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bi                 1997 Evaluated Exercise 1.0 SCOPE AND OBJECTIVES NOTE In the development of an accident sequence, which is severe enough to adequately test the emergency response capabilities, it is necessary to postulate extremely           .
bi 1997 Evaluated Exercise 1.0 SCOPE AND OBJECTIVES NOTE In the development of an accident sequence, which is severe enough to adequately test the emergency response capabilities, it is necessary to postulate extremely unrealistic situations and multiple failures of redundant reactor protection functions and systems. Although the possibility of these events occurring is remote, Players are reminded that they are to respond to the indications as if they were real.
unrealistic situations and multiple failures of redundant reactor protection functions and systems. Although the possibility of these events occurring is
1.1 SCOPE The June 4,1997 Davis-Besse Emergency Preparedness Partial Participation Exercise will test and provide the opponunity to evaluate the Davis-Besse Emergency Plan and
'                    remote, Players are reminded that they are to respond to the indications as if they were real.
)
1.1 SCOPE The June 4,1997 Davis-Besse Emergency Preparedness Partial Participation Exercise           l will test and provide the opponunity to evaluate the Davis-Besse Emergency Plan and         )
Procedures. It will test the Emergency Response Organization's ability to assess and respond to emergency conditions and take actions to protect the health and safety of the public and station personnel.
Procedures. It will test the Emergency Response Organization's ability to assess and respond to emergency conditions and take actions to protect the health and safety of the public and station personnel.
This Partial Participation Exercise will also demonstrate activation and operation of major elements of the Non-utility Emergency Response Organization (ERO). The non-         1 utility ERO responding will include Ottawa, Lucas and Sandusky Counties, and the State of Ohio. Those functions that are most scenario dependent will be played in sequence. However, most non-utility field activities will be played out-of-sequence.
This Partial Participation Exercise will also demonstrate activation and operation of major elements of the Non-utility Emergency Response Organization (ERO). The non-utility ERO responding will include Ottawa, Lucas and Sandusky Counties, and the State of Ohio. Those functions that are most scenario dependent will be played in sequence. However, most non-utility field activities will be played out-of-sequence.
Whenever practical, this Exercise incorporates provisions for " free play" on the part of the participants. Selected "real time" activities will be conducted to allow the repair teams the opportunity to provide service and repairs to station equipment during the course of the Exercise. These " repairs" will allow the response organization to have an increased impact upon the direction that the Exercise proceeds as well as impacting the completion of the Exercise activities. In addition, the Control Room Simulator will be used to permit a degree of" free play" on the part of the Operations staff. The extent of this " free play" may be partially restricted by Controllers as necessary to keep the sequence of events on track.
Whenever practical, this Exercise incorporates provisions for " free play" on the part of the participants. Selected "real time" activities will be conducted to allow the repair teams the opportunity to provide service and repairs to station equipment during the course of the Exercise. These " repairs" will allow the response organization to have an increased impact upon the direction that the Exercise proceeds as well as impacting the completion of the Exercise activities. In addition, the Control Room Simulator will be used to permit a degree of" free play" on the part of the Operations staff. The extent of this " free play" may be partially restricted by Controllers as necessary to keep the sequence of events on track.
The scenario will simulate events resulting in a radiological release to the environment.
The scenario will simulate events resulting in a radiological release to the environment.
This release will be of sufficient magnitude to warrant mobilization of state and local agencies.
This release will be of sufficient magnitude to warrant mobilization of state and local agencies.
The scenario will also incorporate an out-of-sequence medical drill with panicipation l
The scenario will also incorporate an out-of-sequence medical drill with panicipation l
l                       by local emergency medical services and support hospitals.
l by local emergency medical services and support hospitals.
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l l-2                         1997 Evaluated Exercise
l l-2 1997 Evaluated Exercise
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                - 1.2 OBJECTIVES The objectives for this Partial Participation Exercise have been selected from l
- 1.2 OBJECTIVES The objectives for this Partial Participation Exercise have been selected from l
RA-EP-00200, Emergency Plan Drill and Exercise Program procedure (Utility) and from FEMA REP 14 and 15 (Non-Utility). The scenario has been designed such that                                       ,
RA-EP-00200, Emergency Plan Drill and Exercise Program procedure (Utility) and from FEMA REP 14 and 15 (Non-Utility). The scenario has been designed such that each participating organization will be provided with the opportunity to demonstrate their selected objectives. Some non-utility objectives will be demonstrated out-of-sequence to accommodate the responding volunteer organization.
each participating organization will be provided with the opportunity to demonstrate their selected objectives. Some non-utility objectives will be demonstrated out-of-sequence to accommodate the responding volunteer organization.
1.2.1 DAVIS-BESSE NUCIPAR POWER STATION UTILITY OBJECTIVES l
!                        1.2.1 DAVIS-BESSE NUCIPAR POWER STATION UTILITY OBJECTIVES l
i The utility objectives are cross-referenced to RA-EP-00200, Emergency Plan l
i                               The utility objectives are cross-referenced to RA-EP-00200, Emergency Plan l                               Drill and Exercise Program, Attachment 1, Six-Year Exercise Plant, in the first I                               column. The " FACILITIES" column identified the area that the objective is applicable. During the conduct of the Exercise, unidentified objectives may be
Drill and Exercise Program, Attachment 1, Six-Year Exercise Plant, in the first I
:                                successfully accomplished by the ERO. Credit will be given for the objectives and their performance will be documented in the Exercise Report.
column. The " FACILITIES" column identified the area that the objective is applicable. During the conduct of the Exercise, unidentified objectives may be successfully accomplished by the ERO. Credit will be given for the objectives and their performance will be documented in the Exercise Report.
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l l-1-3 1997 Evaluated Exercise 1.2 DAVIS-BESSE NUCLEAR POWER STATION OBJECTIVES REF.
1-3             1997 Evaluated Exercise l-                                                                                                                        ,
FACILITIES OBJECTIVE i
1.2 DAVIS-BESSE NUCLEAR POWER STATION OBJECTIVES REF.
A.1 Administrative CONDUCT AN ASSESSMENT OF THE DBNPS EMERGENCY PLAN.10 CFR 50 APPENDIX E, SECTION IV.F.2.
            #    FACILITIES     OBJECTIVE                                                                                 ,
l A.2 Administrative PROVIDE AN OPPORTUNITY FOR THE STATE, OTTAWA AND LUCAS COUNTIES TO PARTICIPATE IN AN EXERCISE l
i CONDUCT AN ASSESSMENT OF THE DBNPS EMERGENCY                                             l A.1    Administrative PLAN.10 CFR 50 APPENDIX E, SECTION IV.F.2.                                               l l
BIENNIALLY.
A.2   Administrative PROVIDE AN OPPORTUNITY FOR THE STATE, OTTAWA AND LUCAS COUNTIES TO PARTICIPATE IN AN EXERCISE l                               BIENNIALLY.
A.3 Administrative PREPARE AN EXERCISE INFORMATION PACKAGE TO MEET MINIMUM STANDARDS.
A.3   Administrative PREPARE AN EXERCISE INFORMATION PACKAGE TO MEET MINIMUM STANDARDS.
A.4 Administrative CONDUCT A CRITIQUE OF THE EXERCISE.
A.4   Administrative CONDUCT A CRITIQUE OF THE EXERCISE.
l A.5 Administrative ESTABLISH MEANS TO ENSURE COMPLETION OF CORRECTIVE ACTIONS.
l A.5   Administrative ESTABLISH MEANS TO ENSURE COMPLETION OF CORRECTIVE ACTIONS.
A.6 Administrative INVOLVE FEDERAL, STATE, COUNTY AND EP RESPONSE PERSONNEL AND AGENCIES IN A JOINT EXERCISE AT LEAST EVERY TWO YEARS.
A.6   Administrative INVOLVE FEDERAL, STATE, COUNTY AND EP RESPONSE PERSONNEL AND AGENCIES IN A JOINT EXERCISE AT LEAST EVERY TWO YEARS.
A.9 Administrative CONDUCT THE EXERCISE IN VARIOUS WEATHER CONDITIONS (DURING DIFFERENT SEASONS).
A.9   Administrative CONDUCT THE EXERCISE IN VARIOUS WEATHER CONDITIONS (DURING DIFFERENT SEASONS).
B.1 All DEMONSTRATE THE DIRECTION OF 'I HE EMERGENCY j
j          B.1   All           DEMONSTRATE THE DIRECTION OF 'I HE EMERGENCY ORGANIZATION AND IMPLEMENTATION OF THE EMERGENCY PLAN AND EMERGENCY PLAN PROCEDURES.
ORGANIZATION AND IMPLEMENTATION OF THE EMERGENCY PLAN AND EMERGENCY PLAN PROCEDURES.
B.2   Control Room, DEMONSTRATE TE E TRANSFER OF THE EMERGENCY ECC           DIRECTOR DUTIES.
B.2 Control Room, DEMONSTRATE TE E TRANSFER OF THE EMERGENCY ECC DIRECTOR DUTIES.
i B.3   All           DEMONSTRATE THE ABILITY FOR TIMELY ACTIVATION AND STAFFING OF THE EMERGENCY FACILITIES.                                                 ,
i B.3 All DEMONSTRATE THE ABILITY FOR TIMELY ACTIVATION AND STAFFING OF THE EMERGENCY FACILITIES.
i B.4   All           DEMONSTRATE THE ABILITY TO CONTROL ACCESS TO EMERGENCY FACILITIER C.1   Control Room, DEMONSTRATE THE AdlLITY TO ASSESS THE INCIDENT
i B.4 All DEMONSTRATE THE ABILITY TO CONTROL ACCESS TO EMERGENCY FACILITIER C.1 Control Room, DEMONSTRATE THE AdlLITY TO ASSESS THE INCIDENT TSC CONDITIONS.
'                  TSC           CONDITIONS.
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~1.2 DAVIS-BESSE NUCLEAR POWER STATION OBJECTIVES (Cont'd)
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                #    FACILITIES             OBJECTIVE                                                             !
FACILITIES OBJECTIVE C.2 Control Room, DEMONSTRATE THE ABILITY TO RECOGNIZE EMERGENCY
C.2   Control Room,           DEMONSTRATE THE ABILITY TO RECOGNIZE EMERGENCY
]
                                                                                                                    ]
L ECC, TSC ACTION LEVELS (EAL'S) AND PROPERLY CLASSIFY THE I
L                     ECC, TSC               ACTION LEVELS (EAL'S) AND PROPERLY CLASSIFY THE I                                             INCIDENT.
INCIDENT.
D.I   Control Room,           DEMONSTRATE THE ABILITY TO NOTIFY KEY OFFICIALS ECC                     IN THE EMERGENCY ORGANIZATION, VIA NOTIFICATION SYSTEM / PROCEDURES WITHIN 15 MINUTES OF -
D.I Control Room, DEMONSTRATE THE ABILITY TO NOTIFY KEY OFFICIALS ECC IN THE EMERGENCY ORGANIZATION, VIA NOTIFICATION SYSTEM / PROCEDURES WITHIN 15 MINUTES OF -
CLASSIFICATION.
CLASSIFICATION.
D.2   Control Room,           DEMONSTRATE THE ABILITY TO NOTIFY THE NRC OF ANY
D.2 Control Room, DEMONSTRATE THE ABILITY TO NOTIFY THE NRC OF ANY ECC EMERGENCY CLASSIFICATION WITHIN ONE HOUR OF THE OCCURRENCE.
,                    ECC                     EMERGENCY CLASSIFICATION WITHIN ONE HOUR OF THE OCCURRENCE.
D.3 All DEMONSTRATE THE CAPABILITY TO NOTIFY AND/OR ACTIVATE EMERGENCY PERSONNEL IN EACH RESPONSE j
D.3     All                   DEMONSTRATE THE CAPABILITY TO NOTIFY AND/OR                           l ACTIVATE EMERGENCY PERSONNEL IN EACH RESPONSE                         j ORGANIZATION.                                                         j D.4     Control Room,         DEMONSTRATE THE ABILITY TO DEVELOP AND SEND AN                         '
ORGANIZATION.
ECC                   INITIAL EMERGENCY MESSAGE FOR OFFSITE NOTIFICATION.                                                         :
j D.4 Control Room, DEMONSTRATE THE ABILITY TO DEVELOP AND SEND AN ECC INITIAL EMERGENCY MESSAGE FOR OFFSITE NOTIFICATION.
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D.5   Control Room,         DEMONSTRATE THE ABILITY TO DEVELOP AND SEND                           j ECC                     FOLLOW-UP MESSAGES FOR INFO'RMATION FOR OFFSITE AUTHORITIES.
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!              D.6
D.5 Control Room, DEMONSTRATE THE ABILITY TO DEVELOP AND SEND j
* Control Room,           DEMONSTRATE THE COMMUNICATIONS CAPABILITY TSC, ECC               AMONG THE CONTROL ROOM,TSC AND ECC, AND AMONG DBNPS, THE STATE OF OHIO, O'ITAWA COUNTY, AND LUCAS COUNTY EMERGENCY OPERATIONS CENTERS AND THE FIELD ASSESSMENT TEAMS, TO INCLUDE EVALUATION OF THE ABILITY TO UNDERSTAND MESSAGE CONTENT (COMMUNICATIONS EXERCISE REQUIREMENT).
ECC FOLLOW-UP MESSAGES FOR INFO'RMATION FOR OFFSITE AUTHORITIES.
>              D.12 SEC                       DEMONSTRATE THE COMMUNICATIONS CAPABILITY WITH FIXED AND MOBILE SUPPORT FACILITY (MEDICAL DRILL REQUIREMENT). THIS OBJECTIVE WILL BE DONE OUT-OF-SEQUENCE.
D.6
* Control Room, DEMONSTRATE THE COMMUNICATIONS CAPABILITY TSC, ECC AMONG THE CONTROL ROOM,TSC AND ECC, AND AMONG DBNPS, THE STATE OF OHIO, O'ITAWA COUNTY, AND LUCAS COUNTY EMERGENCY OPERATIONS CENTERS AND THE FIELD ASSESSMENT TEAMS, TO INCLUDE EVALUATION OF THE ABILITY TO UNDERSTAND MESSAGE CONTENT (COMMUNICATIONS EXERCISE REQUIREMENT).
D.12 SEC DEMONSTRATE THE COMMUNICATIONS CAPABILITY WITH FIXED AND MOBILE SUPPORT FACILITY (MEDICAL DRILL REQUIREMENT). THIS OBJECTIVE WILL BE DONE OUT-OF-SEQUENCE.
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l-5 1997 Evaluated Exercise 1.2 DAVIS-BESSE NUCI EAR POWER STATION OBJECTIVES (Cont'd)
REF.
REF.
        #    FACILITIES   OBJECTIVE E.1   ECC           DEMONSTRATE THE METHODS AND TECHNIQUES FOR l                           DETERMINING THE SOURCE TERM OF RELEASES OR POTENTIAL RELEASES OF RADIOACTIVE MATERIAL j                           WITHIN PLANT SYSTEMS.
FACILITIES OBJECTIVE E.1 ECC DEMONSTRATE THE METHODS AND TECHNIQUES FOR l
!      E.2   ECC,TSC       DEMONSTRATE THE METHODS AND TECHNIQUES FOR l                          DETERMINING THE MAGNITUDE OF THE RELEASES OF RADIOACTIVE MATERIALS BASED ON PLANT SYSTEM PARAMETERS AND EFFLUENT MONITORS.
DETERMINING THE SOURCE TERM OF RELEASES OR POTENTIAL RELEASES OF RADIOACTIVE MATERIAL j
E.3   ECC           DEMONSTRATE THE ABILITY TO ESTIMATE INTEGRATED DOSE FROM PROJECTED AND ACTUAL DOSE RATES AND TO COMPARE THESE ESTIMATES WITH THE PAG'S.
WITHIN PLANT SYSTEMS.
E.4   OSC           DEMONSTRATE THE ABILITY TO IMPLEMENT EXPOSURE GUIDELINES.
E.2 ECC,TSC DEMONSTRATE THE METHODS AND TECHNIQUES FOR DETERMINING THE MAGNITUDE OF THE RELEASES OF l
E.5   OSC         DEMONSTRATE THE ABILITY TO CONTINUOUSLY MONITOR AND CONTROL EMERGENCY WORKER EXPOSURE.
RADIOACTIVE MATERIALS BASED ON PLANT SYSTEM PARAMETERS AND EFFLUENT MONITORS.
E.15 OSC,SEC       DEMONSTRATE THE CAPABILITY FOR TRANSPORTATION OF A RADIOLOGICAL ACCIDENT VICTIM (MEDICAL DRILL REQUIREMENT). THIS OBJECTIVE WILL BE DONE OUT-OF-SEQUENCE.
E.3 ECC DEMONSTRATE THE ABILITY TO ESTIMATE INTEGRATED DOSE FROM PROJECTED AND ACTUAL DOSE RATES AND TO COMPARE THESE ESTIMATES WITH THE PAG'S.
E.16 RTL,OSC       DEMONSTRATE THE CAPABILITY FOR ONSITE AND OFFSITE RADIOLOGICAL MONITORING TO INCLUDE COLLECTION A'ND ANALYSIS.
E.4 OSC DEMONSTRATE THE ABILITY TO IMPLEMENT EXPOSURE GUIDELINES.
E.17 RTL           DEMONSTRATE THE RESPONSE TO AND ANALYSIS OF SIMULATED EVALUATED AIRBORNE AND LIQUID SAMPLES AS WELL AS DIRECT RADIATION MEASUREMENTS IN THE ENVIRONMENT.
E.5 OSC DEMONSTRATE THE ABILITY TO CONTINUOUSLY MONITOR AND CONTROL EMERGENCY WORKER EXPOSURE.
F.1   ECC           DEMONSTRATE THE ABILITY TO RECOMMEND PROTECTIVE ACTIONS TO APPROPRIATE OFFSITE j                            AUTHORITIES, BASES OF RECOMMENDATIONS TO INCLUDE i                           CONSIDERATION OF PROTECTION AFFORDED BY SHELTERING, AS WELL AS, EVACUATION TIME ESTIMATES.
E.15 OSC,SEC DEMONSTRATE THE CAPABILITY FOR TRANSPORTATION OF A RADIOLOGICAL ACCIDENT VICTIM (MEDICAL DRILL REQUIREMENT). THIS OBJECTIVE WILL BE DONE OUT-OF-SEQUENCE.
E.16 RTL,OSC DEMONSTRATE THE CAPABILITY FOR ONSITE AND OFFSITE RADIOLOGICAL MONITORING TO INCLUDE COLLECTION A'ND ANALYSIS.
E.17 RTL DEMONSTRATE THE RESPONSE TO AND ANALYSIS OF SIMULATED EVALUATED AIRBORNE AND LIQUID SAMPLES AS WELL AS DIRECT RADIATION MEASUREMENTS IN THE ENVIRONMENT.
F.1 ECC DEMONSTRATE THE ABILITY TO RECOMMEND PROTECTIVE ACTIONS TO APPROPRIATE OFFSITE AUTHORITIES, BASES OF RECOMMENDATIONS TO INCLUDE j
i CONSIDERATION OF PROTECTION AFFORDED BY SHELTERING, AS WELL AS, EVACUATION TIME ESTIMATES.
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1-6 1997 Evaluated Exercise 1.2 DAVIS-BESSE NUCLEAR POWER STATION OBJECTIVES (Cont'd)
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            #      FACILITIES     OBJECTIVE F.2     JPIC           DEMONSTRATE THE OPERATION OF THE JOINT PUBLIC INFORMATION CENTER AND THE AVAILABILITY OF SPACE FOR THE MEDIA.
FACILITIES OBJECTIVE F.2 JPIC DEMONSTRATE THE OPERATION OF THE JOINT PUBLIC INFORMATION CENTER AND THE AVAILABILITY OF SPACE FOR THE MEDIA.
F.3     JPIC           DEMONSTRATE THE ABILITY TO BRIEF THE MEDIA IN A CLEAR, ACCURATE AND TIMELY MANNER.
F.3 JPIC DEMONSTRATE THE ABILITY TO BRIEF THE MEDIA IN A CLEAR, ACCURATE AND TIMELY MANNER.
l F.11   OSC           DEMONSTRATE THE CAPABILITY FOR ONSITE FIRST AID.
l F.11 OSC DEMONSTRATE THE CAPABILITY FOR ONSITE FIRST AID.
THIS OBJECTIVE WILL BE DONE OUT-OF-SEQUENCE.
THIS OBJECTIVE WILL BE DONE OUT-OF-SEQUENCE.
F.12   OSC,RTL       DEMONSTRATE THAT THE PROVISIONS ARE AVAILABLE FOR THE EVALUATION OF RADIATION EXPOSURE OF, AND RADIATION UPTAKE IN A RADIOLOGICAL ACCIDENT VICTIM.                          .
F.12 OSC,RTL DEMONSTRATE THAT THE PROVISIONS ARE AVAILABLE FOR THE EVALUATION OF RADIATION EXPOSURE OF, AND RADIATION UPTAKE IN A RADIOLOGICAL ACCIDENT VICTIM.
G.1     ALL           DEMONSTRATE PRELIMINARY DISCUSSION OF RE-ENTRY                               '
G.1 ALL DEMONSTRATE PRELIMINARY DISCUSSION OF RE-ENTRY AND RECOVERY CAPABILITIES AND AVAILABILITY OF PROCEDURES.
AND RECOVERY CAPABILITIES AND AVAILABILITY OF PROCEDURES.                                                                   i f
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==3.0 REFERENCES==
==3.0 REFERENCES==
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==3.1 REFERENCES==
==3.1 REFERENCES==
 
3.1.1 DBNPS Emergency Plan 3.1.2 DBNPS Emergency Plan Implementing Procedures 3.1.3 10 CFR 50.47,50.54 and Appendix E 3.1.4 DBNPS Radiation Protection Manual 3.1.5 DBNPS Offsite Dose Calculation Manual 3.1.6 DBNPS, Unit 1, Tecimical Specifications 3.1.7 DBNPS Piping and Instrumentation Drawings 3.1.8 DBNPS IJpdated Safety Analysis Report 3.1.9 Corporate Emergency Response (CER) Plan 3.1.10 Public Information Emergency Response Procedures 3.1.11 NUREG 0654/ FEMA REP-1 3.1.12 Ohio Plan for Response to Radiation Emergencies at Licensed Nuclear Facilities 3.1.13 Ottawa County Plant for Response to Radiation Emergencies at Licensed Nuclear Facilities 3.1.14 Lucas County Radiological Emergency Response Plan 3.1.15 Sandusky County Radiological Emergency Response Procedure Document 3.1.16 Erie County Radiolgocal Emergency Response Procedure Document 3.1.17 FEMA REP 14 3.1.18 FEMA REP 15 l
3.1.1   DBNPS Emergency Plan 3.1.2   DBNPS Emergency Plan Implementing Procedures 3.1.3   10 CFR 50.47,50.54 and Appendix E 3.1.4   DBNPS Radiation Protection Manual 3.1.5   DBNPS Offsite Dose Calculation Manual 3.1.6   DBNPS, Unit 1, Tecimical Specifications 3.1.7   DBNPS Piping and Instrumentation Drawings 3.1.8   DBNPS IJpdated Safety Analysis Report 3.1.9   Corporate Emergency Response (CER) Plan 3.1.10 Public Information Emergency Response Procedures 3.1.11 NUREG 0654/ FEMA REP-1 3.1.12 Ohio Plan for Response to Radiation Emergencies at Licensed Nuclear Facilities 3.1.13 Ottawa County Plant for Response to Radiation Emergencies at Licensed Nuclear Facilities 3.1.14 Lucas County Radiological Emergency Response Plan 3.1.15 Sandusky County Radiological Emergency Response Procedure Document
3.1.19 FEMA Guidelines, MS-1 3.2 ABBREVIATIONS AFP Auxiliary Feed (Water) Pump ALARA As Low As Reasonably Achievable ARM Area Radiation Monitor ARTS Anticipatory Reactor Trip System ATMOS Atmosphere ATWS Anticipated Transient Without Scram AUX Auxiliary AVG Average BAAT Boric Acid Addition Tank
,              3.1.16 Erie County Radiolgocal Emergency Response Procedure Document 3.1.17 FEMA REP 14 3.1.18 FEMA REP 15 l
3.1.19 FEMA Guidelines, MS-1 3.2 ABBREVIATIONS AFP               Auxiliary Feed (Water) Pump ALARA             As Low As Reasonably Achievable ARM               Area Radiation Monitor ARTS               Anticipatory Reactor Trip System ATMOS             Atmosphere ATWS               Anticipated Transient Without Scram AUX               Auxiliary AVG               Average BAAT               Boric Acid Addition Tank BKWSH              Back Wash
(
(
l               BRKR               Electrical Circuit Breaker l               BWST               Borated Water Storage Tank CAM               Continuous Air Monitor CANS               Computerized Automated Notification System CAS               Central Alarm Station CCW               Component Cooling Water System l
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CERO               Corporate Emergency Response Organization l
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BWST Borated Water Storage Tank CAM Continuous Air Monitor CANS Computerized Automated Notification System CAS Central Alarm Station CCW Component Cooling Water System CERO Corporate Emergency Response Organization l
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CFR Code of Federal Regulations CNDS Condensate System COND Condenser CPM Counts Per Minute CRS Control Room Simulator l
!                          CFR                     Code of Federal Regulations CNDS                     Condensate System                                                                       ,
CS-Containment Spray System CST Condensate Storage Tank j
COND                     Condenser CPM                     Counts Per Minute CRS                     Control Room Simulator l                         CS-                     Containment Spray System CST                     Condensate Storage Tank j                         CT                       Circulating Water and Cooling Tower System                                             '
CT Circulating Water and Cooling Tower System l
l                          CTMT                     Reactor Containment Building CTRM                     Control Room l                         DADS                     Data Acquisition and Display System                                                     !
CTMT Reactor Containment Building CTRM Control Room l
DBAB                     Davis-Besse Administrative Building DBNPS                   Davis-Besse Nuclear Power Station                                                       ,
DADS Data Acquisition and Display System DBAB Davis-Besse Administrative Building DBNPS Davis-Besse Nuclear Power Station l
l                          DEI                     Dose Equivalent Iodine DEMIN                   Demineralizer DHR                     Decay Heat Removal DISCH                   Discharge DP                       Differential Pressure DWS                     Demineralized Water System EAL                     Emergency Action Level EAS                     Emergency Alert System                                                                 ;
DEI Dose Equivalent Iodine DEMIN Demineralizer DHR Decay Heat Removal DISCH Discharge DP Differential Pressure DWS Demineralized Water System EAL Emergency Action Level EAS Emergency Alert System ECC
ECC
* Emergency Control Center EDG Emergency Diesel Generator EEC Energy Education Center EMA Emergency Management Agency ENC Electrical and Controls Section j
* Emergency Control Center EDG                     Emergency Diesel Generator EEC                     Energy Education Center EMA                       Emergency Management Agency ENC                       Electrical and Controls Section                                                         j EOC                       Emergency Operations Center EPZ                       Emergency Planning Zone                                                                 j EVAL                     Evaluated                                                                             j FAT                       First Aid Team FEMA                     Federal Emergency Management Agency FT                       Feet FW                       Feed Water GPM                     Gallons Per Minute HDR                     Header                                                                                 ;
EOC Emergency Operations Center EPZ Emergency Planning Zone j
HLCWT                   High Level Cooling Water Tank HPI                     High Pressure Injection System HVAC                     Heating Ventilation and Air Conditioning System HX                       Heat Exchanger l                          I&C                     Instrument and Control Section L                           IF                       Instructor Facility (at the CRS) l                           IN                       Inch INST                     Instrument i                           JPIC                     Joint Public Infonnation Center KI                       Potassium lodide f
EVAL Evaluated j
Rev.0
FAT First Aid Team FEMA Federal Emergency Management Agency FT Feet FW Feed Water GPM Gallons Per Minute HDR Header HLCWT High Level Cooling Water Tank HPI High Pressure Injection System HVAC Heating Ventilation and Air Conditioning System HX Heat Exchanger I&C Instrument and Control Section l
L IF Instructor Facility (at the CRS) l IN Inch INST Instrument i
JPIC Joint Public Infonnation Center f
KI Potassium lodide Rev.0


3-3                 1997 Evaluated Exercise LP     Low Pressure l     LVL     Level MISC   Miscellaneous MSIV   Main Steam Isolation Valve MTR     Motor MU     Makeup System l     NI     Nuclear instrumentation NRC     Nuclear Regulatory Commission OTSG   Once Through Steam Generator i     OOS     Out of Service OSC     Operations Support Center PA     Public Address System PASS   Post Accident Sampling System PC     Protective Clothing PI     Pres sure Indication PMP     Pu:np PORV   Power Operated Relief Valve PPF     Personnel Processing Facility PR     Public Relations PSF     Personnel Shop Facility PSIA   Pounds Per Square Inch Absolute PSIG   Pounds Per Square Inch Gauge                             l PT     Periodic Test PTS     Pressurized Thermal Shock                                 l PWR     Pressurized Water Reactor                                 l PWST   Primary Water Storage Tank                               l PZR     Pressurizer RRA     Radiologically Restricted Area                           l RC     Radiological Controls RCP     Reactor Coolant Pump RCS     Reactor Coolant System lE     Fixed Radiation Instrument RLF     ReliefValve RM     Radiation Monitor                                       i RMT     Radiation Monitoring Team                               (
3-3 1997 Evaluated Exercise LP Low Pressure l
RP     Radiation Protection RTL     Radiological Testing Laboratory Rx     Reactor SAS     Secondary Alarm System SFP     Spent, Fuel Pool I
LVL Level MISC Miscellaneous MSIV Main Steam Isolation Valve MTR Motor MU Makeup System l
SFAS   Safety Features Actuation System l
NI Nuclear instrumentation NRC Nuclear Regulatory Commission OTSG Once Through Steam Generator i
i      SFRCS   Steam and Feed Water Rupture Control System SJAE   Steam Jet Air Ejector l
OOS Out of Service OSC Operations Support Center PA Public Address System PASS Post Accident Sampling System PC Protective Clothing PI Pres sure Indication PMP Pu:np PORV Power Operated Relief Valve PPF Personnel Processing Facility PR Public Relations PSF Personnel Shop Facility PSIA Pounds Per Square Inch Absolute PSIG Pounds Per Square Inch Gauge PT Periodic Test PTS Pressurized Thermal Shock PWR Pressurized Water Reactor PWST Primary Water Storage Tank PZR Pressurizer RRA Radiologically Restricted Area RC Radiological Controls RCP Reactor Coolant Pump RCS Reactor Coolant System lE Fixed Radiation Instrument RLF ReliefValve RM Radiation Monitor RMT Radiation Monitoring Team RP Radiation Protection RTL Radiological Testing Laboratory Rx Reactor SAS Secondary Alarm System SFP Spent, Fuel Pool l
SPDS   Safety Parameter Display System l
SFAS Safety Features Actuation System i
SPF     Spent Fuel Rev.O
SFRCS Steam and Feed Water Rupture Control System l
SJAE Steam Jet Air Ejector l
SPDS Safety Parameter Display System SPF Spent Fuel Rev.O


_ _ _ ._            > ._. _ . _ _._. _                  ..__....m               . . _ _ . . _ . _ . - . _ _ . _ _ _ _ _ . - - _ - . _
..__....m l
l
3-4 1997 Evaluated Exercise SRST Spent Resin Storage Tank ST Surveillance Test i
* 3-4                           1997 Evaluated Exercise SRST                       Spent Resin Storage Tank                                                               l ST                         Surveillance Test                                                                     i
-SW' Service Water System SYS System Tc Reactor Coolant System Cold Leg Temperature TC Thermocouple TDG Total Dissolved Gases Th Reactor Coolant System Hot Leg Temperature TPCW Turbine Plant Cooling Water
                                -SW'                         Service Water System                                                                   ;
}
SYS                         System Tc                         Reactor Coolant System Cold Leg Temperature                                           .
TRBL Trouble TSC-Technical Support Center VOM Volt Ohm Meter l'
TC                         Thermocouple TDG                         Total Dissolved Gases Th                         Reactor Coolant System Hot Leg Temperature                                             ;
WGST Waste Gas Storage Tank WK Week WR Wide Range Instrument WTR Water.
TPCW                       Turbine Plant Cooling Water                                                           }
XFER Transfer i
TRBL                       Trouble                                                                               !
XMIT Transmit -
TSC-                       Technical Support Center VOM                         Volt Ohm Meter                                                                         l WGST                       Waste Gas Storage Tank WK                         Week                                                                                   .
WR                         Wide Range Instrument                                                                 !
WTR                         Water.                                                                               >
XFER                       Transfer                                                                               i XMIT                       Transmit -
3.3 DEFINITIONS
3.3 DEFINITIONS


====3.3.1 ALERT====
====3.3.1 ALERT====
The level of emergency classification which indicates events are in progress or have occurred which involve an actual or potential' substantial '
The level of emergency classification which indicates events are in progress or have occurred which involve an actual or potential' substantial '
l                                             degradation of the level of safety of the plant.                                                       l l
l degradation of the level of safety of the plant.
1
l 1
,                                  3.3.2 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS): Failure of the
3.3.2 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS): Failure of the reactor control rods to insert into the core upon a signal to do so from the Reactor Protection System or the failure of the Reactor Protection System to trip when limits have been exceeded.
!                                              reactor control rods to insert into the core upon a signal to do so from the
L 3.
!                                              Reactor Protection System or the failure of the Reactor Protection System to trip when limits have been exceeded.
 
L 3.3.3 ASSESSMENT ACTIONS: Those actions taken during or after an accident to obtain and process information that is necessary to make decisions to implement specific emergency measures.
==3.3 ASSESSMENT==
l                                 3.3.4 CONTROL ROOM (CTRM): The principle onsite location from which the reactor is controlled and from which emergency control is initially exercised.                         i The CTRM is located on the 623' elevation of the Auxiliary Building.                                   l
ACTIONS: Those actions taken during or after an accident to obtain and process information that is necessary to make decisions to implement specific emergency measures.
l 3.3.4 CONTROL ROOM (CTRM): The principle onsite location from which the reactor is controlled and from which emergency control is initially exercised.
i The CTRM is located on the 623' elevation of the Auxiliary Building.


====3.3.5 CONTROLLER====
====3.3.5 CONTROLLER====
A member of the control group, assigned to one or more activities or functions for the purpose of keeping the action going according to a                   i scenario, resclving scenario discrepancies, and supervising the actions of the     ,
A member of the control group, assigned to one or more activities or functions for the purpose of keeping the action going according to a i
I                                              players.
scenario, resclving scenario discrepancies, and supervising the actions of the I
l                                                                                                                                                      l i
players.
l i
p Rev.0 p
p Rev.0 p
l L,_.             _      ,                                  _                                  _
lL,_.


_._._..____________....y i
_._._..____________....y i
3-5                 1997 Evaluated Exercise     l i
3-5 1997 Evaluated Exercise l
    .+.                                  .
i
3.3.6. CORRECTIVE ACTIONS: Those emergency measures taken to mitigate or                   ,
.+.
terminate a potential or uncontrolled release of radioactive material or to       j minimize the consequences of such a release.                                       j
3.3.6. CORRECTIVE ACTIONS: Those emergency measures taken to mitigate or terminate a potential or uncontrolled release of radioactive material or to j
minimize the consequences of such a release.
j


====3.3.7 DECONTAMINATION====
====3.3.7 DECONTAMINATION====
The process by which the body or an object is
The process by which the body or an object is relieved of radioactive substances (contamination).
                                                                                                                                          +
+
relieved of radioactive substances (contamination).
i 3.3.8 DOSE ASSESSMENT: The process of estimating the amount of radiation a person will potentially receive as a result of exposure to a radiological release.
i 3.3.8 DOSE ASSESSMENT: The process of estimating the amount of radiation a                 !
l l
person will potentially receive as a result of exposure to a radiological release. l l                                             3.3.9 DRILL: A supervised instruction period aimed at testing, developing, and             l maintaining skills in a particular operation.                                     l t
 
3.3.10 EMERGENCY ACTION LEVELS (EALs)- Radiological dose rates; specific                     ,
====3.3.9 DRILL====
l
A supervised instruction period aimed at testing, developing, and l
'                                                      contamination levels or airborne, waterborne, or surface-deposited concentrations of radioactive materials, or specific instrument readings and indications (including their rate of change) that may be used as thresholds for l                                                       initiating specific emergency measures.
maintaining skills in a particular operation.
l 3.3.11 EMERGENCY CONTROL CENTER (ECC): The Davis-Besse Emergency Response Facility from which overall direction and control are exercised for emergencies at DBNPS. The facility also provides a central point of contact         I with extemal organizations, and is fully activated for emergencies classified as j l                                                       an ALERT or higher.
l t
3.3.10 EMERGENCY ACTION LEVELS (EALs)- Radiological dose rates; specific l
contamination levels or airborne, waterborne, or surface-deposited concentrations of radioactive materials, or specific instrument readings and indications (including their rate of change) that may be used as thresholds for l
initiating specific emergency measures.
l 3.3.11 EMERGENCY CONTROL CENTER (ECC): The Davis-Besse Emergency Response Facility from which overall direction and control are exercised for emergencies at DBNPS. The facility also provides a central point of contact with extemal organizations, and is fully activated for emergencies classified as j
l an ALERT or higher.
l t
l t
l                                               3.3.12 EMERGENCY OPERATIONS CENTER (EOC): An offsite location used by                     l I                                                      state, county and other government agencies and organizations to perform '       l l                                                       radiological assessment and to coordinate offsite activities. The EOCs are       l located as follows:
l 3.3.12 EMERGENCY OPERATIONS CENTER (EOC): An offsite location used by state, county and other government agencies and organizations to perform '
l                                                       Ottawa County:           Ottawa County Emergency Management Agency               .
l I
315 Madison Avenue Port Clinton, Ohio 43452 Lucas County:             Lucas County Emergency Management Agency 2144. Monroe Street Toledo, Ohio 43624 l
l radiological assessment and to coordinate offsite activities. The EOCs are located as follows:
t l
l Ottawa County:
State of Ohio:           Emergency Operations Center / Joint Dispatch Facility 2855 West Dublin-Granville Rd.
Ottawa County Emergency Management Agency 315 Madison Avenue Port Clinton, Ohio 43452 Lucas County:
Worthington, Ohio 43235-2206
Lucas County Emergency Management Agency 2144. Monroe Street l
!                                                        State of Michigan: Emergency Management Division Suite 300 i                                                                                 3005 Washington Square I                                                                                 Lansing, Michigan 48913 i
Toledo, Ohio 43624 t
l State of Ohio:
Emergency Operations Center / Joint Dispatch Facility 2855 West Dublin-Granville Rd.
Worthington, Ohio 43235-2206 State of Michigan: Emergency Management Division Suite 300 i
3005 Washington Square I
Lansing, Michigan 48913 i
l Rev.O l
l Rev.O l
l i         .                                                ,                . . _          _            _.
l i


1 3-6                   1997 Evaluated Exercise 3.3. EMERGENCY PLANNING ZONES (EPZs): Two zones established around a nuclear power station in which predetermined protective action plans are           l l
3-6 1997 Evaluated Exercise 3.3.
needed. One zone, with a radius of 10 miles (16090 meters) for a PLUME EXPOSURE PATHWAY; and the other with a radius of 50 miles (80450                   i meters) for an INGESTION EXPOSURE PATHWAY. In these zones,                         l predetermine PROTECTIVE ACTION plans are needed.                                   :
EMERGENCY PLANNING ZONES (EPZs): Two zones established around a l
l l       3.3.14 EMERGENCY RESPONSE FACILITY: Any of several onsite and offsite                     !
nuclear power station in which predetermined protective action plans are needed. One zone, with a radius of 10 miles (16090 meters) for a PLUME EXPOSURE PATHWAY; and the other with a radius of 50 miles (80450 meters) for an INGESTION EXPOSURE PATHWAY. In these zones, predetermine PROTECTIVE ACTION plans are needed.
centers which are activated to coordinate emergency actions. Included in this     I category are the Control Room, Technical Support Center, Operations Support       f Center, Emergency Control Center, Joint Public Information Center, and State       l and local Emergency Operations Centers.
l l
3.3.15 EVALUATOR: A member of the evaluation group, assigned to one or more               j activities or functions for the purpose of evaluating and making                   I recommendations for improvement. An evaluator may serve in a dual capacity as both a Controller and Evaluator.
3.3.14 EMERGENCY RESPONSE FACILITY: Any of several onsite and offsite centers which are activated to coordinate emergency actions. Included in this category are the Control Room, Technical Support Center, Operations Support f
Center, Emergency Control Center, Joint Public Information Center, and State and local Emergency Operations Centers.
3.3.15 EVALUATOR: A member of the evaluation group, assigned to one or more j
activities or functions for the purpose of evaluating and making recommendations for improvement. An evaluator may serve in a dual capacity as both a Controller and Evaluator.
3.3.16 EXCLUSION AREA: The area surrounding the plant in which the Licensee has the authority to determine all activities including exclusion or removal of persons and property from the area.
3.3.16 EXCLUSION AREA: The area surrounding the plant in which the Licensee has the authority to determine all activities including exclusion or removal of persons and property from the area.
3.3.17 EXERCISE: An event that tests the integrated capability and a major portion of the basic elements within the Emergency Plan.
3.3.17 EXERCISE: An event that tests the integrated capability and a major portion of the basic elements within the Emergency Plan.
3.3.18 GENERAL EMERGENCY: The most severe level of emergency classification which indicates that events are in progress or have occurred which involve         i actual or imminent substantial core degradation or melting with potential for     l loss of containment integrity. Release of radioactive material can be reasonably expected to exceed PAG exposure levels offsite.
3.3.18 GENERAL EMERGENCY: The most severe level of emergency classification which indicates that events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Release of radioactive material can be reasonably expected to exceed PAG exposure levels offsite.
3.3.19 INGESTION PATHWAY: The means by which contaminated water or foodstuff can expose the POPULATION-AT-RISK to radiation. The time of potential exposure could range from hours to months. The principal exposure sources from this pathway are:
3.3.19 INGESTION PATHWAY: The means by which contaminated water or foodstuff can expose the POPULATION-AT-RISK to radiation. The time of potential exposure could range from hours to months. The principal exposure sources from this pathway are:
: 1. Ingestion of contaminated drinking supplies, such as water or milk.
: 1. Ingestion of contaminated drinking supplies, such as water or milk.
Line 233: Line 260:
l Rev.0 l
l Rev.0 l


3-7         1997 Evaluated Exercisc                         ,
3-7 1997 Evaluated Exercisc
              ~
~
!                3.3.20 JOINT PUBLIC INFORMATION CENTER (JPIC): A location for
3.3.20 JOINT PUBLIC INFORMATION CENTER (JPIC): A location for coordinating news releases and providing joint briefings to the news media j
!                      coordinating news releases and providing joint briefings to the news media j                       during an emergency. It provides a central point for information to be disseminated to the public by the utility, the federal, state and local officials.
during an emergency. It provides a central point for information to be disseminated to the public by the utility, the federal, state and local officials.
t l               3.3.21 OBSERVER: Any individual who is authorized to observe, but is not authorized to interact with the players.                                                             !
t l
3.3.22 OFFSITE: Any areas outside the Owner Controlled Area.                                                .
3.3.21 OBSERVER: Any individual who is authorized to observe, but is not authorized to interact with the players.
3.3.22 OFFSITE: Any areas outside the Owner Controlled Area.
3.3.23 ONSITE: The area within the Owner Controlled Area.
3.3.23 ONSITE: The area within the Owner Controlled Area.
l 3.3.24 OPERATIONS SUPPORT CENTER (OSC): An onsite emergency response t                    facility which provides a location where emergency response teams can be assembled and coordinated during an emergency.
l 3.3.24 OPERATIONS SUPPORT CENTER (OSC): An onsite emergency response facility which provides a location where emergency response teams can be t
3.3.25 OWNER CONTROLLED AREA: The area contiguous with the Protected Area, designated by the owner organization to be patrolled for security                             j purposes.
assembled and coordinated during an emergency.
l 3.3.26 PARTICIPANT: An individual who has some part, whether as an Evaluator,                               !
3.3.25 OWNER CONTROLLED AREA: The area contiguous with the Protected Area, designated by the owner organization to be patrolled for security j
Controller, Player or Observer.
purposes.
3.3.27 PLAYERS: Allindividuals who are assigned to perform functions of the                                 l Emergency Response Organization, as described in the appropriate Emergency                           ;
l 3.3.26 PARTICIPANT: An individual who has some part, whether as an Evaluator, Controller, Player or Observer.
Plan Implementing Procedures.
3.3.27 PLAYERS: Allindividuals who are assigned to perform functions of the Emergency Response Organization, as described in the appropriate Emergency Plan Implementing Procedures.
1 3.3.28 PLUME EXPOSURE PATHWAY: The means by which a radioactive cloud                                       I (plume) can expose the POPULATION-AT-RISK to radiation. The time of                                 l l                        potential exposure could range from hours to days. The principal exposure sources for this pathway are as follows:
3.3.28 PLUME EXPOSURE PATHWAY: The means by which a radioactive cloud (plume) can expose the POPULATION-AT-RISK to radiation. The time of potential exposure could range from hours to days. The principal exposure l
sources for this pathway are as follows:
: 1. Whole body external exposure to gamma radiation from the radioactive plume and from deposited material.
: 1. Whole body external exposure to gamma radiation from the radioactive plume and from deposited material.
: 2. Inhalation exposure from the passing radioactive plume.
: 2. Inhalation exposure from the passing radioactive plume.
l 3.3.29 POPULATION AT RISK: Those persons for whom protective actions are being or would be taken.
l 3.3.29 POPULATION AT RISK: Those persons for whom protective actions are being or would be taken.
3.3.30 PROTECTED AREA: The area within the Owner-Controlled Area
3.3.30 PROTECTED AREA: The area within the Owner-Controlled Area encompassed by physical barriers and to which access is' controlled for security
!                        encompassed by physical barriers and to which access is' controlled for security purposes, i
: purposes, i
Rev.0 1
Rev.0 1
l'
l'
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3-8                   1997 Evaluated Exercise 3.3.31 PROTECTIVE ACTION: Those emergency measures taken after an uncontrolled release has occurred, for the purpose of preventing or minimizing radiological dose to persons that would likely be exposed if the action was not taken.
3-8 1997 Evaluated Exercise 3.3.31 PROTECTIVE ACTION: Those emergency measures taken after an uncontrolled release has occurred, for the purpose of preventing or minimizing radiological dose to persons that would likely be exposed if the action was not taken.
3.3.32 PROTECTIVE ACTION GUIDES (PAGs): Projected radiological dose or dose commitment value to individuals in the general population which warrant protective action.
3.3.32 PROTECTIVE ACTION GUIDES (PAGs): Projected radiological dose or dose commitment value to individuals in the general population which warrant protective action.
3.3.33 RADIOLOGICALLY RESTRICTED AREA (RRA): Any area accessed which                           '
3.3.33 RADIOLOGICALLY RESTRICTED AREA (RRA): Any area accessed which 1
1 is limited by the Licensee for the purpose of protecting individuals against undue risks from exposure to mdiation or radioactive materials.
is limited by the Licensee for the purpose of protecting individuals against undue risks from exposure to mdiation or radioactive materials.
3.3.34 RADIOLOGICAL MONITORING TEAMS (RMTs): Two-person teams responsible for monitoring radiation levels in the environment and collecting           l soil, air, vegetation, snow, and water samples for laboratory analysis.
3.3.34 RADIOLOGICAL MONITORING TEAMS (RMTs): Two-person teams responsible for monitoring radiation levels in the environment and collecting soil, air, vegetation, snow, and water samples for laboratory analysis.
3.3.35 SITE AREA EMERGENCY: The level of emergency classification which                         l indicates that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any       j releases of radioactive material are not expected to exceed Protective Action Guide (PAG) exposure levels, except near the Site Boundary.                             j 3.3.36 TECHNICAL SUPPORT CENTER (TSC): An onsite emergency response facility for use by technical and management personnel in support of the command and control functions executed in the Control Room.                             ;
3.3.35 SITE AREA EMERGENCY: The level of emergency classification which indicates that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any j
3.3.37 UNUSUAL EVENT: The lowest level of emergency classification, which                       !
releases of radioactive material are not expected to exceed Protective Action Guide (PAG) exposure levels, except near the Site Boundary.
indicates events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant.
j 3.3.36 TECHNICAL SUPPORT CENTER (TSC): An onsite emergency response facility for use by technical and management personnel in support of the command and control functions executed in the Control Room.
3.3.37 UNUSUAL EVENT: The lowest level of emergency classification, which indicates events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant.
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5.0 SCHEDULE OF EVENTS 5.1 TIMES AND PLACES
!          5.1 TIMES AND PLACES
)
!                                                                                                    )
Preparatory meetings held prior to the week of the Exercise will be schedule and coordinated by the Emergency Preparedness Staff. The meetings schedule for the week of the Exercise will be held with Tables 5.1-1 and Table 5.1-2.
Preparatory meetings held prior to the week of the Exercise will be schedule and   .
Schedule of Meetings Table 5.1-1 j
coordinated by the Emergency Preparedness Staff. The meetings schedule for the week )
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of the Exercise will be held with Tables 5.1-1 and Table 5.1-2.
t Date/ rime 1Yhere
Schedule of Meetings                                 ;
.Whal June 2,1997 Energy Education Center Utility Controllers 1000 -1200 DBNPS Admin Building Final Briefing June 2,1997 Room 209/210 NRC/ Lead Controllers 1430 - 1600 DBNPS Admin. Building NRC Entrance / Briefing / fours June 3,1997 Energy Education Center Utility Players Briefing 1500 - 1545 DBNPS Admin Building June 4,1997 All Facilities Exercise June 5,1997 Energy Education Center Utility Controller Debriefing 0800 - 1200 DBNPS Admin Building June 6,1997 Energy Education Center Utility Player /NRC Critique 0800 - 1100 DBNPS Admin Building June 6,1997 To Be Determined FEMA /NRC Public Meeting l
Table 5.1-1                                     j
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Date/ rime                       1Yhere                         .Whal                   !
1 June 2,1997               Energy Education Center       Utility Controllers 1000 -1200               DBNPS Admin Building         Final Briefing June 2,1997               Room 209/210                 NRC/ Lead Controllers 1430 - 1600               DBNPS Admin. Building         NRC Entrance / Briefing / fours !
June 3,1997               Energy Education Center       Utility Players Briefing 1500 - 1545               DBNPS Admin Building June 4,1997               All Facilities               Exercise June 5,1997               Energy Education Center       Utility Controller Debriefing 0800 - 1200               DBNPS Admin Building June 6,1997               Energy Education Center       Utility Player /NRC Critique 0800 - 1100               DBNPS Admin Building June 6,1997               To Be Determined             FEMA /NRC Public Meeting l
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5-2                   1997 Evaluated Exercise Schedule of Meetings Table 5.1-2 Date/Fime                                       Where                                             What June 3,1997                                 EEC Conference Area             Exercise Offsite Controller Briefing Davis-Besse Admin Building June 4,1997 (All Day)                       Offsite Facilities               Exercise June 5,1997                                 Emergency Preparedness           Exercise Offsite Controller Deriefing DBNPS Admin Building (Second Floor) i h
5-2 1997 Evaluated Exercise Schedule of Meetings Table 5.1-2 Date/Fime Where What June 3,1997 EEC Conference Area Exercise Offsite Controller Briefing Davis-Besse Admin Building June 4,1997 (All Day)
Offsite Facilities Exercise June 5,1997 Emergency Preparedness Exercise Offsite Controller Deriefing DBNPS Admin Building (Second Floor) i h
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* 5-3                   1997 Evaluated Exercise l               5.2 OBSERVER APPROVAL Permission to observe the Exercise must be obtained from:
 
Davis-Besse Nuclear Power Station                       State of Ohio
5-3 1997 Evaluated Exercise l
!                                                                                                                  L Mr. Patrick J. McCloskey, Supervisor                     Mr. Larry Grove, Chief               -
5.2 OBSERVER APPROVAL Permission to observe the Exercise must be obtained from:
l                    Emergency Preparedness                                   Ohio Emergency Management Agency     .
Davis-Besse Nuclear Power Station State of Ohio L
Toledo Edison Company                                   Department of Public Safety 5501 N. State Route 2, Stop DB 3060                     2855 W. Dublin-Granville Road         1 Oak Harbor, OH 43449-9760                               Columbus, OH 43235-2206 PH: (419) 321-7148                                       PH: (614) 889-7173 l                   FAX: (419) 249-2302                                     FAX: (614) 889-7183
Mr. Patrick J. McCloskey, Supervisor Mr. Larry Grove, Chief l
!                    Ottawa County                                           Sandusky County Mr. James P. Greer, Director                             Ms. Berdit;e Parish, Director         ;
Emergency Preparedness Ohio Emergency Management Agency Toledo Edison Company Department of Public Safety 5501 N. State Route 2, Stop DB 3060 2855 W. Dublin-Granville Road 1
l                    Ottawa County EMA                                       Sandusky County EMA                     l 315 Madison Street                                       100 N. Park Avenue Port Clinton, OH 43452                                   Fremont,OH 43420 PH: (419) 734-6901                                       PH: '(419)334-8933
Oak Harbor, OH 43449-9760 Columbus, OH 43235-2206 PH: (419) 321-7148 PH: (614) 889-7173 l
!                    FAX: (419) 249-2361                                     FAX: (419) 334-6427 Lucas County l
FAX: (419) 249-2302 FAX: (614) 889-7183 Ottawa County Sandusky County Mr. James P. Greer, Director Ms. Berdit;e Parish, Director l
        -            Mr. William S. Halsey, Director Lucas County EMA 2144 Monroe Street Toledo, OH 43624 l                    PH: (419) 249-0661 I
Ottawa County EMA Sandusky County EMA 315 Madison Street 100 N. Park Avenue Port Clinton, OH 43452 Fremont,OH 43420 PH: (419) 734-6901 PH: '(419)334-8933 FAX: (419) 249-2361 FAX: (419) 334-6427 Lucas County l
FAX: (419) 249-5360 5.3 IRAVEL INFORMATION This section provides travel information to those individuals from Corporate, other utilities, local / state / federal government, and/or other organizations who may participate ,
Mr. William S. Halsey, Director Lucas County EMA 2144 Monroe Street Toledo, OH 43624 PH: (419) 249-0661 l
in the Exercise.
I FAX: (419) 249-5360 5.3 IRAVEL INFORMATION This section provides travel information to those individuals from Corporate, other utilities, local / state / federal government, and/or other organizations who may participate in the Exercise.
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follows:
follows:
: 1. Air:                                                                             l Detroit Metro Airport                       (70 miles from Davis-Besse)
1.
Detroit, MI Toledo Express Airport                     (50 miles from Davis-Besse)
Air:
Detroit Metro Airport (70 miles from Davis-Besse)
Detroit, MI Toledo Express Airport (50 miles from Davis-Besse)
Toledo, OH i
Toledo, OH i
Cleveland Hopkins Airport                   (85 miles from Davis-Besse)
Cleveland Hopkins Airport (85 miles from Davis-Besse)
Cleveland, OH 4
Cleveland, OH 4
: 2. Automobile:
2.
Automobile:
The Davis-Besse Station is located on Ohio State Route 2, approximately 25 miles east of Toledo,10 miles northwest of Port Clinton, and 75 miles west of Cleveland along State Route 2.
The Davis-Besse Station is located on Ohio State Route 2, approximately 25 miles east of Toledo,10 miles northwest of Port Clinton, and 75 miles west of Cleveland along State Route 2.
: 3. Accommodations:                                                                 l Fairfield Inn (419) 732-2434                         Best Western (800) 231-4871 3760 East State Road                                 Port Clinton, OH Port Clinton, OH                                     Fremont, OH Comfort Inn (419) 732-2929                           Comfort Inn (419) 691-8911 1723 East Perry Street                               2930 Navarre Avenue (SR 2)
3.
Port Clinton, OH                                     Oregon, OH OurGuest (419) 734-3000                             Holiday Inn (800)465-4329 2039 E. Harbor Road                                 Toledo, OH Port Clinton, OH                                     Fremont, OH Sandusky, OH Maumee Bay Resort & Conference Center               Days Inn (419) 734-4945 1750 Park Road #2                                   2149 E. Gill Road Oregon, Oli 43618-9700                               Port Clinton, OH (419)836-1466 t
Accommodations:
Fairfield Inn (419) 732-2434 Best Western (800) 231-4871 3760 East State Road Port Clinton, OH Port Clinton, OH Fremont, OH Comfort Inn (419) 732-2929 Comfort Inn (419) 691-8911 1723 East Perry Street 2930 Navarre Avenue (SR 2)
Port Clinton, OH Oregon, OH OurGuest (419) 734-3000 Holiday Inn (800)465-4329 2039 E. Harbor Road Toledo, OH Port Clinton, OH Fremont, OH Sandusky, OH Maumee Bay Resort & Conference Center Days Inn (419) 734-4945 1750 Park Road #2 2149 E. Gill Road Oregon, Oli 43618-9700 Port Clinton, OH (419)836-1466 t
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Latest revision as of 17:21, 11 December 2024

Rev 0 to 1997 Evaluated Exercise for Dbnps
ML20140B618
Person / Time
Site: Davis Besse 
Issue date: 06/04/1997
From:
CENTERIOR ENERGY
To:
Shared Package
ML20007F471 List:
References
NUDOCS 9703170081
Download: ML20140B618 (20)


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bi 1997 Evaluated Exercise 1.0 SCOPE AND OBJECTIVES NOTE In the development of an accident sequence, which is severe enough to adequately test the emergency response capabilities, it is necessary to postulate extremely unrealistic situations and multiple failures of redundant reactor protection functions and systems. Although the possibility of these events occurring is remote, Players are reminded that they are to respond to the indications as if they were real.

1.1 SCOPE The June 4,1997 Davis-Besse Emergency Preparedness Partial Participation Exercise will test and provide the opponunity to evaluate the Davis-Besse Emergency Plan and

)

Procedures. It will test the Emergency Response Organization's ability to assess and respond to emergency conditions and take actions to protect the health and safety of the public and station personnel.

This Partial Participation Exercise will also demonstrate activation and operation of major elements of the Non-utility Emergency Response Organization (ERO). The non-utility ERO responding will include Ottawa, Lucas and Sandusky Counties, and the State of Ohio. Those functions that are most scenario dependent will be played in sequence. However, most non-utility field activities will be played out-of-sequence.

Whenever practical, this Exercise incorporates provisions for " free play" on the part of the participants. Selected "real time" activities will be conducted to allow the repair teams the opportunity to provide service and repairs to station equipment during the course of the Exercise. These " repairs" will allow the response organization to have an increased impact upon the direction that the Exercise proceeds as well as impacting the completion of the Exercise activities. In addition, the Control Room Simulator will be used to permit a degree of" free play" on the part of the Operations staff. The extent of this " free play" may be partially restricted by Controllers as necessary to keep the sequence of events on track.

The scenario will simulate events resulting in a radiological release to the environment.

This release will be of sufficient magnitude to warrant mobilization of state and local agencies.

The scenario will also incorporate an out-of-sequence medical drill with panicipation l

l by local emergency medical services and support hospitals.

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- 1.2 OBJECTIVES The objectives for this Partial Participation Exercise have been selected from l

RA-EP-00200, Emergency Plan Drill and Exercise Program procedure (Utility) and from FEMA REP 14 and 15 (Non-Utility). The scenario has been designed such that each participating organization will be provided with the opportunity to demonstrate their selected objectives. Some non-utility objectives will be demonstrated out-of-sequence to accommodate the responding volunteer organization.

1.2.1 DAVIS-BESSE NUCIPAR POWER STATION UTILITY OBJECTIVES l

i The utility objectives are cross-referenced to RA-EP-00200, Emergency Plan l

Drill and Exercise Program, Attachment 1, Six-Year Exercise Plant, in the first I

column. The " FACILITIES" column identified the area that the objective is applicable. During the conduct of the Exercise, unidentified objectives may be successfully accomplished by the ERO. Credit will be given for the objectives and their performance will be documented in the Exercise Report.

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FACILITIES OBJECTIVE i

A.1 Administrative CONDUCT AN ASSESSMENT OF THE DBNPS EMERGENCY PLAN.10 CFR 50 APPENDIX E, SECTION IV.F.2.

l A.2 Administrative PROVIDE AN OPPORTUNITY FOR THE STATE, OTTAWA AND LUCAS COUNTIES TO PARTICIPATE IN AN EXERCISE l

BIENNIALLY.

A.3 Administrative PREPARE AN EXERCISE INFORMATION PACKAGE TO MEET MINIMUM STANDARDS.

A.4 Administrative CONDUCT A CRITIQUE OF THE EXERCISE.

l A.5 Administrative ESTABLISH MEANS TO ENSURE COMPLETION OF CORRECTIVE ACTIONS.

A.6 Administrative INVOLVE FEDERAL, STATE, COUNTY AND EP RESPONSE PERSONNEL AND AGENCIES IN A JOINT EXERCISE AT LEAST EVERY TWO YEARS.

A.9 Administrative CONDUCT THE EXERCISE IN VARIOUS WEATHER CONDITIONS (DURING DIFFERENT SEASONS).

B.1 All DEMONSTRATE THE DIRECTION OF 'I HE EMERGENCY j

ORGANIZATION AND IMPLEMENTATION OF THE EMERGENCY PLAN AND EMERGENCY PLAN PROCEDURES.

B.2 Control Room, DEMONSTRATE TE E TRANSFER OF THE EMERGENCY ECC DIRECTOR DUTIES.

i B.3 All DEMONSTRATE THE ABILITY FOR TIMELY ACTIVATION AND STAFFING OF THE EMERGENCY FACILITIES.

i B.4 All DEMONSTRATE THE ABILITY TO CONTROL ACCESS TO EMERGENCY FACILITIER C.1 Control Room, DEMONSTRATE THE AdlLITY TO ASSESS THE INCIDENT TSC CONDITIONS.

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~1.2 DAVIS-BESSE NUCLEAR POWER STATION OBJECTIVES (Cont'd)

REF.

FACILITIES OBJECTIVE C.2 Control Room, DEMONSTRATE THE ABILITY TO RECOGNIZE EMERGENCY

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L ECC, TSC ACTION LEVELS (EAL'S) AND PROPERLY CLASSIFY THE I

INCIDENT.

D.I Control Room, DEMONSTRATE THE ABILITY TO NOTIFY KEY OFFICIALS ECC IN THE EMERGENCY ORGANIZATION, VIA NOTIFICATION SYSTEM / PROCEDURES WITHIN 15 MINUTES OF -

CLASSIFICATION.

D.2 Control Room, DEMONSTRATE THE ABILITY TO NOTIFY THE NRC OF ANY ECC EMERGENCY CLASSIFICATION WITHIN ONE HOUR OF THE OCCURRENCE.

D.3 All DEMONSTRATE THE CAPABILITY TO NOTIFY AND/OR ACTIVATE EMERGENCY PERSONNEL IN EACH RESPONSE j

ORGANIZATION.

j D.4 Control Room, DEMONSTRATE THE ABILITY TO DEVELOP AND SEND AN ECC INITIAL EMERGENCY MESSAGE FOR OFFSITE NOTIFICATION.

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D.5 Control Room, DEMONSTRATE THE ABILITY TO DEVELOP AND SEND j

ECC FOLLOW-UP MESSAGES FOR INFO'RMATION FOR OFFSITE AUTHORITIES.

D.6

  • Control Room, DEMONSTRATE THE COMMUNICATIONS CAPABILITY TSC, ECC AMONG THE CONTROL ROOM,TSC AND ECC, AND AMONG DBNPS, THE STATE OF OHIO, O'ITAWA COUNTY, AND LUCAS COUNTY EMERGENCY OPERATIONS CENTERS AND THE FIELD ASSESSMENT TEAMS, TO INCLUDE EVALUATION OF THE ABILITY TO UNDERSTAND MESSAGE CONTENT (COMMUNICATIONS EXERCISE REQUIREMENT).

D.12 SEC DEMONSTRATE THE COMMUNICATIONS CAPABILITY WITH FIXED AND MOBILE SUPPORT FACILITY (MEDICAL DRILL REQUIREMENT). THIS OBJECTIVE WILL BE DONE OUT-OF-SEQUENCE.

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REF.

FACILITIES OBJECTIVE E.1 ECC DEMONSTRATE THE METHODS AND TECHNIQUES FOR l

DETERMINING THE SOURCE TERM OF RELEASES OR POTENTIAL RELEASES OF RADIOACTIVE MATERIAL j

WITHIN PLANT SYSTEMS.

E.2 ECC,TSC DEMONSTRATE THE METHODS AND TECHNIQUES FOR DETERMINING THE MAGNITUDE OF THE RELEASES OF l

RADIOACTIVE MATERIALS BASED ON PLANT SYSTEM PARAMETERS AND EFFLUENT MONITORS.

E.3 ECC DEMONSTRATE THE ABILITY TO ESTIMATE INTEGRATED DOSE FROM PROJECTED AND ACTUAL DOSE RATES AND TO COMPARE THESE ESTIMATES WITH THE PAG'S.

E.4 OSC DEMONSTRATE THE ABILITY TO IMPLEMENT EXPOSURE GUIDELINES.

E.5 OSC DEMONSTRATE THE ABILITY TO CONTINUOUSLY MONITOR AND CONTROL EMERGENCY WORKER EXPOSURE.

E.15 OSC,SEC DEMONSTRATE THE CAPABILITY FOR TRANSPORTATION OF A RADIOLOGICAL ACCIDENT VICTIM (MEDICAL DRILL REQUIREMENT). THIS OBJECTIVE WILL BE DONE OUT-OF-SEQUENCE.

E.16 RTL,OSC DEMONSTRATE THE CAPABILITY FOR ONSITE AND OFFSITE RADIOLOGICAL MONITORING TO INCLUDE COLLECTION A'ND ANALYSIS.

E.17 RTL DEMONSTRATE THE RESPONSE TO AND ANALYSIS OF SIMULATED EVALUATED AIRBORNE AND LIQUID SAMPLES AS WELL AS DIRECT RADIATION MEASUREMENTS IN THE ENVIRONMENT.

F.1 ECC DEMONSTRATE THE ABILITY TO RECOMMEND PROTECTIVE ACTIONS TO APPROPRIATE OFFSITE AUTHORITIES, BASES OF RECOMMENDATIONS TO INCLUDE j

i CONSIDERATION OF PROTECTION AFFORDED BY SHELTERING, AS WELL AS, EVACUATION TIME ESTIMATES.

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REF.

FACILITIES OBJECTIVE F.2 JPIC DEMONSTRATE THE OPERATION OF THE JOINT PUBLIC INFORMATION CENTER AND THE AVAILABILITY OF SPACE FOR THE MEDIA.

F.3 JPIC DEMONSTRATE THE ABILITY TO BRIEF THE MEDIA IN A CLEAR, ACCURATE AND TIMELY MANNER.

l F.11 OSC DEMONSTRATE THE CAPABILITY FOR ONSITE FIRST AID.

THIS OBJECTIVE WILL BE DONE OUT-OF-SEQUENCE.

F.12 OSC,RTL DEMONSTRATE THAT THE PROVISIONS ARE AVAILABLE FOR THE EVALUATION OF RADIATION EXPOSURE OF, AND RADIATION UPTAKE IN A RADIOLOGICAL ACCIDENT VICTIM.

G.1 ALL DEMONSTRATE PRELIMINARY DISCUSSION OF RE-ENTRY AND RECOVERY CAPABILITIES AND AVAILABILITY OF PROCEDURES.

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3.0 REFERENCES

/ ABBREVIATIONS / DEFINITIONS

3.1 REFERENCES

3.1.1 DBNPS Emergency Plan 3.1.2 DBNPS Emergency Plan Implementing Procedures 3.1.3 10 CFR 50.47,50.54 and Appendix E 3.1.4 DBNPS Radiation Protection Manual 3.1.5 DBNPS Offsite Dose Calculation Manual 3.1.6 DBNPS, Unit 1, Tecimical Specifications 3.1.7 DBNPS Piping and Instrumentation Drawings 3.1.8 DBNPS IJpdated Safety Analysis Report 3.1.9 Corporate Emergency Response (CER) Plan 3.1.10 Public Information Emergency Response Procedures 3.1.11 NUREG 0654/ FEMA REP-1 3.1.12 Ohio Plan for Response to Radiation Emergencies at Licensed Nuclear Facilities 3.1.13 Ottawa County Plant for Response to Radiation Emergencies at Licensed Nuclear Facilities 3.1.14 Lucas County Radiological Emergency Response Plan 3.1.15 Sandusky County Radiological Emergency Response Procedure Document 3.1.16 Erie County Radiolgocal Emergency Response Procedure Document 3.1.17 FEMA REP 14 3.1.18 FEMA REP 15 l

3.1.19 FEMA Guidelines, MS-1 3.2 ABBREVIATIONS AFP Auxiliary Feed (Water) Pump ALARA As Low As Reasonably Achievable ARM Area Radiation Monitor ARTS Anticipatory Reactor Trip System ATMOS Atmosphere ATWS Anticipated Transient Without Scram AUX Auxiliary AVG Average BAAT Boric Acid Addition Tank

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BKWSH Back Wash l

BRKR Electrical Circuit Breaker l

BWST Borated Water Storage Tank CAM Continuous Air Monitor CANS Computerized Automated Notification System CAS Central Alarm Station CCW Component Cooling Water System CERO Corporate Emergency Response Organization l

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CFR Code of Federal Regulations CNDS Condensate System COND Condenser CPM Counts Per Minute CRS Control Room Simulator l

CS-Containment Spray System CST Condensate Storage Tank j

CT Circulating Water and Cooling Tower System l

CTMT Reactor Containment Building CTRM Control Room l

DADS Data Acquisition and Display System DBAB Davis-Besse Administrative Building DBNPS Davis-Besse Nuclear Power Station l

DEI Dose Equivalent Iodine DEMIN Demineralizer DHR Decay Heat Removal DISCH Discharge DP Differential Pressure DWS Demineralized Water System EAL Emergency Action Level EAS Emergency Alert System ECC

EOC Emergency Operations Center EPZ Emergency Planning Zone j

EVAL Evaluated j

FAT First Aid Team FEMA Federal Emergency Management Agency FT Feet FW Feed Water GPM Gallons Per Minute HDR Header HLCWT High Level Cooling Water Tank HPI High Pressure Injection System HVAC Heating Ventilation and Air Conditioning System HX Heat Exchanger I&C Instrument and Control Section l

L IF Instructor Facility (at the CRS) l IN Inch INST Instrument i

JPIC Joint Public Infonnation Center f

KI Potassium lodide Rev.0

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LVL Level MISC Miscellaneous MSIV Main Steam Isolation Valve MTR Motor MU Makeup System l

NI Nuclear instrumentation NRC Nuclear Regulatory Commission OTSG Once Through Steam Generator i

OOS Out of Service OSC Operations Support Center PA Public Address System PASS Post Accident Sampling System PC Protective Clothing PI Pres sure Indication PMP Pu:np PORV Power Operated Relief Valve PPF Personnel Processing Facility PR Public Relations PSF Personnel Shop Facility PSIA Pounds Per Square Inch Absolute PSIG Pounds Per Square Inch Gauge PT Periodic Test PTS Pressurized Thermal Shock PWR Pressurized Water Reactor PWST Primary Water Storage Tank PZR Pressurizer RRA Radiologically Restricted Area RC Radiological Controls RCP Reactor Coolant Pump RCS Reactor Coolant System lE Fixed Radiation Instrument RLF ReliefValve RM Radiation Monitor RMT Radiation Monitoring Team RP Radiation Protection RTL Radiological Testing Laboratory Rx Reactor SAS Secondary Alarm System SFP Spent, Fuel Pool l

SFAS Safety Features Actuation System i

SFRCS Steam and Feed Water Rupture Control System l

SJAE Steam Jet Air Ejector l

SPDS Safety Parameter Display System SPF Spent Fuel Rev.O

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3-4 1997 Evaluated Exercise SRST Spent Resin Storage Tank ST Surveillance Test i

-SW' Service Water System SYS System Tc Reactor Coolant System Cold Leg Temperature TC Thermocouple TDG Total Dissolved Gases Th Reactor Coolant System Hot Leg Temperature TPCW Turbine Plant Cooling Water

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TRBL Trouble TSC-Technical Support Center VOM Volt Ohm Meter l'

WGST Waste Gas Storage Tank WK Week WR Wide Range Instrument WTR Water.

XFER Transfer i

XMIT Transmit -

3.3 DEFINITIONS

3.3.1 ALERT

The level of emergency classification which indicates events are in progress or have occurred which involve an actual or potential' substantial '

l degradation of the level of safety of the plant.

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3.3.2 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS): Failure of the reactor control rods to insert into the core upon a signal to do so from the Reactor Protection System or the failure of the Reactor Protection System to trip when limits have been exceeded.

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3.3 ASSESSMENT

ACTIONS: Those actions taken during or after an accident to obtain and process information that is necessary to make decisions to implement specific emergency measures.

l 3.3.4 CONTROL ROOM (CTRM): The principle onsite location from which the reactor is controlled and from which emergency control is initially exercised.

i The CTRM is located on the 623' elevation of the Auxiliary Building.

3.3.5 CONTROLLER

A member of the control group, assigned to one or more activities or functions for the purpose of keeping the action going according to a i

scenario, resclving scenario discrepancies, and supervising the actions of the I

players.

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3-5 1997 Evaluated Exercise l

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3.3.6. CORRECTIVE ACTIONS: Those emergency measures taken to mitigate or terminate a potential or uncontrolled release of radioactive material or to j

minimize the consequences of such a release.

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3.3.7 DECONTAMINATION

The process by which the body or an object is relieved of radioactive substances (contamination).

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i 3.3.8 DOSE ASSESSMENT: The process of estimating the amount of radiation a person will potentially receive as a result of exposure to a radiological release.

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3.3.9 DRILL

A supervised instruction period aimed at testing, developing, and l

maintaining skills in a particular operation.

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3.3.10 EMERGENCY ACTION LEVELS (EALs)- Radiological dose rates; specific l

contamination levels or airborne, waterborne, or surface-deposited concentrations of radioactive materials, or specific instrument readings and indications (including their rate of change) that may be used as thresholds for l

initiating specific emergency measures.

l 3.3.11 EMERGENCY CONTROL CENTER (ECC): The Davis-Besse Emergency Response Facility from which overall direction and control are exercised for emergencies at DBNPS. The facility also provides a central point of contact with extemal organizations, and is fully activated for emergencies classified as j

l an ALERT or higher.

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l 3.3.12 EMERGENCY OPERATIONS CENTER (EOC): An offsite location used by state, county and other government agencies and organizations to perform '

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l radiological assessment and to coordinate offsite activities. The EOCs are located as follows:

l Ottawa County:

Ottawa County Emergency Management Agency 315 Madison Avenue Port Clinton, Ohio 43452 Lucas County:

Lucas County Emergency Management Agency 2144. Monroe Street l

Toledo, Ohio 43624 t

l State of Ohio:

Emergency Operations Center / Joint Dispatch Facility 2855 West Dublin-Granville Rd.

Worthington, Ohio 43235-2206 State of Michigan: Emergency Management Division Suite 300 i

3005 Washington Square I

Lansing, Michigan 48913 i

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3-6 1997 Evaluated Exercise 3.3.

EMERGENCY PLANNING ZONES (EPZs): Two zones established around a l

nuclear power station in which predetermined protective action plans are needed. One zone, with a radius of 10 miles (16090 meters) for a PLUME EXPOSURE PATHWAY; and the other with a radius of 50 miles (80450 meters) for an INGESTION EXPOSURE PATHWAY. In these zones, predetermine PROTECTIVE ACTION plans are needed.

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3.3.14 EMERGENCY RESPONSE FACILITY: Any of several onsite and offsite centers which are activated to coordinate emergency actions. Included in this category are the Control Room, Technical Support Center, Operations Support f

Center, Emergency Control Center, Joint Public Information Center, and State and local Emergency Operations Centers.

3.3.15 EVALUATOR: A member of the evaluation group, assigned to one or more j

activities or functions for the purpose of evaluating and making recommendations for improvement. An evaluator may serve in a dual capacity as both a Controller and Evaluator.

3.3.16 EXCLUSION AREA: The area surrounding the plant in which the Licensee has the authority to determine all activities including exclusion or removal of persons and property from the area.

3.3.17 EXERCISE: An event that tests the integrated capability and a major portion of the basic elements within the Emergency Plan.

3.3.18 GENERAL EMERGENCY: The most severe level of emergency classification which indicates that events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Release of radioactive material can be reasonably expected to exceed PAG exposure levels offsite.

3.3.19 INGESTION PATHWAY: The means by which contaminated water or foodstuff can expose the POPULATION-AT-RISK to radiation. The time of potential exposure could range from hours to months. The principal exposure sources from this pathway are:

1. Ingestion of contaminated drinking supplies, such as water or milk.
2. Ingestion of contaminated food, such as fresh vegetables or aquatic foodstuff.

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3.3.20 JOINT PUBLIC INFORMATION CENTER (JPIC): A location for coordinating news releases and providing joint briefings to the news media j

during an emergency. It provides a central point for information to be disseminated to the public by the utility, the federal, state and local officials.

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3.3.21 OBSERVER: Any individual who is authorized to observe, but is not authorized to interact with the players.

3.3.22 OFFSITE: Any areas outside the Owner Controlled Area.

3.3.23 ONSITE: The area within the Owner Controlled Area.

l 3.3.24 OPERATIONS SUPPORT CENTER (OSC): An onsite emergency response facility which provides a location where emergency response teams can be t

assembled and coordinated during an emergency.

3.3.25 OWNER CONTROLLED AREA: The area contiguous with the Protected Area, designated by the owner organization to be patrolled for security j

purposes.

l 3.3.26 PARTICIPANT: An individual who has some part, whether as an Evaluator, Controller, Player or Observer.

3.3.27 PLAYERS: Allindividuals who are assigned to perform functions of the Emergency Response Organization, as described in the appropriate Emergency Plan Implementing Procedures.

3.3.28 PLUME EXPOSURE PATHWAY: The means by which a radioactive cloud (plume) can expose the POPULATION-AT-RISK to radiation. The time of potential exposure could range from hours to days. The principal exposure l

sources for this pathway are as follows:

1. Whole body external exposure to gamma radiation from the radioactive plume and from deposited material.
2. Inhalation exposure from the passing radioactive plume.

l 3.3.29 POPULATION AT RISK: Those persons for whom protective actions are being or would be taken.

3.3.30 PROTECTED AREA: The area within the Owner-Controlled Area encompassed by physical barriers and to which access is' controlled for security

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3-8 1997 Evaluated Exercise 3.3.31 PROTECTIVE ACTION: Those emergency measures taken after an uncontrolled release has occurred, for the purpose of preventing or minimizing radiological dose to persons that would likely be exposed if the action was not taken.

3.3.32 PROTECTIVE ACTION GUIDES (PAGs): Projected radiological dose or dose commitment value to individuals in the general population which warrant protective action.

3.3.33 RADIOLOGICALLY RESTRICTED AREA (RRA): Any area accessed which 1

is limited by the Licensee for the purpose of protecting individuals against undue risks from exposure to mdiation or radioactive materials.

3.3.34 RADIOLOGICAL MONITORING TEAMS (RMTs): Two-person teams responsible for monitoring radiation levels in the environment and collecting soil, air, vegetation, snow, and water samples for laboratory analysis.

3.3.35 SITE AREA EMERGENCY: The level of emergency classification which indicates that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any j

releases of radioactive material are not expected to exceed Protective Action Guide (PAG) exposure levels, except near the Site Boundary.

j 3.3.36 TECHNICAL SUPPORT CENTER (TSC): An onsite emergency response facility for use by technical and management personnel in support of the command and control functions executed in the Control Room.

3.3.37 UNUSUAL EVENT: The lowest level of emergency classification, which indicates events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant.

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5.0 SCHEDULE OF EVENTS 5.1 TIMES AND PLACES

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Preparatory meetings held prior to the week of the Exercise will be schedule and coordinated by the Emergency Preparedness Staff. The meetings schedule for the week of the Exercise will be held with Tables 5.1-1 and Table 5.1-2.

Schedule of Meetings Table 5.1-1 j

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t Date/ rime 1Yhere

.Whal June 2,1997 Energy Education Center Utility Controllers 1000 -1200 DBNPS Admin Building Final Briefing June 2,1997 Room 209/210 NRC/ Lead Controllers 1430 - 1600 DBNPS Admin. Building NRC Entrance / Briefing / fours June 3,1997 Energy Education Center Utility Players Briefing 1500 - 1545 DBNPS Admin Building June 4,1997 All Facilities Exercise June 5,1997 Energy Education Center Utility Controller Debriefing 0800 - 1200 DBNPS Admin Building June 6,1997 Energy Education Center Utility Player /NRC Critique 0800 - 1100 DBNPS Admin Building June 6,1997 To Be Determined FEMA /NRC Public Meeting l

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5-2 1997 Evaluated Exercise Schedule of Meetings Table 5.1-2 Date/Fime Where What June 3,1997 EEC Conference Area Exercise Offsite Controller Briefing Davis-Besse Admin Building June 4,1997 (All Day)

Offsite Facilities Exercise June 5,1997 Emergency Preparedness Exercise Offsite Controller Deriefing DBNPS Admin Building (Second Floor) i h

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5.2 OBSERVER APPROVAL Permission to observe the Exercise must be obtained from:

Davis-Besse Nuclear Power Station State of Ohio L

Mr. Patrick J. McCloskey, Supervisor Mr. Larry Grove, Chief l

Emergency Preparedness Ohio Emergency Management Agency Toledo Edison Company Department of Public Safety 5501 N. State Route 2, Stop DB 3060 2855 W. Dublin-Granville Road 1

Oak Harbor, OH 43449-9760 Columbus, OH 43235-2206 PH: (419) 321-7148 PH: (614) 889-7173 l

FAX: (419) 249-2302 FAX: (614) 889-7183 Ottawa County Sandusky County Mr. James P. Greer, Director Ms. Berdit;e Parish, Director l

Ottawa County EMA Sandusky County EMA 315 Madison Street 100 N. Park Avenue Port Clinton, OH 43452 Fremont,OH 43420 PH: (419) 734-6901 PH: '(419)334-8933 FAX: (419) 249-2361 FAX: (419) 334-6427 Lucas County l

Mr. William S. Halsey, Director Lucas County EMA 2144 Monroe Street Toledo, OH 43624 PH: (419) 249-0661 l

I FAX: (419) 249-5360 5.3 IRAVEL INFORMATION This section provides travel information to those individuals from Corporate, other utilities, local / state / federal government, and/or other organizations who may participate in the Exercise.

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Once permission is obtained to attend the Exercise, accommodations can be made as l

follows:

1.

Air:

Detroit Metro Airport (70 miles from Davis-Besse)

Detroit, MI Toledo Express Airport (50 miles from Davis-Besse)

Toledo, OH i

Cleveland Hopkins Airport (85 miles from Davis-Besse)

Cleveland, OH 4

2.

Automobile:

The Davis-Besse Station is located on Ohio State Route 2, approximately 25 miles east of Toledo,10 miles northwest of Port Clinton, and 75 miles west of Cleveland along State Route 2.

3.

Accommodations:

Fairfield Inn (419) 732-2434 Best Western (800) 231-4871 3760 East State Road Port Clinton, OH Port Clinton, OH Fremont, OH Comfort Inn (419) 732-2929 Comfort Inn (419) 691-8911 1723 East Perry Street 2930 Navarre Avenue (SR 2)

Port Clinton, OH Oregon, OH OurGuest (419) 734-3000 Holiday Inn (800)465-4329 2039 E. Harbor Road Toledo, OH Port Clinton, OH Fremont, OH Sandusky, OH Maumee Bay Resort & Conference Center Days Inn (419) 734-4945 1750 Park Road #2 2149 E. Gill Road Oregon, Oli 43618-9700 Port Clinton, OH (419)836-1466 t

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