ML20206D930
| ML20206D930 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 04/27/1999 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| References | |
| NUDOCS 9905040288 | |
| Download: ML20206D930 (300) | |
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VERMONT YANKEE NUCLEAR POWER STATION VERNON, VERMONT p-k/
O 1599 EMERGENCY PREPAREDNESS EXERCISE APRIL 27,1999 1
EXERCISE MANUAL (PLUME PORTION)
VERMONT YANKEE NUCLEAR POWER CORPORATION EXERCISE MATERIAL O 040074
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 TABLE OF CONTENTS Section Iftlt Rev.
1.0 LNTRODUCTION 1.1 Exercise Schedule 0 1.2 Participating Centers / Agencies 1 2.0 EXERCISE OBJECTIVES AND EXTENT OF PLAY 2.1 Vermont Yankee 0 2.2 . State of Vermont 04/15/99 2.3 State of New Hampshire 03/19/99 2.4 Commonwealth of Massachusetts 03/08/99 3.0 EXERCISE GUIDELINES AND SCOPE 3.1 Exercise Guidelines and Ground Rules 1 3.2 Procedure Execution List i O 4.0 CONTROli FR INFORMATION 4.1 ControllerAssignments 0 4.2 Controller Exercise Guidance 1 4.3 Controller Evaluston Criteria 1 5.0 EXERCISE SCENARIO 5.1 initial Conditions 1 5.2 Exercise Sequence of Events 1 5.3 Scenario Timeline 0 6.0 EERCISE MESSAGES 6.1 Command Cards 1 6.2 Message Cards 1 7.0 STATION EVENT DATA O 7.1 Events Summary 0 d 7.2 Event Mini-scenarios 0
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l l VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY PREPAREDNESS EXERCISE l- 1999
!O TABLE OF CONTENTS (continued) l l
l Section Title Pev.
8.0 OPERATIONAL DATA 0 9.0 RADIOLOGICAL DATA 9.1 Area Radiation Monitors 0 i
, 9.2 Process Monitors 0 9.3 In-Plant Radiation Levels 0 i 9.4 Plant Chemistry Data 0 9.5 Plant Stack Release Data 0 9.6 Field Monitoring Maps and Data 0 10.0 METEOROLOGICAL DATA 10.1 On-Site Meteorological Data 1
'O 10.2 General Area NWS Forecasts 0 i
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i I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999
.L1 EXERCISE SCHEDULE NOTE: EXERCISE SCHEDULE TO BE ISSUED UNDER SEPARATE MEMO AND REVIEWED AT THE EXERCISE CONTROLLER BRIEFING SESSIONS. ,
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v VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 12 PARTICIPATING CENTERS / AGENCIES VERMONT YANKEE NUCLEAR POWER CORPORATION Vermont Yankee Emergency Response Organization fAGilitift Vermont Yankee Nuclear Power Station - Vemon, Vermont
. Control Room (notification and communications functions only)
. Technical Support Center (2nd floor of Administration Building) g . Operations Support Center (1st floor of A6ninistration Building)
. Energy Information Center (Govemor Hunt House)
Vermont Yankee Training Center Brattleboro, Vermont
. Simulator Room (Control Room functions,1st floor of Training Center)
. Emergency Operations Facility / Recovery Center (1st floor of Training Center)
. News Media Center (1st and 2nd floor of Training Center)
DUKE ENGINEERING & SERVICES Duke Engineering & Service Office - Bolton, Massachusetts j Facility l
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. Engineering Support Center g
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i Rev.1 Page 1.2-2 p STATE OF VERMONT ]
l O Kev Partmioabna State Aaencies
. Vermont Emergency Management
. Vermont State Health Depa tment Facdities
. State Waming Point, Vermont State Police - Waterbury, Vermont
. Emergency Operations Center - Waterbury, Vermont
- . Incident Field Office - Dummerston, Vermont
. Department of Health Laboratory - Burlington, Vermont
. Emergency Operations Facirrty/ Recovery Center - Brattleboro, Vermont
. News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont j l
Kev Parteioatina Local Aaencies
. Brattleboro, Dummerston, Guilford, Halifax and Vemon Emergency Management Agencies Facdities
. Brattleboro Emergency Operations Center (EOC) - Brattleboro Town Hall
. Dummerston EOC - Dummerston Town Office Building
. Guilford EOC -Guilford Fire Station
. Halifax EOC- Halifax Fire Station
. Vemon EOC- Vemon Fire Station Miscellaneous Parteioants/ Facilities Schools
. Interviews with School /Daycare Principals and Directors
. LaidlawTransportation Soecial Pooulat'on Center
. Linden Lodge
. Thornpson House l
. Brattleboro Retreat
. Rescue Inc.
%J Rado Staten
. WTSA, Brattleboro, VT l
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Rev.1 Page 1.2-3 STATE OF NEW HAMPSHIRE
-v Kev Particioatina State Aoenc'es
. New Hampshire Office of Emergency Management
. New Hamps;iire Division of l'ublic Health Services Facilmes
. State Police Communications Center - Concord, New Hampshire
. State Police Troop C - Keene, New Hampshire
. Southwestem NH District Fire Mutual Aid Keene, New Hampshire o Emergency Operations Center - Concord, New Hampshire
. Incident Field Office - Keene, New Hampshire
. Emergency Operations Facifity/ Recovery Center - Brattleboro, Vermont
. News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont Kev Partichuatina Local Aaencies
. Chesterfield, Hinsdale, Richmond, Swanzey and Winchester Emergency Management Agencies Facilities
. Chesterfield Emergency Operations Center (EOC) Chesterfield Fire Dept.
. Hinsdale EOC Hinsdale Fire Station / Town Hall
. Richmond EOC - Richmond Civil Defense Building
. Swanzey EOC - Swanzey Center Fire Station
. Winchester EOC - Winchester Emergency Service Building Miscellaneous Particioants/ Facilities Schools
. School Administration interviews Receoten Center
. Keene State College Reception /Decon Center Radio Station
. WKNE, Keene, NH
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. COMMONWEALTH OF MASSACHUSETTS Kev Partmioatina State Aaencies
. Massachusetts Emergency Management Agency
. Massachusetts Department of Public Health
. Nuclear incident Advisory Team (field monitoring teams)
. Massachusetts State Police
. Dept. of Environmental Management, District 9 Fire Warden
. Dept. of Fish, Wildlife, & Environmental Law Enforcement EKM!f.il
. Emergency Operations Center - Framingham, Massachusetts
. Area Ill Emergency Operations Center - Belchertown, Massachusetts
. MA State Police Troop B Headquarters Northhampton, Massachusetts
. MA State Police Barracks Dispatch Center- Shelburne, Massachusetts
. Emergency Operations Facility / Recovery Center - Brattleboro, Vermont
. News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont Kev Particioatina Local Aoencies/Oraanizations
. Bemardston, Coirain, Gill, Greenfield, Leyden, Northfield and Warwick Emergency Management Agencies Facilities
. Bemardston Emergency Operations Center (EOC) - Bemardston Fire Station
. Coirain EOC - Colrain Fire Station
. Gill EOC - Gill Fire Station
. Greenfield EOC - Greenfield Fire Station
. Leyden EOC- Leyden Fire Station
. Northfield EOC-Town Hall
. Warwick EOC -Warwick Fire Station 1
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Rev.1 Page 1.2-5 p COMMONWEALTH OF MASSACHUSETTS (continued)
- U Macellaneous Partietoants/ Facilities Schools
. The Giving Tree School, Gill Host Facilities for School Children
. Orange Armory Transoortaton Providers
. Greenfield-Montague Transportation Authority
. Wilson Bus Lines
. Liebenow, Inc.
Radic;ccic.al Monitorina and Decontamination Station
. Colrain O Special Pooulation Centers Q
. Massachusetts Department of Environmental Management District 9 Fire Warden (Northfield State Forest, Warwick Forest in Warwick, Warwick State Forest in Northfield, Mount Grace State Forest in Warwick, ,
Leyden State Forest)
. Massachusetts Department of Fisheries, Wildli's, and Environmental Law Enforcement, Division of Law Enforcement (Bennet Meadow at Route 10 and Connecticut River Bridge in Northf' eld, Captain Kids Island Camping and PicrJe Area in Northfield, Connecticut River Boat Ramp in Northfield, Munn's Ferry Camping and Picnic Area in Northfield, Pauchaug Meadow Wildlife Area in Northfield, Barton Cove Boat Ramp, Riverview Picnic Area in Northfield and Erving)
Rado Staten
. WHYN, Springfield l . WHAl, Greenfield
. WRSI, Greenfield l-Q C
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 2.1 VERMONT YANKEE - EXERCISE OBJECTIVES AND EXTENT OF PLAY O
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INTRODUCTION in order to demonstrate the emergency response preparedness of the Vermont Yankee Nuclear Power Station, an emergency preparedness exercise will be conducted on Tuesday, April 27,1999. This year's exercise is a full-participation biennial exercise, which will involve full participation from Vermont Yankee, State of Vermont, State of New Hampshire, Commonwealth of Massachusetts, and local communities within the plume exposure emergency planning zone (EPZ). In addition and following the plume portion of the exercise, the State of Vermont, the State of New Hampshire, and Commonwealth of Massachusetts will be given the opportunity to demonstrate FEMA REP-14 objectives involving the ingestion exposure EPZ.
The primary objective is to test some of the principal functional areas of Vermont Yankee's emergency response capabilities and to establish exercise objectives that will evaluate certain elements of Vermont Yankee's emergency preparedness program. Some of the objectives are based on previous inspection items from the NRC and corrective actions identified rnd taken by Vermont Yankee. The objectives are used to ascertain the required input to the scenario sequence of events and to establish the controller evaluation criteria.
Exercise objectives and extent of play are presented on the following pages.
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Rev. O P ge 2.1 -1 1999 VERMONT YANKEE EXERCISE OBJECTIVES AND EXTENT OF PLAY r Extent of Play Q Emeroency Classification and Accident Assessment
- 1. Demonstratetheabilityof ControlRoom personnelto A.1 Scenario events initiated on the simulator will recognize emergency initiating events and properly provide the operational and radiological data to classify the condition in accordance with allow personnel to demonstrate this objective in pre-established emergency action levels. accordance with Procedure AP 3125, Emergency Plan Classification and Action Level Scheme.
- 2. Demonstrate the ability of Control Room personnel A.2 The scenario will provide technical information to end Technical Support Center (TSC) staff to players that will allow them to analyze plant coordinate the assessment of plant conditions and conditions and initiate corrective actions in corrective actions to mitigate accident conditions. accordance with established procedures. Early in-plant actions normally performed by the Control Room support personnel may be controlled and performed by Simulator Controllers until after the Alert classification when the Emergency Response Organization is fully activated. Demonstrations of in-plant corrective actions are controlled in accordance with the defined exercise mini-A scenarios. Simulation of response activities will be controlled in accordance with the defined mini-scenarios and as specified in the exercise ground rules.
- 3. Demonstrate that information conceming plant A.3 Telephone communications and the Simulated Plant conditions can be transmitted between the Control Process Computer System (SPPCS) data link will Room and the TSC la a timely manner, be established between the Simulator Control Room and the various Emergency Response 1 Facilities in order to transmit key information and data.
- 4. Demonstrate the ability of the TSC staff to initiate and A.4 Scenario events will enable the TSC to coordinate ;
coordinate corrective actions in an efficient and timely in-plant corrective actions using Operations Support j manner. Center (OSC) personnel, i
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- 5. Demonstrate the ability of appropriate TSC staff to A.5 Scenario events will allow for the discussion participate with the Control Room and the Emergency between the Simulator Control Room (SCR), TSC Operations Facility / Recovery Center (EOF /RC in and EOF /RC staff on EALs and emergency l Emergent:y Action Levels (EALs) and classification classification decisions. l discussions.
' Indicates an identified obsesation from the 1998 Drill and/or 1997 Exercise. The description of the item is provided following each asterisk objective.
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Rrv. 0 l PIge 2.1 -2 A. Emeroency Classification and Accident Assessment (continued) Extent of Plav
- 6. Demonstrate the ability to assess data from A.6 Scenario events will allow Chemistry and Radiation appropriate chemistry samples in support of accident Protection technicians to simulate taking reactor tssessment activities and plant conditions, coolant, containment air, or plant vent stack samples to assess plant conditions. Actual sampling and actual manipulation of sampling system components will be simulated. Time frame to provide sample results will be controlled and compressed. Controllers will provide sample results after sampling activities are discussed by playerr
- 7. Demonstrate the ability to effectively use the A.7 Emergency Response Faciliti nformation i System Emergency Response Facility Information System (ERFIS) workstations in the TSC, EOF and ESC will (ERFIS) in the assessment and trending of plant be connected to the Simulator Control Room using conditions, the SPPCS to 'eive and display scenario-related data. (Controlios may also provide additional data to players as necessary.) This will allow Emergency Response Facility staff personnel the opportunity to ,
demonstrate the use of ERFIS under simulated
- emergency conditions.
l B. Notification and Communication Extent of Plav
- 1. Demonstrate the ability of Control Room personnel to B.1 Scenario events will allow Control Room personnel complete timely plant announcements of declared to make '! ant announcements for declared omergency classifications. emergency classifications.
l 2. Demonstrate that messages are tra ismitted in an B.2 Various communications links will be established cecurate and timely manner and that decisions, between emergency response facilities in order to l
information and messages are property logged and transmit information and data. Record keeping and documented. documentation will be demonstrated in accordance l with established procedures.
- 3. Demonstrate the capability to notify federal and state B.3 Vermont Yankee staff, NRC, and state authorities cuthorities of emergency classification and significant shall be notified in accordance with established changes in plant status in accordance with procedures. NRC will be notified by using the FTS established procedures. 2000 ENS telephone. The State authorities will be notified through the Nuclear Alert System (Orange Phone).
' Indicates an identified obse5ation from the 1998 Drill and/or 1997 Exercise. The description of the item is provided following each asterisk objectivo.
R;v.O P ge 2.1 -3 l
fm Q. Notification und Communication (continued) Extentof Plav
- 4. Demonstrate that appropriate status boards are used B.4 Status Boards (where provided) will be used by to display pertinent accident information at various response personnel to display pertinent information.
(mergency response facilities.
- Status Board Caretakers will be assigned by facility coordinators to maintain the status boards with current information.
I 1998 Drill Observation - SCR-2 and TSC-4:
(The Emergency Core Cooling System / Primary Containment isolation System / Power Supply status boards in the TSC i Communications Area were not effectively maintained or kept up-to-date with current information throughout the drill. This l caused TSC staff to request needed information from the Simulator Control Room on the general plant status conditions l instead of using the information that should be mainta 'x! and updated on these status boards. In addition, the PCIS status board was not initially used or updated. Use of this status board earlier may have identified the loss of indication cf PCIS ,
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,1f7 NRC Exercise Observation - refer to NRC Inspection Repo t 97-01, Section b.2, TSC, page 3 l (Maintaining the status of ECCS and important electrical distribution components was not fully effective.)
- 5. Demonstrate that adequate emergency B.E Ccinmunications will be demonstrated between the p communication systems are in place to facilitate various Emergency Response Facilities using V transmittal of data between emergency response established communications systems as described facilities and federal and state authorities. in Procedure OP 3504, " Emergency Communications."
- 6. Demonstrate that off-site monitoring teams B.6 Off-site Monitoring Teams will be dispatched to the (if necessary) can appropriately identify their location field and directed to specific sample locations for when reporting sample results to the EOF. monitoring activities (if necessary).
- 7. Demonstrate the ability to provide adequate briefings B.7 During the period that the Off Site Monitoring Teams (if necessary) to off-site monitoring teams as will be in the field, . scenario events may require that conditions and information change. periodic updates be transtnitted to the teams in the field (if necessary).
! 8. Demonstrate the ability to adequately communicate B.8 Scenario events will allow the TSC to update plant plant updates to plant personnel as plant conditions personnel on changing plant conditions and plant cnd status information change.
- status information. Periodic plant announcements should be made to brief plant personnel on plant conditions and emergency status information.
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- Indicates an identified observation from the 1998 Drill and/or 1997 Exercise. The description of the itern is provided following each asterisk objective.
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RIv. O P2g3 2.1 4 1998 Drill Observation - TSC-2:
Although plant status changes were periodically announced over the plant intercom system, the frequency of status reports er the plant intercom system needs to be increased to mairitain staff E.wareness of plant status changes and conditions.
1998 Drill Observation - TSC-3; Although the TSC staff did arnounce the protective actions taken by the States over the plant intercom system as specified by procedures. They also announced the Protective Action Recommendations (PARS) made by the Site Recovery Manager (SRM) at the General Emergency, which may not be taken by State officiais.
C. Direction and Control Extent of Play
- 1. Demonstrate the proper transfer ct responsibilities C.1 Scenario events require the activation of the from Shift Supervisor / Plant Emergency Director Emergency Response Organization. As each (SS/ PED) to the Duty & Call Officer (DCO), and position of authority is activated, responsibilities subsequently to the TSC Coordinator and Site associated with that position would be assumed Recovery Manager (SRM) as appropriate. from the SS/ PED up to the SRM.
- 2. Demonstrate the capability of key emergency C.2 All emergency response facilities have designated F a facility management personnel to direct and coordinators who will direct and coordinate coordinate their respective emergency response emergency response activities in their particular cctivities in an efficient and timely manner, area of responsibility.
. Demonstrate appropriate coordination of activities C.3 The SCR will initially contact the federal and state with federal and state govemment agencies. agencies, providing them with appropriate information on plant conditions and emergency status. This function will pass to the TSC and EOF /RC after the facilities are activated and staffed.
D. Emeroency Resoonse Facilities Extent of Play
- 1. Demonstrate the ability of station personnel to D.1 Scenario events will require activation and cctivate and staff the emergency response facilities D.2 operation of Vermont Yankee emergency response in a timely manner.
- 2. Demonstrate and test the adequacy and Center and Engineering Support Center will be cffectiveness of emergency response facilities, activated in accordance with established operations, and equipment.
- procedures. Designated plant and corporate emergency response personnel will participate in the exercise.
' Indicates an identified obsesation from the 1998 Drill and/or 1997 Exercise. The description of the item is provided following each asterisk objective.
RIv. O P ge 2.1 -5
'll i - lthough the EOF and TSC were activated and staffed within one hour after the Alert classification, there appears to be some confusion as to the minimum criteria to declare the EOF and TSC activated.)
1998 Drill Observation - TSC-4:
(Difficulty was encountered with the establishment of the primary and attemate auto ring down communication circuit.)
1998 Drill Observation - OSC-4:
(Communication between the OSC Coordinator Office and Radiation Protection (RP) Checkpoint was hard to maintain on a continuous basis to allow for updates and changes to job tasks and dose commitments.)
E. Plant Auamentation and Staffina Extent of Plav
- 1. Demonstrate the adequacy of plant emergency E.1 Shift personnel will demonstrate the use of the notification methods and procedures to augment emergency call-in system to augment plant staff as plant staff and resources. may be required by scenario events.
- 2. Demonstrate the ability to use outside resources to E.2 The Duke Engineering & Services' Engineering provide technical assistance and logistical support. Support Center (ESC) will be contacted and activated for this exercise. The ESC will provide technical and logistical support as requested by O Vermont Yankee.
- 3. Demonstrate the ability to maintain shift staffing and E.3 Available resources will be evaluated and assigned manpower to provide for future manpower and to support extended operations.
logistics needs.
F. Radioloalcal Exposure Control Extentof Play
- 1. Demonstrate the ability to provide adequate radiation F.1 Scenario events will allow OSC On-Site Assistance protection controls for on-site emergency response F.2 Teams to be dispatched to investigate problems with personnel including dosimetry, equipment, and associated plant equipment. Investigation and protective c!othing. repair activities in the plant will require implementation of radiation controls which include
- 2. Demonstrate the ability to monitor and track radiation morltoring and tracking of radiation exposure of cxposure of on-site emergency response personnel. OSC On-site Assistance Teams. (Refer to i
Procedure OP 3507, " Emergency Radiation Exposure Control.") In addition, the exposure of the Off-Site Monitoring Teams wi!! be monitored and
) tracked in the EOF.
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' Indicates an identified obsersation from the 1998 Drill and/or 1997 Exercise. The description of the item is provided following each asterisk objective.
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R2v. 0 PIge 2.1 -6
. In-Plant Corrective and Repair Actions Extent of Play
- 1. Demonstrate the ability to dispatch and deploy on-site G.1 OSC On-site Assistance Teams should be assistance teams in a timely fashion, consistent with G.2 dispatched to investigate problems associated with plant conditions and assigned function.
- plant equipment. Briefings should be conducted with emergency teams to ensure that job
- 2. Demonstrate the ability to provide adequate briefings requirements are clear and understood. OSC to on-site assistanco teams on job assignments and Team Work Status Forms (VYOPF 3501.06) should tasks.
- be used to keep track of team assignments and work tasks.
1998 Drill Observation - OSC-1:
(Although WOPF 3501.06, OSC Team Work Status Forms were used to maintain a continuous accountability of OSC on-site assistance team assignments and tasks, the status forms were not posted in the OSC as required by the EPIP.)
1998 Drill Observation - OSC-2:
(Although on-site assistance teams were ready to proceed with their job assignments, delays were encountered with verifying respir tor protection qualifications and receiving dose commitments.)
x i rv i n - refer to NRC inspection Report 97-01, Section b.3, OSC, page 3 and page 4 Some delays in dispatching on-site assistance teams caused by issues dealing with respiratory protection qualifications and usage.)
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- 3. Demonstrate the ability of on-site assistance teams G.3 OSC On-site Assistance Teams will be given the to perform corrective actions on plant equipment G.4 opportunity to perform corrective actions associated during emergency conditions, with plant equipment. Demonstrations of in-plant corrective actions are controlled in accordance with '
- 4. D?monstrate the ability to provide adequate defined mini-scenarios. Simulation of repair cdministrative controls and documentation for activities will be controlled in accordance with the necessary repairs of plant equipment and systems defined mini-scenarios and as specified in the during an emergency, ground rules. The mini-scenarios will allow players to implement the appropriate emergency work controls in accordance with established procedures.
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' Indicates an identified obsebation from the 1998 Drill and/or 1997 Exercise. The description of the item is provided following each asterisk objective, t
r-R;v. O PIge 2.1 -7
, . Radiolooical Assessment Extent of Plav l
- 1. Demonstrate that adequate dose assessment H.1 The scenario will provide information on plant activities can be performed to determine off-site H.2 conditions and in-plant radiological conditions to radiological consequences.
- H.3 players that will allow them to evaluate off-site H.4 potential radiological consequences. The scenario
- 2. Demonstrate that radiological assessment personnel H.5 will provide off-site radiological data that will allow ct the EOF can obtain radiologicht and players to evaluate off-site radiological conditions (if meteorological data in a timely manner. necessary). Players will implement appropriate sections of Procedures OP 3513, " Evaluation of
- 3. Demonstrate the ability to perform timely assessment Off-Site Radiological Conditions" and OP 3511, "
cf off-site radiological conditions to support the Off-Site Protective Action Recommendations," as formulation of protective action recommendations for may be required by scenario events.
the plume exposure pathway.
- 4. D2monstrate the ability to assess potential off-site radiological consequences based on plant conditions.
- 5. Demonstrate the ability to project plume trajectory cnd potentially affected downwind sectors (if necessary) using computer dose assessment
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model (METPAC).
- l 1997 NRC Exercise Observation - refer to NRC Inspection Report 97 01, Section b.5, Dose Assessment, page 5 l (METPAC "what if* calculations were made without increasing the source term to get an upper limit.)
- 6. Demonstrate adequate staffing, equipment readiness H.6 Off-site monitoring teams will be assigned at the ,
check, and deployment (if necessary) of off-site H.7 OSC. Players will implement appropriate sections j monitoring teams. of Procedure OP 3510,"Off-Site and Site Boundary Monitoring," as may be required by scenario events.
- 7. Demonstrate the use of appropriate equipment and procedures to perform off-site radiological monitoring (if necessary).
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' Indicates an identified obseEation from the 1998 Drill and/or 1997 Exercise. The description of the item is provided following each asterisk objective.
R:v. O Pzge 2.1 -8
_l. Protective Action Decision Makina Extent of Plgy (d1. Demonstrate the ability to implement appropriate on- 1.1 On-site protective action measures will include
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site protective measures for emergency response radiation exposure control, site accountability and personnel. use of protective equipment and supplies.
Appropriate on-site protective measures will be implemented as required by scenario events.
- 2. Demonstrate the adequacy of the protective action 1.2 Protective action decision making will be decision making process to make appropriate demonstrated in accordance with Procedure OP recommendations conceming off-site radiological 3511, "Off Site Protective Actions consequences. Recommendations."
J. P,yblic Information Extent of Plav
- 1. Demonstrate the ability to develop and periodically J.1 The flews MerJia Center (NMC) will be activated and disseminate timely and accurate press releases to J.2 staffed. Inicanation on the simulated scenario the public and the news media. J.3 events occurring at the plant will be gathered, verified, and incorporated into news releases. After
- p. Demondrate the ability to provide briefings and to approval, Information will be disseminated and C interface with the public and news media. briefings on the information will be conducted at the NMC.
- 4. Demonstrate the ability to provide rumor control. J.4 A communication line will be established to provida for rumor control concerning the simulated accident. j
- 5. Demonstrate the ability to coordinate news release J.5 State public information representatives should be I with the state's public irtrmation representatives. present at the NMC. Information conceming news releases will be coordinated with the states' public information representatives.
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j ' Indicates an identified observation from the 1998 Drill and/or 1997 Exercise. The description of the item is provided following each l asterisk objective.
R,v.O PIge 2.1 -9
. Parallel and Other Actions Extent of Piav
- 1. Demonstrate the adequacy of methods to establish K.1 Security activities will be implemented in accordance cnd maintain access control and personnel with established procedures to control access to the i cccountability within the protected area.
- protected area. Assembly of emergency response personnel and evacuation of contractors / visitors will be implemented to test personnel accountability process within the protected area (Refer to Procedure OP 3524, "Ernergency Actions to Ensure initial Accountability and Security Response").
However, after the plant evacuation and initial accountability checks have been completed, contractors / visitors may be allowed to retum to work and they will be exempted from additional personnel accountability checks or exercise related announcements.
4 1998 Drill Observation - SEC-1:
(Tha following observations were noted regarding initial accountability within the protected area of the plant:
Some accountability sheets were not provided at the OSC and the RP checkpoint e Some individuals failed to sign the accountability sheets upon ERF activation at the Alert classification.
e Two individuals took approximately 18 minutes to go through Gatehouse 2 on the initial Alert PA announcement to the leave the site and report to the EOF. This could affect Security's ability to complete on-site accountability in a timely manner.
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- 2. Demonstrate the licensee's capability for self-critique K.2 Exercise critique will be conducted with controllers cnd ability to identify areas needing improvement. and players. Critique items will be compiled and ,
documented in accordance with Procedure OP !
3505, " Emergency Preparedness Exercises and l Drills."
Notr The annual Radiological monitoring drill and semi-annual Health Physics drill will be included as part of this exercise. A separate Health Physics drill will be held to demonstrate the actual sample collection and analysis of in-plant chemistry samples, which includes the use of the Post Accident Sampling System.
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- lrdcates an identified observation from the 1998 Drill and/or 1997 Exercise. The description of the item is provided following each asterisk objective.
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SPECIAL POPULATIONS FACILmES SCHEDULE ORGANIZATIONS / FACILITIES 1995 1997 1999 Brattleboro Campgrounds (Summer 97) !
Fort Dummer Camp Waubanoug (Summer 97) l Dummerston Campgrounds (Summer 97)
Hidden Acres KOA (Summer 97)
Public Schools Superintendent of WSWSU X Superintendent of WSESU X -
Brattleboro Middle School X Brattleboro Union H.S. X Canal Street School (Brattleboro) X Green Street School (Brattleboro) X Dummerston Elementary Schoo! X Guilford Central School X I I Halifax West School X Vemon Elementary X Private Schools & Day Care Centers X The Austine School Three licensed Day Cares X Two Registered Day Cares X -
The Neighborhood School X X l World Learning and School for Intemational Nursing Homes Eden Park X Linden Lodge X Thompson House X -
C:\ WINDOWS \ TEMP \VYEXOP2.99.WEge 24 of 25 April 15,1999 0
ORGANIZATIONS / FACILITIES 1995 1997 1999 VT Bapust Home & Gathermg Place Vernon Green X Congregate Care Facilities (ARC) X Survey Local Alternate Warning Point (RocWgham VSP) X SpecialFacilities:
Brattleboro Retreat X M Fr 1
Brattleboro Memorial Hospital '
(Excluding the MS-1 plan already demonstrated.)
Large Employers:
- 1. This type of sample may nat be season or may be difficult to arrange in an exercise format.
Teams will be papered to explain acd demonstrate how they would sample any products not readily available orin season.
- 2. Local participation will be limited to a .; mall group of state and local officials.
c C:\ WINDOWS \ TEMP \VYEXOP2.99 WHBge 25 of 25 April 15,1999
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 2.3 STATE OF NEW HAMPSHIRE- EXERCISE OBJECTIVES AND EXTENT OF PLAY O
O .
- i. .
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l STATE OF NEW HAMPSHIRE
' -O >*' rou== xxrosu== ^so isonsrios RAT =wiv =x==ciss VERMONT YANKEE 3/19/99 l OBJECITVES AND EXTENT OF PLAY OBJECTIVE #1 :
MOBILIZATION OF EMERGENCY PERSONNEL ;
Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and Seld operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
l EXTENT OF PLAY PLUME EXPOSURE PATHWAY PHASE :
Emergency facilities will be alerted in accordance with the NHRERP.
l Those facilities which are to participate in the exercise will mobilize accordingly.
l Rosters for relief shiAs will be available in each participating facility. 'Ihose
- facilities that are not participating will acknowledge receipt of notification, but will l take no further action. Controllers will simulate facilities not participating.
1l .
FACHRIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE -
STATE EOC, EOF, IFO, MEDIA CENTER, JOINT INFORMATION CENTER, IDCAL EOCs IN HINSDALE, RICHMOND, WINCHESTER, O_ SWANzEv. CHESTEaristo. ^No resNE < Host Comm nitv). ST^rs WARNING POINT, SOUTHWESTERN NEW HAMPSHIRE DISTRICT FIRE l
I MUTUAL AID.
EXTENT OF PLAY INGESTION PATHWAY PHASE :
l Facilities will be staged independently at predetermined times. Controllers at each facility will suppon participating facilities by managing the flow of communications and data to support exercise play and objective demonstration.
FACHRIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY i PHASE:
- NEW HAMPSHIRE STATE EOC.
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
l O 3"*"
OBJECTIVE #2 -
FACILrrIES-EOUIPMENT. DISPLAYS AND WORK ENVIRONMENT -
Demonstrate the adequacy of facilities and equipment, displays, and other materials to support emergency operations.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY PHASE :
Each participating facility will demonstrate its capabilities in accordance with this objective.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUNE EXPOSURE PATHWAY PHASE :
STATE EOC, EOF, IFO, MEDIA CENTER, JOINT INFORMATION CENTER, LOCAL EOCs IN HINSDALE, RICHMOND, WINCHESTER, SWANZEY, CHESTERFIELD, AND KEENE (Host Community), STATE WARNING POINT, SOUTHWESTERN NEW HAMPSHIRE DISTRICT FIRE MUTUAL AtD.
EXTENT OF PLAY INGESTION PATHWAY PHASE :
Each participating facility will demonstrate its capabilities in accordance with this objective.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE:
NEW HAMPSHIRE STATE EOC.
g i
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
l I
2 3/19/99 O
OBJECTIVE #3 :
DIRECTION AND CONTROL:
Demonstrate the capability to direct and control emergency operations.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY PR~ 1 Participating state and local facilities will den. strate their ability to direct and control emergency operations in acewdance with the. . OfRERP.
FAN 1TER DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
STATE EOC, EOF, IFO, MEDIA CENTER, JOINT INFORMATION CENTER, LOCAL EOCs IN HINSDALE, RICHMOND, WINCHESTER, SWANZEY, CHESTERFIELD, AND KEENE (Host Conunnnity), STATE WARNING POINT, SOUTHWESTERN NEW HAMPSHIRE DISTRICT FIRE MUTUAL AID.
EXTENT OF PLAY INGESTION PATHWAY PHASE :
Participating state and local facilities will demonstrate their ability to direct and control emergency operations in accordance with the NHRERP.
FAN TIWR DEMONSTRATING THIS OBJECTIVE DURING THE INGC3 TION PATHWAY PHASE:
? NEW HAMPSHIRE STATE EOC.
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
OBJECTIVE #4 :
COMMUNICATIONS :
Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY PHASE :
Facilities participating in the exercise will demonstrate the primary and a back up communications resource per facility.
l O 3/19/99 >
l FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
STATE EOC, EOF, IFO, MEDIA CENTER, JOINT g
INFORMATION CENTER, LOCAL EOCs IN HINSDALE, RICHMOND, l WINCHESTER, SWANZEY, CHESTERFIELD, AND KEENE (Host Community), STATE WARNING POINT, SOUTHWESTERN NEW HAMPSHIRE DISTRICT FIRE MUTUAL AID, MONITORING TEAMS.
EXTENT OF PLAY INGESTION PATHWAY PHASE :
N/A.
FACIIJTIES DEMONSTRATING THIS OBECTIVE DURING THE INGESTION PATHWAY PHASE:
STATE EOC.
AREAS REOUIRING COMECITVE ACTION :
None Cited.
OBECITVE#5 :
EMERGENCY WORKER EXPOSURE CONTROL:
Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers. g EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
This objective will be demonstrated in accordance with the NHRERP by facilities that participate in the exercise.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
EOCs IN HINSDALE, RICHMOND, WINCHESTER, SWANZEY, CHESTERFIELD, MONITORING TEAMS.
EXTENT OF PLAY INGESTION PATHWAY :
This objective will be demonstrated in conjuaction with the plume exposure pathway portion of the exercise.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE:
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
4 3/19/99 0
F~
O " " " " "
FrpT n RADIOLOGICAL MONTTORING-AMBIEffr RADIATION MONITORING :
Demonstrate the appropriate use of equipment and procedures for
@=nining Seld radiation measurements.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
l Two NHOHM radiological monitoring teams will be ag :wi Each team will monitor six points. The time at which any point is monitored is not expected to coincide with the request of accident n=== ment personnel for monitoring support.
FACILITIES DEMONSTRATING THIS OBECrlVE DURING THE PLUME EXPOSURE PATHWAY PHASE -
FIELD MONITORINGTEAMS
! EXTENT OF PLAYINGESTION PATHWAY :
This objective will be demonstrated during the plume phase.
FACILrrIES DEMONSTRATING THIS OBECrlVE DURING THE INGESTION PATHWAY PHASE:
"'^
O AREAS REOUIRINO CORRECTIVE ACTION:
l None Cited.
l OBECTIVE#7 :
PLUME DOSE PROECTION:
Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering.
I
- EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
This objective will be demonstrated in accordance with the NHRERP in the context of the exercise scenario. PHAAP, METPAC and other accident assessment programs may be used.
FACILrrIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
STATE EOC.
EXTENT OF PLAY INGESTION PATHWAY :
O 3,19,99 s h
N/A O
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE:
N/A AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
OBJECTTVE #8 :
FIFTn RADIOLOGICAL MONITORING-AIRBORNE RADIOIODINE AND PARTICULATE ACTIVITY MONTIORING :
Demonstrate the appropriate use of equipment and procedures for the measurement of airbome radio iodine concentrations as low as 10^-7 (0.0000001)
Micro curie per cubic centimeter in the presence of noble gasses and obtain samples of particulate activity in the airbome plume.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
This objective will be demonstrated in accordance with the NHRERP. Use of Silver Zeolite filter media will be simulated. Charcoal filter cartridges will be used. Cartridges will be prepared for transportation to the State Lab for analysis. g FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : .
FIELD MONITORING TEAMS. !
EXTENT OF PLAY INGESTION PATHWAY :
This objective will be demonstrated as part of the plume exposure phase of the exercise.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE:
N/A AREAS RECWlNG CORRECTIVE ACTION :
j None Cited.
)
1 6
3/19/99 w
i
O .
PLUME PROTECTIVE AC%N DECISION MAKING :
Demonstrate toe capability to make timely and appropriate pantactive action dar ininne (PAD).
EXTENT OF PLAY PLUME EXPOSURE PATHWAY t This objective win be damaneated by the state decision making team in accordance with the NHRERP. I.ocal organizations will be notified and respond in accordance with their plans and procedures w4 to the recammandad protective action.
The New Hampshire decision making team will discuss its decisions with the Vermont and Massachusetts decision making teams and coordinate public notification activity. -
FArtr rrtM DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
STATE EOC.
EXTENT OF PLAYINGESTION PATHWAY:
N/A O
, PHASE:
FACILITIFW5 DEMONSTRA'IING THIS OBECTIVC DURING THE INGESTION PATH STATE EOC.
AREAS REOUIRING CORRECTIVE ACTION:
None cited.
OBECTIVE #10 -
AI.ERT AND NOTIFICATION: .
Demonstrate the capability to promptly alert and notify the public within the 10-mile Plume Pathway Emergency Planning Zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate state or local of5cials.
EXTENT OF PLAY PLUME EXPOSURE :
Sounding of sirens and broadcast of EAS/ EPI messages will be simulated.
EAS/ EPI messages will M formulated and distributed by the New Hamachire EOC in accordance with the NHRERP. Simulation of the activation of the EAS system will be coordinated with Vermont and Massachusetts officials. WKNE will receive O 3/19,99 >
]
EASEPI messages in accordance with the NHRERP but will not broadcast any messages. Activation of NOAA weather tone alert radios will be simulated.
Requests for their activation will be made by NHOEM to the Vermont State EOC.
h{ {
i EPZ communities will demonstrate this objective through the .tceipt of activation times fmm their local liaisons and will demonstrate their capability to monitor EAS and NOAA stations. .
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
STATE EOC, WKNE, Southwestern New Hampshire District Fue Mutual Aid.
EXTENT OF PLAYINGESTION PATHWAY:
This objective will be demonstrated during the plume exposure phase of the exercise.
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE INGVSTION PATHWAY PHASE:
N/A AREAS REOUIRING CORPICTIVE ACTION :
None Cited.
O OBECTIVE#11 :
PUBLICINSTRUCTIONS ANDEMERGENCYINFORMATION -
Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instmetions to the public.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
Public information messages will be developed periodically. Messages will be developed based upon scenario information. Broadcast of these messages will be simulated. The messages will be distributed to the EOF, IFO, Media Center, JIC and WKNE by the NH EOC.
local EOCs will receive information concerning protective action recommendations from their respective local liaison. Iocal EOCs do not prepare public information messages and do not have a representative at the Media Center.
Iocal EOCs will monitor EAS and NOAA radios per their procedures. j j
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE I PATHWAY PHASE :
8 3/19/99 ;
STATE EOC, MEDIA CENTER.
O EXTENT OF PLAYINGESTION PATHWAY; Public information messages will be developed periodically. M-==p will be developed based upon scenario infe..=' a Broadcast of these messages will be simidated The message distribution will be =imat=*ad FACamES DEMONSTRATING TiflS OBJECTIVE DURING THE INGESTION PATHWAY PHASE:
STATE EOC.
AREAS REOUIRING CORREC'1IVE ACTION :
None Cited.
~
OBJECTIVE #12 -
EMERGENCYINFORMATION-MEDIA Demonstrate the capability to coordinate the development and dissemination of clear, accurate, and timely information to the news media.
EXTENTOF PLAY PLUME EXPOSURE :
'Ibe demonstration of this objective occurs at the state EOC , the Media Center and JIC. Controllers will simulate media response.
O The gri ibiiity f- bri<m
- mea wa -- <
- activities in New Fnmachire lies with the State. New Hampshire will coordinate its' media information with Vermont, Massachusetts and the Utility in accordance with the NHRERP.
EPZ community officials may respond to questions about local emergency response but 'are encouraged to refer press inquires to the Media Center. A controller message will be generated for each community to initiate a response and referral to media inquiries made to local officials.
FANTrIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : -
STATE EOC, MEDIA CENTER, LOCAL EOC"S.
EXTENT OF PLAY INGESTION PATHWAY:
The demonstration of this objective will occur at the state EOC. Emergency Public Information Messages will be developed at the EOC. Their distribution will bein accordance with the NHRERP.
FAN TIM DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE:
STATE EOC.
O 3'i9
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
g OBJECTIVE #13 -
EMERGENCY INFORMATION-RUMOR CONTROL :
Demonstrate the capability to establish and operate rumor contml in a coordmated and timely manner.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
In accordance with the NHRERP, demonstration of this objective will occur at the Joint Information center. Incoming calls will be provided by controllers. At least one false or misleading rumor relating to PARS will be provided by the controllers. Calls to the rumor control center will occur at a rate of at least six per hour per operator during the Site Area Emergency and General Emergency levels.
Rumor control personnel will screen messages for trends.
Communities will refer calls which address issues beyond local jurisdiction to the rumor control number. A controller message will be generated for exh community to initiate a response and referral of information.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASEt g JOINT INFORMATION CENTER. W EXTENT OF PLAY INGESTION PATHWAY :
This objective will be demonstrated during the plume exposure phase of the exercise.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWA_Y PHASE:
N/A AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
10 3/19/99 0
4
OBJECTIVE #14 :
IMPIF4ENTATION OF PRCfrECTIVE ACTION-USE - OF KI FOR EMERGENCY WORKERS. INSTmmONAIJZED INDIVIDUAI.S.AND THE GENERAL PUBLIC :
Demonstrate the capability and resources to i=ala=aat Potassium Iodide (KI) protective actions for emergency workers, institutianalived individuals, and if the state plan specifies, the general public.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
The decision to use or not use KI for emergency workers and institutinaali=4 individuals will be demonstrated at the State EOC.
The capability to distribute and admini< tar KI will be demonstrated at appropriate state and local facilities. Actual distribution of KI to emergency workers and institutionalired individuals will occur in accordance with procedures -
the ingestion of KI will be simulated No KI will be ingested by emergency workers dunng this exercise.
Quantities of KI are stored at local EOCs, EPZ Nursing Homes and Hospitals and the IFO.
The NHRERP does not provide for the issuance of KI to the general public.
Calls to institutions will be simniad I 1
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE -
O STATE EOC, LOCAL EOCs in Ensdale Richmond Winchester Swanzey and Chesterfield, MONfrORING TEAMS, ACCESS AND TRAFFIC CONTROL Personnel.
EXTENT OF PLAYINGESTION PATHWAY :
This objective will be demonstrated durirg the plume exposure pathway phase of the exercise.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY ,
PHASE: l N/A .
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
1 O 3'29'99 '1 4
I l I
l l OBECTIVE #15 : !
IMPIFMENTATION OF PROTECTIVE ACTIONS-SPECIAL POPULATIONS :
Demonstrate the capability and resources mswy to implement appropriate protective actions for special populations.
1 l
EXTENT OF PLAY PLUME EXPOSLPE PATHWAY -
The ability and resources to implement protective actions for special populations !
will be demonstrated in accordance with the NHRERP.
Each local EOC will simulate calls to special needs populadons per their special needs call lists and arrange for appropriate resources to meet the special needs. Controller messages will simulate requests for assistance. Dispatch of resources and response to requests for assistance will be simulated.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSUtG PATHWAY PHASE :
STATE EOC, IFO, STSA, LOCAL EOCs in Hmsdale Winchester Richmond Swanzey and Chesterfield.
EXTENT OF Pl.AY INGESTION PATHWAY :
This objective will be demonstrated during the plume phase of the exercise.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE :
N/A g
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
OBJECTIVE #16 -
IMPLEMENTATION OF PROTECTIVE ACTION-SCHOOLS :
Demonstrate the capability and resourtes necessary to implement protective actions for school children within the Plume Pathway Emergency Planmng Zone :
(EPZ).
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
Calls will be made to each school to verify transportation resource requirements. Calls will be made to transportation providers to verifj resource capabilities.
In an out of sequence demonstration One bus will be dispatched to the schools in Hinsdale, Winchester and Chesterfield (Three Busses Total). School Admmistrative i personnel will be interviewed regarding their procedures 12 3/19/99 O
i L
f.
j()
i FACg1TES DEMONSTRATING THIS OBECrlVE DURING THE PLUME EXPOSURE PATHWAY PHASE:
STATE EOC, LOCAL EOCs, EPZ SCHOOLS out of sequence.
EXTENT OF PLAYINGESTION PATHWAY:
l This objective will be demonstrated during the plume exposure phase of the exercise.
FACILrrIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE:
N/A l AREAS REOUIRINO CORRECTIVE ACTION:
None Cited. .
. OBJECTIVE #17 :
TRAFFIC AND ACCESS CONTROL-Demonstrate the organi'adonal capability and resources to control evacuation traffic flow and to control access to evacuated and sheltered areas.
O EXTENT QF PLAY PLUME EXPOSURE PATHWAY :
Local police will be asked to talk through procedures for the staffing of traffic control points l in theirjurisdiction. Traffic control Equipment to implement the traffic control plan will be iaprd One access control point and the ability to handle a traffic impedunent will be demonstrated by Troop C New Hmm,'= hire State Police.
Demonstrations will occur durmg plume exposure pathway phase of the exercise at times to be coordinated between facility controllers and FEMA l
evaluators. The demonstrations will consist of a talk through of actions needed to implement the Access control plan. -
FACILrrIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
EXTENT OF PLAYINGESTION PATHWAY :
State EOC personnel will conduct a talk through of the issues involved in implementing Phase H of Access Control at the end of the Plume phase exercise.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY 13 Q '3/19/99 d.
PHASE:
STATE EOC g AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
OBJECTIVE #18 -
RECEPTIONCENTER-MONITORINGDECONTAMINATION. ANDREGISTRATION:
Demonstrate the adequacy of pmcedures facilities, equipment, and personnel for the radiological monitoring, decontamination, and registration of evacuees.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
Keene State College will demonstrate the ability to operate the reception /
monitoring / decon and Emergency Worker Decon facilities there. This demonstration will take place independently and out of sequence. Seven Vehicles and Seven simulated evacuees (One female and one male " Contaminated") will be processed during the demonstration in accordance with FEMA rep 14 guidance.
FACILITIES DEMONSTRATING THIS OBJECITVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
KEENE STATE COLLEGE, RECEPTION /DECON CENTER.
EXTENT OF PLAY INGESTION PATHWAY :
N/A g
FACILITIES DEMONSTRATING THIS OBJECIWE DURING THE INGESTION PATHWAY PHASE:
N/A AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
14 3/19/99 O
7.
OBJECTIVE #19 :
[O p l Demonstrate the adequacy of facilities, equipment, supplies, 5+=-: ='. and l p&s forcongregate care ofevacuees.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY ;
The Congregate care centers will not be activated. A tour of new congregate care facilities that support the Keene State CaIV Waa center will be enaarted with a controller and an ARC repr=nentive ir '=g= '--My and out of sequence.
FAMUIM DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSJ35 PATHWAY PHASE :
CONGREGATE CARE FACILrrIES SUPPORTING KEENE STATE COLLEGE.
FACILrrIES DEMONSTRATING THIS OBECTIVE DURING THE INGESTION PATHWAY l PHASE:
N/A I i
! AREAS REOUIRING CORI'ECTIVE ACTION :
None cited.
,O OBECTIVE #20 -
MEDICAL SERVICES-TRANSPORTATION:
Demonstrate the %'g of vehicles, equipment, procedures, and personnel for transporting contaminated, injured or exposed individuals.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY ;
This objective has been demonstrated during the Noverber 10,1998 MS-1 drill at the Cheshire Medical Center.
- )
EALM3S DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE I E% AY PHASE :
WINCHESTER FIRE DEPARTMENT AMBULANCE.
EXTENT OF PLAYINGESTION PATHWAY :
This objective is demonstated in conjunction with the plume exposure phase of the exercise.
FACILrrIES DEMONSTRATING THIS OBECTTVE DURING THE INGESTION PATHWAY t 3/19/99 is
l PHASE:
N/A g AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
OBECTIVE #21 -
MFnICAL SERVICES-FACILITIES :
Demonstrate the adequacy of the equipment procedures, supplies, and I
personnel of medical facilities responsible for treatment of contaminated, injured, or exposed individuals.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
This objective has been be demonstrated dc'ag the November 10,1998 MS-1 drill at the Chesliire Medical Center.
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
CHESHIRE MEDICAL CENTER.
EXTENT OF PLAY INGESTION PATHWAY:
This objective is be demonstrated in conjunction with the plume exposure exercise phase.
g FACILITIES DEMONSTRATING THIS OBECTIVE DUkhNG TH(T.s ESTION PATHWAY PHASE:
N/A AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
OBECTIVE #22 : .
EMERGENCY WORKERS. EOUTPMENT AND VEHICOS- MONITORING AND DECONTAMINATION :
Demonstrate the adequacy of procedures for the monitoring and decontamination of emergency workers, equipment and vehicles.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
This Objective will be demonstrated out of Sequence at Keene State College See Objective #19.
16 3/19/99 1
L FAr'frrTIFR DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE
,Q l
PATliWAY PHASE :
EMERGENCY WORKER MONITORING /DECON FACHlTY.
EXIENT OFPLAYINGESTION PATHWAY:
'Ihis objective will be demonstrated in conjunction with the plume exposure phase of the exercise.
FACHJrIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE:
N/A AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
OBJECTIVE #23 -
SUPPLEMENTARY ASSISTANCE TEDERAI/OTHER):
Demonstrate the capability to identify the need for external assistance and to request such assistance from Federal or other support organizations.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
American Red Cross and Civil Air Patrol will send representatives to l facilities in accordance with the NHRERP. New Famphire will coorrlinare its requests for supplementary assistance with Vermont and Massachusetts pursuant to the NHRERP. The Compact Administrator of the New England Radiological Health Compact is respcasible for coordmation of technical assistance for Vermont, New Hampshire and Massachusetts. The Administrators activity will be simulated.
FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE t STATE EOC. l 1
EXTENT OF PLAY INGESTION PATHWAY : ,
This objective will be demonstrated in conjunction with the plume exposure phase of the exercise.
FACILITTFR DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE:
N/A l t
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
3/19/99 17 l
QDECTIVE #24 :
EQSIEMERGENCY SAMPLING :
l Demonstrate the use of equipment and procedures for the collection and l transportation of samples from areas that received deposition from the airborne plume. ,
l EXTENT OF PLAY PLUME EXPOSURE : )
This objective will be demonstrated in conjunction with the ingestion phase of the exercise i i
l FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE
! PATHWAY PHASE :
l N/A 1
EXTENT OF PLAY INGESTION PATHWAY:
l This objective will be demonstrated at the State EOC by a discussion of l
sampling strategy and by the simulated deployment of sampling teams.
l FACILITIES QEMONSTRATING THIS OBECTIVE DURING THE INGESTION PATHWAY PHASE:
N/A AREAS REOUIRING CORRECTIVE ACTION: g None Cited. W v8ECTIVE #25 :
LABORATORY OPERATIONS:
Demonstrate laboratory operations and procedures for measuring and analyzing samples.
I EXTENT OF PLAY PLUME EXPOSURE PATHWAY : :
The State Laboratory in Concord will demonstrate this cbjective in conjunction with the ingestion pathway phase of the 2000 Seabrook Station Exercice.
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
N/A.
3/19/99 18 O
l
_ - _ --_- - --_- _ -_----- _ - _ - _ __ A
~
EXTENT OF PLAYINGESTION PATHWAY:
The State Laboratory in Concord will demonstrate this objective 2000 Seabrook Sution Exercise. j FACILTTIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE: I NHOHMSLAB. j AREAS DEOUIRING CORRECTIVE ACTIOII:
None Cited.
OBJECTIVE #26 :
INGESTION EXPOSURE PATHWAY-DOSE PROJECTION AND PROTECTIVE ACTION DECISION MAKING :
Demonstrate the capability to project dose to the public for the Ingestion l Pathway and to recommend protective measures.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
The activity required to demonstrate this objective will occur during the Ingestion Pathway phase of the exercise.
Q FAnf RIM DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : i N/A f
EXTENT OF PLAYINGESTION PATHWAY The activity required to demonstrate this objective will occur dunng three l separate phases of the exercise. The State EOC Accident Assessment Team will i develop a post accident monitoring plan to identify the plume foot print. This will ;
occur at the end of the plume exposure pathway phase of the exercise on Day One of )
the exercise.
On the Moming of day Two of the exercise the OHM Accident Assessment j Team will convene at the State EOC. DOE fly over results, one meter dose rates, ,
monitoring team data and some preliminary laboratory results (soil samples) will be l available for them to determine projected milk concentration / response levels and 1, ;
2,' and 50 year dose projections. Summary tables will then be provided for i remaining samples. The table will compare the samples against the PAR limits ;
aheady determined. With the aid of this data the accident assessment staff will develop Milk Pathway Protective Action Recommendations and Relocation / Retum protective action recommendations.
3/19/99 19
Play will continue at the state EOC on the Aftemoon of Day Two simulating days 2, and 4. The state EOC will be staffed for an ingestion pathway scenario. Play will begin with a discussion of the implementation of previously determined milk, g
and relocation / return protective actions. A discussion will also be initiated to i identify requirements for emergency re-entry. Appropriate news advisories will be devek,;d which reflects the actions taken. Accident assessment staff will identify any additional sampling requirements they might have. This will end the activities for Day Two.
On the Morning of Day 3 summary tables will be provided the Accident assessment staff will formulate a series of recommendations based on their analysis of these results. The EOC team will convene to consider and implement the recommended agricultural PARS. Appropriate news advisories will be developed.
A long term sampling plan will be dtscussed and an appropriate news advisory will be developui. This will end exercise play.
FACILa iES DEMONSTRATING THIS OBECTIVE DURING THE INGESTION PATHWAY PHASE:
STATE EOC.
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
OBECTIVE #27 -
INGESTION EXPOSURE PATHWAY-PROTECTIVE ACTION IMPLEMENTATION :
Demonstrate the capability to implement protective actions for Ingestion l
Exposure Pathway.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY:
i This objective will be demonstrated in conjunction with the Ingestion Pathway phase of the exercise.
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
N/A.
EXTENT OF PLAY INGESTION PATHWAY :
Emergency Public Information Messages for the ingestion pathway will be developed according to scenario driven activity. The emergency distribution of the farmers brochure will be discussed. A discussion of the methods of and authorities for the implementation ofingestion pathway protective measures will be conducted.
FACILTTIES DEMONSTRATING THIS OBECTIVE DURING THE INGESTION PATHWAY PHASE:
20 3/19/99 0
l
STATE EOC.
AREAS REOUIRING CORRECTIVE ACTION:
None Cited.
OBECITVE # 28 -
RET ACATION. RE-ENTRY. AND RETURN-DENION MAKING :
Demonstrate the capability to develop decisions on relocation, and retum.
EXTENT OF PLAY-This objective will be demonstrated in conjunction with the Ingestion Pathway phase of the exercise.
FACILITTFR DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
. N/A.
EXTENT OF PLAY INGESTION PATHWAY PHASE :
See Extent of Play for Objective #26.
fat 1T rrrFR DEMONSTRATING THIS OBECTIVE DURING THE INGERTION PATHWAY PHASE-O STATE EOC.
AREAS REOUIRING CORRECTIVE ACTION -
None Cited.
OBECTIVE #29 -
RET OCATION. RE-ENTRY. AND RETURN-IMPT RMENTATION :
Demonstrate the capability to implement relocation, re-entry, and return.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
{
This objective will be demonstrated in conjunction with the Ingestion Pathway phase of the exercise.
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
N/A.
O 3'19'99 21
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i
F i
l EXTENT OF PLAY INGESTION PATHWAY :
See Extent of Play for Objective #26. g l
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE INGESTION PATHWAY PHASE:
STATE EOC.
l AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
OBECTIVE #30 :
CONTINUOUS. 24-HOUR STAFFING : !
Demonstrate tne capability to maintain staffing on a continuous 24-hour {'
basis through an actual shift change.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
Second shift staffing rosters will be provided at each facility. An actual shift tumover will not be demonstrated.
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
N/A.
EXTENT OF PLAY INGESTION PATHWAY :
This objective will be demonstrated in conjunction with the Plume Phase of the exercise.
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE INGESTION PATHWAY PHASE:
N/A AREAS REOUIRING CORRECTIVE ACTION :
None Cited. ,.
OBECTIVE #31 -
OFF SITE SUPPORT FOR THE EVACUATION OF ON SITE PERSONNEL :
Demonstrate the capability to provide off site support for the evacuation of on site personnel.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
, N/A.
1 l
3/19/99 22 O
l l
l O FANfrIFR DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
N/A.
EXTENT OFPLAYINGESTION PATHWAY:
N/A.
FAN TITFR DEMONSTRATING THIS OBECTIVE DURING THE INMRTION PATHWAY 3 PHASE: !
N/A.
AREAS REOUIRING CORRECTIVE ACTION:
None Cited.
QBECTIVE #32 - l UNANNOUNCED EXERCISE OR DRILL-l Demonstrate the capability to carry out emergency response functions in an unannounced exercise or drill.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
'Ihis exercise will be a scheduled exercise.
This Objective was Demonstrated during the Drill Can&cM Saptamhar 18,1998.
O FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
N/A EXTENT OF PLAY INGESTION PATHWAY: !
N/A !
l FACILrrIES DEMONSTRATING THIS OBECTIVE DURING THE INGESTION PATHWAY PHASE:
N/A.
AREAS REOUIRING CORRECTIVE ACTION :
None Cited.
i OBJECTIVE #33 -
i OFF-HOURS EXERCISE OR DRILL -
Demonstrate the capability to carry out emergency response functions during an off-hours exercise or drill.
O 3/19 99 22 i
l i
l EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
The exercise will be conducted during regular working hours.
g FACILTTIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
This Objective was Demonstrated during the September 18,1998 Drill.
l EXTENT OF PLAY INGESTION PATHWAY:
! Demonstration of this objective will occur in conjunction with the Plume I
Phase of the exercise.
FACILITIES DEMONSTRATING THIS CBECTIVE DURING THE INGESTION PATHWAY PHASE:
N/A.
AREAS REOUIRING CORRECTIVE ACITON :
None cited 1
OBECflVE #34 :
LICENSEE OFF STTE RESPONSE ORGANIZATIONS :
Demonstrate the capability of licensee off site response organization (licensee (ORO)) personnel to interface with non participating organizations and g
accomplish coordmation essential for emergency response.
EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
N/A.
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
N/A.
- EXTENT OF PLAYINGESTION PATHWAY :
N/A.
FACILITIES DEMONSTRATING THIS OBECTIVE DURING THE INGESTION PATHWAY l
PHASE:
i N/A.
l AREAS REOUIRING CORRECTIVE ACTION :
l None Cited.
24 3/19/99 O
l.
l
, l l )
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 l
2.4 f&MMQtoof.al.Iti.QE. MASSACHUSETTS - EXERCISE OBJECTIVES AND EXTENT OF PLAY l
l lO l
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b,^ MASSACHUSETTS OBJECTIVES AND EXTENT-OF-PLAY VERMONT YANKEE NUCLEAR POWER STATION EXERCISE APRIL 27,28,29,1999 OVERVIEW 4
The following organizations / locations will demonstrate in 1999:
Massachusetts State Emergency Operations Center Area IH Emergency Operations Center MEMA & MDPH staff at the EOF Nuclear Incident Advisory Team (field monitoring teams)
MEMA staff at the Media Center Massachusetts State Police, Troop B Headquaners in Northampton Massachusetts State Police Shelburne Barracks Dispatch Center Massachusetts Highway Department, District 2 Dept. of Environmental Management, District 9 Fire Warden Dept. of Fish, Wildlife, & Environmental Law Enforcement Bernardston EOC Colrain EOC Gill EOC O oree riciasoc Leyden EOC Northfield EOC Warwick EOC I
Schools '
The Giving Tree School, Gill Host Facilities for School Children Grange Armory l Transoortation Providers Greenfield-Montague Transportation Authority Wilson Bus Lines Liebenow, Inc.
Radiological Monitoring and Decontamination StatiqD Colrain The following locations / organizations are not participating in the 1999 Vermont Yankee Exercise:
Vermont Yankee . 1 March 8,1999 1999 Extent-of-Play
1 l
senan Bernardston Elementary FullCircle School, Bernardston h
l l Colrain CentralSchool GillElementary School Otter Pond Preschool, Gill Nonhfield Mount Hermon School, Gill and Northfield Campuses Pearl Rhodes Elementary School, Leyden Linden Hill School, Northfield l
Northfield Elementary
- Pioneer Valley Regional School, Northfield
! Warwick Elementary School Host Facilities for School & Day Care Children U-Mass Greenfield Community College l Girls' Club of Greenfield l
Mass Care Shelters Greenfield Armory Greenfield High School Federal Street School Transconation Providers Laidlaw Transit, Inc.
F. M. Kuzmeskus Bus Co.
Chapin & Sadler Radiological Monitorine and Decontamination Stations Gill Greenfield Warwick ,
.Q1htt Greenfield Community College Children's Camps Massachusetts State Laboratory O
Vermont Yankee 2 March 8,1999 1999 Extent-of-Play
O oE1ECTivs it uoErtiziTros or zusaGusCY esasossst Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and Seld operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
EXTENT OF PLAY:
State EOC - State EOC emergency staff who normally work at other locations will arrive at the EOC at the times they normally report for work unless they are paged / called and directed to report for duty at an earlier time. Operations / communications staff will show rosters and call-down or computerized lists to the FEMA evaluator.
EQE - MEMA and MDPH personnel will be in the area awaiting notification.
Media Center - MEMA personnel will be in the area awaiting notification.
NIAT Field Monitoring Team Personnel - Will be in the area awaiting notification.
Greenfield EOC - Calls to demonstrate the activation of Greenfield Community College (GCC) host school facility, receptiou center and the emergency worker radiological monitoring and decontamination station, will be made in sequence; however, no personnel will actually be J mobilized.
Communication with the mass care shelters at the Greenfield Armory, Greenfield High School, and Federal Street School will be demonstrated once; however, these facilities will not be activated. Subsequent calls to these locations will be logged at appropriate times but not made.
State Police Troco B - Will assign personnel for one state traffic and access control point, however no mobilization will occur.
Massachusetts Hiehway Decartment. District 2 - No mobilization to the field will occur, but staff .
will open the facility at the Deerfield Garage to allow a FEMA inspection of equipment for access control.
School Suoerintendents' Offices - Will make only the initial call to EPZ schools in their jurisdictions. Will contact transportation providers according to implementing procedures, will tally resources, but will not request the deployment of vehicles and drivers during the main exercise.
ARCAs:
67-97-01-A-30: The Northfield Health Officer will participate in this exercise.
Vermont Yanked 3 March 8,1999 1999 Extent-of-Play I ..
i
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OBJECTIVE 2: FACILITIES-EQUIPMENT, DISPLAYS, AND WORK I ENVIRONMENT h Demonstrate the adequacy of facilities, equipment, displays and other materials to support emergency operations.
EXTENT OF PLAY:
The only new facility (to the emergency response plan) is the Massachusetts State Police Shelburne Barracks, which now houses dosimetry supplies. In addition, FEMA will inspect the supply of access control equipment at the Massachusetts Highway Department facility at the Deerfield Garage.
ARCAs: None OBJECTIVE 3: DIRECTION AND CONTROL Demonstrate the capability to direct and control emergency operations.
EXTENT OF PLAY:
EPZ EOCs -If any towns are directed to evacuate, EOC personnel will demonstrate continuity of government through a discussion of logistics. Closing of the local EOC and relocation to a facility outside the EPZ will be simulated through discussion. All appropriate communications with MEMA Area III will be fully demonstrated.
ARCAs: ,.
67-97-03-A-24: Local EOCs will have documentation available indicating that maintenance checks and inventories have been conducted on a quarterly basis; the Radiological Instrumentation & Calibration Facility will provide documentation of annual change-out and calibration.
67-97-03-A-27: Staff at the Colrain EOC will demonstrate availability of the current version of the Colrain Emergency Response Plan.
67-97-03-A-28: In Colrain, if the CDV-700 survey meters are equipped with earphones, their use will be demorv. rated. Records will indicate that dosimetry has been calibrated according to the frequency recommended by FEMA. g Vermont Yankee 4 March 8,1999 1999 Extent-of-Play
I
' OBJECTIVE 4: COMMUNICATIONS
, i l Demonstrate the capability to communicate with all appropriate emergency personnel at facilities
! and in the field. '
i EXTENT OF PLAY:
l State EOC. Area III EOC. EOF - Contact with locations / organizations that are not demonstrating in 1999 or am demonstrating out of sequence will be simulated by logging a contact at the appropriate time (s) in the exercise unless otherwise noted in the extent of play for other objectives.
EPZ Town EOCs - Contact with locations / organizations that are not demonstrating in 1999 or are demonstrating out of sequence will be simulated by logging a contact at the appropriate time (s) in the exercise unless otherwise noted under Objectives 15 or 16.
School Suoerintendents' Offices - Please see Objective 16.
! ARCAs: None OBJECTIVE 5: EMERGENCY WORKER EXPOSURE CONTROL
-Q Demonstrate the ability to continuously monitor and contre! radiation exposure of emergency workers.
EXTENT OF PLAY i
No exceptions.
i ARCAs: .
l l
93-41: The Northfield Health Officer wi'l participate in the exercise and will demonstrate plan requirements for reading dosimeters at regular intervals and maintaining an emergency worker exposure log. ;
67-95-05-A-25: If emergency workers in Massachusetts are advised to take KI, MEMA Area III I will demonstrate advising local EOCs and state agencies with emergency workers in the field of the recommendations. In turn, those workers will simulate taking KI and note the action on their emergency worker exposure forms. If KI is not recommended for emergency workers in Massachusetts, FEMA evaluators will interview selected emergency workers in the field about
(
procedures for obtaining, using, and recording the use of KI. !
I O'
Vermont Yanked 5 March 8,1999 1999 Extent-of-Play
OBJECTIVE 6: FIELD RADIOLOGICAL MONITORING-AMBIENT RADIATION MONITORING Demonstrate the appropriate use of equipment and procedures for determuung field radiation measurements.
EXTENT OF PLAY:
NIAT Field Teams - Two field teams will each demonstrate obtaining a minimum of two complete samples. Controller messages will provide simulated radiation measurements.
ARCAs: None OBJECTIVE 7: PLUME DOSE PROJECTION Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering.
EXTENT OF PLAY:
ERE- MDPH will demonstre.te determuung if and where a plume exists in Massachusetts, as well as projected dose, if any, bsed on utility information and simulated field team data provided in a g controller message ?.om the information, the MDPH will formulate appropriate protective action W recommendations.
ARCAs: Nene OBJECTIVE 8: FIELD RADIOLOGICAL MONITORING-AIRBORNE RADIOIODLNE AND PARTICULATE ACTIVITY MONITORING Demonstrate the appropriate use of equipment and procedures for the measurement of airborne ,,
radiciodine concentrations as low as 10" (0.0000001) microcuries per cubic centimeter in the presence of noble gases and obtain samples of particulate activity in the airbome plume.
EXTENT OF PLAY:
NIAT Field Teams - Two field teams will each demonstrate measurement of airborne radiciodine concentration and particulate matter. Each monitoring team will demonstrate obtaining a muumum of two air samples. Controller messages will provide simulated monitoring data.
Teams will use charcoal cartridges to simulate silver zeolite cartridges, but the silver zeolite cartridges will be available for inspection by FEMA.
O Vermont Yankee 6 March 8,1999 1999 Extent-of-Play
.O "'^r 9 r o## i tii er e r -ai - di> r r tr== rort a tr==8 rer tr sport orthe sampie.
Actual transport to the designated laboratory for analysis will not be performed. No actual radiological material will be used.
ARCAs:
67-97-03-A-23: The NIAT field monitoring teams will demonstrate operable equipment and supplies, including batteries and hard-case instrument containers.
OBJECTIVE 9: PLUME PROTECTIVE ACTION DECISION-MAKING Demonstrate the capability to make timely protective action decisions (PAD).
EXTENT OF PLAY:
If any Massachusetts towns are directed to shelter-in-place, decision-makmg will be demonstrated for appropriate follow-up action before termination of emergency phase exercise play; e.g.,
rescinding the shelter-in-place directive, directing formerly sheltered persons to report for monitoring if the plume affected their location, issuing public information, etc.
If any Massachusetts towns are directed to evacuate, decision-makmg for appropriate post-evacuation follow-up action will be demonstrated during post-emergency phase exercise play.
(See Objectives 28 and 29).
ARCAs: None OBJECTIVE 10: ALERT AND NOTIFICATION -
Demonstrate the capability to promptly alert and notify the public within the 10-mile plume pathway emergency planning zone (EPZ) and disseminate instmetional messages to the public on the basis of decisions by appropriate State and/or local officials.
EXTENT OF PLAY:
State EOC - Actions to demonstrate performance ofinitial notification of the public will be performed up to the point of actual transmission of the Emergency Alert System (EAS) message.
The message will be prepared and the radio stations will be contacted. A standard test message will be faxed to WHYN and WHAI and broadcast once at approximately the time ofinitial notification to the public. WRSI will pick up the message from WHYN over the EAS.
Vermont Yankee 7 March 8,1999 1999 Extent-of-Play
f The Massachusetts State EOC will coordmate with the Vermont and New Hampshire State EOCs on activating the NOAA tone-alert radios throughout the EPZ. Activation of the NOAA tone-g alert radios will be demonstrated out-of-sequence using a test message.
Bernardston. Colrain. and Northfield EOCs - EOCs will demonstrate all actions necessary to perform this objective up to the point of actual sounding of the sirens. Actual sounding of the sirens will not be performed. Other EPZ towns do not have sirens, but rely on NOAA weather-alert radios.
ARCAs:
67-97-10-A-29: The Colrain EOC will demonstrate all steps up to, but not including, the activation of sirens for all siren activation sequences directed by MEMA.
OBJECTIVE 11: PUBLIC INSTRUCTIONS AND EMERGENCY INFORMATION Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instmetions to the public.
EXTENT OF PLAY:
State EOC - Following the initial alert and notification, subsequent contacts to the EAS stations will be simulated.
ARCAs: None l OBJECTIVE 12: EMERGENCY INFORMATION-MEDIA Demonstrate the capability to coordinate the development and dissemination of clear, accurate and timely information to the news media. ..
EXTENT OF PLAY:
l Media Center - Controllers will act as media representatives and real media personnel may be present and participate.
l ARCAs:
67-97-13-A-26: The PIO will provide detailed instructions, as contained in the Emergency Public Information Calendar, to support any precautionary or protective actions directed for persons in Massachusetts.
O l
Vermont Yankee 8 March 8,1999
} 1999 Extent-of-Play l
I
OBJECTIVE 13: EMERGENCY INFORMATION-RUMOR CONTROL Demonstrate the capability to establish and operate rumor control in a coordinated and timely I manner.
EXTENT OF PLAY:
l State EOC - Control cell personnel will make calls simulatirc members of the public and media personnel The rumor control personnel will demonstrate the abdity to handle calls on the mmor control line. Handling at least one rumor trend (three or more calls of the same nature) will be j demonstrated. Two rumor control operators each will respond to an average of six calls per hour once the Public Alert and Notification System has been activated at Site Area Emergency.
l
_ Media Center - Information generated as a result ofincoming calls to the EOC Rumor Control l phones will be included in news briefings. At least one rumor trend will be handled. I 1
i EPZ EOCs - Control cell personnel will make calls to each local EOC simulating members of the l public. Each EOC will demonstrate determuung which call (s) may be handled by the EOC I (queries about town response) and which call (s) must be referred to the State Runor Control /Public Information line (all other types of calls).
ARCAs:
O 67-97-13-A-25: This ARCA was resolved in the June 3,1998, Seabrook Exercise. MEMA established its own control cell for State Rumor Control and ensured that the correct number of calls was made to rumor control operators.
OBJECTIVE I4: IMPLEMENTATION OF PROTECTIVE ACTIONS-USE OF KI FOR EMERGENCY WORKERS, INSTITUTIONALIZED INDIVIDUALS, AND THE GENERAL PUBLIC Demonstrate the capability and resources to implement potassium iodide (KI) protective actions ,
for emergency workers, institutionalized individuals, and, if the State Plan specifies, the general public.
EXTENT OF PLAY:
Actual ingestion of KI will not occur. Empty KI tablet containers (small zip-lock bags) will be included in the dosimetry packets. KI inventories will be available for inspection at each distribution location.
Massachusetts does not provide KI to members of the general public.
O ARCis: Nee.
Vermont Yankee 9 March 8,1999 1999 Extent-of-Play L
OBJECTIVE 15: IMPLEMENTATION OF PROTECTIVE ACTIONS-SPECIAL POPULATIONS g
Demonstrate the capability and resources necessary to implement appropriate protective actions for special populations.
EXTENT OF PLAY:
Mmachusetts Deoartment of Environmental Management (DEM) - The District 9 Fire Warden will dispatch one alerting person / team to each of the following areas:
- North 5 eld State Forest e Warwick State Forest in Warwick
. Warwick State Forest in Northfield
. Mount Grace State Forest in Warwick e Leyden State Forest The actual alert and notification will be simulated by displaying appropriate equipment and pre-scripted messages to the evaluator. Members of the public in the vicinity will not be affected.
A FEMA evaluator will be present at District 9 Fire Warden's Office to observe communications, dosimetry distribution, equipment, maps, and prescripted messages and to interview the DEM field personnel. The FEMA evaluator will accompany one of the five field personnel / teams g dispatched.
As per procedures, only notification will be made to the Erving State Forest personnel.
Massachusetts Deoartment of Fisheries. Wildlife. and Environmental Law Enforcement. Division of Law Enforcement - Will dispatch two teams to alert, notify, and clear persons from the Connecticut River, including the areas listed below. The two teams will consist of one person in a vehicle and two persons with a boat.
. Bennett Meadow at Rte.10 and the Connecticut River Bridge in Northfield e Captain Kids Island Camping and Picnic Area in Northfield
. Connecticut River Boat Ramp in Northfield e Munn's Ferry Camping and Picnic Area in Northfield e Pauchaug Meadow Wildlife Area in Northfield e Barton Cove Boat Ramp by Rte. 2 in Gill e Riverview Picnic Area in Northfield and Erving The actual alert and notification will be simulated by displaying appropriate equipment to the evaluator. Members of the public in the vicinity will not be affected; no boats will be launched.
Instead, a FEMA evaluator will observe arrival of the personnel at the location, check equipment, maps, pre-scripted messages, and' dosimetry, and will interview the personnel on their procedures.
O Vermont Yankei 10 March 8,1999 1999 Extent-of-Play l
Bernardston EOC - EOC staff will simulate contacting persons on their special needs lists by logging the calls at the appropriate time. The list of special needs individuals will be shown to the FEMA evaluator; however the information is confidential so copies of the list will not be provided to the evaluator.
No vehicles for alerting persons with special needs or providing transponation to the transportation dependent will be mobilized.
The Fire Liaison will dispatch personnel to alert, notify, and clear persons from the Travelers Woods (KOA) Campground and the Purple Meadow Campground. Actual notification will be simulated; s mpers will not be affected.
Colrain EOC - EOC staff will simulate contacting persons on their special needs lists by logging the calls at the appropriate time. The list of special needs individuals will be shown to the FEMA evaluator; however the information is confidential so copies of the list will not be provided to the evaluator.
No vehicles for alening persons with special needs or providing transportation to the transponation dependent will be mobilized.
The Fire Liaison will dispatch personnel to alen, notify, and clear persons from the vicinity of the Green River. Actual notification will be simulated; members of the public will not be affected.
O_
Gdl EOC - EOC staff will simulate contacting persons on their special needs lists by logging the calls at the appropriate time. The list of special needs individuals will be shown to the FEMA evaluator; however the information is confidential so copies of the list will not be provided to the evaluator.
No vehicles for alerting persons with special needs or providing transportation to the transponation dependent will be mobilized.
The Fire Liaison will notify the Franklin County Boat Club and the Oak Ridge Golf Club. No personnel will be dispatched to clear the Oak Ridge Golf Club. The Banon Cove Camp Ground s will not be notified because it doesn't open for the season until May 28,1999.
Greenfield EOC - EOC staff will simulate contacting persons on their special needs lists by logging the calls at the appropriate time. The list of special needs individuals will be shown to the FEMA evaluator; however the information is confidential so copies of the list will not be provided to the evaluator.
l The Police Liaison will demonstrate notification of the Boy Scout Camp by dispatching a cruiser to the site; however, no emergency message will be given to any Scouts using the facility nor will they be affected in any way.
O Vermont Yankel 11 March 8,1999 1999 Extent-of-Play i
No vehicles for alerting persons with special needs or providing transportation to the transportation dependent will be mobilized.
h The capability to correctly operate a TTY will be demonstrated in Greenfield by sending and receiving a test message to/from a TTY at Greenfield Community College.
Leyden EOC - EOC staff will simulate contacting persons on their special needs lists by logging the ca!!s at the appropriate times. The list of special needs individuals will be shown to the FEMA !
evaluator; however the information is confidential so copies of the list will not be provided to the evaluator.
N: vehicles for alerting persons with special needs or providing t ansportation to the transportation dependent will be mobilized.
Northfield EOC - EOC staff will simulate contxting persons on their special needs lists by logging the calls at the appropriate time. One call will be made to a control cell; all subsequent calls will be simulated. The list of special needs individuals will be shown to the FEMA evaluator; however the information is confidential so copies of the list will not be provided to the evaluator.
No vehicles for alerting persons with special needs or providing transportation to the transportation dependent will be mobilized. h The EOC will demonstrate contacting the Northfield Mountain Recreational Area to confirm notification procedures; however, no emergency message will be given and persons at Northfield Mountain will not be affected.
Warwick EOC - EOC staff will simulate contacting persons on their special needs lists by logging the calls at the appropriate time. The list of special needs individuals will be shown to the FEMA evaluator; however the information is confidential so copies of the list will not be provided to the evaluator.
No vehicles for alerting persons with special needs or providing transportation to the transportation dependent will be mobilized.
ARCAs:
67-97-15-A-31: The NorthF.:!d FOC will make a single call to a control and will simulate contacting the persons on their special needs list by logging the calls at the appropriate time. 4 l
67-95-15-A-42: This ARCA (knowledge of the plan and procedures) was resolved during an out- )
of-sequence interview of Camp Lion Knoll personnel by FEMA during the summer of 1997.
I Vermont Yankee 12 March 8,1999 1999 Extent-of-Play
I OBJECTTVE 16: IMPLEMENTATION OF PROTECTIVE ACTIONS-SCHOOLS
.O Demonstrate the capability and resources - - y to implement protective actions for school children within the plume pathway emergency planning zone.
f EXTENT OF PLAY:
Area III EOC - Contact with the University of Massachusetts campus police will be demonstrated once, at the time of initial notification, but all other calls to the University of Massachusetts will be simulated by logging the call (s) at the appropriate time (s). The UMass host facility will not be activated.
l EPZ EOCs - Initial notification will be made to all public school superintendents' offices, private
' schools, and day care centers. Subsequent calls will be made to The Giving Tree Preschool in Gill, which is the only school participating fully in this exercise. No funher calls will be made to other schools; instead, calls will be simulated and logged at the appropriate times during the exercise.
Assignments of school bus escons will be demonstrated, but escons will not be dispatched during the course of the main exercise.
l After the main exercise has concluded, an exercise of school transfer routes will be demonstrated in the towns of Bernardston, Colrain, and Gill, as follows:
Bernardston
! The exercise will begin at the direction of the local EOC's Controller, who will indicate tennination of the main exercise and the beginning of the out-of-sequence school transfer route exercise.
j The controller will direct the Greater Montague Transit Authority to dispatch one vehicle (probably a van) to the Full Circle School.
l l The Bernardston EOC will dispatch the escort vehicle with dosimetry to the Full Circle i School. -
l The Controller and FEMA Evaluator will travel with the escort vehicle to the school.
At the Full Circle School, the escon vehicle driver will issue dosimetry to the GMTA driver and lead the GMTA vehicle to Greenfield Community College host facility.
l The demonstration will conclude at Greenfield Community College; the Controller and FEMA Evaluator will return to the Bernardston EOC in the escort vehicle.
O Vermont Yankee 13 March 8,1999 1999 Extent-of-Play l
Colrain The exercise will begin at the direction of the local EOC's Controller, who willindicate g
termination of the main exercise and the beginning of the out-of-sequence school transfer route exercise.
The controller will direct Liebenow, Inc. to dispatch one vehicle (probably a van) to Colrain Central School.
The Colrain EOC will dispatch the escort vehicle with dosimetry to the Colrain Central School.
The Controller and FEMA Evaluator will travel with the escort vehicle to the school.
At the Colrain Central School, the escon vehicle driver will issue dosimetry to the Liebenow driver and lead the Liebenow vehicle to Greenfield Community College host facility.
The demonstration will conclude at Greenfield Community College; the Controller and FEMA Evaluator will return to the Colrain EOC in the escort vehicle.
Gill The exercise will begin at the direction of the local EOC's Controller, who willindicate termination of the main exercise and the beginning of the out-of-sequence school transfer g
route exercise.
The controller will direct the Wilson Bus Company to dispatch one vehicle (probably a van) to the Northfield-Mount Hermon School, Gill Campus.
i The Gill EOC will dispatch the escort vehicle with dosimetry to the Northfield-Mount Hermon School. l l
The Controller and FEMA Evaluator will travel with the escort vehicle to the school. -
At the Northfield-Mount Hermon School, the escort vehicle driver will issue dosimetry to the Wilson driver and lead the Wilson vehicle to UMass host facility. l The demonstration will conclude at UMass; the Controller and FEMA Evaluator will ,
return to the Gill EOC in the escort vehicle.
Gill-Montague Regional School District School Superintendent's Office - Only the initial call will
> be made to the Gill Elementary School and to the F. M. Kuzmeskus Bus Company. During the J
call to the bus company, vehicles and drivers will be tallied for their availability and their ETA h Vermont Yanked 14 March 8,1999 1999 Extent-of-Play i
e I A noted. No dispatch of vehicles will occur. No funher calls wiH be rnade to schools or the bus
\/
. company; all appropnate foBow-up calls will be siradatad and logged at the i ppropriate times during the exercise.
Mohawk Trail Rerional Whnol District Sq- = E='s Oha - Only the initial cai: will be nade l to the Colrain Central Elementary School and to Liebenow, Inc. (bus company). During t% call l to the bus company, vehicles and drivers will be tallied for their availability and their ETA noted.
No dispatch of vehicles will occur. No further cells will be made to schools or the bus company; all appropriate follow-up calls will be sinadatad and logged at the appropriate times during the exercise.
Pioneer Vallev Rerional School District Sunarintandant's Office - Initial notification only will be made to Pioneer Valley Regional School, Northficki Elementary Sc';ool, Bernardston Elementary School, and Pearl Rhodes Elementary School in Ieyden and Warwkk Elementary School. No further calls will be made to schools; all appropriate follow-up calls will be simulated and logged at the appropriate times during the exercise.
l The Pioneer Valley School Superintendent will arrange for a sufficient number of buses to transfer
- . all the schoolchddren in the district in one trip. Vehicles and drivers will be tallied for their l availability and their ETA noted. No dispatch of vehicles will occur. No further calls will be made to schools or the bus company; all appropriate follow-up calls will be simulated and logged at the, appropriate times during the exercise.
O Call (s) will be made to the Orange Police Station to activate the Orange Arrrery and confirm
! readmess of that facility to receive students.
l Schools and Day Care Centers - The Giving Tree School in Gill will receive initial and subsequent contacts. Students will not be involved. No vehicles will be dispatched for precautionary transfer l
or evacuation.
l The following schools and day care centers will not participate: I e Full Circle School, Bernardston e Bernardston Elementary School ..
- Colrain Central Elementary School
- Gill Elementary School e Otter Pond Preschool, Gill
.* Northfield-Mount Hermon School, Gill Campus e Northfield-Mount Hermon School, Northfield Campus
- Linden Hill School, Northfield e Pioneer Valley Regional School, Nonhfield e Pearl Rhodes Elementary School, I2yden e Northfield Elementary School e Warwick Elementary School Vermont Yankee 15 March 8,1999 L 1999 Extent-of-Play l
5 l
Host Facilities As described above, the Pioneer Valley Regional School District Superintendent's Office will contact the Orange Police Department when a precautionary transfer of school children is directed. Following termination of exercise play in the Warwick EOC, the FEMA evaluator will proceed to the Orange Police Station, conduct an interview on procedures for activating the Orange Armory, which will be opened for an inspection by FEMA.
The University of Massachusetts host facility at the Amherst Campus, Greenfield Community College, and the Girls' Club of Greenfield will not be demonstrated in 1999.
ARCA:
67-97-16-A-32: The Pioneer Valley School Superintendent vrill arrange for a sufficient number of buses to transfer all the schoolchildren in the district in one trip.
OBJECTIVE 17: TRAFFIC AND ACCESS CONTROL Demonstrate the orgamzational capability and resources necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas.
EXTENT OF PLAY:
. State EOC - State Police and Highway Department liaisons will demonstrate coordination of traffic and access control, but no personnel or equipment will actually be deployed in sequence.
The demonstration will include interstate coordination of traffic and access control, if appropriate.
Arer. III EOC - The Massachusetts State Police liaison will demonstrate coordination of traffic and access control through discussion and communication, but no personnel or equipment will be deployed to field locations.
Massachusetts State Police. Troco B. Northamoton - Personnel who might be assigned traffic and access control duties will be interviewed by the FEMA evaluator on the procedures for operating an access control point. These questions may include the following topics: purpose, .l kind, and use of dosimetry, procedures for reading dosimetry, reporting levels, obtaining equipment for setting up an access control point, procedures for operating an access control point. I Massachusetts Hichway Deoartment Facility. Deerfield - A FEMA evaluator will visit :he Massachusetts Highway Department facility in Deerfield to inspect equipment and supplies that would be used in support of traffic and access control operations.
EPZ EOCs - EPZ EOCs will demonstrate through discussions and communications the ability to direct and monitor traffic control operations within theirjurisdictions. No personnel or equipment will be deployed to field locations. Instead, local highway representatives at the local EOCs will g Vermont Yankee 16 March 8,1999 1999 Extent-of-Play
1
^
participate in a discussion of procedures and resources avadable for traffic control At a time to be deternuned, the FEMA evaluator will visit the local highwcy garage to inspect equipment that would be used for traffic control point.
ARCAs: None OBJECTIVE 18: RECEFFION CENTER-MONITORING, DECONTAMINATION, AND REGISTRATION Demonstrate the adequacy of procedures, facilities, equipment and personnel for the radiological monitoring, decontamination and registration of evacuees.
EXTENT OF PLAY:
Gree.nfield Community College Reception Center will not be demonstrated in this exercise.
ARCA:
67-97-18-A-33: During the next exercise involving Greenfield Community College Reception Center, monitoring teams will demonstrate determining background radiation and monitoring at a rate of one to two inches a second.
OBJECTIVE 19: CONGREGATE CARE 1
Demonstrate the adequacy of facilities, equipment, supplies, personnel, and procedures for congregate care of evacuees.
EXTENT OF PLAY: !
i i This Greenfield Armory, Greenfield High School, and Federal Street School will not be demonstrated in 1999, but shelter surveys will be provided to FEMA.
l ARCAs: None ;
OBJECTIVE 20: MEDICAL SERVICES-TRANSPORTATION o
Vermont Yanked 17 March 8,1999 1999 Extent-of-Play t
Demonstrate the adequacy of vehicles, equipment, procedures and personnel for transporting contammated, injured, or exposed individuals.
EX'IENT OF FLAY:
This objective was last demonstrated by Bay State Health System Ambulance on November 3, 1998, and is documented in the Annual Medical Services Exercise report for Vermont Yankee Nuclear Pcwer Station, published by FEMA on December 1,1998.
ARCAs: None OBJECTIVE 21: MEDICAL SERVICES-FACILITIES Demonstrate the adequacy of the equipment, procedures, supplies, and personnel of medical facaities responsible for treatment of contaminated, injured, or exposed individuals.
EXTENT OF PLAY:
This objective was last demonstrated by Frankhn Medical Center on November 3,1998, and is documented in the Annual Medical Services Exe.ase report for Vermont Yankee Nuclear Power Station, published by FEMA on December 1,1998. g ARCAs: None OBJECTIVE 22: EMERGENCY WORKERS, EQUIPMENT, AND VEHICLES-MONITORING AND DECONTAMINATION Demonstrate the adequacy of procedures for the monitoring and decontamination of emergency workers, equipment, and vehicles. ..
EXTENT OF PLAY:
l This objective will not be demonstrated by Gill, Greenfield, or Warwick in 1999.
This objective will be demonstrated by Colrain out of sequence after exercise play in the Colrain EOC has terminated. An independent scenario will be used to drive the exercise play at the RM&D Station.
Individuals simulating emergency workers in Colrain will be processed through the facility, with one male and one female declared contaminated. Personnel decontamination demonstration will O
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Vermont Yankee 18 March 8,1999 4
1999 Extent-of-Play
1 i
be sirnulated using a discuuion of methods and techniques. Vehicle monitoring will be performed l on one vehicle, and handhng of contaminated vehicles will be discussed.
ARCAs: None OBJECTIVE 23: SUPPLEMENTARY ASSISTANCE (FEDERAI/OTHER)
Demonstrate the ability to identify the need for external assistance and to request such assistance from federal or other suptwrt organizations. ,
EXTENT OF PLAY: l l
This obytive will not be evaluated in 1999.
ARCAs: None l
l 0
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U Vermont Yankee 19 March 8,1999 1999 Extent-of-Play
OBJECTIVE 24: POST- EMERGENCY SAMPLING O
Demonstrate the use of equipment and procedures for the collection and transportation of samples from areas that received deposition from the airborne plume.
EXTENT OF PLAY:
This objective will be demonstrated in November 1999, during the Pilgrim Exercise.
ARCAs: None OBJECTIVE 25: LABORATORY OPERATIONS Demonstrate laboratory operations and procedures for measuring and analyzing samples.
EXTENT OF PLAY:
This objective will be demonstrated in November 1999, during the Pilgrim Exercise.
ARCAs: None g
OBJECTIVE 26: INGESTION EXPOSURE PATHWAY-DOSE PROJECTION AND PROTECTIVE ACTION DECISION-MAKING Demonstrate the capability to project dose to the public for the ingestion exposure pathway and to recommend protective actions.
EXTENT OF PLAY:
2 No exceptions.
ARCAs: None OBJECTIVE 27: INGESTION EXPOSURE PATHWAY- PROTECTIVE ACTION IMPLEMENTATION Demonstrate the capability to hnplement protective actions for the ingestion exposure pathway.
EXTENT OF PLAY: g Vermont Yanked 20 March 8,1999 1999 Extent-of-Play 1
r l
O S- EOC This ob;ective wiii be demonstrated in a tabiete, format. Exercise ,iay wiii inciude the demonstrui.n of communications and coordination that will be required between organivations a vnplement ingestion pathway protective actions. However, actual field play of implementation activities will be simulated. For example, communication and coordination with l agencies responsible for implementing food, milk and water controls within the ingestion pathway EPZ will be demonstrated, but actual communications with food producers and processors will be
! simulated by showing the FEMA evaluators the contact list (s) of farmers, food producers, and processors that would be used in a real emergency. Since the information is confidential, a copy i will not be provided to FEMA; however, the evaluator will be shown either a hard copy or the
! data on computer. Depending on the scenario, the MDPH Dose Assessment Group may assist Vermont or New Hampshire if requested.
^
All coordination and communicacon with state-level emergency response orgamzations, including state organizations in Vermont and New Hampshire and participating federal organizations, will l be fully demonstrated. Coordination and commumcation with local communities will be simulated through a discussion and loggic;; at the appropriate time (s).
All appropriate news advisories informing the public of protective actions and other essential information will be developed and dissemmated within the State EOC and Area III EOC. News advisories will be sent to the Media Center ifit is still in operation; if not, they will be sent directly to the Vermont and New Hampshire state EOCs. They will not be sent to the media outlets.
O Instead, MEMA will demonstrate all steps up to, but not including, the dissemmation of news advisories to the radio stations listed in the Emergency Public Information Calendar, as well as to wire services and major media outlets in Boston and Springfield, Mass.
MDPH will discuss methods of distributing pre-printed instructional material on ingestion-related protective actions to the general public and to farmers, food processors, and food distributors.
Brochures for farmers, agricultural workers, food processors and food distributors are available and stockpiled ready for distribution as needed. Distribution lists will be provided by MDPH and distribution methods discussed, but actual distribution will be simulated. l
\
As the public alert and notification system (combination of NOAA weather-alert radios or town ..
sirens and selected EAS radio stations) is designed to serve only the EPZ communities, the public alert and notification system will not be used for post-emergency phase public information.
All other actions regarding implementation of ingestion exposure pathway implementation will be simulated through discussion and logging of the action (s) at the appropriate time (s).
i Area III EOC - The EOC will be partially staffed and will demonstrate coordination and l cmumunications with the State EOC and other state emergency response organizations. All other auns regarding implementation ofingest. ion exposure pathway implementation will be simulated truuugh discussion and logging of the action (s) at the appropriate time (s).
h EPZ EOCs - Will not participate in post-emergency phase demonstrations.
Vermont Yankee 21 March 8,1999 1999 Extent-of-Play l'
- 1 l
ARCAs: None OBJECTIVE 28: RELOCATION, RE-ENTRY, AND RETURN-DECISION MAKING Demonstrate the capability to develop decisions on relocation, re-entry, and return.
EXTENT OF PLAY:
State EOC -If required by the scenario, decision-making regarding relocation, re-entry to previously evacuated areas, and return to previously evacuated areas will be fully demonstrated.
All appropriate state-level and interstate coordination and communication will be demonstrated.
Communication and coordination with federal agencies participating in the exercise will be fully demonstrated. Any communications or coordination with towns or non-participating federal agencies will be simulated by logging the call (s).
Area III EOC - Will demonstrate coordination and communications with the State EOC and other state emergency response orgamzations. Communication and coordination with local EOCs will be simulated through discussion and logging of the action (s) at the appropriate time (s).
EPZ EOCs - Will not participate in post-emergency phase demonstrations. g ARCAs: None OBJECTIVE 29: RELOCATION, RE ENTRY, AND RETURN -IMPLEMENTATION Demonstrate the capability to implement appropriate measures for relocation, re-entry, and return.
EXTENT OF PLAY: .
State EOC - Depending on the scenario requirements for relocation, re-entry, and return, the following elements may be demonstrated as detailed below:
- Coordination with Area III in preparation for relocation, re-entry, or return will be discussed in detail
- Consideration and discussions oflogistics
- Rescinding of any evacuation directives that are no longer needed and informing evacuees through notice to reception centers (if still open), mass care shelters, and through news advisories, etc. Notices and news advisories will be prepared but not delivered to shelters, reception centers, or the news media.
O Vermont Yankee 22 March 8,1999 1999 Extent-of-Play
1 I
Termination of access control will be demonstrated through discussion and appropriate Communications e Maintenance of traffic control will be demonstrated through a discussion and communications to exchange information and verify personnel and equipment requirements. No deployment will occur.
- Establishment of new access control points will be demonstrated through a discussion and i communications to exchange information and verify personnel and equipment requirements.
No deployment will occur.
l
- Communication and coordination with State Police and Highway representatives will be fully demonstrated but no deployment will occur.
- All appropriate state-level and interstate communications related to traffic and access control will be fully demonstrated.
- Any communications to town police or highway /public works departments will be simulated .
by logging the call (s) e Appropriate public information will be developed during demonstration of the post-emergency phase. News advisories will be written and disseminated within the State EOC, Area III EOC, and the Media Center if still in operation; however, they will not be sent to the media outlets.
- As the public alert and notification system (combination of NOAA weather-alert radios or town sirens and selected EAS radio stations) is designed to serve only the EPZ commumties, '
the public alert and notification system will not be used for post-emergency phase public i information. Instead, MEMA will demonstrate decision-makmg and all steps up to, but not !
,q including, the dissemination of news advisories to the radio stations listed in the Emergency I U Public Information Calendar, as well as to wire services and major media outlets in Boston and Springfield, Mass.
Area III EOC - Partial staff will demonstrate coordination and communications with the State EOC and other state emergency response organizations. Depending on the requirements of the i scenario, the following elements may be demonstrated:
- Preparation for relocation, re-entry, or return will be fully discussed with the State EOC.
- Coordination and communication with local officials in preparation for relocation, re-entry, or return will be .cimulated through discussion and logging at the appropriate time (s) i e Consideration and discussions of logistics will be fully demonstrated ,
EPZ EOCs - Will not participate in post-emergency phase demonstrations.
ARCAs: None OBJECTIVE 30: CONTINUOUS,24-HR STAFFING Demonstrate the capability to maintain staffing on a continuous 24-hour basis through an actual shift change.
O ExrENr OP PtAv:
Vermont Yankee 23 March 8,1999 1999 Extent-of-Play
f This objective will be demonstrate'd at the following locations in 1999.
State EOC
~
Rosters will be developed showing two shifts for the following key personnel:
e Director j e Operations Officer
- Public Affairs Officer e Technical Hazards Officer e Communications Officer
- Public Information Officer
- MDPH EOF Liaison
- MDPH Representative at the State EOC e Mass. Highway Dept. Liaison e Mass. State Police Liaison Area III EOC Rosters will be developed showing two shifts for the following key personnel:
. Director e Operations g
- Communications w This objective will not be demonstrated at the following locations:
- Leyden EOC ..
- Northfield EOC e Warwick EOC ARCAs: None OBJECTIVE 31: OFFSITE SUPPORT FOR THE EVACUATION OF ONSITE PERSONNEL Demonstrate the capability to provide offsite support for the evacuation of onsite personnel.
l O
Vermont Yankee 24 March 8,1999 1999 Extent-of-Play
! l Q EXTENT OF PLAY:
This objective does not apply to Massachusetts.
OBJECTIVE 32: UNANNOUNCED EXERCISE OR DRILL Demonstrate the capability to carry out emergency response functions in an unannounced exercise or drill.
EXTENT OF PLAY:
This objective was demonstrated out of sequence in September 1998.
ARCAs: None OBJECTIVE 33: OFF-HOURS EXERCISE OR DRILL Demonstrate the capability to carry out emergency response functions during an off-hours exercise or drill.
EXTENT OF PLAY:
This objective was demonstrated out-of-sequence in September 1998.
ARCAs: None
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Vermont Yankee 25 March 8,1999 1999 Extent-of-Play
R:v.1 Page 3.1-1 VERMONT YANKEE NUCLEAR POWER STATION f
s EMERGENCY PREPAREDNESS EXERCISE 1999 11 EXERCISE GUIDELINES AND GROUND RULES The Vermont Yankee Emergency Preparedness Exercise will be conducted on Tuesday, April 27,1999.
1999 is a 'Tull-participabon biennial" exercise The exercise will involve full p.itk,ip.t.wn from Vermont Yankee, State of Vermont, State of New Hampshire, Commonwealth of Massachusetts, and local towns within the plume exposure EPZ. All Vermont Yankee emergency response facilities will be fully activated, and the scenario will be driven by the simulator, as in past drills and exercises. State and local off-site objectives will be demonstrated for FEMA observation and evaluation This section provides the guidance and ground rules for conducting the 1999 Vermont Yankee Emergency Preparedness Exercise it provides the framework for conducting the exercise, demonstrating emergency response capabilities, and evaluating response activities.
- l. Concepts of Operabons and Control A. Exercise Controller Operations Vermont Yankee management has appointed an Exercise Coordinator to oversee all exercise activities. The Exercise Coordinator is responsible for approving the objecbves and developing the scenario time sequence. The Exercise Coordinator is aiso responsible for the selection and training of exercise controllers who are required to conduct and evaluate the exercise.
Vermont Yankee will supply Controllers for major locations where an emergency response action will be demonstrated Before the exercise, the Controllers will be provided with the appropriate materials necessary for their assigned function. The material willinclude any maps and messages to be used j and forms for documenting and evaluating observed activities.
In each facility where an activity takes place, the designated Lead Controller will make judgment decisions to keep the action going in accordance with the scenario time line. The Lead Controllers will provide advice to other Controllers assigned to their facility to resolve minor exercise control issues or concems that may occur if a major exercise control problem arises, the Controller should first contact the Lead Controller who will then contact the Exercise Coordinator for guidance or resolution of the problem. All major requests for scenario modifications or holding periods must be cleared through the Exercise Coordinator. Controllers also have the authority to resolve scenario-related problems that may occur during the exercise.
r RLv.1 Paga 3.1-2
.D i(v) Controllers will observe the players as they perform their assigned emergency response functions.
Controllers are responsible for being knowledgeable in the area of their assigned function and possible activities that may be observed. In the event of corrective or repair activities, the Cnntroller shall be cognizant of procedures assaciated with the action. If an activity is to be simulated (as identified within the specific mini-scenarios or exercise ground rules), the Controller shall request the players to describe the actions that would be initiated to effect the desired outcome of the assigned l task within the scenario time sequence of events and constraints allowed. The Controllers will critique the effectiveness of the emergencv response actions taken and will also provide a written evaluation of their observations.
The initial conditions will be provided to a Control Room operations crew, located in the Simulator.
The accident scenario will be run on the plant simulator to generate the plant and reactor system parameters for the exercise. Additional message cards and scenario parameters will be provided by Controllers at the times indicated in the exercise sequence of events or when required by player actions.
As information is provided to the players, they should determine the nature of the emergency and implement appropriate plant procedures including emergency plan impicmenting procedures and
/O emergency operating procedures. These procedures should include a determination of the
'b emergency classification in accordance with the Vermont Yankee Emergency Plan. Notifications will be made to the appropriate federal and state authorities.
The hypothesized emergency will continue to develop based on data and information provided to the operators located in the simulator. Wherever possible, operators should complete actions as if they were actually responding to plant events. Inconsistencies in the scenario may be intentional and ;
may be required to test the capabilities of the emergency response facilities to the maximum extent possible in a limited period of time.
B. Avoidino Violations of Laws Violation of laws is not justifiable during the exercise. To implement this guideline the following actions must be taken:
- 1. Participants must be specrfically informed of the need to avoid violating any federal, state and local laws, regulations, ordinances, statutes and other legal restrictions. The orders of l
all police, sheriffs or other authorities shall be followed as appropriate.
O V 2. Participants will not direct illegal actions to be taken by other participants or members of the general public.
E Rev.1 Page 3.1-3 b 3. Partopants wiH not intentionah take illegal schons when responding to scenario events. j Specificany, local traffic laws (i.e. speed limits) wiu be observed. !
l C. Avoidano Personnel and Property Endanoerment l AH participants will be instructed to avoid endangenng property (public or private), other personnel responding to the events, members of the general public, animals and the environment.
l l
D. Actions to Minimize Public Inconvenience r
l l It is not the intent, nor is it desirable, to effeciively train or test the public response during the conduct I of the exercise Public inconvenience is to be avoided.
The conduct of the exercise could arouse public concem that an actual emergency is occurring. It is
' rW-a t that conversations that can be monitored by the public (radio, loudspeakers, etc.) be prefaced and concluded with the words, "THIS IS A DRILL; THIS IS A DRILL" I l
- 11. General Guidance for the Conduct of the Exercise O A. Exercise Simulation l
Since the exercise is intended to demonstrate actual capabilities as realistically as possible, participants will be instructed to act as they would in an actual emergency. Wherever possible, emergency response acbons will be carried out. Some of the exercise objectives will be j l demonstrated by simulating the maneinted emergency response acbons. Simulation of response )
l ;
l activities will occur when specific acbons do not have to be performed, and when schons are outside '
of the defined mini-scenarios (refer to Section 7.2). When an emergency response is to be simulated, the Controller will provide verbal or wntten direcbons on acbons that are to be simulated.
The following describes those specific actions that do not have to be performed and can be simulated by participants. No acbon will be allowed which alters or affects the ongoing operation of the plant.
wiH be connected to the Simulated Plant Process Computer (SPPCS) via the simulator to receive and display scenario-related data. The Main Plant Control Room's workstation terminals will remain tied to the plant process computer (ERFIS).
O
Rev.1 Page 3.1-4
- 2. A number of individuais from the Vermont Yankee Emergency Response Organization will
, be pre-staged to facilitate exercise and simulator related logistics. Individuals that will be pre-staged include the following:
- a. The Operating crew in the Simulator Control Room and the crew's AOs and other personnel at the plant to compliment the operating crew at the Simulator.
- b. The Chemetry technician assigned as the Chemetry Communicator in the Simulator Control Room if requested by SS/ PED.
- c. An individual assigned as an Altemate Communicator in the Simulator Control if requested by SS/ PED.
- d. An R&CE person assigned to the Simulator Control Room for data acquisition if requested by TSC personnel.
& An RP person assigned to the Simulator Control Room for data acquisition if requested by TSC Coordinator.
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\ f. R&CE personnel to set up the ERFIS terminals in the SPPCS mode
- 3. Meteorological data will be simulated through the simulator SPPCS computer.
- 4. After plant evacuabon and accountability have been completed, plant personnel and contractors /vmitors, not directly involved in the exercise, will be allowed to retum to work at the discrebon of the TSC Coordinator.
- 5. Discussion of potassium iodide (Kl) usage will be done if scenario conditions warrant its use.
However, distnbubon and ingestion of KI will be simulated.
- 6. If off-site monitoring sampling is required, charcoal cartndges will be used in place of silver zoollte cartridges
- 7. Off-Site monitoring teams and security boundary monitoring personnel will not wear either protective clothing or respirators
- 8. The inner gate and electrically controlled doors will not be left in the open position during the exercise
Rev.1 Page 3.1-5
' 9. The plant Gai-Tronics is available between the Simulator Control Room and the plant through the use of an interface device Although not a complete duphcabon it will allow a person in the plant to talk directly to the simulator over the plant Gai-Tronics. However, actual plant announcements will be coordinated by the controllers and made from the Vermont Yankee plant Main Control Room.
- 10. Exercee Controllers will not be issued dosimetry unless plant access is required before the exercme Security will be nobfied of the Exercise Controllers assigned locatens.
- 11. The Exercise Controller may simulate all decontamination acbons assocated with the scenario events af'er discussion and approval.
- 12. Plant personnel may simulate the use of rsspiratory pn/=,ction equipment after discussion and approval by the Exercme Controller.
B. Player's Guidehnes and Gamesmanship The following is a list of general guidelines and instructons for the players regarding the exercise. ,
- 1. Participants will include Exercise Controllers, Players, and NRC and FEMA Evaluators.
Exercise Controllers will provide players with command and message cards to initiate emergency response actions and evaluate player actions. NRC/ FEMA Evaluators will also evaluate and note player acbons. Exercise Controllers and NRC/ FEMA Evaluators will wear badges foridentificaten purposes
- 2. Always identify yourself by name and funcbon to the Exercise Controllers. Wear a name tag if one is provided.
- 3. You may ask the Exercise Controller for informabon such as:
- a. Initial conditions of the plant and systems including:
o operating history of the core o initial coolant activity o generalweather conditions o availability of systems according to the scenario
- b. Area radiation data at the location of emergency teams.
c.- Airbome data at the location of emergency teams after a sample has been properly obtained.
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/ d. Activity from nose swabs or skin contaminabon surveys.
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- 4. You rney ,r!gt ask the followmg from the Exercise Controllers:
l a. Informabon contained in procedures, drawings, or instruebons.
- b. Judgments as to which procedures should be used.
- c. Data which will be made available later in the scenario.
- d. Assistance in performing actions.
- e. Assistance in performing calculations.
- 5. Play out all schons, as much as possible, in accordance with your plan and procedures as if it ware an actual emergency. If an acbon or data is to be simulated, he Exercise Controller willprovideappig ^ direcbon i
- 6. Periodically speak aloud, identifying your key schons and decmions to the Exercise
! N' Controllers and NRC Evaluators, especially if present in your facility and observing your funcbons. This may seem artifical, but it will assist the controllers in determining the various l response achons being initiated and is to your benefit.
- 7. When you are assigned to complete a response action, notify an Exercise Controller before performing the action Let the Exercise Controllers decde which actions will be observed and which ones will not. If the Exercise Controller elects to observe your activity, ensure the Exercme Controller remains with you to observe the task (i.e. do not lose the controller en-route to the area where the schon will take place).
- 8. If you are in doubt about completing a response acbon, ask your Exercise Controller for clanfication. The Exercise Controller will not prompt or coach you. Emergency response schons must not place participants in any r)otentially hazardous situabons. ,
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- 9. The scenario has been scrutinized to anticipate as many success paths that may be inibated by the response teams. In the event you or your staff determine there may be altamabve responses to scenario conditions, you may not be allowed to initiate your proposed "fix".
However, the inibabwe will be noted but you will be requested to continue your response in accordance with the proposed scenario events from the Exercise Controller. In addition, the Exercise Controller may penodically issue messages or instruebons designed to initiate response acbons. .You miat accept these messages immediately. They are essential to the proper ceir$6(i of the exercise scenario.
- 10. If the Exercise Controller intervenes in your response achons and recommends you redirect or reconsider your play acbons, it is for a good reason The Exercise Controller's direchon l
l may be essential to ensure demonstrabon of objechves for all participating groups.
I- 11. If you disagree with your Exercise Controller, discuss your concems in a professional manner. However, the Exercise Controller's final decisions should be followed l
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- 12. Respond to questions in a timely manner.
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- 13. Do not accept exercise-related scenario messages / instructions from the NRC Evaluators.
They should work through Vermont Yankee Exercise Controllers if they want to initiate additional emergency conditions. However, you may answer questions directed to you by j the NRC Evaluators if you do not know the answer, offer to get them the answer as soon as possible (without interfering with exercise activities) or refer them to your lead facilti player or Exercise Controller.
- 14. You must respond as if elevated radiation levels are actually present based on the scenario informabon you receive. This may require you to wear protechve clothing, respirators, or additionaldosimetry.
- 15. Exercise Controllers are exempt from simulated radiation levels and other emergency conditions. Do not let this confuse you or cause you to act unwisely. However, no one is exempt from normal plant radiological pracbees and procedures.
- 16. Use status boards and logbooks as much as possible to document and record your actions.
- 17. Alwayr begin and end all communications with the words "THIS IS A DRILL," so that
- exercisselsted communicabons are not confused with an actual emergency.
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- 18. Keep a list of items that you believe will improve your plans and procedures. A player debriefing will follow the exercise. Provide any comments or observations to your lead player or Exercise Controller after the exercise. Areas for improvement or weaknesses when corrected will improve the overall emergency response capability.
The following is a list of items to improve gamesmanship during the exercise:
- 1. Make it known when significant events occur or when you are about to perform a significant activity.
- 2. Keep all messages, status boards, and problem boards accurate, current, timed, and dated.
- 3. Hold briefings regularly, approximately every 30-45 minutes, or as conditions warrant.
4, Key players should wear badges that identify their role. Bound logbooks should be used in all emergency response facilities. !
- 5. All announcements, including those on the Gai-Tronics, should state "THIS IS A DRILL."
- 6. Avoid simulation unless it has been specified. Use protective clothing where called for (e.g.,
step-off pads, etc.). !
k C. Simulator Control Room (SCR) Information The following describes how the SCR emergency .esponse activities will be integrated with the plant Control Room functions during the exercise:
- 1. Players reporting to the plant Control Room will be directed to an area (SS office) that will have a Control Room Controller sad communications link with the simulator. All Control Room exercise communications should be directed to the SCR.
- 2. An interface device has been installed to connect the Simulator Control Room in Brattleboro with the plant Gai-Tronics system. Although not a complete duplication it will allow a person in the plant to talk directly to the simulator over the plant Gai-Tronics. The Controller in the plant Main Control Room will monitored and manually actuated the interface, causing a slight delay between initial communications. CHANNEL 3 will be the designated line to be used for communications between the Simulator Control Room and the Plant. CHANNEL 1 and CHANNEL 2 will be the designated lines for all other plant exercise related communications and messages.
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( 3. Gai-Tronics announcements done in the Simulator Control Room will be coordinated by the Simulator Control Room Controller and made from the Vermont Yankee plant Main Control Room. The announcements will be made and repented by the Controller or Operating crew in the plant Main Control Room.
- 4. TSC Communicators normally assigned to the Control Room and a Radiation Protection Technician for transmitting radiological and meteorological data will be pre-staged in the simulator, j i
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- 5. Personnel movement in and out of the SCR will be limited to the Exercise Controllers and designated exercise participants.
- 6. Communications equipment in the SCR is the same as the plant Control Room. The commercial telephone extensions are different, but the auto-ring down circuits and speaker telephones will be operable. The orange Nuclear Alert System (NAS) State telephone and Federal Telecommunications System (FTS 2000) Emergency twu cation System (ENS)-
NRC telephone will be operable. The orange Nuclear Alert System telephone extension in !
the Simulatoris 613.
A D. Personnel Accountability and Participation (Exemoted Participants)
Procedures require that all participants be identified. Proper identification will not only help eliminate confusion, but is necessary for security and accountability. This requirement applies to all areas within the plant fence, Govemor Hunt House, EOF /RC, simulator area, News Media Center, and the Vermont Yankee Corporate Office in Brattleboro.
Although it is expected that all personnel will respond to the declared emergency as delineated in the applicable procedures, it is recognized that a number of persons (e.g., normal plant operations shift, normal security complement, fire watches, etc.) will not participate due to the nature of their assigned duties and activities. Department Heads will be requested to review their area of responsibility and provide the Exercise Coordinator with a list of names for anyone that should be exempted from participation. The number of exemot personnel should be minimized.
Plant Security will be provided with the list of exempt personnel for the exercise. All other personnel, not listed, are expected to participate as required by the Emergency Plan. The list of exempt n personnel will include the On-Shift Security Crew, Operating Crew, and Duty Chemistry and !
U Radiation Protection Technician and other individuals identified by the Department Heads.
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Rev.1 Page 3.1-10 E. Off-S te Particiombon (Federal. State and Loca0 This year, Vermont Yankee is conducting a " full partici,.stion biennial" exercise that will involve substantial participabon from the States of Vermont, New Hampshire, Commonwealth of Massachusetts and the local towns within the plume exposure EPZ. This is NRC's and FEMA's biennial look at the state of emergency preparedness of all three states, local towns and Vermont Yankee. No NRC Emergency incident Response Team participabon is planned for this exercee The capability to notify federal, state, and local authorities of emergency classifications in accordance with established procedures will be demonstrated as follows:
- 2. Vermont, New Hampshire, and Massachusetts State Police dispatchers and State Emergency Operabons Centers (EOCs) will be nobfied through the orange Nuclear Alert System telephone
- 3. Vermont, New Hampshire, and Massachusetts State officials at the EOF /RC and the News Media Center (NMC) will be nobfied by the appropii.i. Vermont Yankee personnel (if available and participating in the exercise).
If any state official tries to contact the actual plant Control Room REGARDING THE EXERCISE, the Vemon switchboard should transfer the call to the Simulator Control Room in Brattleboro F. Exercise Cnbaues The following is a brief description of the critique sessions that will be held after the exercise. The critique sessions are held to determine whether the stated exercise objechves were met, verify the effectiveness of the emergency plan and procedures, and iden5fy areas for future improvements.
The specific schedule for the critique sessions will be announced at the conclusion of the exercise.
Emeroency Response Facility Cnbaues The Controllers will conduct the critique sessions. Excrcise participants will be debnefed on the findings for their particular emergency response facility (s). Four critique sessions will be held:
- 4. News Media Center
E Rev.1 Page 3.1-11 Lead Controller Debne6no This session will be conducted to compile all exercme comments and findings. Participation is limited to Lead Controllers or other Exercise Controllers as needed Exercise Critmue This session will be conducted to present a summary of mapr findings identified during the exercise Partopants include Vermont Yankee management, Exercise Controllers, key players, and the NRC.
H. Exercme Termnaten The Exercise Coordinator will terminate the exercise when all emergency response acbons have l- been completed h accordance with the exercise scenario time sequence and exercise objectives.
l The following steps will be implemented to terminate the exercise D 1. The Exercee Coordinator will obtain informaton from the Lead Controllers regarding the status of player schons and the demonstration of the exercise objectives.
- 2. The Lead Controllers are responsible for informing the Exercise Coordinator of their facility status and whether the emergency response acbons and objectives have been satisfactorily observed.
- 3. Upon receipt of informabon from the Lead Controllers, the Exercise Coordinator will inform the Site Recovery Manager and TSC Coordinator that all exercise objectives have been completed and the exercise can be terminated.
- 4. A coordinated decmon to terminate the exercme will be made between the Site Recovery Manager and the TSC Coordinator. The Site Recovery Manager will also receive concurrence from the states to terminate exercise activities.
- 5. The Site Recovery Manager will terminate the exercise.
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y-L Rt.v.1 Page 3.1-12 I The exercise may also be terminated under the following circumstances:
A. In the event of an actual plant emergency condition should occur, the following actions will be taken:
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- 1. The Shift Supervisor will contact the TSC Coordinator and inform him of the plant status.
- 2. The TSC Coordinator will, in tum, contact the Site Recovery Manager and inform him of the plant status.
- 3. The Site Recovery Manager will immediately inform any State representatives at the EOF of the ,
l nature of the emergency.
- 4. Concurrent with the notification in Step 2, the Control Room will announce the following statement over the plant paging system:
I l "The emergency plan exercise has been terminated. I repeat. The emergency plan exercise has l been terminated."
This message may be immediately followed by the appropnate emergency announcements.
- 5. The Exercise Coordinator will be responsible for directing the, actions of all other exercise A participants.
B. In the event that actual off sita emergency impacts the response actions of Vermont Yankee participants, the following actions should be taken:
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- 1. The Shift Supervisor will notify the Control Room Controller who, in tum, will notify the Exercise !
Coordinator. l
- 2. A coordinated decision will be made in conjunction with the Site Recovery Manager and/or the TSC and EOF Coordinators concoming the completion of the exercise.
- 3. The Exercise Coordinator will be responsible for temporarily halting the exercise until such time a decision is made to terminate or continuing the exercise. !
- 4. If the final decision is to terminate the exercise, the Exercise Coordinator will be responsible for directing the activities of all exercise participants, as well as for informing the NRC of the exercise termination
- 5. If the final decison is to continue the exercise, the Exercise Coordinator is responsible for informing all Controllers of any projected changes to the expected response action (s).
- 6. The Exercise Coordinator will direct the organization as to the appropriate actions required for 7
restoring the exercise scenario sequence.
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( Page 3.2-1 L VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999
- 12. EMERGENCY PLAN IMPLEMENTING PROCEDURE EXECUTION UST Procedure Number Rev.No. Illa AP 3125 16 Emergency Plan Classification and Action Level Scheme OP 3500 18 Unusual Event OP 3501 19 Alert OP 3502 31 Site Area Emergency OP 3503 33 General Emergency OP 3504 31 Emergency Communications OP 3507 28 Emergency Radiation Exposure Control OP 3510 23 Off-Site and Site Boundary Monitoring OP 3511 11 Off site Protective Action Recommendations OP 3513 20 Evaluation of Off-Site Radiological Conditions OP 3524 15 Emergency Actions to Ensure Initial Accountability and Security Response OP 3525 9 Radiological Coordination OP 3531 12 Emargency Call-in Method OP 3533 3 Poet Accident Sampling of Reactor Coolant OP 3534 2 Post Accident Sampling of Plant Stack Gaseous Releases OP 3535 2 Post Accident Sampling and Analysis of Primary Containment OP 3536 1 in Plant Air Sample Analysis with Abnormal Condition
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 il CONTROLLER ASSIGNMENTS NOTE: ASSIGNMENTS TO BE ISSUED UNDER SEPARATE MEMO AND REVIEWED AT THE EXERCISE CONTROLLER BRIEFING SESSION O
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Rev.1 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE Page 4.2-1 1999 M CONTROLLER EXERCISE GUIDANCE Before the exercise, each Controller will be provided a scenario package that corresponds to their respective assignments. It is the responsibility of the Controller to read the contents -
of the scenario package and understand their controller assignments.
Each Controller will be requested to attend appropriate training or briefing sessions before the exercise. Any questions regarding the scenario or assignments should be discussed at this time. Each Controller should ensure that they are familiar with location (s) required by l their assignment.
Controllers should familiarize themselves with their assigned Lead Controller before the exercise. The Lead Controller is responsible to direct Controller activities throughout the course of the exercise. At the exercise termination, each Controller is responsible to provide their comments, observations and documentation to the Lead Controller. Each Lead Controller is responsible to provide this documentation to the Exercise Coordinator.
Each Lead Controller is also responsible to provide a brief summary of their Controller comments to the Exercise Coordinator for presentation during the critique.
l Controllers should identify themselves to players and explain their role in the exercise. !
Players should be told that if any actions are going to deviate from standard plant or l emergency procedures must be identified to the Controllers. Controllers should keep a detailed log of their observations throughout the exercise. This log should note the time, location, activity and player responses. Section 4.3 contains log sheets, checklists,' and i evaluation forms for documentation purposes.
The primary role of the Controller is to document the emergency response activities of the players. In order to document emergency response activities, each Controller is required to complete the Emergency Exercise / Drill Controller's Evaluation Form (VYOPF 3505.02).
When completing this form, each Controller should provide information on overall performance and observations (strength noted of positive actions taken or expected actions done well), comments / recommendations (specific areas that may warrant further evaluation for improvement), and potential weaknesses (inadequate performance). (inadequate indicates tha* the demonstrated performance could have precluded effective implementation of plans or procedures.) For comments / recommendations and potential weaknesses (inadequate performance), the Controller should provide a clear written description of the finding or observation.
i Rev.1 g Page 4.2-2 Controllers should Dg1 allow their biases to be documented as recognized weaknesses or deficiencies. Observations and comments may be further subdivided according to the following major headings: Facility Activation and Organizational Control, Communications, Adherence to Plans and Procedures, Equipment Capabilities, Scenario, Training, Facility Layout, Off-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Comments.
Facility Activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the facility was activated; (3) when initial activities are organized; (4) whether personnel performance follows the organized arrangements l specified by plant procedures; and (5) the efficiency of methods of authority transfer. If a transfer of responsibility occurs, then the Controller should determine if affected personnel are aware that the transfer has occurred.
Communication comments should identify: (1) personnel familiarity with emergency communk:ations use; (2) whether sufficient communications were available to ensure a timely, efficient, and effective flow of information; (3) whether there were enough communications personnel to make use of all available equipment; (4) the adequacy of I
communications logs and describe the effectiveness of data transfer; (5) whether there were any problems in the design of the existing communications system (i.e., location relative to traffic flow); (6) whether there were any recognized difficulties in use of computer systems; and (7) whether status boards are effectively used. Controllers should document their comments in this area very carefully, providing sufficient details to track any recognized deficiencies.
Plans and Procedures comments should identify: (1) whether personnel were familiar with the details or overall concepts of applicable procedures; (2) whether situations developed which required deviation from the procedure or plan; (3) whether personnel were overwhelmed with procedural requirements distracting them from performing their required emergency response function; and (4) whether the procedures adequately described the actions required to complete an assigned function.
1 Eauloment Caoability comments should identify: (1) whether all necessary materials and i equipment were available and functional; (2) whether emergency response personnel checked operability of equipment prior to conducting their assignment; (3) whether backup l equipment was readily available when malfunctions were reported; (4) whether the available systems provide an adequate service; and (5) whether equipment malfunctions impacted the expected emergency response.
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Rev.1 Page 4.2-3 Scenario related comments should identify: (1) whether sufficient information was availab's to ensure appropriate player response; (2) whether the scenario details deviated from actual procedural requirements; and (3) whether the scenario detail provided any prompts to the player.
Trainina comments should identify: (1) whether plant personnel have been provided sufficient training for their assigned ERO position; and (2) whether ERO personnel understand their emergency response roles and responsibilities.
Facility Lavout comments should identify: (1) whether the available work space was adequate; (2) whether traffic flow hindered the response efforts; (3) whether the communications available in the work area were adequate; (4) whether the noise level hindered emergency response efforts; and (5) whether sufficient references were available to complete the job assignment.
Off-Site Monitorina comments should identify: (1) the adequacy of sampling methods; (2) the adequacy of reporting and documentation; and (3) the effectiveness of the team in defining radiological status. Dose projection methods should also be evaluated with this general category. Consideration of dose projection methods should identify (1) the effectiveness of methods to interpret off-site conditions; and (2) the effectiveness of using the dose projections in positioning off-site teams.
Personnel Dosimetry /Exoosure Control comments should identify: (1) the timeliness and effectiveness of dosimetry distribution; (2) the effectiveness of protective measures; (3) the adequacy of established contamination control access points; (4) the adequacy of exposure planning measures afforded in plant activities; and (5) the adequacy of decontamination and posting techniques.
Controller's evaluation and documentation forms are found in Section 4.3. All documentation recorded must be provided to the Lead Controller after the exercise.
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R3v.1 O' VERMONT YANKEE NUCLEAR POWER STATION Page 4.3-1 EMERGENCY PREPAREDNESS EXERCISE 1999 i
M CONTROLLER EVALUATION CRITERIA As discussed in Sections 4.1 and 4.2, each Controller has been assigned specific areas of I response to observe and evaluate. This section has been developed to assist the Controllers in recording and documenting their findings and observations. The following attachments are included:
Attachment A provides a form to be used to maintain an event chronology log.
l Attachment B contains evaluation checklists for each emergency response facility. Each ,
Controller should complete the appropriate checklist. l
, Procedural Form WOPF 3505.02, ' Emergency Exercise / Drill Controller's Evaluation l
Form," is provided to summarize major findings and observations. EACH CONTROLLER MUST COMPLETE THIS FORM (WOPF 3505.02).
All three attachments should be completed and submitted to the Lead Facility Controller. .
Each Lead Facility Controller will submit the completed attachments to the Exercise l Coordinator for documentation of exercise observations and findings.
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Rev.1 Page 4.3-2 ATTACHMENT A
( Vermont Yankee Nuclear Power Statbn Err,ercericv ",eeccrse Exercisa/ Drill Controlier's Observations-Chrcrd-:-i+1 Loa TIME COMMENTOBSERVATION O
V Name: Area Evaluated:
O Date:
PAGE _OF _
Ray. I Page 4,3_3 ATTACHMENT B Vermont Yankee f Faaraency Rvereine/ Drill Evaluation & acklist INSTRUCTIONS The following checklists are provided to assist the Controller with their evaluation of the drill / exercise. The Controller should complete the checklist (s) for their assigned locations (s). To complete the evaluation checklist (s), use the rating scale listed below.
The cornpleted checklist should be used as a ' road map" to document your observations and comments on procedural form VYOPF 3505.02. Controllers should provide a clear written description of their findings and observations.
Ratina Symbol Ratina Rvnlanation for Commants Adequate A Adequate indicates that the demonstrated performance was consistent with plans and procedures. Comments may include 1
strong positive strengths or expected actions done well.
Inadequate I Inadequate indicates that the demonstrated performance could have precluded effective implementation of plans and procedures. This also may include an aspect of player's j response that warrants further evaluation for improvement l or corrective action. Conunents should provide a clear description of finding and observation noted. This may include recommendations for improvement, if possible.
I Not Observed or N No comments are required.
Not Applicable CHECKLISTS Section Engs I. Control Room (Simulator and Actual) 4.3-4 II. Technical Support Center 4.3-5 III. Operations Support Center 4.3-7 IV, Emergency Operations Facility / Recovery Center 4.3-9 V. Site and Off-Site Monitoring 4.3-11 VI. Security 4.3-12 VII. News Media Center 4.3-13 l
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R v.1 Pcg3 4.3 4 I.CONTitOL ROOM
- A. Accident Assessment /Emercency Classification Ratina comments h 1. Did the Control Room sLf f demonstrate the ability to recognize emergency initiating Yes/No conditions and classify the events in accordance with AP 31257 .
- 2. Did the Control Room staff demonstrate the Yes/No ability to coordinate the assessment of plant conditions and corrective actions with the Technical Support Center?
B. Notification and Com mmication i
- 1. Did the Control Room staff demonstrate the Yes/No ability to notify the plant staff of an emergency through the use of alarms and the public address system?
- 2. Did the Control Room staff demonstrate the Yes/No ability to notify federal and state authorities of emergency classifications in accordance with established procedures?
- 3. Was information flow within the Control Yes/No Room and to other appropriate emergency response facilities timely, complete, and accurate?
- 4. Was adequate record keeping of everts, Yes/No actions, and communications documented and j logged by the Control Room staff?
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- 5. Were adequate emergency communication Yes/No systems available in the Control Room to transmit data and information to other emergency response facilities?
- 6. Did the Control Room staff maintain an Yes/No effective open line of communication with the NRC over the ENS as requested?
C. Activation and Resoonse
- 1. Did the Control Room staff demonstrate the Yes/No ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
- 2. Was the person in charge in the Control Yes/No Room clearly identifiable and was good command and control taken at the Control Room?
- 3. Did the Control Room staff interface with Yes/No the NRC site response team in an effective manner?
_ ,. Controller Name:
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Rav. 1 Paga 4.3-5 II. TECHNICAL SUPPORT CENTER
,, - ~ A. Accident Assessment /Emeroency classification Ratina Comments s_, 1. Did the TSC staff demonstrate the ability Yes/No to support the Control Room in identifying the cause of the incident, mitigating the consequences of that incident, and placing the plant in a stable condition?
- 2. Did the TSC staff demonstrate the ability Yes/No to coordinate the assessment of plant conditions and corrective actions with the the Control Room?
- 3. Did the TSC staff demonstrate the ability Yes/No to initiate and coordinate corrective actions in an efficient and timely manner?
- 4. Did the TSC staff demonstrate the ability Yes/No to direct and coordinate the taking of appropriate chemistry samples to analyze plant conditions?
- 5. Did the TSC staff demonstrate the ability Yes/No to participate with the Control Room and EOF /RC in emergency classification and EAL discussion?
B. EDtification and communication f~%s 1. Was informacion flow within the TSC and to Yes/No other appropriate emergency response
- (-/) facilities timely, complete, and accurate?
- 2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the TSC staff?
- 3. Were adequate emergency communication Yes/No '
systems available in the TSC to transmit data and information to other emergency response facilities?
- 4. Was information concerning plant Yes/No conditions disseminated between the Control Room and TSC performed in a timely manner?
- 5. Were status boards utilized and maintained Yes/No to display pertinent accident information at the TSC?
- 6. Did the TSC staff provide technically Yes/No qualified individuala to man the open line i of communications over the ENS and HPN phone links with the NRC as requested?
n l Controller Name:,
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Rav. 1 Paga 4.3-6 II. TECHNICAL SUPPORT CENTER (cont'd)
C. Activation and Ramonnme Ratina Comments
- 2. Did the TSC staff demonstrate the ability Yes/No to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
- 3. Were initial and continuous accountability Yes/No chec.ks of TSC and CR personnel performed?
- 4. Did the TSC Coordinator establish and Yes/No coordinate access control into the Protected Area and Control Room?
- 5. Did the TSC Coordinator demonstrate the Yes/No ability to maintain command and control of TSC emergency response activities?
- 6. Did the TSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had developed?
- 7. Was the TSC organization and initiation of Yes/No activity efficient and well organized?
- 8. Did the TSC staff interface with the NRC Yes/No site response team in an effective manner?
e Controller Name:
I Rav. 1 Paga 4.3-7 III. OPERATIONS SUPPORT CENTER 73 A. Notification and Communication Ratina Comments
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(_,/ 1. Was information flow within the OSC and Yes/No to other appropriate emergency response facilities timely, complete, and accurate?
- 2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the OSC staff?
- 3. Were adequate emergency communication Yes/No systems available in the OSC to transmit data and information to other emergency response facilities?
- 4. Were job aids, such as forms or status boards Yes/No used to display team assignment; and tasks at the OSC?
B. Activation and Resoonse
- 2. Did the OSC staff demonstrate the ability Yes/No to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
- 3. Were initial and continuous accountability Yes/No checks of OSC personnel performed?
- A
- 4. Did the OSC Coordinator and OSC Yes/No l\ ') Coordinator's Assistant demonstrate the ability to maintain command and control of OSC emergency response activities?
- 5. Did the OSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had developed?
- 6. Was the OSC organization and initiation of Yes/No 1 activity efficient and well organized? l
- 7. Did the OSC staff demonstrate the Yes/No ability to provide adequate radiation protection controls for on-site ,
emergency response personnel? ]
- 8. Did the OSC staff demonstrate the Yes/No ability to perform radiological habitablity assessments of emergency response facilities and implement appropriate habitability controls?
Controller Name:
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R2v. 1 Paga 4.3-8 III. OPERATIONS SUPPORT CENTER (cont'd)
Ratina Comments
[ss 9. Did the OSC staff demonstrate the
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ability to monitor and track radiation Yes/No
- exposure of on-site emergency response j l personnel? '
i 10. Did the OSC staff demonstrate the Yes/No
! ability to obtain and analyze appropriate chemistry samples as j ' directed by the TSC?
- 11. Did the OSC staff demonstrate the _ Yes/No ability to initiate, brief, and dispatch on-site assistance teams?
- 12. Were on-site assistance teams able to Yes/No trouble-shoot and evaluate problems with plant equipment and systems?
- 13. Were there adequate administrative Yes/No controls and documentation taken to perform the necessary repairs of plant equipment and systems during an emergency situation?
- 14. Did the OSC staff interface with the NRC Yes/No l site response team in an effective manner?
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Rry. 1 Paga 4.3-9 IV. EMRRGENCY OPERATIONS FACILITY / RECOVERY CENTER
- A. Notification and Cnmmunication Ratina Comments
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- 1. Was information flow within the EOF /RC Yes/No and to other appropriate emergency response facilities timely, complete, and accurate?
- 2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the EOF /RC staff?
- 3. Were adequate emergency communication Yes/No systems available in the EOF /RC to transmit data and information to other emergency response facilities?
- 4. Was information concerning plant Yes/No conditions disseminated between the TSC and EOF /RC performed in a timely manner?
- 5. Were status boards utilized and maintained Yes/No to display pertinent accident information at the EOF /RC?
- 6. Did the EOF staff provide technically Yes/No qualified individuals to man the open line of communications over the ENS and HPN phone links with the NRC as requested?
B. Activation and Resoonse
'/ 2. Did the EOF /RC staff demonstrate the Yes/No ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
- 3. Did the Corporate Security Force Yes/No establish access control into the EOF /RC?
- 4. Did the EOF Coordinator demonstrate the Yes/No ability to maintain command and control of l EOF emergency response activities? 4
- 5. Did the EOF /RC keep other emergency Yes/No response facilities advised of the !
status of their activities and information which they had developed?
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- 6. Were the EOF /RC organization and.the Yes/No i initiation of activity efficient and ,
well organized?
- 7. Did the EOF staff demonstrate the ability Yes/No ,
to monitor habitability conditions and 1 establish the necessary monitoring controls at the EOF and News Media Center?
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Rav. 1 Paga 4.3-10 IV. EMERGKNCY OPERATIONS FACILITY / RECOVERY CENTER (cont'd)
Ratina Comments
/'~ 7..'Did the Site Recovery Manager demonstrate Yes/No the ability to maintain the consnand and control of the'overall emergency response effort and organization?
'8. Did the Site Recovery Manager Yes/No demonstrate the ability to de-escalate from the emergency phase into the recovery phase?
- 9. Were preliminary recovery plans .
Yes/No established and discussed between the Site Recovery Manager and appropriate personnel?
- 10. Did the EOF staff interface with the NRC Yes/No site response team in an effective manner?
C. Radioloalcal Amnessment
- 1. Was information concerning radiological Yes/No and meteorological data obtained by appropriate EOF personnel in a timely manner? j
- 2. Did the EOF staff demonstrate the ability Yes/No to perform off-Site dose assessment in accordance with OP 35137
- 3. Did the EOF staff demanetrate the ability Yes/No to effectively track and define the plume i utilizing the computerized dose assessment model (METPAC)?
- 4. Did the EOF staff demonstrate the ability Yes/No to coordinate off-site monitoring data with State authorities?
D. Protective Action Decision Makina
- 1. Did the Radiological Assistant's staff ______ Yes/No demonstrate the ability to perform timely essessment of off-site radiological
' conditions to support the formulation of L protective action recommendations?
- 2. Did the EOF Coordinator obtain and- Yes/No provide the necessary information to the Site Recovery Manager concerning protective action recommendations in accordance with OP 3511?
- 3. Did the site Recovery Manager Yes/No demonstrate the ability to make protective action recommendations to off-site authorities in accordance with F Procedure OP 3511?
Controller Name:
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V. SITE AND OFF-SITE MONITORING
, A. Activation and Resnonse Ratina Comments
- 1. Did site and off-site monitoring Yes/No teams demonstrate the ability to transmit information over the radio using proper units and terminology in accordance with Procedure OP 3510?
- 2. Were site and off-site monitoring Yes/No teams dispatched and deployed in a timely manner?
- 3. Were team members familiar with the use Yes/No of equipment, field monitoring procedures, and what was required of them?
- 4. Were off-site monitoring teams able to Yes/No determine and comminicate their location in the field using appropriate maps and sample points - (landmarks) ?
- 5. Were off-site monitoring teams briefed Yes/No on plant conditions and changes?
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4 Rav. 1 Paga 4.3-12 g g A. Activation and Remnonne Ratina Comments k 1. Did the Security staff demonstrate Yes/No the ability to perform accountability of personnel within the Protected Area in accordance with Procedure OP 3524?
- 2. Were access control points established Yes/No and maintained to control access at the site and the Protected Area?
- 3. Did the Security staff demonstrate the Yes/No ability to appropriately izqplement Emergency Plan Implementing Procedures and did they follow them?
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Rav. 1 Paga 4.3-13 VII. NEWS MEDIA CENTER A. Activation and Resnonse
) Ratina Comments l 1
-1. Did the News Media staff demonstrate the __. Yes/No ability to activate and staff the News Media Center?
- 2. Was information flow between the News Yes/No Media Center and the EOF /RC timely, cornplete, and accurate?
- 3. Were the News Media staff familiar with Yes/No their plans and procedures and do they follow them?
- 4. Did the News Media staff demonstrate the Yes/No ability to provide accurate and timely information concerning the emergency to the public and the news media?
- 5. Did the News Media staff demonstrate the Yes/No ability to coordinate news releases with the state's public information representatives?
- 6. Did the News Media staff demonstrate the Yes/No ability to provide briefi.gs for and to interface with public and news media?
- 7. Did the News Media Center Coordinator Yes/No discuss the habitability conditions of the News Media Center with appropriate l
State and Federal officials and assembled media staff?
- 8. Did the News Media staff interface with the Yes/No
! -NRC site response team in an effective manner?
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Rsv. 1 Patga 4.3-14 l EMERGENCY EXERCISE / DRILL CONTROLLER'S EVALUATION FORM g introller's Names Exercise / Drill Date: Anril 27, 1999 v Ex rcise/ Drill
Title:
1999 Vennent Yankee Rmaroency Preoaredness Exercise Controller's Location:
Observed: Player Function Ov0rall Performance and Observations: (Include the proper and ef fective use of procedures, cquipment and personnel)
Connents and Reconsnendations (Specific):
Potential Weaknesses:
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Emergency Plan Review: Date:
VYOPF 3505.02 (Sample)
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Page 5.1-1 g VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 jd INITIAL CONDITIONS (Information provided to the players at the start of the exercise).
- 1. The reactor is now at approximately 100% power. The reactor has been operating steady state for the last fifteen months with no recent shutdowns. The Rod Sequence is A-2 and the Rod Group is 209. The core is nearing the end of the current operating cycle.
- 2. The Operatk ns crew tumover log provides the following updated plant information:
- a. It has been determined that there is a minor leak in the drywell (about 3/4 gpm). A temperature profile of the drywell has not been useful in identifying the location of the leak. The long-range plans are to shut down over the weekend and make a p) drywell ently in order to identify the source.
- b. Drywell leakage is 2.48 gpm total.1.5 identified and 0.98 unidentified.
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- c. At 0600, ISO New England not;fied the plant that the National Weather Service issued a severe thunderstorm waming for the Southem Vermont area.
- 3. The initial plant and reactor system parameters associated with the start of the exercise l are shown on Table 5.1-1, " Initial Plant and Reactor System Values" and " Vermont Yankee Daily Plant Status Report."
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- 4. The following on-site meteorological conditions exist at 0815:
Wind Speed, mph (upper / lower) 8.0/6.0 Wind Direction, degrees (upper / lower) 271/266 Delta Temperature, *F (upper / lower) -0.8f-0.2 Ambient Temperature,'F 44.0 Precipnation, inches per % hour 0.50
- 5. Regional Meteorological Forecast information:
l l A high-pressure system is currently centered over Montreal, Canada. The combination of a warm and relatively hum;d air mass and solar heating may result in strong !
l thunderstorms. At 0600, the National Weather Service in Albany, NY issued a severe l
l thunderstorm waming for Windham County Vermont, Cheshire County New Hampshire, i 1
and Franklin County Massachusetts effective until 1200 noon. Expect heavy niinfall,
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strong gusty winds and lightning. At 0815, National Weather Service Doppler radar !
indicated a tomado developing in the area. A tomado waming has been issued for s Windham County Vermont and Cheshire County New Hampshire.
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Rev.1 Page 5.1-3 Table 5.1-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 159 inches Reactor Pressure 1008 psig Reactor Coolant Temperature 527 *F Reactor Power- APRM (average) 99.8 %
Core Plate D/P 18 psid Total Core Flow 47 x 10'lbm/hr Main Steam Line Flow-Total 6.4 x 10' Ibm /hr Main Steam Line Radiation (average) 150 mR/hr Condenser Hotwell Level 56 %
Condenser Vacuum 2.5 in. Hg(Abs)
Condensate Storage Tank Level 50 %
p Recirc Drive Flow 29.6 Kgpm/ loop
\ Feedwater Flow 6.3 x 10'lbm/hr Reactor Building D/P -1.44 in H2O Drywell Pressure 1.9 psig Drywell Temperature 140 *F Torus Water Level 11.05 ft Torus Temperature 78*F Drywell/ Torus 02 Concentration 1.44 %
High Range Containment Monitors 3.0 R/hr Containment Gas / Particulate 450/975 cpm Reactor Building Vent Monitors Gas /Part 150/1500 cpm Reactor Building Vent Exhaust N/S 2.0/2.0 mR/hr Steam Jet Air Ejector (ARM) 75 mR/hr SJAE Discharge Rate 690 uCl/sec Stack Gas 1/2 150/200 cpm High Range Noble Gas Monitor <0.1 mR/hr O
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t VERMONT YANKEE DAILY OPERATIONS REPORT, APRIL 27, 1999 PLANT STATUS: 100% POWER 1 GEN. GROSS OUTPUT 13142 MNE I OFFGAS 690 FCi/sec (MEASURED)
RE VESSEL COND. 0.092 unho/csa DRYNELL LEAKAGE: 2.48 GPM PLANT OPERATIONAL
SUMMARY
& SIGNIFICANT EVENTS:
- 0600 NOTIFIED BY ISO NEW ENGLAND OF SEVERE WEATHER PREDICTED FOR THE
! SOUTHERN VERMONT AREA THIS MORNING l ' CONTINUE FULL POWER OPERATIONS l samassamassammassmuzzassassmammazzassumassassammassammassmassmasamazassmammusa SIGNIFICA3rr MEW WORs DESCRIPTION DEPT / PRIORITY
- 36246 INVESTIGATE AIR INLEAKAGE ON *B" l COND. PUMP MAINT 2 l smasammasmsamusassanzassassamazassmazzamaramanazzamazassmammasammusmazzassumma l
TECM SPEC /LCO EQUIPMENT OUT OF SERVICE:
SYSTEM /COMPOMENT ,
DATE TIME 17 TN"LE TIME EAST / WEST SWGR CO2 SYS 3.13.D.2 11/19/98 0858 14 DAYS
STATUS /COtetBarfs OM MAJOR WORK IM PROGRESS / MAJOR WOREAROUNDS j
- DAILY DRYWELL TEMPERATURE PROFILES BEING TAKEN BY OPS. l
- STOP LIST ITEMS FOR MINI SEUTDOWN BEING COMPILED BY OPG AMD MAINTEMANCE I TODAY: l PMT OF "B" IA DRYER l
- B" CONDENSATE PUMP INLEAKAGE INVESTIGATION AMD REPAIR.
SLC PUMP QUARTERLY SURVEILLANCE
- MEXT WEEK ROUSE REATING BOILER ANNUAL INSPECTIONS (TEC REP)
CASK ROOM WORK: SETUP NEN LINERS FOR RAD WASTE PROCESSING QUARTERLY PRIMARY CONTAIbEEENT VALVE SURVIILLANCES
........as....s====m=======amas==========================================
l l LONG TERM PROBLEMS SOLVED:
l NOME l masammassammassassassumsmassmasazamassamassassmassessmassmassmassaammassamasas i PREPARED BY NGL "THIS IS A DRILL - FOR DRILL PURPOSES ONLY" s
Rev.1 Page 5.21 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 L2 EXERCISE SEQUENCE OF EVENTS The exercise begins at 0815 with the reactor (simulator) running at 100% power. The reactor has been in a steady state for the last fifteen months with no recent shutdowns. The Rod Sequence is A-2 and the Rod Group is 209. The core is nearing the end of the current operating cycle. The Circulating Water System is operating in Open Cycle. A minor leak (about 3/4 gpm) has been determined in the drywell. A temperature profile of the drywell has not been useful in identifying the location of the leak. The long-range plans are to shut down over the weekend and make a drywell entry in order to identify the source. At this time, the total drywell leakage is 2.48 gpm, of which 1.5 is identified and 0.98 is unidentified (Refer to Mini-scenario 7.2.1). At 0600, ISO New England notifled the night shift of receipt of a severe thunderstorm warning in the Southern Vermont area.
Command Cards SCR-C-1 (Prior to 0815): Guidelines provided to Simulator Control Room players on the use of GalTronics and the plant evacuation alarm during the drill SCR-C-2 (0815 or when needed): Instructions provided to Simulator Control Room players that early in-plant actions may be controlled and performed by the simulator Controllers.
Message Cards INITIAL-M-1 (start of drill or facill :etivation): Exercise scenario initial conditions provided to the Simulator Control Room players and to appropriate Emergency Facility Coordinators upon activation. Security (Prior to 0815): A list of Exercise Controllers and nonpartichants, who are exempt from accountabilty checks, provided to Securty Shift Supervisor.
At approximately 0830, Security informs the Simulator Control Room that a tornado funnel cloud has touched down on the west cooling tower, causing severe damage to the west cooling tower fans.
Security further reports that the funnel cloud quickly dissipated within one minute. In addition, Simulator Control Room indications will show that there is no power indication to the number one west cooling tower fan. The number one fan has a zero ground due to the structural damage caused by the tornado. At this time, the Control Room crew should implement OP 3127, " Natural Phenomena" to conduct site walk-downs to determine the extent of the damage.
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Message Cards - SEC-M-1 (0830 or when needed): Securky ShNt Supervisor reports O the Control Room that a tornado funnel cloud ht into the west cooling tower, causing severe damage to the west cooling tower fans and the funnelcloud quickly disspated wthin one minute.
An ALERT should be declared (approximately 0840) based on AP 3125 " Natural Phenomenon" (Any tornado striking a safety class structure as evidenced by physical damage). Notifications should be made to appropriate plant personnel and off-site agencies.
Since the initial message to the Control Room indicated that the west cooling tower has been damaged, additional verification may or may not take place before an Alert is declared. However, information to the players will indicate that the west cooling tower is severely damaged on additional walk-down inspections (Refer to Mini-scenario 7.2.2).
Command Cards SCR-C-3 (0840 or when needed): Instructions provided to Simulator Control Room communicator about the operabilNy of the FTS 2000 ENS telephone.
SCR-C-4 (0900 or when needed): Instructions to controlthe declaration of the Alert.
! A Message Cards SEC-M-2 (0840 or when needed): Guidelines provided to Securty ShNt Supervisor on VY/
DE&S pager actkation and Wider Station (Vernon Hydro) notrication. TSC-M-1 (0840 or when needed): Guidelines provided to TSC Coordinator on assignment cf TSC Comn unicators to Control Room. l l
Following the ALERT declaration, the Technical Support Center (TSC), Operations Support Center (OSC), and Emergency Operations Facility / Recovery Center (EOF /RC) should activate and staff.
The News Media Center has the option to activate at the Alert class!fication. State and local l Emergency Operations Centers (EOCs) should also activate and staff. The Control Room ataff l
continues to coordinate site walk-downs to assess the damage from the tornado.
By 0915, it is expected that several teams or plant personnel will be dispatched to conduct site walk- l downs ard inspections in accordance with OP 3127 NATURAL PHENOMENA Appendix "C" gen e el Ge r eng ne omb st on intake and exha s and oom v n llation Upon walk-down of the EDG Inspection, the inspection will reveal that the "B" EDG tornado relief damper has tripped, which will require resetting (Refer to Min scenario 7.2.3 and Mini-scenario b 7.2.4).
Rev.1 Page 5.2-3 0
By 1000, the Engineering Support Center (ESC) should be providing technical and engineering support to Vermont Yankee staff. The ESC meteorologist should be providing a weather forecast for the VY site. At this time, updated weather forecast information is avaliable from the National Weather Service (NWS) Indicating that the tornado and severe thunderstorm warnings have been terminated (Refer to message card NWS-M-1.)
Message Cards EOF-M 1 (1000 or as reaumatadh information to be provided to EOF Rad Assessment staff on the National Weather Service forecast or plant she meteorological conditions. ESC-M-1 (1000 or as reauestedk Information provided to ESC Meteorologist on weather forecast for the Vermont Yankee ske. NWS.M-1 (1000k Updated NationalWeather Service information is provided to players.
At 1035, the plant experiences a stator cooling runback causing a significant power spike to occur.
When the Average Power Range Monitor (APRM) scram signal is received, the reactor scrams and control rods fall to insert causing an Anticipated Transient Without Scram (ATWS) condition.
Reactor power will remain above 2%. At this time, fuel clad failure begins due to the power spike associated with the stator cooling runback and ATWS condition.
A SITE AREA EMERGENCY should be declared (approximately 1045) based on AP 3125, " Loss of Systems or Equipment"(Automatic and manual SCRAM signals are present OR Manual SCRAM
~ signalis present AND reactor power remains above 2%).
Command Cards EOF-C-1 (1055 ra when neededh Instructions to control the declaration of the SRe Area Emergency.
The shift will follow the appropriate procedures to mitigate the ATWS condition. This should include altemative methods to insert control rods and to shut down the reactor. Prior to manually inserting control rods, 0; erations should direct the Reactor Building Auxiliary Operator (AO) to manually close the Control Rod Drive (CRD) 56 valve in the Reactor Building per EOP-2, Appendix G (Refer to Mini-scenario 7.2.5).
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\"J By 1115, when the reactor is shutdown and no boron has been injected, a plant cooldown should commence, not to exceed 100 degree F per hour. In addition, the primary containment radiation I levels have increased and continue to trend upward due to the fuel clad damage. Off-site dose assessment activities may be initiated to determine potential off-site dose projections and off-site monitoring teams may be dispatched to preselected monitoring points based on meteorological conditions.
In-plant samples of plant systems (reactor coolant and primary containment) and radiological surveys also may be initiated to assess plant conditions and support accident assessment activities (Refer to Mini-scenario 7.2.8).
At 1220, the Simulator Operator will insert a casualty that simulates a steam line break occurring on the High Pressure Coolant injection (HPCI) system. The break is located outside the drywell in the HPCI room at about the 213' elevation of the Reactor Building.
Area Radiation Monitors (ARMS) in the Reactor Building start to increase significantly due to the steam leak and failure of the HPCI 15 and HPCI 16 isolation valves to isolate. Efforts by the Reactor Operator to isolate the HPCI leakage will be unsuccessful.
I By 1230, the Plant Vent Stack (PVS) is indicating a release of radioactivity to the environment.
Dose assessment activities should be initiated to track plume direction and project off-site doses.
A GENERAL EMERGENCY should be declared (approximately 1235) based on AP 3125, " Fuel Damage"(Loss of 2 of 3 fission product barriers with potentialloss of the third). Notifications should be made to appropriate plant personnel and off-site agencies on the escalation to the General Emergency. The Site Recovery Manager should formulate and provide protective action recommendations to State authorities based on plant and off-site radiological conditions.
Command Cards EOF-C 2 (1245 or when needed): Instructions to control the declaration of the General l Emergency.
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Rev.1 Page 5.2-5 By 1305, teams should be requested to be dispatched from the Operations Support Center (OSC) to investigate the problem associated with the HPCI 16 valve and/or HPCI 15 valve to isolate the HPCI system leak. (Refer to Mini-scenario 7.2.6 and Mini-scenario 7.2.7,respectively. The repair activities for HPCI 15 valve may be controlled at this time - message card TSC-C-1.)
Command Cards TSCC-1 (1305 or when needed): Instructions to control On-ste Assistance Team to investigate the problem wth the HPCI inboard isolation valve (HPCI 15).
By 1320, repairs to HPCI 15 are completed, allowing closure of the valve. Upon valve closure, the source term of the release to the environment is isolated and the PVS high range monitor readings will start to decrease. Off-site activities will continue to track the release. The release of radioactivity to the environment will continue to decrease over time based on the volume exchange rate of the Reactor Building through the Standby Gas Treatment System. Plant conditions are stabilizing.
,O At approximately 1325, ARMS located in the Reactor Buildings and PVS monitors indicate a
' Q decreasing trend.
By 1335, plant staff should complete activities to stabilize plant conditions. Exercise objectives should have been demonstrated.
At 1345, the exercise may be terminated.
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R v. 0 P ge 5.3 - 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 EXERCISE SCENARIO TIME LINE CLOCK SCENARIO TIME TIME DESCRIPTION 0815 0:00 <- Initial conditions established in the Simulator Control Room. Initial conditions also provided to plant management at the moming meeting.
0830 0:15 <- Security informs the Simulator Control Room that a funnel cloud has touched down on the west cooling tower, causing damage to the west cooling tower fans. Security further reports that the funnel cloud has dissipated.
0840 0:25 <- ALERT (A-5-d, AP 3125, NATURAL PHENOMENON, &ny tomado striking a safety class structure as evidenced by physical damage) 0915 1:00 <- OP 3127, " Natural Phenomena" will be implemented. This will include site walk-downs to determine the extent of the damage, using Appendix C of OP 3127. During the walk-down, investigation will reveal the "B" EDG tomado relief damper has tripped, which will require resetting.
0935 1:20 <- Plant personnel will be dispatched to reset the "B" EDG tomado damper.
2:00 <- The "B" EDG tomado damper is reset l
[_1015
)
% d35 2:20 <- Stator cooling runback occurs. During the runback, when the APRM scram signal is received, the reactor will not scram. Fuel clad failure begins due to the power spike associated with the runback and ATWS condition.
l 1040 2:25 <-- Main steam line radiation levels will start rising, due to fuel cladding failure. j 1045 2:30 <- SITE AREA EMERGENCY (S-7-c, AP 3125 - LOSS OF SYSTEMS OR EQUIPMENT) - Automatic and manual SCRAM signals are present OR Manual SCRAM signal is present AND reactor power remains above 2%)
1050 2:35 <--- Operations initiate actions to mitigate ATWS. Primary containment radiation levels start to increase and continue to trend upward due to the fuel clad damage.
1115 3:00 <-- (Time approximate) When the reactor is shutdown and no boron has been injected, a plant coaldown will commence, not to exceed 100 deg. F per hour 1220 4:05 <- A steam line break on the HPCI system occurs. The break is located outside the drywellin the HPCI room on the 213' elevation of the Reactor Building. Coincident with the steam line break, HPCI 15 and HPCI 16 isolation valves fail to isolate.
1230 4:15 <- ARMS in the Reactor Building have increased significantly. Plant Vent Stack indicates a release of radioactivity to the environment.
4:20 <- GENERAL EMERGENCY (G-2-a, AP 3125 - FUEL DAMAGE)- Loss of 2 of 3 fission V(~7i35 product barriers with the potentialloss of the third.
R:v. O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 EXERCISE SCENARIO TIME LINE (continued)
CLOCK SCENARIO TIME TIME DESCRIPTION 1250 4:35 <- Off-site protective action recommendations issued to State authorities.
1305 4:50 <- OSC Assistance teams should be assembled and dispatched to investigate the problem associated with the HPCI-15 and HPCI 16 valves to isolate the HPCI system j leak. '
1320 5:05 <- Operations successfully closes the HPCI inboard isolation valve (HPCI-15). Leakage into the Reactor Building is isolated.
1325 5:10 <-- Plant Vent Stack monitor readings indicate a decreasing trend. Source of release to the environment has been isolated.
1335 5:20 (- Plant staff complete activities to stabilize plant conditions.
1345 5:30 <- EXERCISE MAY BE TERMINATED v
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VERMONT YANKEE NUCLEAR POWER STATION ,
EMERGENCY PREPAREDNESS EXERCISE 1 1999 i
6.1 COMMAND CARDS
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R v.1 Page 6.1-1 VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY PREPAREDNESS EXERCISE 1999 SCENARIO COMMAND CARD 1
FROM: Simulatnr CR I and Controller COMMAND NO.: SCR-C-1 TO: Shift Suoervisor CLOCK TIME: Prior to 0815 i
LOCATION: Simulatnr Control Room SCENARIO TIME: Prior to 00:00 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
l Communications systems that are available in the Control Room have been duplicated in the Simulator Control Room (SCR) EXCEPT for GAITRONICS/ PLANT EVACUATION ALARM.
Please use the GAITRONICS/ PLANT EVACUATION ALARM in the SCR to complete the required PA announcements. An exercise controller will then direct a member of the shift operations crew at the plant to repeat the announcements from the Main Control Room.
An interface device has been installed to connect the Simulator Control Room in Brattleboro with the plant GAITRONICS system. It will allow a person at the plant to talk directly to the simulator over l the plant GA'TRONICS. The Controller in the plant Main Control Room will monitor and manually l actuate th's interfece, causing a slight delay between initial communications. CHANNEL 3 is the l designated the line to be used for communications between the Simulator Control Room and the l Plant. CHANNEL 1 and CHANNEL 2 are the designated lines for all other plant exercise related I
communications and messages.
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Rev.1 Page 6.1-2 VERMONT YANKEE NUCLEAR POWER STATION n EMERGENCY PREPAREDNESS EXERCISE L 1 1999 u
l SCENARIO COMMAND CARD FROM: Simulator CR Lead Controller COMMAND NO.: SCR-C-2 TO: Shift Sunen/Isor CLOCK TIME: 0815 or when needed LOCATION: Simulator Control Room SCENARIO TIME: 00:00 THIS IS A DRILL DO NOT Initiate any actions affecting normal plant operations.
Early in-station actions normally performed by Control Room support personnel may be controlled and performed by the simulator controllers until after the operating shift personnel are augmented by the Emergency Response Organization.
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Page 6.1-3 VERMONT YANKEE NUCLEAR POWER STATION f EMERGENCY PREPAREDNESS EXERCISE 1999 l(
SCENARIO COMMAND CARD '
FROM: Simulator CR Lead Controller COMMAND NO.: SCR-C-3 TO: Simulator Communicator CLOCK TIME: 0840 or when needed LOCATION: Simulator Control Room SCENARIO TIME: 0:25
................................................................................................................... l l THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
I
! For exercise purposes, when you lift the receiver on the FTS 2000 Emergency Notification System (ENS) telephone there IS NO DIAL TONE.
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l Controller Note- l l When Communicator contacts the NRC Operations Center via the commercial telephone, ensure l that the Communicator Informs the NRC that this is a simulated drill-related failure and there is no !
l real problem with the FTS 2000 System.
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R:v.1 Page 6.1-4 VERMONT YANKEE NUCLEAR POWER STATION
- EMERGENCY PREPAREDNESS EXERCISE l 1999 scENABlo_coMMatacAan FROM: Simulator CR Lead Controller COMMAND NO.: SCR-C-4 TO: Shift Suoervisor CLOCK TIME: 0900 LOCATION: Simulator Control Room SCENARIO TIME: 00:45 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
DECLARE AN ALERT BASED ON AP 3125," NATURAL PHENOMENON - Any tornado striking a safety class structure as evidenced by physical damage."
THIS IS A DRILL m
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-m EMERGENCY PREPAREDNESS EXERCISE 1999 f
l SCENARIO COMMAND CARD t
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l FROM: EOF Lead Controller COMMAND NO.: EOF-C-1 TO: Site Recoverv Manaaer CLOCK TIME: 1055 LOCATION: EOF SCENARIO TIME: 02:40 1
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. i 1
1
................................................................................................................... i DECLARE A SITE AREA EMERGENCY BASED UPON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT-Automatic and manual scram signals present OR Manual scram signal present AND reactor power remains above 2%."
O THIS IS A DRILL t pi ...................................................................................................................
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Rsv.1 Page 6.1-6 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE is 1999 SCENARIO COMMAND CARD FROM: EOF Lead Controller COMMAND NO.: EOF-C-2 TO: Site Recoverv Manaaer CLOCK TIME: 1245 LOCATION: EOF SCENARIO TIME: 04:30
.................................... m ..... m ...................... m ...........................................
THIS IS A DRILL DO NOT Initiate any actions affecting normal plant operations.
.... m ................................................ m .........................................................
DECLARE A GENERAL EMERGENCY BASED ON AP 3125, " FUEL DAMAGE - Loss of 2 of 3 fission product barriers with the potentla! loss of the third."
.......... m m m .... m ....................... m m .............. m ...........................................
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999
&?.ENARIO COMMAND CARD i
, FROM: TSC Lead Controller COMMAND NO.: TSC-C-1
! 10: TSC Coordinator CLOCK TIME: 1305 LOCATION: TSC SCENARIO TIME: 04 50 THIS IS A DRILL DO NOT Initiate any actions affecting normal plant operations.
i Dispatch an OSC Assistance Team to investigate the malfunction of the primary containment HPCI inboard isolation valve (HPCI-15) at the Motor Control Center (MCC) 9-D on the Reactor Building Elevation 252'.
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R:v.1 Page 6.21 VERMONT YANKEE NUCLEAR POWER STATION f)U EMERGENCY PREPAREDNESS EXERCISE 1999 SCENARIO MESSAGE CARD l
FROM: Facility Lead Controller MESSAGE NO.: INITIAL-M-1 TO: Facility Coordinator CLOCK TIME: Start of Exercise or l LOCATION: Various ERFs SCENARIO TIME: Facility Activation l 4
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THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
For initial conditions, provide Section 5.1 of the exercise manual to players.
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CONTROLLER NOTE:
Please make sure the initial conditions are given to the following individuals: Shift Supervisor, Duty Call l Officer, Plant Manager, Plant Superintendents, Operations Manager, Assistant Operations Manager, l Operations Planning Coordinator, and Director of Operations.
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EMERGENCY PREPAREDNESS EXERCISE 1999 SCENARIO MESSAGE CARD FROM: Security Lead Controller MESSAGE NO.: SEC-M-1 TO: Security Shift Suoervisor CLOCK TIME: 0830 LOCATION: Gatehouse 2 SCENARIO TIME: 00:15
......................................................e.........ee................... ...............*................e THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
! instruct the Security Shift Supervisor to immediately inform the Simulator Control Room Shift Supervisor l of the following information:
l A security guard observed a tomado funnel cloud hit into the west cooling tower, causing severe damage l to the west cooling tower fans. The tomado funnel cloud also passed near the penthouse above the I l( ' Emergency Diesel Generator Room, and then quickly dissipated from the plant site within one minute. It l( appears that some small trees were also uprooted and debris scatter around the plant site near the west l cooling tower.
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THIS IS A DRILL w
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l FROM: Sacrrity I end Controller MESSAGE NO.: SEC-M-2 l TO: Security Shift Suoervisor CLOCK TIME: 0840 LOCATION: Gatehouse 2 SCENARIO TIME: 0015 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
CONTROLLER NOTES::
l 1. FOR EXERCISE PURPOSES, ensure when the Security Shift Supervisor implements Appendix ll of the core procedures (OP 3500,3501,3502,3503) that Wilder Station (Vemon Hydro) is notified of the
- appropriate emergency classification, and all Exercise related notifications are preceded by and end l
with "THIS IS A DRILL."
- 2. FOR EXERCISE PURPOSES, direct the Security Shift Supervisor when using Procedure OP 3531,
" Emergency Call-in Method" to implement the following instructions:
- a. DO NOT ACTIVATE THE COnmlGUNITY ALERTNETWORK(CAN) SYSTEM. This system will not be used for this exercise.
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- b. ACTlVATE THE VERMONT YANKEE PAGER SYSTEM. Use the pager code "000" as the appropriate emergency classification code for Pager activation during this drill. THIS IS THE PAGER ;
CODE FOR A DRILL
- c. CONTACT DE&S AND ACTIVATE DE&S PERSONNEL PAGER SYSTEM Use pagor code as DEFINED IN THE PROCEDURE as the appropriate emergency classification code for Pnger activation during this exercise.
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- d. Make sure that all drill-related notifications are preceded and ended with "THIS IS A DRILL."
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1999 l
SCENARIO MESSAGE CARD
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l FROM: TSC Lead Controller MESSAGE NO.: TSC-M-1 TO: TSC Coordinator CLOCK TIME: 08:40 or uoon assianment of Communicators i
l LOCATION: IS.Q SCENARIO TIME: 00.25 THIS IS A DRILL DO NOT Initiate any actions affecting normal plant operations.
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l After simulating assignment of your TSC Communicators to the Control Room, the prestaged TSC l Communicators at the Simulator Control Room can now be used.
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1999 1
SCENARIO MESSAGE CARD l FROM: Rad Assessrnent Controller MESSAGE NO.: EOF-M-1 TO: Radioloalcal Assistant CLOCK TIME: 1000 or as reauested LOCATION: EOF / Dose Assessment Area SCENARIO TIME: 01:45
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THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
CONTROLLER NOTE:
When EOF /RC personnel request weather information, provide the General Area NWS Forecasts
~. Information and Plant / EOF Weather observations (as appropriate) contained in Section 10.2 (Page 10.2-1)
! of the exercise manual.
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EMERGENCY PREPAREDNESS EXERCISE 1999 j
SCENARIO MESSAGE CARD FROM: ESC Lead Controller MESSAGE NO.: ESC-M-1 TO: ESC Meteorologist CLOCK TIME: 1000 or as reauested LOCATION: ESQ SCENARIO TIME: 01:45 i
THIS IS A DRILL '
DO NOT initiate any actions affecting normal plant operations.
CONTROLLER NOTE:
When the ESC Meteorologist request information about weather forecast or site specific meteorological information, provide the meteorological information contained in Section 10.2 of the exercise manual as follows:
- 1. Provide the general area NWS Forecast information contained in Section 10.2 (page 10.2-1) on ESC activation or when requested.
- 2. Provide Vermont Yankee Site Forecast information contained in Section 10.2 (page 10.2-2 through 10.2-4) at the appropriate time stated.
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I Rsv.1 Page 6.2 7 VERMONT YANKEE NUCLEAR POWER STATION (C)v EMERGENCY PREPAREDNESS EXERCISE 1999 SCENARIO MESSAGE CARD FROM: Facility Lead Controller MESSAGE NO.: NWS-M-1 TO: Facilitv Coordinator CLOCK TIME: 1000 LOCATION: Various ERFs SCENARIO TIME: 01:45 (VY, State and Local)
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
The National Weather Service in Albany NY canceled the tornado and severe thunderstorm wamings for Windham County Vermont, Cheshire County New Hampshire, and Franklin County Massachusetts as of 10:00 A.M.
The National Weather Service radar indicated the storm has dissipated and cleared the area. The weather forecast for the remainder of the day is as follows:
Mostly sunny. Temperatures rising to the mid to upper 60's. Easterly winds from 4 to 8 mph.
CONTROLLER NOTE:
L Make sure this information is provided to the key Facility Managers or Coordinators located at VY ERFs and l State and local town Emergency Operations Centers (EOCs).
i THIS IS A DRILL T; .......................................................................................................................
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o-I l Rev.O Page 7.1-1 Vermont Yankee Nuclear Power Station Emergency Preparedness Exerciso 1999 Zd. EVENTS
SUMMARY
l The following supplementary material provides information for Controllers having in-plant control assignments to ensure that scenario events are properly controlled and defined. The information provided in this section assumes that the " players', who are dispatched to perform repair, rescue, or other activities, will take certain actions in response to the scenario. The Controller must be cognizant of the actions of player assignments and provide information regarding the results of the players' actions, as appropriate. The information provided in this section does not preclude the possibility that the Controller will be required to provide additional information to the players.
Approximate -
. Mini-Scenario Time Event Location 7.2.1 N/A Small Leak in the Drywell Drywell 7.2.2 0840 Tomado Striking the West Cooling Tower West Cooling Tower l
l 7.2.3 0915 "B" EDG Relief Damper "B" EDG Room Trip l
i 7.2.4 0915 Site Walk-Downs Various Locations 7.2.5 1035 Manualinsertion of Control Room &
Control Rods and Reactor Building CRD-56 Operation Elevation 252' 7.2.6 1220 HPCI 16 Motor Cable Vault Operator Short 7.2.7 1220 HPCI 15 Failure Reactor Building to Close Elevation 252' 7.2.8 N/A Chemistry Samples of Various Locations Plant Systems and in-Plant Radiological Surveys
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7.2 EVENT MINI-SCENARIOS O
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' Rev.0 Page 7.2-1 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 I&1 Mini-scenario - Small Leak in the Drvwell
- 1. General Descriotion it has been identified that there is a small leak in the drywell. Without a drywell entry, the location of the leak cannot be determined.
- 11. Description of Plaver Responses / Observations / Corrective Actions At this point no further player actions should need to be performed in order to determine the source of the leak. Continued containment profiles may be taken without any noticeable change.
Continued drywell leakage evaluations may be performed.
l CONTROLLER NOTES:
Ensure no major equipment, (i.e. HPCI, RCIC) that may affect the scenario is prematurely isolated.
l Ill. Event Closeout The event terminates at the end of the exercise.
IV. Messaoes i All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players, i
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7,2,2 Mini-scenario - Tomado mirikinn the West Coolina Towgr l
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- 1. General Descriotion j i
A tomado touched down near the west cooling tower uprooting some small trees along with causing structural damage to west cooling tower fans 1,2 and 3. There is no indication on the CRP 9-6 that there is power to number 1 fan. The number 1 fan has a zero ground due to the structural damage.
ll. Descriotion of Plaver Resoonses/ Observations / Corrective Actions l
It is expected the control room will refer to OP 3127 NATURAL PHENOMENA Appendix "C" l HURRICANE / TORNADO WALKDOWN CHECK SHEET. This may involve several teams or persons dispatched to conduct site walk-downs. Since this event has already been reported to the control room that the west cooling tower has been damaged, additional verification may or may not take place before an Alert is declared. If players are dispatched to the cooling towers to assess damage the results of the observation will be that the structural damage is such the L
stairs leading to the top have been tom apart and pieces of the tower are laying on the ground.
! CONTROLLER NOTES:
1 Information to the players should be clear enough to get the message across that the west cooling tower is severely damaged and will need extensive repair.
l l Ill. Event Closeout When assessment has been reported.
IV. Messaaes All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players.
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Rev.O O VERMONT YANKEE NUCLEAR POWER STATION Page 7.2-3 EMERGENCY PREPAREDNESS EXERCISE 1999
! 7.2.3 Mini-scenario - B EDG Rollef Damper Trio
- 1. General Descriution After the tomado passed over the west cooling tower, it touched down again near the penthouse above the "B" Emergency Diesel Generator (EDG) Room. This caused the relief damper to trip.
II. Descriotion of Plaver Resoonses/ Observations / Corrective Actions I l l I
l Part of the procedure OP 3127 Appendix C is to walk-down the EDG engine combustion intake, l exhaust, and room ventilation. It is expected that operators will be dispatched by the OSC to l- perform this function. During the walk-down, it will be determined that the "B" EDG relief damper l has tripped. This should be reported to the OSC where maintenance will be directed to reset the
! damper. The assigned maintenance individual should reset the damper IAW OP 3127 and report back to the OSC.
O V CONTROLLER NOTES: j
- 2. The results can be reported with out first notifying the OSC Lead Controller.
Ill. Event Closeoul When the damper has been reset and reported to the OSC.
I IV. Messages All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players.
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E Rev.O Page 7.2-4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 L3d M,ini-scenario - SITE WALK-DOWNS I
- 1. General Descriotion After the tomado passed over the west cooling tower, it touched down again near the penthouse above the "B" Emergency Diesel Generator Room. No other structural damage is observed. There is some debris located around the plant.
II. Descriotion of Plaver Responses / Observations / Corrective Actions Part of the procedure OP 3127 Appendix C is to walk-down other areas of the site. Additional OSC teams should be assigned to this task. The areas to be covered should follow OP 3127.
i CONTROLLER NOTES:
Direction to the players should be to report what they see. Depending on the availability of the controllers this direction may be given before the player leaves the OSC area or if controllers are avcilable to go with the player then direction may be given during the walk-down. OSC may decide to send numerous teams out to conduct a more comprehensive walk-down than specified in OP 3127, which will require controller judgement on how to provide input.
Ill. Event Closeout When the results of the walk-downs have been reported to the OSC.
IV. Messages All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players.
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i Rev.O O VERMONT YANKEE NUCLEAR POWER STATION Page 7.2-5 EMERGENCY PREPAREDNESS EXERCISE 1999 7,2 5 Mini-scenario -RANUAL INSERTION OF CONTROL RODS AND CRD-59 OPERATION L jeneral Dessiotion When the plant experiences a stator cooling runback and reactor scram, rods will not insert during the subsequent scram. EOP-2 directs the operator to drive rods in by Appendix G. In order to do this with a scram signal present; drive water must be diverted to the directional control valves to insert control rods. This is accomplished by shutting charging water header isolation valve CRD-56.
II. Descriotion of Plaver Responses / Observations / Corrective Actions i
l When the decision to manually drive control rods into the core is made, Operations will request ,
the Reactor Building Auxiliary Operator to shut CRD-56 per OE 3107, Appendix G. Upon request 1 of the Control Room, the Reactor Building Auxiliary Operator (AO) will proceed to the Reactor Building Elevation 252' to shut CRD-56. When the AO reaches valve lecation, he will simulate closing CRD-56 and told that the valve is successfully shut. The AO should then inform the O Control Room that CRD-56 shuts.
CONTROLLER NOTES:
- 1. All actions associated with manually closing of CRD-56 will be simulated. No manipulation of equipment or valves should be done.
- 2. When the AO manually simulates shutting CRD-56, the Controller should first report the completion of task to OSC Lead Controller. The OSC Lead Controller will report the closure to the Simulator Controller. At this time, the Controller will allow the AO to report the closure to the Control Room. This is to facilitate the timing for operators to manually drive control rods into the core.
111. Event Closeout This event !s terminated when the AO reports to the Simulator Control Room that CRD-56 is shut.
IV. Messages All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players. This may include the following expected activities:
Auxiliary Operator activity when told to shut CRD-56.
Results of Auxiliary Operator shutting CRD-56.
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 L3ft Mini-scenario - HPCI -16 Motor Operator Short
- 1. General Descriotion When the automatic isolation signal is sent to HPCI system, the primary containment outboard l isolation HPCI-16 remains open due to the motor operator for the valve shorted out. Valve positiori indication on the 9-3 panel will go out indicating the breaker has tripped.
At approximately 1220, a major line break occurs on the HPCI system. The break is located in the HPCI room about 213' elevation of the Reactor Building, initially, Operators' efforts to close outboard HPCI-16 from the Simulator Control Board will not be successful.
- 11. Descriotion of Plaver Resoonses/ Observations / Corrective Actions Since Simulator Control Board indicates the HPCI outboard valve (HPCI-16) failed to close, an OSC team should be assembled, briefed, and dispatched to investigate the HPCI-16 breaker
, located on DC-i in the cable vault. Upon furthe; investigation by electrical maintenance it is Q determined that the motor operator has failed.
CONTROLLER NOTES:
Provide necessary input to players as they trouble shoot the problem.
Ill. Event Closeout l Report to the OSC that the valve cannot be closed without a steam tunnel entry.
IV. Messaaes All information will be provided verbally by the Controller. Responses will be appropriate to the l activities of the players.
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1999 l: ZAI Mini-scenario - HPCI-15 Failure to Close
- l. General Description l
When the automatic isolation signal is sent to HPCI system, the primary containment inboard isolation HPCI-15 remains open due to the 42 device not getting a close signal from the control circuitry. The valve indication on the 9-3 panel will inddia open.
- . At approximately 1220, a major line break occurs on the HPCI system. The break is located in l the HPCI room about 228' elevation of the Reactor Building. Initially, Operators' efforts to close inboard HPCI-15 from the Simulator Control Board will not be successful.
l l1. Descriotion of Piaver Responses / Observations / Corrective Actions Since Simulator Control Board indicates the HPCI inboard valve (HPCI-15) failed to close, an l OSC team should be assembled, briefed, and dispatched to investigate the HPCI-15 breaker M located at the MCC-9D on the 252' level north east side of the Reactor Building. Precautions j snould be addressed due to the fact that a HPCI system leak on the southwest side of the
! Reactor Building is in progress at the present time and closing this valve will probably stop this l leak. It is expected that the OSC Team investigating the HPGl-15 breaker will enter the 252' l elevation of the Reactor Building from the north Reactor Building entrance.
At MCC-9D, the OSC Team will locally push the "ciose" 42 contacts inside the valve breaker and will successfully close the valve.
CONTROLLER NOTES:
l l 1. Radiation levels will be provided to the team as the team proceeds through the Reactor l l Building (Refer to Section 9.3). Controllers should provide the dose rate and airborne levels i after surveys or air samples are properly obtained. Players should be told that they should ;
respond as if the scenario-related radiation and airbome levels are present based on the information that they received.
- 2. Closure of the HPCI (HPCI-15) valve will have an effect on the exercise time line and i termination of the exercise. Therefore, this event needs to be coordinated between the '
Exercise Coordinator and Lead OSC Controller and controlled by the Controller. The ;
Controller will need to contact the Lead OSC Controller whether the task needs to be delayed or can be completed.
- 3. Once the repair team locally push the "close" 42 contacts to close the HPCI-15 valve, this information should be passed on to the OSC Lead Controller who will inform the Simulator Lead Controller that the HPCI-15 valve can be closed. At this time, the Controller can inform b the team that they can report the completion of the task. This is to facilitate the timing to show that HPCI 15 valve indication is closed on the Simulator Control Room Board and to isolate the leak into the Reactor Building.
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Rev.0 Page 7.9-S VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 Ill. Event Closeout The event terminates when the team demonstrates that pushing the "close" 42 contacts inside the valve breaker closes the HPCI inboard (HPCI-15) valve.
IV. Messaaes All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players. This may include the following expected activities:
OSC Team reports to MCC-90 on 252' level northeast side of Reactor Building.
Results of opening the breaker door and pushing the "close" 42 contacts on HPCI (HPCI-15) valve.
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EMERGENCY PREPAREDNESS EXERCISE 1999 Lgd bani acenario - Chemistry Samnies of Plant Systems and in dent p-a,daake! Sur;=;
- i. GeneralDescriotion I-Scenario events postulated for the exercise may require that samples of plant systems will need
- to be taken and analyzed to assess plant conditions and support accident assessment activities.
Additional in-plant radiological surveys may be done to monitor and assess plant radiological conditions. This mini-scenario outlines the extent of play and players' expected actions to be i demonstrated.
II. Dementien of Plaver Resoonses/ Observations / Corrective Actions l A. Chemistry Samples of Plant Systems Samples of plant systems may be requested throughout the exercise scenario, it is expected that system samples of reactor coolant, primary containment and plant stack effluent may be requested. Plant systems sampling may be initially directed from the Simulator Control Room i
and then transferred to the TSC after activation. Depending on the plant radiological l conditions at the time of the sample request, samples may be taken using established routine sampling procedures or post accident sampling techniques as cpecified in post accident sampling procedures (OP 3533, OP 3534, OP 3535 and OP 3536). When samples of piant systems are requested, qualified personnel from Radiation Protection and Chemistry will be l
dispatched to obtain and analyze the requested sample. The assigned sample team or technician should be familiar with the procedural requirements and administrative controls to obtain and analyze the requested sample.
Once the TSC and OSC are activated and staffed, all sample requests should be coordinated through the OSC. The assigned sample team should consult with the OSC Coordinator or attemate for specific instructions and obtain a dose commitment limit for the sampling ;
evolution to be conducted. After the team is briefed, the sampling team should be able to ]
locate the required equipment and then go or simulate going to the sample location. (For l purpose of timeliness, these actions may be simulated after discussions and approval of the Controller.) Once there or simulated there, the sample team or technician should be instructed to briefly discuss the actions necessary to obtain and analyze the sample.
CONTROLLER NOTES:
i l 1. ~All actions to nbtain and analyze the sample should be simulated. No manipulation of 1 equipment or sampling system components should be done. The appropriate equipment and tools should be available, but not used. No actions should be taken that will affect the safety l of personnel or ongoing operation of the plant.
I I 2. Because of the time compression of the exercise and the neec for plant system sample results to be used to demonstrate the ability to assess the data in support of accident assessment activities, the time frame to obtain and analyze the actual sample will be simulated and compressed. The assumed sampling process time wi!! be approximately 15 minutes per sample taken unless the actual sample time is shorter.
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 Therefore, after the assumed sampling process time of 15 minutes and the sample team briefly discusses the sampling cctivities to obtain and analyze the sample, the controller should provide the appropriate information on sample results to the sample team. The sampling team should then report and log sample results in accordance with the sampling procedure requirements.
B. In-Plant Radioloaical Survevs Plant radiological surveys (general area dose rates and air samples) will be conducted to establish the necessary radiation protection controls for on-site personnel. Radiation Protection and Chemistry technicians and other qualified personnel will conduct radiological surveys to verify plant habitability and to define the necessary radiation protection controls to support in-plant corrective actions and repair activities. While conducting these radiological surveys, plant personnel should be instructed that they should actually demonstrate these activities to eam information about scenario-related area radiation and airbome activity levels.
Controllers should provide the dose rate and airborne levels after surveys or air samples have been properly obtained. (Information on in-plant radiation levels is contained in Section 9.3 Q
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of the manual.) Players should be tolti that they should respond as if the scenario-related radiation and airbome levels are actually present based on the information that they received.
CONTROLLER NOTES:
Actions to conduct radiological surveys should ng] be simulated unless directed by the Exercise Controller. The appropriate equipment should be used to obtain the information. However, no actions should be taken that will affect the safety of personnel or ongoing operation of the plant.
Ill. Event Closecut This event terminates when the sampling teams report sample results of plant system samples requested or when radiological surveys are conducted and completed throughout the exercise scenario.
IV. Messaaes All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players.
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VERMONT YANKEE NUCLEAR POWER STATION Rev.0 EMERGENCY PREPAREDNESS EXERCISE Page 8.0-1 1999 8.8 OPERATIONAL DATA SCENARIO TIME 00:00 00:15 00:30 00:45 01:00 01:15 INSTR. CLOCK TIME 08:15 08:30 08:45 09:00 09:15 09:30 IMM PANEL ID DESCRIPTION UNITS 1 9-3 FT-23-106-1 HPCI FLOW QPM 0 0 0 0 0 0 2 63 FL10139A RHR A FLOW OPM 1 1 1 1 1 1 3 9-3 F1-101395 RHR 5 FLOW OPM 1 1 1 1 1 1 4 9-3 ' Fi 14-50A CS A FLOW GPM 0 0 0 0 0 0 5 93 FF14-505 G5 5 FLOW GPM 0 0 0 0 0 0 6 93 PI 16-19-12A DRYWELL PRESS PSIO 2.3 2.3 2.3 2.3 2.3 2.3 7 93 PI-16-19-125 DRYWELL t"Mt55 PSIG 2.3 2.3 2.3 2.3 2.3 2.3 8 94 Fl 13-91 RCIC FLOW OPM 0 0 0 0 0 0 9 9-4 FF12-141 A RWGU FLOW GPM 65 65 65 65 65 65 10 9-4 F1-121418 RWCU FLOW GPM 65 65 65 65 65 65 11 94 2165A RX GOOLANT TEMP DEG F 527 526 526 526 526 526 12 94 2-1658 RX COOLANT TEMP DEG F 527 526 526 526 526 526 13 94 2-159A REGIRG A LOOP FLOW KGPM 29.6 29.6 29.6 29.6 29.6 29.6 14 94 2 1598 RECIRC B LOOP FLOW KGPM 29.6 29.6 29.6 29.6 29.6 29 6 15 9-5 7-46A APRM/lRM A % 100 100 100 100 100 100 16 95 7-468 - APRM/lRM B % 100 101 101 101 tot 101 17 9-5 7-46G APRM/IRM C % 99 100 100 100 100 100 18 9-5 7-46D APRM/lRM D % 100 101 101 tot 101 101 19 9-5 7 46E APRM/lRM E % 101 100 100 100 100 100 20 9-5 7-46F APRM/lRM F % 101 100 100 100 100 100
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21 9-5 7-43A SRM A CPS 3.85E+05 4.60E+05 4.60E+05 4.60E+05 4.60E +05 4.61E +05 22 9-5 7-43B SRM B CPS 4.59E+05 4.46E+05 4.46E+05 4.4AE+05 4 46E+05 4.47E+05
- 23 9-5 7-43G SRM C GPS 5.15E+05 4.51E+05 4.51E+05 4.51E+05 4.51E +05 4.51E+05 24 95 7-430 SRM D CPS 4.30E4 4.48E+05 4.48E+05 4.48E+05 4.48E+05 4.48E+05
- 25 9-5 2-3 95 CORE FLOW MLB/HR 47 47 47 47 47 47 26 9-5 2-3-95 COREDP PSID 18 17 17 17 17 17 27 9-5 F1-3-310 GMD FLOW GPM 55.9 55.2 b5.2 55.2 55.2 55.2 28 9-5 6-96 WIDE RANGE PRESS PSIG 1008 1013 1013 1013 1013 1013 29 95 6-95 NAR RANGE t'Mt55 PSIG 1005 1010 1010 1010 1010 1010 30 95 6-97 FEEDWATER FLOW MLB/HR 6.3 6.4 64 64 64 6.4 31 9-5 6-97 MAIN vitam FLOW MLB/HR 6.4 6.4 6.4 6.4 6.4 64 32 95 6-98 NAR RANGE LEVEL INCHES 159 158 158 158 158 158 33 95 6-95 WIDE RANGE LEVEL INGHES 476 200 200 200 200 200 34 9-6 Ll-107-5 CST LEVEL % 50 61 61 61 61 59 35 9-6 LI-102-5A HOTWELL LEVEL N % 57 56 56 56 56 76 36 9-6 Ll-102-6B HOTWELL LEVEL S % 55 54 54 54 54 54 37 97 PF10129 GONDEN5ER VAGUUM IN HG 2.5 1.3 1.3 1.3 1.3 1.4 38 98 D/G A BKR OPEN OPEN OPEN OPEN OP.F.J OPEN 39 9-5 D/G B BKR OPEN OPEN OPEN OPEN OPEN OPEN 40 9-23 16-19-33A/C TORUS TEMP DEG F 78 80 80 80 80 80 41 9 25 LF46A TORUS LEVEL tttl 11.05 11.1 11.1 11.1 11.1 11.1 42 9 25 Li-46B TORUS LEVEL FEET 11.05 11.1 11.1 11.1 11.1 11.1 43 9-25 TR 1619-44 TORUS PRESS PSIG 0 0 0 0 0 0 44 9 25 TR 1619-44 DRYWELL PRESS PSIG ?.3 2.3 2.3 2.3 2.3 2.3 45 9 25 PR-1 156 3 DW/ TORUS DP P51D 1.95 1.85 1.85 1.85 1.86 1.86 46 9 25 TR-1619-45 DRYWELL TEMP DEG F 140 143 143 143 143 143 47 9-26 PF1 125 3A RX BUILDING DP IN H2O -1.44 1.52 1.52 1.52 1.52 -1.51 48 9-26 PI-1-125-3B RX BUILDING DP IN H2O 1.44 1.52 1.52 1.52 1.52 1.51 49 9-26 Fi-1-1251 A 5GT5 FLOW GFM 25 59 59 59 59 56 80 9-26 F111251B SGTS FLOW CFM 0 0 0 0 0 0 51 GAD DW/ TORUS O2 GONG. % 1.44 1.44 1.44 1.44 1.43 1.42 k%
Note: The ops data is dependent on operator actions taken in response to the conditions presented within the scenerlo. Ops data reflects plant conditions assuming certain basic operator actions being taken. Ops data taken from simulator. !
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VERMONT YANKEE NUCLEAR POWER STATION Rev.0 EMERGENCY PREPAREDNESS EXERCISE Page 8.0 2 ,
L 1999 8.0 OPERATIONAL DATA SCENARIO TIME 01:30 01:45 02:00 02:15 02:30 02:45 INSTR. CLOCK TIME 09:45 10:00 10:15 10:30 10:45 11:00 ITEM PANEL ID DESCRIPTION UNITS 1 9-3 FT 231081 HPCI FLOW GPM 0 0 0 0 0 0 l 2 9-3 Fb10139A RHR A FLOW GPM 1 1 1 1 7231 7100 1 3 93 Fi-101395 RHR 5 FLOW GPM 1 5 1 1 281 7362 l 4 93 Fb14-50A CS A FLOW GPM 0 0 0 0 0 0
! 5 93 F1-14-505 C5 B FLOW GPM 0 0 0 0 0 0 l
_67 9-3 93 Pi-16-1912A DRYWELL PRESS Pl-16-19125 DRYWELL r'Ress PSIG PSIG 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 8 9-4 F1-13 91 RCIC FLOW GPM 0 0 0 0 409 0 9 94 F1-12141 A RWGU FLOW GPM 65 65 65 65 0 0 10 9-4 FL12-141B RWCU FLOW GPM 65 65 65 65 0 0 11 9-4 2-165A RX COOLANT TEMP DEG F 526 526 526 524 513 507 12 94 2 1658 RX COOLANT TEMP DEG F 526 526 526 524 513 507 13 9-4 2-159A REGIRG A LOOP FLOW KGPM 29 6 29.6 29.6 0 0 0 14 9-4 2-1598 RECIRC B LOOP FLOW KGPM 29 6 29.6 29.6 0 0 0 15 9-5 7-46A APRM/lRM A % 100 100 100 99 1 0 16 95 7-46B APRM/lRM B % 101 101 101 99 1 0 17 95 7 46G APRM/lRM G % 100 100 100 99 1 0 18 95 7-46D APRM/lRM D % 101 101 101 99 1 0 19 9-5 7-46E APRM/IRM E % 100 100 100 99 1 0 20 9-5 7-46F APRM/lRM F % 100 100 100 99 1 0 21 9-5 7-43A SRM A GP5 4.61E+05 4.50E +05 4.60E+05 4.57E +05 2.74E+03 1.90E +05 22 9-5 7-43B SRMB CPS 4.47E+05 4.46E+05 4.46E+05 4.43E+05 2.66E+03 3.80E+05 l _ 23 9-5 7-43G SRM G we 4.51E+05 4.51E+05 4.51E+05 4.47E+05 2.69E+03 4.00E+05 ,
24 9-5 7-430 SRM D CPS 4.48E+05 4.48E+05 4.48E+05 4.45E+05 2.67E+03 2.00E+05 J 95 2-3-95 CORE FLOW MLB/HR 47 47 47 46 0 0 l ' 2526 95 2-3-95 CORE DP PSID 17 17 17 16 0 0 I 27 9-5 F1-3-31D GRD FLOW GPM 55.2 55.2 55.2 55.4 126 55.9 28 95 6-96 WIDE RANGE PRESS PSIG 1013 1013 1013 1000 922 932
)
29 9-5 6-96 NAR RANGE PRESS PSIG 1010 1010 1010 998 950 950 30 05 6-97 FEEDWATER FLOW MLB/HR 64 6.4 6.4 6.3 0.4 0.1 31 95 6-97 MAIN sIEAM FLOW MLB/HR 6.4 6.4 6.4 6.3 0.2 0 32 9-5 6-98 NAR RANGE LEVEL INCHES 158 158 158 159 127 127 33 95 6-95 WIDE RANGE LEVEL INGHE5 200 200 200 200 50 48 34 96 U-107-5 CST LEVEL % 59 59 59 61 61 62 j 35 9-6 Li-102-5A HOTWELL LEVEL N % 84 75 75 55 67 61 36 9-6 LL102-5B HOTWELL LEVEL S % 54 58 58 54 63 58 37 97 PI 10129 CONDEN5ER VAGUUM IN HG 1.4 1.3 1.3 1.3 0.8 1.2 38 9-8 D/G A BKR OPEN OPEN OPEN OPEN OPEN OPEN 3D 9-8 D/G B BKR OPEN OPEN OPEN OPEN OPEN OPEN 40 9-23 1619-33A/C TORUS TEMP DEG F 80 80 80 80 80 82 41 9-25 U-46A TORUS LEVEL I-Et:I 11.1 11.1 11.1 11.1 11.1 11.1 42 9-25 L1-468 TORUS LEVEL !"EET 11.1 11.1 11.1 11.1 11.1 11.1 43 9-25 TW16-19 44 TORUS PRESS PSIG 0 0 0 0 0 0.1 44 9 25 TR-16-19-44 DRYWELL PRESS PSIG 2.3 2.3 2.3 2.3 2.3 2.3 45 9-25 PR-1-156-3 DW/ TORUS DP P51D 1.86 1.86 1.86 1.85 1.85 1.5 46 9-25 TR-1619-45 DRYWELL TEMP DEG F 143 143 143 142 141 141 47 9-26 PI-1 125 3A RX BUILDING DP IN H2O 1.51 1.51 1.51 1.16 -0.34 -0.75 48 9-26 Ph1 125 38 RX BUILDING DP IN H2O 1.51 1.51 1.51 1.16 -0.34 -0.75 49 9-26 F1-11251A 5G15 FLOW CFM 58 58 58 56 1500 1500 50 9 26 Fb1125-1B SGTS FLOW CFM 0 0 0 0 1500 1500 51 GAD DW/ TORUS O2 CONG. % 1.41 1.4 1.4 1.36 1.35 1.34 0 Note % ope data is dependent on operator actions taken in response to the conditions presented within the uenerlo, Ops data reflects plant conditions assuming certain basic operator actions being taken. Ops data taken from almulator.
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VERMONT YANKEE NUCLEAR POWER STATION Rev.O
!/ EMERGENCY PREPAREDNESS EXERCISE Page 8.0 3 j
- Q 8.0 OPERATIONAL DATA 1999 SCENARIO TIME 03:00 03:15 03:30 03:45 04:00 04:15 INSTR. CLOCK TIME 11:15 11:30 11:45 12:00 12:15 12.30 ITEM PANEL ID DESCRIPTION UNITS 1 9-3 FT 23-108-1 HPCI FLOW GPM 0 0 0 0 0 0 2 9-3 F1-10139A RHR A FLOW GPM 7100 7100 7100 7100 7100 7100 3 93 F1-10-139B RHR B FLOW GPM 7362 7362 7363 7363 7363 7362 4 9-3 Fl.14-50A CS A FLOW GPM 0 0 0 0 0 0 5 9-3 F1-14-50B CS B FLOW GPM 0 0 0 0 0 0 6 9-1 PI-161912A DRYWELL PRESS PSIG 2.3 2.3 2.3 2.3 2.3 2.3 7 9-3 PI-1619-12B DRYWELL PRESS PSIG 2.3 2.3 2.3 2.3 2.3 2.3 8 9-4 F1-13-91 RCIC FLOW GPM 0 0 0 0 0 0 9 9-4 F1-12-141 A RWCU FLOW GPM 0 0 0 0 0 0 10 9-4 F1-12-141B RWCU FLOW GPM 0 0 0 0 0 0 11 S4 2-165A RX COOLANT TEMP DEG F 401 452 479 489 498 462 12 9-4 2-165B RX COOLANT TEMP DEG F 491 452 479 489 498 462
~
13 9-4 2-159A RECIRC A LOOP FLOW KGPM 0 0 0 0 0 0 14 94 2 1598 RECIRC B LOOP FLOW KGPM 0 0 0 0 0 0 15 95 7 46A APRM/!RM A % 0 0 1 0 0 0 16 9-5 7-46B APRM/lRM B % 0 0 0 0 0 0 17 9-5 7-46C APRM/lRM C % 0 0 0 0 0 0 18 9-5 7 46D APRM/lRM D % 0 0 0 0 0 0 19 95 7-46E APRM/lRM E % 0 0 0 0 0 0 l 20 95 7 46F APRM/lRM F % 0 0 0 0 0 0 21 95 7-43A SRM A GPS 3.38E+02 2.94E+02 2.62E+02 2.42bM2 2.25E+05 2.15E +02 22 9-5 7 43B SRM B CPS 3.39E+02 2.94E+02 2.62E+02 2.42E+02 2.25E+05 2.14E+02 l 23 95 7-43C SRM C CPS 3.39E+02 2.94E+02 2.62E+02 2.42E+02 k25E+05 2.14E+02
^
24 9-5 7-43D SRM D CPS 3.37E+02 2.94E+02 2.62E+02 2.42E+02 2.26tMS 2.15E+02 25 9-5 2-3-95 CORE FLOW MLB/HR 1 5 11 13 6 2 1
- 26 9-5 2-3-95 CORE DP PSID 0 0 1 1 0 1 l
! 27 95 F1-6 310 CRD FLOW GPM 55.3 55.4 55.4 55.4 55.3 55.4 l 28 9-5 6-we WIDE RANGE PRESS PSIG 625 628 651 684 667 460 29 9-5 6 96 NAR RANGE PRESS PSIG 950 950 950 950 950 950 30 9-5 6-97 FEEDWATER FLOW MLB/HR 0 0 0 0.1 0 0.3
, 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 0 0 0 0 0 0 l 32 9-5 6-98 NAR RANGE LEVEL INCHES 127 127 127 127 148 127 33 9-5 6-98 WIDE RANGE LEVEL INCHES 59 69 104 131 166 126 34 9-6 LI-107 5 CST LEVEL % 61 60 59 59 58 58 l
35 9-6 U-102-5A HOTWELL LEVEL N % 57 57 58 57 58 57 36 9-6 Li-102-5B HOTWELL LEVEL S % 54 54 54 54 54 54 37 9-7 Pi-101-29 CONDEN5ER VACUUM IN HG 10 16.1 20.3 23 3 25.3 26.7 38 9-8 D/G A BKR OPEN OPEN OPEN OPEN OPEN OPEN 39 9-8 D/G B BKR OPEN OPEN OPEN OPEN OPEN OPEN j 40 9 23 16-19-33A/C TORUS TEMP DEG F 87 85 79 74 69 69 l 41 9-25 LI-46A TORUS LEVEL FEET 11.2 11.21 11.22 11.22 11.23 11.26 42 9 25 Li-46B TORUS LEVEL FEET 11.2 11.21 11.22 11.22 11.23 11.26
, 43 9 25 TR-16-19-44 TORUS PRE 55 PSIG 0.3 0.3 0.2 0.2 0.3 0.3 l 44 9-25 TR-16-19-44 DRYWELL PRESS PSIG 2.3 2.3 2.3 2.3 2.3 2.3 l 45 9-25 PR-1-156 3 DW/ TORUS DP PSID 1.67 1.76 1.92 1.92 1 93 1.95 l 46 9-25 TR 1619-45 DRYWELL TEMP DEG F 141 140 140 140 139 139 47 9 26 Pl-1125-3A RX BUILDING DP IN H2O 1.05 1.13 1.11 1.09 1.09 -2.53 48 9-26 PI-1-125-3B RX BUILDING DP IN H2O 1.05 -1.13 1.11 -1.09 1.09 2.53 49 9-26 F1-1-125-1 A SGTS FLOW CFM 1500 1500 1500 1500 1500 1500 l 50 9-26 F1-1-125-1B SGTS FLOW CFM 1500 1500 1500 1500 1500 1500 51 CAD DW/ TORUS O2 CONC. % 1.33 1.32 1.31 1.3 1.29 1.29 q
,%J i
Note: The ops data is dependent on operator actions taken in response to the conditions presented Within the scenarlo. Ops data reflects plant conditions assuming certain basic operator actions being taken. Ops data taken from simulator.
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l- VERMONT YANKEE NUCLEAR POWER STATION Rev. 0
!- EMERGENCY PREPAREDNESS EXERCISE Page 8.0-4 1999 8.0 OPERATIONAL DATA SCENARIO TIME 04:30 04:45 05:00 05:15 05:30 INSTR. CLOCK TIME 12:45 13:00 13:15 13:30 13:45 ITEM PANEL ID DESCRIPTION UNITS 1 9-3 FT-23-108-1 HPCI FLOW GPM 0 0 0 0 0 2 9-3 F1-10139A RHR A FLOW GPM 7100 7100 7100 7100 7100 3 9-3 F1-101395 RNR 5 FLOW QPM 7352 7352 7352 7352 7352 4 9-3 F1-14 50A CS A FLOW GPM 0 7,0 40 40 40 5 94 F1-14-505 C5 5 FLOW QPM 0 40 40 40 40 8 93 Ph161912A DRYWELL PRESS PSIG 2.3 2.3 2.3 2.3 2.3 7 93 Pi-161912B DRYWELL PRESS PSIG 2.3 2.3 2.3 2.3 2.3 8 94 F1-13 91 RCIC FLOW GPM 0 0 0 0 0 l 9 9-4 F1-12141 A RWCU FLOW GPM 0 0 0 0 0 10 9-4 F1-12-141B RWCU FLOW GPM 0 0 0 0 0 11 94 2165A RX COOLANT TEMP DEG F 384 342 340 338 338 12 94 2-165B RX COOLANT TEMP DEG F 384 342 340 338 338 13 94 2-159A RECIRC A LOOP FLOW KGPM 0 0 0 0 0 14 9-4 2-159B RECIRC B LOOP FLOW KGPM 0 0 0 0 0 15 9-5 7-46A APRM/lRM A % 0 0 0 0 0 16 95 7-46B APRM/lRM B % 0 0 0 0 0 17 9-5 7-46C APRM/lRM C % 0 0 0 0 0 18 95 7-46D APRM/lRM D % 0 0 0 0 0 19 95 7-46E APT.M/lRM E % 0 0 0 0 0 20 9-5 7-46F APRM/lRM F % 0 0 0 0 0 21 9-5 7 43A SRM A CPS 2.05E+02 1.95E+02 1.77E +02 1.4SE+02 1.25E+02 22 9-5 7-43B SRM B CPS 2.05E+02 1.95E+02 1.77E+02 1.48E+02 1.25E+02 23 95 7-43C SRM C CPS 2.05E+02 1.95E+02 1.77E+02 1.48E+02 1.25E+02 p, 24 95 7-43D SRM D CPS 2.05E+02 1.95E+02 1.77E+02 1.48E+02 1.25E+02
( 25 9-5 2-3-95 CORE FLOW MLB/HR 14 14 14 12 12
!\ 26 9-5 2-3-95 CORE DP PSID 1 1 1 1 1 27 9-5 Fi-3 310 CRD FLOW GPM 55.3 55.3 55.2 55.2 55.2 28 9-5 6-96 WIDE RANGE PRESS PSIG 191 107 106 105 105 29 9-5 6-96 NAR RANGE PRESS PSIG 950 950 950 950 950 30 9-5 6-97 FEEDWATER FLOW MLB/HR 0.1 0.1 0.1 0.1 0.1 31 95 6-97 MAIN STEAM FLOW MLB/HR 0 0 0 0 0 32 0-5 6-98 NAR RANGE LEVEL INCHES 127 127 127 127 127 33 95 6-98 WIDE RANGE LEVEL INCHES 153 157 157 158 158 !
34 9-6 Q 107-5 CST LEVEL % 56 55 55 54 54 35 9-6 Li-102-5A HOTWELL LEVEL N % 54 54 54 54 54 36 9-6 U 102-5B HOTWELL LEVEL S % 54 54 54 54 54 37 97 Pl-101-29 CONDENSER VACUUM IN HG 27.7 28.3 28 28 28 38 9-8 D/G A BKR OPEN OPEN OPEN OPEN OPEN 39 9-8 D/G B BKR OPEN OPEN OPEN OPEN OPEN 40 9-23 1619-33A/C TORUS TEMP DEG F 64 60 60 59 59 41 9-25 Li-46A TORUS LEVEL FEET 11.26 11.27 11.28 11.28 11.28 42 9 25 Lh46B TORUS LEVEL FEET 11.26 11.27 11.28 11.28 11.28 43 P 'S TR-1619-44 TORUS PRESS PSIG 0.3 0.3 0.3 0.3 0.3 44 9-25 TR 1619 44 DRYWELL PRESS PSIG 2.3 2.3 2.3 2.3 2.3 45 9 25 PR 1 156-3 DW/ TORUS DP PSID 1.96 1.96 1.96 1.96 1.96 46 9-25 TR 1619 45 ORYWELL TEMP DEG F 138 137 137 136 135 47 9 26 Pb1125-3A RX BUILDING DP (N H2O 2.48 2.37 -2.2 2.2 -2.1 48' 9 26 PL1-125-33 RX BUILDING DP IN H2O -2.48 2.37 -2.2 2.2 -2.1 49 9 26 F1-1125-1 A SGT5 FLOW CFM 1500 1500 1500 1500 1500 50 9 26 FL1125-1B SGTS FLOW CFM 1500 1500 1500 1500 1500 l 51 CAD DW/ TORUS O2 CONC. % 1.28 1.27 1.26 1.26 1.25 b
\ i Note: The ops data is dependent on operator actions taken in response to the conditions presented within the scenerlo. Ops data reflects plant conditions assuming certain basic operator actions being taken. Ops data taken from almulator,
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VERMONT YANKEE NUCLEAR POWER STATION Rev.0 j EMERGENCY PREPAREDNESS EXERCISE Page 9.1 1 1 1999 9.1 AREA RADIATA MONITORS
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SCENARIO TIME 00:00 00:15 00:30 00:45 01:00 01:15 CLOCK TIME 00:15 08:30 08:45 09:00 09:15 09:30 t
ARM No. PANEL BLDG /ELV DESCRIPTION UNITS M1 9-11 RB/252 RX BLDG HI RADS N R/hr <1 <1 <1 <1 <1 <1 RMS Il-2 9 11 RB/252 RX BLDG HI RADS S R/hr <1 <1 <1 <1 <1 <1 l RMS 11-3 9-11 RB/252 TIP RM HI RAD R/hr <1 <1 <1 <1 <1 <1 1 9'.11 RB/232 SUPP CHAMB RB EXT CW mR/hr 8 8 8 8 8 8 2 9-11 RB/252 N PERSONNEL RX BLDG mR/hr 4 4 4 4 4 4
! 3 9-11 RB/252 S EQUIP RR RX BLDG mR/hr 0.3 0.3 0.3 0.3 0.3 0.3 4 9-11 RB/252 RX BLD NEUTRON TIP mR/hr 5 5 5 5 5 5 5 9-11 RB/252 PERSONNEL HATCH RX B mR/hr 520 520 520 520 520 520 6 9-11 RB/280 ELEV ENTR 280FT RX mR/hr 8 8 8 8 8 '8
-7 9 11 RB/252 CRD REPAIR RX BLDG m R/hr 11 11 11 11 11 11 8 9 11 RB/303 ELEV ENTR 303FT RX mR/hr 4 4 4 4 4- 4 9 9-11 RB/303 H2O CLEANUP RX BLDG mR/hr 4 4 4 4 4 4 10 9-11 RB/318 ELEV ENTR 318FT RX mR/hr 7 7 7 7 7 7 9-11 RB/318 H2O CLEANUP RX BLDG ' mR/hr 4 4 4- -4 4 4 12 9-11' RB/345 ELEV ENTR 348FT RX mR/hr 4 4 4 4 4 4 14 9-11 RB/345 WEST REFUEL RX BLDG mR/hr 5 5 5 5 5 5
-15 9-11. RB/345 SPENT FUEL POOL RX mR/hr 15 15 15 15 15 15 !
18 9-11 RB/318 NEW FUEL VAULT RX B mR/hr 0.5 0.5 0.5 0.5 0.5 0.5 l 17 9 11 RW/252 PUMP RM RADWASTE BL mR/hr 1 1 1 1 1 1 1 18 9-11 RW/252 RADW OPER AREA RW B mR/hr 1 1 1 1 1 1 l
19 9 11 RW/230 PUMP / TANK AREA RW B mR/hr 1.5 1.5 1.5 1.5 1.5 1.5 20 9-11 TB/248 N ACCESS 248FT TURB mR/hr 2 2 2 2 2 2
! 21 9 11 TB/248 MAIN STM VALVE TURB mR/hr 240 240 240 240 240 240 l 22 9 11 TB/232 COND DEMIN TURB BLD m R/hr 0.3 0.3 0.3 0.3 0.3 0.3 23 9 11 TB/252 DECON/ MACH SHOP TB mR/hr 0.15 0.15 0.15 0.15 0.16 0.15 24 9-11 TB/272 TURB STM IN TURB BL mR/hr 8 8 8 8 8 8 25 9-11 AB/272 VIEW GALLERY CONT RM mR/hr 0.9 0.9 0.9 0.9 0.9 0.9 28 9-11' TB/252 REAR GATE TURB WAREF mR/hr 0.18 0.18 0.18 0.18 0.18 0.18 13 9-11 TB/228 MOIST SEP AREA TURB mR/hr 135 135 135 135 135 135 l
O VERMONT YANKEE NUCLEAR POWER STATION Rev.0 EMERGENCY PREPAREDNESS EXERCISE Page 9.1-2 1999 9.1 AREA RADIATION MONITORS l
SCENARIO TIME 01:30 01:45 02:00 02:15 02:30 02:45 CLOCK TIME 09:45 10:00 10:15 10:30 10:45 11:00 ARM No. PANEL BLDG /ELV DESCRIPTION UNITS i RMS ll-1 0-11 RB/252 RX BLDG HI RADS N R/hr <1 <1 <1 <1 <1 <1 ,
RMS ll-2 9-11 RB/252 RX BLDG HI RADS S R/hr <1 <1 <1 <1 <1 <1 l RMS 11-3 9-11 PS/252 TIP RM HI RAD R/hr <1 <1 <1 <1 <1 <1 j 1 9-11 RB/232 SUPP CHAMB RB EXT CW mR/hr 8 8 8 8 6 50 l 2 9-11 RB/252 N PERSONNEL RX BLDG mR/hr 4 4 4 4 0.2 0.2 3 9-11 RB/252 S EQUIP RR RX BLDG mR/hr 0.3 0.3 0.3 0.3 0.2 0.2 4 9-11 RB/252 RX BLD NEUTRON TIP mR/hr 5 5 5 5 5 5 5 9-11 RB/252 PERSONNEL HATCH RX B mR/hr 520 520 520 520 350 200 6 9-11 RB/280 ELEV ENTR 280FT RX B mR/hr 8 8 8 8 5 5
-7 9-11 RB/252 CRD REPAIR RX BLDG mR/hr 11 11 11 11 4 4 j 8 9-11 RB/303 ELEV ENTR 303FT RX B mR/hr 4 4 4 4 1 1 9 9-11 RB/303 H2O CLEANUP RX BLDG mR/hr 4 4 4 4 4 4 )
10 9-11 RB/318 ELEV ENTR 318FT RX B mR/hr 7 7 7 7 3 3 11 9-11 RB/318 H2O CLEANUP RX BLDG mR/hr 4 4 4 4 2 2 12 9-11 RB/345 ELEV ENTR 348FT RX B mR/hr 4 4 4 4 1 1 14 9-11 RB/345 WEST REFUEL RX BLDG mR/hr 5 5 5 5 1 1 15 9-11 RB/345 SPENT FUEL POOL RX B mR/hr 15 15 15 15 8 8 16 9-11 RB/318 NEW FUEL VAULT RX B mR/hr 0.5 0.5 0.5 0.5 0.3 0.3 17 9-11 RW/252 PUMP RM RADWASTE BLt mR/hr 1 1 1 1 1 1 18 9-11 RW/252 RADW OPER AREA RW B mR/hr 1 1 1 1 1 1 19 9-11 RW/230 PUMP / TANK AREA RW B mR/hr 1.5 1.5 1.5 1.5 1.5 1.5 20 9-11 TB/248 N ACCESS 248FT TURB m R/hr 2 2 2 2 1 1 21 9-11 TB/2451 MAIN STM VALVE TUR3 mR/hr 240 240 240 240 70 350 22 9-11 TB/232 COND DEMIN TURB BLDG mR/hr 0.3 0.3 0.3 0.3 0.1 0.1 23 9-11 TB/252 DECONTAM.TURB BLDG mR/hr 0.15 0.15 0.15 0.15 0.15 0.15 24 9-11 TB/272 TURB STM IN TURB BLD mR/hr 8 8 8 8 7 8 25 9-11 AB/272 VIEW GALLERY CONT RM mR/hr 0.9 0.9 0.9 0.9 0.11 0.11 26 9-11 TB/252 REAR GATE TURB WAREF mR/hr 0.18 0.18 0.18 0.18 0.01 0.01 13 9-11 TB/228 MOIST SEP AREA TURB mH/hr 135 135 135 135 1 1 9
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VERMONT YANKEE NUCLEAR POWER STATION Rev.0 l EMERGENCY PREPAREDNESS EXERCISE Page 9.1-3 1999 9.1 AREA RADIATION MONITORS SCENARIO TIME 03:00 03:15 03:30 03:45 04:00 04:15 CLOCK TIME 11:15 11:30 11:45 12:00 12:15 12:30 -
ARM No. PANEL BLDG /ELV DESCRIPTION UNITS RMS 11-1 9-11 RB/252 RX BLDG HI RADS - N R/hr <1 <1 <1 <1 <1 <1 RMS 11-2 9-11 RB/252 RX BLDG Hi RADS S R/hr <1 <1 <1 <1 <1 2 RMS 11-3 9-11 RB/252 TIP RM HI RAD R/hr <1 <1 <1 <1 <1 <1 1 9-11 RB/232 SUPP CHAMB RB EXT CW mR/hr 150 500 1500 2800 3000 4000 2 9-11 RB/252 N PERSONNEL RX BLDG mR/hr 0.2 0.2 0.2 0.2 0.2 400 3 9-11 RB/252 S EQUIP RR RX BLDG mR!hr 0.2 0.2 0.2 0.2 0.2 800 J 4 9-11 RB/252 RX BLD NEUTRON TIP mR/hr 5 5 5 5 5 400 5 9-11 RB/252 PERSONNEL HATCH RX B mR/hr 600 2000 6000 8000 OSH(>1E4) OSH 6 9 11 RB/280 ELEV ENTR 280FT RX B m R/hr 5 5 5 5 5 100 7 9-11 RB/252 CRD REPAIR RX BLDG mR/hr 4 4 4 4 4 500 9-11 RB/303 ELEV t'.NTR 303FT RX B mR/hr 1 1 1 1 1 100 W9 9-11 RB/303 H2O CL.EANUP RX BLDG mR/hr 4 4 4 4 4 200 10 9-11 RB/318 ELEV ENTR 318FT RX B mR/hr 3 3 3 3 3 50 11 9-11 RB/318 H2O CLEANUP RX BLDG mR/hr 2 2 2 2 2 200 12 9-11 RB/345 ELEV ENTR 348FT RX B mRihr 1 1 1 1 1 50 14 9-11 RB/345 WEST REFUEL RX BLDG mR/hr 1 1 1 1 1 50 j 15 9-11 RB/345 SPENT FUEL POOL RX B mR/hr 8 8 8 8 8 50 16 9-11 RB/318 NEW FUEL VAULT RX B mR/hr 0.3 0.3 0.3 0.3 0.3 OSH 17 9-11 RW/252 PUMP RM RADWASTE BLt mR/hr 1 1 1 1 1 1 18 9-11 RW/252 RADW OPER AREA RW B mR/hr 1 1 1 1 1 1 19 9-11 RW/230 PUMP / TANK AREA RW B mR/hr 1.5 1.5 1.5 1.5 1.5 1.6 20 9-11 TB/248 N ACCESS 248FT TURB mR/hr 1 1 1 1 1 1 21 0-11 TB/248 MAIN STM VALVE TURB mR/hr 290 275 265 260 250 245 22 9 11 TB/232 COND DEMIN TURB BLDG mR/hr 0.1 0.1 0.1 0.1 0.1 0.1 23 9 11 TB/252 DECONTAM. TURB BLDG mR/hr 0.15 0.15 0.15 0.15 0.15 0.15 24 9 11 TB/272 TURB STM IN TURB BLD mR/hr 8 7 7 7 7 7 25 9-11 AB/272 VIEW GALLERY CONT RM mR/hr 0.11 0.11 0.11 0.1 0.1 0.1 26 9-11 TB/252 REAR GATE TURB WAREF mR/hr 0.01 0.01 0.01 0.01 0.01 0.01 13 9-11 TB/228 MOIST SEP AREA TURB mR/hr 1 1 1 1 1 1 OSH = Off-scale High 1
f V
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VERMONT YANKEE NUCLEAR POWER STATION Rev.0 EMERGENCY PREPAREDNESS EXERCISE Page 9.1-4 1999 9.1 AREA RADIATION MONITORS - !
SCENARIO TIME 04:30 04:45 05:00 05:15 05:30 CLOCK TIME 12:45 13:00 13:15 13:30 13:45
' ARM No. PANEL BLDG /ELV DESCRIPTION UNITS "
RMS 111 9-11 RB/252 RX BLDG HI RADS - N R/hr <1 <1 <1 <1 <1 RMS 11-2 9-11 RB/252 RX BLDG HI RADS - S R/hr 2 4 5 4 3 RMS 11-3 9-11 RB/252 TIP RM H1 RAD R/hr <1 <1 <1 <1 <1 ,
1 9-11 RB/232 SUPP CHAMB RB EXT CW mR/hr 7000 7500 OSH(>1E4) OSH OSH I 2 9-11 RB/252 N PERSONNEL RX BLDG mR/hr 520 670 800 750 700 3 9-11 RB/252 S EQUIP RR RX BLDG mR/hr 860 950 OSH(>1 E3) OSH OSH J 4 9-11 RB/252 RX BLD NEUTRON TIP mR/hr 520 670 800 750 700 5 9-11 RB/252 PERSONNEL HATCH RX B mR/hr OSH(>1E4) OSH OSH OSH OSH
- 6 9-11 RB/280 ELEV ENTR 280FT RX B mR/hr 220 370 500 480 450
_ 7 9-11 RB/252 CRD REPAIR RX BLDG mR/hr 700 950 1200 1100 1000 8 9 11- RB/303 ELEV ENTR 303FT RX B - mR/hr 220 370 500 480- 450
-9 9 RB/303 H2O CLEANUP RX BLDG mR/hr 320 500 600 580 550 10 9-11 RB/318 ELEV ENTR 318FT RX B m R/hr 100 150 200 190 180
)
11 9 11 RS/318 H2O CLEANUP RX BLDG mR/hr 260 340 400 380 350 12 9-11 RB/345 ELEV ENTR 348F1 RX B mR/hr 100 150 200 190 180 14 9 11 RB/345 WEST REFUEL RX BLDG mR/hr 100 150 200 190 180 15 9-11 RB/343 SPENT FUEL POOL RX B mR/hr 100 150 200 190 180 16 9-11 RB/318 NEW FUEL VAULT RX B mR/hr OSH(>1E2) OSH OSH OSH OSH 17 - 9-11 RW!252 PUMP RM RADWASTE BLI mR/hr 1 1 1- 1 1 18 9-11 RW/252 RADW OPER AREA RW B mR/hr 1 1 1 1 1 l 19 9-11 RW/230 PUMP / TANK AREA RW B mR/hr 1.6 1.6 1.6 1.6 1.6 20 9-11 TB/248 N ACCESS 248FTTURB mR/hr 1 1 1 1 1 l 21 9-11 TB/248 MAIN STM VALVE TURB mR/hr 240 240 230 220 200 22 9-11 TB/232 COND DEMIN TURB BLDG mR/hr 0.1 0.1 0.1 0.1 0.1 l 23 9 11 TB/252 DECONTAM.TURB BLDG mR/hr 0.15 0.15 0.15 0.15 0.15 24 9-11 - TB/272 TURB STM IN TURB BLD mR/hr 7 7 7 7 7 25 9-11 AB/272 VIEW GALLERY CONT RM mR/hr 0.1 0.1 0.1 0.1 0.1 I 26 9-11 TB/252 REAR GATE TURB WAREF mR/hr 0.01 0.01 0.01 0.01 0.01 13 9-11 TB/228 MOIST SEP AREA TURB mR/hr 1 1 1 1 1 OSH = Off-scale High 1
l
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VERMONT YANKEE NUCLEAR POWER STATION Rev.O
'O EMF.RGENCY PREPAREDNESS EXERCISE Page 9.2-1 I
s_,) 1999 I
9.2 PROCESS MONITORS SCENARIO TIME 00:00 00:15 00:30 00:45 01:00 01:15 ARM CLOCK TIME 08:15 08:30 08:45 09:00 09:15 09:30 NO. PANEL BLDG /ELV DESCRIPTION UNITS 9-2 ST/257 STACK GAS MON-GAS 1 cpm 150 150 150 150 150 150 9-2 ST/257 STACK GAS MON-GAS 2 cpm 200 200 200 200 200 200 9-2 ST/257 STACK HI RANGE mR/hr 0.1 0.1 0.1 0.1 0.1 0.1 9-2 RB/280 CONTAINMENT MON GAS cpm 450 450 450 450 450 450 9-2 RB/280 CONTAINMENT MON-PAR cpm 975 975 975 975 975 975 27 9-2 DW/252 DRYWELL CH A R/hr 3 3 3 3 3 3 28 9-2 DW/252 DRYWELL CH B R/hr 3 3 3 3 3 3 9-2 RB/280 RX BLDG VENT GAS cpm 150 150 150 150 150 150 9-2 RB/280 RX BLDG VENT - PART cpm 1500 1500 1500 1500 1500 1500 31 9 10 RB/280 RX BLDG VENT NORTH mR/hr 2 2 2 2 2 2 32 9-10 RB/280 RX BLDG VENT SOUTH mR/hr 2 2 2 2 2 2 453A 9-10 RB/345 SPENT FUEL POOL WEST mR/hr 3 3 3 3 3 3 4538 9-10 RB/345 SPENT FUEL POOL EAST mR/hr 3 3 3 3 3 3 9-10 RB/256 MAIN STM LINE A mR/hr 140 140 140 140 140 140 9-10 RB/256 MAIN STM LINE B mR/hr 150 150 150 150 150 150 9-10 RB/256 MAIN STM LINE C mR/hr 150 150 150 150 150 150 O 9-10 RB/256 MAIN STM LINE D mR/hr 140 170 170 170 150 140 I 38' 9-10 TB/248 SJAE(AIR EJECTOR) mR/hr 75 75 75 75 75 75 l
l l
l l
a
VERMONT YANKEE NUCLEAR POWER STATION Rev.0 3 EMERGENCY PREPAREDNESS EXERCISE Page 9.2-2 1999 9.2 PROCESS MONITORS SCENARIO TIME 01:30 01:45 0*:00 02:15 02:30 02:45 ARM CLOCK TIME 09:45 10:00 10:15 10:30 10:45 11:00 NO. PANELBLDG/ELV DESCRIPTION UNITS 9-2 ST/257 STACK GAS MON-GAS 1 cpm 150 150 150 150 150 150 9-2 ST/257 STACK GAS MON-GAS 2 cpm 200 200 200 200 200 200 l 9-2 ST/257 STACK HI RANGE mR/hr 0.1 0.1 0.1 0.1 0.1 0.1 9-2 RB/280 CONTAINMENT MON GAS cpm 450 450 450 450 20 20 9-2 RB/280 CONTAINMENT MON-PAR cpm 975 975 975 975 900 840 27 9-2 DW/252 DRYWELL CH A R/hr 3 3 3 3 2 100 28 9-2 DW/252 DRYWELL CH B R/hr 3 3 3 3 2 100 9-2 RB/280 RX BLDG VENT GAS cpm 150 150 150 150 150 150 9-2 RB/280 RX BLDG VENT - PART cpm 1500 1500 1500 1500 1500 1500 31 9-10 RB/280 RX BLDG VENT NORTH mR/hr 2 2 2 2 0.1 0.1 32 9-10 RB/280 RX BLDG VENT SOUTH mR/hr 2 2 2 2 0.1 0.1
'453A 9-10 RB/345 SPENT FUEL POOL WEST mR/hr 3 3 3 3 3 3 453B 9-10 RB/345 SPENT FUEL POOL EAST mR/hr 3 3 3 3 3 3 9-10 RB/256 MAIN STM LINE A mR/hr 140 140 140 140 30 190 9-10 RB/256 MAIN STM LINE B mR/hr 150 150 150 150 30 210 9-10 RB/256 MAIN STM LINE C mR/hr 150 150 150 150 30 200 3 9-10 RB/256 MAIN STM LINE D mR/hr 130 130 130 130 30 185 l ' 38 9-10 TB/248 SJAE(AIR EJECTOR) mR/hr 75 75 75 75 20 95 l
i
)
7.
' /7 VERMONT YANKEE NUCLEAR POWER STATION Rev.O
' V EMERGENCY PREPAREDNESS EXERCISE 1999 Page 9.2-3 9.2 PROCESS MONITORS SCENARIO TIME 03:00 03:15 03:30 03:45 04:00 04:15 ARM CLOCK TIME 11:15 11:30 11:45 12:00 12:15 12:30 No. PANELBLDG/ELV DESCRIPTION UNITS 9-2 ST/257 STACK GAS MON-GAS 1 cpm 150 150 150 150 150 OSH 9-2 ST/257 STACK GAS MON-GAS 2 cpm 200 200 200- 200 200 OSH 9-2 ST/257 STACK HI RANGE mR/hr 0.1 0.1 0.1 0.1 0.1 40 i 9-2 RB/280 CONTAINMENT MON GAS cpm 20 20 20 20 20 20 9-2 RB/280 - CONTAINMENT MON-PAR cpm 770 710 710 710 710 600
]
27 9-2 DW/252 DRYWELL CH A R/hr 300 1000 3000 4500 6000 6000 28 9-2 DW/252 DRYWELL CH B R/hr 300 1000 3000 4500 6000 6000 9-2 RB/280 RX BLDG VENT GAS cpm 150 150 150 150 150 OSH>1E6 9-2 RB/280 RX BLDG VENT - PART cpm 1500 1500 1500 1500 1500 OSH>1E6 31 9-10' RB/280 RX BLDG VENT NORTH mR/hr 0.1 0.1 0.1 0.1 0.1 22 32 9-10 RB/280 RX BLDG VENT SOUTH mR/hr 0.1 0.1 0.1 0.1 0.1 230 l 453A 9-10 RB/345 SPENT FUEL POOL WEST mR/hr 3 3 3 3 3 50 453B 9-10 RB/345 SPENT FUEL POOL EAST mR/hr 3 3 3 3 3 400 9-10 RB/256 MAIN STM LINE A mR/hr 160 150 145 140 135 130 0 10 RB/256 MAIN STM LINE B mR/hr 170 160 155 150 145 140 l-
- 9-10 RB/256 MAIN STM LINE C mR/hr 165 155 150 145 140 135 9 10 RB/256 MAIN STM LINE D mR/hr 150 145 140 135 130 125 '
]-38 9-10 TB/248 SJAE(AIR EJECTOR) mR/hr <1 <1 <1 <1 <1 <1 NOTE: OSH = Off Scale High i l
l 1
O .
1 L-
i I
VERMONT YANKEE NUCLEAR POWER STATION Rev.O EMERGENCY PREPAREDNESS EXERCISE Page 9.2-4 1999 9.2 PROCESS MONITORS SCENARIO TIME 04:30 04:45 05:00 05:15 05:30 ARM CLOCK TIME 12:45 13:00 13:15 13:30 13:45 NO. PANEL BLDG /ELV DESCRIPTION UNITS 9-2 ST/257 STACK GAS MON-GAS 1 cpm OSH>1 E6 OSH OSH OSH OSH 9-2 ST/257 STACK GAS MON-GAS 2 cpm OSH>1E6 OSH OSH OSH OSH 9-2 ST/257 STACK HI RANGE mR/hr 100 125 140 130 115 9-2 RB/280 CONTAINMENT MON GAS cpm 20 20 20 20 20 9-2 RB/280 CONTAINMENT MON-PAR cpm 600 600 600 600 600 27 9-2 DW/252 DRY'NELL CH A R/hr 6000 -6000 6000 6000 6000 r 28 9-2 DW/252 DRYWELL CH B R/hr 6000 6000 6000 6000 6000 9-2 RB/280 RX BLDG VENT GAS cpm OSH>1E6 OSH OSH OSH OSH 9-2 RB/280 RX BLDG VENT PART cpm OSH>1 E6 OSH OSH OSH OSH 31 9-10 RB/280 RX BLDG VENT NORTH mR/hr 750 OSH>1 E3 OSH OSH OSH 32 9-10 RB/280 RX BLDG VENT SOUTH mR/hr 750 OSH21E3 OSH OSH OSH 453A 9-10 RB/345 SPENT FUEL POOL WEST mR/hr 100 150 200 190 180 l 4538 9-10 RB/345 SPENT FUEL POOL EAST mR/hr 450 550 600 580 550 9-10 RB/256 MAIN STM LINE A mR/hr 125 120 115 110 105 l 9-10 RB/256 MAIN STM LINE B mR/hr 135 130 125 120 115 9-10 RB/256 MAIN STM LINE C mR/hr 130 125 120 115 110 9-10 RB/256 MAIN STM LINE D mR/hr 120 115 110 105 100 I mR/hr <1 <1 <1
, SJAE(AIR EJECTOR) <1 <1 NOTE: OSH = Off Scale High I
l f
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O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 9.3 IN- PLANT RADIATION LEVELS O
O .
TABLE 9.3-1 RIv. O Rnctor Building, Elev tion 345' P:g39.3-1 ,
(mR/hr unliss otherwise noted)
/
t \ Clock Scenario ARM ARM ARM ARM ARM Zone Zone Zone Zone h Time 08:15 Time 00:00 12 4
14 5
15 15 453 A 3
453B 3 5 1 ll 3
lil 3
IV 3
10 45 02:30 1 1 8 3 3 1 3 3 3 12 20 04:05 20 20 20 20 150 20 80 150 20 12:30 04:15 50 50 50 50 400 50 200 400 50 12:45 04:30 100 100 100 100 450 100 225 450 100 13:00 04:45 150 150 150 150 550 150 275 550 150 j 13:15 05:00 200 200 200 200 600 200 300 600 200 j 13:30 05:15 190 190 190 190 580 190 290 580 190 13:45 05:30 180 180 180 180 550 180 275 550 180 Zone Readings are average throughout zone.
General area contamination levela increase to SK dpm/100 cm2 after 1220.
I r%
'i%) )
REACTOR BUILDING W- N = ELEVATION 345'
.i to'aQ') e OPE ~ _
=
=
l
=
(( '
HATCH - -
MONITORS :
! g- 3 g ae.ci-eaa.
Elev.aor Entrance s,m
\ !. III a_ O C
O,, neacio,emno
~.-A.. won
! k
/M, l ..- .4 0:.:
O P
. O a- .- .
a Fuel Pool West , ,
{ i SperuF W Poon Equipenent Pool i e' Cavity j Spent FuelPool .............
f g ,,, ,, ,,,, i.......................... _ i.
'/ g l 0
{ "N, g !. . . .10. . . . . . . . .
O i
- 5;!
U p l Ac-io unmi.
IV @
Ac.ic iac
' Elev. 55 i i Tool I
I l
TABLE 9.3-2 Rw. 0 ,
Rector Building, El:vition 318' PJga 9.3-2 (mR/hr unless otherwise noted)
- A l
( Clock Scenario ARM ARM ARM Zone Zone Zone Zone Zone Zone Zone Time Time 10 11 16 I 11 111 IV V VI Vil 08:15 00:00 7 4 0.5 7 4 300 4 60 0.5 0.5 10:45 02:30 3 2 0.3 3 2 100 2 60 0.3 0.3 12:20 04:05 20 80 20 20 80 80 90 70 30 20 I 12:30 04:15 50 200 OSH(>1 E2) 50 200 200 300 110 110 80 12:45 04:30 100 260 OSH 100 260 260 390 160 160 120 13:00 04:45 150 340 OSH 150 340 340 510 210 210 150 l
13:15 05:00 200 400 OSH 200 400 400 600 260 260 195 13:30 05:15 190 380 OSH 190 380 380 570 250 250 190 13:45 05:30 180 350 OSH 180 350 350 525 240 240 180 Zone Readings are average throughout zone.
General area contamination levels increase to SK dpm/100 cm2 after 1220.
n U
REACTOR BUILDING
= N= ELEVATION 318' J LJ 'J '"J L. '
- EED . -'
- e. w / (zmEp c:acaemc a f" 5- -
i
, , +Cw. !
[d%
MONITORS 3 g. 'O g ; cuS,E nl ' U I
, ,0 II l J I"a%"a.~ l Iy 21 g n.c e m . . l IIIrj @
.~~c~<*~* _ , = o llgge ,
x w r Cieanup _
a
__i__"__'___"___I_ # I I
Ca3 i
, iA i 1 - "
g a' "-=' ' "em *- s,.oi l soio. e oig nieooi og r
Poui
[
l @
y l I
! _______________'_Ys !i l
[ j \
lk ; t l Coohn0 Water - :-- '
O-'00 8 ' ~
A Surge Tas*
b y7 IEO *bCl V'
h l - ,
e.
='
u r,
I -
r, a e.-
r, cu rl -------@
r ,i r VII r
r TABLE 9.3 3 R;v. O R: actor Building, Elevition 303' P:ge 9.3-3 (mR/hr unless ctherwise noted) l
/O Clock Scenario ARM ARM Zone Zone Zone Zone Zone Zone Zone d Time Time 8 9 1 11 Ill IV V VI Vil 08:15 00:00 4 4 4 3 600 3 60 0.1 02 ,
1 10:45 02:30 1 4 1 3 600 3 60 0.1 02 '
12:20 04:05 40 80 40 80 700 80 40 30 40 t 12:30 04:15 100 200 100 200 800 200 100 80 100 l 12:45 04:30 220 320 220 320 920 320 160 130 220 370 500 370 13:00 04:45 500 1100 500 250 200 370 13:15 05:00 500 600 500 600 1200 600 300 240 500 13:30 05:15 480 580 480 580 1180 580 290 230 480 13:45 05:30 450 550 450 550 1150 550 275 220 450 Zone Readings are average throughout zone.
General area contamination levels increase to 10K dpm/100 cm2 after 1220.
1 I
! ,[%
L) l REACTOR BUILDING N= ELEVATION 303' J u '8 '
DOOOOOV' op a Es O U c= = II ! IV H x p-7
M E ,__ _______,
W _________________N*
' J y
l RWCU Phase urnp A ] SFP HX l MONITORS III l ,Pg g m go,,, c
- l
- ~
3 0 _j p------------------r-----[--
y l $
O, ,levatorErwarce ,
E
~
}, % f I
C .
nosctor sui 6eng A B '
/ l VI 6 Reactor Water cleanup Raccw Purnp / Bottomof Fuel gog g
l I necc,% i
~
l g i \ l
[ . % g k l C
_O _ _ _ _ _ _ _ _ N -____________________.1_____ _ _
v - o f Eh OO CJ VII
, r, rm OOm r, r, e
s TABLE 9.3-4 Arv. O Rrctor Building, Elev1 tion 280' Prge 9.3-4 (mR/hr unless otherwise noted)
Scenario RB Vent N RB Vent S Zone Zone Zone Zone Zone Zone Zone Zone 4 Clock Time Time ARM 6 ARM 31 ARM 32 I ll 111 IV V VI Vil Vill l 08:15 00:00 8 2 2 8 25 8 7 2 2 2 8 l 10:45 02:30 5 0.1 0.1 5 15 5 5 0.1 0.1 0.1 5
{
l 1220 04:05 40 90 90 40 50 60 60 60 90 100 40 l l 12:30 04:15 100 230 230 100 120 150 150 150 225 230 100 l 12:45 04:30 220 750 750 220 240 330 330 330 495 750 220 I l 13:00 04:45 370 OSH>1E3 OSH>1E3 370 390 555 555 555 800 1480 370 l 13:15 05:00 500 OSH OSH 500 520 750 750 750 1350 2500 500 l l 13:30 05:15 480 OSH OSH 480 500 720 720 720 1300 2400 480 l 13:45 05:30 450 OSH OSH 450 470 675 675 675 1200 2400 450 Zone Readings are average throughout Zone. j General area contamination levels increase to 10K dpm/100 cm2 after 1220.
i i
o v
REACTOR BUILDING
= N= ELEVATION 280' a u, uc. m ,u g ggg g u ---
0000 . --> uuuo i o- r s=
00 Mc c="N
,,,,,,_ 00 Pum
@nw"f a-9IV@ n "f @pAssy. l l ,,,,,
1 war 3 4 j [
MONITORS ---
iauWE '
-- ~ ~
Eu J
--- ~
Eui- l ucg.] n n.
III i y 5 o.
O, Ei. valor Erdtara _,---
-- g c
3 OSI<%
- n. _ ,
Exhaust MorWot a
gl 7p-r-7k j Rgen Hs Ban's.3, *' ;-
g g g,g rn p
/ ,
2s w -- - w.
h n.-io,e e.uoi Exhaust MctWar e
d II t f[
< s Ti
'g co ,a
- r, r r.i a
Q~m tsaam ) ./p.,i uon ggg) yg
? , ,
s I _ ,,,co i , va uc s., x, u,,,
y
.i _
r ye - , , N / ""jg g :
l m j 's /a ~
K') , >
g'<A'- - - -
=r; ; ;p((,
- " _'Ml ; [
y == = , ,
l pVIII ,, . . . _
,p ,,-
~
r l
l l
I TABLE 9.3-5 Rev. O Reaciar Buddino. Elevaten 252' Page 9 3-3 (rnR/hr unless othermee noted)
Cloon scenano Astm ARM ARM ARM ARM RM- Zone Zone Zone Zone Zone Zone Zone f
l Time Yerne 2 3 4 5 7 14-29 W
' 4 I IV V VI VB Os 18 00-00 4 0.3 6 520 11 100 5 4 0.3 50 CJ 11 20 I i r 10 46 02.30 0.2 0.2 5 350 4 p 100 8 02 0.2 30 0.2 4 20 11 00 02 45 0.2 0.2 5 200 4 100 5 0.2 0.2 to 0.2 4 10 11:18 03 00 0.2 0.2 5 000 4 100 s 0.2 0.2 to 0.2 4 to 11 30 03 16 0.2 0.2 5 Joo 4 100 5 0.2 of 200 02 4 10 ti et 03 30 0.2 0.2 5 6000 4 100 5 02 0.2 000 OJ 4 10 12-00 03 48 0.2 0.2 6 8000 4 100 $ 02 0.2 soo 0J 4 10 12:16 04 00 0.2 02 6 OSHW1E4) 4 100 6 02 0.2 1500 02 4 to j 12:20 04-06 160 320 160 OSH 200 40 1so iso 320 2000 a00 200 40 l 12:30 0415 400 000 400 OSH $00 100 400 400 a00 2000 2000 600 100 12 40 04.30 620 860 $20 OSH 700 100 620 820 880 2000 2000 700 140 13 00 04 45 670 950 670 OSH 950 100 670 e70 eSo 2000 3500 eso 100 13.15 05 00 800 OSH&1(3) 000 OSH 1200 100 000 soo 2000 2000 5000 1200 240 12 30 0$ 16 750 OSH 750 OSH 1100 100 750 750 1920 2000 de00 1100 220 13 as 05 30 700 OSH 700 OSH 1000 100 700 700 1000 2000 4500 1000 200 Clock $ceneno NORTH " SOUTH " TIP " RMR A"' RHR B"' RClC"' HPCl*"
Time Time RMS 111 RMS IL2 RMS 15 3 OUA0 OUAD QUA0 QUAD 08 15 00 00 <1 <1 <1 6 5 1 1 11 00 02 48 <1 <1 <1 to 60 1 1 12.20 04 05 <1 1 el 50 60 1 2500 12.30 0415 <1 2 41 SO 60 1 6600 1246 04 30 <1 2 <T E ' ~ SO 1 8400 13 00 04 46 41 4 <1 60 50 1 9000 13 15 05.00 <1 5 <1 50 60 1 14000 13 30 06 15 4 41 50 50 13500
_<1 1 13 45 05 30 <1 3 e1 50 SO 1 12500 Zone Rea$ngs are everage throughout Ione.
General area contamination leven increase lo 15K dpm/100 cm2 after 1220.
" RMS ll Reedings et R/hr (%gh-Range Acre 0ent ARMS . IR/hr 1010.000 R/ht)
"* Zone Readngs are evers08 00# 'aise throughout the RHR RCIC and HPCI Quad eievation areas.
(O)
REACTOR BUILDING c N= ELEVATION 252' 7, ,--- -
,eRHR snmm --
! - DW Ante Room i I III O ,"i To AHA A Ouad -------1----* -- ,
MONITORS
(- RHR AVaiveIV 3 RnR,
- Vahre RMS 11 1 (NW Airlock) Room Room
. _ _ _ _ _ _ _ _ _ _ _ .. , p .
Y se Aaeunaica m RMS 112 (SW Alttack) 8 h _,
aMs u.s (Tie noorn ooor) 3
/
/ //
g3:
c E
Reac40r W M i 2 PersonnelBudding Accesa I CRD Chute i - %
g:- ::
g E ,
Or sono souin l sc,em o ce.a.,e vame a i
!D O, nEquipment Railroad Access ,
' w g,,
O, nea
, - On orT4P Withdrawal L --- II 1 l --
Monitor Q \
/w h [h 111 [5\f\
neac Or sudding neactor ,
Personnel Access Hatch r ser ,/ ! O n 0, O, RodDehre Aspair no Co,,,0, E**'** , 'sRT]J)3c'#.:1, l y 30am (Elev. l , g a ea g g o p,R F l VII l O
- g
+ h f
RM I4 nadwaue Han v ). dkr.m----- , g me.am TM g i VI RMS 112 =
s TO RCIC 000 i aau TiP Cao(Mwes i g ~~
l g
1 3 -
g l
, \ teneCl
=
- i 1 , ,
f
]
TABLE 9.3 6 Rw. O Turbine D3ck, Elevation 272' Page 9.3-6 (mR/hr unless otherwise noted)
Clock Scenano ARM Zone Zone Zone Turbine Deck CAM (cpm) 1 Time Time ARM 24 I 11 til NG Particulate j
- 08
- 15 00:00 8 100 150 8 250 900 10:45 02:30 7 80 100 8 250 900 11:30 to END 03:15 7 10 20 7 250 900 Zone Readings are average dose rates throughout zone.
General area contamination levels <1K dpm/100 cm2.
s
- o V
TURBlNE DECK ELEVATION 272' aaa 333 som m. y g Aser
, N ______
CEI3 1 ---c) <r g} <r g n, r !g
- g m
il '
.
- l m
i m ,i b,l
) i c,,,III !D M l l
l
, al 2.
_______________, ._. , m E
4
' E II R l leewi F + + +
e
+ + +
l MONITOR (D -
N =
V r%
Turtnne Steam Wet O
l I
TABLE 9.3-7 Rzy. O Turbina Building Truck Bay, Mak -Up D:mirtrilintion Cond. Pcge 9.3-7 Demineralization Areas. Elevation 252' (mR/hr unless otherwise noted) q J
Clock Scenario RM-14-23A ARM RM 14-36 Zone Zone Zone Zone Time Time (com) 26 (com) l il 111 IV 08:15 00:00 150 0.18 '. 50 0.2 0.2 0.1 0.2 10:45 to END 02:30 150 0.01 150 0.7 0.3 0.2 0.2 Zone Readings are average dose rates throughout zone.
General area contamination levels <1K dpm/100 cm2.
q
]
PRETREATMENT ROOM, BOILER ROOM, TURBINE LOADING BAY, MUDS, DIESELS, COND. DEMIN. HATCH ELEVATION 252' 1 hN -
i i
l = l'NJ U Ul Willilli!g !~
- i Make up Ellllillig li a i l- I l ,,.C = <l i
l
\
1 e
=
a u , ; 1
' - o .
. )
=
--- O , ,
j g aa =
g -c *c'5! l i r ----- ' I j oo ,
6 t=,
r - T-9e @ l l i -
n II
-. i o_.
Q O l [ -l3mr- " *dFi l O d O 9 l 2 l III R- > 2 o
- t m OM a y
l I l = -
Im 9: ,D LI i
l 5 c-----. L-.._.___,. 1
,, cw !
N
- ,u .
'~
MONITORS
' ~~~~~'-
SJAE ROOM p-o 1-
- o -
Ras,osd Track g g i,,,, j
.q RM 14'S g j g ,,,,_, ,
ca Ruws g 0 u
y, 0 i l i------------ ------
ggggg g 1~ .-, - 0 0 GL cm,.. n ,... io. u., ;
O o O o IV -
l t no mo O 3 1
1
F' TABLE 9.3-8 Riv. O Turbina Building Cond. Bry, ElIvrtion 248' Pag 3 9.3-8 (mR/hr unl;ss c.thIrwis3 notid)
Clock l
'-s Scenario ARM ARM Zone Zone Zone Zone Zone Zone !
'! Time Time 20 21 Ill IV V VI Vil Vill 08:15 00:00 2 240 2 2 4 8 240 2 l 10:45 02:30 1 70 1 1 1 1 70 1 I
11:00 02:45 1 350 1 1 1 1 350 1 I 11:15 03:00 1 290 1 1 1 1 290 1 11:30 03:15 1 275 1 1 1 1 275 1
{
11:45 03:20 1 265 1 1 1 1 265 1 12:00 03:45 1 260 1 1 1 1 260 1 12:15 04:00 1 250 1 1 1 1 250 1 l 12:30 04:15 1 245 1 1 1 1 245 1 l 12:45 04:30 1 240 1 1 1 1 240 1 13:00 04:45 1 240 1 1 1 1 240 1 13:15 05:00 1 230 1 1 1 1 230 1 13:30 05:15 1 220 1 1 1 1 220 1 13:45 05:30 1 200 1 1 1 1 200 1 Zone Readings are average dose rates throughout zone.
General area contamination levels <1 K dpm/100 cm2.
I 73 w)
TURBINE BUILDING
= N= ELEVATION 248' dr - m,J W"
W l
_ IV )
O n- ma o Io . ,
y ))D[_
MONITORS i rc =- '
MII l g a- ,. . .o o ,. . .. o l C '
g Q. clung g l l = Steam P i C Turtune Busiding North Personnel Access
)_ ,, J 8 8 8 gI h I g Tsom n.e u.a l @R _J t_
l
~ij -- Mt- g--
m m.~. 4, ,
-sz c=a- c~
i noom g
Y l
- ifl - l rl come,. ,te
- l 4 7@ @f- -
!gi -
III
%t%o. l I v v v vi ::l 00
.- ------------ :<l p ,
lb
, % i , i d t l
l t l t
TABLE 9.3-9 Rsv. O Turbini Building, DImintrrliz: tion /OG Arias, ElIvition 237 pig 3 9.3-9 (mR/hr unless otherwise noted)
'/3 Clock Scenario ARM ARM Zone Zone Zone h Time Time 22 38 l 11 til 08:15 00:00 0.3 75 0.2 0.5 0.2 10:45 02:30 0.1 20 0.1 0.5 0.2 11:00 02:45 0.1 95 0.1 0.5 0.2 11:15 to END 03:00 0.1 <1 0.1 0.5 0.2 Zone Readings are average dose rates throughout zone.
General area contamination levels <1K dpm/100 cm2.
A o l\ ./
TURBINE BUILDING ELEVATION 232' g av Meceever TarAs and Dryers 7 ""La**J," cC] Ia,smif - g@@ O " ed a m., ' ao ~-
MONITORS g 010 p p 5 _ p ,_______________4 u] o o O EaD o -a a -- !O b,, il f~E ""3 M m ;E E i a 0 ea m g a- I l' Ol v ffL g
! a. .
I p .l t
*: 0 l"' g"
_ 5R m 6 1 l @ l i III 6 l_
}l wr F : me
- l. @ riimun mmd-l. fl I -
/^%
l
TABLE 9.3-10 RIv. O Turbina Building Cond. Bry, El;v: tion 222'6' 228'6' PJg3 9,3-10 (mR/hr unless otherwise noted)
- (
G/ Clock Scenario ARM Zone Zone Zone Zone Zone Zone Time Time 13 I il lit IV V VI 08:15 00:00 135 3 1 50 150 2 75 10:45 02:30 1 1 1 30 50 2 55 11:15 to END 03:00 1 1 1 5 15 2 10 Zone Readings are average dose rates throughout zone. General area contamination levels <1 K dpm/100 cm2. l .m V TURBINE BUILDING ELEVATIONS 222' AND 228' l NN = i i l i I 4 i III ' MONITOR cl
.al a .
Illlllllli . I C3 i O e., k_ e]" *** '5:e ~rt~ c l -
@1m.i A'a t 5.,.'"
m I
, ADA ADA O
" g, goc l
l,@"toj D=" n WE c3 ' _ i O
- i. M l- @ l"" E II
]
'-t- '-t- !
i IV l V ? i m _m._..____ J _ C l 1 m e m-ne , vvvv BB ! j l =
- r. I o
i i - - - .. . _ _ _ , El a o El m..i i
< <. - - o l .
9---0 0-------- i____________ I
'1 0
O LP FW mRe > j u;
' ['
8 i I a <, m m. > y c t e Fw ma se o
,bn i
l I
.. i i
.)_
L
1 E-TABLE 9.3-11 Rzv. 0 Torus Arsa (Citwilk and Torus Elzvrtion Arns) Pag:n 9.311 (mR/hr unless otherwise noted) Clock Scenario ARM Zone l9, b Time Time 1 V* I 08:15 00:00 8 8 10:45 02:30 6 6 11:00 02:45 50 50 11:15 03:00 150 150 11:30 03:15 500 500 11:45 03:30 1500 1500 12:00 03:45 2800 2800 12:15 04:00 3000 3000 12:30 04:15 4000 4000 12:45 04:30 7000 7000 13:00 04:45 7500 7500 13:15 05:00 OSH(>1E4) 12000 13:30 05:15 OSH 12000 13:45 05:30 OSH 12000 Zone readings are average dose rates throughout the Torus Catwalk and Torus elevation areas. l l b TORUS CATWALK ) l 4 l l l MONITOR b " l Nw Access Hatch 33 Reactor Budeng OI Suppresson Chariter C Est. Catwak Z
, M
! (D I< Y
<2 d H
SE Access Hatch
>o) v n
I
r ,0 l VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY PREPAREDNESS EXERCISE l 1999 l l l l 9.4 PLANT CHEMISTRY DATA l SECTION i 9.4.1 Reactor Coolant Data 9.4.2 Primary Containment Data 9.4.3 Reactor Building Data l l \ l ! l D .
p L R:V0 Page 9.4.1 1 I p VERMONT YANKEE NUCLEAR POWER STATION V EMERGENCY PREPAREDNESS EXERCISE l 1999 l 9.4.1 REACTOR COOLANT DATA A. Reactor Coolant Activity Concentrations (uCi/ml) Isotope Prior to 1035 1035 -1045 1045 -1100 1100-1115 1115 -1130 1130-1200 1200 - End 1-131 3.5E-04 6.4E-03 4.7E-02 5.6E-01 6.9E+00 8.0E+01 2.7E+02 1-132 2.8E-04 7.2E-03 5.4E-02 6.4E-01 7.8E+00 9.2E+01 2.9E+02 1-133 5.2E-04 4.2E-02 1.1 E-01 1.2E+00 1.4E+01 1.7E+02 5.2E+02 1-134 4.1 E-04 9.8E-03 6.5E-02 6.6E-01 7.2E+00 7.8E+01 2.6E+02 l-135 4.5E-04 1.2E-02 8.4E-02 1.0E-01 1.2E+01 1.4E+02 4.5E+02 l Totallodine 2.0E-03 7.7E-02 3.6E-01 3.2E+00 4.8E+01 5.6E+02 1.8E+03 1-131 D.E. 5.5E-04 1.9E-02 8.5E-02 9.3E-01 1.2E+01 1.4E+02 4.6E+02 Kr-83m 1.2E-03 3.6E-03 2.7E-02 3.7E-01 5.0E+00 6.7E+01 2.3E+02 Kr-85m 2.5E-02 6.0E-02 3.1 E-01 2.5E+00 2.1 E+01 1.7E+02 4.4E+02 Kr-85 4.8E-03 1.1 E-02 4.5E-02 2.8E-01 1.7E+00 1.1 E+01 2.4E+01 i i Kr-87 2.9E-03 8.5E-03 6.8E-02 9.0E-01 1.2E+01 1.7E+02 5.4E+02 Kr-88 1.0E-03 3.6E-03 3.7E-02 7.2E-01 1.4E+01 2.7E+02 1.0E+03 Xe-131m 9.1 E-05 2.6E-04 2.0E-03 2.5E-02 3.3E-01 4.2E+00 1.4E+01 Xe-133m 7.3E-04 2.1 E-03 1.7E-02 2.2E-01 2.8E+00 3.6E+01 1.3E+02 Xe-133 ' 5.3E-03 1.3E-02 9.5E-02 1.1 E+00 1.3E+01 1.4E+02 4.3E+02 Xe-135m 5.8E-03 1.6E-02 1.1 E-01 1.4E+00 1.6E+01 1.9E+02 5.9E+02 Xe-135 2.2E-03 6.6E-03 6.4E-02 1.1 E+00 1.8E+01 3.0E+02 1.2E+03 Total Gas 4.9E-02 1.2E-01 7.7E-01 8.5E+00 1.0E+02 1.3E+03 4.6E+03 i O
Rsv 0 Page 9.4.12 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 9.4.1 Bg6CTOR COOLANT DATA B. Reactor Coolant Gas Sample Dose Rates Unshielded 73p Shielded (1 inch lead) (mR/hr per cc)* NM (mR/hr per cc)* Time Contact 1 ft $s4 Contact 1 ft Prior to 1035 1.4E-02 9.8E-05 9sSd 1.7E-04 1.2E-06 1035-1045 3.6F-02 2.5E-04 %hti 4.4E-04 3.1 E-06 1045-1100 2.3E-01 1.5E-03 !MM 2.7E-03 1.9E-05 1100 -1115 2.5E+00 1.7E-02 Mi@ 3.0E-02 2.1 E-04 1115 -1130 3.0E+01 2.1 E-01 P7M 3.7E-01 2.6E-03 1130-1200 3.9E+02 2.7E+00 hd 4.8E+00 3.4E-02 1200 - End 1.3E+03 9.2E+00 &&S 1.6E+01 1.2E-01 O
- Values must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rate in mR/hr.
?
O
r, R:v 0 Page 9.4.13 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXF.RCISE 1999 9.4.1 REACTOR COOLANT DATA C. Reactor Coolant Liquid (lodine) Sample Dose Rates Unshielded $ id Shielded (1 inch lead)
~
(mR/hr per cc)* 3%M (mR/hr per cc)* Time Contact 1 ft "sfts! Contact 1 ft Prior to 1035 1.6E-03 1.1 E-05 ?sM 2.0E-05 1.3E-07 1035 -1045 6.0E-02 4.2E-04 Ed4 7.5E-04 5.1 E-06 1045 -1100 2.8E-01 1.9E-03 RGN 3.5E-03 2.3E-05 1100 -1115 2.5E+00 1.7E-02 (ss$ 3.1 E-02 2.1 E-04 1115 -1130 3.7E+01 2.6E-01 @:M{#i 4.7E-01 3.2E-03 1130-1200 4.4E+02 3.0E+00 R@ 5.5E+00 3.7E-02 1200 - End 1.4E+03 9.7E+00 N#5 1.7E+01 1.2E-01
- Values must be multiplied by the sample volume in milliliters to obtain the sample dose rate in mR/hr.
i l O l l l
r: l ! Rsv 0 Page 9.4.21 ,V O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 9.4.2 PRIMARY CONTAINMENT DATA A. Primary Containment Air Concentrations (uCi/cc) Isotope Prior to 1050 1050-1100 1100 -1115 1115 1130 1130 -1200 1200 - End 1-131 2.0E-11 1.9E-06 2.3E-05 2.0E-04 3.4E-03 1.4E-02 1-132 1.6E-11 2.2E-06 2.7E-05 3.3E-04 3.9E-03 1.5E-02 1-133 3.8E 11 4.6E-06 5.1 E-05 5.9E 04 7.1 E-03 2.7E-02 1-134 8.8E-12 2.6E-06 2.8E-05 3.0E-04 3.3E-03 1.3E-02 1-135 3.0E-11 3.4E-06 7.2E-06 4.7E-04 5.8E-03 2.3E-02 Totallodine 1.1 E-10 1.5E-05 1.4E-04 2.0E-03 2.3E-02 9.2E-02 1131 D.E. 3.3E-11 3.5E-06 3.9E-05 5.0E-04 6.0E-03 2.4E-02 O KR-83M 5.1 E-07 4.3E-06 6.1 E-05 8.3E-04 1.1 E-02 4.6E-02 v KR-85M 1.6E-07 5.1 E-05 4.3E-04 3.7E-03 3.0E-02 9.8E-02 KR-85 1.0E-08 7.4 E-06 5.0E-05 3.1 E-04 1.9E-03 5.7E-03 KR-87 1.3E-07 1.1 E-05 1.5E-04 2.0E-03 2.7E-02 1.1 E-01 KR-88 3.3E-07 5.9E-06 1.2E-04 2.3E-03 4.4E-02 2.0E-01 XE-131M 0.0E+00 3.2E 07 4.2E-06 5.5E-05 7.0E-04 2.8E-03 i XE-133M 5.2E-08 2.6E-06 3.6E-05 4.7E 04 6.0E-03 2.5E-02 l XE-133 1.8E-07 1.5E-05 1.8E-04 2.1 E-03 2.4E-02 9.0E-02 XE-135M 2.1 E-07 1.8E-05 2.2E-04 2.7E-03 3.1 E-02 1.2E-01 XE-135 5.5E-07 1.0E-05 1.8E-04 2.9E-03 4.9E-02 2.3E-01 XE-138 0.0E+00 1.0E-05 1.1E 04 2.6E-03 1.2E-02 4.0E-02 j Total Gas 2.1E-06 1.3E-04 1.4E-03 1.7E-02 2.2E-01 9.3E-01 l l l I
\
l
Rsv 0 Page 9.4.2 2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 9.4.2 PRIMARY CONTAINMENT DATA B. Primary Containment Sample Dose Rates Unshielded Shielded (1 inch lead) (mR/hr per cc)* (mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 1050 6.1 E-07 4.3E-09 W.'!( 7.6E-09 5.3E-11 1050 -1100 3.6E-05 2.5E-07 FW1 4.5E-07 3.1 E-09 1100 -1115 4.1 E-04 2.9E-06 WR 5.1 E-06 3.6E-08 1115 -1130 5.0E-03 3.5E-05 Digli 6.1 E-05 4.3E-07 1130 -1200 6.5E-02 4.5E-04 E$d 8.0E-04 - 5.6E-06 1200 - End 2.7E-01 1.9E-03 FMd 3.3E-03 2.3E-05 O
- Values must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rate in mR/hr.
O .
p Rev.0
- s Page 9.4.3-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 9.4.3 REACTOR BUILDING DATA A. Rdactor Buildina Air Concentrations in uCi/cc Elevations 213' and 232'- See Notes Below i
isotope Pnor to 1220 1220-1230 1230-1245 1245 1300 1300 - 1320 1320 -1330 1330 to END l131
- 8.40E-03 1.90E-02 2.50E-02 2.70E-02 2.40E-02 2.20E-02 1132 9.10E-03 2.10E-02 2.70E-02 2.90E-02 2.60E-02 2.30E-02 1133 1.60E-02 3.80E-02 4.90E-02 5.20E-02 4.70E-02 4.20E-02 1-134 8.20E-03 1.90E-02 2.40E-02 2.60E-02 2.30E-02 2.10E-02 1135 1.40E-02 3.30E-02 4.20E-02 4.50E-02 4.00E-02 3.60E-02 Totallodine
- 5.6E-02 1.3E-01 1.7E-01 1.8E-01 1.6E-01 1.4E-01 Kr-83m 2.8E-02 6.6E-02 7.2E-02 6.9E-02 6.2E-02 5.6E-02 Kr-85m 5.6E-02 1.3E-01 1.4E-01 1.3E-01 1.2E-01 1.1 E-01 Kr-85 3.1 E-03 7.1 E-02 7.8E-02 7.4E-03 6.6E-03 6.0E-03 Kr-87 6.8E-02 1.6E-01 1.7E-01 1.6E-01 1.5E-01 1.3E-01 O
Kr-88 1.3E-01 3.0E-01 3.3E-01 3.1 E-01 2.8E-01 2.5E-01 Xe-131m 1.7E-03 4.0E-03 4.4E-03 4.2E-02 3.8E-03 3.4E-03 Xe 133m 1.6E-02 3.7E-02 4.1 E-02 3.9E-02 3.5E-02 3.1 E-02 Xe-133 5.5E-02 1.3E-01 1.4E-01 1.3E-01 1.2E-01 1.1 E-01 Xe-135m 7.5E-02 1.7E-01 1.9E-01 1.8E-01 1.6E-01 1.5E-01 Xe 135 1.5E-01 3.4E-01 3.7E-01 3.5E-01 3.2E-01 2.9E-01 Xe-138 2.3E-02 5.2E-02 5.7E-02 5.5E-02 4.9E-02 4.4E-02 Total Noble Gas 6.1 E-01 1.5E+00 1.6E+00 1.5E+00 1.3E+00 1.2E+00 l Notes: l
- 1. (*) Denotes Activity Concentrations below MDL J
- 2. Reactor Building Elevation 252 -divide values by a factor of 3
- 3. Reactor Building Elevations 280' and 303'- divide values by a factor of 7
- 4. Reactor Building Elevations 318' and 345'-divide values by a factor of 13 1
4 i l Rev.O Page 9.4.3-2 g VERMONT YANKEE NUCLEAR POWER STATION j g EMERGENCY PREPAREDNESS EXERCISE 1999 l 9.4.3 REACTOR BUILDING DATA (continued)
- 8. Reactor Buildina Air Concentrations in DAC-hr i Elevations 213' and 232 - See Notes Below l Time lodine Noble Gas Prior to 1220 Not Applicable Not At .iicable 1220-1230 6.0E+05 1.10 +05 1230-1245 1.4E+06 2.6E+05 1245-1300 1.8E+06 2.8E+05 1300 -1320 1.9E+06 2.6E+05 1320-1330 1.7E+06 2.4E+05 l 1330 to END 1.6E+06 2.1 E+05 C. Reactor Buildina Air Concentrations in eauivalent inhalation dose rate (mrem /hr)
Elevation 213' and 232' - See Notes Below Time lodine Noble Gas , Prior to 1220 Not Applicable Not Applicable 1220-1230 1.5E+06 2.8E+05 1230-1245 3.5E+06 6.4E+05 1245-1300 4.5E+06 7.0E+05 1300-1320 4.9E+06 6.6E+05 1320-1330 4.3E+06 6.0E+05 1330 to END 4.0E+06 5.4E+05 D. Reactor Buildina Air Samole Dose Rates (lodine Cartridae Ontv) Elevation 213' and 232' - See Notes Belon Unshielded Shielded (mR/hr per cc)* (1 in. lead in mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 1220 As Read As Read 4 As Read As Read 1220-1230 4.3E-02 3.0E-04 . M 5.4E-04 3.8E-06 1230-1245 1.0E-01 7.0E-04 -N 1.3E-03 8.8E-06 1245-1300 1.3E-01 9.0E-04 m x 1.6E-03 1.1 E-05 1300-1320 1.4E-01 9.6E-04 '" 1.7E-03 1.2E-05 1320-1330 1.2E-01 8.6E-04 m- P 1.6E-03 1.1 E-05 i 1330 to END 1.1 E-01 7.7E-04 r '- 1.4E-03 9.7E-06 1315 to END 1.1 E-01 7.7E-04 24 1.4E-03 9.7E-06
- Values must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rate in mR/hr. i
- Notes
- )
- 1. Reactor Building Elevation 252'- divide values by a factor of 3 i
- 2. Reactor Building Elevations 280' and 303'- divide values by a factor of 7
- 3. Reactor Building Elevations 318' and 345'-divide values by a factor of 13
m O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 9.5 PLANT VENT STACK DATA O l O
I Rtv 0 Pag 3 9.5.-1 7s VERMONT YANKEE NUCLEAR POWER STATION ; ('") EMERGENCY PREPAREDNESS EXERCISE 1999 l 9.5 E[, ANT VENT STACK DATA A. Plant Vent Stack Activity Concentratkns (uCl/m)* i Isotope Prior to 1220 1220-1230 1230 -1245 1245 -1300 1300-1320 1320-1330 1330 to END ' l131 3.3E-13 1.1 E-07 2.8E-07 4.1 E-07 5.1 E-07 4.8E-07 4.4E-07 l132 S.3E-13 1.1 E-07 3.0E-07 4.5E-07 5.5E-07 5.2E-07 4.7E-07 l-133 3.3E 13 2.0E-07 5.4 E-07 8.0E-07 9.9E-07 9.4 E-07 8.5E-07 j l-134 3.3E-13 1.0E-07 2.7E-07 4.0E-07 5.0E-07 4.7E-07 4.2E-07 l l-135 3.3E-13 1.8E-07 4.7E-07 6.9E 07 8.6E-07 8.1 E-07 7.3E-07 Total lodine 1.7E-12 7.0E-07 1.9E-06 2.8E-06 3.4E-06 3.2E-06 2.9 E-06 l 131 D.E. 4.6E 13 1.8E-07 4.8E-07 7_1 E-07 8.8E-07 8.3E-07 7.5E-07 Kr-83m 3.5E-04 9.4 E-04 1.3E-03 1.5E-03 1.4E-03 1.3E-03 O Kr-85m " 7.0E-04 1.8E-03 2.5E-03 2.9E-03 2.8 E-03 2.5E-03 Kr-85 3.8E-05 1.0E-04 1.4 E-04 1.6E-04 1.5 E-04 1.4 E-04 Kr-87 8.5E-04 2.3E-03 3.0E-03 3.5E-03 3.4 E-03 3.0E-03 Kr-88 1.6E-03 4.3E-03 5.8E-03 6.7E-03 6.4 E-03 5.8E-03 Xe-131m 2.2E-05 5.8E-05 7.8E-05 9.0E-05 8.6E-05 7.7E-05 Xe-133m 2.0E-04 5.3E 04 7.1 E-04 8.3E-04 7.9E-04 7.1 E-04 Xe 133 6.8E-04 1.8E-03 2.4 E-03 2.8E-03 2.7E-03 2.4E 03 Xe-135m 9.3E-04 2.5E-03 3.3E-03 3.9E-03 3.7E-03 3.3E-03 Xe-135 1.8E 03 4.9E-03 6.6E-03 7.7E-03 7.3E-03 6.6E-03 I Xe-138 2.8E-04 7.5E-04 1.0E-03 1.2E-03 1.1 E-03 1.0E-03 _ Total Gas 7.5E-03 2.0E-02 2.7E-02 3.1 E-02 3.0E-02 2.7E-02
- To convert con :entration (uCi/cc) to release rate (uCi/sec) multiply by the assumed stack flow rate of 3.5E+07 cc/sec.
" indicates actMty concentration below MDL
f Rev.0 Page 9.5-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 9.5 PLANT VENT STACK DATA B. PVS Gas sample Dose Rates (Grab Sample) Unshielded Shielded (1 inch lead) (mR/hr per cc)* (mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 1220 As Read As Read As Read As Read 1C20 - 1230 2.1 E-03 1.5E-05 2.6E-05 1.9E-07 1230 -1245 5.7E-03 4.0E-05 . < 7.0E-05 5.0E-07 1245 -1300 7.7E-03 5.4 E-05 P 9.5E-05 6.8E-07 1300 -1320 9.0E-03 t).3E-05 %9 1.1 E-04 8.0E-07 1320-1330 8.5E-03 5.9E-05 2" 4 1.0E-04 7.5E-07 1330 to END 7.6E-03 5.3E-05 h D 9.4E-05 6.7E-07 p C. PVS Air Sample Dose Rates (lodine Cartridge) V Unshielded Shielded (1 inch lead) (mR/hr per cc)* (mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 1220 As Read As Read 5: 'a As Read As Read 1220 -1230 5.4 E-07 3.8E-09 M 6.8E-09 4.8E-11 1230-1245 1.4E-06 9.8E-09 % -M 1.8E-08 1.2E-10 1245 -1300 2.1 E-06 1.5 E-08 C4 ' 2.6E-08 1.8E-10 1300 -1320 2.6E-06 1.8E-08 F: 4 3.3E-08 2.3E-10 1320-1330 2.5E-06 1.7E-08 - 3.1 E-08 2.2E-10 1330 to END 2.2E-06 1.5E-08 , 2.8E-08 1.9E-10 D. General Area Exposure Rates at Stack (mR/hr) Time At Stack Door inside Prior to 1220 As Read v v As Read 1220 -1230 1 . '4~ 4
~
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~ b 10 1245 -1300 4 4 ^ s ;C -
- 12 1300 -1320 5 .
15 1320-1330 5 ' 12 m 1330 to END 4 10 i
- Values must be multiplied by the sample volume in cubic centimeters to obtain the sarnple dose rates in mR/hr.
i O . VERMONT YANKEE NUCLEAR POWER STATION . EMERGENCY PREPAREDNESS EXERCISE 1999 9.6 FIELD MONITORING MAPS AND DATA O O
l l l Rev. 0 Q , Page 9.6-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE l 1999
)i L 1 FIELD HONITORING MAPS AMD DATA Plume gamma dose rates and radioiodine concentrations have been estimated as a function of time and distance from the plant site using a variable trajectory dose assessment model (METPAC). Geographical representations of 1
the plume are provided in this section for each 15 minute average of the meteorological conditions, starting at clock time 1230 (scenario time 04:15).
]
During the exercise, controllers will use the information contained in this section to provide field monitoring teams with the appropriate survey results and radiological data for various times and locations. The designated field monitoring teams will be directed to monitor and track the plume relative to the meteorological conditions postulated for the scenario. Figures 9.6-1 through 9.6-8 depict the plume location at various times throughout the scenario. These figures represent a plume width that is equivalent to a 3-sigma value of the centerline icnditions. Since the figures show a plume width relative to the centerline, survey results were calculated for various color-coded map areas (blue, yellow, and green). Field data tables have been developed for Vermont Yankee, State of Vermont,
, State of New Hampshire and Commonwealth of Massachusetts field monitoring teams. The tables contained the radiological data to be provided to the field monitoring teams for various times and locations. (The tables follow l
the figure for a given scenario time period.) Radiological data era the tables, have been provided for each plume segment and ! colored map area shown on the associated figures. Radiological data for locations between two plume segments can be estimated by interpolating between the values for those segments. .
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I i [ Rev. 0
, Pe.ge 9.6-2 Before the exercise, training will be provided to Controllers on the use of the figures and tables. The Controllers should use the following specific instructions:
- 1. As field monitoring teams are designated, check that team members follow the appropriate procedures. This will include the initial equipment check.
- 2. While traveling to assign monitoring locations, or while traversing the plume, or at assigned monitoring locations, use the attached figures and tables to issue appropriate radiological data.
- 3. Attempt to estimate the team's accrued radiation exposure as a function of time spent in an affected area. Use the values provided for the PIC-6 or the closed window, waist level reading for the gamma dose rate. L9 not issue pocket dosimeter results to team members, unless. they actually '
simulate checking their dosimeter reading. The pocket dosimeters have specific ranges and intervals in mR or R values. Ask them the ranges
-associated with the pocket dosimeter utilized. Attempt to provide values that reflect. the -team's_ accrued exposure and range of the pocket dosimeter.
- 4. Ask the field monitoring teams what equipment they have available for I 1
their use. Ask them the scales. associated with the equipment; log the i answers to ensure that you do not provide them with data that is not i consistent with the range of the equipment. If a situation occurs where i
.the lower range or upper range of the equipment is exceeded, issue them i an "off-scale low" value and "off-scale high= value, respectively. '
l l-l l I
Rev. 0 Page 9.6-3
- 5. For gamma (dose rates) survey readings taken by field monitoring teams, i
the following info Tation should be use: I
- a. If an P.M-14/HP-210 is used to track the plume, the meter count rate of 3,500 cpm on the RM-14/EP-210 is equivalent to approximately 1.0 i I
mR/hr. Therefore, 14 mR/hr will cause the RM-14/HP-210 to read '
'off-scale'high." .The upper range of the RM-14/HP-210 is 50,000 cpm.
- b. Whenever a team takes a aground level" survey, the results should j be the same as the " waist level" survey.
- c. Some field monitoring teams may take open window and closed window readings with their dose rate survey meters. If a team is lecated in h .
j the plume'and hir concentration is greater than zero, assume the open window reading is two times the closed window reading for the gamma dose rate reading.
- 6. For air sample measurements taken by field monitoring teams, the following information should be use:
- a. The field monitoring teams will substitute a charcoal cartridge instead of the absorber media cartridge (silver zeolite) contained in the field monitoring kits. All air sample data will be given as though the absorber media cartridges (silver zeolite) were being used in the kits.
- b. An . assumed air sample volume has been .used to calculate the net count rates for the air sample results. The sample volume was assumed to be 10-cubic foot (283 liters) for Vermont Yankee; 354 liters for State of Vermont; 10-cubic foot (283 liters) for State of.New Hampshire and 20-cubic foot (566 liters) for Massachusetts field monitoring teams. If
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different volumes are collected, the air sample data provided in the tables should be adjusted proportionally.
I i ( l l l l (m Rev. 0 Page 9.6-4 l
- c. Air sample net count rates for the adsorber media cartridges (silver zeolite) provided in the field data tables have been developed using
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Conc.(uCi/cc)= "* ExFxT METPAC thyroid dose rate projections. The formula used is as follows: where: E= Instrument Detector Efficiency in cpm /dpm (counts per 1 l disintegration) F= Flow rate of sample in Ipm or cfm 4 { T= Sample collection time in minutes l i CF = Ccnversion Factor (4.5 E-10 yCi-liter /dpm-cc for flow rate in lpm ga 1.6 E-ll 4CI-f t'/dpm-cc for flow rate in cfm l
- d. For air sample net count rate for the particulate filter paper, it is assumed that a G-M survey meter is used to obtain the sample count rates. Filter count rates (cpm) were estimated frc'm the radiciodine air concentration for the respective standard air sample volume taken.
NOTE: THE PLUME PLOT FIGURES ARE GRAPHIC REPRESENTATIVES OF ATMOSPHERIC DISPERSION, LARGER FIGURES WILL BE AVAILABLE TO SITE AND OFF-SITE MONITORING CONTROLLERS FOR THEIR USE ON PROVIDING DATA TO FIELD MONITORING TEAMS. l t j
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TABLE 9.6.1 Rev. O Prge 9.6-Sa ON SITE VERMONT YANKEE FIELD DATA AIR SAMPLE DATA * (RM-14)" <rm GAMMA DOSE RATE RADECO/HV-1BC PARTICULATE l CONC. 10 CF FILTER"' CLOCK MAP PIC-6 RM-14 l-131 SILVER ZEOLITE TIME AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) 123dT245 BLUE <1 1054 0.00E+00 <40 <40 YELLOW <1 AS READ 0.00E+00 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 1245-1300 BLUE <1 3262 0.00E+00 <40 440 YELLOW <1 326 0.00E+00 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 1300-1315 BLUE 1 3815 0.00E+00 <40 <40 YELLOW <1 382 0.00E+00 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 1315-1330 BLUE 1 4340 0.00E+00 <40 <40 YELLOW <1 434 0.00E+00 <40 <40 GREEN <1 AS READ 0.00E400 <40 <40 1330-1345 BLUE 1 4095 0.00E+00 <40 <40 [ \ YELLOW <1 410 0.00E+00 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 1345-1400 BLUE 1 3885 0.00E+00 <40 <40 YELLOW <1 389 0.00E+00 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 J 1400-1415 BLUE 1 3570 0.00E+00 <40 <40 YELLOW <1 357 0.00E+00 <40 <40 GREEN <1 30 0.00E+00 <40 <40 i NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, divide the value given in the table by two (2) and provide the resulting value to the players. ( (Dj " The RM-14 detector efficiency for 1 131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge.
"* The particulate filter sample count rate (cpm) was estimated from the I-131 air concentrations for a 10 cubic fee L
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TABLE 9.6.23 Riv. O P:ge 9.6-63 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1230-1245 (SCENARIO TIME 0415-0430) AIR SAMPLE DATA * (RM-14)" GAMMA DOSE RATE RADECO/HV-1BC PARTICULATE PLUME CONC. 10 CF FILTER *" SEGMENT DISTANCE MAP PIC-6 RM 14 1-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/ce) (NET CPM) (NET CPM) 1.00 SITE BLUE <1 1250 0.00E+00 <40 <40 BOUNDARY YELLOW <1 125 0.00E+00 <40 <40 GREEN <1 12 0.00E+00 <40 <40 2.00 0.70 BLUE 1 3570 4.29E-10 <40 <40 YELLOW <1 357 4.29E 11 <40 <40 GREEN <1 36 4.29E-12 <40 <40 3.00 1.40 BLUE <1 2769 8.31E-10 <40 <40 YELLOW <1 277 8.31 E-11 <40 <40 GREEN <1 28 8.31 E-12 <40 <40 NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, divide the value given in the table by two (2) and provide the resulting value to the players. ( s ** The RM-14 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge. The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 10 cubic feet s
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TABLE 9.6.3a R:v.O PIge 9.6-7e VERMONT YANKEE FIELD DATA AT CLOCK TIME 1245-1300 (SCENARIO TIME 0430-0445) AIR SAMPLE DATA' (RM-14)" GAMMA DOSE RATE RADECO/HV-1BC PARTICULATE i PLUME CONC. 10 CF FILTER"' SEGMENT DISTANCE MAP PIC-6 RM-14 l131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1 3745 0.00E+00 <40 <40 BOUNDARY YELLOW <1 375 0.00E+00 <40 <40 GREEN <1 37 0.00E+00 <40 <40 l 2.00 0.50 BLUE 3 11480 4.85E-10 <40 <40 YELLOW <1 1148 4.65E 11 <40 <40 1 GREEN <1 115 4.85E-12 <40 <40 3.00 1.10 BLUE 3 10920 3.70E-09 <40 <40 YELLOW <1 1092 3.70E-10 <40 <40 GREEN <1 109 3.70E-11 <40 <40 4.00 1.80 BLUE <1 1862 3.49E-10 <40 <40 YELLOW <1 186 3.49E-11 <40 <40 O GREEN <1 19 3.49E-12 <40 <40 5.00 2.40 BLUE <1 1428 3.08E-10 <40 <40 YELLOW <1 143 3.08E 11 <40 <40 GREEN <1 14 3.08E-12 <40 <40 l l l NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally, For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, divide the value given in the table by two (2) and provide the resulting value to the players. The RM 14 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge. r]j *" The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 10 cubic feet s L
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i I TABLE 9.6.4a R tv. O Pcge 9.6-83 l VERMONT YANKEE FIELD DATA AT CLOCK TIME 1300-1315 (SCENARIO TIME 0445-0500) l lh./ s AIR SAMPLE DATA * (RM-14)" l GAMMA DOSE RATE RADECO/HV-1BC PARTICULATE PLUME CONC. 10 CF FILTER"' l l SEGMENT DISTANCE MAP PIC-6 RM-14 l-131 SILVER ZEOLITE l l NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1 4305 0.00E+00 <40 <40 BOUNDARY YELLOW <1 431 0.00E+00 <40 <40 GREEN <1 43 0.00E+00 <40 <40 2.00 1.00 BLUE 3 10780 1.62E-09 <40 <40 YELLOW <1 1078 1.62E 10 <40 <40 I GREEN <1 108 1.62E-11 <40 <40 l 3.00 1.50 BLUE 2 7140 1.28E-09 <40 <40 YELLOW <1 714 1.28E-10 <40 <40 I GREEN <1 71 1.28E-11 <40 <40 4.00 2.10 BLUE 2 5250 1.18E-09 <40 <40 YELLOW <1 525 1.18E 10 <40 <40 ! GREEN <1 53 1.18E-11 <40 <40 L) 5.00 2.80 BLUE <1 1162 2.02E 10 <40 <40 I YELLOW <1 116 2.02E-11 <40 <40 GREEN <1 12 2.02E 12 <40 <40 6.00 3.40 BLUE <1 942 1.70E-10 <40 <40 l YELLOW <1 94 1.70E-11 <40 <40 1 GREEN <1 9 1.70E-12 <40 <40 NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, l divide the value given in the table by two (2) and provide the resulting value to the players. fg ** The RM 14 detector efficiency for I 131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge. The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 10 cubic feet s I I
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m 1 TABLE 9.6.5a RIv. O Pege 9.6-921 VERMONT YANKEE FIELO DATA AT CLOCK TIME 1315-1330 (SCENARIO TIM 6 0500-0515) AIR SAMPLE DATA * (RM-14)" GAMMA DOSE RATE RADECO/HV 1BC PARTICULATE PLUME CONC. 10 CF FILTER *" SEGMENT DISTANCE MAP PIC-6 RM-14 l-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1 4935 0.00E+00 <40 <40 BOUNDARY YELLOW <1 494 0.00E+00 <40 <40 GREEN <1 49 0.00E+00 <40 <40 2.00 0.50 BLUE 4 15155 6.74E-10 <40 <40 YELLOW <1 1516 6.74E-11 <40 <40 GREEN <1 152 6.74E-12 <40 <40 3.00 1.00 BLUE 5 17850 7.43E-09 93 42 YELLOW <1 1785 7.43E 10 <40 <40 GREEN <1 179 7.43E-11 <40 <40 4.00 2.00 BLUE 2 6405 1.39E-09 <40 <40 YELLOW <1 641 1.39E-10 <40 <40 GREEN <1 64 1.39E 11 <40 <40 ( 5.00 2.60 BLUE 1 4270 7.37E-10 <40 <40 YELLOW <1 427 7.37E-11 <40 <40 GREEN <1 43 7.37E 12 <40 <40 6.00 3.10 BLUE <1 3217 5.86E-10 <40 <40 YELLOW <1 322 5.86E 11 <40 <40 GREEN <1 32 5.86E-12 <40 <40 7.00 3.80 BLUE <1 802 1.28E-10 <40 <40 YELLOW <1 80 1.28E-11 <40 <40 GREEN <1 8 1.28E-12 <40 <40 NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, divide the value given in the table by two (2) and provide the resulting value to the players. s The RM-14 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge.
/ \ \.~ ) *" The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 10 cubic feet s
r-TABLE 9.6.Sa Riv.O PIge 9.6-9a2 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1315-1330 (SCENARIO TIME 0500-0515) l O ( AIR SAMPLE DATA * (RM-14)" GAMMA DOSE RATE RADECO/HV-1BC PARTICULATE PLUME CONC. 10 CF FILTER *" , SEGMENT DISTANCE MAP PIC-6 RM-14 1131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) 8.00 4.50 BLUE <1 672 1.07E 10 <40 <40 i YELLOW <1 67 1.07E 11 <40 <40 GREEN <1 7 1.07E-12 <40 <40 V I 1 NOTES: l Air sample data are based on a sample volume of 10 cubic feet for the air sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, l divide the value given in the table by two (2) and provide the resulting value to the players. l l The RM-14 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge. The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 10 cubic feet s I I i
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TABLE 9.6.6a Rry. O Pige 9.6-10a1 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1330-1345 (SCENARIO TIME 0515-0530) AIR SAMPLE DATA * (RM-14)" GAMMA DOSE RATE RADECO/HV 1BC PARTICULATE PLUME CONC. 10 CF FILTER"* SEGMENT DISTANCE MAP PIC-6 RM 14 l-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCl/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1 4655 0.00E+00 <40 <40 BOUNDARY YELLOW <1 466 0.00E+00 <40 <40 GREEN <1 47 0.00E+00 <40 <40 2.00 0.50 BLUE 4 14280 5.35E-10 <40 <40 YELLOW <1 1428 5.35E-11 <40 <40 GREEN <1 143 5.35E-12 <40 <40 3.00 1.00 BLUE 5 16800 7.08E-09 88 40 YELLOW <1 1680 7.08E-10 <40 <40 GREEN <1 168 7.08E 11 <40 <40 4.00 1.50 BLUE 3 9555 2.07E-09 <40 <40 YELLOW <1 956 2.07E 10 <40 <40 GREEN <1 96 2.07E-11 <40 <40 4 5.00 2.10 BLUE 2 8330 2.30E-09 <40 <40 YELLOW <1 833 2.30E-10 <40 <40 GREEN <1 83 2.30E 11 <40 <40 6.00 3.10 BLUE 1 4165 8.54E-10 <40 <40 YELLOW <1 417 8.54E-11 <40 <40 GREEN <1 42 8.54E-12 <40 <40 7.00 3.60 BLUE <1 2923 4.71E 10 <40 <40 YELLOW <1 292 4.71 E-11 <40 <40 GREEN <1 29 4.71 E-12 <40 <40 NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cubic feet sample was collected instead of 10 cubic feet,
- divide the value given in the table by two (2) and provide the resulting value to the players.
l The RM 14 detector efficiency for I 131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge, kj "* f The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 10 cubic feet s j i l l
.]
TABLE 9.6.6a Riv. O Pige 9.6-10a2 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1330-1345 (SCENARIO TIME 0515-0530) l ' / l Q AIR SAMPLE DATA * (RM-14)" GAMMA DOSE RATE RADECO/HV-1BC PARTICULATE PLUME CONC. 10 CF FILTER"* SEGMENT DISTANCE MAP PIC-6 RM-14 l-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) 8.00 4.10 BLUE <1 2254 3.57E-10 <40 <40 YELLOW <1 225 3.57E 11 <40 <40 GREEN <1 23 3.57E 12 <40 <40 9.00 4.80 BLUE <1 599 8.92E-11 <40 <40 YELLOW <1 60 8.92E 12 <40 <40 GREEN <1 6 8.92E-13 <40 <40 10.00 5.50 BLUE <1 515 7.43E 11 <40 <40 YELLOW <1 51 7.43E-12 <40 <40 GREEN <1 5 7.43E 13 <40 <40 NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example,if a 5 cubic feet sample was collected instead of 10 cubic feet, divide the value given in the table by two (2) and provide the resulting value to the players. f~.,, The RM 14 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge. The particulate filter sample count rate (cpm) was estimated from the I 101 air concentrations for a 10 cubic feet s l
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AIR SAMPLE DATA * (RM 14)" GAMMA DOSE RATE RADECO/HV 1BC PARTICULATE PLUME CONC. 10 CF FILTER"* SEGMENT DISTANCE MAP PIC-6 RM-14 l-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1 4375 0.00E+00 <40 <40 BOUNDARY YELLOW <1 438 0.00E+00 <40 <40 GREEN <1 44 0.00E+00 <40 <40 1 2.00 1.00 BLUE 3 11165 1.68E-09 <40 <40 YELLOW <1 1117 1.68E-10 <40 <40 GREEN <1 112 1.68E-11 <40 <40 ) 3.00 1.50 BLUE 3 9310 2.01 E-09 <40 <40 YELLOW <1 931 2.01E 10 <40 <40 GREEN <1 93 2.01E 11 <40 <40 4.00 2.00 BLUE 2 7875 2.18E-09 <40 <40 YELLOW <1 788 2.18E-10 <40 <40
/ GREEN <1 79 2.18E 11 <40 <40 h
5.00 2.50 SLUE 2 5845 1.23E-09 <40 <40 YELLOW <1 585 1.23E-10 <40 <40 GREEN <1 58 1.23E 11 <40 <40 6.00 3.10 BLUE 1 5215 1.16E-09 <40 <40 t YELLOW <1 522 1.16E-10 <40 <40 GREEN <1 52 1.16E-11 <40 <40 l 7.00 4.10 BLUE <1 2989 5.75E-10 <40 <40 ) YELLOW <1 299 5.75E-11 <40 <40 GREEN <1 30 5.75E 12 <40 <40 l NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, I divide the value given in the t.Able by Mo (2) and provide the resulting value to the players. p The RM-14 detector efficiency for 1 131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge. The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 10 cubic feet s 1 f
F l TABLE 9.6.7e RIv. 0 Pcge 9.6-11a2 VERMONT YANKEE FIELD DATA AT CLOCK Y:ME 1345-1400 (SCENARIO TIME 0530-0545) t O j AIR SAMPLE DATA * (RM-14)" GAMMA DOSE RATE RADECO/HV-1BC PARTICULATE l PLUME CONC'. 10 CF FILTER *" SEGMENT DISTANCE MAP PIC-6 RM-14 l-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) i 8.00 4.60 BLUS <1 2174 3.28E-10 <40 <40 YELLOW <1 217 3.28E-11 <40 <40 GREEN <1 22 3.28E-12 <40 <40 9.00 5.10 BLUE <1 1705 2.43E-10 <40 <40 YELLOW <1 170 2.43E-11 <40 <40 GREEN <1 17 2.43E-12 <40 <40 10.00 5.80 BLUE <1 469 6.60E 11 <40 <40 YELLOW <1 47 6.60E 12 <40 <40 GREEN <1 5 6.60E-13 <40 <40 11.00 6.50 BLUE <1 413 5.51 E-11 <40 <40 YELLOW <1 41 5.51E 12 <40 <40 O GREEN <1 4 5.51E 13 <40 <40 G NOTES: Air sample data are based on a sample volume of 10 cubic fees for the air sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, divide the value given in the table by two (2) and provide the resulting value to the players. p The RM-14 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge. U)" f The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 10 cubic feet s
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F l j TABLE 9.6.8a Rw. O J ( P ge 9.6-1231 l - VERMONT YANKEE FIELD DATA AT CLOCK TIME 1400-1415 (SCENARIO TIME 0545-0600) i O. AIR SAMPLE DATA * (RM 14)" GAMMA DOSE RATE RADECO/HV-1BC PARTICULATE PLUME CONC. 10 CF FILTER"* SEGMENT DISTANCE MAP PIC-6 RM-14 l-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1 4060 0.00E+00 <40 <40 BOUNDARY YELLOW <1 406 0.00E+00 <40 <40 GREEN <1 41 0.00E+00 <40 <40 2.00 0.50 BLUE 4 12460 4.67E-10 <40 <40 YELLOW <1 1246 4.67E-11 <40 <40 GREEN <1 125 4.67E-12 <40 <40 3.00 1.00 BLUE 4 15120 6.36E-09 79 <40 YELLOW <1 1512 6.36E-10 <40 <40 GREEN <1 151 6.35E-11 <40 <40 4.00 2.00 BLUE 2 6720 1.45E-09 <40 <40 YELLOW <1 672 1.45E-10 <40 <40 O GREEN <1 67 1.45E-11 <40 <40 v) I
<40 5.00 2.50 BLUE 2 5600 1.18E-09 <40 YELLOW <1 560 1.18E-10 <40 <40 GREEN <1 56 1.1BE 11 <40 <40 6.00 3.06 BLUE 1 4830 1.08E-09 <40 <40 ;
YELLOW <1 483 1.08E-10 <40 <40 l GREEN <1 48 1.08E-11 <40 <40 7.00 3.60 BLUE 1 3990 7.85E-10 <40 <40 YELLOW <1 399 7.85E 11 <40 <40 GREEN <1 40 7.85E-12 <40 <40 NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler, if different volumes rare collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, I divide the value given in the table by two (2) and provide the resulting value to the players. The RM-14 detector efficiency for I-131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge.
'" The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 10 cubic feet s
e TABLE 9.6.8a RIv. O ! Pcge 9.6-12:2 VERMONT YANKEE FIELD DATA AT CLOCK TIME 14001415 (SCENARIO TIME 0545-0600) AIR SAMPLE DATA * (RM-14)" GAMMA DOSE RATE RADECO/HV-1BC PARTICULATE l PLUME CONC. 10 CF FILTER"* SEGMENT DISTANCE MAP PIC-6 RM 14 l-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) 8.00 4.10 BLUE 1 3640 7.03E 10 <40 <40 YELLOW <1 364 7.03E-11 <40 <40 GREEN <1 36 7.03E 12 <40 <40 9.00 5.10 BLUE <1 2268 4.10E-10 <40 <40 YELLOW <1 227 4.10011 <40 <40 GREEN <1 23 4.10E-12 <40 <40 10.00 5.60 BLUE <1 1691 2.40E 10 <40 <40 YELLOW <1 169 2.40E-11 <40 <40 GREEN <1 16.9 2.40E 12 <40 <40 11.00 6.20 BLUE <1 1344 1.76E 10 <40 <40 YELLOW <1 134 1.76E 11 <40 <40 O GREEN <1 13 1.76E 12 <40 <40 12.00 6.90 BLUE <1 382 5.06E 11 <40 <40 YELLOW <1 38 5.06E 12 <40 <40 GREEN <1 4 5.06E 13 <40 <40 13.00 7.50 BLUE <1 340 4.22E 11 <40 <40 l YELLOW <1 34 4.22E 12 <40 <40 GREEN <1 3 4.22E-13 <40 <40 4 l l NOTES: Air sample data are based on a sample volume of 10 cubic feet for the air sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cubic feet sample was collected instead of 10 cubic feet, divide the value given in the table by two (2) and provide the resulting value to the players. The RM 14 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the silver zeolite cartridge.
\_ / ""
The particulate filter sample count rate (cpm) was estimated from the I 131 air concentrations for a 10 cubic feet s
r, Rev.1 Q Page 10.1-1 Q VERMOMT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE J 1999 10J. ON-SITE METEOROLOGICAL DATA CLOCK UPPER UPPER UPPER LOWER LOWER LOWER RAIN LOWER ATM PRESS TIME SPEED DIR DELTAT SPEED DIR DELTAT INCHES TEMP lNCHES MPH DEGREES DEGF MPH DEGREES DEGF 1/4 HR DEGF MERCURY (Note 1) (Note 2) 08:00 5.30 270.00 -1.60 3.30 265.00 1.00 0.25 47.00 28.75 08:15 8.00 271.00 -0.80 6.00 266.00 -0.20 0.50 44.00 28.60 08:30 42.00 150.00 -1.20 40.00 145.00 -0.60 0.50 40.00 28.50 08:45 35.00 170.00 -1.35 33.00 165.00 -0.75 0.25 42.00 28.40 09:00 22.00 244.00 -1.50 20.00 239.00 -0.90 0.10 47.00 28.90 09:15 8.20 262.00 -1.55 6.20 257.00 -0.95 0.00 51.00 29.20 09:30 7.90 281.00 -1.60 5.90 276.00 -1.00 0.00 53.00 29.50 09:45 7.60 315.00 -1.65 5.60 310.00 1.05 0.00 55.00 29.60 10:00 7.40 327.00 -1.70 5.40 322.00 -1.10 0.00 55.60 29.90 10:15 7.80 345.00 -1.72 5.80 340.00 -1.12 0.00 56.10 30.00 10:30 8.20 344.00 1.76 6.20 339.00 -1.16 0.00 56.60 30.10 10:45 8.60 342.00 -1.78 6.60 337.00 -1.18 0.00 56.90 30.10 11:00 9.10 343.00 -1.80 7.10 338.00 -1.20 0.00 57.30 30.10 11:15 8.60 340.00 -1.83 6.60 335.00 -1.23 0.00 57.60 30.20
^11:30 8.10 337.00 -1.87 6.10 332.00 -1.27 0.00 57.80 30.20 '
Ol1:45 7.60 334.00 -1.88 5.60 329.00 -1.28 0.00 58.10 30.30 12:00 7.10 58.00 -1.90 5.10 53.00 -1.30 0.00 58.40 30.30 12:15 6.30 60.00 -1.90 4.30 55.00 -1.30 0.00 58.90 30.50 12:30 5.50 65.00 -1.88 3.50 60.00 -1.28 0.00 59.20 30.50 12:45 4.30 67.00 1.92 2.30 62.00 -1.32 0.00 59.50 30.50 13:00 4.00 63.00 -1.90 2.00 58.00 -1,30 0.00 59.70 30.40 13:15 4.20 66.00 -1.87 2.20 61.00 -1.27 0.00 59.90 30.40 13:30 4.10 68.00 -1.83 2.10 63.00 -1.23 0.00 60.30 30.30 13:45 4.00 70.00 -1.76 2.00 65.00 1.16 0.00 60.50 30.20 14:00 4.10 72.00 1.70 2.10 67.00 -1.10 0.00 60.40 30.20 14:15 4.10 72.00 1.70 2.10 67.00 -1.10 0.00 60.40 30.20 14:30 4.10 90.00 -1.70 2.10 85.00 -1.10 0.00 60.40 30.20 l I NOTES:
- 1. The height differential for the upper delta temperature on the primary tower is 262 ft.
- 2. The height differential for the lower delta temperature on the primary tower is 165 ft.
O J
l ./ Rev. O I Page 10.2-1 i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 10.2 GEMERAL ARE& MNS FOREchsTS (See Note) - Synoosis (08:00) Severe t.hunderstorms are expected this morning. A wind shif t from the west to the east-northeast is expected late this morning. Valid (08:00-12:00) Severe thunderstorms early then clearing late morning. Temperatures rising from current 40's into the 60's. Wind speed and direction variable due to thunderstorms.
- Valid (12:00-16:001 l Mostly sunny. Temperatures rising to the mid to upper 60's. Easterly winds from 4 to 8 MPH.
l valid (16:00-23:00) l Partly cloudy. Low temperatures in the upper 40's. Winds light and variable. PLANT / EOF WEATHER OBSERVATIONS (See Note) - Valid (08:00-17:00) Time General Observations 08:00-09:00 Thunderstorms with moderate to high winds.
~09:00-14:00 Mostly sunny with light to moderate winds.
14:00-17:00 Partly cloudy with light winds. NOTE: GENERAL AREA NWS FORECASTS SHOULD BE PROVIDED UPON REOUEST. PLANT / EOF WEATHER OBSERVATIONS WILL BE POSTED AS APPROPRIATE. t l
i l- j l l l l t Rev. O Page 10.2-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 1 10.2 VERMONT YANKEE SITE FORECAST ! I To be orovided to the ESC Meteorolocist by the ESC Controller at 08:15. I WEATHER FORECAST FOR SITE: VY - VEPRON Date of Forecast: 04-26-99 ; Time of Forecast: 08:15 : Current Site Meteorology (as of 08:15 ): l 38012 VVind Somed Wind Direction Qana SidL Precioltation Temoerature Gjana i l Lower 6.0 MPH 266 DEG FROM 02 DEG F E 0.50 IN/15 MIN Upper 8.0 MPH 271 DEG FROM -0.8 DEG F [ 1 Forecast Site Meteorology: l Sensor Wind Sneed Wind Direction Preclottatlan IkDe Qaus Slatt Temocrature ClaES 08:15-10:00 Lower 4.0 MPH 260 DEG FROM -0.8 DEG F D 0.25 IN/15 MIN Upper 7.5 MPH 270 DEG FROM -12 DEG F 0 10:00-12:00 Lower 8.0 MPH 330 DEG FROM 1.2 DEG F D 0.00 IN/15 MIN l Upper 8.0 MPH 340 DEG FROM -1.8 DEG F 0 12:00-14:00 Lower 4.0 MPH 60 DEG FROM 1.3 DEG F D 0.00 IN/15 MIN l j j Upper 5.0 MPH 65 DEG FROM -1.9 DEG F D l l National Weather Service Forecast for site region: Severe thunderstorms early then clearing late morning. Temperatures rising from current 40's into the 60's. Wind speed and direction variable due to thunderstorms. ! l Special Weather Statements: Severe thunderstorm warning for Windham County Vermont, Cheshire County New Hampshire, and Franklin County Massachusetts effective until 1200 noon. l
.Q.
Q Expect heavy rainfall, strong gusty winds and lightning. At 0815 National Weather Service doppler radar indicated a tornado developing in the area. i j A tornado warning has been issued for Windham County Vermont and Cheshire ! County New Hampshire, j i l L
Rev. O Page 10.2-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1999 10.2 VERMONT YANKEE SITE FORECAST To be orovided to the ESC Meteorolocist by the ESC Controller at 10:00. WEATHER FORECAST FOR SITE: _VY - VERNON Date of Forecast: 04-26-99 Time of Forecast: 10:00 Current Site Meteorology (as of 10:00 ): Sensor Wind Somed Wind Direction QggTemoerature Stab. Class Precloitation Lower 5.4 MPH 322 DEG FROM -1,1 DEG F D 0.00 IN/15 MIN Upper 7.4 MPH 327 DEG FROM 1.7 DEG F D Forecast Site Meteorology: Ilme Sensor Wind Somed Wind Direction Dda Temnerature Stab. Class Proclottation 10:00 Lower 6.0 MPH 330 DEG FROM 1.2 DEG F D 0.00 IN/15 MIN 12:00 Upper 8.0 MPH 340 DEG FROM 1.8 DEG F D 12:00- Lower 4.0 MPH 60 DEG FROM 1.3 DIG F D 0.00 IN/15 MIN 14:00 Upper 5.0 MPH 65 DEG FROM 1.9 DEG F D 14:00- Lower 3.0 MPH 90 DEG FROM 0.2 DEG F E 0.00 IN/15 MIN 16:00 Upper 4.0 MPH 90 DEG FROM 0.5 DEG F E National Weather Service Forecast for site region: Temperatures rising from current 40's into the 60's. Wind speed and direction shifting from light to moderate westerly winds to light east-northeasterly by midday. Special Weather Statements: Tornado and severe thunderstorm warnings have been cancelled. l
T7 ]
- Rev. O Page 10.2-4 l VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY PREPAREDNESS EXERCISE l 1999 l
10,2 VERMONT YANKEE SITE FORECAST l To be orovided to the ESC Meteorolocist by the ESC Controller at 12:00. l WEATHER FORECAST FOR SITE: VY - VEPRON I !. Date of Forecast: 04-26-99 Time of Forecast: 12:00 Current Site Meteorology (as of 12 00 ): j Sensor WJDd Wind Direction Delta Temoerature M Precloitation SQA8d C1888 Lower 5.1 MPH 325 DEG FROM 1.3 DEG F D 2 .#.00 IN/15 MIN Upper 7,1 MPH 330 DEG FROM 1.9 DEG F D Forecast Site Meteorology: l T. lids Sensor WJDd Wind Direction Delta Temoerature M Precioltation SDSBd ClBEA l 12:00-' Lower 4.0 MPH 60 DEG FROM 1.3 DEG F D 0.00 IN/15 MIN l 14:00 Upper 5.0 MPH 65 DEG FROM 1.9 DEG F D t 14:00- Lower 3.0 MPH 90 DEG FROM 0.2 DEG F E 0.00 IN/15 MIN
- l. 16:00 I Upper 4.0 MPH 90 DEG FROM 0.5 DEG F E j
( 16:00- Lower 2.0 MPH 60 DEG FROM 0.5 DEG F E 0.00 IN/15 nAIN 18:00 l Upper 5.5 MPH 70 DEG FROM 1.0 DEG F E i National Weather Service Forecast for site region: I Mostly sunny. Temperatures rising to the mid to upper 60's. Easterly j winds from 4 to 8 MPH. Special Weather Statements: None}}