CLOSED 6009 52 V3504 AUX FM PUt(P STENi SL%'PLY VALVE B CLOSED 6009
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 SAFETY INJECTION. LOOP A AVG FLOW 145. 600D PN 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 145. GOOD GPN 55 P2160 SERVICE WATER PNPS A h B HEADER 85. SOOn PSIG 56 P2161 SERVICE WATER PNFS C h D HEADER 85. 6009 PSIG 57 BKR041 SERVICE WATER PNF A GOOD 58 IIR042 SERVICE WATER PlIP B GOOD 59 INR043 SERVICE WATER PIIP C GOOD 60 IIR044 SERVICE WATER PNP D 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 MAJOR PARAMETERS ENGINEERED SAFEGUARDS Reactor Shutdown ES NO Hi h Head S.I. Pum s N-31 CPS FI-924 GPM N-32 N-35
~CPS !-II AMPS FI-925 2 'j~GPM 1A. SE STBY OOS N-3 6 Avg. Nuclear Power
~~wl AMPS 1B SE STBY OOS o 1C NSER STBY OOS RCS Pressure PRZR Level PSIG BAST Lave = ~O A RCP STOPPED Low Head S.I. Pum s B RCP UNNIN STOPPED FI-626 O G M 1A S/G Level 1A. INSERV TB OOS RECIRC 1B 1A S/G S/G Level Pressure
~o&
~ 5 PSIG 1B. INSERV RWST Level =
TB OOS RECIRC 1B S/G Pressure 0 PSIG Turbine/Generator NE FFLIN Containment S ra Pum s 4 KV Buses RGIZE DEENERGIZED FI-931A Q GPM 480V. Buses NERGIZ DEENERGIZED Fl-931B D GPM DC Batteries A~5o VOLTS B/Sb VOLTS 1A. INSERV TB OOS Cnmt Pressure . oa PSIG 1B.
-Cnmt Sump A Level Cnmt Sump B Level
~3. FEET INCHES INSERV TB NaOH Tank Level = ~4 OOS A Loop Hot Leg ~ OF Containm nt ecirc Fans A Loop Cold Leg Zi OF 1A. NSERV STBY OOS B Loop Hot Leg ~ OF 1B. N ERV STBY OOS B Loop Cold Leg ~ 4 OF 1C. S STBY OOS RVLIS
- CET i+i
~92,3
~ 1D. NSER STBY OOS Post Accident Dampers OPE CLOSED A Total Aux FW Flow O OF'/G GPM S/G B Total Aux FW Flow ~IG GPM Service Wa er Pum s 1A. NSERV STBY OOS DIESEL GENERATORS 1B.'SER STBY OOS 1C. SER STBY OOS A. UNNING UNLOAD STBY OOS 1D. NSER STBY OOS B.
TSC ED STBY OOS D TB OOS A&B Header ressure ~APSIG Security RUNNING UNLOA D B OOS Com onent Coolin Water Pum s 1A. INSERV STBY 00 ENGINEERED. SAFEGUARDS 1B. NSE V STBY OOS Aux. Feedwater Pum s Surge Tan vel = 5 ~ 4 1A. INSERV TB OOS Standb Aux. Fee ater Pum s 1B. SER STBY OOS 1C. INSERV TB OOS Turb. Driven INSERV B OOS 1D. INSERV TB OOS CST Level / FEET
- CET = Average of Selected Core Exit Thermocouples
8s 1992 09! 30 R. E. GINA SI)ILATOR PAGE 1 TREND GROUP ASSIGN%AT SUt(t(ARY GROUP'VENT1 PROCEDURE'PIP f< PLANT STATUS POINT ID DESCRIPTION E. U.
1 ATiS ANTICIPATED TRANSIENT W/0 SCRAt( ATWS ALN 2 RXT REACTOR TRIP BRENER STATUS RX TRIPPED ALN 3 N31'32 SMCE RANGE DETECTOR N-31 i. 00000+00 INH)t CPS 4 SONCE RI(GE DETECTOR N-32 1.0000&0 INH8 CPS 5 ta5 INTER)(EDIATE RANGE DETECTOR N-35 6. 13757"1 1 GOOD At(P 6 N36 INIEt(t(EDIATE RAN6E DETKTOR N-36 5.34561-11 GOOD At(P 7 NP AVERA6E NUCLEAR POWER .00 GDOD X 8 PRCS REACTOR COOLANT SYSTEt( AVG PRESS 934. LALt( PSIG 9 LPLR PRESSURI lER AVERAGE LEVEL .0 LAL)( X f0 FRCLA REACTOR COOLNT LOOP A AVG FLOW 103.3 600D X 11 FRCLB REACTOR COOLANT LOOP B AVG FLOW 103.0 600D X 12 RXT16 RCPA BRENER CAUSE RX TRIP NOT TRIP GOOD 13 RXT17 RCPB BRENER CAUSE RX TRIP NOT TRIP GOOD 14 TSUBTC INCORE TC SUBCOOLED t)ARGIN 45.9 600'EGF 15 LSGA STtl GB( A NARROW RANGE AVG LEVEL 49.6 GOOD X 16 LSGB STN GEN B NARROW RANGE AVG LEVEL .0 LAL)( X 17 PSGA STtt GEN A AVERAGE PRESSURE 1053. GOOD PSIG 18 PS6B STt( GEN 8 AVERA6E PRESSURE 580. LWR)( PSI6 f9 GENBKRf GBGQTOR ON LINE BRENER 161372 TRIPPED ALRtl 20 GENBKR2 GamATOR ON INE BREAKER 9X1372
~
TRIPPED ALRt(
21 BUS11A BUS f1A SUPPLY BRENER TRIPPED ALRtl 22 BUS11B BUS 11B SLPPLY BRENER TRIPPED ALR)(
23 BUS12A NOT TERNINATED Ott PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERt(INATED OW PPCS (7/19/91) NOT TRIP DEL 25 811A12A BUS 11A TO 12A TIE BRENER NOT TRIP ALRt(
26 B11812B BUS 11B TO 128 TIE BRENER NOT TRIP AUI 27 PCV CONTAIN)(ENT AVERAGE PRESSURE .02 GOOD PSIG 28 LSI(PA CONTAINEhT PJt(P A AVcCAGE LE4l3. 2.1 6009 FAT 29 L0942E SUtP 8 LEVEL 8 INCHES (TRAIN A) LO)tER GOOD 30 L0943E SUtP 8 LEVEL 8 INCHES (TRAIN B) LONER GOOD 31 LO'942D SUtP 8 LEVEL 78 INCHES (TRAIN A) LO)tER 6009 32 L0943D SUtP 8 LEVEL 78 INCHES (TRAIN 8) LOI(ER 6000 33 L0942C SUtP B LEVEL 113 INCHES(TRAIN A) LO)tER GOOD 34 L0943C SSP B LEVEL 113 INCHES(TRAiN 8) LONER 6009 35 L09428 SUtP B LEVEL 180 INES(TRAIN A) LOWER 600D 36 L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LOWER GOOD 37 L0942A SUtP B LEVEL 214 INCHES(TRAIN A) LONER 6009 38 L0943A SUtf B LEVl3. 214 INCHES(TRAIN B) LONER GOOD 39 T0409A RCL4 HOT LEG TB(PERATUK 494.6 GOOD DEGF 40 T0410A RCLB HOT LEG TB(PERATNK 494.6 600D DEGF 41 T0450 RCLA COLD LEG TB(PERAT(mE 495.5 GOOD DE6F 42 TO451 RCLB COLD LE6 TB(PERATIRE 487.6 600D DE6F 43 TAVGAWID RCLA TAVG (TNT/TCOLD WIDE RN6) 494.8 6000 KGF 44 TAVGBWID RCLB TAVG (THOT/TCOLD WIDE RNG) 491.0 6000 DEGF LRV REACTOR VESSEL AVERAGE LEVEL 100.8 600D X 46 TCCORE Ei.f INCORE TC AVERAGE TB(P 492.2 600~ DEGF 47 FAUXFWA S/G A TOTAL AUX FEEDWATER FLOW 0. 600 D GPtt 48 FAUXFWB S/6 B TOTAL AUX FEEDWATBt FLOW 182. GOOD GPt(
49 BKR081 t(TR AUXILIARYFEEDWATER PlNP A OFF 6009 50 BKR082 ttTR AU)(ILIARY FEEDWATER PU)(P B ON GBQD 51 V3505 AUX FW PUt(P STEA)t SUPP(.Y VALVE A CLOSED 600D 52 V3504 AUX FW PlNP STEA)( SUPPLY VALVE 8 CLOSED 6009
OCr 8, 1992 R. E. GINA SINlLATOR PA6E 2 TREND GROI'SSIGQKNT RNNARY GROUP: EVENTi PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE NIL E. U.
53 FSIA SAFETY INJECTION.LOOP A AVG FLOM 257. GOOD GPtl 54 F GIB SAFETY INJECTION LOOP B AVG FLOM 256. GOOD GPN 55 P2160 SERVICE MATER PIPS A h B HEADER 85. GOOD PSIG 56 P2161 SERVICE MATER PIIPS C h D HEADER 85. 6008 PSIG 57 BKR041 SERVICE MATER PtIP A GOOD 58 BKR042 SERVICE MATER PlmP B GOOD 59 BKR043 SERVICE MATER PlIP C GOOD 60 BKR044 SERVICE MATER PUNP D GOOD E+J
ROGRAM NAME:LRGTSZ.E OCT 08,92 R.E. GINNA NUCLEAR POlER PLANT 09:30:00 TREND GROUP ASSIGNHEHT
SUMMARY
GROUP HAME GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT m DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FL'W 1485. GOOD GPM 2 LRWST REFUELIHG WATER STORAGE TANK LVL 94.5 GOOD X 3 WS033 33 FOOT LEVEL WIND SPEED 4.1 GOOD MPH 4 WD033 33 FOOT LEVEL WIND DIRECTION 50. GOOD DEG.
5 WT033 33 FOOT LEVEL TEHPERATURE 60.7 GOOD DEGF 6 WT250 250 FOOT LEVEL TEHPERATURE 60.6 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEMP -0.1 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAIKMEHT 7.35678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9 LETDOWN LINE MONITOR 1.47701+02 GOOD MR/H 12 R34 AREA 34 AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35 PASS SAMPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINMENT IODINE MONITOR R10A 9.58719+01 GOOD CPM R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPM R12 CONTAIHMEHT GAS MOHITOR 7.38002i02 GOOD CPM R10B PLANT VENT IOOIHE MONITOR R108 4.30543>01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658t03 GOOD CPM 21 R19 STEAM GEHERATOR BLOWDOWN DRAIN 1.57174+04 HALM CPH 22 R29 AREA 29-COHTAINMENT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINHENT HIGH RANGE 5.09440-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 9.99999+06 BALM CPM 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS ~ 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435.05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261.03 GOOD UCI/CC 29 R14AS PLANT VEHT CHAN 5-LOW RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RAHGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANI'ENT CHAN 9 HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOW RANGE GAS 9.99999.03 BALM UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 1.85392+00 HALM UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-Hl RANGE GAS 1.85436+00 HWRN UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 3.02040+00 HALM MR/HR 36 R32 AREA 32 STEAM LIHE B (SPIKG) 1.01048.02 GOOD MR/NR 37 CVH CV HYDROGEN COHCEHTRATION .0 GOOD X 38 TCV03 CV BASEMENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCV08 CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEHP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD OEGF 0 J
Time: Jg~)
Message: ~~X INNA TATI N 1 2 EVAL ATED EXER I E MESSA E F RM
~f: RI I<<C <<IR Emergency Coordinator RPII Rp I I 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 Reactor Shutdown YES NO Hi h Head S.I. Pum s N-31 N-32 CPS CPS FZ-924 FI-925
~GPMO GPM N-35 /.os-I AMPS 1A. INSERV TB OOS N-36 '-// AMPS 1B. INSERV TB OOS Avg. Nuclear Power 1C. INSERV TB OOS RCS Pressure PRZR Level
~FPSIG ye 2.4 BAST Level = ~OS A RCP STOPPED Low Head S.I. Pum s B RCP RUNNIN STOPPED FI-626 O GPM lA S/G Level 2. 1A. INSERV OOS RECIRC 1B S/G Level 1B. INSERV TB OOS RECIRC
'1A S/G Pressure /0 / PSIG RWST Level = S.
1B S/G Pressure 2.Z PSIG Turbine/Generator INE/ Containment S ra Pum s 4 KV Buses 480V Buses DC Batteries Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level A Loop Hot Leg N RGIZ ENERGIZ A /SOVOLTS
~ DEENERGIZED FI-931A DEENERGIZED B(3OVOLTS
~FO
~ /
1.
G PSIG FEET INCHES OF FZ-93IB~GPM 1A.
1B.
GPM INSERV STB INSERV TB NaOH Tank Level =
Containment Recirc Fans OOS OOS A Loop Cold Leg /1 OF 1A. NSE V STBY OOS B Loop Hot Leg 817. OF 1B. NSERV STBY OOS B Loop Cold Leg OF 1C. INS STBY OOS RVLIS /oo.S' 1D. IN STBY OOS
- CET ~97. 9 OF. Post Accident Dampers PE CLOSED S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow ~~SGPM Service Water Pum s 1A. SE STBY OOS DIESEL GENERATORS 1B. NSE V STBY OOS 1C. NSER STBY OOS A. NING UNLOADE STBY OOS 1D. NS STBY OOS B. RUNNIN ADED STBY OOS A&B Header Pressure S 5 PSIG TSC RUNN NG ADED TB OOS Security RUNNING UNLOA D OOS Com onent Coolin Water Pum s 1A. IN E V STBY 00 ENGINEERED SAFEGUARDS 1B NSERV STBY OOS Aux. Feedwater Pum s Surge Tan vel = ~2 1A. INSERV B OOS Standb Aux. Feedwater Pum s 1B. NSE V STBY OOS 1C. INSERV TB OOS Turb. Driven ERV STBY OOS 1D. INSERV B OOS CST Level FEET
- CET = Average of Selected Core Exit Thermocouples
- 8) 1992 09:45 R. E. GINA SIILATOR PA6E 1 TREND GROUP ASSIGHNEHT SUttt(ARY 6ROUP: EVENT1 PROCEDURE: EPIP 1-5 PLA)(T STATUS POINT ID DESCRIPTION E. U.
1 ATl6 ANTICIPATED TRANSIENT M/0 SCRAtt ATWS ALRN 2 RXT REACTOR TRIP BS(ER STATUS RX TRIPPED ALIN 3 N31 SISCE RANGE DETECTOR N-31 8. 46249+01 GOOD 4 N32 So(ICE RANGE DETECTOR N-32 8.75988+01 6009 5 N35 INTERt(EDIATE RANGE DETECTOR N-35 1.01391-11 6009 6 N36 INTERt(EDIATE RAN6E DETECTOR N-36 1.01391-11 6009 7 t(P AVERAGE NUCLEAR POWER .00 6009 8 PRCS REACTOR COOLANT SYSTEt( AVG PRESS 1085 Lu 9 LPZR PRESSURIZER AVERAGE LEVEL 50 0 2 Goon 10 FRCLA REI:TOR COOLNT LOOP A AVG FLOW 103.1 6009 11 FRCLB REACTOR COOLANT LOOP B AVB FLOW 102.5 Goon 12 RXT16 RCPA BREAKER CAUSE RX TRIP NOT TRIP 6009 13 RXT17 RCPB BREAKER CAUSE RX TRIP HOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED t)ARGIN 58.9 Boo<
15 LSGA STtt GEN A NARROW RAHGE AVG LEVEL 62.6 HWRH 16 LSBB STt( GEN B NA)SOW RANGE AVG LEVEL 33.4 Goon f7 PSBA STH GEtt A AVERAGE PRESSURE 1081. 6009 PSIG 18 PSBB STH GEN B AVERAGE PRESSURE 622. 6009 PSIG GENBKR1 GBHQTOR ON LINE BREAKER 16f372 TRIPPED ALfN 20 GEHBKR2 GBGQTOR ON LINE BREAKER 9X1372 TRIPPED ALR)(
21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRt(
22 BUS11B BUS 11B SUPPLY BREAKER TRIPPED AUN 23 BUSf2A NOT TERNIHATED OH PPCS (7/19/91) NOT TRIP DEL 24 BUS12B HOT TERNIHATED OH PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS 11A TO 12A TIE BRENER NOT TRIP ALR)(
26 B11B12B BUS ifB To 128 TIE BRENER NOT TRIP ALRt(
27 PCV CONTAIN)(EHT AVERAGE PRESSURE ".O9 6009 PSIG 28 LSI(PA CONTAItlt(EHT S)t(P A AVEIWBE i&EL 2.1 GOOD FKf 29 LO942E SU)P B LEVEL 8 INCHES (TRAIN A) LO)tER 6009 30 LO943E SUtP B LEVEL 8 INCHES (TRAIN 9) Lo)(ER Boon 31 LO942D SUtP 8 LEVEL 78 INCHES (TRAIN A) LOWER 6009 32 LO943D SUtP B LEVEL 78 INCHES (TRAIN B) LONER 6009 33 LO942C SUtP B L&EL 113 INCHES(TRAIN A) LOWER 6009 34 LO943C SUtP B LEVEL 113 INCHES(TRAIN B) LOWER 6009 35 LO942B SU)P B LEVEL 180 INDUS(TRAIN A) LOWER 6009 36 LO943B SUtP B LB(EL 180 INCHES(TRAIN B) LO))ER 6009 37 LO942A SUtP B LEVEL 214 INCHES(TRAIN A) LONER 6009 38 LO943A SUtP B LElr'EL 214 INCHES(TRAIN B) LOWER 6009 39 TO409A RCLA HOT LEG TEtlPERATSK 497.4 6009 DEGF 40 T041OA RCLB HOT LE6 TEtiPERATUliE 497.4 6009 KGF 41 TO450 RCLA COLD LEB TE)PERAT(BE 497.9 6009 DEBF 42 T0451 RCLB COLD LEG TEt(PERAT(SE 494.6 6009 DEGF 43 TAVBAMID RCLA TAVG (THOT/TCOLD WIDE RNG) 497.7 6009 DEGF 44 TAVBBWID RCLB TAVB (THOT/TCOLD WIDE RHB) 496.0 6009 DEGF 45 LRV REACTOR VESSEL AVERAGE LEVEL 100.5 6009 X 46 TCCORE E1.1 IHCOPE TC AVERAGE TEt)P 497.4 Gooe DEBF 47 FAUXFWA S/G A TOTAL AUX FEEDWATER FLOW O. GOOD GN 48 FAUXFWB S/6 B TOTAL AUX FEENAlrB FLOW 364. 6009 BPN 49 BKRO81 t(TR AUXILIARYFEEDWATER PlNP A OFF 6009 50 BKR082 t(TR AUXILIARYFEEDWATER PUt(P B ON 6009 51 V3505 AUX FW PIN'TEA)t RFPLY VALVE A CLOSED 6009 52 V3504 AUX FM PlNP STEAN SUPPLY VALVE B OPEN AUN
OCT Bi 1992 09:45 R. E. GINA SINKATOR PA6E 2 TREND GROUP ASSIGNNENT SIOIRY 6ROUP! EVENT1 PRXEDUREl EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE NNL E. U.
53 FSIA SAFETY INJECTION. LOOP A AVG FLOM 0. 600D PN 54 FSIB SAFETY INJECTION LOOP B AV6 FLOW 0. GOOD GPtl 55 P2160 SERVICE MATER PNPS A 5 B HEADER 85. 600D PSI6 56 P2161 SERVICE MATER PIIPS C 5 D HEADER 85. GOOD PSIG 57 BER041 SERVICE MATER PlIP A GOOD 58 INR042 SERVICE MATER PlIP B GOOD 59 BER043 SERVICE MATER PNP C 600D 60 BKR044 SERVICE MATER P1IP D 600D
0 OGRAM NAME I
- LRGTSZ.E
~
OCT 08,92
.E.
~ ~ GIHNA NUCLEAR POWER PLANT 09:44:00 TREND GROUP ASSIGHHENT
SUMMARY
GROUP NAME GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 F0619 COHPONEHT COOLING LOOP TOTAL FLW 1485. G(a) GPM 2 LRWST REFUELING WATER STORAGE TANK LVL 94.5 GOOD X 3 'WS033 33 FOOT LEVEL WIND SPEED 4.9 GOOD MPH 4 WD033 33 FOOT LEVEL WIND DIRECTION 49. GOOD DEG.
5 WT033 33 FOOT LEVEL TEHPERATURE 61.3 GOOD DEGF 6 WT250 250 FOOT LEVEL, TEMPERATURE 61.3 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEMP 0.0 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINMEHT 7.35678i00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.3994& 00 GOOD MR/H 11 R09 AREA 9.LETDOWN LINE MONITOR 1.47701+02 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354.01 GOOD MR/H 13 R35 AREA 35-PASS SAHPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINMENT IODINE MONITOR R10A 9.58719+01 GOOD CPM 15 R11 CONTAINHENT AIR PARTICULATE . 5 '8901+02 GOOD CPH R12 CONTAINMENT GAS MONITOR 7.38002+02 GOOD CPM R10B PLANT VEHT IODINE HONITOR R108 4.30543+01 GOOD CPH R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM 19 R14 AUX BLDG EXHAUST GAS'MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658+03 GOOD CPM 21 R19 STEAM GENERATOR BLOWDOWN DRAIN 1.57174+04 BALM CPM 22 R29 AREA 29-CONTAINMEHT HIGH RANGE 5.05861.01 GOOD R/HR 23 R30 AREA 30-CONTAIHMEHT HIGH RANGE 5 '9440.01 QXO R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 4.40835i06 HALM CPM 25 R12A5 CV VENT CHAN 5 LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD HR/HR 27 R12A7 CV VENT CHAH 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9 HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14AS PLANT VENT CHAN 5-LOW RANGE GAS 4.40312.07 GOOD UCI/CC 30 R14A7 PLAHT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAH 5-LOW 'RAHGE GAS 9.99999-03 HALM UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 2.20392-01 BALM UCI/CC 34 R15A9 AIR EJECTOR CHAH 9-HI RANGE GAS 2.20436-01 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 3.02040100 HALM MR/HR 36 R32 AREA 32 STEAM LIHE 8 (SPIHG) 1 ~ 01048-02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION ~ 0 GOOD X 38 TCV03 CV BASEMEHI'VL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCVOB CV IHTERHEDIATE LVL 6 FT TEHP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEHP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEHP ¹17 117.5 GOOD 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 site, connection and operation of IVlobile Dl Unit.
h iiiiiii 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
INNA 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 ii 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 Hi h Head S.I. Pum s N-31 N-32
~~CPS FI-924 . GPM CPS FI-925 Q GP N-35 i.oe-I AMPS 1A. INSERV OOS N-36 -ll AMPS 1B INSERV TB OOS Avg. Nuclear Power o 1C INSERV TB OOS RCS Pressure PRZR Level 073 PSIG BAST Level = ~p A RCP RUNNING TOP Low Head S.I. Pum s B RCP STOPPED FI-626 Cl GPM 1A S/G Level 1A. INSERV T OOS RECIRC 1B 1A S/G S/G Level Pressure
~'8
~d7 4
~E.
1B S/G Pressure 2.~ PSIG Turbine/Generator ONLINE/ FLIN Containment S ra Pum s 4 KV Buses NERGIZ DEENERGIZED FI-931A 0 GPM 480V Buses NERGIZE DEENERGIZED FI-931B 0 GPM DC Batteries A tSO VOLTS B/BO VOLTS 1A. INSERV B OOS Cnmt Pressure /7 PSIG 1B. INSERV TB OOS nmt Sump A Level 2. I FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg OF Containme Recirc Fans A Loop Cold Leg OF 1A. INSER STBY OOS B Loop Hot Leg f4.I OF 1B. S STBY OOS B Loop Cold Leg ~ 2 OF 1C. NSER STBY OOS RVLIS 1D. NSER STBY OOS
- CET f V4.24F Post Accident Dampers PE CLOSED 3/G A S/G B Total Aux Total Aux FW Flow ~GPM Flow ~13. Service Water FW GPM Pum s 1A. NSER STBY OOS DIESEL GENERATORS 1B. S R STBY OOS 1C. NSE STBY OOS A. RUNNING UNLOADED T OOS 1D. SE V STBY OOS B. RUNNING UNLOADED B OOS A&B Header ressure fh PSIG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. INSERV STBY 0 ENGINEERED SAFEGUARDS 1B. NSER STBY OOS Aux. Feedwater Pum s Surge Tan vel = ~L-1A. INSERV TB OOS Standb Aux. Fe ater Pum s 1B. NSER STBY OOS 1C. INSERV TB OOS Turb. Driven INSERV TB OOS 1D. INSERV TB OOS CST Level FEET
- CET = Average of Selected Core Exit Thermocouples
Bs 1992 10:00 R. E. GINA Sit(ULATOR PAGE 1 TREND GIP ASSIGI(Et(T SUt(t(ARY 6ROUP: EVENTi PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E. U.
1 ATMS ANTICIPATED TRANSIENT W/0 SCRAtt ATNS ALRN 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRt(
3 N31 SolSCE RANGE DETECTOR N-31 8.52117+01 6009 CPS 4 N32 SISCE RANGE DETECTOR N-32 8.8206801 6009 CPS 5 N35 INTEf(t(EDIATE RANGE DETECTOR N-3S 1.01391"Ii 6009 At(P 6 N36 INTER)(EDIATE RANGE DETECTOR N-36 1.01391-11 6009 7 NP AVERAGE NUCLEAR POWER .00 6009 X 8 PRCS REACTOR COOLANT SYSTE)( AVG PRESS 1073. LALt( PSIG LPIR PRESSURIIER AVERAGE LEVEL 51.5 6009 X 10 FRCLA REACTOR COOLANT LOOP A AVG FLOW 12.3 INHB X 11 FRCLB REACTOR COOLANT LOOP 8 AVG FLOW 106.9 600D X 12 RXT16 RCPA BREAKER CAUSE Rr TRIP TRIPPED ALR)(
13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 TSUBTC INCORE TC SUBCOOLED t(ARGIN 58.7 Booe DEGF IS LSBA STt( GEN A NARROW RANGE AV6 LEVEL 60.4 HNRt( X 16 LSBB ST)( GEN B NARROW RANGE AVG LEVEL 49.3 6009 'X 17 PSBA STt( GEN A AVERAGE PRESSURE 1067. 6009 PSIG 18 PSGB STH GEN B AVERAGE PRESSURE 622. GOOD PSIG 19 GENBKRl GBERATOR ON LINE BREAKER 161372 TRIPPED ALRl 20 GENBKR2 BBGQTOR ON LINE BREAKER 9)(1372 TRIPPED ALRt(
21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRt(
22 BUS11B BUS 11B SIPPLY BREAKER TRIPPED ALRt(
23 BUS12A NOT TERt(I@ATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERt(INATED ON PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS 11A TO 12A TIE BREA(ER NOT TRIP AUI 26 BIIB129 BUS 11B TO 128 TIE BREIER NOT TRIP ALRt(
27 PCV CONTAIN)(ENT AVERAGE PRESURE -. 17 6009 28 LS(NPA CONTAINt(ENT SUt(P A AVE)mGE LEVEL 2.1 6009 29 L0942E SU)P 8 LEVEL 8 INCHES (TRAIN A) LONER 6009 30 L0943E SU)P B LEVEL 8 It/CHES (TRAIN B) LONER 6009 31 L0942D SU)P B LEVEL 78 INCHES (TRAIN A) LONER 6009 32 L0943D SUtP B LEVEL 78 INCHES (TRAIN B) LONER 6009 L0942C SUtP B LEVEL 113 INCHES(TRAIN A) LONER 6009 34 L0943C SUtP B LEVEL 113 INCHES(TRAIN B) .LONER BOOB 35 L09428 SUtP B LEVEL 180 INCHES(TRAIN A) LONER 6009 36 L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LONER 6009 37 L0942A SU)P B LEVEL 214 INCHES(TRAIN A) LONER 6009 38 L0943A SUtP B LEVEL 214 INCHES(TRAIN B) LONER 6009 39 T0409A RCLA HOT LEG TEt(PERATURE 493.9 6009 KGF 40 T0410A RCLB HOT LEG TBlPERATURE 496.1 6009 DEBF 41 T0450 RCL4 COLD LEG TEt(PERAT(BE O'.2 6009 DEGF 42 T0451 'RCLB COLD LEG TEt(PERAT(RE 494.2 6009 DEGF 43 TAVGAMID RCLA TAVG (THOT/TCOLD WIDE RNG) 494.1 6009 KGF 44 TAVGBMID RCLB TAVG (THOT/TCOLD WIDE RNG) 495.2 GOOD DE6F 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.6 46 TCCORE El. 1 INCORE TC AVERAGE TEt(P 496.2 DEGF 47 FAUXFWA S/G A:OTAL AUX FEEDMATW FLOW 0. BM9 GPt(
48 FAUXFWB S/6 9 TOTAL AUX FEEDVAm FLOW 129. 6009 9%
49 BKR081 t(TR AU)(ILIARY FEEDMATER PUtF A OFF 6009 50 BKR082 t(TR AU)(ILIARY FEEDMATER PU)(P B 6009 51 V3505 AUX FW PUt(P STEAtl SUPPLY VALVE A CLOSED 52 V3504 AUX FW PlIP STEA)t SLR'LY VALVE B CLOSED
OCT 8~ 892 10:00 R. E. GINA SitSLATN PAGE 2 TREND 6IIP ASSIGNMENT QNNRY 6ROUP: EVENTi PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION NLUE QNL E. U.
53 FSIA SAFETY INJECTION. LOOP A AVG FLOW 0. 6009 Ptl 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. 6009 GPN 55 P2160 SERVICE WATER HIPS A h B HEADER 85. 6009 PSI6 56 P2161 SERVICE WATER PNPS C 5 D HEADER 85. 600D PSI6 57 BKR041 SERVICE WATER PNP A 6009 58 BKR042 SERVICE WATER PIIP B 6009 59 BKR043 SERVICE WATER PllP C 600D 60 BKR044 SERVICE WATER PlIP 9 6009
ROGRAM I NAME:LRGTSZ.E~ OCT 08,92
.E.
~ ~ GIKHA NUCLEAR POWER PLANT 10:00:00 TREND GROUP ASSIGKHENT SUMHARY GROUP NAHE GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS F0619 COMPONENT COOLING LOOP TOTAL FLW 1485. G(XS GPM 2 LRWST REFUELING WATER STORAGE TANK LVL 94.5 GOOD 3 WS033 33 FOOT LEVEL WIND SPEED 5.0 GOOD MPH 4 WD033 33 FOOT LEVEL WINO DIRECTION 55. GOOD DEG.
5 WT033 33 FOOT LEVEL TEMPERATURE 61.3 GOOD DEGF 6 WT250 250 FOOT LEVEL TEMPERATURE 61 4 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEMP 0.1 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINMENT, 7.35678+00 GOOD MR/H 10 R05 AREA 5 SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDOWN LINE MOHITOR 1 47701+02 GOOD HR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD MR/M 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD MR/H 14 R10A COHTAINMEHT IODINE MONITOR R10A 9.58719+01 GOOD CPH R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPH R12 CONTAINHENT GAS MONITOR 7.38002+02 GOOD CPM R108 PLANT VENT IODINE MONITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIDUID 'WASTE DISPOSAL MONITOR 2.78658+03 GOOD CPH 21 R19 STEAM GENERATOR BLOWDDWN DRAIN 1.57174+04 BALM CPM 22 R29 AREA 29-CONTAINMENT HIGH RANGE 5.05861.01 GOOD R/HR R30 AREA 30-CONTAINHENT HIGH RAHGE 5.09440-01 GOOD . R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPH 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS 1.89699.07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMHA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-HID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VEHT CHAN 5-LOW RANGE GAS 4.40312-07 GOOD UCI/CC 30 R'I4A7 PLANt VENT CHAN 7 MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLAN'I VENT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOW RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 1.34492 05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CNAH 9-Hl RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAH LIHE A (SPING) 3.02040+00 NALH MR/HR 36 R32 AREA 32 STEAM LINE 8 (SPING) 1.01048-02 GOOD MR/NR 37 CVN CV HYDROGEN CONCENTRATION ~0 GOOD 38 TCV03 CV BASEHENT LVL 6 FT TEMP ¹3 95 ~ 1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 Ft TEHP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE'LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEHP ¹9 106.7 GOOD DEGF 42 TCV10 CV IHTERMEDIATE LVL 6 Ft TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD. DEGF 0 J
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.
- 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 MAJOR PAEULMETERS . ENGINEERED SAFEGUARDS
'eactor Shutdown ES NO Hi h Head S.I. Pum s N-31 FI-924 ~GPM N-32 C PS FI-925 ~GPM N-35 . E-s AMPS. 1A. INSERV TB OOS N-36 ~oI-AMPS 1B. INSERV B OOS Avg. Nuclear Power 0 1C. ZNSERV TB OOS RCS Pressure OP<7 PSIG BAST Level = /O PRZR Level >4 l g A RCP RUNNING TOPPE Low Head S.Z. Pum s B RCP UNNING STOPPED FZ-626 GPM 1A S/G Level S.~ 4 1A. INSERV TB OOS RECIRC 1B S/G Level 1B. INSERV TB OOS RECIRC 1A 1B S/G S/G Pressure Pressure
~IO7 PS 2.~ PSIG IG RWST Level = ~~4 Turbine/Generator 0 LIN Containment S ra Pum s 4 KV Buses 480V Buses ERGIZE DEENERGIZED FZ-931A 0 GPM ERGIZE DEENERGIZED FI-931B C9 GPM DC Batteries A~VOLTS PO B/3O VOLTS 1A. INSERV TB OOS Cnmt Pressure o I 0 PSIG 1B. INSERV T OOS Cnmt Sump A Level ~2. ~e FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg 'fge OF Containment Recirc Fans A Loop Cold Leg ~1'i~OF 1A. NSER STBY OOS B Loop Hot Leg ~6~40 F 1B. NS STBY OOS B Loop Cold Leg 1C. INSE STBY OOS RVLIS 1D. NSE STBY OOS
- CET OF Post Acci ent Dampers PE CLOSED S/G A Total Aux FW Flow ~GPM S/G B Total Aux FW Flow ~~GPM Service Water Pum s 1A. INSERV STBY 0 DIESEL GENERATORS 1B. S STBY OOS 1C. ER STBY OOS A. RUNNING UNLOADED TB OOS 1D. NSER STBY OOS B. RUNNING UNLOADED TB OOS A&B Header Pressure 7 0 PSIG TSC RUNNING UNLOADED OOS Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. INSERV STBY OS ENGINEERED SAFEGUARDS 1B. ERV STBY OOS Surge Tan vel =
Aux. Feedwater Pum s 1A. INSERV T OOS Standb Aux. Feedwater Pum s 1B. NSER STBY OOS 1C. INSERV TBY OOS Turb. Driven INSERV TB OOS 1D. INSERV 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 POINT ID DESCRIPTION E. U.
1 ATWS ANTICIPATED TRANSIENT W/0 SCRAN ATWS AUI 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRN 3 N31 SIKE RANGE DETECTOR N-31 8.91247%1 600D CPS N32 SMCE RANGE DETECTOR N-32 9.00531401 6009 CPS 5 N35 INTERNEDIATE RANBE DETECTOR N-35 1.01391-11 6009 ANP 6 N36 INIERNEDIATE RANGE DETECTOR N-36 1.01391-11 6009 ANP 7 NP AVERAGE NUCLEAR POWER .00 6009 X 8 PRCS REACTOR COOLANT SYSTEN AVG PRESS 1084. LALN PSIG 9 LPZR PRESSURILER AVERAGE LEVEL 42.7 6009 X 10 FRCLA REACTOR COOLANT LOOP A AVG FLOW 12.3 INHB X 11 FRCLB REACTOR COOLANT LOOP 8 AVG FLOW 106.9 6009 X 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRtl 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED t%5IN 60.5 DEGF 600'3.2 15 LSBA STN GEN A NARROW RANGE AVG LEVEL HWRt(
16 LSGB STN GEN 8 NARROW RANGE AVG LEVEL 48.1 GO09 X 17 PSGA STN 6EN A AVERAGE PRESSURE 1078. 6009 PSI6 18 PSGB STN GEN 8 AVERAGE PRESSURE 622. 6009 PSIG 19 GENBKR1 GBGQTOR ON LINE BREAKER 161372 TRIPPED AUI 20 GENBKR2 BBGQTOR ON LINE BREAKER 9X1372 TRIPPED ALRN 21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRtf 22 BUS118 BUS 118 SUPPLY BREAKER TRIPPED AUI 23 BUS12A NOT TERNINATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS128 NOT TERNINATED Ott PPCS (7/19/91) NOT TRIP DEL 25 811AI2A BUS liA TO 12A TIE BREAKER NOT TRIP ALRtf 26 8118128 BUS 118 To 128 TIE BRENER NOT TRIP ALRN 27 PCV CONTA It(NENT AVERAGE PRESSURE ".19 6009 28 LSlNPA CONTAINNENT PJNP A AVERAGE LEVEL 2.2 6009 29 L0942E SUtP 8 LEVEL 8 INCHES (TRAIN A) LOWER G009 30 L0943E SUtP B LEVEL 8 It(CHES (TRAIN 8) LONER 6009 31 L0942D SUtP' LEVEL 78 It<CHES (TRAIN A) LOWER GOOD 32 L0943D SSP 8 LEVEL 78 INQ!ES (TRAIN 8) LOMER 6009 33 L0942C SUNUP 8 LEVEL 113 INCHES(TRAIN A) LOWER 6009 34 L0943C SUti' LEVEL 113 INCHES(TRAIN 8) LOMER 6009 35 L09428 SUtP 8 LEVEL 180 INCHES(TRAIN A) LOWER 6009 36 L09438 SUtP 8 LEVEL 180 INCHES(TRAIN 8) LOWER 6009 37 L0942A SUtl-' LE'<re 214 INCHES(TRAIN A) LOWER 6009 38 L0943A SUtP 8 LEVEL 214 INCHES(TRAIN 8) LOMER 6009 39 T0409A RC(A HOT LEG TENPERATSK 493.5 GOOD DE6F 40 T0410A RCLB HOT LEG TENPERATURE 495.7 6009 KGF 41 T0450 RCLA COLD LEG TENPERATlBE 493.8 6009 DEBF 42 T0451 RCLB COLD LEG TE)(PERAT(BE 494.0 6009 DE6F 43 TAVGAWID RCLA TAVG (THOT/TCOLD WIDE RNG) 493.7 6009 DE6F 44 TAVGBWID RCLB TAVG (THOT/TCOLD WIDE RNB) 494.8 6009 DEBF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.6 6009 46 TCCORE E1.1 It'CORE TC AVERAGE TENP 495.7 600e DEGF 47 FAUXFWA S/6 A TOTAL AUX FEEDMATER FLOW 0. 6009 PN 48 FAUXFWB S/G 8 TOTAL AUX FEEDWATER FLOW 197. 6009 6PN 49 BKR081 NTR AUXILIARYFEEDWATER PUt(P A OFF G009 50 BKR082 NTR AUXILIARYFEEDMATER PUNP 8 ON 6(I9 51 V3505 AUX FW PlIP STEAN SUPPLY VALVE A CLOSED 6009 52 V3504 AUX FW PU5'TEAN SUPPLY VALVE 8 CLOSED 6009 g-'/I/
XT Gs 1992 10: 14 R. E. GIN@ SIRLATOR PAGE 2 TREND Gm'SSIGlST RNNSY GROUPS EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U.
53 FSIA SAFETY INJECTION LOOP A AVG FLN 0. 600 D GPM 54 FSIB SAFETY INJECTION LOOP 8 AVG FLON 0. 600 D GPN 55 P21b0 SERVICE @TER PlNPS A 5 8 HEADER 72. 600D PSI6 5b P21bi SERVICE NTER PIWPS C h D HEADER 80. GOOD PSIG BKR041 SERVICE HATER PNP A OFF 6009 58 BKR042 SERVICE HATER PNP 8 ON 600D 59 BKR043 SERVICE WTER PuP C ON Gm b0 BKR044 SERVICE WTER PNP 0 ON GOOD E+J
ROGRAM KAME:LRGTSZ.E~ OCT 08,92
.E.
~ ~ GINNA KUCLEAR POKER PLANT 10:16:00 TREND GROUP ASSIGNMEHT SUHHARY GROUP NAHE GROUP DESCRIPTIOH EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPT ION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLU 1485. 6000 GPM 2 LRIIST REFUELING iIATER STORAGE TANK LVL 94.5 6000 X 3 IIS033 33 FOOT LEVEL NIKD SPEED 4.9 6000 MPH 4 M0033 33 FOOT LEVEL KIND DIRECTION 80. GOOD DEG.
5 MT033 33 FOOT LEVEL TEMPERATURE 61.3 GOOD DEGF 6 lIT250 250 FOOT LEVEL TEHPERATURE 63.3 GOOD DEGF 7 IIDT2 250 TO 33 FOOT LEVEL DELTA TEMP 2.0 GOQO DEGF 8 R01 AREA 1-COHTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINHENT 7.35678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 6000 HR/H 11 R09 AREA 9-LETOOMN LINE HOHITOR 1.46701+02 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAHPLE PANEL 1.09283+00 GOOD MR/H 14 CONTAINMENT 1001HE MONITOR R'10A 9.58719+01
'10A GOOD CPM R11 CONTAIHHENT AIR PARTICULATE 5. 18901+02 GOOD CPM R12 COHTAINHENT GAS MOHITOR 7.38002+02 GOOD CPH R108 PLANT VENT IOOIKE HOHITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS HONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID UASTE DISPOSAL MONITOR 2.78658+03 GOOD CPH 21 R19 STEAM GENERATOR BLOMDOMN DRAIN 1.52174+04 HALM CPM 22 R29 AREA 29-CONTAINHENT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINMENT HIGH RANGE 5.09440-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1 '7835+03 GOOD CPM 25 R12AS CV VENT CHAN 5-LOU RAHGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 6000 MR/HR 27 R12A7 CV VENT CHAN 7-HID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14AS PLANT VENT CHAN 5-LO1I RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7 MID RANGE GAS 6.86543.05 GOOD UCI/CC 31 R14A9 PLANT VENT CNAH 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32
'IR R15AS EJECTOR CHAN 5-LOM RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-HID RANGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAH LINE A (SPING) 2.90040+00 HALM MR/HR 36 R32 AREA 32 STEAM LINE 8 (SPIKG) 1.01048.02 6000 MR/HR 37 CVH CV HYDROGEN COHCENTRATION .0 GOOD X 38 TCV03 CV BASEHEHT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERHEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATIHG LVL 6 FT TEHP ¹17 117.5 GOOD DEGF
Time: ~1~1 Message: ~1
~l ~ NA TATI N 2 EVAL ATED EXER I E ME A E F RM
~Mf:A SNAP<
MAZOR PAEULMETERS ENGINEERED SAFEGUARDS Reactor Shutdown YES NO Hi h Head S.I. Pum s N-31 2. CPS FI-924 O GPM N-32 N-35
~CPS I.es (I A-MPS FI-925 1A.
C) GPM INSERV T OOS N-36 II A-MPS 1B. INSERV OOS Avg. Nuclear Power o 1C. INSERV B OOS RCS Pressure O7O7 PSTG BAST Level =
PRZR Level 3 A RCP RUNNING TOPPED Low Head S.I. Pum s B RCP UNNZN STOPPED FZ-626 GPM 1A S/G Level t'e~ 4 1A. INSERV TB OOS RECIRC 1B S/G Level ~sv 1B. INSERV TB OOS RECIRC lA S/G Pressure 07/ PSIG RWST Level = 3.
1B S/G Pressure PSIG Turbine/Generator ONLINE FFLI Containment S ra Pum s 4 KV Buses NERGIZ DEENERGZZED FI-931A & GPM 480V Buses RG D DEENERGIZED FI-931B C) GPM
'DC Batteries A~OVOLTS BIMVOLTS 1A. INSERV T OOS Cnmt Pressure ~ Ll PSIG 1B. INSERV S B OOS Cnmt Sump A Level FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop Hot Leg ~iMQ OF Containment Recirc Fans A Loop Cold Leg VVF 1A. NSE STBY OOS B Loop Hot Leg ~HiS: OF 1B. SE STBY OOS B Loop Cold Leg 'fsI 0 OF 1C. SE STBY OOS RVLIS ~V. 1D. SER STBY OOS
- CET M9'S;7 OF Post Accident Dampers OPE CLOSED S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow ~AF GPM Service Water Pum s 1A. INS V STBY 0 DIESEL GENERATORS 1B. S STBY OOS 1C. NSER STBY OOS A. RUNNING UNLOADED TB OOS 1D. NSER STBY OOS B. RUNNING UNLOADED TB OOS A&B Header ressure ~~b PSZG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. INSERV STBY 0 ENGINEERED SAFEGUARDS 1B. NSER STBY OOS Aux. Feedwater Pum s Surge Tank Level = ~'f 1A. INSERV TB OOS Standb Aux. Feedwater Pum s 1B. SE STBY OOS 1C. INSERV ST OOS Turb. Driven INSERV TB OOS 1D. INSERV STB OOS CST Level ~FEET
- CET = Average of Selected Core Exit Thermocouples
8i 1992 10:30 R. E. GINA SIWLATOR PAGE 1 TREND GRI)P ASSIGN)(ENT SU)tt(ARY 6ROUP: EVENT1 PROCEDURE'PIP I< PLANT STATUS POINT ID DESCRIPTION VALUE I)AL E. U.
1 ATKi ANTICIPATED TRANSIENT M/0 SCRAt( ATMS ALRt(
2 RXT REACTOR TRIP BRENER STATUS RX TRIPPED ALR)(
3 N31 SMICE RA)(GE DETECTOR N-31 8.20350IOI 600D N32 SONCE RAN6E DETECTOR N-32 8.79019401 600D 5 N35 INTER)(EDIATE RANGE DETECTOR N-35 1.01391-11 6009 6 N36 INTER)(EDIATE RANK DETECTOR N"36 1.01391"li 600D 7 NP AVERAGE NUCLEAR POMER .00 GOOD 8 PRCS REACTOR COOLANT SYSTE)f AVG PRESS 1076. LAL)t 9 LPLR PRESSURIZER AVERAGE LEVEL 43.0 600D 10 FRCLA REACTOR COOLANT LOOP A AVG FLOM 12.3 INH3 11 FRCLB REACTOR COOLANT LOOP 8 AVG FLOM 106.9 600D 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALR)t 13 RXT17 RCPB BRENER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED HAIN 59.6 600~ DE6F 15 LSGA STt( GEN A NARROM RANGE AVG LEVEL 62.2 HMR)( y.
16 LSGB STt( 6EN 8 NARROM RANGE AV6 LEVEL 57.1 GOOD y.
17 PSGA STt( GE)t A AVERAGE PRESSURE 1071. GOOD PSIG 18 PS6B STtt GEN 8 AVERAGE PRESSURE 622. GOOD PSIG GENBKRl 696&OR ON LINE BRENER 161372 TRIPPED ALRt(
20 GENBKR2 GBGNTOR ON LINE BRENER 9X1372 TRIPPED ALR)(
21 BUSllA BUS 11A SUPPLY BRENER TRIPPED ALRtf 22 BUS11B BUS 11B SL'PPLY BREAKER TRIPPED ALR)(
23 BUS12A NOT TER)(It(ATED Ot( PPCS (7/19/91) NOT TRIP DEL 24 BUS128 NOT TERHINATED 0)t PPCS (7/19/91) NOT TRIP DEL 25 Bi 1A12A BUS 1lA TO 12A TIE ERENER NOT TRIP ALRtt 26 B11B12B BUS 11B TO 128 TIE BRENER NOT TRIP ALRtt 27 PCV CONTAIN)(Et(T AVERAGE PRESSURE -.21 GOOD 28 LSRlPA CONMINMEtiT StJ5' AVERAGE LEVEL 2.2 GOOD 29 L0942E SU%' LEVEL 8 It(CHES (TRAIN A) LOWER GOOD 30 L0943E SUtP B LEVEL 8 It(CPS (TRAIN B) LOWER 6009 31 L0942D SUlF' LEVEL 78 It<CHES (TRAIN A) LOWER 6000 32 L0943D SU%' LEVEL 78 INCHES (TRAIN 8) LOWER 6009 33 L0942C SUtI' LEVEL 113 INCHES(TRAIN A) LOWER 6XD 34 L0943C SUtP 8 LEVEL 113 INCHES(TRAIN 8) LOWER 6000 35 L0942B SU!I' LEVEL 180 INCHES(TRAIN A) LOWER 6000 36 L0943B SUtF' LEVEL 180 INCHES(TRAIN 8) LOWER 600))
37 L0942A SSP 8 LEVEL 214 INCHES(TRAIN A) LOWER GOOD 38 L0943A SUtP B LEVEL 214 INCHES(TRAIN 8) LOWER GOOD 39 T0409A RCLA HOT LEG TE)(PERATURE 493.5 6000 DEGF 40 T0410A RCLB HOT LEG TEt(PERATURE 495.5 GOOD KGF 41 T0450 RCLA COLD LEG TEt(PERATNE 493.8 GOOD DEGF 42 T0451 RCLB COLD LEG TEt(PERATNE 494.0 GOOD lKGF 43 TAVGAMID R(u TAVG (THOT/TCOLD MIDE RNG) 493.7 GOOD DE6F 44 TAVGBMID RCLB TAVG (THOT/TCOLD MIDE RN6) 494.7 GOOD DEGF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.6 )(
46 TCCORE El. 1 INCOPE TC AVERAGE TEttP 495.7 6000 DEGF 47 FAUXFMA S/G A TOTP AUX FEEDMATER FLOM 0. 6009 PN 48 FAUXFMB S/6 B TOTAL AUX FEEDMATlJt FLOW 158. 600D GPt(
49 BKR081 t(TR AUXILIARYFEEDMATER PU)(P A OFF GOOD 50 BKR082 t(TR AUXILIARYFEEDMATER PU)(P B ON GDOD 51 V3505 AUX FM PUtP 'STEAt( SUPPLY VALVE A 52 V3504 AUX FM PUt'iP STEA)l SUPPLY VALVE 8 CLOSED 600D I
p-/2/
XT 8s 1992 10:30 R. E" GINA SINILATOR PAGE 2
'TREND GROUP ASSIMENT SNNARY GROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U.
53 FSIA SAFETY IN:ECTION:LOOP A AVG FLOW 0. 600 D GPtI 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. GOOD GPN 55 P2160 SERVICE MATER PINPS A & B HEADER 72. 600D PSI6 56 P2161 SERVICE MATER PNIPS C & D HEADER 80. GOOD PSI6 57 BKR041 SERVICE WATER PNP A 600D 58 BNR042 SERVICE MATER PlNP B GOOD 59 INR043 SERVICE MATER PNIP C GOOD 60 INR044 SERVICE MATER PNIP 0 Gm EMJ
ROGRAM NAHE:LRGTSZ.E OCT 08,92 R.E.
~ ~ GINNA NUCLEAR PSJER PLANT 10:32:00 TREND GROUP ASSIGNHENT
SUMMARY
GROUP NAHE GROUP DESCRIPTIOH EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE EHGR UNITS 1 F0619 COHPONENT COOI.IHG LOOP TOTAL FLII 1485. GOOD GPH 2 LRNST REFUELING 'MATER STORAGE TANK LVL 94 ' GOOD X 3 NS033 33 FOOT LEVEL MIND SPEED 4.8 GOM MPH 4 IID033 33 FOOT LEVEL IJIND DIRECTION 80. GOOD DEG.
5 llT033 33 FOOT LEVEL TEMPERATURE 61.3 GOOD DEGF 6 MT250 250 FOOT LEVEL TEMPERATURE '3.0 GOOD DEGF 7 IST2 250 TO 33 FOOT LEVEL DELTA TEMP 1.7 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINHENT 7.35678+00 GOOD HR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDOWN LINE MONITOR 1.43501+02 GOOD HR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINHENT IODINE HONITOR R10A 9.58719+01 GOOD CPM R11 CONTAINHENT AIR PARTICULATE 5.18901+02 GOOD CPH R12 CONTAINMENT GAS HONITOR 7 38002+02 G(XX) CPH R10B PLANT VENT IODINE HONITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPH R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID HASTE DISPOSAL HONITOR 2.78658+03 GOOD CPH 21 R19 STEAH GENERATOR BLDNDDNN DRAIN 1.47174+04 HALH CPH 22 R29 AREA 29-CONTAINHEHT HIGH RANGE 5.05861.01 GOOD R/HR 23 R30 AREA 30-COHTAINHEHT HIGH RANGE 5.09440-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPM 25 R12AS CV VENT CHAN 5-LRI RANGE GAS 1.89699.07 GOOD UCI/CC 26 R'l2A6 CV VENT CHAN 6 AREA GAMMA 2.53990.02 GOOD HR/NR 27 R12A7 CV VENT CHAN 7-HID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CNAH 5-Lml RANGE GAS 4.40312.07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-HID RANGE GAS 6.86543.05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LQI RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAM 7-MID RANGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAH LINE A (SPING) 2.85040+00 NALM MR/HR 36 R32 AREA 32 STEAH LINE 8 (SPING) 1.01048.02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD X 38 TCV03 CV BASEMENT LVL 6 FT TEHP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERHEDIATE LVL 6 FT TEHP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEHP ¹9 106.7 GOOD DEGF 42 TCV10 CV IHTERHEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD DEGF 0 J
Time: ~~4 Message: ~4 INNA 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:
- 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.
- 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.
199 EVALUATED EXERCISE Time: /0'/b MAZOR PAEUQIETERS ENGINEERED SAFEGUARDS Reactor Shutdown ES NO Hi h Head S.I. Pum s N-31 N-32
~CPS CPS F1-924 ~GPM Fl-925 ~GPM N-35 I.o a-I AMFS 1A INSERV TB OOS N-36 ~/AMPS 1B. INSERV B OOS Avg. Nuclear Power 1C. INSERV TB OOS RCS Pressure O7 PSIG BAST Level = /O PRZR Level A RCP RUNNING TOPPE Low Head S.I. Pum s B RCP UNNI STOPPED FI-626 O GPM 1A S/G 1B S/G Level Level
~ls AVE
& 1A. INSERV TB OOS RECIRC 1B. INSERV TB OOS RECIRC lA S/G Pressure 4 PSZG RWST Level = S.
1B S/G Pressure R~ PSIG Turbine/Generator ONLINE/ F Containment S ra Pum s 4 KV Buses NERGIZ DEENERGIZED FI-931A C7 GPM 480V Buses NERGIZ DEENERGIZED FI-931B~GP DC Batteries A~lo VOLTS B ISOVOLTS 1A. INSERV T OOS Cnmt Pressure ~~ 2a. PSTG 1B. INSERV TB OOS Cnmt Sump A Level 24 3 FEET NaOH Tank Level =
Cnmt Sump B Level INCHES A Loop .Hot Leg OF Containment Recirc Fans A Loop Cold Leg f73 P OF 1A. SERV STBY OOS B Loop Hot Leg 8.K 0F 1B. NSE STBY OOS B Loop Cold Leg 97 .o 0F 1C. R STBY OOS RVLIS %& 1D. INSERV STBY OOS
- CET ~9.7 OF Post Aces ent Dampers OPE CLOSED S/G A Total Aux FW Flow O GPM 5/G B Total Aux FW Flow ~SGPM Service Water Pum s 1A. INSERV STBY OS DIESEL GENERATORS 1B. S STBY OOS 1C. SE STBY OOS A. RUNNING UNLOADED TB OOS 1D. NSER STBY OOS B. RUNNING UNLOADED TB OOS A&B Header Pressure ~7 0 PSTG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. INSERV STBY OS ENGINEERED SAFEGUARDS 1B. NSE V STBY OOS Aux. Feedwater Pum s Surge Tau vel = ~5 1A. INSERV B OOS Standb Aux. Fe water Pum s 1B. NSE STBY OOS 1C. INSERV TB OOS Turb. Driven INSERV TB OOS 1D. INSERV TB OOS CST Level ~FEET
- CET = Average of Selected Core Exit Thermocouples
,8~ 1992 10'44 R. E. GMA SINULATOR PA6E 1 TREND GROUP ASSIBNNENT SUNNARY 6ROUP: EVENT} PROCEDURE} EPIP 1-5 PLANT STATUS POINT'D DESCRIPTION U.
1 ATMS ANTICIPATED TRANSIENT M/0 SCRAN ATMS ALRfi 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALR)(
3 N31 SO(jKE RANGE DETECTOR N-31 8.6397}%} 6009 CPS N32 SMCE RANGE DETECTOR N-32 8.8206M)i 6009 CPS
'5 N35 INTERNEDIATE RANGE DETECTOR N-35 1.01391-11 6009 ANP 6 N36 INTEI(NEDIATE RANGE DETECTOR N-36 1.01391-11 6009 7 NP AVERAGE NUCLEAR POWER .00 6009 X 8 PRCS REACTOR COOLANT SYSTEN AVG PRESS 1071. LAL)( PSIB LP2R PRESSURI2ER AVERAGE LEVEL 43.4 6009 X 10 FR%A REACTOR COOLANT LOOP A AVG FLOW 12.3 INHB X ii FRCLB REACTOR COOLANT LOOP B AVG FLOW 106.9 6009 X 12 RXT}6 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRN 13 RXT}7 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED NARBIN 59,0 600t DEGF 15 LSBA STN GEN A NARROM RANGE AVG LEVEL 6}.5 HMRt( X 16 LSBB STN GEN B NARROM RANGE AVG LEVEL 64.3 HMR)( X 17 PSBA STN GEN A AVERAGE PRESSURE 1065. 6009 PSIG 18 PSBB STN BEN B AVERAGE PRESSURE 622. GOOD PSIG 19 GENBKR} GENERATOR ON LINE BREAKFR 161372 TRIPPED ALRt(
20 GENBKR2 GsSRATOR ON LINE BREAKER 9X1372 TRIPPED ALRt(
21 'BUSA BUS 11A SUPPLY BREAKER TRIPPED ALRt( 22 BUS}1B BUS 11B SUPPLY BREAKER TRIPPED ALRt( 23 BUS12A NOT TERNINATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS}2B NOT TERNlhATED Ott PPCS (7/19/91) NOT TRIP DEL 25 B}1A}2A BUS ilA TQ 12A TIE BRENER N)T TRIP ALRN 26 Bi}B12B BUS 1}B TO 128 TIE BREAKER NOT TRIP ALRt( 27 PCV CONTAINNENT AVERAGE PRESSURE -.21 GOOD 28 LS(@PA CONTAINNENT SUNP A AVERAGE LEVEL 2.3 HMRt( 29 L0942i SU)4' LEVEL 8 INCHES (TRAIN A) ~ LONER GOOD 30 L0943E SU%' LEVEL 8 INCHES (TRAIN 9) LOltER 6009 31 L0942D SSP B LEVEL 78 INCHES (TRAIN A) LOWER 6009 32 L0943D SUtP B LEVEL 78 INQSS (TRAIN B) LOWER 6009 33 L0942C SUtP B LEVEL 113 INCHES(TRAIN A) LOWER 6009 34 LO943C SUN' LEVEL 113 INCHES(TRAIN B) LOWER 6009 35 L0942B SU%' LEItcL 180 INCHES(TRAIN A) LONER 6009 36 L09439 SUtP B LEVEL }80 INCHES(TRAIN B) LOWER GOOD 37 L0942A SUt} B LEVEL 214 INCHES(TRAlt< A) LOWER 6009 38 L0943A SUtP B LEVEL 214 INCHES(TRAIN B) LOWER 6009 39 T0409A RCL/) HOT LEG TENPERATUFE 493.5 600D DEBF 40 T0410A RCLB HOT LEG TENPERATURE 495.5 6009 KGF 41 T0450 RCLA COLD LEG TE)IPERATNE 493.8 6009 DEGF 42 T0451 'RCLB COLD LEG TE)IPERATNE 494.0 6009 DEGF 43 TAVGAMID RCLA TAVG (THQT/TCOLD WIDE RNB) 493.7 G009 DEBF 44 TAVGBMID RCLB TAVB (THOT/TCOLD WIDE RNB) 494.7 6009 DEBF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.6 6009 / 46 TCCORE El.l INCORE TC AVERAGE TENP 495.7 600~ DE6F 47 FAUXFWA S/6 A TOTAL AUX FEEDMATER FLOW 0. 6009 PN 48 FAUXFMB S/G B TOTAL AUX FEEDMATER FLOW 158. 6009 GPN 49 BKR081 NTR AUXILIARYFEEDMATER PU)(P A OFF GOOD 50 BKR082 NTR AUXILIARYFEEDMATER PUNP B ON GOOD 51 V3505 AUX FM PUt(P STEAN SUPPLY VALVE A CLOSED 6009 52 V3504 AUX FM PUt(P STEA)I SUPPLY VALVE B CLOSED GOOD F-12
OCT Hs 1992 10:44 R. E. 6INA SINLATOR PASE 2
'REND 6ROUP ASSISINENT SUSARY 6ROUP: EVBIT1 PRXEDURE'PIP 1-5 PLANT STATUS POINT IO DESCRIPTION VALUE NNL E. U.
53 FSIA SAFETY INJECTION LOOP A AV6 FLOW 0. 600D 6Pll 54 FSIB SAFETY INJECTION LOOP B AV6 FLOM 0. 600D 6PII 55 P2160 SERVICE MATER PNIPS A h B HEADER 72. 600D PSI6 56 P2161 SERVICE MATER PNIPS C 5 0 HEADER 80. 6000 PSI6 57 INR041 SERVICE MATER PNIP A 600D 58 BIIR042 SEINICE WATER PNIP B 600D 59 BKR043 SEINICE WATER PINP C 600D 60 BIIR044 SEINICE WATER PUIIP D 600D
OGRAM HAME:LRGTSZ.E~ OCT 08,92
.E.
~ ~ GINNA NUCLEAR PONER PLANT 10:49:00 TREND GROUP ASSIGNHENT
SUMMARY
GROUP NAHE GROUP DESCRIPTION EVEHT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTIOH CURRENT VALUE QUALITY CODE ENGR UNITS F0619 COMPONENT COOLING LOOP TOTAL FLll 1485. GOOD GPH 2 LRIIST REFUELIHG IIATER STORAGE TANK LVL 94.5 GOOD )I 3 WS033 33 FOOT LEVEL HIND SPEED 5.2 GOOD MPH 4 M)033 33 FOOT LEVEL MIND DIRECTION 79. GOOD DEG. 5 MT033 33 FOOT LEVEL TEMPERATURE 61.4 GOOD DEGF 6 WT250 250 FOOT LEVEL TEMPERATURE 63.5 GOOD DEGF 7 IST2 250 TO 33 FOOT LEVEL DELTA TEHP 2.1 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GO(e MR/H 9 R02 AREA 2-CONTAIHHEHT 7.35678i00 GOOD HR/H 10 R05 AREA 5.SPENT FUEL PIT 1.3994&00 GOOD MR/H R09 AREA 9-LETDONN LIHE MONITOR 1.41701+02 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINMENT IODINE HONITOR R10A 9.58715401 GOOD CPM R11 CONTAINMEHT AIR PARTICULATE 5.18901+02 GOOD CPH R'12 CONTAINMENT GAS HONITOR 7.38002+02 GOOD CPM R10B PLANT VEHT IODINE MONITOR R108 4.30543i01 GOOD CPH R'13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID IIASTE DISPOSAL MOHITOR 2.78658t03 GOOD CPM 21 R19 STEAM GEHERATOR BLONDONN DRAIN 1.42174i04 HALH CPH 22 R29 AREA 29-CONTAINMENT HIGH RANGE 5.05861-01 GOOD R/HR R30 AREA 30 CONTAINMENT HIGH RANGE 5.09440.01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPH 25 R12A5 CV VEHT CHAN 5-LDN RANGE GAS 1.89699.07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAHHA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAH 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAH 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOLI RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7 HID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CNAH 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAM 5-LOW'RANGE GAS 2.09411.07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-HID RANGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-Hl RAHGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 2.72040t00 HALH MR/NR 36 R32 AREA 32 STEAM LINE B (SPING) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEN COHCEHTRATIOH .0 GOOD X 38 TCV03 CV BASEMEHT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEHP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEHP ¹17 117.5 GOOD DEGF 0-
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 Reactor Shutdown YES NO Hi h Head S.I. Pum s N-31 CPS FI-924 CO GPM N-32 ~~CPS FI-925 ~GPM N-35 ~=-// AMPS 1A INSERV OOS 0IMPS N-36 1B. INSERV B OOS Avg. Nuclear Power 1C. INSERV TB OOS RCS Pressure PRZR Level oÃei psIG 93 ~ BAST Level = ~g A RCP R NG/ TOPPED Low Head S.I. Pum s B RCP UNNIN STOPPED FI-626 N GPM lA S/G Level 1B S/G Level
~'L 4 1A. INSERV 1B ~ INSERV OOS RECIRC TB OOS RECIRC 1A S/G Pressure ~o~PSIG RWST Level =
1B S/G Pressure 85 PSIG Turbine/Generator NLINE FFLI Containment S ra Pum s 4 KV Buses NERGIZED DEENERGIZED FI-931A GPM 480V Buses DC Batteries ERGIZE DEENERGIZED FI-93 IB~GPM AfSo VOLTS B/So VOLTS 1A. INSERV TB OOS Cnmt Pressure em I PSIG 1B. INSERV TB OOS Cnmt Sump A Level Z. 3 FEET NaOH Tank Level = Cnmt Sump B Level INCHES A Loop Hot Leg 9d. OF Containment Recirc Fans A Loop Cold Leg OF 1A SE STBY OOS B Loop Hot Leg l~n.2 OF 1B. INSE STBY OOS B Loop Cold Leg ~gZ- OF 1C. R STBY OOS RVLIS c~7 1D. INSER STBY OOS
- CET 9JL'5~~OF Post Aces ent Dampers PEN CLOSED A Total Aux FW Flow o GPM '/G S/G B Total Aux FW Flow V2 GPM Service Water Pum s 1A. INS STBY 0 DIESEL GENERATORS 1B. SE STBY OOS 1C. SE STBY OOS A. RUNNING UNLOADED T Y OOS 1D. SE STBY OOS B. RUNNING UNLOADED B OOS A&B Header Pressure ~V ~PSIG TSC RUNNING UNLOADED OOS Security RUNNING UNLOADED T OOS Com onent Coolin Water Pum s 1A. INS V STBY 00 ENGINEERED.SAFEGUARDS Aux. Feedwater Pum s 1B.
Surge Tan NSERV STBY OOS Level = ~/ 1A. INS RV TB OOS Standb Aux. Fe ater Pum s 1B. NSER STBY OOS 1C. INSERV T OOS Turb. Driven INSERV STB OOS 1D. INSERV TB OOS CST Level FEET
- CET = Average of Selected Core Exit Thermocouples
OCT Gi 1992 II:(O R. E. BIWA SltaLATOR PAGE 1 TREND 6ROUP AKIGtmENT SUt(NARY 6ROUP: EVENT1 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E. U, 1 ATNS ANTICIPATED TRANSIENT N/0 SCRA)( ATWS ALRI( 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRII 3 N31 SMICE RANGE DETECTOR N-31 8.46249+01 600D CPS 4 N32 So(SCE RA%E DETECTOR N-32 8.28893+01 600D CPS 5 N35 INTERMEDIATE RANGE DETECTOR N"35 1.01391-11 6000 NP 6 N36 INIERt(EDNTE RANGE DETECTOR,N-36 1.01391-11 GOOD At(P 7 NP AVERAGE NLGSAR POWER .00 6000 X 8 PRK REACTOR COOLANT SYSTEt( AVG PRESS 1056. LALII PSIG 9 LPIR PRESSURIIER AVERAGE LEVEL 43.1 600D X 10 FRCLA REACTOR COOLANT LOOP A AVG FLOW 12.3 INHH 11 FRCLB REACTOR COOLANT LOOP B AVG FLOW 107.5 GOOD X 12 R)(T16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRI( 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP Goon 14 TSUBTC INCORE TC SUKOOLED tmRBIN 63.1 Gooe KGF 15 LSGA STN GEN.A NARRON RAhBE AVG LEVEL 59.6 HNRN X
'X 16 LSGB STtl GEN B NARROW RANGE AVG LEVEL 50.5 6000 !7 PSGA STN GEN A AVERAGE PRESSURE 1053. 6009 PSIG 18 PSGB STtt GEtt B AVERAGE PRESSURE 585. LNRt( PSIG 19 GENBKRI GBGQTOR ON LINE BREAKER 161372 20 GENBKR2 GENERATOR ON LINE BREAKER 9X1372 TRIPPED ALRI(
21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRI( 22 BUS11B BUS 11B SUPPLY BREAKER TRIPPED ALR( 23 BUS12A NOT TERHlt(ATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS12B t<OT TERHINATED ON PPCS (7/19/91) NOT TRIP DEL 25 BIIA12A BUS 11A TO 12A T[E BREWER NOT TRIP ALRI( 26 B110129 BUS 11B TO 12B TIE BREAKER NOT TRIP ALRI( 27 PCV CONTAIOENT AVERAGE PRESURE -.21 6000 28 LS(NPA CONTAIN)(ENT SUt(P A AVERAGE LEVEL 2.3 HWRt( 29 L0942E SUtP B LEVEL 8 INCHES (TRAIN A) LOWER GOOD 30 L0943E SUtP B LEVEL 8 INCHES (TRAIN 0) LONER Boon 31 L09429 SUtP B LEVEL 78 INCHES (TRAIN A) LOWER 6000 32 L0943D SUtP B LEVEL 78 INCHES (TRAIN B) LOWER 6000 33 L0942C SUtP B LEAL 113 INCHES(TRAIN A) LOWER 6000 34 L0943C SUtP B LEVEL 113 INCHES(TRAIN B) LONER 6000 35 L09420 SUIP B LEVEL 180 INCHES(TRAIN A) LOWER 6000 36 L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LOWER 6000 37 L0942A SUtP B LEVEL 214 It(CHES(TRAIN A) LOWER 6000 38 L0943A SUNUP B LEVEL 214 INCHES(TRAIN B) LOWER 6000 39 T0409A BC'OT LEG TEt(PERATLK 490.4 600D DE6F 40 T0410A RRB HOT LEG TEIIPERATUlt= 490.2 6009 KGF 41 T0450 RCLA COLD LEG TEtFERATNE 488.4 6000 DEGF 42 T0451 RCLB COLD LEB TEtPERATNE 488.2 6000 DEGF 43 TAVBAWID RCLA TAVG (TKIT/TCOLD WIDE RNB) 489.4 6000 KGF 44 TAVBBWID RCLB TAVG (TtK)T/TCOLD WIDE RNB) 489.2 GOOD DEGF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.7 6000 X 46 TCCORE El. 1 INCORE TC AVERAGE TEt(P 489.9 Boot DEBF 47 FAUXFWA S/G A TOTAL AUX FEEDMATER FLOM 0. 6009 GPtl 48 FAUXFWB S/G B TOTAl. AUX FEEDMATER FLOW 72. 6000 GPtl 49 BKFQBI t(TR AUXILIARYFEEDMATER PUt(P A OFF GOOD 50 BKR082 tITR AU)(ILIARY FEEDNATER PIWP 0 ON 6600 51 V3505 AU)( FW PUI(P STEAN SIFPLY VALVE A cLOBED . Boon 52 V3504 AUX FM PULE'TEA)I SL4'PLY VALVE B CLOSED 6000 p
OCT Gi 1992 11:00 R. E. GINA SINKATOR PAGE 2 TREND 6ROUP ASSIGNEttT RNtNRY GROUP: EVENT1 PRXEDURE'PIP 1-5 PLAttT STATUS POINT ID 'DESCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY INJECTION'LOOP A AVG FLOW 0. 600D PN 54 F GIB SAFETY INJECTION LOOP B AVG FLOW 0. GOOD 6PN 55 P2160 SERVICE WATER PUtrPS A h B HEADER 72. 600D PSI6 56 P2161 SERVICE MATER PNPS C 5 D HEADER 80. GOOD PSI6 57 BKR041 SERVICE WATER PUtIP A GOOD 58 BKR042 SERVICE WATER PNP B GOOD 59 BKR043 SERVICE WATER PNP C GOOD 60 BKR044 SERVICE WATER PINP D GOOD
OGRAM NAME:LRGTSZ.E
~ OCT 08,92 R.E.
~ ~ GINNA NUCLEAR POUER PLANT 11:01:00 TREHD GROUP ASSIGNHENT
SUMMARY
GROUP NAME GROUP DESCRIPTIOH EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 ~ F0619 COMPONENT COOLING LOOP TOTAL FLII 1485. GOOD GPH 2 LR'IIST REFUELIMG IIATER STORAGE TANK LVL 94.5 GOOD X 3 WS033 33 FOOT LEVEL IIIND SPEED 4.8 GOOD MPH 4 IJD 033 33 FOOT LEVEL MIND DIRECTION 79. GOOD DEG. 5 IIT033 33 FOOT LEVEL TEHPERATURE 62.4 GOOD DEGF 6 MT250 250 FOOT LEVEL TEMPERATURE 64.9 GOOD DEGF 7 NDT2 250 TO 33 FOOT LEVEL DELTA TEMP 2.5 GOOD DEGF 8 R01 AREA 1-CONTROL ROOH 9.02214-02 6000 HR/H 9 R02 AREA 2-CONTAINMEHT 7.35678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.3994&00 6000 MR/H 11 R09 AREA 9-LETDONM LINE MONITOR 1.38701+02 6000 MR/H 12 R34 AREA 34 AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINMEHT IODINE HOHITOR R10A 9.58719101 GOOD CPH R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPM R12 COHTAIHHEHT GAS MONITOR 7.38002+02 GOOD CPM R10B PLANT VEHT IOOIHE MONITOR R10B 4.30543+01 GOOD CPM R'13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPH R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID IIASTE DISPOSAL HONITOR 2.78658+03 6000 CPM 21 R19 STEAM GEHERATOR BLOMDONN DRAIH 1.38174+04 HALH CPM 22 R29 AREA 29-CONTAINHENT HIGH RANGE 5.05861-01 GOOD R/NR 23 R30 AREA 30-CONTAINMENT HIGH RANGE 5.09440.0'I GOOD R/HR 24 R15 COHDEHSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPM 25 R12A5 CV VENT CHAM 5-LOII RANGE GAS 1.89699-07 6000 UCI/CC 26 R12A6 CV VENT CHAH 6-AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261.03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOM RAMGE GAS 4 '0312.07 GOOD UCI/CC 30 R14A7 PLANT VEHT CHAN 7.MID RANGE GAS 6.865C3-05 GOOD UCI/CC 31 R14A9 PLANT VEHT CHAN 9 HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5 LOU RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-HID RANGE GAS 1.34492-05 6000 UCI/CC 34 R15A9 AIR EJECTOR CHAN 9 Hl RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 2.680CO+00 BALM MR/HR 36 R32 AREA 32 STEAH LINE B (SPIKG) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEH CONCENTRATION .0 GOOD X 38 TCV03 CV BASEMENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 . TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCV08 CV INTERMEDIATE LVL 6 FT TEHP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 6(XN DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD 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 INITIALCONDITIONS: 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 INNA 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.
ROCHKSTKI GAS AND KLECTltC COIttOltATION mrna s GINNA STATION: DATE: PAGE OF sOB: Sks'rcpt
' >g AtV $ 78~~ LEAL MADE BY:
o
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 Reactor Shutdown E NO Hi h Head S.I. Pum s N-3 1 3 CPS FI-924 O GPM N-32 ~~CPS FI-925 & GPM N-35 N-36 t,~ I I g,@~AMPS AMPS 1A. 1B. INSERV INSERV T TB OOS OOS Avg. Nuclear Power 1C. INSERV TB OOS RCS Pressure 025 PSIG BAST Level = 0 PRZR Level A RCP R TOPPE Low Head S.I. Pum s B RCP UNN N STOPPED FI-626 GPM 1A S/G Level 1A INSERV B OOS RECIRC 1B S/G Level .I 1B. INSERV B OOS RECIRC lA S/G Pressure PSIG RWST Level = 3. 1B S/G Pressure PSIG Turbine/Generator ONLINE FL NE Containment S ra Pum s 4 KV Buses NERGIZE DEENERGIZED FI-931A 0 GPM 480V Buses NERGIZE DEENERGIZED Fi-931B~GPM DC Batteries A~OVOLTS B/So VOLTS 1A. INSERV B OOS Cnmt Pressure ~ 2. PSIG 1B. INSERV TB OOS Cnmt Sump A Level FEET NaOH Tank Level = Cnmt Sump B Level INCHES A Loop'Hot Leg 7z. OF Containment Recirc Fans A Loop Cold Leg Qadi ~ OF 1A. NSE STBY OOS B Loop Hot Leg 7 ~ OF 1B. NSER STBY OOS B Loop Cold Leg OF 1C. NSE STBY OOS RVLIS 1D. NSE STBY OOS
*CET e OF Post Accident Dampers PE CLOSED S/G A Total Aux FW Flow O GPM S/G B Total Aux FH Flow ~&GPM Service Water Pum s 1A. INSERV STBY 0 DIESEL GENERATORS 1B. NSE STBY OOS 1C. ER STBY OOS A.
B. RUNNING UNLOADED RUNNING UNLOADED STB OOS TSC RUNNING UNLOADED TB OOS OOS 1D. SERV STBY OOS A&B Header Pressure ~0 PSXG Security RUNNING UNLOADED STB OOS Com onent Coolin Water Pum s 1A. INSER STBY ENGINEERED SAFEGUARDS 1B. NSER STBY OOS Aux. Feedwater Pum s Surge Tank Level ~7 1A. INSERV TB OOS Standb Aux. Feedwater Pum s 1B. NS R STBY OOS 1C. INSERV TB OOS Turb. Driven INSERV B OOS 1D. INSERV TB OOS CST Level a*CET = Average FEET of Selected Core Exit Thermocouples F-~W
8s 1992 11: 15 R. E. GINA SIMULATOR PA6E 1 TRB(D GROUP ASSIGHMEHT
SUMMARY
GROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E. U. 1 AT% ANTICIPATED TRANSIENT M/0 SCRAM ATMS ALRt( 2 RXT REACTOR TRIP BRENER STATUS RX TRIPPED ALII 3 N31 SMKE RANGE DETECTOR H-31 8.31763K)I 6009 CPS N32 SONCE RA%E DETECTOR N-32 8.66958~01 6009 CPS 5 N35 INIEfIEDIATE RANGE DETECTOR N-35 1.01391-11 6009 AMP 6 H36 INTERMEDIATE RANGE DETECTOR N-36 1.01391-11 6009 AMP 7 t(P AVERAGE NUCLEAR POWER .00 6009 '/ 8 PRCS REACTOR COOLANT SYSTEM AVG PRESS 1025. LALt( PSIG 9 LPIR PRESSURIIER AVERAGE LEVB. 41.6 600D X 10 FRCLA REACTOR COOLANT LOOP A AVG FLOW 12.6 INHB / 11 FRCLB REACTOR COOLANT 1.00P B AVG FLOW 109,4 6009 / RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALfi 13 RXTij RCPB BRENER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED MARGIN 77.9 600~ KGF 15 LSGA STM GEH A NARROW RANGE AVG LEVEL 53.5 6009 X 16 LSGB STM GB( B NARROW RANGE AVG LEVEL 36.1 6009 17 PSGA STM GEH A AVERAGE PRESSURE 1024. 6009 PSIG 18 PSGB STM 6Ett B AVERAGE PRESSURE 469. LALM PSI6 19 GEHBKR! GEtGMTOR. ON LINE BREAKER 1G1372 TRIPPED ALRt( 20 GENBKR2 GsJRRATOR ON LINE BREAKER 9X1372 TRIPPED ALII 21 BUS11A BUS 11A SUPPLY BRENER TRIPPED ALRt( 22 BUS11B BUS llB SUPPLY BRENER TRIPPED ALII 23 BUS12A HOT TERMINATED OH PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERMINATED OH PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS 11A TG 12A TIE BRENER NOT TRIP ALRt( 26 BllB12B BUS 11B TG 12B TIE BRENER NOT TRIP ALRt( 27 PCV CONTAINMEHT AVERAGE PRESSURE -.21 GOOD PSIG 28 LSWPA CGNTAIHMEt(T SUMP A AVERAGE LEVEL 2.4 HWRN 29 L0942E SSP B LEVEL 8 INCHES (TRAIN A) LO)(ER 6009 30 L0943E SUtP B LEVEL 8 INCHES (TRAIN 9) LONER G009 31 L0942D SUtF' LEVEL 78 ItKHES (TRAIN A) LONER 6009 32 L09439 SUtP B LEVEL 78 IHC)'.cS (TRAIN B) LONER 6009 33 L0942C SUtP B LEVFL 113 INCHES(TRAIN A) LONER 6009 34 L0943C SUN' LEVEL 113 INCHES(TRAIN B) LO))ER 6009 35 L0942B SUtP B LE(tcL 180 INCHES(TRAIN A) LO)tER 6009
- 36. L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LO)tER GOOD 37 L0942A SU%' LEVcL 214 INCHES(TRAIN A) LO)tER 6009 38 L0943A SUP B LEVEL 214 INCHES(TRAIN B) LO))ER 6009 39 T0409A RCLA HOT LEG TEMPERATURE 472.7 6009 DE6F 40 T0410A RCLB HOT LEG TEMPERATURE 471.8 GOOD DEGF 41 T0450 RCLA COLD LEG TE)(PERATIEE 469.6 6009 OE6F 42 T0451 RCLB COLD LEG TE)(PERATNE 469.4 6009 DEGF 43 TAVGAMID RCLA TAVG (THDT/TCOLD WIDE RNG) 471.2 GOOD DEGF 44 TAKBWID RCLB TAVG (T)OT/TCOLD WIDE RNG) 470.6 6009 DE6F 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.9 6009 X 46 TCCORE El. 1 INCORE TC AVERAGE TEMP 471.5 600~ DE6F 47 FAUXFMA S/G A:OTAL AUX FEEI'4(ATcD FLOW 0. 6009 PN 48 FAUXFMB S/6 B TOTAL AUX FEECSNW FLOW 196. 6009 GPM 49 BKR081 MTR AUXILIARY FEEINATER PUlP A OFF 6009 50 BKR082
'TR AUXILIARYFEEOMATER PUt(P B ON 6109 51 V3505<< AUX FM PUtt STEAtl SUPPLY VALVE A CLOSED GOOD V3504 AUX FM PU!F STEAN SUPPLY VALVE B CLOSED 6009
OCT 8> 1992 11: 15 R. E. GINA SINULATOR PA6E 2 TREND GROUP ASSIGNNENT RNMY GROUP: EVENT1 PRXEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY INJECTION:LOOP A AV6 FLON 0. GOOD GPt1 54 F GIB SAFETY INJECTION LOOP B AVG FLON 0. Goon GPtl 55 P2160 SERVICE NATER PUIIPS A h B HEADER 72. 600 D PSI6 56 P2161 SERVICE HATER PNPS C h D HEADER 80. Goon PSIG 57 BKR041 SERVICE NTER PUIIP A Goon 58 BKR042 SERVICE NATER PlIP B ON 600D 59 BKR043 SERVICE NTER PIIP C ON 600 D 60 BKR044 SERVICE HATER PUIIP D ON GOOD
ROGRAM NAME:LRGTSZ.E OCT 08,92 R.E.
~ ~ GIHNA NUCLEAR POWER PLANT 11:15:00 TREND GROUP ASSIGNHEHT
SUMMARY
GROUP NAME GROUP DESCRIPT ION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 F0619 COMPOHENT COOLING LOOP TOTAL FLW 1485. Gmm GPM 2 LRWST REFUELING WATER STORAGE TANK LVL 94.5 GOOD X 3 WS033 33 FOOT LEVEL WIND SPEED 5.6 GOOD KPH 4 WD033 33 FOOT LEVEL WIND DIRECTION 80. GOOD DEG. 5 WT033 33 FOOT LEVEL TEKPERATURE 62.5 GOOD DEGF 6 WT250 250 FOOT LEVEL TEMPERATURE 64.9 GOOD DEGF 7 WOT2 250 TO 33 FOOT LEVEL DELTA TEMP 2.4 GOOD DEGF 8 R01 AREA 1-COHTROL ROOK 9.02214-02 GOOD KR/H 9 R02 AREA 2-CONTAINMENT 7.35678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.3994& 00 GOOD MR/H 11 R09 AREA 9 LETDOWN LINE MONITOR 1.36701+02 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD KR/H 13 R35 AREA 35-PASS SAMPLE PAHEL 1.09283+00 GOOD MR/H 14 R10A CONTAINMENT IOOIHE MONITOR R10A 9.58719+01 GOOD CPH R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPK R12 COHTAINKEHT GAS MONITOR 7.38002+02 GOOD CPK R10B PLANT VENT IOOIHE MOHITOR R10B 4.30543t01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS KONITOR 4.22831+01 GOOD CPK 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658+03 GOOD CPK 21 R19 STEAM GENERATOR SLOWDOWN DRAIN 1.32174+04 HALM CPM 22 R29 AREA 29-CONTAINMEHT HIGH RANGE 5.05861.01 GOOD R/HR 23 R30 AREA 30-CONTAIHMEHT NIGH RANGE 5.09440-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPM 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990.02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOW RAHGE GAS 4.40312.07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RAHGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VEHT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15AS AIR EJECTOR CHAN 5 'OW RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RAHGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 2.50040+00 NALK KR/HR 36 R32 AREA 32 STEAM LINE 8 (SPING) 1. 01048-02 GOOD MR/HR 37 CVH CV HYDROGEN CONCEHTRATIOH .0 GOOD 38 TCV03 CV BASEMENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD 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:
~4 11'essage:
INNA 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 Reactor Shutdown ES NO Hi h Head S.I. Pum s N-31 N-32
~~CPS CPS FI-924 F1-925 O GPM
~GPM N-35 &I AMPS 1A. INSERV B OOS N-36 g l/ AMPS 1B. INSERV B OOS Avg. Nuclear Power 1C. INSERV OOS RCS Pressure PRZR Level
~b&7Z PSIG BAST Level = /O A RCP RUNNING TOPPE Low Head S.I. Pum s B RCP RUNNIN STOPPED FI-626 N G M 1A S/G Level .C a 1A. INSERV OOS RECIRC 1B S/G Level MV 1B. INSERV T OOS RECIRC 1A S/G Pressure oO PSIG RWST Level = S.
1B S/G Pressure 0 PSIG Turbine/Generator ONLINE FFLIN Containment S ra Pum s 4 KV Buses NERGZZ DEENERGIZED FI-931A & GPM 480V Buses ERGZZE DEENERGIZED FI-931B lD GP DC Batteries A~So VOLTS B/3OVOLTS 1A. INSERV OOS Cnmt Pressure PSIG 1B. INSERV T OOS Cnmt Sump A Level ~a<+FEET NaOH Tank Level = Cnmt Sump B Level INCHES A Loop Hot Leg S7 OF Containment Recirc Fans A Loop Cold Leg .0 OF 1A. NSERV STBY OOS B Loop Hot Leg Q~O OF 1B. SE STBY OOS B Loop Cold Leg %XKZ oF 1C. SER STBY OOS RVLIS 1D. NSER STBY OOS
- CET S/G A Total Aux FW Flow
~.b
~GPM OF Post Acc dent Dampers PE CLOSED S/G B Total Aux FW Flow Z.o2 GPM Service Water-Pum s 1A. INSERV STBY 0 DIESEL GENERATORS 1B. NSE STBY OOS 1C. NSE STBY OOS A. RUNNING UNLOADED TB OOS 1D. NSER STBY OOS B. RUNNING UNLOADED STBY OOS TSC RUNNING UNLOADED OOS A&B Header Pressure ~PSZG Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s ENGINEERED SAFEGUARDS 1A. I ERV STBY 1B. NSER STBY OOS Surge Tan vel Aux. Feedwate m s 1A. INSERV B OOS Standb Aux. Feedwater Pum s 1B. NSER STBY OOS 1C. INSERV TB OOS Turb. Driven INSERV TB OOS 1D. INSERV STB OOS CST Level FEET
- CET = Average of Selected Core Exit Thermocouples
8i 1992 11:30 R. E. 6INA SINLATOR PA6E 1 TREND GROUP ASSIGN)(ENT SUt(t(ARY 6ROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE E. U. 1 ATI6 ANTICIPATED TRAt(6IENT W/0 SCRAt( ATMS ALRt( 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRt( 3 N31 SSSCE RANGE DETECTOR N-31 8. 75988+01 6(mD CPS 4 N32 SONCE RANGE DETECTOR N-32 7.92501+01 GOOD CPS 5 N35 INTERt(EDIATE RANGE DETECTOR N-35 1.01391-11 GOOD At(P b N3b INTERt(EDIATE RANGE DETECTOR N-3b 1.01391-11 GOOD At(P 7 i"(P AVERAGE NUCLEAR POWER .00 GOOD y. 8 PRCS REKTOR COOLANT SYSTEtl AVG PRESS 1002. GOOD PSIG 9 LPIR PRESSURIlER AVERAGE LEVEL 41.7 GOOD 10 FRCLA REACTOR CCEA(T LOOP A AVG FLOW 12.8 INHB / 11 FRCLB REACTOR COOLANT LOOP B AVG FLOW 110.8 GOOD / 12 RXT1b RCPA BREAKER CAUSE RX TRIP TRIPPED ALRt( 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP GOOD 14 TSUBTC INCORE TC SUP3NLED t(ARGIN 90.1 600~ DEGF 15 LSGA STN GEN A NARROW RANGE AVG LEVEL 48.b 600D / ib LS6B STN GEN B t(ARROW RAKE AVG LEVEL 34.9 GOOD 7. 17 PSGA STt( GEtt A AVERAGE PRESSURE 1000. GOOD PSIG 18 PSGB STN GEN B AVERAGE PRESRJRE 401. LALN PSIG 19 GENBKR1 GENERATOR ON LINE %FAKER 161372 TRIPPED ALRt( 20 GENBKR2 GENERATOR ON LINE BREAKER 9X1372 TRIPPED ALRt( 21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRtl 22 BUS118 BUS liB SUPPLY BREAKER TRIPPED ALRt( 23 BUS12A t(QT TERNlhATED OM PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERtlit(ATED OM PPCS (7/19/91) NOT TRIP DEL 25 Bi IA12A BUS 11A TO 12A TIE BREAKER NOT TRIP ALRt( 2b B11B12B BUS iiB TO 12B TIE BREAKER NOT TRIP ALR)( 27 PCV COl(TAINl"iENT AVERAGE PRESSURE -.24 GOOD PS16
')8 LSNPA CQNTAItit(Et(T SUMP A AVERAGE LEVEL SlRt( FM 29 L0942E SM' LEVEL 8 INCHES (TRAIN A) LONER GOOD 30 L0943E SM B LEVEL 8 INCHES (TRAIN B) LOMER 600D 31 L0942D SUt(P B LEVEL 78 INCHES (TRAIN A) LOWER GQOD 32 L0943D SU@' LEVEL 78 INCHES (TRAIN B) LONER GOOD 33 L0942C SUN' LEVEL 113 INCHES(TRAIN A) lONER 6009 34 L0943C SM~ B LEVEL 113 INCH.=S(TRAIN B) ,LONER GOOD 35 L0942B SU% B LEVEL 180 INCHES(TRAIN A) LOWER GOOD 3b L0943B SUtP B LEVEL 180 INCHES(TRAIN B) LOWER 600D 37 L0942A SU%' LEVEL 214 INCHES(TRAIN A) LONER 600D 38 L0943A S"tP B LEVEL 214 It/CHES(TRAIN B) LONER 600D 39 T0409A RCLA HOT LEG TEt(PERATUP= 457.8 GOOD DEGF 40 T0410A RCLB HOT LEG TEt(PERATUK 457.0 GOOD DEGF 41 T0450 RCLA CP D LEG TE)PERATURE 455i0 GOOD DE6F 42 T0451 RCLB COLD LEG TEt(PERATNE 454.8 GOOD DE6F 43 TAVGAMID RCLA TAVG (THQT/TCOLD WIDE RNG) 45b.4 GOOD DEGF TAVGBMID RCLB TAVG (TNT/TCOLD WIDE RNG) 455.9 GOOD DEGF 45 LRV REACTOR VESSEL A'FRAGE LEVEL 99.9 GOOD 7.
4b TCCORE E1.1 INCOFE TC AVERAGE TEt(P 45b.b 600~ D-"GF 47 FAUXFMA S/G A TOTAL AUX FEEDWATER FLO(( 0. GOOD 6PN 48 FAUXFWB S/G B TOTAL AUX FEEDMATER FLOW 202. GOOD GPt( 49 BKR081 t(TR AUXILIARYFEEDMATER PUt(P A OFF 600D 50 BKR082 MTR AUXILIARY FEEDMATER PUt(P B ON GOOD 51 V3505 AUX FM PUP STEAN SUPPLY VALVE A CLOSED GOOD 52 V3504 AUX FM PU5'TEAN SUPPLY VALVE B CLOSED GOOD
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 SAFETY INJECTION LOOP A AV6 FLOW 0. Gxa m 54 FSIB SAFETY INJECTION LOOP B AV6 FLOM 0. GOOD GPN 55 P2160 SERVICE MATER PlmPS A h B HEADER 72. GOOD PSIG 56 P2161 SERVICE WATER PNPS C 5 9 HEADER 80. 600D PSIG 57 BKR041 SERVICE MATER PINP A GOOD 58 BKR042 SERVICE MATER PUNP B GOOD 59 BKR043 SERVICE WATER PUNP C 6OOD 60 NR044 SERVICE WATER PUe D GOOD
ROGRAH KAME:LRGTSZ.E~ OCT 08,92 R.E.
~ ~ GIKHA NUCLEAR POWER PLANT 11:31:00 TREND GROUP ASSIGNMENT
SUMMARY
GROUP NAME GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS
- l. F0619 COMPOHENT COOLING LOOP TOTAL FLW 1485. GOOD GPH 2 LRWST REFUELING WATER STORAGE TANK LVL 94.5 GOOD X 3 WS033 33 FOOT LEVEL WIND SPEED 5.6 GOOD MPH 4 WD033 33 FOOT LEVEL WIHD DIRECTION 79. GOOD DEG.
5 WT033 33 FOOT LEVEL TEHPERATURE 62.7 GOOD DEGF 6 WT250 250 FOOT LEVEL TEHPERATURE 64.8 GOGO DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEHP 2.1 QXX) DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-COHTAINHEHT 7.35678+00 0000 MR/H 10 RDS AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDOWN LIHE MOHITOR 1.34701+02 GOOD MR/H 12 R34 AREA 34 AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAHPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINMENT IODINE MONITOR R10A 9.58719+01 GOOD CPH R11 CONTAINHEHT AIR PARTICULATE 5.18901+02 GOOD CPH R12 CONTAINMEHT GAS MONITOR 7.38002+02 GOOD CPH R108 PLANT VENT IODINE MONITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPH R14 ~ AUX BLDG EXHAUST GAS MOHITOR 4.22831+01 GOOD CPM 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658+03 GOOD CPM 21 R19 STEAM GEKERATOR BLOWDOWN DRAIN 1.28174+04 HALM CPM 22 R29 AREA 29-CONTAINMENT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30.CONTAINMEHT HIGH RANGE 5.09440-01 GOOD R/HR 24 R15 COKDEHSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPH 25 R12AS CV VENT CHAN 5-LOW RANGE GAS 1.89699.07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VEN'I CHAN 7-MID RAHGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOW RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLAHT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CKAN 9-HIGH RAHGE GAS 3.72621-03 GOOD UCI/CC 32 R15AS AIR EJECTOR CHAN 5-LOW RANGE GAS 2 '9411-07 UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9 Hl RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 2.50040+00 BALM MR/NR 36 R32 AREA 32 STEAM LINE 8 (SPING) 1.01048.02 GOOD MR/HR 37 CVH CV HYDROGEN CONCEHTRATIOH .0 GOOD X 38 TCV03 CV BASEHENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 Tcvoe CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATIKG LVL 6 FT TEMP ¹17 117.5 GOOD 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"""
"B" S/G ARV steam leak is repaired and ready for return to service.
'he 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 INNA 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 Reactor Shutdown YES NO Hi h Head S.Z. Pum s N-31 ~~CPS FI-924 C7 GPM N-32 CPS FI-925 & GPM N-35 ~0-II AHPS INSERV TB OOS N-36 Avg. Nuclear Power
~-I/ AMPS 1B.
1C ~ ZNSERV INSERV TB B OOS OOS RCS Pressure 'f7 PSIG BAST Level = /O PRZR Level ~&.3 A RCP RUNNING OPP Low Head S.I. Pum s B RCP RUNNIN STOPPED FZ-626 O GPM 1A S/G Level ~sd & 1A INSERV TB OOS RECIRC 1B S/G Level ~)a7 1B. INSERV TB OOS RECIRC 1A S/G Pressure Pressure
~~PSIG RWST Level =
1B S/G PSIG Turbine/Generator ONLINE FF I Containment S ra Pum s 4 KV Buses NERGIZE DEENERGIZED FZ-931A & GPM 480V Buses NERGIZE DEENERGIZED FI-931B & GPM DC Batteries A~VOLTS B/30VOLTS 1A. INSERV T OOS Cnmt Pressure ~ ZCa PSZG 1B. INSERV TB OOS Cnmt Sump A Level FEET NaOH Tank Level = Cnmt Sump B Level INCHES A Loop Hot Leg ~3.Z. OF Containment ecirc Fans A Loop Cold Leg Wla 7 OF lA. S STBY OOS B Loop Hot Leg ~~3. OF 1B. NS STBY OOS B Loop Cold Leg '~l.h OF 1C. SE STBY OOS RVLIS 1D. NSE STBY OOS
- CET .3 OF. Post Accident Dampers OPE CLOSED S/G A Total Aux FW Flow O GPM S/G B Total Aux FW Flow O GPM Service Water Pum s 1A. INSE STBY OOS DIESEL GENERATORS 1B. NSERV STBY OOS 1C. SER STBY OOS A. RUNNING UNLOADED TB OOS 1D. NSER STBY OOS B. RUNNING UNLOADED TB OOS A&B Header Pressure 7&&70 PSZG TSC RUNNING UNLOADED TBY OOS Security RUNNING UNLOADED B OOS Com onent Coolin Water Pum s 1A. I V STBY ENGINEERED SAFEGUARDS Aux. Feedwater Pum s 1B. NSE V STBY OOS Surge Tank Level = ~/
1A. INSERV OOS Standb Aux. Fe water Pum s 1B. INSERV TB OOS 1C. INSERV T OOS Turb. Driven INSERV B OOS 1D. INSERV TB OOS CST Level ~g FEET
- CET = Average of Selected Core Exit Thermocouples
Gi 1992 11:45 R. E. GINA Slt(ULATOR PAGE 1 TREND 6ROUP ASSIG)NENT SUt)t(ARY 6ROUP: EVENTl PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U. 1 ATMS ANTICIPATED TRANSIENT W/0 SCRAtt ATMS ALII 2 RXT REACTOR TRIP BRENER STATUS RX TRIPPED ALR)( 3 N31 SISCE RANGE DETECTOR N-31 7.87043+01 6009 CPS 4 N32 SISCE RANGE DETECTOR N-32 8.34639%1 6009 CPS 5 N35 INTEI(t(EDIATE RANBE DETECTOR N-35 1.01391-11 6009 At(P 6 N36 INTER)(EDIATE RANBE DETECTOR N-36 1.01391-11 6009 7 HP AVERAGE NUCLEAR POWER .00 6009 y. 8 PRCS REACTOR COOLANT SYSTEtt AVG PRESS 976. 6009 PSIG 9 LPLR PRESSURI IER AVERA6E LEVEL 46.3 6009 X 10 FRCLA REKTOR CQOUNf LOOP A AVB FLOW 12.9 INHB 7. 11 FRCLB REACTOR COOLAt(T LOOP 8 AVB FLOW 111.9 6009 z 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRtt 13 R)(T17 RCPB BREAKER CAUSE RX TRIP NQT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED MARIN 100.1 600e DEGF 15 LSGA STtt GEH A HARROM RANGE AVG LEVEL 42.5 6009 X 16 LSBB STM GEN B t(ARROW RA%E AVG LEVEL 40.7 6009 X 17 PSBA STM GEN A AVERAGE PRESSURE 973. 6009 PSIG 18 PSBB STt( GEN B AVERAGE PRESSURE 350. LALN PSIG 19 GENBKRl CBERATOR ON LINE BRENER 161372 TRIPPED ALQf 20 GENBKR2 GENERATOR ON LINE BREAKER 9X1372 TRIPPED ALR)( 21 BUS11A BUS 11A SUPPLY BRENER TRIPPED ALRN 22 BUS11B BUS 118 SUPPLY BRENER TRIPPED AUI 23 BUS12A NOT TERNINATED ON PPCS (7/19/91) NQT TRIP DEL 24 BUS12B NOT TERHINATED Qt( PPCS (7/19/91) NOT TRIP DEL 25 Bl lA12A BUS llA TO 12A TIE BREAKER NOT TRIP ALRt( 26 811B12B BUS 119 TO 12B TIE BREAKER NOT TRIP ALRtf 27 PCV CQNTAINtiENT AVERAGE PRESSURE -.26 6009 PSIG 28 LSI(PA CONTAltitlEhT S)iP A AVERAGE LEVEL 2.4 tIRt( FcCT 29 L0942E SUtP B LEVEL 8 INCHES (TRAIt( A) LONER G009 30 L0943E SUtP B LEVEL 8 INCHES (TRAIN 9) LOMER GOOD 31 L0942D SUtP 8 LE4S. 78 INCHES (TRAIN A) LOMER GOOD 32 L0943D SU)P B LEVEL 78 INCHES (TRAIN B) LOMER GOOD 33 L0942C SUtP B LEVEL 113 It(CHES(TRAIN A) LOMER GOOD 34 L0943C SUtP B LDH, 113 It(CHES(TRAIN B) LOMcR GOOD 35 L0942B SUtP B LEVEL 180 INCHES(TRAIN A) LOMER 6009 36 L0943B SUtP B LE4S. 180 INCHES(TRAIN B) LOMER GOOD 37 L0942A SUtP B LEVEL 214 INCHES(TRAIN A) LOMER 6009 38 L0943A SUtP B LEVEL 214 INCHES(TRAIN B) LOMER 6009 39 T0409A RCLA HOT LEG TFt1PER4T()K 443.2 6009 DEBF 40 T0410A RCEB HOT LEG TE5'ERATURE 443.4 6009 I)EGF 41 T0450 RCLA COLD LEG TEt(PERAT(SE 441.7 6009 t)EGF 42 T0451 RCLB COLD LEG TEt)PERATURE 441.5 6009 DEGF 43 TAVBAMID RCLA TAVB (THOT/TCQLD WIDE RNB) 442.4 GOOD KGF 44 TAVBBMID RCLB TAVG (THAT/TCOLD WIDE RNB) 44 '.5 GOOD 066F 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.8 6009 y. 46 TCCQRE El.l IHCORE TC AVERAGE TEt(P 443.3 600e DEGF 47 FAUXFMA S/G A TOTAL AiJX FEEDMATER FLOW 0. 6009 GP)( 48 FAUXFMB S/6 B TOTAL AUX FEEDMATER FLS( 1. 6009 GPt( 49 BKR081 t(TR AUXILIARYFEEDMAmi . Put(P 4 OFF GOOD 50 BKR082 t)TR AUXILIARY FEEDMATER PUt)P 9 OFF 6909 51 V3505 AUX FW PU)(P STEA)t SL4'PLY VALVE A CLOSED 6009 52 V3504 AUX FW PU5'TEAt) SL'PPLY VALVE B CLOSED GOOD
OCT Bi 1992 il:45 R. E. GINA SINLATOR PAGE 2 . TREND GSP AKIGNENT RNNRY 6ROUP: EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION QUAL E. U. 53 FSIA SAFETY INACTION'LOCH A AVG FLOW 0. 6009 GPN 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. 600 D GPN 55 P21b0 SERVICE WATER PtNPS A h B HEADER 72. GOOD PSI6 56 P2161 SERVICE WATER PNPS C h D HEADER 80. 600D PSIG 57 BKR041 SERVICE WATER PUNP A OFF GOOD 58 BKR042 SERVICE WATER PUNP B ON GOOD 59 BKR043 SERVICE WATER PUNP C ON GOOD h0 BKR044 SERVICE WATER PUNP D ON GOOD E+3
ROGRAM HAME:LRGTSZ.E OCT 08,92 R.E. GINHA NUCLEAR PSIER PLANT 11 47 00 TREND CROUP ASSIGNMENT
SUMMARY
GROUP NAME GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY GX)E ENGR UNITS 1 F0619 C(NPONEHT COOLING LOOP TOTAL FLII 1485. GOOD GPM 2 LRMST REFUELIMG lIATER STORAGE TANK LVL 94.5 GOOD X 3 US033 33 FOOT LEVEL lIIHD SPEED 6.2 60(O MPM 4 40033 33 FOOT LEVEL IIIHD DIRECTION 76. GOOD DEG. 5 l6033 33 FOOT LEVEL TEMPERATURE 65.0 GOOD DEGF 6 lIT250 250 FOOT LEVEL TEMPERATURE 66.8 GOOD DEGF 7 lOT2 250 TO 33 FOOT LEVEL DELTA TEMP 1.8 GOOD DEGF 8 R01 AREA 1-CONTROL ROOH 9.02214.02 GOOD MR/N 9 R02 AREA 2-CONTAINHENT 7.35678+00 GOOD HR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDSIN LINE MONITOR 1.32701+02 GOOD HR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUHP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAHPLE PANEL 1.09283+00 GOOD MR/M 14 R10A CONTAINMEHT IODINE HOHITOR R10A 9.58719+01 GOOD CPM R11 CONTAINMENT AIR PARTICULATE 5.18901+02 GOOD CPM R12 CONTAINHENT GAS MONITOR 7.38002+02 GOOD CPH R10B PLANT VENT IODINE MONITOR R10B 4.30543+01 QXO CPH R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID IIASTE DISPOSAL MONITOR 2.78658+03 6000 CPM 21 R'19 STEAH GENERATOR BLSNSIM DRAIN 1.28174+04 BALM CPM 22 R29 AREA 29-CONTAIMHENT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINMEHT HIGH RANGE 5.09440.01 GOCD R/MR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPH 25 R12A5 CV VENT CHAN 5-LSI RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6 AREA GAHMA 2.53990-02 MR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435-05 UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOlI RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RANGE GAS 6.86543-05 6000 UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RAMGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LSI RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-HID RANCE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-MI RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 2.42040100 MALH HR/MR 36 R32 AREA 32 STEAM LINE 8 (SPING) 1.01048-02 6000 MR/HR 37 CVH CV NYDROGEN CONCENTRATION .0 6000 X 38 TCV03 CV BASEMENT LVL 6 FT TEHP ¹3 95.1 CODD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 CODD DEGF 40 TCVOB CV INTERMEDIATE LVL.6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEHP ¹10 106.2 COOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 COCO DEGF 0-J
Time: ~114 Message: ~4l~ INNA 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 INITIALCONDITIONS: 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: Voice communications staff to initiate investigation on cause of telephone system malfunction. 1
- 2. 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 ~C' 'N
- 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: HP technician responds and conducts monitoring of contaminated individual.
- 2. HP/Chemistry Manager is informed.
- 3. TSC entrance secured to prevent further spread of contamination.
- 4. Follow-up actions required by HP-6,3 are initiated for documentation and decontamination.
- 5. 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 MAZOR PAE&METERS ENGINEERED SAFEGUARDS Reactor Shutdown ES NO Hi h Head S.Z. Pum s N-31 CPS FI-924 O GPM N-32 N-35
~CPS
~O~AAMPS FI-925 1A 0 GP INSERV TB OOS N-36 =Wf AMPS 1B. INSERV TBY OOS Avg. Nuclear Power 0 1C INSERV OOS RCS Pressure +@LPSZG BAST Level =
PRZR Level A RCP R NG
/ TOPP Low Head S.I. Pum s B RCP UNNIN STOPPED FZ-626 O G M 1A S/G Level ga2 1A. INSERV B OOS RECIRC 1B S/G Level e. 1B. INSERV OOS RECIRC 1A S/G Pressure PSIG RWST Level = 3.
1B S/G Pressure 2 4 PSZG Turbine/Generator ONLIN FFLIN Containment S ra Pum s 4 KV Buses ERGIZE DEENERGZZED FI-931A D GPM 480V Buses NERGZZE DEENERGZZED Fl-93 1B C7 GP DC Batteries Ange VO B/BOVOLTS 1A. INSERV B OOS Cnmt Pressure ~2. PSIG 1B. INSERV B OOS Cnmt Sump A Level ~i,~FEET NaOH Tank Level = Cnmt Sump B Level @~i INCHES A Loop Hot Leg ~>~70 F Recirc Fans 9'ontainment A Loop Cold Leg OF 1A. NS STBY OOS B Loop Hot Leg ~BA.Q OF 1B. SER STBY OOS B Loop Cold Leg OF 1C. SE STBY OOS RVLIS ~g 1D. NSE STBY OOS
*CET OF Post Accident Dampers OPEN CLOSED S/G A Total Aux FW Flow 0 GPM
~a.
S/G B Total Aux FN Flow GPM Service Water Pum s DIESEL GENERATORS 1A. I STBY OO 1B. SER STBY OOS 1C. STBY OOS A. RUNNING UNLOADED TB OOS 1D. NSER STBY OOS B. RUNNING UNLOADED TSC RUNNING UNIADADED TB OOS OOS A&B Header Pressure v~f'0 PSIG Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. ZNSE V STBY OOS ENGINEERED SAFEGUARDS 1B. Aux. Feedwater Pum s NSERV STBY OOS Surge Tank Level = ~/ 1A. INSE V TB OOS Standb Aux. Feedwater Pum s 1B. NS R STBY OOS 1C. INSERV TB OOS Turb. Driven INSERV TB OOS 1D. ZNSERV TB OOS CST Level F
- CET = Average of Selected Core Exit Thermocouples
Gi 1992 12'00 R. E. GINA Sit((LATOR PAGE 1 TREND GROUP ASSIBNt(Et(T SUtft(ARY GROUP: EVENTI PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION E. U. ATI6 ANTICIPATED TRANSIENT M/0 SCRuf ATNS ALII 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALfm 3 N31 SONCE RANGE DETECTOR N-31 8.11894%1 6009 CPS N32 SOlRCE RAhGE DETECTOR N-32 8.09093%1 600D CPS 5 N35 It(TERt(EDIATE RANGE DETECTOR N-35 1.01391-11 6009 At(P 6 N36 INTEfNEDIATE RANGE KTECTOR N-36 1.01391-11 GXD At(P 7 NP AVERAGE N(GER POWER .00 6009 X 8 PRCS REACTOR COOLufT SYSTEtf AVG PRESS 958. 6009 PSIG LPLR PRESSURIIER AVERAGE LEVEL 51.8 6009 X 10 FRCLA REKTOR COOLANT(T LOOP A AVG FLOW 12.9 INHB X
'X 11 FRCLB REACTOR COOLANT LOOP 8 AVG FLOW 112.5 600D 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRtf 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED t(ARGIN 105.4 600~ K6F 15 LSBA STff GEtf A NARROW RANGE AVG LEVEL 38.2 600D X 16 LSGB STtf GEN 8 t(ARROW RANGE AVG LEVEL 40.8 6009 X 17 PS6A STt( GEtf A AVERAGE PRESSURE 953. 6009 PSI6 18 PSGB STt( GEN 8 AVERAGE PRESSURE 326, LALN PSIG 19 GENBKRI GENERATOR ON LINE BREAKER 1G1372 TRIPPED ALRtj 20 GB(BKR2 GEhERATOR ON LINE BREAKER '9X1372 TRIPPED ALRtf 21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRt(
22 BUS 118 BUS 118 SlFPLY BREAKER TRIPPED ALRtf 23 BUS12A NOT TERMINATED Off PPCS (7/19/91) NOT TRIP DEL 24 BUS128 NOT TERt(INATED ON PPCS (7/19/91) NOT TRIP DEL 25 811A12A BUS 11A TO 12A TIE BRENER NOT TRIP ALRtf 26 8118128 BUS 118 TO 128 TIE BRE(CER NOT TRIP ALRff 27 PCV CONTAItft(ENT AVERAGE PRESSURE ~ 28 6009 PSI6 28 LBNPA C0%'Aiht(ENT PJt(P A AVEfmGE LEVEL 2.5 HWRtf FEET 29 L0942E SUtf' LEVS. 8 It(CHES (TRAIN A) LONER 6009 30 L0943E SUtP 8 LEVEL 8 INCHES (TRAIN 8) LONER GOOD 31 L09429 SUtf' LEVEL 78 JNCHES (TRAIN A) LONER 6009 32 L0943D SU%' LESS 78 INCI:ES (TRAIN 8) LONER 600D 33 L0942C SU@ 8 LEVEL 113 INCHES(TRAIN A) LONER 6009 34 L0943C SUtP 8 LESS. 113 INCHES(TRAIN 8) LONER 6009 35 L09428 SUtf' LEVEL 180 INCHES(TRAIN A) LONER GOOD 36 L09438 SUtP 8 LEVEL 180 INCHES(TRAIN 8) LONER 6009 37 L09a2A PJtf' LEVS. 214 IhGfES(TRAIN A) LONER 6009 38 L0943A SLtiP 8 LEVEL 214 INCHES(TRAIN 8) LONER 6009 39 T0409A RCuf HOT LEG TEf(PERATUR= 434.7 6009 DEGF 40 T0410A RCLB HOT LEG TEt(PERATUK 436.0 6009 DEGF 41 T0450 RCLA COLD LEG TEtfPERATNE 434.6 6009 DEBF 42 T0451 PCLB CO' LEG TEtiPERATURE 434.6 GOOD KGF 43 TAVGAW!9 PCLA TAVG (Tf(OT/TCOLD WIDE RNG) 434.6 6009 DE6F 44 TAVGBMID R".U3 TAVG (THDT/TCOLD WIDE RNG) 435.3 6009 K6F LRV PEACTOR VESS<< AVERAGE LEVEL 99.7 GOOD X 46 TCCORE Ei.'t'COPE TC AVcBAGE TEt'i~ 435.9 600~ KBF a7 FAUXFWA S!C A TOTAL AUX FEEDMAlS( FLOW 0. 6009 GPtf 48 FAUXFWB S/G 8 TOTAL AJX FEEDMATER FLOW 42, 600D 49 BKR081 t(TR AUXILIARYFEEBLER PUt(P A OFF 600D 50 BKR082 tfTR AUXILIARYFEEDMATER PU)fP 8 ON 6()09 51 V3505 AUX FM PUt(P STEAtf SUPPLY VALVE A CLOSED GOOD 52 V3504 AUX FM PUN'TEA)f SUPPLY VALVE 8 CLOSED 6009
XT Gs 1992 12'00 R. E. GINA SINULATOR PAGE 2 TREND GROUP ASSIGNENT SUNQRY GROUPS EVENTi PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY INJECTION.'LOOP A AVG FLOW 0. 600 D GPtf 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. GOOD GPN 55 P2160 SERVICE WATER PNPS A 5 B HEADER 72. 6XD PSI6 5b P2161 SERVICE WATER PmfPS C h D HEADER 80. GOOD PSIG 57 BKR041 SERVICE WATER PtNP A OFF GOOD 58 BKR042 SERVICE HATER PUffP B ON GOOD 59 BKR043 SERVICE WATER PlNP C ON 600D 60 BKR044 SERVICE WATER PUtfP D ON 600D
ROGRAM NAME:LRGTSZ.E OCT 08,92 R.E.
~ ~ GINNA KUCLEAR POWER PLANT 12:01:00 TREND GROUP ASSIGNMEHT
SUMMARY
GROUP HAHE GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLW 1485. GOOD GPM 2 LRWST REFUELING WATER STORAGE lANK LVL 94.5 G(XS X 3 WS033 33 FOOT LEVEL WIKD SPEED 6.1 GOOD MPH 4 WD033 33 FOOT LEVEL WIKD DIRECTION 77. GOOD DEG. 5 WT033 33 FOOT LEVEL TEMPERATURE 65.1 GOtX) DEGF 6 WT250 250 FOOT LEVEL TEMPERATURE 66.8 G(XX) DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEHP 1.7 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAIHHEHT 7.35678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.3994& 00 GOOD MR/M 11 R09 AREA 9.LETDOWN LINE MONITOR 1.29701+02 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283i00 GOOD MR/H 14 R10A CONTAINHEHT IODINE MONITOR R10A 9.58719+01 GOOD CPM R11 CONTAINMEHT AIR PARTICULATE 5.18901+02 GOOD CPH R12 CONTAINMEHT GAS MOHITOR 7.38002+02 GOOD CPM R108 PLANT VENT 1OOIHE MONITOR R108 4.30543t01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPH 20 R18 LIQUID WASTE DISPOSAL MOHITOR 2.78658+03 GOOD CPH 21 R19 STEAM GENERATOR SLOWDOWN DRAIN 1.19174+04 HALM CPH 22 R29 AREA 29-CONTAINMENT HIGH RANGE 5.05861-01 GOOD R/HR R30 AREA 30-CONTAINMENT HIGH RANGE 5 '9440.01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPM 25 R12AS CV VENT CHAN 5-LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7 MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CNAH 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14AS PLAHT VENT CHAN 5-LOW RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLAHT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RAKGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOW RAHGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7 HID RAKGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-Hl RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 2.33040+00 HALM MR/HR 36 R32 AREA 32 STEAM LINE B (SPIHG) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD X 38 TCV03 CV BASEHEHT LVL 6 FT TENP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCV08 CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERHEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD DEGF 0 J
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 Reactor Shutdown ES NO Hi h Head S.Z. Pum s N-31 CPS FI-924 C) GPM N-32 ~OCPS FZ-925 N GPM N-35 NH/ AMPS 1A INSERV TB OOS N-36 AMPS 1B. INSERV TB OOS Avg. Nuclear Power 0 1C INSERV TB OOS RCS Pressure PSIG BAST Level = /C7 PRZR Level A RCP R G OP PE Low Head S.Z. Pum s B RCP UNNIN STOPPED FI-626 O GPM 1A S/G Level 1A. INSERV OOS RECIRC 1B S/G Level ~E ~to 1'NSERV OOS RECIRC 1A S/G Pressure PSIG RWST Level = VS-1B S/G Pressure PSIG Turbine/Generator ONLINE FL Containment S ra Pum s 4 KV Buses ERGIZE DEENERGIZED FZ-931A GPM 480V Buses NERGIZED DEENERGIZED FI-931B C) GP DC Batteries A~SOVOLTS B~VOLTS 1A. INSERV T OOS Cnmt Pressure ~ R. PSZG 1B. INSERV OOS Cnmt Sump A Level ?. FEET NaOH Tank Level = Cnmt Sump B Level INCHES A Loop Hot Leg ~Qg.dLOF Containment ecirc Fans A Loop Cold Leg OF 1A. E STBY OOS B Loop Hot Leg I . OF 1B. SE STBY OOS B Loop Cold Leg ~i.O OF 1C. SE STBY OOS RVLIS
- CET
~K> ~ 1D. STBY OOS Post Accident Dampers EN CLOSED S/G B A Total Aux FW Flow Total Aux Flow
~GPM
~fGPM oF'/G Service Water FW Pum s 1A. INSE V STBY OS DIESEL GENERATORS 1B. SE STBY OOS 1C ~ SER STBY OOS A. RUNNING UNLOADED T OOS 1D. N R STBY OOS B. RUNNING UNLOADED STB OOS TSC RUNNING UNLOADED TB OOS A&B Header ressure ~PSIG Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s ENGINEERED SAFEGUARDS 1A. I ERV STBY OOS 1B. INSERV STBY OOS Surge Tan vel =
Aux. Feedwater Pum s 1A. INSERV TB OOS Standb Aux. Feedwater Pum s 1B. S R STBY OOS 1C. INSERV T OOS Turb. riven INSERV B OOS 1D. INSERV TB OOS CST Level /2 F
- CET = Average of Selected Core Exit Thermocouples
Gr 1992 12:15 R. E. GINA Sft(ULATOR PA6E 1 TREND GROUP ASSIG)ST SUM)IRY GROUP: EVENTi PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QUAL E. U. 1 ATMS ANTICIPATED TRANSIENT M/0 SCRAM ATMS RLRt( 2 R)(T REACTOR TRIP BREAKER STATUS RX TRIPPED ALII 3 N31 SMKE RANGE DETECTOR N-31 8.55064+01 GOOD CPS N32 SISCE RRt(GE DETECTOR N-32 7.95241+01 6000 CPS 5 N35 INTERMEDIATE RAN6E DETECTOR N-35 1.01391"11 GOOD AMP 6 N36 INTERMEDIATE RANGE DETECTOR N-36 1 ~ 01391-11 600D AMP 7 NP AVERA6E NUCLEAR POWER .00 GOOD X 8 PRCS RECTOR COOLANT SYSTEM AVG PRESS 899. GOOD PSIG ~ 9 LPLR PRESSURIZER AVERAGE LEVEL 58.9 GOOD X 10 FRCLA REACTOR COOLW(T LOOP A AVG FLOW 13.0 INHB X 11 FRCLB REACTOR COOLANT LOOP B AVG FLOW 114.0 GOOD X 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRt( 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 600D 14 TSUBTC INCORE TC SUBCOOLED MARGIN 115.7 600~ DEGF 15 LSGR STM GEN A NARROM RANGE AVG LEVEL 29.4 LMRN 16 LS6B STM GEN B NARROW RAKE AVG LEVEL 36.0 GOOD 17 PSGA STM GEN A AVERAGE PRESSURE 919. GOOD PSI6 18 PSGB STM GEN B AVERAGE PRESSURE 268. LALt( PSIG f9 GEtlBKRl GENERATOR ON LINE BREAKER 161372 TRfPPED RUI 20 GENBKR2 GYRATOR ON LINE BREAKER 9X1372 TRIPPED ALR)( 21 BUS11R BUS 11A SUPPLY BREAKER TRIPPED ALRtf 22 BUS11B BUS 11B SUPPLY BREAKER TRIPPED AUI 23 BUS12A NOT TERMIt(ATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERMINATED ON PPCS (7/19/91) NOT TRIP DEL 25 B11A12R BUS 11A TO 12A TIE BREAKER NOT TRIP RLRt( 26 B11812B BUS 11B TO 128 TfE BREAKER NOT TRIP AUI 27 PCV CONTAINMENT AVERAGE PRESSURE - 28 600D PSIG 28 LSlNPA CO)1TAIt(MENT SUMP A AVERAGE LEVEL 2.5 HMRN FKT 29 L0942E SU)A' LEVEL 6 INCHES (TRAIN A) LONER GOOD 30 L0943E SUB' LEVEL 8 INCHES (TRAIN B) l.ONER GOOD 31 L0942D SUtf' LEVEL 78 INOKS (TRAIN A) LONER GOOD 32 L0943D SUtf' LEVEL 78 fNCHES (TRAIN B) LONER GOOD 33 L0942C SUMP B LEVEL 113 INCHES(TRAIN A) LONER 600D 34 L0943C SrJYP 8 LEVEL 113 INCHES(TRAIN B) LONER 6000 35 L0942B SUMP B LEVEL 180 It(CHES(TRAIN A) LONER 6009 36 L0943B SUtf' LEVEL 180 INCHES(TRRIN B) LONER 600D 37 L0942A SUtf B LEVEL 214 INCHES(TRAIN A) LONER 6000 38 L0943A SUtP B LEVEL 214 INCHES(TRAIN B) LONER 600D 39 T0409R RCLR HOT LEG TEMPERATURE 418.9 GOOD DEGF 40 T0410R RCLB HOT LEG TEMPERATURE 418.0 GOOD KGF 41 T0450 RCLR COLD LEG TEMPERAT(RE 416.2 GOOD KGF 42 T0451 RCLB COLD LEG TEMPERRTNE 416.0 GOOD KGF 43 TAVGAMID RCLR TAVG (THOT!TCOLD WIDE RNG) 417.5 GOOD KGF 44 TR'LGBMID RCLB TAVG (T)GT/TCOLD WIDE RNG) 417.0 6000 K6F 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.6 GOOD X 46 TCCORE El.l ft, ORE TC AVERAGE TEMP 417.7 600> KGF 47 FAUXFMR S/G R TOT&'UX FEEBtA7rZ FLOW 0. GOOD GPtf 48 FRUXFMB S/G B TOTAL AUX FEENATER FLOW 189. 600D PM 49 BKR081 MTR AUXILIARYFEEDMATER PUMP A OFF 600D 50 BKR082 MTR AUXILIARY FEEDMRTER PUMP B ON 680D 51 V3505 AUX FM PUt(P STER)( SUPPLY VALVE A CLOSED GOOD 52 V3504 RUX FM PUN'TEAN SUPPLY VALVE B CLOSED GOOD 8'76
OCT 8~ 1992 12:15 R. E. GIWA SINULATOR PAGE 2 TREND GROUP ASSIGNNENT SUNNARY 6ROUP: EVENT1 PROCEDURES EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE QlAL E. U. 53 FSIA SAFETY INJECTION:LOOP A AVG FLOW 0. GOOD GPN 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. GOOD 6PN 55 P2160 SERVICE MATER PIIPS A h B HEADER 72. GOOD PSIG 56 P2161 SERVICE MATER PNPS C h D HEADER 80. 600 D PSIG
'57 INR041 SERVICE WATER PNP A GOOD 58 IIR042 SERVICE WATER PlNP B 600D 59 INR043 SERVICE MATER PIIP C 6009 60 BKR044 SERVICE MATER PNF 0 GOOD EMJ
OGRAK NAHE:LRGTSZ.E OCT 08,92 R.E.
~ ~ GINNA NUCLEAR POWER PLANT 12:15:00 TREND GROUP ASSIGNHEHT SUHHARY GROUP NAME GROUP DESCRIPTIOH EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE EHGR UNITS 1 COKPONEHT COOLING LOOP TOTAL FLW 1485. GOOD GPK 2' LRWST REFUELIHG WATER STORAGE TANK LVL 94.5 GOOD X WS033 33 FOOT LEVEL WIND SPEED 6.5 GOOD KPH 4 WD033 33 FOOT LEVEL WIND DIRECTION 77. GOOD OEG.
5 WT033 33 FOOT LEVEL TEMPERATURE 66.0 GOOD DEGF 6 WT250 250 FOOT LEVEL TEHPERATURE 67.8 GOOD DEGF 7 WOT2 250 TO 33 FOOT LEVEL DELTA TEHP 1.8 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINMENT 7.35678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD KR/H 11 R09 AREA 9.LETDOWN LINE MONITOR 1.27501+02 GOOD KR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD KR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD KR/H 14 R10A CONTAINMENT IODINE MONITOR R10A 9.58719+01 GOOD CPH 0'0619 R11 R12 R10B CONTAINHENT AIR PARTICULATE COHTAINKENT GAS MONITOR PLANT VENT IODIHE MONITOR R10B 5.18901+02 7.38002+02 GOOD GOOD CPM CPM 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS KOHITOR 4.22831+01 GOOD CPH 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658i03 GOOD CPK 21 R19 STEAM GENERATOR BLOWDOWN DRAIN 1.14174+04 HALH CPM 22 R29 AREA 29 CONTAINHENT HIGH RANGE 5.05861.01 GOOD R/NR 23 R30 AREA 30-COHTAINHEHT HIGH RANGE 5.09440.01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPH 25 R12A5 CV VENT CHAN 5 LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAHHA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAH 7 MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1 41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOW RANGE GAS 4.40312.07 GOOD UCI/CC
,30 R14A7 PLANT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9-HIGH RANGE GAS 3.?2621-03 GOOD UCI/CC 32 R15AS AIR EJECTOR CHANS-LOW RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-HID RANGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-Hl RANGE GAS 1. 27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAK LIHE A (SPING) 2.25040t00 HALH KR/HR 36 R32 AREA 32 STEAH LINE 8 (SPING) 1.01048.02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD 38 TCV03 CV BASEMENT LVL 6 FT TEHP ¹3 95 ~ 1 GOOD DEGF 39 TCV07 CV IHTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERHEDIATE LVL 6 FT TEHP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERHEOIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD 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. Cooldown and depressurization of the Plant.
- 2. Repair and return to service of the "A" CCW Pump to ensure a redundant pump for decay heat removal.
- 3. Repair and return to service of the "A" Service Water Pump.
- 4. Repair and return to service of the Natural Gas line to the Screenhouse.
- 5. 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 Reactor Shutdown (YYE NO Hi h Head S.X. Pum s N-31 ~CI CPS FI-924 0 GPM N-32 ~~CPS FI-925 & GPM N-35 z~/ AMPS 1A. INSERV TB OOS N-36 ~-s/ AMPS 1B. INSERV TB OOS Avg. Nuclear Power C7 1C. INSERV TB OOS RCS Pressure ~FE- PSTG BAST Level = Io PRZR Level b~~l.
A RCP RUNNING TOPPED Low Head S.I. Pum s B RCP ~ RUNNIN STOPPED FI-626 O GPM 1A S/G Level 1A. INSERV OOS RECIRC 1B S/G Level S7. 7 1B. INSERV TB OOS RECIRC 1A S/G Pressure PSIG RWST Level = ~E.V 1B S/G Pressure 2. 93 PSIG Turbine/Generator ONLINE FFLI Containment S ra Pum s 4 KV Buses NERGIZE DEENERGIZED FI-931A & GPM 480V Buses R DEENERGIZED FI-931B O GPM DC Batteries A /BO VOLTS B/30 VOLTS 1A. INSERV TB OOS Cnmt Pressure ~ ~ 30 PSIG 1B. INSERV TB OOS Cnmt Sump A Level 2,ek FEET NaOH Tank Level = Cnmt Sump B Level ~~INCHES A Loop Hot Leg Bm.~oF Containment Recirc Fans A Loop Cold Leg ~ax a OF 1A. NSE V STBY OOS B Loop Hot Leg .2 OF 1B. SER STBY OOS B Loop Cold Leg ~oa. OF 1C. SE STBY OOS RVLIS g5 4 1D. NSER STBY OOS
- CET ~OS ~ 0F Post Accident Dampers E CLOSED S/G A Total Aux FW Flow 0 GPM S/G B Total Aux FW Flow Ia.a GPM Service Water Pum s 1A. XNSERV STBY 0 DIESEL GENERATORS 1B. SE STBY OOS 1C. NSER STBY OOS A. RUNNING UNLOADED TB OOS 1D ~ NSER STBY OOS B. RUNNING UNLOADED TB OOS A&B Header Pressure ~7
'0 PSIG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED T OOS Com onent Coolin Water Pum s 1A. INSERV STBY 00 ENGINEERED SAFEGUARDS 1B. NSE STBY OOS Aux. Feedwater Surge Tan evel = M/
Pum s 1A. INSERV T OOS Standb Aux. Feedwater Pum s 1B. SE STBY OOS 1C. INSERV TB OOS Turb. Driven INSERV TB OOS 1D. INSERV STB OOS CST Level ~1 FEET
- 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 ATMS ANTICIPATED TRANSIENT W/0 SCRAM ATWS ALRN 2 RXT REACTOR TRIP BREAKER STATUS R)( TRIPPED ALRN 3 N31 SOlRCE RANGE DETECTOR N-31 7.95241+01 6009 CPS N32 SmSCE RA)IGE DETECTOR N-32 8.46249+01 GOOD CPS N35 INTERMEDIATE RANEE DETECTOR N-35 1.01391-11 6009 AMP 6 N36 INTERMEDIATE RANGE DETECTOR N-36 1.01391-11 6009 AMP 7 NP AVERAGE NLQZ8 POWER .00 GOOD X 8 PRCS REACTOR COOLANT SYSTEM AVG PRESS 892. GOOD PSIG 9 LP2R PRESSURI2ER AVERAGE LEVEL 61.8 HMRN X 10 FRY REKTOR COOLANT LOOP A AVG FLOW 13.2 INHB X 11 FRM REKTOR COOLANT LOOP B AVG FLOW 115.2 6009 X 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRN 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP GOOD TSUBTC INCORE TC SUBC(mLED MARGIN 128.6 600~ DEGF 15 LSGA STM GEN A NARROW RANGE AVG LEVEL 21.7 LMRN X 16 LSGB STM GBI B NARROW RA%E AVG LEVEL 51.7 GOOD X 17 PSGA STM GEN A AVERAGE PRESSURE 891. 6009 PSIG 18 PSGB STM GEN 8 AVERAGE PRESSURE 233. LALM PSIG 19 GENBKRI GBHNTOR ON LINE BREAKER 161372 TRIPPED ALRN 20 GEt(BKR2 GBERATOR ON LINE BREAKER 9X1372 TRIPPED ALRN 21 BUS11A BUS 1fA SUPPLY BREAKER TRIPPED ALRN 22 BUS11B BUS 11B SlFPLY BREAKER TRIPPED ALRN 23 BUS12A NOT TERMIt(ATED Ott PPCS (7/f9/91) NOT TRIP DEL 24 BUS12B NOT TERMIt(ATED ON PPCS (7/19/91) NOT TRIP DEL 25 BiiA12A BUS ifA To 12A TfE BREAKER NOT TRIP ALRN 26 B11812B BUS 11B To 128 TIE BRENER t40T TRIP ALRN 27 PCV CONMINMEt(T AVERAGE PRESSURE -.30 6009 PSIG 28 LQNPA CONTAINMENT SUMP A AVERAGE LEVEL 2.6 HMRN FKf 29 L0942E SU)P B LEVEL 8 INCHES (TRAIN A) LONER 6009 30 L0943E SU)P B LEVEL 8 INCHES (TRAIt4 B) LONER 6009 31 L0942D SU)P B LEVEL 78 INCIIES (TRAIN A) LONER 6009 32 L0943D SU)P B LEVEL 78 INQKS (TRAIN B) LONER 6009 33 L0942C SU)P B LEVEL 113 INCHES(TRAIN A) LONER 6009 34 L0943C SU)P B LEVEL 113 INCHES(TRAIN B) Lo)IER 6009 35 L0942B SU)P B LEVEL 180 INCHES(TRAIN A) Lo)4ER 6009 36 L0943B SUIP B LEVEL 180 INCHES(TRAIN B) LOWER G009 37 L0942A SU)P B LEVEL 214 INCHES(TRAIN A) LOWER 6009 38 L0943A SU)P B LEVEL 214 INCHES(TRAIN B) LONER GOOD 39 T0409A RCLA HOT LEG TEMPERATURE 403.8 6009 DEGF 40 T0410A RCLB HOT LEG TEMPERATUR" 404.2 6009 DEGF 41 T0450 RCLA COLD LEG TEtIPERATURE 402.5 6009 DEGF 42 T0451 RCLB COLD LEG TBIPERATNE 402.5 GOOD DEGF 43 TAVGAMID RCLA TAVG (THOT/TCOLD WIDE RNG) 403.2 6009 DE6F TAVGBMID RCLB TAVG (THOT/TCOI.D WIDE RNG) 403.4 600D DEGF 45 LRV REACTOR VESSEL AVERAGE LEVEL 99.5 GOOD X 46 TCCORE Ei ~ 1 INCORE TC AVERAGE TEMP 403.6 600~ DEGF 47 FAUXFMA S/G A TOTAL AUX FEEDMATER FLOW 0. 6009 GPM 48 FAUXFWB S/G B TOTAL AUX FEEDMATER FLOW 125. GOOD GPM 49 BKR081 MTR AUXILIARYFEEDMATER PUMP A OFF 6009 50 BKR082 MTR AUXILIARYFEEDMATER PUMP B ON GOOD 51 V3505 AUX FM PUMP STEAN SUPPLY VALVE A CLOSED 6009 52 V3504 AUX FW PUMP STEAN SUPPLY VALVE B CLOSED GOOD
OCT 8~ 1992, 12!30 R. E. GIt5A SIIIULATOR PAGE 2 TREND GROUP ASSIGIDIENT SINNRY GROUP: EVEIIT1 PROCEDURE: EPIP 1-5 PLNT STATUS POINT ID DESCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY INJECTION'LOOP A AVG FLOW 0. GOOD 6PtI 54 FSIB SAFETY INJECTION LOOP B AV6 FLOW 0. GOOD 6PN 55 P2160 SERVICE WATER PINPS A h B HEADER 72. GOOD PSIG 56 P2161 SERVICE MATER PNIPS C 5 D HEADER 80. 600D PSIG 57 BKR041 SEINICE WATER PINP A GOOD 58 BKR042 SERVICE WATER PUlIP B 600D 59 BKR043 SERVICE WATER PINP C GOOD 60 BKR044 SERVICE MATER PNP 0 600D
ROGRAM NAME :LRGTSZ.E
~ OCT 08,92 R.E.
~ ~ GIHHA NUCLEAR POWER PLANT 12:30:00 TREHD GROUP ASSIGNMEHT
SUMMARY
GROUP NAME GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLW 1485. GOOD GPM 2 LRWST REFUELIHG WATER STORAGE TANK LVL 94.5 GOOD x 3 WS033 33 FOOT LEVEL WIND SPEED 8.5 GOOD MPH 4 WD033 33 FOOT LEVEL 'WIHD DIRECTION 67. GOOD BEGS 5 WT033, 33 FOOT LEVEL TEMPERATURE 69.0 GOOD DEGF 6 WT250 250 FOOT LEVEL TEMPERATURE 67.8 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEMP 1.8 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAIHMENT 7.35678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD MR/H 11 R09 AREA 9-LETDOWN LINE MONITOR 1.24701+02 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35 PASS SAMPLE PANEL 1.09283+00 GOOD MR/H 14 R10A CONTAINMENT IODINE MONITOR R10A 9.58719+01 GOOD CPM R11 CONTAINMENT AIR PARTICULATE 5 '8901+02 GOOD CPM R12 CONTAINMEHT GAS MOHITOR 7.38002+02 GOOD CPM R108 PLANT VENT IODINE MOHITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM 19 R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658+03 GOOD CPM 21 R19 STEAM GENERATOR BLOWDOWH DRAIN 1.09474+04 HALM CPM 22 R29 AREA 29-COHTAIHHEHT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINMEHT HIGH RANGE 5.09440.01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1 '7835+03 GOOD CPM 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS 1.89699.07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAH 5-LOW RANGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAH 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15AS AIR EJECTOR CHAN 5-LOW RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9 HI RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 2. 18040t00 HALM MR/HR 36 R32 AREA 32 STEAM LINE 8 (SPIHG) 1.01048-02 GOOD MR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD x 38 TCV03 CV BASEMENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹'IO 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD DEGF 0 J
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. Cooldown and depressurization of the Plant.
- 2. Repair and return to. service of the "A" CCW Pump to ensure a redundant pump for decay heat removal ~
- 3. 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. "A" S/G Tube inspection and repair.
- 2. Possible "B" S/G Tube inspection.
- 3. "A" S/G Tube rupture evaluation for root cause.
4, 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 Hi h Head S.I. Pum s N-31 0 CPS FI-924 0 GPM N-32 g CPS FI-925 GPM N-35 feb'-If AMPS 1A. INSERV TB OOS N-36 gl AMPS 1B. INSERV T OOS Avg. Nuclear Power 1C INSERV TB OOS RCS Pressure 47 PSIG BAST Level = / PRZR Level dO A RCP RUNNING TOPPE Low Head S.I. Pum s B RCP RUNNING STOPPED FI-626 O GPM 1A S/G Level 1A. INSERV T OOS RECIRC 1B S/G Level ~.2 1B. INSERV TB OOS RECIRC 1A S/G Pressure ~~~PSIG RWST Level = ~3. 1B S/G Pressure woz PSIG Turbine/Generator ONLINE FFLIN Containment S ra Pum s 4 KV DC Buses 480V Buses Batteries Cnmt Pressure Cnmt Sump A Level Cnmt Sump B Level A Loop Hot Leg RG ENERGIZE A~VOLTS
~ DEENERGIZED DEENERGIZED B/30 VOLTS
~aS S
- 2. ~ Ce
~(INCHES
>9m.r7 OF PSIG FEET .
FI-931A FI-931B 1A. 1B. NaOH INSERV INSERV GPM O GPM Tank Level = Containment T ecirc OOS OOS Fans A Loop Cold Leg ~Et .s. OF 1A. NSER STBY OOS B Loop Hot Leg ~i.ELOF 1B. B Loop Cold Leg RVLIS
~. I OF 1C.
1D. SER SER NSE STBY STBY STBY OOS OOS OOS
- CET OF Post Accident Dampers PEN CLOSED S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow ~GPM Service Water Pum s 1A. INSERV STBY DIESEL GENERATORS 1B. NSER STBY OOS 1C. SERV STBY OOS A.
B. RUNNING UNLOADED TB OOS RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED T OOS 1D. A&B Header NS STBY OOS ressure ~0 PSIG Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. INSERV STBY 00 ENGINEERED SAFEGUARDS Aux. Feedwater Pum s 1B. Surge Tan NSERV STBY OOS Level = ~% 1A. INSERV TB OOS Standb Aux. Fee ater Pum s 1B. SER STBY OOS 1C. INSERV TB OOS Turb. Driven INSERV T OOS 1D. INSERV TB OOS CST Level ~iFEET
- CET = Average of Selected Core Exit Thermocouples
8~ 1992 12:45 R. E. Glt5A SIMULATOR PA6E 1 TREND GROUP ASSIG)MENT SUM)(ARY GROUP: EVENT1 PROCEDURES EPIP 1-5 PLA)IT STATUS POINT ID DESCRIPTION VALUE E. U. 1 ATWS ANTICIPATED TRANSIENT W/0 SCRAM ATNS ALRII 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALR)( 3 N31 SmSCE RANGE DETECTOR N-31 7.95241+01 GOOD CPS 4 N32 SolSCE RWGE DETECTOR N-32 8.5802M)1 6000 CPS 5 N35 INIEI(MEDIATE RANGE DETECTOR N"35 1.01391-11 6000 AMP 6 N36 INTERMEDIATE RANGE DETECTOR N-36 1 ~ 01391-11 6000 At(P 7 t(P AVERAGE NIKLEAR PONER .00 GOOD / 8 PRCS REACTOR COOLANT SYSTEM AVG PRESS 767. 6000 PSI6 9 LPZR PRESSURIIER AVERAGE LEVEL 60.0 HWRN I/ 10 FRCLA REACTOR CGOL@T LOOP A AVG FLOW 13.3 INHB y. 11 FRCLB REACTOR COOLANT LOOP B AVG FLOW 116.0 6000 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALRN 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6000 14 TSUBTC INCGRE TC SUBCOOLED MARGIN 122.9 600i DEGF 1S LSGA STM GEN A tQRROM RAt(GE AVG LEVEL 18.8 LMRtl X 16 LSGB STM GEt( B NARROW RANGE AVG LEVEL S6.2 6000 X 17 PSGA STM GEN A AVERAGE PRESSURE 768, 6009 PSIG 18 PSGB STM GEN B AVERAGE PRESS)RE 202. LAL)I PSIG 19 GENBKR1 GEtGQTOR ON LINE BREAKER 161372 TRIPPED ALRN 20 GENBKR2 GESITOR ON LINE BREAKER 9X1372 TRIPPED ALRI( 21 BUS11A BUS 11A SUPPLY BREAKER TRIPPED ALRt( 22 BUS11B BUS 11B RFPLY BREAKER TRIPPED ALRN 23 BUS12A NGT TERMINATED Ott PPCS (7/19/91) NGT TRIP DEL 24 BUS12B NOT TERMINATED ON PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS iiA TO 12A TIE BREAKER NOT TRIP ALRN 26 BiiB12B BUS 11B TO 12B TIE BREAKER NOT TRIP ALRtf 27 PCV CONTAIeENT AVERAGE PRESSURE -.34 6009 PSI6 28 LSINPA CONTAINMENT SUt(P A AVERAGE LE4EL 2.6 HWRI( FKT 29 LO942E SU)P B LEVEL 8 INCHES (TRAIN A) LONER 6000 30 LO943E SUtP B LEVEL 8 INCHES (TRAIN B) LONER GOOD 31 LO942D SU)P B LEVEL 78 IN&KG (TRAIN A) LONER 6000 32 LO943D SU)P B LEVEL 78 INCHES (TRAIN B) LONER 6000 33 LO942C SU)P B LEVEL 113 INCHES(TRAIN A) LONER GOOD 34 LO943C SUtP B LEVEL 113 INCHES(TRAIN B) LONER 6000 35 LO942B SU)P B LEVEL 180 INCHES(TRAIN A) LONER 6000 36 LO9438 SUtP 0 LEVEL 180 INCHES(TRAIN B) LONER 6000 37 LO942A SU)P B LEVEL 214 INCHES(TRAIt< A) LONER 6009 38 LO943A SU)P 0 LEVEL 214 INCHES(TRAIN B) LONER 6000 39 TO409A RCLA HOT LEG TEMPERATURE 392.7 GOOD DEGF 40 TO41OA RCLB HGT LEG TEMPERATURE 392.9 6000 KGF 41 TO450 RCLA Col.D LEG TE)IPERATlRE 391.2 GOOD DEGF 42 TO451 RCLB COLD LEG TE)IPERATISE 391.1 6000 DE6F 43 TAVGAWID RCU) TAVG (THOT/TCOLD WIDE RNG) 392.0 GOOD DEGF 44 TAVGBMID RCLB TAVG (THOT/TCOLD WIDE RNG) 392.0 6000 KGF LRV RECTOR VESSP AVERAGE LEVEL 99.3 6000 46 TCCGRE Ei.i INCORE TC AVERAGE TEMP 392.7 Goo'009 KGF 47 FAUXFWA S/6 A TOTAL AUX FEEDWATER FLW O. IPM 48 FAUXFWB S/G 8 TOTAL AUX FEEDWATR FLOW 86. 6000 GPM 49 BKRO81 MTR AUXILIARYFEEDWATER PU)IP A OFF 6009 50 BKR082 t(TR AUXILIARYFEEDWATER PUt(P 0 ON 6000 51 V35OS AUX FW PUIIP STEA)I SUPPLY VALVE A CLOSED GOOD 52 V3504 AUX FM PUI(P STEA)l Sl)PPLY VALVE B CLOSED 6000
OCT 8~ 1992 12:45 R. E. GINA SIRLATOR PA6E 2 TREND GROUP ASSIGNNENT RNNRY GROUP! EVENT1 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION OVAL E. U. 53 FSIA SAFETY INJECTION'LKP A AVG FLOW 0. GOOD GPN 54 FSIB SAFETY INJECTION LOOP B AVG FLIN 0. GOOD IF'00 55 P2160 SERVICE MATER PlIPS A h B HEADER 72. D PSIG 56 P2161 SERVICE MATER PIIPS C h 9 HEADER 80. GOOD PSIG 57 BKR041 SERVICE MATER PlmP A OFF GOOD 58 BKR042 SERVICE WATER PSF B ON GOOD 59 BKR043 SERVICE MATER PNP C ON 600D 60 BKR044 SERVICE MATER PlIP D ON GOOD
ROGRAM NAME :LRGTSZ ~ E OCT 08,92 R.E.
~ ~ GIHNA NUCLEAR POWER PLANT 12 45 00 TREND GROUP ASSIGNMENT
SUMMARY
GROUP NAME GROUP DESCRIPT ION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLIHG LOOP TOTAL FLW 1485 ~ GOOD GPM 2 LRWST REFUELING 'WATER STORAGE TANK LVL 94.5 GOOD x 3 WS033 33 FOOT LEVEL WIND SPEED 8.7 GOOD MPH 4 WD033 33 FOOT LEVEL WIHD DIRECTION 65. GOOD DEG. 5 WT033 33 FOOT LEVEL TEMPERATURE 66.0 GOOD DEGF 6 WT250 250 FOOT LEVEL TEMPERATURE 67.8 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEMP 1.8 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-COHTAINMEHT 7.35678+00 GOOD MR/H 10 R05 AREA 5-SPEHT FUEL PIT 1.39946+00 GOOD MR/H R09 AREA 9-LETDOWN LINE MONITOR 1 ~ 22501+02 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PAHEL 1.09283i00 GOOD MR/H 14 R10A CONTAINMEHT IODINE MONITOR R10A 9.58719+01 GOOD CPM R11 CONTAINMENT AIR PARTICULATE 5 '8901+02 GOOD CPM R12 CONTAINMENT GAS MONITOR 7.38002+02 GOOD CPM R108 PLANT VENT IODINE MONITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM R14 AUX BLDG EXHAUST GAS MONITOR 4.22831+01 GOOD CPM 20 R18 LIQUID WASTE DISPOSAL MONITOR 2.78658+03 GOOD CPM 21 R19 STEAM GENERATOR SLOWDOWN DRAIN 1.02474+04 BALM CPM 22 R29 AREA 29-COHTAINMEHT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINMENT HIGH RANGE 5.09440.01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPM 25 R12A5 CV VENT CHAN 5-LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMHA 2 '3990.02 GOOD MR/NR 27 R12A7 CV VENT CHAN 7-MID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RAHGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOW RAHGE GAS 4.40312-07 GOOD UCI/CC 30 R14A7 PLANI'ENT CHAN 7 MID RAHGE GAS= 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VEHT CHAN 9-HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAH 5-LOW RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RAHGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-Ml RANGE GAS 1. 27941.03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 2. 16040+00 HALM MR/NR 36 R32 AREA 32 STEAM LINE B (SPING) 1.01048-02 GOOD MR/NR 37 CVH CV HYDROGEN CONCENTRATION ~ 0 GOOD X 38 TCV03 CV BASEMENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCV08 CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEMP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEHP ¹17 117.5 0-GOOD 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. Cooldown and depressurization of the Plant.
- 2. Repair and-return to service of the "A" CCW Pump to ensure a redundant pump for decay heat removal.
- 3. Repair and return to service of the" A" Service Water Pump.
- 4. 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. "A" S/G Tube inspection and repair.
- 2. Possible "B" S/G Tube inspection.
- 3. "A" S/G Tube rupture evaluation for root cause.
- 4. 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 Reactor Shutdown E NO Hi h Head S.I. Pum s N-31 CPS FI-924 N GPM N-32 N-35
~CPS -s( AMPS FI-925 ~GPM 1A INSERV TB OOS N-36 AMPS 1B. INSERV B OOS Avg. Nuclear Power 0 1C INSERV TB OOS RCS Pressure ~@i PSIG BAST Level = ~1 PRZR Level 3).a A RCP RUNNING TOPP Low Head S.I. Pum s B RCP UNNIN STOPPED FI-626 O GPM 1A S/G Level 27.1 1A. INSERV TB OOS RECIRC 1B S/G Level 1B. INSERV TB OOS RECIRC 1A S/G Pressure PSIG RWST Level = 3.
1B S/G Pressure l7 PSIG Turbine/Generator ONLINE FFLI Containment S ra Pum s 4 KV Buses NERGIZED DEE RGIZED FI-931A O GPM 480V Buses NERGI E DEENERGIZED FI-931B & GPM DC Batteries AI3o VOLTS BI30 VOLTS 1A. INSERV T OOS Cnmt Pressure 3'SIG 1B. INSERV TB OOS Cnmt Sump A Level 2.7 FEET NaOH Tank Level = 'F Cnmt Sump B Level ~(INCHES A Loop Hot Leg ~SPOOF Containment Recirc Fans A Loop Cold Leg ~3I 70F. lA. SE STBY OOS B Loop Hot Leg OF 1B. SE STBY OOS B Loop Cold Leg 3t/.s OF 1C. NSE STBY OOS RVLIS
- CET
'~/
~~..9'F 1D. NSER STBY OOS Post Accident Dampers PEN CLOSED S/G A Total Aux FW Flow GPM S/G B Total Aux FW Flow a GPM Service Water Pum s 1A. IN RV STBY 0 DIESEL GENERATORS 1B. NSE STBY OOS 1C. ER STBY OOS A. RUNNING UNLOADED TB OOS 1D. NSERV STBY OOS B. RUNNING UNLOADED TB OOS A&B Header Pressure 7~'0 PSIG TSC RUNNING UNLOADED TB OOS Security RUNNING UNLOADED TB OOS Com onent Coolin Water Pum s 1A. INS STBY 0 ENGINEERED SAFEGUARDS 1B. NSER STBY OOS Aux. Feedwater Pum s Surge Tan Level = ~i~4 1A. NSE STBY OOS Standb Aux. Fe water Pum s 1B. NSER STBY OOS 1C. INSERV STB OOS Turb. Driven INSERV TB 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 ATl6 ANTICIPATED TRANSIENT M/0 SCRN 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED 3 N31 SmmCE RANGE DETECTOR N-31 8.40424+01 Goon CPS 4 N32 SmnCE RA%E DETECTOR N-32 8.60992+01 6009 CPS 5 N35 INTERNEDIATE RANGE KfECTOR N-35 1.01391-11 6009 I(P 6 N36 INTERNEDIATE RANGE DETECTOR N-36 1.01391-11 600D Al(P 7 NP AVERAGE NLQZ8 POMER F 00 6009 0/ 8 PRCS REACTOR COOLANT SYSTB( AVG PRESS 646, GOOD PSIG 9 LPLR PRESSURIlER AVERAGE LEVEL 31.5 6009 X 10 FRCLA REACTOR COOLNT LOOP A AVG FLOM 13.5 INHH y. 11 FRCLB REACTOR COOLNI'OOP B AVG FLOM 116.7 6009 7 12 RXT16 RCPA BRENER CAUSE RX TRIP TRIPPED ALRt( 13 RXT17 RCPB BREAKER CAUSE RX TRIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED t(ARGIN 113.2 600~ DEGF 15 LSGA STtt 6Bl A NARROM RA%E AVG LEVEL 28.7 LMRtt X 16 LSGB STN GEN B NARROM RAtlGE AVG LEVEL 55.4 Goon / 17 PSGA STt( GB( A AVERAGE PRESSURE 615. 6009 PSIG 18 PSGB STN GEN B AVERAGE PRESSURE 174. LALN PSIG 19 GENBKRl GEtGQTOR ON LINE BREAKER 161372 TRIPPED AUI 20 GBIKR2 GENERATOR ON LINE BRENER 9Xf372 TRIPPED ALRt( 21 BUSllA BUS 11A SLPPLY BREAKER TRIPPED 22 BUS11B BUS 11B SUPPLY BREAKER TRIPPED 23 BUS12A NOT TERNINATED Ott PPCS (7/19/91) NOT TRIP 24 BUS12B tloT TERt(lt(ATED ON PPCS (7/19/91) NOT TRIP 25 Bl lA12A BUS 11A TO 12A TIE BREAKER NOT TRIP 26 B11B129 BUS 11B To 12B TIE BREAKER NOT TRIP 27 PCV CONTAINtiENT AVERAGE PRESSURE -.36 28 LS(IPA CONTAItlt(B(T PJt(P A AVERAGE LEVEL 2.7 29 L0942E SIP B LEVEL 8 INCHES (TRAIN A) LONER 6009 30 L0943E SUtP B LEVEL 8 It(CHES (TRAIN 9) LONER GOOD 31 L0942D SU)P B LEVEL 78 INCHES (TRAIN A) LONER 6009 32 L0943D SU)P B LEVEL 78 IN&KG (TRAIN B) LONER 6009 33 L0942C SUtP B LEVEL 113 INCHES(TRAIN A) LONER GOOD 34 L0943C SU)P B LEVEL 113 INCHES(TRAIN B) LONER 6009 35 L0942B SU)P B LEVEL 180 INCHES(TRAIN A) LONER Goon 36 L0943B SU)P 8 LEVEL 180 INCHES(TRAIN B) LONER GOOD 37 L0942A SUtP B LEAL 214 INCHES(TRAIN A) LONER GOOD 38 L0943A SU)P B LEVEL 214 INCHES(TRAIN B) LONER GOOD 39 T0409A RCLA HOT LEG TB(PERATUfK 385.9 600D DEGF 40 T0410A RCLB HOT LEG TEt(PERATURE 383.7 Goon D""BF 41 T0450 RCLA COLD LEG TB(PERATNE 381.7 6009 DEGF 42 T0451 RCLB COLD LEG TB(PERAT(RE 381.5 6009 DEGF 43 TAVGAMID RCLA TAVG (THOT/TCOLD MIDE RNG) 383.8 6009 IEGF 44 TAVGBWID RCLB TAVG (THOT/TCOLD MIDE RNG) 382.6 6009 DEGF 45 LRV REI:TOR VESSEL AVERAGE LEVEL 99.1 GOOD X 46 TCCORE El 1 INCORE
~ TC AVERAGE TBP '382.9 600~ DE6F 47 FAUXFMA S/6 A TOTAL AUX FEEDMATER FLOM 53 I 6009 GPt(
48 FAUXFMB S/G B TOTAL AUX FEEDMATER FLON 24. GOOD GPt( 49 BKR081 NTR AUXILIARYFEEDMATER PUt(P A ON 50 BKR082 t(TR AUXILIARYFEEDMATER PUlP B ON 6009 51 V3505 AUX FM PUttP STEAN SUPPLY VALVE A CLOSED 6009 52 V3504 AUX FM PU!P STBI SUPPLY VALVE B CLOSED Goon
'I w- AD%3
OCT 8~ 1992 13l00 R. E. GINA SIMULATOR PAGE 2 TREND GROUP ASSIGNMENT
SUMMARY
6ROUP: EVENTI PROCEDURE: EPIP 1-5 PLAtIT STATUS POINT ID DESCRIPTION VALUE QUAL E. U. 53 FSIA SAFETY INJECTION'LOOP A AVG FLOW 0. GOOD GPM 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. GOOD GPM 55 P2160 SERVICE WATER PNFS A h B HEADER 72. 600D PSIG 56 P2 161 SERVICE WATER PNFS C h D HEADER 80. GOOD PSI6 57 BNR041 SERVICE WATER PNF A OFF GOOD 58 ImR042 SERVICE WATER PNF B ON GOOD 59 BKR043 SERVICE WATER PNF C ON 600D 60 IIR044 SERVICE WATER PNF D ON GOOD E+J
ROGRAH NAHE:LRGTSZ.E OCT 08,92 R.E. GINNA NUCLEAR POWER PLANT 13:01:00 TREND GROUP ASSIGNHENT SUMHARY GROUP NAHE GROUP DESCRIPTION EVEHT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE DUALITY CODE ENGR UNITS 1 F0619 COMPONENT COOLING LOOP TOTAL FLW 1485. GOOD GPH 2 LRWST REFUELING 'WATER STORAGE TANK LVL 94.5 GOOD x 3 WS033 33 FOOT LEVEL WIHD SPEED 8.7 GOOD MPH 4 W0033 33 FOOT LEVEL WIND DIRECTION 65. GOOD DEG. 5 WT033 33 FOOT LEVEL TEHPERATURE 66.0 GOOD DEGF 6 WT250 250 FOOT LEVEL TEHPERATURE 67.8 GOOD DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEHP 1.8 GOOD DEGF 8 R01 AREA 1-CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-COHTAINHENT 7.35678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.3994& 00 GOOD MR/H 11 R09 AREA 9-LETDOWN LINE MONITOR 1.20701+02 GOOD MR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD HR/H 14 R10A CONTAINMENT IODINE MONITOR R10A 9.58719+01 GOOD CPM R11 COHTAINHENT AIR PARTICULATE 5.18901+02 GOOD CPH R12 CONTAINHENT GAS MONITOR 7.38002+02 GOOD CPH R108 PLANT VENI'OOIHE MOHITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPH 19 R14 AUX BLDG EXHAUST GAS MONITOR 4. 22831+01 GOOD CPH 20 R18 LIQUID WASTE DISPOSAL HONITOR 2.78658+03 GOGO CPM 21 R19 STEAM GENERATOR BLOWDOWN DRAIN 9.90174+03 KALM CPM 22 R29 AREA'9.CONTAINHEHT HIGH RANGE 5 '5861-01 GOOD R/HR 23 R30 AREA 30-CONTAINHENT HIGH RANGE 5.09440-01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPM 25 R12AS CV VENT CHAN 5-LOW RANGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD MR/HR 27 R12A7 CV VENT CHAN 7-HID RANGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RANGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAN 5-LOW RANGE GAS 4.40312.07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RANGE GAS 6.86543.05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9.HIGH RAHGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOW RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7.MID RANGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 1.27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPING) 1.93040+00 HALH MR/HR 36 R32 AREA 32 STEAM LINE B (SPING) 1.01048.02 GOOD HR/HR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD 38 TCV03 CV BASEMENT LVL 6 FT TEHP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERHEDIATE LVL 6 FT TEHP ¹7 106.0 GOOD DEGF 40 TCV08 CV INTERMEDIATE LVL 6 FT TEHP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 FT TEMP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERMEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF 43 TCV17 CV OPERATING LVL 6 FT TEHP ¹17 117.5 GOOD DEGF 0 J
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 ES NO Hi h Head S.I. Pum s N-31 ~~CPS FI-924 O GPM N-32 ~OCPS FI-925 C) GPM N-35 g.OE-II AMPS 1A. INSERV T OOS N-36 Ass'->I AMPs 1B. INSERV T OOS Avg. Nuclear Power 1C. INSERV B OOS RCS Pressure $ 3O PSIG BAST Level = /O PRZR Level & A RCP RUNNING TOPP Low Head S.I. Pum s B RCP UNNIN STOPPED FI-626 GPM 1A S/G Level ~s.o & 1A. INSERV OOS RECIRC 1B S/G Level 1B. INSERV TB OOS RECIRC 1A S/G Pressure Pressure
~~PSIG RWST Level = 9'3.
1B S/G /z. (r PSIG Turbine/Generator ONLINE FFLIN Containment S ra Pum s 4 KV Buses ERGIZE DEENERGIZED FI-931A GPM 480V Buses ERGIZE DEENERGIZED FI-931B N GPM DC Batteries A/Sb VOLTS B/B~'VOLTS 1A. INSERV T OOS Cnmt Pressure .3g PSIG 1B. INSERV TB OOS Cnmt Sump A Level 2..7 FEET NaOH Tank Level = Cnmt Sump B Level ~(INCHES A Loop Hot Leg OF Containme ecirc Fans A Loop B B Cold Leg Loop Hot Leg Loop Cold Leg 3'F SS 2.
/ST 'F OF OF 1A.
1B. lc. SERV SERV SE STBY STBY STBY OOS OOS OOS RVLIS
- CET V$" 9'F 1D.
P ost NSERV STBY Accident Dampers OOS OPE CLOSED S/G A Total Aux FW Flow 88 GPM S/G B Total Aux FW Flow 2-9 GPM Service Water Pum s 1A. INSE V STBY OS DIESEL GENERATORS 1B. NS R STBY OOS 1C. NSERV STBY OOS A. RUNNING UNLOADED TB OOS 1D. NSER STBY OOS B. RUNNING UNLOADED TB OOS TSC RUNNING UNLOADED TB OOS A&B Header Pressure V~0 PSIG Security RUNNING UNLOADED OOS Com onent Coolin Water Pum s 1A. INSERV STBY 0 ENGINEERED SAFEGUARDS 1B. NSERV STBY OOS Surge Tau Level = ~d Aux. Feedwater Pum s 1A. SE STBY OOS Standb Aux. Feedwater Pum s 1B. NSE STBY OOS 1C. INSERV STB OOS Turb. Driven CST Level ~FE INSERV TB T OOS 1D. INSERV TB OOS
- CET = Average of Selected Core Exit Thermocouples
81 1992 13:16 R. E. GINA Sft(ULATOR PAGE 1 TREND GROUP ASSIGN>(Et(T SUI(ARY GROUP: EVENT1 PROCEDURE: EPIP 1"5 PLANT STATUS POINT ID DESCRIPTION E. U. 1 ATWS ANTICIPATED TRANSIENT W/0 SCRN ATWS ALfm 2 RXT REACTOR TRIP BREAKER STATUS RX TRIPPED ALRt( 3 N31 SolsCE RANGE DETECTOR N-31 8.40424+01 6009 CPS 4 N32 So(ICE RANGE DETECTOR N-32 8.03523+01 6009 CPS 5 N35 INTERt(EDIATE RANGE DETECTOR N-35 I.Oi39f-ff 6009 NP 6 tG6 It(TER>(EDIATE RANGE DETECTOR N-36 1.01391"ii GOOD At(P 7 NP AVERAGE NUCLEAR POWER .00 6009 8 PRCS REACTOR COOLANT SYSTEtl AVG PRESS 530. 6009 PSIG 9 LPLR PRESSURIIER AVERAGE LEVEL 32.4 6009 X 10 FRCLA RECTOR COKAVT LOOP A AVG FLOW 13,6 INHB 11 FRCLB REI:TOR COOLW(T LOOP B AVG FLOW 118.6 6009 X 12 RXT16 RCPA BREAKER CAUSE RX TRIP TRIPPED ALR)( 13 RXT17 RCPB BREAKER CAUSE RX 'IHIP NOT TRIP 6009 14 TSUBTC INCORE TC SUBCOOLED t(ARGIN 116.5 600~ DEGF 15 LSGA STt( GEtt A NARROW RANGE AVG LEVEL 30.0 LWRN 16 LSGB STN GEN B NARROW RANGE AVG LEVEL 34.4 Goon X 17 PSGA STt( GEt( A AVERAGE PRESSURE 525. LWfi PSIG 18 PSGB STt( GEN B AVERAGE PRESSURE 126. LALN PSIG BBSKRI GBERATOR ON LINE BREAKER 161372 TRIPPED ALRt( 20 GBSKR2 GBERATOR ON LINE BREAKER 9X1372 TRfPPED ALRtj 21 BUS11A BUS 11A SUPPLY BS(ER TRIPPED ALRtl 22 BUS118 BUS liB SliPPLY BREAKER TRfPPED ALRt( 23 BUS12A t(OT TERt) lt(ATED ON PPCS (7/19/91) NOT TRIP DEL 24 BUS12B NOT TERNINATED ON PPCS (7/19/91) NOT TRIP DEL 25 B11A12A BUS 11A TO 12A TIE BRENER NOT TRIP ALfm 26 B11B12B BUS 11B TO 12B TfE BREA((ER NOT TRIP ALRt{ 27 PCV CONTAIN)(ENT AVERAGE PRESSURE -.38 6009 PSIG 28 LSiNPA Cot(TAIttt(EtIT SUt(P A AVERAGE LEVEL 2.7 HWRt( FFEf 29 L0942E SiRP B LEVEL 8 INCHES (TRAIN A) LONER Goon 30 L0943E SUtP B LEVEL 8 INCHES (TRAIN 9) LONER 6009 31 L0942D SU>P B LEVEL 78 INCHES (TRAIN A) LONER 6009 32 L09439 SU)P B LEVEL 78 INC)XS (TRAIN B> LONER 6009 33 L0942C SU>P B LEVEL 113 INCHES(TRAIN A) LONER 6009 34 L0943C SU)P B LEVEL 113 INCHES(TRAIN B) /ONER Goon 35 L0942B SU)P B LEVEL 180 INCHES(TRAIN A> LONER 6009 36 L0943B SU)P B LEVEL 180 INCHES(TRAIN B) LONER Goon 37 L0942A SIP B LEVEL 214 INCHES(TRAIN A) LONER 6009 38 L0943A SU>P B LEVEL 214 INCHES(TRAIN B) LONER 6009 39 T0409A RCLA HOT LEG TEt)PERATUR= 360.3 6009 DEGF 40 T0410A RCLB HOT LEG TEt(PERATUfK 359.8 6009 KGF 41 T0450 RCLA COLD LEG TPiPERAT(HE 358.2 Goon DEGF 42 T0451 RCLB COLD LEG TEt(PERAT(SE 357.9 6009 DEGF 43 TAVGAWID RCLA TAVG (THOT/TCOLD WIDE RNG) 359.3 GOOD DEGF 44 TAVGBWfD RCLB TAVG (THOT/TCOLD WIDE RNG) 358.9 6009 DEGF 45 LRV REACTOR VESSEL AVERAGE LEVEL 98.9 X 46 TCCORE El. 1 INCORE TC AVERAGE TEt(P 359.4 Goo> DEGF 47 FAUXFWA S/G A TOTAL AUX FEEDWATER FL(I 55. GOOD GP>( 48 FAUXFWB S/G B TOTAL AUX FEENA7R FLOW 23. 6009 8't( 49 BKRO81 t(TR AUXILIARYFEEDWATER PUt(P A ON 6009 50 BKR082 t(TR AUXILIARYFEEDWATER PUt(P 9 ON 6009 51 V3505 AUX FN PlNP STEA)f SUPPLY VALVE A CLOSED 52 V3504 AUX FW PUt(P STEAtf SUPPLY VALVE B CLOSED 6009
XT 8~ 1992 13:ib R. E. GINA SINULATOR PAGE 2
--- TREND GMlUP ASSIGNBtT StNMY 6tm'VENTi PROCES'PIP 1-5 PLANT STATUS POINT ID DESCRIPTION VALUE NNL E. U.
53 FSIA SAFETY INJECTION LOOP A AV6 FLOW 0. 600 D fPtt 54 FSIB SAFETY INJECTION LOOP B AVG FLOW 0. 600D GPN 55 P2160 SERVICE WATER PtNPS A 5 B HEADER 72. 600D PSIG 56 P2161 SERVICE WATER PtNPS C h D HEAXR So. GOOD PSIG
'57 Bt<R041 SERVICE WATER PtNP A OFF 600D 58 IaR042 SERVICE WATER PUtP B ON 600D 59 BttR043 SERVICE WATER PtNP C ON 600D 60 BttR044 SERVICE WATER PtNP 0 ON 600D E+J
ROGRAM NAME :LRGTSZ.E OCT 08,92 R.E. GINHA NUCLEAR PONER PLANT 13:14:00 TREND GROUP ASSIGNHENT
SUMMARY
GROUP HAME GROUP DESCRIPTION EVENT 2 PROCEDURE: EPIP 1-5 PLANT STATUS POINT ID DESCRIPTION CURRENT VALUE QUALITY CODE ENGR UNITS 1 F0619 COMPOHEHT COOLING LOOP TOTAL FLIJ 1485. GOOD GPM 2 LRNST REFUELING MATER STORAGE TANK LVL 94.5 GOOD x 3 WS033 33 FOOT LEVEL llIND SPEED 8.7 GOOD MPH 4 ll0033 33 FOOT LEVEL MIND DIRECTION 65 GOOD DEG. 5 UT033 33 FOOT LEVEL TEMPERATURE '6.0 GOOD DEGF 6 IH250 250 FOOT LEVEL TEHPERATURE 67.8 GOGO DEGF 7 WDT2 250 TO 33 FOOT LEVEL DELTA TEHP 1.8 GOOD DEGF 8 R01 AREA 1 CONTROL ROOM 9.02214-02 GOOD MR/H 9 R02 AREA 2-CONTAINHENT 6.40678+00 GOOD MR/H 10 R05 AREA 5-SPENT FUEL PIT 1.39946+00 GOOD HR/M 11 R09 AREA 9-LETDONN LINE MONITOR '1.47701+02 GOOD HR/H 12 R34 AREA 34-AUX BLDG CV SPRAY PUMP 9.09354-01 GOOD MR/H 13 R35 AREA 35-PASS SAMPLE PANEL 1.09283+00 GOOD MR/H R10A CONTAINMEHT IODINE MONITOR R10A 9.58719101 GOOD CPM R11 CONTAINMEHT AIR PARTICULATE 5.18901+02 GOOD CPM R12 COHTAINHENT GAS MONITOR 7.38002+02 GOOD CPH R10B PLANT VENI'ODINE MOHITOR R10B 4.30543+01 GOOD CPM R13 AUX BLDG EXHAUST AIR PARTICULATE 8.58327+01 GOOD CPM 19 R14 AUX BLDG EXHAUST GAS HONITOR 4.22831+01 GOOD CPH 20 R18 LIQUID lJASTE DISPOSAL HONITOR 2.78658>03 GOOD CPM 21 R19 STEAM GENERATOR BLONDOWN DRAIN 1.57174+04 BALM CPM 22 R29 AREA 29-CONTAINMEHT HIGH RANGE 5.05861-01 GOOD R/HR 23 R30 AREA 30-CONTAINMENT HIGH RANGE 5.09440.01 GOOD R/HR 24 R15 CONDENSER AIR EJECTOR EXHAUST 1.57835+03 GOOD CPM 25 R12AS CV VENT CHAN 5-LOU RAHGE GAS 1.89699-07 GOOD UCI/CC 26 R12A6 CV VENT CHAN 6-AREA GAMMA 2.53990-02 GOOD MR/NR 27 R12A7 CV VENT CHAN 7-MID RAHGE GAS 3.57435-05 GOOD UCI/CC 28 R12A9 CV VENT CHAN 9-HIGH RAHGE GAS 1.41261-03 GOOD UCI/CC 29 R14A5 PLANT VENT CHAH 5 LOU RANGE GAS 4.40312.07 GOOD UCI/CC 30 R14A7 PLANT VENT CHAN 7-MID RANGE GAS 6.86543-05 GOOD UCI/CC 31 R14A9 PLANT VENT CHAN 9 HIGH RANGE GAS 3.72621-03 GOOD UCI/CC 32 R15A5 AIR EJECTOR CHAN 5-LOU RANGE GAS 2.09411-07 GOOD UCI/CC 33 R15A7 AIR EJECTOR CHAN 7-MID RANGE GAS 1.34492-05 GOOD UCI/CC 34 R15A9 AIR EJECTOR CHAN 9-HI RANGE GAS 1. 27941-03 GOOD UCI/CC 35 R31 AREA 31 STEAM LINE A (SPIHG) 1.87040+00 HALM MR/MR 36 R32 AREA 32 STEAM LINE B (SPING) 1.01048.02 GOOD MR/NR 37 CVH CV HYDROGEN CONCENTRATION .0 GOOD x 38 TCV03 CV BASEMENT LVL 6 FT TEMP ¹3 95.1 GOOD DEGF 39 TCV07 CV INTERMEDIATE LVL 6 FT TEMP ¹7 106.0 GOOD DEGF 40 TCVOB CV INTERMEDIATE LVL 6 FT TEMP ¹8 106.6 GOOD DEGF 41 TCV09 CV INTERMEDIATE LVL 6 F'I TEHP ¹9 106.7 GOOD DEGF 42 TCV10 CV INTERHEDIATE LVL 6 FT TEHP ¹10 106.2 GOOD DEGF 3 TCV17 CV OPERATING LVL 6 FT TEMP ¹17 117.5 GOOD DEGF
SECTION 9.0 ONSITE RADIOLOGICALAND 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 Release Point Release Rate Ci/sec 0700- Air Ejector 1.77 E-3 (Noble Gas)* 0915 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- ARV 8.32 E-3 (Noble Gas)* 0810 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 Release Point 'elease Rate Ci/sec 0915- Air Ejector 5.24 E-1 (Noble Gas)* 0935 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- Air Ejector 6.23 E-2 (Noble Gas)* . 0955 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- Air Ejector 1.25 E-4 (Whole Body) 0915 8.75 E-7 (Child Thyroid) 0755- ARV 6.52 E-5 (Whole Body) 0810 4.56 E-7 (Child Thyroid) 0915- Air Ejector 5.34 E-3 (Whole Body) 0935 1 48 E-3 (Child Thyroid) 0936- Air Ejector 6.51 E-4 (Whole Body) 0955 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: Time: 0915-0935 hr Nuclide Curie/Sec Total Curies Released Kr-85 4.0 E-04 4.8 E-01 Kr-85m 1.3 E-02 1.7 E+01 Kr-87 1.8 E-02 2.3 E+01 Kr-88 2.1 E-02 2.5 E+01 Xe-131m 4.9 E-03 5.9 E+00 Xe-133 3.3 E-01 4.0 E+02 Xe-133m 4.9 E-02 5.9 E+01 Xe-135 4.9 E-02 5.9 E+01 Xe-135m 1.6 E-02 1.9 E+01 Xe-138 6.3 E-02 7.6 E+01 Total Noble Gas 5.2 E-01 6.3 E+02 I-131 7.8 E-05 9.3 E-02 1-1 32 1.3 E-05 1.5 E-02 I-1 33 5.4 E-05 6.3 E-02 l-1 34 8.6 E-05 1.0 E-01 1-1 35 3.1 E-05 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 4.8 E-05 5.8 E-02 Kr-85m 1.5 E-03 1.8 E+00 Kr-87 2.1 E-03 2.5 E+00 Kr-88 2.5 E-03 3.0 E+00 Xe-131m 5.8 E-04 7.0 E-01 Xe-133 3.9 E-02 4.7 E+01 Xe-133m 5.8 E-03 7.0 E+00 Xe-1 35 5.8 E-03 7.0 E+00 Xe-135m 1.9 E-03 2.3 E+00 Xe-138 7.5 E-03 9.0 E+00 Total Noble Gas 6.2 E-02 7.5 E+01 l-1 31 6.3 E-06 1.1 E-02 l-1 32 1.5 E-06 1.8 E-03 l-1 33 6.5 E-06 7.8 E-03 1-1 34 1.0 E-05 1.2 E-02 I-1 35 3.7 E-06 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 I/SEC 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 7 7 7 888889999990000 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 2 1 2 3450113401334501340134 0 0 5 5 0 0 5 0 5 0 5 0 6 5 6 0 5 0 5 0 5 0 5 0505 1 3 4 CLOCK TIME
~ 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
'I 1 1 1 1 1 1 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 UCI/GM 1.0E+02 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 RADIOLOGICALDATA MAPS
4 )\
Ooor 25 ROCHESTER GAS AHD ELEC STATZOH R'ZNNA Servtea Budding 0 D OO 0 DATE:~Kith TZME: SURVEYED BY: 0 SURVEY INST: SERZAL NUMBER: COUNTZNG ZHST: SERZAL NUMBER! (ONER: \ (, D: g o A p~ )'0 ~n I I
~
A /9 0
'a 0 ~Door 24 me~
A 0 Cl REMARKS: CI g C3 0 MR A= 0.01 mR/hr (500 dpm/100cm> ALL READZHCS ZN MR/HR UNLESS OTMERHZSE NOTED
ROCHESTER GAS AND ELECTRIC GINNA STATION SERVICE BUILDING NORTH ~...,~~-:mOO- ~<OO ~SURVEY ZNSTRUNENT: SURVEYED BY: COUNTING ZNSTRUMENT I SERIAL NUMBER: SERZAL NUMBER REMARKS: POWER: LLD: AREA SURVEYED: 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
'X J
eII I 2 IJ 2 J
~ Sj
'3. eJ IE IJ I
4 J
"Ar 2 IJ 0
I 2 cC eJ ff t Q i OR.Elbe,k.
'2 CI 2 4J I e
J eEI I'l. cj I 2 cd X 2
'2 2
4
~ READINGS ZN MRII'HR UNLESS 9-/o OTlKRIIISI NOTED
ROCHESTER GAS & ELECTR)C CORP GlNNA STAT)ON GG GC SERVICE BUILDING p~~yp Q660 8 Qt A Surveyed By: Survey Meter: Da~e: Time:
~i~i~W Serial Number: k Power:
G SMEAR INFORMATlON A= 0.01 mR/hr Instrument: Serial Number:
<500 dpm/100cm2 LLD:
Smear ¹ d m/100cm2 I 5gi A 0 h.
-I o I l I I
I Remarks:
;,;~~ ( C:(rh C 'Vv.9. '. (l
>)n-i'(.i)(~;x ' (~ - I.
I f Z 4+401 9'-// Allreadings are in mrlhr unless otherwise noted
~ ~
II ~ ~ I I a I II ~ ~ II I I Ilail 1lm illLllL~
~ ~ '
~
I I t Ig a I
~ ~ es l Illballl IllIll l
I I I ~ ~ I I II I ~ ~ stt tK I Ill 'l lm Lllllll
0 RG&E G INNA STATION TURBINE BUILDING MEZZANINE FLOOR SURVEY NAP 0700'- DATE: lCClR TLHE: HDRTH A= 0.01 mR/hr (500 dpm/100cm2 B= 0.02 mR/hr I I ~500 dpm/100cm2 A I C= 0.02 mR/hr oeee o ae4 l I ll 850 dpm/100cm2 Il il (on countertop of II sample sink) DPA~ I e en
~ 5
&lQlLSs II II ~
~
LL ll C g
0 RC& E CINNA STATION TURBINE BUILDING AEZ2ANINE 9'LOOR SURVEY NAP CR5 DATE: L;IqE:~~)
!IORTH A= 0.01 mR/hr
<500 dpm/100cm2 8= 0.80 mR/hr I
I <500 dpm/100cm2 I tT C= 0.80 mR/hr eeee o eel il II 5000 dpm/100cm2 Il il 'on countertop of A sample sink) uPNI avv A
~ ~
I II
~ A II LL Ll CH'R C g
RC&E C INNA STATION TURBINE BUILDING AEZZANENE ":LOOR SURVEY NhP NORTH A= 0.01 mR/hr
<500 dpm/100cm2 B= 0.02 mR/hr I
I <500 dpm/100cm2 eeet o eeet I C= 0.02 mR/hr 5000 dpm/100cm2 I l II (on countertop of II sample sink) B Q 0 GPN/I.QQ Ci% A
~ ~
I I I II II ~ II II ~ I
RC6 E CINNh SThTION TURBI.iE BUILDINC BhSEHENT FLOOR A= 0.05 mR/hr SURVEY KKP
<500 dpm/$ 00cm2 B= 0.02 mR/hr
<500 dpm/100cm2 NORTH a ada 0 0 OO OO G I I I
,o B DhTEi 8 ll- os Tm:~~~
POVER i BY: io A ~o ot
~
lI ~~
~~
~ ~ ~~
o~ ~~
~ ~
~ ~ ~o Ip i a.a i INSTRUMENT:
I:
~
~~ oo ~~ ~ ~
SERIhL SNEARS D?i~i/ICC Gn
~ 4 8
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 NORTH 4444 OOOO OO Q I I cW(-
QATE) (0 RX TIME'~lOO POMR! BY: iO I ~Q ~ ~ E~ t 'g
~
~~
~~
~ ~ ~~
~ ~ ~ ~
~O
~ ~
~1
~~
~ io La.a I- INSTRUMENT:
~ ~~
SERIAL 1: SMEARS DPMI'ICQ m2 i CfrEE '~ Au'
RC6E GINNh SThTION TURBINE BUILDING BhSEMENT FLOOR A= 0.01 mR/hr SURVEY NAP <500 dpm/100cm2 B= 0.80 mR/hr
<600 dpm/100cm2 NORTH oassa OO OO OO I I CA ib DhTEs IOQ Q TTHR:~CR 0 POWERs BY:
A INSTRUMENT: ~ t Q~ ~~ ~ ~ ~0 ~ ~ ~
~~ ~~ ~~
~y ~O qt ~~
SERIhL ft 2 D?M/LCC Gn I j%i~
'rr
~
.ir~
I '~ lA a a r
) wd
"-- l!>
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: / Serial ¹'s: / Power: LLD: Note: All readings are in mr/hr unless otherwise noted. No. etpmi100cm2 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)
II AtI NaQH H2S04 To AVT
. Sample Sink Tank Tank Dl Room B Ano/rrsr Rod tlonitor Control Panel A AVT 6
H20 Door Heater Desk 28 Door 67 Door 19
¹ = Smear Location -x-x- = Rad/Cont. Barrier 0 Cont. Area Radiation Level Neutron Radiation Level 0= High Cont. Area
= Contact Reading Radiation Area echnician Remarks:
I I- ("GA r k /-. I ~V .'o a'*~ i High Rad. Area BrQA:ew '. (t. -\'t ed t. ~! r').~-Q '. <<t ~~ tO Locked High Rad.. Area
R.E.GINNA'TATION ';"Co'nderisate'.,'.,:..l,'oils>In9,"-.'Bulldin'O.-'-"'.Contre'8,'; Paneal:A'rea', Date: 0 ('RW Time: CA&- 'l 450 'echnician: Inst. Type: -
/ Serial ¹'s: / Power; LLD:
Note: All readings are in mr/hr unless otherwise noted. No. dpm/100cm2 A= 0.01 mR/hr
<500 dpm/100cm2 B= 0.30 mR/hr 5000 dpm/100cm2 (on countertop of (AII (A II sample sink)
NoQH H2S04 To AVT Sample Sink Tonk Tonk Dl Room Ror trN'tet A
~ AVT Control Panel 6
H20 Door Heater 28 Door 67 Door 19
¹ = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level High Cont. Area !
c = Contact Reading I Radiation Area echnician
\
Remarks: g. 'ur.') g t' ' ~ v m t r. c. High Rad. Area M-"r~ = )C* i'.) ri 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: / Serial ¹'s: I Power: LLD: Note: All readings are in mr/hr unless otherwise noted. ellfelt'oof No. dpm/100cm2 27 Low High Condensate Condensate Waste Waste Tank Tank B D Demin 0 Dilute 0 NH4QH 0 Mixed C Demin Anion Dilute Regen NaQH B Demin Cation Dilute Regen H2SQ4 A Demin A= 0.01 mR/hr
<500 dpm/100cm2 B= 0.02 mR/hr
<500 dpm/100cm2 Smear Location -x-x- = Rad/Cont. Barrier 0 Cont. Area Radiation Level Neutron Radiation Level ps High Cont. Area c = Contact Reading r
+ Radiation Area 4.u/ /(c.
Is p=
~
echnician Remarks: ~~n-.V \ High Rad. Area
<<PIP'i
. (
I i c.,cr'N - Wtc-(C) Locked High Rad. Area
4
- .~Co'n'dinsat'8','.:Peflitifiig,'-.,'Biiildjijj';-."""-Oemineraltzer';:;Artea:::.
Technician: Date: 0 l> lime:~1k-.l rDD Inst. Type: / Serial ¹'e: I Power: Li.o: Note: All readings are in mr/hr unless otherwise noted. I>> I el 'oor No. I t I dpm/100cm2 27 Low High Condensote Condensate Waste Waste Tank Tank D Demin 0 Dilute NH40H Mixed C Demin Anion Dilute Regen NaQH A 8 Demin Cation Dilute Regen H2S04 A Demin A= 0.01 mR/hr
<500 dpm/100cm2 B= 0.80 mR/hr
<500 dpm/100cm2
¹ O = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level High Cont. Area c = Contact Reading Radiation Area echnician Remarks: Ar(r r Y~J2 High Rad. Area
)tc 0 - l~-t Locked High Rad.
Area
cv R.E.GINNA STATlON Technician: inst. Type: 0 0 0 0 QOOVI'$ -'o Date: Io I ll. Time:61co Note: All readings are ln mr/hr unless ottterwise noted .
-. i:
A= 0.01 mR/hr
<500 dPm/ 00cm2 1
-A3t) dpm/100cm2 Purge ---> (---N Containment R10A,11,12 CV Vent -->
Plant Vent ---> - - -R10B,13,14 0 0 0 0 A Purge 0 Exhaust o Fan o A 0 8 Purge Exhaust Fan ¹ = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level High Cont. Area c = Contact Reading Radiation Area Technician Remarks: High Rad. Area (tP >+i(ut = CI '(0 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 8 L A 0 Purqe t:xhoust Fan W 0 L R 0 A utjn 8 4 Sleon Purge Ooar shousT rtst 57 0 0 ChernisTrT L<O OJ. Woler-sloroge Tonk ¹ = Smear Location -x-x- = Rad/Cont. ~ Barrier Cont. Area High Cont. Area ~ Radiation Level Neutron Radiation Level i c ~ Contact Reading Radiation Area echnician Remarks: J,;~&un 4'-.,;ri- ( .)~C(C~h High Rad. Area ~Pic-i(.t)rr-k - ~'t2-t Locked High Bad.. Area R.E.GINNA STATlON '~~rdglottINSSW" STottkg~RTa'aa'iiiT)~::::L'at'rtal-,-:.". Technician: Cate: ~ Ttma: 67CO-Cert~ inst. Type: / Serial ¹'a: l pc~et. Note: All readings are in mr/hr unless otherwise noted. dpm/100cm2 A= 0.01 mR/hr B Main --'> <500 dpm/100cm2 Steam 8= 0.05 mR/hr <500 dpm/100cm2 (--N A Oi Containment A Q 0 0 A Main r W Steam --> I I I I I I I I I I I I I A Ooor 45 HHB Racttim Tonk A go Q¹ = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area r Radiation Level Neutron Radiation Level Q>> High Cont. Area c = Contact Reading + = Radiation Area , echnician Remarks: 't'Q'9 ;u~(". ( ~ t I Q High Rad. Area ~ -->0 Locked High Rad. I O Area R.EeGINNA STATlON Technician: Date: l0 'Kl I'L Tirae:gil6-0<< Q Inst. Type: / Serial ¹'a: i pew: LLD Note: All readings are ln mr/hr unless otherwise noted. No. dpm/100cm2 A= 0.01 mR/hr 8 Main <500 dpm/100cm2 Steam --> B= 3.0 mR/hr <500 dpm/100cm2 (--N lA I Containment B 0 0 A Main B c Steam --> I I I I I 000 f A 45 HHB Reottartt fora go ¹ = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level High Cont. Area c = Contact Reading \ Radiation Area echnician Remarks: 4(>>'>> ' k> l( r High Rad. Area ~(p(-'ic.uh(~i = ~ i E tb 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: / are in Serial ¹ e mr/hr unless otherwise noted. l po: LLD: Note: All readings No. dpm1100cm2 A= 0.01 mR/hr B Main rlr r <500 dpm/100cm2 Steam --> ~ C B= 0.3 mR/hr I ~ r P I>> <500 dpm/100cm2 (--N I I A Containment 0 A Main I Steam --> I I I I I I I I I I I A Door 45 NS Rectorn 1onh A Ho Q¹ = Smear Location -x-x- ~ Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level 0>> High Cont. Area c = Contact Reading + = Radiation Area echnician Remarks: Q>> High Bad. Area (t;-i 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 ---> No, dpm/100cm2 Tunnel Entry A= 0.01 mR/hr
<600 dpm/100cm2 B= 0.05 mR/hr 0 <600 dpm/100cm2
(--N Door 36 Containment Turbine 0 Driven Aux. FW ~ <
Pump--- 0 Door 37 Turbine Aux. PW-Pump Oil
)~ljlj A r i D
Tank A So~
o8 Chillers 0
0 0 Motor Driven Aux. FW Pumps -----""
0 Q¹ = Smear Location -x-x- ~ Rad/Cont. Barrier Cont. Area Radiation Level ~ Neutron Radiation Level High Cont. Area !
c = Contact Reading Radiation Area echnician Remarks: High Rad. Area
~lr=-(< '~c Qt~u(~"i< = tC-'lie Locked High Rad.
Area
i): u~2% 'pb.>'e.;:,. ',. T Q~,"'>>' 'p,> +'N~:+>: A,gj~ej+i>> ';>e '>'>r~9?~i~i~+<>>>>T>>>$>>%~)
R.E.GINNA STATlON '~'tntmtedfko. -":g~ '- .IIt aeNat"k4vof Technician:
fnst. Type: / Serial ¹'s: Power:
Note: Ail readings are in mr/hr unless othertlvise noted.
Cable ---) d pm/100cm2 Tunnel Entry A= 0.01 mR/hr 0
O (500 dpm/100cm2 B= 2.0 mR/hr 0 <500 dpm/100cm2 Door 36 A Containment B)O Turbine 0 Driven Aux. FW ~ ~
Pump--- 0 0
OO
~c+
~
Door 37
>".,".'7w - >~DO A D So 3 o8 C hitters 0
0 0 Motor Driven Aux FW Pumps-------
0
¹ I
= Smear Location -x-x- ~ Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level High Cont. Area c ~ Contact Reading Radiation Area echnician Remarks:
A
>M'l9 t'<-.. i'r v vG Cc. High Rad. Area k)c',i:s = C'i F -to Locked High Rad.
Area
R.E.GINNA STATKRI , hitarinadhte-: BiiMa9:.:: South;"- MezxeHns k.evel A= 0.01 mRlhr oats: tCIst t'L Time:~aCr- t/tao
<500 dpm/100cm2 Serial ¹'s: / Power: LLO:
Note: All readings are in mr/hr unless otherwise noted.
Door Door No. dpm/100cm2 45 46 Door 65 Control Point Sign-in
/
Desk Containment Nuclear j Sample j Room I
Passbos Nuclear Sample Shed HEPA Fitters Door 503
,Q¹ = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level s Neutron Radiation Level High Cont. Area I¹'c = Contact Reading Radiation Area Techniclan Remarks: t4 v~ t' tv'- Aha (C4 High Rad. Area
'two "- (C.-'l i r -.
r,a. = C l ~ - l 0 Locked High Rad.
Area
A=0.1 mR/hr ",;fnrtefinadfati'-',BiiMiij.'.,S{iuth;:=Mezz~I Lese}.
<500 dpm/100cm2
'-'R/hr Date: l0 'Rl i%Time: 455 lul roc LLD:to+
B=10 Serial ¹'s: / Power:
<500 dpm/100cm2 (hr unless otherwise noted. Crol((
Ooor Ooor ND. dpm/100cm2 45 46 Ooor 65 Control Point Sign-in
/
Oesk Containment Nuclear l Somple l'oom r
I Passbox Nucleor Sample Shed HEPA Fillers Ooor 503
- Qar = Smear Location -x-x- = Rad/Cont. Barrier 0 Cont. Area Radiation Level ! Neutron Radiation Level Q>> High Cont. Area
'¹c = Contact Reading + Radiation Area Technician Remarks:
8>"- Lt t 'g'Ag (ut~ t >G cc 8= High Rad. Area
=((~-tO + Locked High Bad.
Area
R.E.GINNA STATION 'ntermidiats SiRdln9 South', - Basement'evei A= 0.01 IR/hr Date: lb I L Time:~b~oO l/00
<500 dpm/100cm2 Serial ¹'s: / Power: LLD:
Note: A/I readings are m mr/hr unless otherwise noted. Q Quot tgVt No. dpm/100cm2 Ooor 38 To Hot Shop <---
1A Hydrogen Recombiner Laundry Panels Tanks Containment Chemical Drain Tank H PA Chas cad/
Spenl Fuel Pil, Conlrolled Access Fans i Skimmer Filler 8
e 0
I
= Smear Location -x-x- = Rad/Cont. Barrier 4 Cont. Area
,(Q¹ l~ = Radiation Level Neutron Radiation Level 0= High Cont. Area c = Contact Reading Radiation Area echnician Remarks: I <<t r lr <<w( High Rad. Area c u +i t'~c'.Z = Zt -'tb Locked High Rad.
Area
" A.
A=0.1 mR/hr fntermediati; Rdh8ns- South. - Basernera'evel
<500 dpm/1 00cm2 B=100 mR/hr Date: lO l~ Time:~ASS IA opRr~ rort Serial ¹'s: /
<600 dpm/100t:m2 Ihr unless otherwise noted.
No. dpm/100cm2 Ooor 38 To Hot Shop <---
lA Hydrogen Recombiner l.aundry Tanks A IB Panels Containment Chemical Orain Tank H PA iilrr A
sop Spent Fuel Pit Controlled Access Fans I Skimmer Filler A 6
= Smear Location -x-x- = Rad/Cont. Barrier 4 Cont. Area
,V+¹
! = Radiation Level Neutron Radiation Level 0= High Cont. Area Contact Reading echnician Remarks: ( . +
0=
Radiation Area High Rad. Area 4t F- (t, ~uc ice hc = (tC - t Locked High Rad.
Area
e R.E.GINNA STATION min'ated; Storage BuBdine Technician: Date: 9'L Time:QlQQ - 4tDI-I inst. Type: Serial ¹'s: / Power: LLD:
Note: All readings are in mr/hr unless otherwise noted.
No. dpm/100cm2 A= 0.05 mR/hr
<500 dpm/100cm2 Door 6l0 Slorage Racks Art>>stoa I SA LSA R ~
0 I
Slorage Racks L RCP Molor v l P
0 0
R I
X- X- X o I I
X Oecon Areo Slorage Racks I I Smear Location -x-x- = Rad/Cont. Sarrier 4 Cont. Area Radiation Level Neutron Radiation Level 0= High Cont. Area
'c = Contact Reading Radiation Area echnician Remarks: ~Ci cc High Rad. Area
-.x =()-:-'t'i Pr t >tC.< hD> - ~l Cr 3~ 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.
No. dpm/100cm2 A= 0.10 mR/hr
<500 dpm/100cm2 R-18 8 I I X X I
-- --x--x-- --r--r--- Spent Fuel Pit X I C I I X X r Oecon Pit A I I X
I T X I
X I
X W X X HEPA I I I A X X Filters I I
I I I X X X Drain K I I Q X X
X X I
X I
X ~
Bridqe x
CRS
'ro sre .m I Transfer Canal
~sor i- .. .- ..
~sop New rvet Storaqe Areo I
Smear Location -x-x- = Rad/Cont. Barrier Cont. Area l
Radiation Level Neutron Radiation Level 0= High Cont. Area
¹c = Contact Reading Radiation Area
'e chnlcian Remarks. h,~4 -c; . High Rad. Area Ct Locked High Rad.
Area 9-3B
R.E.GINNA STATlON .;:.:..Ru88ary Sultry,,OPerat@g,'k;ever - Nest End A= 0.50 mR/hr
<500 dpm/100cm2 Date: lO 8 L Time: CQCO- (400 Serial ¹'e: I Power: LLD:
Note: All readings are in mr/hr unless otherwise noted.
No. 'pm/100crnR New Fuel Storage Door 29 CV Penetrolion ron A
Og 0
0 C
C W
H 0 RWST 0
0 o
OO Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level 0= High Cont. Area
¹c = Contact Reading + Radiation Area Technician Remarks: 'Cr C'ri'D ,'~C (c~h 6= High Rad. Area t
f~ C >~-tG + 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 Serial ¹'a:
l Time:e7ee-
/
gee Power: LLD, Note: All readings are in mr/hr unless otherwise noted.
No. ~ dpm/100cm2 qQhler A
CVCS A
8
~
CVCS
~ i
~ >
~ >
C i~~
X X X X X I
x I
X CVCS RWST A wGC Room An
- Q> = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level 00= High Cont. Area
¹c = Contact Reading Radiation Area Technician Remarks: High Rad. Area
'k':z = Z't ~- t, k Locked High Rad.
Area
I R.E'GINNA STATlON :;,';AUXIN~ BUffcQAQ. 88$ 8ntent: LevEA'.@fest- End
-A= 0.10 mR/hr Date: 1 't>K Time:gQd- IGLOO
<500 dpm/100cm2 Serial ¹'s: / Power: LLD:
Note: All readings are in mr/hr unless otherwise noted.
Art(B SFP PUMPS Na.. dpm/100cm2 A
-- Ad(B RHR Fans CVCS X X e e te
. I QA 8
CVCS 8 E
A x
Qa C
CVCS RWST R E ter E
C A Xt Lx-x-GS PIIP FK i~
- (¹+ = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level High Cont. Area
~/
I ¹c = Contact Reading r Radiation Area Technician Remarks: A'crxv Ar siv ir<<C'e% High Rad. Area Ql tA&t( v .< Ti tne:Q7gD t+DO Serial ¹'s: / Power: LLD:
Note: All readings are in mr/hr unless otherwise noted.
~VV RWST ttpm/100cm2 I I 0
A A
I;g) ggQ xlot Monitor Tonk x
I B
li'; 0 Bus 14 Door I 26 1
B Monitor Tonk A Aux. Bldg.
Supply A/H Unit RMWT ooooo 0
0 Q
~ erettte riroeesstno p p A
BAST 8
8A BAST Resin rater liner g ner 0
B A rretisems p ~ 0 Door 28 Door 27
'~+¹ = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area Radiation Level Neutron Radiation Level High Cont. Area i¹c = Contact Reading Radiation Area Technician
'I, Remarks: / >~iK rM &C l CC. High Rad. Area Zll--ttt Mt( Locked High Rad.
c cJ= Area
R E.GINNA STATtON AuxiHary::.SiiHdlrTS'fat8rmetHate,.Levd: - past aid A= 0.10 mR/hr C.
Date: 'IQl 6 Ttrne:~QQOQ- (QOQ (500 dpmI100cm2 Serial ¹'s: / Power: LLD.
Note: All readings are in mr/hr unless otherwise noted.
No. 'pm/100cm2 RWST 44 Bus 16 A
A GPT I
~ oo G B
GPT
.'0 Charcaaf/HERA riller A
C GPT p
, GOT 0 A SDP ooOo RC Pl Vault filler VCT Lo O CHT A
r
";¹ ) = Smear Location -x-x- = Rad/Cont. Barrier Cont. Area I
Radiation Level Neutron Radiation l.evel High Cont. Area c = Contact Reading Radiation Area Fechnician Remarks: Ah ~C; 1c~t High Rad. Area Ktwa.= ~lE-lK <~ >>((<r t = (l f=- lo l.ocked High Rad,:.
Area
R.E.GIKNA STATloN 'Auxlli~"BQQdjnQ>'. 80$ 8Ntnf, Levg-A= 0.10 mR/hr Date: LO .L Time: CQ~-
4500 dpm1100cm2 ¹'s: b5(5'erial
/ Power: LLp, Note: All readings are in mr/hr unless otherwise noted.
Np dpm/100cm2 St Pumps CS Pumps A a
~~~~~
~e~e~
e gQQA WHUr Pomp
~ eee ~
~e~~~
BR Ec WO miami, Waste Non-regen Holdup Tank I
X A Hx I
X I=.,
Xjoe't A+9 Chorging 0 Pump 0 Cooling 0 Fans Sepr Retien t
WEFT Oo rn ~
4 Spent Resin Tank Room Sur e Tank
~ 4 NaoH 8
~ L R 'I e ~ e t:0
~
rr 0 Cl;
~ ou T.
R Chorging Pump Room ~l
'.¹ ~ Smear Location -x-x- = Rad/Cont. Barrier 0 Cont. Area i
Radiation Level Neutron Radiation Level 00= High Cont. Area
'¹c = Contact Reading Radiation Area Te chntctan Remarks. 7~! 0 c <hit 5 VG /CCh High Rad. Area
~Dire = - Z iC-tO I
Locked High Rad.
Area
0 R.E.GINNA STATION -':. Auxlllacy~ByQdfii9;.':BiWfliBAfLeveIr A=0.1 mR/hr
<500 dpm/100cm2 Date: (0 Time: O'QQ--.',f ggg B=100 mR/hr Serial ¹'s: / Power: LLQ.
r/hr unless otherwise noted.
<500 dpm/100cm2 dpml1OOcm2 Sl Pumps CS Pumps GA A A
~~~~~
~ ~ ~~~
~A wHUT Run p O 0 ~~~~~
~>>~ ~~
X j BR
~ ~~~>> 8 Imii c wp ~~~ ~~
Waste xt ' Non-regen Holdup Tonk X A Hx I
X WE XI 4 ArttIT Alc gJ
'l Charging 0
0 Pump Cooling Q~
0 Fans Sect Return Oo Xt
~
~
~
B 8 Spent Resin Tank Room Sur e Tank NOOH 8
~ tR
~
t:0 N a 4pu E
R Charging Pump Room I~ =
't~¹ Smear Location -x-x- = Rad/Cont. ~ Barrier Cont. Area Radiation Level Neutron Radiation Level Q>> High Cont. Area
'¹c = Contact Reading r + Radiation Area
~ ~
Te chntctan Remarks.
've = (ll=-((
Y&wrrr&
t(t.)t cX' Alibi a tr-fr>>Ci r Ch 0= High Rad. Area
. Locked High Rad.
Area
SECTION 9.3 IN.-PLANT AND POST-ACCIDENT SAMPLING RESULTS
TABLE 9.2A REACTOR COOLANT SYSTEM Radioactive Gasses and lodines (Collection between 07:00 - 09:15)
Concentration (pCi/gm)
Nuclide Corrected to time of Shutdown Kr-85m 2.88E-02 Kr-87 4.02E-02 Kr-88 4.66E-02 Xe-133 '.51E-01 Xe-135 1.10E-01 Xe-135m 3.72E-02 Xe-138 1.43E-01 Rb-88 2.62E-02 Gas Total 1.16E+00 1-1 31 3.20E-02 1-1 32 1.05E-01 l-1 33 4.18E-02 l-134 1.51E-01 1-135 7.55E-02 iodine Total 4.05E1 I-131 Dose Equivalent 4.7E-02
TABLE 9.2B REACTOR COOLANT SYSTEM Radioactive Gasses and lodines (Collection between 09:16 - 14:00)
RCS Gas Sample Concentration (pCi/gm)
Nuclide Corrected to time of Shutdown Kr-85m 2.88E-01 Kr-87 4.02E-01 Kr-88 4.66E-01 Xe-133 7.51E+00 Xe-135 1.10E+00 Xe-135m 3.72E-01 Xe-138 1.43E+00 Rb-88 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 Concentration (pCi/gm)
Nuclide Corrected to time of Shutdown I-1 31 2.72E-01 I-1 32 1.76E-01 I-1 33 1.65E-01 1-134 1.51E-01 I-135 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 STEAM GENERATOR (Collection between 07:00 - 09:15)
Concentration (pCi/gm)
Nuclide Corrected to time of Shutdown eIAee ~ I Bee I-131 3.78E-05 1.62E-07 I-132 1.35E-05 6.33E-07 l-133 4.65E-05 1.03E-06 I-134 1.56E-04 5.85E-07 I-135 8.73E-05 1.22E-06 Cs-134 3.27E-06 4.64E-08 Cs-137 2.96E-06 7.20E-08 TOTAL ACTIVITY 3.47E-04 3.75E-06 Sample Dose Rates (based upon 3500cc sample)
I IAII II 8 II 1 meter <0.01 mR/hr <0.01 mR/hr 1 foot <0.01 mR/hr <0.01 mR/hr On contact 5.83 mR/hr <0.01 mR/hr
TABLE 9.3B STEAM GENERATOR (Collection between 09:16 - 13:00)
Concentration (pCi/gm)
Nuclide Corrected to time of Shutdown
~
I All IlBl ~
I-131 2.8E-02 5.93E-05 I-132 1.8E-02 5.38E-06 I-134 1.7E-02 2.56E-05 I-1 35 1.5E-02 Cs-1 34 1.5E-02 3.13E-06 Cs-1 37 2.9E-04 1.87E-05 TOTAL ACTIVITY 9.33E<2 1.12E-04 Sample Dose Rates (based upon 1000cc sample)
I IAII IIBII 1 meter 0.045 mR/hr <0.01 mR/hr 1 foot 0.56 mR/hr <0.01 mR/hr On contact 449 mR/hr 0.538 mR/hr
TABLE 9.4A AIR EJECTOR (Sample collection between 07:00 - 09:15)
Concentration (pCi/gm)
Nuclide Corrected to time of Shutdown Kr-85m 5.59E-03 Kr-87 5.26E-03 Kr-88 9.21E-03 Xe-131m 1.38E-02 Xe-133 9.87E-02 Xe-133m 2.40E-03 Xe-135 3.95E-02 Xe-135m 6.25E-03 Xe-138 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)
Concentration (pCi/gm)
Nuclide Corrected to time of Shutdown Kr-85 3.72E-02 Kr-85m 1.18E+00 Kr-87 5.06E-01 Kr-88 1.91E+00 Xe-131m 4.53E-01 Xe-133 3.96E+01 Xe-133m 4.76E+00 Xe-135 4.73E+00 Xe-135m 'I.73E+00 Xe-138 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)
Concentration (pCi/gm)
Nuclide Corrected to time of Shutdown Kr-85'r-85m 4.87E-03 1.55E-01 Kr-87 6.62E-02 Kr-88 2.50E-01 .
Xe-131m 5.93E-02 Xe-133 4.03E+00 Xe-133m 5.97E-01 Xe-135 5.93E-01 Xe-135m 2.00E-01 Xe-138 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)
Concentration (pCi/gm)
Nuclide Corrected to time of Shutdown Kr-85'r-85m 1.92E-09 6.10E-08 Kr-87 2.61E-08 Kr-88 9.85E-08 Xe-131m 2.34E-08 Xe-133 1.59E-06 Xe-133m 2.35E-07 Xe-135 2.34E-07 Xe-135m 2.20E-07 Xe-138 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 CONTAINNlENTHYDROGEN CONCENTRATION Time H dro en VOL.%
06:30-1 4:00 0.0 TABLE 9.7 Reactor Cooiant S stem RCS and Containment Sum Boron/ H Data
~Sam le Time m Boron pH RCS 06:45-09:15 571 6.8 RCS 09:16-09:30 2097 5.1 RCS 09:31-14:00 2207 4.7 Sump 06:45-1 4:00 < 10. 7.5
TABLE 9.8 CONTINUOUS AIR MONITOR READINGS IN AUXILIARYBUILDING (READINGS IN COUNTS. PER MINUTE) 0630-1130 hrs: GAS IODINE PARTICULATE TOP FLOOR 50 100 100 INTERMEDIATE FLOOR 50 100 100 BASEMENT FLOOR 100 200 200 09:16 - 10:00 hrs:
TOP FLOOR 100 200 200 INTERMEDIATE FLOOR 50 100 100 BASEMENT FLOOR 100 200 200 10:01 - 14:00 hrs:
TOP FLOOR 50 200 200 INTERMEDIATE FLOOR 50 100 100 BASEMENT FLOOR 100 200 200
TABLE 9.9 AIR SAMPLE RESULTS IN TSC AND CONTROL ROOM (Readings in Counts per Minute) 07:00 - 09:15 hrs: IODINE PARTICULATE BACKGROUND TSC 50 50 50 CONTROL ROOM 50 50 50 09:16 - 10:00 hrs:
TSC 80 50 50 CONTROL ROOM 80 50 50 10:01 - 14:00 hrs:
TSC 50 50 50 CONTROL ROOM 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
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I
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~
I "5 ZS Aal, ~ Ia 2'5 15 I CQ WS'Ch M &2SCALE 1:Ipp ppp H / OI/OOOO/oiS I k+OICI(h Ileo Iloe ICO O
//Og O25 COO$ 0 ICO 15I 225 Ila INOO~~ IO CO I I ON lOCO 20 ON 0 CO
%UZI'
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 NATIONALWEATHER 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 AVERAGE UNIT CODE STDDEV MIN SPD 33A 3.6 MPH 0.9 2.8 7.0 SPD 33B 3 ' MPH 0.8 2-3 6.8 SPD 150A 4.5 MPH 0.9 2 ' 6.9 SPD 150B 57.1 MPH 0.0 57.0 57.2 SPD 250 7' MPH 0.4 13 ' 15.1 DIR 33A 197.0 DEG 9.0 178.0 232.0 DIR 33B 196. 0 DEG 9.0 179.0 225.0 DIR150A 174.0 DEG 3.0 166.0 183.0 DIR150B 56.0 DEG 0.0 55.0 57.0 DIR250 198. 0 DEG 10.0 174.0 230.0 "ER 33A 48.8 TER 33B 48.7 TER150A 49.2 TER150B 51.4 TER250A 55.2 DT150-33A 2.6 F/
DT150-33B 2.4 F/
DT250-33A 6.5 F/
DT250-33B 6.0 F/ 0 PRECIPITATION 1.08 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 MPH 0.9 2.8 7.0 SPD 33B MPH 0 0.8 2-3 6.8 SPD 150A MPH 0 ~0. 2 ' 6.9 SPD 150B 57. 1 MPH 0 0.0 57.0 57.2 SPD 250 6.1 MPH p~4 13-2 15.1 DIR 33A 209. 0 DEG 0 11. 0 183.0 247.0 DIR 33B 195.0 DEG 7.0 197. 0 295.0 DIR150A 174.0 DEG 0 3.0 166.0 183.0 DIR150B 56.0 DEG 0 0. 0 55.0 57. 0 DIR250 188.0 DEG 9.0 184. 0 230. 0 TER 33A 52.9 0 i'ER 33B 53.3 0 TER150A F TER150B 53.6 TER250A 55.4 DT150-33A 5.0 F/
DT150-33B 3.0 F/
DT250-33A 2.5 F/ p DT250-33B "2.0 F/ 0 PRECIPITATION 1.08 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 CODE STDDEV MIN SPD 33A 3.8 MPH 0.9 2.8 7.0 SPD 33B 3.9 MPH 0.8 2 ' 6.8 SPD 150A 4;8 MPH 0.9 2 ' 6.9 SPD 150B 57. 1 MPH 0.0 57.0 57.2 SPD 250 7' MPH 0.4 13-2 15.1 DIR 33A 193.0 DEG 9.0 172. 0 229.0 DIR 33B 197.0 DEG 7.0 197.0 295.0 DIR150A 184.0 DEG 3.0 166.0 183.0 DIR150B 56.0 DEG 0. 0 55.0 57. 0 DIR250 188.0 DEG 1. 0 154. 0 160. 0 ER 33A 52. 9 TER 33B 53. 3 TER150A 53. 3 TER150B 53.6 TER250A 55.5 DT150-33A 0.4 F/
DT150-33B 0.3 F/
DT250-33A 2.5 F/ 0 DT250-33B 2-3 F/ 0 PRECIPITATION 1.08 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 AVERAGE CODE STDDEV MIN SPD 33A 3 ' MPH 2.8 7.0 SPD 33B 3 ' MPH 0.8 2-3 6.8 SPD 150A 4.5 MPH 0.9 2 ' 6.9 SPD 150B 57. 1 MPH 0.0 57. 0 57.2 SPD 250 7 ' MPH 0.4 13-2 15.1 DIR 33A 202.0 DEG 9.0 172.0 229.0
'DIR 33B 195.0 DEG 7.0 197.0 295.0 DIR150A 174.0 DEG 3.0 166.0 183.0 DIR150B 56.0 DEG 0.0 55. 0 57. 0 DIR250 158. 0 'DEG 1.0 154.0 160.0 ZER 33A 53.0 TER 33B 53.1 0 TER150A 53.4 TER150B 53.5 TER250A 55.5 DT150-33A 0.4 F/
DT150-33B 0.5 F/
DT250-33A 2.5 F/ 0 DT250-33B 2 ' F/ 0 PRECIPITATION 1.08 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 AVERAGE UNIT CODE STDDEV MIN SPD 33A MPH 0.9 2.8 7.0
.SPD 33B MPH 0 0.8 2-3 6.8 SPD 150A MPH 0.9 2 ' 6.9 SPD 150B 57 1F MPH 0.0 57.0 57.2 SPD 250 7 ' MPH 0.4 13 ' 15.1 DIR 33A 215 ' DEG 11.0 184.0 242.0 DIR 33B 198.0 DEG 11.0 197.0 255.0 DIR150A 201. 0 DEG 13. 0 175. 0 238.0 DIR150B 56.0 DEG 0.0 55.0 57.0 DIR250 158.0 DEG 1.0 154. 0 160.0 x'ER 33A 53. 5 TER 33B 53.7 TER150A 53.5 TER150B 53.6 TER250A 55.6 DT150-33A 0.0 F/
DT150-33B 0.0 F/
DT250-33A 2-1 F/ 0 DT250-33B 1.9 F/ 0 PRECIPITATION 1.08 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 3.6 MPH 0 0.9 2.8 7.0 SPD 33B 3.5 MPH 0 0.8 2 ' 6.8 SPD 150A 4.7 MPH 0 0.9 2 ' 6.9 SPD 150B 57 ' MPH 0.0 57. 0 57.2 SPD 250 F 1 MPH 0.4 13. 2 15. 1 DIR 33A 222.0 DEG 13. 0 186. 0 268.0 DIR 33B 230.0 DEG 0 7.0 197.0 295.0 DIR150A 202.0 DEG 0 3.0 179.0 230.0 DIR150B 56. 0 DEG 0. 0 55.0 57.0 DIR250 168. 0 DEG 0 3.0 154. 0 180. 0 TER 33A 57.7 ER 33B 57.7 TER150A 57. 9 0 TER150B 57. 9 0 TER250A 58.0 DT150-33A 0.2 F/
DT150-33B 0.2 F/
DT250-33A 0.3 F/ 0 DT250-33B 0.1 F/ 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 3.6 MPH 0.9 2.8 7.0 SPD 33B 3 ' MPH 0.8 2-3 6.8 SPD 150A 4.5 MPH 0.9 2-7 6.9 SPD 150B 57 ' MPH 0.0 57.0 57.2 SPD 250 F 1 MPH 0.4 13 ' 15.1 DIR 33A 194.0 DEG 9.0 172.0 229. 0 DIR 33B 195.0 DEG 7.0 197.0 295.0 DIR150A 174.0 DEG 3.0 166.0 183.0 DIR150B 56.0 DEG 0. 0 55.0 57. 0 DIR250 158.0 DEG 1.0 154. 0 160.0
'ER 33A 58.7 TER 33B 58.7 TER150A 57.9 TER150B 58.1 TER250A 58.0 DT150-33A 0.8 F/
DT150-33B 0.8 F/
DT250-33A -0. 7 F/ 0 DT250-33B -0.7 F/ 0 PRECIPITATION 1.08 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 AVERAGE CODE STDDEV MIN SPD 33A 2 ' MPH 3.0 9.7 SPD 33B 2.5 MPH 0.9 3-7 8.7 SPD 150A 3 ' MPH 2.0 3.0 11.0 SPD 150B 57.2 MPH 0.0 57.1 57.2 SPD 250 3.5 -
MPH 3.0 12 ' 14.4 DIR 33A 47.0 DEG 3.0 ~08. 0 312.0 DIR 33B 42. 0 DEG 8.0 110.0 300.0 DIR150A 65.0 DEG 14. 0 5.0 153.0 DIR150B 55.0 DEG 0.0 54. 0 56.0 DIR250 64. 0 DEG 3.0 15. 0 141.0 z'ER 33A 59.6 TER 33B 59.6 TER150A 58.8 TER150B 58.8 TER250A 58.9 DT150-33A 0.8 F/
DT150-33B 0.8 F/
DT250-33A -0.7 F/
DT250-33B -0.7 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 AVERAGE UNIT CODE STDDEV MIN SPD 33A 3.8 MPH 0.8 2-3 7-7 SPD 33B MPH 0;9 2.6 7 '
SPD 150A MPH 1.0 2 ' 7.5 SPD 150B 57.2 MPH 0.0 57.1 57.3 SPD 250 7' MPH 0.9 8.6 13.6 DIR 33A 79.0 DEG 15. 0 44.0 118. 0 DIR 33B 82.0 DEG 14. 0 40.0 128.0 DIR150A 85.0 DEG 6.0 145.0 178.0 DIR150B 56. 0 DEG "0.0 55.0 56.0 DIR250 79.0 DEG 3.0 144 0~ 167. 0 TER 33A 59.8 ZER 33B 59.8 TER150A 59.4 TER150B 59.4 TER250A 59.0 DT150-33A -0.4 F/
DT150-33B -0. 4 F/
DT250-33A -0.8 F/
DT250-33B -0.8 F/ 0 PRECIPITATION 1.08 '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 CODE STDDEV MIN MAX SPD 33A F 1 MPH 0.9 2.9 7 '
SPD 33B 3 ' MPH 0.7 3.4 6.8 SPD 150A 5.2 MPH 0.7 3.4 6.9 SPD 150B 57 ' MPH 0.0 57.2 57.4 SPD 250 9.5 1.0 ~6. 11-1 DIR 33A 52.0 DEG 3.0 35. 0 126.0 DIR 33B 54 ~ 0 DEG 4.0 30.0 130. 0 DIR150A 55.0 DEG 3.0 36.0 121. 0 DIR150B 56.5 DEG 0.0 54. 0 56. 0 DIR250 57.0 DEG 5.0 35.0 129.0 TER 33A 59.9 j.'ER 33B 59.9 TER150A 59.9 0 TER150B 59.9 0 TER250A 59. 3 DT150-33A 0.0 F/
DT150-33B 0.0 F/
DT250-33A '0.6 F/
DT250-33B 0.6 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 09:15 RECORD NUMBER 3984 RG&E GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN SPD 33A 3.8 MPH 0 1.0 2.0 7 '
SPD 33B 3.8 MPH 0 1.0 2 ' 7-1 SPD 150A 4.9 MPH 0 1.0 2-2 7 '
SPD 150B 57.3 MPH 0 0.0 57.2 57.4 SPD 250 7 ' MPH 1~1 4.5 9.8 DIR 33A 50.0 DEG 19. 0 10. 0 96.0 DIR 33B 51.4 DEG 18. 0 10. 0 93.0 DIR150A 52.0 DEG 10. 0 11.0 90. 0 DIR150B 53.0 DEG 0.0 54.0 56.0 DIR250 54.0 DEG 8.0 135.0 178.0
'VER 33A 60.7 TER 33B 61.2 TER150A 60.7 TER150B 60.7 TER250A 60.7 DT150-33A 0.0 F/
DT150-33B 0.0 F/, ~ 0 DT250-33A 0.0 F/
DT250-33B 0.5 F/ 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 09:30 RECORD NUMBER 3985 RG&E GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A 4.1 MPH 1' 2-2 7.6 SPD 33B 4.2 MPH 0 1~1 2 ' 7 '
SPD 150A 5.1 MPH 1~3 2 ' 7.5 SPD 150B 57. 0 MPH 0 0.4 56.3 57.4 SPD 250 7.4 MPH 1.5 3 ' 10.7 DIR 33A 50. 4 DEG 9.0 55.0 291. 0 DIR 33B 51.0 DEG 14.0 35.0 319. 0 DIR150A 49. 0 DEG 0 14. 0 174.0 311.0 DIR150B 52.0 DEG 5. 0 54. 0 69. 0 DIR250 55.0 DEG 0 16. 0 166.0 282.0
'PER 33A 60. 7 ER 33B 60.7 TER150A 60.3 0 TER150B 60.3 TER250A 60.6 DT150-33A 0.4 F/
DT150-33B 0.4 F/ 0 DT250-33A 0.0 F/ 0 DT250-33B 0.1 F/ 0 PRECIPITATION 1.08 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 AVERAGE UNIT CODE 8TDDEV MIN SPD 33A 4.9 MPH 0, 1~3 0.6 8.3 SPD 33B 4.8 MPH 1-2 2.0 8.2 SPD 150A 4.8 MPH 1' 1.9 8.3 SPD 150B 5.7 0.1 56.3 56.9 MPH'PH SPD 250 6.9 1-2 3.6 9.5 DIR 33A 49.0 DEG 17.0 97.0 334. 0 DIR 33B 49.9 DEG 14. 0 52.0 333.0 DIR150A 55.0 DEG 11.0 68.0 8.0 DIR150B 56.0 .DEG 3.0 57.0 68.0 DIR250 54. 0 DEG 10.0 163.0 355.0
~ER 33A 61. 3 TER 33B 61.6 TER150A 62. 0 TER150B 62. 0 TER250A 61.3 DT150-33A 0.7 F/
DT150-33B 0.7 F/
DT250-33A 0.0 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 AV 10/8/92 10:00 RECORD NUMBER 3987 RG&E GINNA PLANT SENSOR NAME AVERAGE CODE STDDEV, ~MI SPD 33A 5.0 0 1.4 2.5 9.1 SPD 33B 5~1 0 1.5 2.4 9.0 SPD 150A 5.2 MPH 1.5 2.5 9.1 SPD 150B 57.0 MPH 0 0.0 56.9 57.1 SPD 250 6.1 MPH 2.0 11.0 96.0 DIR 33A 55.0 DEG 0 13. 0 40.0 135.0 DIR 33B 58.0 DEG 14. 0 35.0 146.0 DIR150A 61 ' DEG 13. 0 42.0 137.0 DIR150B 65.0 DEG 0. 1.0 53.0 57.0 DIR250 69. 0 DEG 0 12.0 46.0 134.0 TER 33A 61.3 0 TER 33B 61.7 0 TER150A 62.5 TER150B 62.6 TER250A 61. 4 DT150-33A 1 ' F/
DT150-33B 1-3 F/ 0 DT250-33A 0.1 F/
DT250-33B 0.4 F/
PRECIPITATION 1.08 INCH 0 0;00 0.00 0.00
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 4.9 0 1.4 0.6 6.9 SPD 33B 4 ' MPH ~4 0.5 6.6 SPD 150A 4.8 MPH 1 ' 0.6 6.4 SPD 150B 51.1 MPH 0.0 57.0 57. 1 SPD 250 6.6 MPH 1.8 1.0 9.1 DIR 33A 80.0 DEG 14.0 30. 0 141.0 DIR 33B 81.0 DEG 13.0 31. 0 146.0 DIR150A 72.0 DEG 12. 0 32.0 139.0 DIR150B' 54.0 DEG 0.0 53.0 55.0 DIR250 77.0 DEG 10.0 54.0 128.0 TER 33A 61.3 ER 33B 61.3 TER150A 62. 0 TER150B 62.3 TER250A 63.3 F DT150-33A 0.7 F/
DT150-33B 2.0 F/
DT250-33A 2.0 F/
DT250-33B 2-1 F/ 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 10: 30 RECORD NUMBER 3989 RG&E GINNA PLANT SENSOR NAME AVERAGE CODE STDDEV MZN 'AX SPD 33A 4.8 MPH 1-3 6.9 SPD 33B 4.9 MPH 1 3 1.4 7.9 SPD 150A 7.9 MPH 1 ' 5.0 9.0 SPD 150B 57.+ 0.0 57.0 57.2 SPD 250 7.8 MPH 0.5 0.8 9.2 DIR 33A 81.0 DEG 12.0 41.0 140.0 DIR 33B 79.0 DEG 13.0 37.0 . 148.0 DIR150A 86. 0 DEG 16.0 39.0 162.0 DIR150B 53.0 DEG 0.0 53.0 54. 0 DIR250 89.0 DEG 14.0 27.0 156.0 r
TER 33A 61. 3 x'ER 33B 61. 3 TER150A 62.2 TER150B 62.2 TER250A 63.0 DT150-33A 1.0 F/
DT150-33B 1~1 F/
DT250-33A 2 ' F/
DT250-33B 2 ' 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 AVERAGE UNIT CODE STDDRV MIN SPD 33A 5.2 MPH 1.0 2.8 8.5 SPD 33B 6.2 MPH 1' F 1 9 '
SPD 150A 5.5 MPH 0 1' 2.5 9.0 SPD 150B 57.2 MPH 0.0 57.1 57.2 SPD 250 5.1 MPH 1' 2.4 8.2 DIR 33A 79.0 DEG 14.0 36. 0 127. 0 DIR 33B 77.0 DEG 12. 0 35. 0 139. 0 DIR150A 79.0 DEG 9.0 48.0 122. 0 DIR150B 53.0 DEG 0.0 52.0 54. 0 DIR250 77.0 DEG 11.0 32.0 144.0 TER 33A 61.4 ZER 33B 61.4 TER150A 62.5 TER150B 62.4 TER250A 63.5 DT150-33A F/
DT150-33B 1.0 F/
DT250-33A F 1 F/ 0 DT250-33B 2-1 F/ 0 PRECIPITATION 1.08 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 4.8 MPH 0 1.4 1 ' 7.4 SPD 33B 5' MPH 0 1.4 1.5 7.6 SPD 150A 2.8 MPH 1.6 1.6 6.0 SPD 150B 57.2 MPH 0.0 57.1 57.2 SPD 250 5.1 MPH 0 1' 2.4 8.2 DIR 33A 79 ' DEG 28.0 130. 0 DIR 33B 80.0 DEG 0 14. 0 39.0 153.0 DIR150A 79.0 DEG 0 14. 0 26. 0 111. 0 DIR150B 33.0 DEG 0 0.0 52. 0 54. 0 DIR250 77.0 DEG 11.0 32.0 144.0 TER 33A 62.4 0 ER 33B 62.4 TER150A 63.3 0 TER150B 63.3 0 TER250A 64. 9 DT150-33A 0.9 F/
DT150-33B 0.9 F/ 0 DT250-33A 2.4 F/
DT250-33B 2.5 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 11:15 RECORD NUMBER 3992 RG&E GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN MAX SPD 33A MPH 2.4 10.0 SPD 33B MPH 1~3 F 1 9.4 SPD 150A MPH 1-3 2-2 9.5 SPD 150B 57 ' MPH 0.0 57. 1 57.3 SPD 250 6.8 MPH 1~1 3.8 9.3 DIR 33A 80.0 DEG 14. 0 37.0 144.0 DIR 33B 82.0 DEG 13.0 41.0 DIR150A 81.0 DEG 13.0 39.0 133.0 120.0'R DIR150B 78.0 DEG 0. 0 42.0 134.0 DIR250 69. 0 DEG 11. 0 32.0 129.0 TER 33A 62. 5 33B 62.5 TER150A 63.6 TER150B 63.7 TER250A 64.9 DT150-33A F 1 F/
DT150-33B 1~2 F/
DT250-33A 2.4 F/ 0 DT250-33B 2.5 F/ 0 PRECIPITATION 1.08 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 UNZT CODE STDDEV MZN SPD 33A 5.6 MPH 0 -3 2.6 8.1
-SPD 33B 5.7 MPH 1-2 2.6 8.0 SPD 150A 8.0 MPH 2.0 3.0 11.0 SPD 150B 57.2 MPH 0.0 57.2 57.3 SPD 250 6.5 MPH 1~3 4.3 9.7 DIR 33A 79.0 DEG 11.0 36.0 129.0 DIR 33B 80.0 DEG 11.0 37.0 138.0 DIR150A 79.0 DEG 6. 0 53. 7 116.0 DIR150B 54.0 DEG 0.0 53.0 55.0 DIR250 78.0 DEG 8.0 20.0 125.0 TER 33A 62.7 0 l'ER 33B 62.7 TER150A 63.9 TER150B 63.9 TER250A 64.8 DT150-33A 1 ' F/
DT150-33B 1 ' F/
DT250-33A 2.5 F/
DT250-33B 2.4 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 CODE STDDEV MIN MAX SPD 33A 6.2 MPH 1.5 2 ' 9.8 SPD 33B 6.4 MPH ~4 2.0 9.7 SPD 150A 6.6 MPH 1~3 2.5 9.5 SPD 150B 57.2 MPH 0.0 57.1 57.3 SPD 250 7-2 MPH ~1. 3.6 10.3 DIR 33A 76.0 DEG 15.0 15.0 115.0 DIR 33B 81.0 DEG 15. 0 16.0 114. 0 DIR150A 77.0 DEG 17.0 21.0 125. 0 DIR150B 53.0 DEG 0.0 52.0 55.0 DIR250 70. 0 DEG 9.0 20.0 114.0 TER 33A 65.0 i'ER 33B 65.0 TER150A 65.3 0, TER150B 65.5 TER250A 66.8 DT150-33A 0.3 F/
DT150-33B 0.5 F/
DT250-33A 1.8 F/
DT250-33B 1.9 F/
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 6.1 MPH 1.5 2-2 9.8 SPD 33B 6 ' MPH 1.4 2.0 9.7 SPD 150A 6.5 MPH 1-3 2.5 9.5 SPD 150B 57.2 MPH 0.0 57.1 57.3 SPD 250 7' 1.4 3.6 10.3 DIR 33A 77.0 DEG 0 15.0 15. 0 115.0 DIR 33B 80.0 DEG 15.0 16.0 114.0 DIR150A 78.0 DEG 17. 0 21.0 125. 0 DIR150B 53.0 DEG 0.0 52.0 55. 0 DIR250 ~7 ~ 0 DEG 9.0 20.0 14.0 TER 33A 65.1 ER 33B 65.0 TER150A 65.3 TER150B 65.5 TER250A 66.8 DT150-33A 0.3 F/ 0 DT150-33B 0.5 F/ 0 DT250-33A 1.8 F/ 0 DT250-33B 1.9 F/ 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 12:15 RECORD NUMBER 3996 RGErE GINNA PLANT SENSOR NAME AVERAGE UNIT CODE STDDEV MIN SPD 33A 6.5 MPH 1.5 2 ' 9.8 SPD 33B '.6 MPH 1.4 2.0 9.7
. SPD 150A 6.7 MPH 0 1~3 2.5 9.5 SPD 150B 57.2 MPH 0.0 57.1 57.3 SPD 250 7.4 MPH 1.4 3.6 10.3 DIR 33A 77.0 DEG 15.0 15.0 115. 0 DIR 33B 85.0 DEG 15.0 16.0 114.0 DIR150A 79.0 DEG 17. 0 21. 0 125.0 DIR150B 53 0 DEG 0. 0 52. 0 55. 0 DIR250 79.0 DEG 9. 0 20. 0 114. 0 TER 33A 66.0 ER 33B 66.0 TER150A 66.3 TER150B 66.5 TER250A 67.8 DT150-33A 0.4 F/
DT150-33B 0.5 F/
DT250-33A 1.9 F/
DT250-33B 1.8 F/ . 0 PRECIPITATION 1.08 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 AVERAGE UNXT CODE STDDEV MIN MAX SPD 33A 8.5 MPH 0 2 ' 12.8 SPD 33B 8' MPH 0 1.4 3.0 12 '
SPD 150A 7 ' MPH 0 1' 2.5 9.5 SPD 150B 57 ' MPH 0 0.0 57.1 57.3 SPD 250 7.4 MPH 1.4 3.6 10.3 DIR 33A 67. 0 DEG 0. 15.0 11.0 104.0 DIR 33B 65. 0 DEG 14.0 11.0 103.0 DIR150A 69.0 DEG 0 15. 0 12. 0 115. 0 DIR150B 53.0 DEG 0.0 52. 0 55.0 DIR250 69. 0 DEG 9.0 20.0 100.0 TER 33A 66.0 F ER 33B 66.0 F TER150A 66.3 TER150B 66.5 TER250A 67.8 0 DT150-33A 0.4 F/ 0 DT150-33B 0.5 F/ 0 DT250-33A 1.9 F/
DT250-33B 1.8 F/
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 AVERAGE UNIT CODE STDDEV MZN SPD 33A SPD 33B SPD 150A ,7 8 '
8 7
~ 9 MPH MPH MPH 0 0 '.4 1' 2 '
3.0 2.5 12.8 12 ~ 7 9.5 SPD 150B 57 ' MPH 0 0.0 57.1 57.3 SPD 250 7.9 MPH 0 1.4 3.6 10.3 DIR 33A 65.0 DEG 0 15. 0 11.0 104.0 DIR 33B 63.0 DEG , 0 14.0 11.0 103.0'2.'0 DIR150A 62.0 DEG 0 15. 0 115.0 DIR150B 53. 0 DEG 0.0 52.0 55.0 DIR250 66. 0 DEG 9.0 20.0 100.0 TER 33A 66. 0 0 ER 33B 66.0 TER150A 66. 3
'ER150B 66.5 TER250A 67.8 DT150-33A 0.4 F/
DT150-33B 0.5 F/
DT250-33A 1.9 F/
DT250-33B 1.8 F/
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 TABLE 10.3 TABLE 10.4 DISTANCE IVII 0.5 09:21 09'42 10:01 1.0 09:27 09:48 10:07 2.0 09:39 10:00 10:19 3.0 09:51 10:12 10:31 4.0 10:03 10:24 10:43 5.0 10:15 10:36 10:55 6.0 10:27 10:48 11:07 7.0 10:39 11:00 11:19 8.0 10:51 11:12 11:31 9.0 11'03 11:24 11:43 10.0 11:15 11:36 11:55 11.0 11:27 11:48 12:07 1 2.0 11:39 12:00 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 RADIOLOGICALSURVEY/SAMPLING DATA (RG8cE FIELD TEAMS)
CLOSE WINDOW OPEN WINDOW DOSIMETRY GROSS GROSS (mr/hr) (mr/br) INCREMENT IODINE PARTIC.
EXPOSURE CARTRIDGE FILTER ZONE 3 FEET CONTACT 3 FEET CONTACT (mREM) (CPM) (CPM)
A 7.3 7.3 9.5 9.5 70 BKG 3.4 3.4 4.5 4.5 50 BKG 1.5 1.5 2.0 2.0 45 BKG 0.7 0.7 0.9 0.9 BKG BKG 0.4 0.4 0.6 0.6 BKG BKG 0.3 0.3 0.4 0.4 BKG BKG 0.2 0.2 0.2 0.2 BKG BKG 0.1 0.1 0.2 0.2 BKG BKG 0.1 0.1 0.1 0.1 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.
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TABLE 10.3-B RADlOLOGICALSURVEY/SAMPL(NG:DATA (COUNTY TEAMS)
CLOSE WINDOW OPEN WINDOW DOSIMETRY GROSS GROSS (mr/hr) (mr/hr) INCREMENT IODINE PARTIC.
EXPOSURE CARTRIDGE FILTER ZONE 3 FEET CONTACT 3 FEET CONTACT (mREM) (CPM) (CPM) 7.3 7.3 9.5 9.5 90 BKG 3.4 3.4 4.5 4.5 60 BKG 1.5 1.5 2.0 2.0 50 BKG 0.7 0.7 0.9 0.9 BKG BKG 0.4 0.4 0.6 0.6 BKG BKG 0.3 0.3 0.4 0.4 BKG BKG 0.2 0.2 0.2 0.2 BKG BKG 0.1 0.1 0.2 0.2 BKG BKG 0.1 0.1 0.1 0.1 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.
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TABL'E 10.4-A RADIOLOGICALSURVEY/SAMPLING DATA (RGEEE SURVEY TEAMS)
CLOSE WINDOW OPEN WINDOW (mr/hr)'mr/hr) DOSIMETRY INCREMENT EXPOSURE GROSS IODINE CARTRIDGE GROSS PARTIC.
FILTER ZONE 3 FEET CONTACT 3 FEET CONTACT (mREM) (CPM) (CPM) 0.9 0.9 BKG BKG 0.4 0.4 0.5 0.5 BKG BKG 0.2 0.2 0.2 0.2 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.
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TABLE 10.4-B RADIOLOGICALSURVEY/SAMPLING DATA (COUNTY TEAMS)
CLOSE WINDOW OPEN WINDOW DOSIMETRY GROSS GROSS (mr/hr) (mr/br) INCREMENT IODINE PARTIC.
EXPOSURE CARTRIDGE FILTER ZONE 3 FEET CONTACT 3 FEET CONTACT (mREM) (CPM) (CPM) 0,9 0.9 BKG BKG 0.4 0.4 0.5 0.5 BKG BKG 0.2 0.2 0.2 0.2 BKG BKG 0.1 0.1 0.1 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 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.
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TABLE 10.5 POST-PLUME SURVEY DATA (FOR PANCAKE PROBES AND RM-14 METER)
PANCAKE PROBE (GROSS CPM)
ZONE 1 METER 1 CM A BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG BKG NOTE: BKG = Use ac ual back round readin of surve ins rurnen bein used.
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TABLE 10.6 POST-PLUME SURVEY DATA (GAMMA MICRO-R/HOUR READINGS)
GROSS GROSS MICRO-R/HOUR MICRO-R/HOUR ZONE @1 METER 91 CM A BKG BKG BKG BKG BKG BKG D BKG BKG BKG BKG BKG BKG G BKG BKG BKG BKG BKG BKG NOTE: BKG = Use actual back round readin of surve instrumen bein sed.
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SECTION 10.3 FIELD AIR SAIVIPLE ISOTOPIC DATA
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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 CS-137 BA-140 LA-140 20NE ACTIVITY READING UCI/CC (CPH) UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UCI/CC UC I/CC 6.71E-11 4.6E+01 1.99E-11 1.39E.11 7.96E-12 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 2.98E-11 4.2E+01 8.85E-12 6.20E-12 3.54E-'l2 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 1.33E-11 4.1E+01 3.96E-12 2.77E-12 1.58E-12 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 6.23E-12 4.1E+01 1.85E-12 1.29E-12 7.39E-13 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 3.83E-12 4.DE+01 1.14E-12 7.95E-13 4.55E-13 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 2.52E-12 4.DE+01 7.47E-13 5.23E-13 2.99E-13 O.DOE+00 O.OOE+00 0.DOE+00 O.DOE+00 1.61E-12 4 'E+01 4.77E-13 3.34E-13 1.91E-13 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 1.15E-12 4.DE+01 3.42E-13 2.40E-13 1.37E-13 O.DOE+00 O.DOE+00 O.DOE+00 O.DOE+00 9.10E-13 4.0E+01 2.70E-13 1.89E-13 1.08E-13 O.DOE+00 O.OOE+00 O.DOE+00 O.DOE+00 TABLE 10.7-B SILVER 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 8.5E+01 1.99E-09 3.39E-10 1.39E-09 2.19E-09 7.96E-10 2.98E-09 6.DE+01 8.85E-10 1.50E-10 6.20E-10 9.74E-10 3.54E-10 1.33E-09 4.9E+01 3.96E-10 6.73E-11 2.77E-10 4.35E-10 1.58E-10 6.23E-10 4.4E+01 1.85E-10 3.14E-11 1.29E-10 2.03E-10 7.39E-11 3.83E-10 4.3E+01 1.14E-10 1.93E-11 7.95E-11 1.25E-10 4.55E-11 2.52E-10 4.2E+01 7.47E-11 1.27E-11 5.23E-11 8.21E-11 2.99E-11 1.61E 10 4.1E+01 4.77E-11 8.10E-12 3.34E-11 5 ~ 24E-11 1.91E-11 1.15E-10 4.1E+01 3.42E-11 5.82E-12 2.40E-11 3.76E-11 1.37E-11
- 9. 10E.11 4.1E+01 2.70E-11 4.59E-12 1.89E-11 2.97E-11 1.08E-11
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