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| 4 VERMONT YANKEE NUCLEAR POWER STATION i
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| VERNON, VERMONT l
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| i I t EMERGENCY PREPAREDNESS EXERCISE MARCH 19,1997 I
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| EXERCISE MANUAL l
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| l VERMONT YANKEE NUCLEAR POWER CORPORATION l EXERCISE MATERIAL 1 N b\'!!
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| (,hU15 UIII".
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| YERMONT YANKEE NUCLEAR PONER STATION umsman-CY PREyans w3SS EXERCISE 1997 TABLE OF CONTENTS Section Title Egy
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| ==1.0 INTRODUCTION==
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| 1.1 Exercise Schedule 0 l 1.2 Participating Centers / Agencies 0 ,
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| 2.0 EXERCISE OBJECTIVES AND EXTENT OF PLAY l
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| i 2.1 Vermont Yankee 0 2.2 State of Vermont 1/14/97 2.3 State of New Hampshire 1/08/97 2.4 Commonwealth of Massachusetts 12/16/96 ;
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| e 3.0 EXERCISE GUIDELINES AND SCOPE 3.1 Exercise Guidelines and Ground Rules 0 l!
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| 3.2 Procedure Execution List 0 i
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| 4.0 CONTROLLER INFORMATION 4.1 Controller Assignments 0 t 4.2 Controller Exercise Guidance 0 l 4.3 controller Evaluation Criteria 0 5.0 EXERCISE SCENARIO 5.1 Initial conditions 0 l
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| 5.2 Exercise Sequence of Events O 5.3 Scenario Timell.'e 0 6.0 EXERCISE MESSAGES 6.1 Command Cards 0 6.2 Message Cards 0 7.0 STATION EVENT DATA 7.1 Events Summary 0 7.2 Event Mini-scenarios 0 I
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| 8.0 OPERATIONAL DATA 0 i
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| VERMONT YANEEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 TABLE OF CONTENTS (continued)
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| Section Title Bav a.
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| 9.0 RADIOLOGICAL DATA 9.1 Area Radiation Monitors O 9.2 Process Monitors O 6 9.3 In-Plant Radiation Levels O 9.4 Plant Chemistry Data 0 9.5 Plant Vent Stack Data 0 9.6 Field Monitoring Maps and Data 0 10.0 METEOROLOGICAL DATA 10.1 On-Site Meteorological Data 0 "
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| 10.2 General Area NWS Forecasts 0 l
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| l l VEPMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 M EXERCISE SCHEDULE l 1 l NOTE: EXERCISE SCHEDULE TO BE ISSUED UNDER SEPARATE MEMO AND REVIEWED AT l THE EXERCISE CONTROLLER BRIEFING SESSIONS.
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| Rev. O
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| ! Page 1.2-1 1
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| VERMONT YANKEE NUCLEAR POWER STATION j EMERGENCY PREPAREDNESS EXERCISE I 1 1997 l l
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| l l 1.,s.3 PARTICIPATING CENTERS / AGENCIES l
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| 1 1
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| VERMONT YANKEE NUCLEAR POWER CORPORATION Vermont Yankee Emergency Response Organization Facilities l
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| l Vermont Yankee Nuclear Power S*,ation - Vernon, Vermont J l
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| * Control Room (notification and communications functions only)
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| * Technical Support Center (2nd floor of Administration Building) l
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| * Operations Support Center (1st floor of Administration Building)
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| * Energy Information Center (Governor Hunt House) l i
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| Vermont Yankee Training Center - Brattleboro, Vermont
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| * Simulator Room (Control Room functions, let floor of Training Center)
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| * Emergency Operations Facility / Recovery Center (1st floor of Training Center)
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| * News Media Center (1st and 2nd floor of Training Center) !
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| l YANKEE ATONIC ELECTRIC COMPANY Yankee Nuclear Services Division - Bolton, Massachusetts Facility
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| * Engineering Support Center i
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| . . . . - ~ . . - -. . - - - - - . . - ~ . ... .- - .. - - - - --. -- - . - . _ -. - _ _ .. -
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| Rev. O Page 1.2-2 STATE OF VERMONT Kev Particinatino State Acencies
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| * Vermont Emergency Hanagement
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| * Vermont State Health Department l l
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| l Facilit19s i l
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| * State Warning Point, Vermont State Police - Waterbury, Vermont i
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| ! - Emergency Operations Center - Waterbury, Vermont
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| * Incident Field Office - Dummerston, Vermont
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| * Department of Health Laboratory - Burlington, Vermont l
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| * Emergency Operations Facility / Recovery Center - Brattleboro, Vermont t
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| * News Hedia Center, Vermont Yankee Training Center - Brattleboro, Vermont
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| (
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| l I Kev Particinatino Local hoencies I
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| * Brattleboro, Dummerston, Guilford, Halifax and Vernon Emergergy hanagement Agencies Facilities ,
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| * Brattleboro Emergency Operations Center (EOC) - Brattleboro Town Hall ,
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| * Dummerston EOC - Dummerston Town Office Building
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| * Guilford EOC - Guilford Fire Station f a Halifax EOC - Halifax Fire' Station
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| - Vernon EOC - Vernon Fire Station 5 Miscellaneous Particinants/ Facilities Schools (Out of Sequence - Interviews with School Principal and one Superintendent on the day following the exercise)
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| * The Austine School i
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| * Dummerston Elementary School
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| * Guilford Central School
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| - The Neighborhood School
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| * The Halifax West School .
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| * Superintendent of WSWSU
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| * Superintendent of WSESU l T
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| Recention Center (Limited Participation - Notification Process) {
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| * Bellows Falls Union High School ,
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| * Westminster EOC r
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| Rev. 0 l Page 1.2-3 i special Poculation Center (Out of Sequence - Interview Process) ,
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| * Eden Park Nursing Home i
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| * Campgrounds (Summer 97)
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| Fort Dummer camp Waubanoug Hidden Acres K0A Rad 10 Station
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| * WTSA, Brattleboro, VT
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| Rev. O Page 1.2-4 STATE OF NEW EAMPSEIRE Kev Particinatino State Acencies
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| * New Hampshire Office of Emergency Management
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| * Department of Public Health Service Facilities
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| * State Police Communications Center - Concord, New Hampshire
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| * State Police Troop C - Keene, New Hampshire
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| * Southwestern NH District Fire Mutual Aid - Keene, New Hampshire
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| * Emergency Operations Center - Concord, New Hampshire Emergency Operations Facility / Recovery Center - Brattleboro, Vermont
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| * News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont Kev Particinatino Local Acencies
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| * Chesterfield, Hinsdale, Richmond, Swanzey and Winchestar Emergency Management Agencies Facilities
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| * Chesterfield Emergency Operations Center (EOC) - Chesterfield Fire Dept.
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| Hinsdale EOC - Hinsdale Fire Station / Town Hall
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| * Richmond EOC - Richmond Civil Defense Building
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| * Swanzey EOC - Swanzey Center Fire Station
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| * Winchester EOC - Winchester Emergency Service Building Miscellaneous Particicants/Faellities Schools (Out of Sequence - Interviews with School Administration Officials) i
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| * EPZ Schools in Hit.sdale, Winchester and Chesterfield Radio Station
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| * WKNE, Keene, NH i
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| - - . - . . .- - - . --. - . . . . . . - - - . . - . . ~ ..__ . . . . - ~ . _ . . . -
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| Rev. O Page 1.2-5 ColeeDNWEALTE OF MASSACEUSETTS Kev Particinatino State Acencies l
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| l
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| * Massachusetts Emergency Management Agency l
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| * Massachusetts Department of Public Health Facilities
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| * Emergency Operations Center - Framingham, Massachusetts
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| * Area III Emergency Operations Center - Belchertown, Massachusetts
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| * Emergency Operations Facility / Recovery Center - Brattleboro, Vermont
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| * News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont Kev Particinatino Local Acencic5/oraanizations
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| * Bernardston, Colrain, Gill, Greenfield, Leyden, Northfield and Warwick Emergency Management Agencies
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| (
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| * State Police Troop B - Northampton, Massachusetts i
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| Facilities
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| * Bernardston Emergency operations Center (EOC) - Bernardston Fire Station l
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| * Colrain EOC - Colrain Fire Station
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| * Gill EOC - Gill Fire Station
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| * Greenfield EOC - Greenfield Fire Station I
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| * Leyden EOC - Leyden Fire Station Northfield EOC - Town Hall
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| * Warwick EOC - Warwick Fire Station i Miscellaneous Particicants/ Facilities Schools (Out of Sequence - Interviews with School Principals or their j designees) j
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| * Bernardston Elementary School
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| * Pioneer Valley Regional School, Northfield
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| * Pearl Rhodes Elementary School, Leyden
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| * Northfield Elementary School !
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| * Escort Vehicles - out of Sequence at the end of exercise to the following l locations:
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| Bernardston Elementary School j
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| Gill Elementary School Northfield Mount Hermon School, Northfield Campus i Warwick Elementary School t
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| __ .. _ . . ~ . . _
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| d Rev. O Page 1.2-6 Recention Center (Out of Sequence - Date to be determined)
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| * Greenfield cermunity College Reception Center Conarmaate care Facilities (Shelter Surveys Only) i
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| - Mass care Shelters: Greenfield Armory, Greenfield High School, Federal Street j School I
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| j Soecial Poculation Centers
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| * Massachusetts Department of Environmental Management (District 9 Fire Warden)
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| * Massachusetts Department of Fisheries, Wildlife, and Environmental Law l Enforcement, Division of Law Enforcement i
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| Radio Station WHYN, Springfield j
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| VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 I 1
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| 2.1 VERMONT YANKEE - EXERCISE OBJECTIVES AND EXTENT OF PLAY l
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| Rev. 0 Page 2.1-1 -
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| 2d EXERCISE OBJECTIVES AND EXTENT OF PLAY - VERMONT YANKEE j Extent of Plav l ;
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| i A. Emeroenev Classification and Accident Assessment '
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| 1 4 i j 1. Demonstrate the ability of Control Room A.1 Scenario events initiated on the simulator will provide j personnel to recognize emergency the operational and radiological data to allow personnel
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| ; initiating events and properly classify the to demonstrate this objective in accordance with
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| ! condition in accordance with a Procedure AP 3125, Emergency Plan Classification and pre-established emergency action levels. Action Level Scheme.
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| j 3. Demonstrate the ability of Control Room
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| ' A.2 The scenario will provide technical information to 1 personnel and TSC staff to coordinate the players which wil' allow them to analyze plant :
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| ! assessment of plant conditions and conditions and initiate correcrive actions in accordance !
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| i corrective actions to mitigate accident with established procedures. Early in plant actions cenditions.
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| normally performed by the Centrol Room support
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| . l i personnel may be controlled and performed by I Simulator Controllers until after the Alert classification l j
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| when the Emergency Response Organization is fully j i
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| activated. Demonstration of in-plant corrective actions '
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| are controlled in accordance with the defined exercise j mini-scenarios (Refer to Section 7.2). Simulation of response activities will be controlled in accordance with the defined mini-scenarios and as specified in the
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| exercise ground rules.
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| ! 3. Demonstrate that information concerning A.3 Telephone communications and the Simulated Plant plant conditions can be transmitted Process Computer System (SPPCS) data link will be between the Control Room and the TSC in established between the Simulator Control Room and a timely manner, the various Emergency Response Facilities in order to transmit key information and data.
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| A.
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| : 4. Jmonstrate the ability of the TSC staff to A.4 Scenario events viill enable the TSC to coordinate !
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| initiate and coordinate corrective actions in in-plant corrective actions through the use of OSC j an efficient and timely manner. personnel. {
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| * indicates an identified item from 1996 Exercise.
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| Rsv.O Pags 2.1-2 l
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| Extent of Plav
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| : 5. Demonstrate .he ability of appropriate TSC A.5 Scenario events will allow for the discussion between staff to participate with the Control Room the SCR, TSC and EOF /RC staff on EALs and and the EOF /RC in EALs and classification emergency classification decisions.
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| discussions."
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| : 6. Demonstrate the ability to assess data A.6 Scenario events will allow for Chemistry and Radiation from appropriate chemistry samples in Protection technicians to simulate taking reactor support of accident assessment activities coolant, containment air, or plant vent stack samples and plant conditions. to assess plant conditions. Actual sampling and actual ,
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| I manipulation of sampling system cos.1ponents 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 players.
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| : 7. Demonstrate the ability to effectively use A.7 ERFIS work stations in the TSC, EOF and ESC will be the Emergency Response Facility connected to the Simulator Control Rdom through the j information System (ERFIS) in the use of the Simulated Plant Process Computer System assessment and trending of plant (SPPCS) to receive and display scenario-related data. ;
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| conditions. (Controllers 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.
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| B. Notification and Communication
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| : 1. Demonstrate the ability of Control Room B.1 Scenario events ~will allow Control Room personnel to personnel to complete timely plant make plant announcements for declared emergency announcements of declared emergency classifications.
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| classifications.
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| : 2. Demonstrate that messages are B.2 Various communications links will be established transmitted in an accurate and timely between emergency response facilities in order to manner and that decisions, information transmit information and data. Record keeping and and messages are properly logged and documentation will be demonstrated in accordance documented.' with established procedures.
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| * indicates an identified item from 1996 Exercise. ,
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| l Rev. 0 Page 2.1-3 Extent of Plav i 3. Demonstrate the capability to notify B.3 Vermont Yankee staff, NRC, and state authorities shall federal and state authorities of emergency be notified in accordance with established procedures, classification and significant changes in NRC will be notified by using the FTS 2000 ENS plant status in accordance with telephone. The State authorities will be notified established procedures. through the Nuclear Alert System (Orange Phone).
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| : 4. Demonstrate that appropriate status B.4 Status Boards (where prcvided) will be used by boards are used to display pertinent response personnel to display pertinent information.
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| accident information at various emergency Status Board Caretakers will be assigned by facility response faciliti3s.* coordinators to maintain the status boards with current information. I I
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| : 5. Demonstrate that adequate emergency B.5 Communications will be demonstrated between the communication systems are in place to various Emergency Response Facilities using facilitate transmittal of data between established communications systems as described in emergency response facilities and federal Procedure OP 3504, " Emergency Comm,unications."
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| and state authorities.
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| l S. Demonstrate that off-site monitoring B.6 Off site Monitoring Teams will be dispatched to the I teams (if necessary) can appropriately field and directer' to specific sample locations for identify their location when reporting monitoring act'vities (if necessary). ,
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| sample results to the EOF. i
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| : 7. Demonstrate the ability to provide B.7 During the period that the Off Site Monitoring Teams adequate briefings (if necessary) to off site will be in the field, scenario ovents may require that monitoring teams as conditions and periodic updates be transmitted to the teams in the information change. field (if necessary).
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| : 8. Demonstrate the ability to adequately B.8 Scenario events will allow the TSC to update plant communicate plant updates to plant personnel on changing plant conditions and plant personnel as plant conditions and status status information. Periodic plant announcements information change.' should be made to.brief plant personnel on plant conditiow and emergency status information.
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| 6
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| Rev.O Page 2.1-4 Extent of Plav C. Direction and Control
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| : 1. Demonstrate the prcper transfer of C.1 Scenario events r* auire the activation of the responsibilities from SS/ PED to the DCO, Emergency Response Organization. As each position and subsequently to the TSC Coordinator of authority is activated, responsibilities associated and Site Recovery Manager as appropriate. with that position will be assumed from the SS/ PED up to the Site Recovery Manager.
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| : 2. Demonstrate the capability of key C.2 All emergency response facilities have designated emergency response facility management coordinators who will direct and coordinate emergency I personnel to direct and coordinate their response activities in their particular area of respective emergency response activities responsibility.
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| in an efficient and timely manner.
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| : 3. Demonstrate appropriate coordination of C.3 The SCR will initially contact the federal and state activities with federal and state agencies, providing them with appropriate information government agencies. on plant conditions and emergency status. This function will pass to the TSC and EOF /RC after the facilities are activated and staffed.
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| s D. Emeroenev Resoonse Facilities
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| : 1. Demonstrate the ability of station D.1 Scenario events will require activation and operation of personnel to activate and staff the D.2 Vermont Yankee emergency response facilities. The emergency response facilities in a timely SCR, Control Room (communication functions only),
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| manner. TSC, OSC, EOF /RC, News Media Center and Engineering Support Center will be activated in accordance with established procedures. Designated plant and corporate emergency response personnel will participate in the exercise.
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| : 2. Demonstrate and test the adequacy and ,
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| effectiveness of emergency response facilities, operations, and equipment. I i
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| ' indicates an identified item from 1996 Exerc'se.
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| 4
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| Rev.O Page 2.15 Extent of Plas E. Plant Auamentation and Staffina
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| : 1. Demonstrate the adequacy of plant E.1 Shift personnel will demonstrate the use of the 1 emergency notification methods and emergency call-in system to augment plant staff as procedures to augment plant staff and may be required by scenario events.
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| ; resources.
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| : 2. Demonstrate the ability to use outside E.2 The Yankee Nuclear Services Division's (YNSD) resources to provide technical assistance Engineering Support Center (ESC) will be contacted and logistical support. and activated for this exercise. The ESC will provide technical and logistical support as requested by Vermont Yankee. YNSD Site Responders will be i prestaged and respond to the plant at an appropriate time, consistent with their activation and mobilization procedures.
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| ; 3. Dorronstrate the ability to maintain shift E.3 Available resources will be evaluated and assigned to 1
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| staffing and manpower to provide for support extended operations. ;
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| future manpower and logistics needs.
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| F. Radioloaical Exoosure Control l
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| : 1. Demonstrate the ability to provide F.1 Scenario events will allow OSC On-Site Assistance adequate radiation protection controls for F.2 Teams to be dispatched to investigate problems with on site emergency response personnel associated plant equipment. Investigation and repair including dosimetry, equipment, and activities in the plant will require implementation of protective clothing.' radiation controls which include monitoring and tracking of radiation exposure of OSC On-site
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| : 2. Demonstrate the ability to monitor and Assistance Teams. (Refer to Procedure OP 3507, "
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| track radiation exposure of on-site Emergency Radiation Exposure Control.") in addition, emergency response personnel, the exposere c', the Off-Site Monitoring Teams will be monitored and tracked in the EOF.
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| : 3. Demonstrate the ability to monitor F.3 Habitability surveys of the Emergency Response radiological conditions of Emergency Facilities will be conducted in accordance with Response Facilities and implement established procedures. Results of the habitability appropriate habitability controls.' surveys will be evaluated, and appropriate controls will be implemented as required by scenario events.
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| ' Indicates an identified item from 1996 Exercise.
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| Rev.O Page 2.1-6 Extent of Plav i
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| G. in-Plant Corrective and Reoair Actions
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| : 1. Demonstrate the ability to dispatch and G.1 OSC On-site Assistance Teams should be dispatched deploy on-site assistance teams in a timely G.2 to investigate problems associated with plant fashion, consistent with plant conditions equipment. Briefings should be conducted with and assigned function, emergency teams to ensure that job requirements are
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| : 2. Demonstrate the ability to provide clear and understood. OSC Team Work Status Forms (VYOPF 3501.06) should be used to keep track of adequate briefings to on-site assistance team assignments and work tasks.
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| ; teams on job assignments and tasks.
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| : 3. Demonstrate the ability of on-site G3 OSC On-site Assistance Teams will be given the
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| ; assistance teams to perform corrective G.4 opportunity to perform corrective actions associated actions on plant equipment during emergency conditions. with plant equipment. Demonstration of in-plant corrective actions are controlled in aceprdance with l
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| : 4. Demonstrate the ability to provide defined exercise mini-scenarios (Refer to Section 7.2). I Simulation of repair activities will be controlled in adequate administrative controls and documentation for necessary repairs of accordance with the defined mini-scenarios and as specified in the exercise ground rules. The exercise plant equipment and systems during an mini-scenarios will allow players to implement the emergency situation. I appropriate emergency work controls in accordance with established procedures.
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| H. Radiolooical Assessment
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| : 1. Demonstrate that adequate dose H.1 The scenario will provide information on plant assessment activities can be performed to i H.2 conditions and in-plant radiological conditions to determine off site radiological consequences.
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| H.3 players that will allow them to evaluate off-site H4 potential radiological consequences. The scenario will H.5 provide off-site radiological data that will allow players
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| : 2. Demonstrate that radiological assessment to evaluate off-site radiological conditions (if personnel at the EOF can obtain necessary). Players willimplement appropriate radiological and meteorological data in a i sections of Procedures OP 3513, " Evaluation of Off-timely manner.
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| Site Radiological Conditions" and OP 3511. " Off-Site Protective Action Recommendations," as may be required by scenario events.
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| *lndicates an identihed item from 1996 Exercise.
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| 9 R:v.0 Page 2.17 l
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| ! Extent of Plav
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| ' )
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| l 3. Demonstrate the ability to perform timely
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| ; assessment of off-site radiological conditions to support the formulation of I i
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| protective action recommendations for the plume exposure pathway.
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| k
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| ) 4. Demonstrate the ability to assess potential I off-site radiological consequences based on plant conditions.
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| : 5. Demormtrate the ability to project plume trajectory and potentially affected '
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| downwind sectors (if necessary) using computer dose assessment model (METPAC).
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| : 6. Demonstrate adequate staffing, equipment H.6 Off-site monitoring teams will be assigned at the OSC.
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| readiness check, and deployment (if H.7 Players willimplement appropriate sections of necessary) of off-site monitoring teams.* Procedure OP 3510. "Off Site and Site Boundary :
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| Monitoring, "as may be required by scenario events.
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| h, 7. Demonstrate the use of appropriate ]
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| j equipment and procedures to perform off- '
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| site radiological monitoring (if necessary),
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| : l. Protective Action Decision Makino
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| : 1. Demonstrate the ability to implement 1.1 On-site protective action measures willinclude appropriate on-site protective measures for radiation exposure control and plant evacuation of emergency response personnel, nonessential personnel. After plant evacunion and accountability has been completed, pit.nt personnel and contractors /vis'itors not directly involved in the exercise may be allowed to return to work at the discretion of the TSC Coordinator.
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| ' Indicates an identified item from 1996 Exercise.
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| Rev. O Page 2.1-8 Extent of Plav
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| : 2. Demonstrate the adequacy of the 1.2 Protective action decision making will be demonstrated protective action decision making process in accordance with Procedure OP 3511, "Off Site to make appropriate recommendations Protective Actions Recommendations".
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| concerning off-site radiological consequences.
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| J. Public Information
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| : 1. Demonstrate the ability to develop and J.1 The News Media Center (NMC) will be activated and periodically disseminate timely and J.2 staffed. Information on the simulated scenario events accurate press releases to the public and J.3 occurring at the plant will be gathered, verified, and the news media. incorporated into news releases. After approval, ;
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| information will be disseminated and briefings on the I
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| : 2. Demonstrate the ability to provide information will be conducted at the NMC.
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| l l
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| briefings and to interface with the public I and news media.
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| : 3. Demonstrate the ability to communicate I and coordinate news releases between the EOF and the News Media Center.
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| : 4. Demonstrate the ability to provide rumor J.4 A communication line will be established to provide for control. rumor control concerning the simulated accident.
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| : 5. Demonstrate the ability to coordinate J.5 State and public information representatives should be news releases with the state's public present at the NMC. Information concerning news information representatives, releases will be coordinated with the states' public information representatives.
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| * Indicates an identified item from 1996 Exercise.
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| Rev.0 ,
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| j Page 2.19 4
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| 1
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| ! Extent of Plav i
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| K. Parallel and Other Actions '
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| : 1. Demonstrate the adequacy of methods to K.1 Security activities will be implemented in accordance establish and maintain access control and with established procedures to control access to the personnel accountability within the protected area. Assembly of emergency response protected area. personnel and evacuation of contractors / visitors will be implemented to test personnel accountability process within the protected area (Refer to Procedure OP 3524, " Emergency Actions to Ensure Initial Accountability and Security Response"). However, after the plant evacuation and initial accountability ;
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| checks have been completed, contractors / visitors may ]
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| be allowed to return to work and they will be l exempted from additional personnel accountability checks or exercise-related announcements.
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| : 2. Demonstrate the licensee's capability for K.2 Exercise critique will be conducted witii exercise self-critique and ability to identify areas controllers and players. Critique items will be compiled needing improvement. and documented in accordance with Procedure OP 3505, " Emergency Preparedness Exercises and Drills."
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| Note: 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 (PASS).
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| l l
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| l
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| 'l
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| * Indicates an identified item from 199S Exercise.
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| 4_, k1-.--u- 4a-- A=- A ~ 4 &e 6 an -a2,A &LG---MmD,* +La2 .-e-*A- H > Gh. A - k.r4- ML4 &AJ2=L- As-& 4_-+-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 1
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| 2.2 STATE OF VERMONT - EXERCISE OBJECTIVES AND EXTENT OF PLAY l
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| l l
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| January 14,1997 VERMONT 1997 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION REP-14 OBJECTIVES STATE OF VERMONT LOCAL JURISDICTION t
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| : 1. Mobilization ofEmergency Personnel Yes Yes ,
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| Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate i the capability to activate and staff emergency facilities for emergency operations.
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| Extent ofPlay.
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| State and local jurisdictions will be alerted and notified at each ECL Mobilization of State and local personnel to staff emergency facilities and field operations will be in accordance with state and local plans.
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| EOF staff for Vermont, IFO staff and monitoring teams will be pre-staged in the Brattleboro area.
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| The following facilities will be activated and staffed:
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| Vermont State EOC State Warning Point Emergency Operations Facility <
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| Department of Health Laboratory Incident Field Office News Media Center-Vermont staff -
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| Local EOC's in the Towns of: !
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| Brattleboro i Dummerston :
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| Guilford Halifax Vernon 1
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| J'_ - - - - - . - - . . ~ _ .-
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| ( -
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| ARCA: Issue No.: 67-95-01-A Pre-positioned participants at the Brattleboro EOC (refer to 1995 Exercise Report, pg 39).
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| : 2. Facilities-Equipment, Displays and Work Environment. Yes Yes Demonstrate the adequacy of facilities, equipment, displays, and other materials to support emergency operations.
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| Extent of Play.
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| Facilities, equipment, maps and displays will be used to support response operations. State EOC & IFO access control will be demonstrated. Imal access control will be performed by staff on duty.
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| Those facilities with back-up power will demonstrate adequacy by presenting up-to-date maintenance logs for inspection.
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| ARCA: None.
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| : 3. Direction and Control.
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| Demonstrate the capability to direct and control emergency Yes Yes operations.
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| Extent ofPlay.
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| Direction and control of all State and local emergency operations will be demonstrated by the appropriate EOC staff in accordance with State and local plans.
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| ARCA: None.
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| : 4. Communications.
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| Demonstrate the capability to communicate with all appropriate Yes Yes emergency personnel at facilities and in the field.
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| Extent ofPlay.
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| State and local emergency response personnel, including field teams will demonstrate the capability to communicate with appropriate vyenopt.97 2 January 14.1997
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| _-_. _ _ ____ - - - _ _w__ _ - - _ _ _ _ . _ _ _ _ - _ _ _ _ - - - - - _ _ - _ _ - - - _- ___-----_\- _ - _ _ . _ _ -_-_ _ __s
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| t i
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| Rhr-14 OBJECTIVES STATE OF VERMONT ~ LOCAL JURISDICTION !
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| locations. This includes communications between utility and State facilities personnel and between State and Local facilities personnel. ;
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| Coordinated response efforts between all participating states will be demonstrated.
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| ARCAS:
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| Issue No.: 67-95-04-A-01 There was a fax machine over load and fax machine problems i that delayed the information flow to towns. Too much information was provided. l (refer to 1995 Exercise Report, pg 28). :
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| Issue No.: 67-95-04-A Fax problem with the Vermont Public :
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| Information Officer et the JIC (Joint Information Center / Media Center). ;
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| (refer to 1995 Exercise Report, pg 31). ;
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| i Unresolved Issue No.: 93-31: Consultation between the Nuclear Information Director and the Site Recovery Manager concerning the !
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| ! News Media Habitability did not take place in accordance with procedures.
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| (Refer to 1995 Exercise Report, pg 32).
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| : 5. Emergency Worker Exposure Control. t Demonstrate the capability to continuously monitor Yes Yes and control radiation exposure to emergency workers.
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| Extent ofPlay. .
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| Each off-site organization having a responsibility for emergency workers (IFO, Local EOCs, & Field Monitoring Teams) will utilize appropriate dosimetry '
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| to control radiation exposure. The IFO and local EOC's will demonstrate i the capability to issue, zero, and read dosimeters and record readings. Each !
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| emergency worker will be issued an emergency worker packet. Procedures ,
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| will be demonstrated to manage exposure of emergency workers.
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| ARCAS: l Issue No.: 67-95-05-A Dosimetry used did not show the latest calibration date I at Brattleboro EOC (refer to 95 Exercise Report, pg 39). !
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| i Issue No.: 67-95-05-A Brattleboro EOC staff did not periodically read their DRDs !
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| i vyexopl.97 3 January 14,1997 f
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| . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - . - _ _ _ . _ - - . _ - . z_ -- _._ _ _ _ _ . _ - - _ - _. . . . - - - _- -_
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| Rin -14 OBJECTIVES STATE OF VERMONT LOCAL JURISDICTION ,
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| (refer to 95 Exercise Report, pg 39).
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| Issue No.: 67-95-05-A Dummerston EOC staff did not read their DRDs every 30 minutes or every 15 minutes after release and were not aware of their maximum exposure limit (refer to 95 Exercise Report, pg 39).
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| Issue No.: 67-95-05-A No record of electrical leakage testing, calibration or inspection for instruments at Dummerston EOC (refer to 95 Exercise Report, pg 4 I).
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| Issue No.: 67-95-05-A Dosimeters lacked evidence of being inspected for electrical leakage at Guilford EOC (refer to 95 Exercise Report, pg 45).
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| Unresolved Issue No.: 93 Systemic problem with dosimetry Dummerston, pg 42 -Inspection records or calibration of survey instruments were not available.
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| Ifalifax, pg 44 -Failed to issue dosimetry to staff, dosimeters and survey instruments showed no evidence of inspection for electrical lenkage or calibration.
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| : 6. Field RadiologicalMonitoring-Ambient Radiation Monitoring. Yes N/A Demonstrate the appropriate use of equipment and procedures for determining field radiation measurements.
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| Extent ofPlay.
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| * Two 2 person teams will be fielded for plume monitoring during the exercise. 3 Teams will take sample measurements in keeping with scenario events at pre-selected sampling sites. Teams will inventory and perform operational .
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| checks on their equipment the day before the exercise at the Department of lfcalth in Burlington. FEMA is invited to inspect this inventory and operational ,
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| check at that time. FEMA will notify the VT Ilealth Dept. (802-863-7730) by March l 17,1997 if they are unable to inspect the teams in Burlington on the 18'". In the event i that FEMA cannot inspect the equipment on the 18'", arrangements for inspection prior to the Alert stage of the exercise will be made. Otherwise, the teams will take this ;
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| pre-checked equipment to their pre-staging location to be dispatched the next day for scenario-related field measurements.
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| vyexopl.97 4 January 14,1997 I
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| i
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| Rb. -14 OBJECTIVES STATE OF VERMONT LOCAL JURISDICTION ARCAS:
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| Unresolved Issue No.: 93 Revise ingestion pathway sampling kits to contain proper equipment (CD V-138 dosimeter),(refer to 95 Exercise Report, pg 35 and 36)
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| Unresolved Issue No.: 93 Outdated sample tags and two copies of sampling procedures, each with different instructions,(refer to 95 Exercise Report, pg 35 & 37).
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| : 7. Plume Dose Projection. Yes N/A Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering.
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| Extent ofPlay.
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| The State will demonstrate the capability to Iccate the plume and develop dose projections based on utility information and field team data. From this information the State will develop appropriate protective action recommendations. Initial PAR's may be derived solely from utility information. Additional field team data may be utilized to adjust initial PAR's.
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| ARCA: None
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| : 8. Field Radiological Monitoring-Airborne Radiciodine and Particulate Activity Monitoring.
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| Demonstrate the appropriate use of equipm nt and procedures for Yes N/A for the measurement of airborne radioiodine concentrations as low as (10-7) 0.0000001 microcurie per cur centimeter in the presence of noble gases and obtain samples of particulate activity in the airbome plume.
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| Extent ofPlay.
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| Field teams will perform operational checks of equipment the day before the exercise (Refer to Exercise Objective #6). Airborne radioiodine and particulate samples are taken in accordance with vyexopl.97 5 january 14,1997 g - - _
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| o
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| RE. -i4 OB3ECrlVES STATE OF VERMONT LOCAL JURISDICTION procedures. Field teams will measure radioiodine and particulate matter outside of plume. Field teams will transmit data to the llealth Services Coordinatcr in accordance with procedures. Samples will be prepared for transportation with appropriate packaging and labeling. Transportation will be simulated. Each field team will take one sample.
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| ARCA: None.
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| : 9. Plume Protective Action Decision making.
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| Demonstrate the capability to make timely and appropriate Yes N/A protective action decisions (PAD).
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| Extent ofPlay. i State decision makers will demonstrate the ability to make initial and subsequent PADS. coordination with o herjurisdictions, n
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| (i.e., Nil and M A) will be demonstrated.
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| ARCA: None
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| : 10. Alert & Notification.
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| Demonstree the capability to promptly alert and notify the public Yes Yes within L .10-mile plume pathway emergency planning zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials.
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| Extent ofPlay.
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| Actions for public alerting and notification will be demonstrated up to the point of actual activation of NOAA transmitter, sounding of sirens and broadcast of EBS messages. NOAA activation of weather alert radios and EBS broadcasts will be simulated. Brattleboro and Vernon will simulate the sounding of their sirens. The public alerting and notification process will include demonstrating the vycupt.97 6 January 14,1997
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| 7 's .
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| Rt.. -14 OBJECTIVES STATE OF VERMONT LOCAL JURISDICTION necessary coordination of time sequence activities with New Itampshire. Massachusetts and resyctive Vermont towns.
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| Towns will demonstrate actions up through the receipt of activation times to simulate siren sounding and will demonstrate capability to monitor EBS broadcast messages. (NOTE Only Vernon and Brattleboro have sirens.)
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| 1
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| : 11. Public Instruction and Emergency Information.
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| Demonstrate the capability to coordinate the formulation Yes N/A and dissemination of accurate information and instructions to the public.
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| Extent ofPlay.
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| The State will demonstrate the capability to formulate and disseminate information and instructions to the public. The State will demonstrate coordination of message content with other appropriate staffjurisdictions, organizations, facilities and States (Nil, M A). The State will demonstrate the capability to provide instructions to the public including information on the initiation and implementation of protective actions. Information should delineate local government jurisdictions affected by the message.
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| Vermont will continue to use the EBS system under the existing standards.
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| The EAS system in Vermont will not be fully implemented in time for this exercise.
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| ARCA: None.
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| : 12. EmergencyInformation-Afedia.
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| Demonstrate the capability to coordinate the development and Yes Partial dissemination of clear, accurate, and timely information to the news media.
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| Extent ofPlay.
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| The State designated spokesperson will coordinate activities and participate ,
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| in joint briefings with the media at the News Media Center (JIC) at the Vermont Yankee Corporate Office in Brattichoro. The State EOC will vyexopi.97 7 January 14,1997
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| l l RE. -14 OBJECTIVES STATE OF VERMONT LOCAL JURISDICTION t
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| l provide updated information to the News Media Center. The local l EOC's will refer media questions not related to town specific activities to .
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| the News Media Center. The local town option to generate news releases about their scwn r; xific activities will be simulated at the discretion of the town.
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| ARCA: Unresolved Issue No.: 93 Utility spokesperson did not discuss the News Media Center habitability with the News Media staff (refer to 95 Exercise Report, pg 32).
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| : 13. Emergency information-Rumor Control j Demonstrate the capability to establish and operate rumor control in a Yes N/A '
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| coordinated and timely manner.
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| i Extent ofPlay.
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| The State EOC has a rumor control number publicized in mailings to residents within the 10-mile EPZ. the State EOC will notify the State representative at the News Media Center (JIC) of the nature of the rumor. Controllers will issue appropriate number of calls to the Rumor Control number at the State EOC. [
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| State EOC rumor control operator will field a minimum of six calls per hour.
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| t ARCA: None t
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| : 14. Implementation ofProtective Actions - Use ofKIfor
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| ; Emergency Workers, institutionalized individuals and l the GeneralPublic. .
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| Demonstrate the capability and resources to implement Yes Yes ,
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| potassium iodide (KI) protective actions for emergency workers and institutionalized individuals. '
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| Extent ofPlay.
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| The State will make the determination to authorize use of K1 by t emergency workers, and institutionalized individuals. Local plans call for KI to be issued to emergency workers with their dosimetry when dispatched to field assignment. KIissue will be simulated. [
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| Emergency workers will simulate the ingestion of KI when authorized i
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| vycxopl.97 8 January 14.1997
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| Rhi -14' ~OBJECriVES STATE OF VERMONT LOCAL JURISDICrlON by the State Health Department through the local EOC coordination.
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| Distribution and ingestion of KI will be simulated during the exercise.
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| The state of Vermont does not supply KI to the general public.
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| ARCA: 93-5 Emergency workers at the Italifax EOC were not informed of the possibility of having to take KI. The RAD Officer was aware of the necessary instructions for the issuance of KI but Emergency Workers were not briefed.
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| : 15. Implementation ofProtective Actions-Special Populations Demonstrate the capability and resources necessary to implement Yes Yes appropriate protective actions for special populations.
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| Extent ofPlay.
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| FEMA will interview the Director of the Eden Park Nursing flome re: Emergency Plan. The State will notify local EOC's to alert special populations within the areas identified for protective actions.
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| Local EOC's wi:1 identify special population groups. All towns will show special populations roster and the ability to implement that notification procedure. Actual contact will be simulated.
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| The directors of the following four camps, campgrounds, or parks will be interviewed by a FEMA evaluator in the Summer of 1997.
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| Hidden Acres- Dummerston KOA- Dummerston Fort Dummer- Brattleboro, Camp Waubanoug- Brattleboro ARCA: None
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| : 16. Implementation ofProtective Actions-Schools. Yes Yes
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| , Demonstrate the capability and resources necessary to implement protective actions for school children within the plume pathway emergency planning zone (EPZ).
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| ARCA: Issue No.: 67-95-16-A During school interview at vycxopt.97 9 January 14,1997
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| l 1
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| Rbr-14 OBJECTIVES STATE OF VERMONT LOCAL JURISDICTION l
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| \
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| Guilford Central School, the principal indicated school officials and bus drivers need training in dosimetry instruments and techniques of their use (refer to 95 Exercise Report, pg 49).
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| Extent ofPlay.
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| 4 Out of Sequence FEMA Interviews with 5 School Principals ;
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| and i Superintendent on the day following the exercise. ,
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| The Austine School Dumerston Elementary School Guilford Central School e The Neighborhood School. j i The Superintendent of the Windham South West Supervisory Union (WSWSU).
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| llatifax West School ,
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| Additionally a school bus driver from Laidlaw Transportation will demonstrate out l of sequence (the mid morning after the exercise) by interview how the evacuation j
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| . from the Vernon Elementary School to the Reception Center at Bellows Falls Union !
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| liigh School would be conducted.
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| i 1
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| .17 Traffic und Access Control. l Demonstrate the organizational capability and resources necessary Yes Yes to control evacuation traffic flow and to control access to evacuated and sheltered areas.
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| Extent ofPlay.
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| State and local EOC's consistent with the developing scenario events and PARS will determine the location of TCP/ACP's. Selected local ;
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| towns in the EPZ impacted by scenario events will deploy personnel to a single TCP/ACP. In the event that the scenario does not impact a Vermont town, Halifax and Guilford will deploy personnel to a single TCP/ACP in each town. t ARCA: None. !
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| : 18. Reception Center - Monitoring Decontamination, and Registration. Yes Yes ;
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| Demonstrate the adequacy of procedures, facilities, equipment (See Extent of play.) ;
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| vycxop t.97 10 January 14,1997
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| [
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| I
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| - . ._ _- . . _ . . . _ . . . . -- . , . - - . _ . , . . _ _ . . _ . _ - . . . - . - - - . . - . . , . . _ __ __._. ?
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| REr-14 OBJECTIVES STATE OF VERMONT LOCAL JURISDICTION and personnel for the radiological monitoring, decontamination and registration of evacuees. Monitor and decon two vehicles. ;
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| Extent of Play. The state EOC will demonstrate the Reception .
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| Center notification procedure. This notification will go through the IFO to the Westminster Emergency Director. The Westminster ,
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| Emergency Director will operate the radios and simulate message ,
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| traffic to the extent consistent with the operation of the Bellows Falls Union fligh School (BFUllS.) FEMA is invited to observe the Reception Center exercise at BFUllS in the Summer of 1997.
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| ARCA:
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| 67-9618-A-01 An operability source for compliance with the portal L monitor standard was not done because it was not called for in the <
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| Reception Center Radiation Specialist's checklist.
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| 67-96-18-A-02 Survey instmments were not calibrated annually.
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| : 19. Congregate Care.
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| 4 Demonstrate the adequacy of facilitics, equipment, supplies, personnel, and procedures for congregate care of evacuees. .. No
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| . No !
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| Extent of Play. Adequately demonstrated in 1995. I i
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| ARCA: None -
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| : 20. MedicalServices - Transportation.
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| Demonstrate the adequacy of vehicles, equipment, procedures Will be demonstrated and personnel for transporting contaminated, injured or during MS-1 Drill in Summer of 1997.
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| exposed individuals j i
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| ARCA:
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| 67-%-20-A-01 A range of readings was not included on the instrument !
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| or in its carrying box.
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| i vyenopl.97 II January 14,1997 i
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| "~ ~ ~ '
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| Rbe -14 OBJECTIVES STATE OF VERMONT LOCAL' JURISDICTION 67-%-20-A-02 While monitoring with the llF-210 pancake probe, the probe touched crew members and the stretcher being monitored, possibly spreading contamination.
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| 2I. MedicalServices - Facilities.
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| Demonstrate the adequacy of the equipment, procedures, supplies Will be demonstrated and personnel of medical facilities responsible for treatment of during MS-1 Drill contaminated, injured, or exposed individuals In Summer of 1997.
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| ARCA:
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| 67-%-20-A-03 During the de-gowning process, one staff member removed one potentially contaminated glove and then used the inner, clean glove to remove the other outer glove.
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| This step could potentially cross contaminate the staff worker unnecessarily.
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| : 22. Emergency Workers, Equipment, and Vehicles-Monitaring and Decontamination. Yes N/A Demonstrate the adequacy of procedures for the monitoring and decontamination of emergency workers, equipment and vehic!cs.
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| Extent of Play. The IFO will demonstrate decontamination of I female, I male, and 2 vehicles in sequence on the Exercise day..
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| ARCA: None '
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| t l 23. Supplementary Assistance (FederaV0ther).
| |
| Demonstrate the capability to identify the need for external No N/A assistance and request such assistance from Federal or other support organizations.
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| Extent ofPlay. Adequately demonstrated in 1995. I t
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| vycxopt.97 12 january 14,1997 l
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| t
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| ~' - I
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| _ . ~ __ _ . - . _ _ - . _..
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| RE -14 OBJECTIVES STATE OF VERMONT LOCAL JURISDICTION ARCA: None :
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| : 30. Continuous 24 Hour Staffing.
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| Demoastrate the capability to maintain staffing on a continuous Yes Yes 24 hour basis through an actual shift change. ,
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| l Extent of Play.
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| Key personnel will demonstrate a shift change prior to the mid-point of the exercise which will be activated by a controller. The following organizations will demonstrate a shift change in 1997:
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| State EOC in Waterbury IFO in Dummerston (including IIcalth Dept field teams)
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| Brattleboro Town EOC Guilford Town EOC Vernon Town EOC The reminder will demonstrate in 1998.
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| i 4
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| VM9 I 13 January 14,1997
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| l l OBJECTIVES BY ORGANIZ. ON/ LOCATION
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| | |
| ==SUMMARY==
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| ORGANIZATION / LOCATION OBJECTIVE NUMBER l
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| Vermont State EOC 1,2,3,4,5',7,8',9,10,11,12',13,14',16',17,30 State Warning Point 1,4 ;
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| Department ofIIcalth Laboratory I,62,8 5 Emergency Operations Facility (EOF) 1,2,4 !
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| ! News Media Center (JIC)-VT Staff 1,2,4,11,12,13' Emergency Alert system Station (WTSA) 0 Incident Field Office 1,2,3,4,5,14,17,22,30 Reception Center l *,18*
| |
| i Brattleboro EOC 1,2,3,4,5,10,11,12,14,15,175 ,30 l I,2,3,4,5,10,11,12,14,15, 17 5 Dummerston EOC Guilford EOC 1,2,3,4,5,10,11,12,14,15,175,30 Halifax EOC 1,2,3,4,5,10,11,12,I4,15, 17 5 Vernon EOC 1,2,3,4,5,10,11,12,14,15,175,30 State Field Monitoring teams 4,5,6,8,14 l Special Population Centers Brattleboro Campgrounds (Summer 97)
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| Fort Dummer 15 ,
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| Camp Waubanoug 15 Dummerston Campgrounds (Summer 97) ,
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| flidden Acres 15 i
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| KOA 15 Schools AND Day Care Centers The Austine School 16 t Dummerston Elementary School 16 !
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| Guilford Central School 16 !
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| The Neighborhood School 16 l Superintendent of WSWSU 16
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| : Superintendent of WSESU 16' Italifax West School 16 :
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| Legend: l
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| ' Provides directional control.
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| * Very limited participation. i 5 '
| |
| Equipment checkout occurs here. If the scenario does not impact a Vermont town, llalifax &
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| ' Simulated Transportation of Samples would go here. Guilford will each deploy personnel to a single TCP/ACP.
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| vycxop t.97 14 January 14,1997 i
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| . - _ . .. - - - . - - . . . ..-. .. _-. - ..-..- . . _.. .. - . - ._ - - - - . . - .- ~ .
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| f e
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| 4 VERMONT YANKEE NUCLEAP POWER STATION EMERGENCY PREPAREDNESS EXERCISE I 1997 1
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| l
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| )
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| 1 i
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| 1 5
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| ; 2.3 ETATE OF NEW HAMPSHIRE - EXERCISE OBJECTIVES AND EXTENT OF PLAY i
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| i b
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| i 1
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| i a
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| P 4
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| 0 4 b
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| l L
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| I STATE OF NEW. HAMPSHIRE 1997 PLUME EXPOSURE PATHWAY EXERCISE VERMONT YANKEE NUCLEAR POWER STATION 1/08/97 OBJECTIVES AND EXTENT OF PLAY OBJECTIVE #1 :
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| MOBIT 17ATION OF EMERGENCY PERSONNEL : .
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| Demonstrate the capability to alert and fully mobilize personnel for both l emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY PHASE -
| |
| Emergency facilities will be alerted in accordance with the NHRERP.
| |
| Those facilities which are to participate in the exercise will mobilize accordingly.
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| Rosters for relief shifts will be available in each participating facility. Those :
| |
| facilities that are not participating will acknowledge receipt of notification, but )
| |
| will take no further action. Controllers will simulate facilities not participating. !
| |
| Monitoring Teams and New Hampshire personnel at the News Media Center, EOF, and IFO will be pre staged.
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| 1 FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
| |
| STATE EOC, EOF, NEWS MEDIA CENTER, LOCAL EOC'S: !
| |
| HINSDALE, WINCHESTER, CHESTERFIELD, SWANZEY, RICHMOND l AND KEENE (host), STATE WARNING POINT, SOUTHWEST NEW I HAMPSHIP.E DISTRICT FIRE MUTUAL AID.
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| AREAS REOUIRING CORRECTIVE ACTION :
| |
| 67-95-01-A-16: Winchester selectmen did not provide coverage for key positions in local EOC.
| |
| OBJECTIVE #2 : ,
| |
| FACILITIES-EOUIPMENT. DISPLAYS AhT) WORK ENVIRONMENT : l 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.
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| i 1/08/97 .
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| I 1.3-1 l l
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| l
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| FACTITTfFR DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE j - PATHWAY PHASE :
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| ' STATE EOC, EOF, NEWS MEDIA CENTER, LOCAL EOC'S: .
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| HINSDALE, WINCHESTER, CHESTERFIELD, SWANZEY, RICHMOND j AND KEENE (host), STATE WARNING POINT, SOUTHWEST NEW j
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| : HAMPSHIRE DISTRICT FIRE MUTUAL AID. !
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| i i
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| AREAS REOUIRING CORRECTIVE ACTION :
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| 2 None Cited i
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| - OBJECTIVE #3 : :
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| DIRECTION AND CONTROL :
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| Demonstrate the capability to direct and control emergency operations.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY PHASE: 1 Participating state and local facilities will demonstrate their ability to direct and control emergency operations in accordance with the NHRERP.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
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| STATE EOC, EOF, NEWS MEDIA CENTER, LOCAL EOC'S: HINSDALE, '
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| WINCHESTER, CHESTERFIELD, SWANZEY, RICHMOND AND KEENE (host), STATE WARNING POINT, SOUTHWEST NEW HAMPSHIRE DISTRICT FIRE MUTUAL AID.
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| 3 AREAS REOUIRING CORRECTIVE ACTION 67-87-03-A-29 EOF Water Sample locations were not based on phme monitoring.
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| 67-95-03-A-17 Winchester EOC did not inform school of General Emergency classification.
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| OBJECTIVE #4 :
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| COMMUNICATIONS :
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| Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and in the field. ;
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY PHASE :
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| Facilities participating in the exercise will demonstrate the primary and a back up communications resource per facility.
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| 1/08/97 1 l
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| 1.3-2 .
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| ^
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| FACILITE DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE
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| $ PATHWAY PHASE :
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| STATE EOC, EOF, NEWS MEDIA CENTER, LOCAL EOC'S: HINSDALE, WINCHESTER, CHESTERFIELD, SWANZEY, RICHMOND AND KEENE (host), STATE
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| ; WARNING POINT, SOUTHWEST NEW HAMPSHIRE DISTRICT FIRE MUTUAL AID,
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| ' MONITORING TEAMS.
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| i 4 AREAS REOUIRING CORRECTIVE ACTION -
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| ! 67-87-42-A- Field Monitoring Team Experienced difficulty communicating from
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| ; the field to the ifo by radio and telephone.
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| i
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| : OBJECTIVE #5 :
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| I EMERGENCY WORKER EXPOSURE CONTROL :
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| : Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers.
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| j EXTENT OF PLAY PLUME EXPOSURE PATHWAY -
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| This objective will be demonstrated in accordance with the NHRERP by facilities that participate in the exercise.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPQS1!RE PATHWAY PHASE -
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| LOCAL EOC'S: HINSDALE, WINCHESTER, CHESTERFIELD, !
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| SWANZEY, RICHMOND AND KEENE (host), FIELD TEAMS, TROOP C, ,
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| NHDOT, EPZ EMERGENCY WORKERS (Traffic and Access Control) .
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| AREAS REOUIRING CORRECTIVE ACTION :
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| 67-95-05-A-18 Winchester EOC Second Shift RADEF officer did not know the authorized exposure limits.
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| 67-95-05-A-21 Keene not all Emergency Workers were familiar with exposure ;
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| limits.
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| OBJECTIVE #6 : )
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| i FIFT n RADIOLOGICAL MONITORING-AMBIENT RADIATION MONITORING -
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| Demonstrate the appropriate use of equipment and procedures for -
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| determining field radiation measurements.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| Two NHDPHS radiological monitoring teams will be dispatched. Three monitoring points per team will be monitored.
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| h 1/08/97 1.3-3 ,
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE -
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| FIELD MONITORING TEAMS AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited.
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| 1 OBJECTIVE #7 :
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| PLUME DOSE PROJECTION:
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| Demonstrate the capability to develop dose projections and protective
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| ! action recommendations regarding evacuation and sheltering.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY -
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| This objective will be demonstrated in accordance with the NHRERP in the context of the exercise scenario. METPAC, PHAAP, and other accident l assessment programs will be used.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING T[~E PLUME EXPOSURE PATHWAY PHASE :
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| STATE EOC.
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| ! AREAS REOUIRING CORRECTIVE ACTION -
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| 67-95-07-A-10 State EOC NH dose assessment team needs to effectively use monitoring teams to locate plume boundaries 67-95-07-A-11 State EOC NH dose assessment team over looked data transmitted by the EOF.
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| l OBJECTIVE #8 :
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| FIELD RADIOLOGICAL MONITORING-AIRBORNE RADIOIODINE AND PARTICULATE ACTIVITY MONITORING :
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| Demonstrate the appropriate use of equipment and procedures for the
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| ! measurement of airborne radioiodine concentrations as low as 10'-7 (0.0000001) l Microcurie per cubic centimeter in the presence of noble gasses and obtain samples of particulate activity in the airborne plume.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY : .
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| This objective will be demonstrated in accordance with the NHRERP.
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| Use of Silver Zeolite filter media will be simulated by charcoal filter cartridges.
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| Cartridges will be prepared for transportation to the EOF for analysis.
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| AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited l
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| 1/08/97 1.3-4 r
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| l OBJECTIVE #9 :
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| PLUME PROTECTIVE ACTION DECISION MAKING :
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| Demonstrate the capability to make timely and appropriate protective action decisions (PAD).
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| This objective will be demonstrated by the state decision making team in accordance with the NHRERP. Local organizations will be notified and respond '
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| in accordance with their' plans and procedures according to the recommended protective action. t The New Hampshire decision making team will discuss its decisions with the Vermont and Massachusetts decision making teams and coordinate public notification activity.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSU PATHWAY PHASE :
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| STATE EOC.
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| 1 AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited OBJECTIVE #10 :
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| ATFRT AND NOTIFICATION:
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| Demonstrate the capability to promptly alert and notify the public within the 10-mile Plume Pathway Emergency Planning Zone (EPZ) and disseminate i instructional messages to the public on the basis of decisions by appropriate state or local officials.
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| EXTENT OF PLAY PLUME EXPOSURE :
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| Activation of NOAA Weather Radios, Sounding of sirens and broadcast of I EBS messages will be simulated. EBS messages will be formulated and 4
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| distributed by the New Hampshire EOC in accordance with the NHRERP.
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| Simulation of the activation of the EBS system will be coordinated with Vermont and Massachusetts officials. WKNE will receive EBS messages in accordance with the NHRERP but will not broadcast any messages.
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| EPZ communities will demonstrate this objective 'through the receipt of ;
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| activation times from their local liaisons and will demonstrate their capability to monitor NOAA and EBS stations.
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| FACILITIES DEMONSTRATING THIS OBP3CTIVE DURING THE PLUME EXPOSU PATHWAY PHASE :
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| STATE EOC, WKNE, SOlfsH WEST NEW HAMPSHIRE DISTRICT FIRE MUTUAL AID. .! '
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| l 1/08/97 1.3-5 t
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| AREAS REOUIRING CORRECTIVE ACTION :
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| Nors Cited '
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| OBJECTIVE #11 :
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| PUBLIC INSTRUCTIONS AND EMERGENCY INFORMATION -
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| Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instructions to the public.
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| 3 EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| Public infonnation messages will be developed periodically. Messages will be developed based upon scenario information. Broadcast of these messages 1 will be simulated. The messages will be distributed to the EOF, IFO, News
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| ! Media Center and WKNE by the NH EOC.
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| Local EOCs will receive information concerning protective action recommendations from their respective local liaison. Local EOCs do not prepare public information messages and do not have a representative at the News Media i Center. Local EOCs will monitor NOAA and EBS radios per their procedures.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE t PATHWAY PHASE :
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| STATE EOC, NEWS MEDIA CENTER. -
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| AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited i
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| .QBJECTIVE #12 :
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| EMERGENCY INFORMAT1QN -NEM Demonstrate the capability to coordinate the development and dissemination of clear, accu ate, and timely information to the news media.
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| EXTENT OF PLAY PLUME EXIOSURE -
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| The demonstration of this objecdve occurs at the state EOC , the News Media Center. Controllers will simulate media response.
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| The primarv rerponsibility for briefing the media with respect to off site activities in New Hampshire lies with the State. New Hampshire will coordinate its' media information with Vermont, Massachusetts and Vermont Yankee in accordance with the NHRERP.
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| EPZ community officials may respond to questions about local emergency l response but are encouraged to refer press inquires to the News Media Center. A l controller message will be generated for each community to initiate a response and referral to media inquiries made to local officials.
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| : 1/08/97 1.3-6 i
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| : FACTIITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE l PATHWAY PHASE :
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| STATE EOC, NEWS MEDIA CENTER, LOCAL EOC'S: HINSDALE, i WINCHESTER, CHESTERFIELD, SWANZEY, RICHMOND AND KEENE
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| : (host) .
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| 1 AREAS REOUIRING CORRECTIVE ACTION -
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| ; None Cited OBJECTIVE #13_;
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| j EMERGENCY INFORMATION-RUMOR CONTROL :
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| j- Demonstrate the capability to establish and operate rumor control in a
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| : coordinated and timely manner.
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| 3 EXTENT OF PLAY PLUME EXPOSURE PATHWAY -
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| l In accordance with the NHRERP, demonstration of this objective will
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| ;l occur at ue News Media Center. Incoming calls will be provided by controllers.
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| j At least one false or misleading rumor relating to PARS will be provided by the i controllers. Calls to the rumor control center whl occur at a rate of at least six l per hour per operator during the Site grea Em:rgency and General Emergency l
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| ] levels. Rumor control personnel will,treen utessages for trends. Communities l
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| will refer calls which address issues beyond local jurisdiction to the rumor control i number. A controller message will be gnerated for each community to inhte a j response and referral of information. -
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| l FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE l PATHWAY PHASE : -
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| NEWS MEDIA CENTER.
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| l AREAS REOUIRING CORRECTIVE ACTION - <
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| None Cited i OBJECTIVE #14 -
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| IMPLEMENTATION OF PROTECTIVE ACTION-USE OF KI FOR EMERGENCY j WORKERS. INSTITUTIONALIZED INDIVIDUA1 R.AND THE GENERAL PUBLIC : l Demonstrate the capability and resources to implement Potassium Iodide {
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| (KI) protective actions for emergency workers, institutionaliied individuals,and if the state plan specifies the general public. l l
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| 1 EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| The decision to use or not use KI for emergency workers and l institutionalized individuals will be demonstrated at the State EOC. The capability '
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| to distribute and administer KI will be demonstrated at appropriate state and local facilities. Actual distribution of KI to emergency workers and institutionalized individuals will be simulated. No KI will be administered.
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| I 1/08/97 l l
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| 1.3-7
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| 1 Quantities of KI are stored at local EOC's, EPZ Nursing Homes and l
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| Hospitals and the IFO. The NHRERP does not provide for the issuance of KI to the general public. Calls to institutions will be simulated.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE l
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| PATHWAY PHASE -
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| STATE EOC, LOCAL EOC'S: HINSDALE, WINCHESTER, CHESTERFIELD, SWANZEY AND RICHMOND, MONITORING TEAMS, l ACCESS AND TRAFFIC CONTROL POINTS (ONE PER JURISDICTION),
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| AREAS REOUIRING CORRECTIVE ACTION : j None Cited !
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| OBJECTIVE #15 :
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| IMPLEMENTATION OF PROTECTIVE ACTIONS-SPECIAL POPULATIONS -
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| Demonstrate the capability and resources necessary to implement appropriate protective actions for special populations.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| 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 populations per their special needs call lists and arrange for appropriate simulated resources to meet the special needs during regular exercise play.
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| Controller messages will simulate requests for assistance. Dispatch of resources and Response to requests for assistance will be simulated..
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
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| LOCAL EOC'S: HINSDALE, WINCHESTER, CHESTERFIELD, SWANZEY AND RICHMOND.
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| AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited i
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| OBJECTIVE #16 : l I
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| IMPLEMENTATION OF PROTECTIVE ACTION-SCHOOLS :
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| Demonstrate the capability and resources necessary to implement protective actions for school children within the Plume Pathway Emergencv Plannmg Zone (EPZ). l I
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY.L Calls will be made to each school to verify transportation resource j requirements. Calls will be made to transportation providers to verify resource 1/0.8/97 1.3-8 9
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| k
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| ~
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| capabilities. Transportation Resources will be simulated. Interviews with school administration officials will take place out of sequence.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE -
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| STATE EOC, LOCAL EOC'S: HINSDALE, WINCHESTER and, CHESTERFIELD (EPZ Schools in Hinsdale, Winchester, and Chesterfield out of sequence).
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| AREAS REOUIRING CORRECTIVE ACTION :
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| 67-95-16-A-13: Hinsdale Julie's Day Care and Children's Nursery School did not receive notification durmg the exercise. ,
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| OBJECTIVE #17 : i TRAFFIC AND ACCESS CONTROL :
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| Demonstrate the organizational- capability and resources to control l evacuation traffic flow and to control access to evacuated and sheltered areas. c EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| Local police will be asked to demonstrate the staffmg of one traffic control point in their jurisdiction. One access control point and the ability to handle a.
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| traffic impediment will be demonstrated by Troop C New Hampshire State Police and NHDOT. Demonstrations will occur during plume exposure pathway phase of the exercise at tunes to be coordinated between Facility Controllers and FEMA !
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| Evaluators. The demonstrations will consist of a talk through of actions that would be taken at the selected ACP, TCP, or impediment sites. Travel to the 1 ACP/ TCP site will be optional. Traffic will not be disrupted.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE l PATHWAY PHASE -
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| )
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| LOCAL EOC'S: HINSDALE, WINCHESTER, SWANZEY, ;
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| RICHMOND and, CHESTERFIELD, TROOP C, NH DOT. l AREAS REOUIRING CORRECTIVE ACTION :
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| 67-95-17-A-14 Richmond Police were not available to set up the required Traffic Control Point.
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| OBJECTIVE #18 :
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| RECEP'110N CENTER-MONITORING. DECONTAMINATION. AND REGISTRATION :
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| Demonstrate the adequacy of procedures facilities, equipment, and personnel for the radiological monitoring, decontammation, and registration of evacuees.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| Activities at the Keene Reception Center will be simulated.
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| 1/08/97 1.3-9 s
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| EACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE
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| . PATHWAY PHASE :
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| ; Activities will be simulated.
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| l .
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| l AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited l l
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| OBJECTIVE #19 :
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| l CONGREGATE CARE :
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| l Demonstrate the adequacy of facilities, equipment, supplies, personnel, and procedures for congregate care of evacuees.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| The Congregate care centers will not be activated. A tour of new congregate care facilities that support the Keene reception center will be conducted with a controller and an ARC representative independently and out of sequence.
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| I FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSIBE PATHWAY PHASE :
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| THERE ARE NO NEW CONGREGATE CARE FACILITIES SUPPORTING KEENE. ,
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| AREAS REOUIRING CORRECTIVE ACTION:
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| None Cited OBJECTIVE #20 :
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| MEDICAL SERVICES-TRANSPORTATION :
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| Demonstrate the adequacy of vehicles, equipment, procedures, and personnel for transporting contaminated, injured or exposed individuals.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| This objective was demonstrated during the November 1996 MS-1 drill.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
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| KEENE FIRE DEPARTMENT EMS AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited r- 1/08/97 1.3-10 L
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| d OBJECTIVE #21 : ,
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| ; MEDICAL SERVICES-FACILITIES -
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| Demonstrate the adequacy of the equipment procedures, supplies, and '
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| personnel of medical facilities responsible for treatment of contaminated, injured, or exposed individuals.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| This objective was demonstrated during the November 1996 MS-1 drill.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
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| j 1 1
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| CHESHIRE MEDICAL CENTER AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited 1
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| OBJECTIVE #22 :
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| l EMERGENCY WORKERS. EOUIPMENT. AND VEHICIFR- MONITORING AND i DECONTAMINATION -
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| " Demonstrate the adequacy of procedures for the monitoring and decontamination of emergency workers, equipment and vehicles.
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| 1 5
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| 3 EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| ; The activation and operation of this facility will be simulated. The j emergency worker monitoring /decon facility in Keene has been evaluated during
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| ; past exercises with no negative comments.
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| i I
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
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| THE EMERGENCY WORKER FACILITY WILL BE SIMULATED.
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| AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited OBJECTIVE #23 - .
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| SUPPLEMENTARY ASSISTANCE (FEDERAL /OTHER) :
| |
| Demonstrate the capability to identify the need for external assistance and to request such assistance from Federal or other support organizations.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| American Red Cross and Civil Air Patrol will send representatives to facilities in accordance with the NHRERP. New Hampshire will coordinate its requests for supplementary assistance with Vermont and Massachusetts pursuant to the NHRERP. The Compact Adnunistrator of the New England Radiological Health Compact is responsible for coordination of technical assistance for New 1/08/97 1.3-11
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| -1
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| Hampshire, 'Vennont and Massachusetts. The Administrators activity will be simulated.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
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| STATE EOC.
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| AREAS REOUIRING CORRECTIVE ACTION -
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| None Cited t
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| OBJECTIVE #24 :
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| POST EMERGENCY SAMPLING :
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| Demonstrate the use of equipment and procedures for the collection and transportation of samples from areas that received deposition from the airborne plume.
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| EXTENT OF PLAY PLUME EXPOSURE :
| |
| N/A 1
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE 't PATHWAY PHASE :
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| N/A AREAS REOUIRING CORRECTIVE ACTION:
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| None Cited.
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| OBJECTIVE #25 :
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| LABORATORY OPERATIONS:
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| Demonstrate laboratory operations and procedures for measuring and j analyzing samples.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
| |
| The State Laboratory in Concord will demonstrate this objective in ,
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| conjunction with the ingestion pathway phase of the exercise, l FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE I
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| : PATHWAY PHASE :
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| i N/A.
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| AREAS REOUIRING CORRECTIVE ACTION : ,
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| ! None Cited !
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| 1/08/97 l
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| l 1.3-12 6
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| I
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| OBJECTIVE #26 :
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| INGESTION EXPOSURE PATHWAY-DOSE PROJECTION AND PROTECTIVE ACTION
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| . DECISION M AKING -
| |
| Demonstrate the capability to project dose to the public for the Ingestion Pathway and to recommend protective measures.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
| |
| The activity required to demonstrate this objective will occur during the Ingestion Pathway phase of the exercise.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
| |
| N/A AREAS REOUIRING CORRECTIVE ACTION -
| |
| None Cited OBJECTIVE #27 :
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| INGESTION EXPOSURE PATHWAY-PROTECTIVE ACTION IMPIFMENTATION -
| |
| Demonstrate the capability to implement protective actions for Ingestion Exposure Pathway.
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| EXTENT OF PLA.Y PLUME EXPOSURE PATHWAY:
| |
| This objective will not be demonstrated.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE -
| |
| N/A AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited OBJECTIVE # 28 :
| |
| RELOCATION. RE-ENTRY. AND RETURN-DECISION MAKING :
| |
| Demonstrate the capability to develop decisions on relocation, and return.
| |
| EXTENT OF PLAY :
| |
| N/A FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
| |
| N/A ,
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| 1/08/97 1.3-13 L
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| n - -- .-. - , - . . - -
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| l AREAS REOUIRING CORRECTIVE ACTION :
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| : i. None Cited l
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| t OBJECTIVE #29 :
| |
| RFI OCATION. RE-ENTRY. AND RETURN-IMPLEMENTATION -
| |
| Demonstrate the capability to implement relocation, re-entry, and return. l f )
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| j EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
| |
| l This objective will be demonstrated in conjunction with the Ingestion l Pathway phase of the exercise. l l
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| FACILITES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE l
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| ! PATHWAY PHASE : l N/A.
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| AREAS REOUIRING CORRECTIVE ACTION :
| |
| None Cited
| |
| ! OBJECTIVE #30 :
| |
| CONTINUOUS. 24-HOUR STAFFING :
| |
| Demonstrate the capability to maintain staffing on a continuous 24-hour basis through an actual shift change.
| |
| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
| |
| l Second shift staffing of KEY positions will be demonstrated at selected facilities according to procedures. Shift turnover will be prompted by a controller l message at each of the selected facilities.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE :
| |
| SELECTED LOCAL EOC'S: CHESTERFIELD, RICHMOND, SWANZEY, WINCHESTER AND KEENE.
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| AREAS REOUIRING CORRECTIVE ACTION -
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| 67-95-30-A-12 Chesterfield EOC Shift Change not Demonstrated for Key EOC Staff.
| |
| 67-95-30-A-15 Richmond EOC Shift Change not Demonstrated for Key EOC Staff.
| |
| 67-95-30-A-19 Winchester EOC Shift Change not Demonstrated for Key EOC Staff.
| |
| 67-95-30-A-20 Keen Emergency Management Director did not demonstrate Shift Change h
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| i i 1/08/97 :
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| 1.3-14
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| OBJECTIVE #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.
| |
| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EX PATHWAY PHASE :
| |
| N/A.
| |
| AREAS REOUIRING CORRECTIVE ACTION :
| |
| None Cited OBJECTIVE #32 :
| |
| UNANNOUNCED EXERCISE OR DRH L L Demonstrate the capability to carry out emergency response functions in an unannounced exercise or drill.
| |
| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
| |
| This objective will be a scheduled as a separate drill.
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| l i FACILITIES PATHWAY PHASE DEMONSTRATING
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| : THIS OBJECTIVE DURING THE PLUME EXP N/A AREAS REOUIRING CORRECTIVE ACTION :
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| None Cited OBJECTIVE #33 :
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| OFF-HOURS EXERCISE OR DRILL :
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| Demonstrate the capability to carry out emergency response functions during an off-hours exercise or drill. -
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY :
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| The exercise will be conducted during regular working hours.
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| FACILITIES PATHWAY PHASE DEMONSTRATING
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| : THIS OBJECTIVE DURING THE PLUME EXPO N/A 1
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| AREAS REOUIRING CORRECTIVE ACTION -
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| None Cited 1/08/97 l
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| 1.3-15 l
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| | |
| DEJECTIVE #34 :
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| LICENSEE OFF SITE RESPONSE ORGANIZATIONS -
| |
| Demonstrate the capability of licensee off site response organization (licensee (ORO)) personnel to interface with non participating organizations and accomplish coordination essential for emergency response.
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| EXTENT OF PLAY PLUME EXPOSURE PATHWAY -
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| N/A.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE -
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| N/A.
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| ]!XTENT OF PLAY INGESTION PATHWAY -
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| N/A.
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| FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE -
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| N/A.
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| AREAS REOUIRING CORRECTIVE ACTION -
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| None Cited.
| |
| 1/08/97 1.3-16
| |
| | |
| -. ._ . . _. .- ~. . .. - .- . .. . .
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| i l
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| I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 !
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| 1 l
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| l l 2.4 COMMONWEALTH OF MASSACHUSETTS - EXERCISE OBJECTIVES 1
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| AND EXTENT OF PLAY i
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| l 1
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| 1 1
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| l 1
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| i e
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| J k
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| | |
| OBJECTIVES AND EXTENT-OF-PLA Y VERMONT YANKEE NUCLEAR POWER STATIONEXERCISE March 19,1997 OVERVIEW The following locations / organizations are not participating in the 1997 Vermont Yankee Exercise:
| |
| - Radiological monitoring and decontamination station for emergency workers in Colrain and Gill.
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| - Orange Armory Host Facility
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| - UMass, Amherst Host Facility
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| - Transportation Providers
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| - Full Circle School, Bernardston
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| - Colrain Elementary School
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| - Gill Elementary School
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| - Otter Pond Preschool
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| - Northfield Mount Hermon, Gill Campus
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| - Northfield Mount Hermon, Northfield Campus
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| - Linden Hill School,Northfield
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| - Warwick Elementary School
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| - Camp Keewanee, Camp Lion Knoll, Camp Northfield
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| - State Laboratory The following organizations / locations will demonstrate in 1997, but out of sequence:
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| - School bus route escort vehicles in Bernardston, Gill, Northfield and Warwick
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| - Radiological monitoring and decontammation stations for emergency workers in Greenfield and Warwick
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| - Greenfield Community College Reception Center
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| - Mass Care Shelters: Greenfield Armory, Greenfield High School, Federal Street School (shelter surveys only).
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| l December 16,1996 EOP97.VY
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| | |
| d OBJECTIVE 1: MOBILIZATION OF EMERGENCY PERSONNEL Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations.
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| EXTENT OF PLAY:
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| State EOC State EOC emergency wff who normally work at other locations will arrive at the EOC at the times they normally report for work unless they are pagedicalled and directed to
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| ~
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| report for duty at an earlier time. Operations / communications staff will show call-down or computerized lists to the FEMA evaluator.
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| The following State Agencies with primarily Ingestion Pathway responsibilites will not participate at the State EOC in 1997:
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| Department of Food and Agriculture Department of Health. Division of Food and Drug Department of Fisheries, Wildlife, and Environmental Law Enforcement (optional)
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| Department of Environmental Protection Area III EOC - MEMA and other state agency staff who normally work at other locations will arrive at the Area III EOC at the times they normally report for work unless they are paged / called and directed to report for duty at an earlier time. Call-down lists will be shown to the FEMA evaluator. Other emergency staff will be notified in accordance with procedures.
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| EQI - MEMA and MDPH personnel will be prestaged at the EOF.
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| Media Center - MEMA personnel will be prestaged at the Media Center. No MDPH representative will be dispatched to the Media Center, s
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| Field Monitorine Team Personnel - Will be crestaged at the Greenfield EOC. ;
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| Greenfield EOC - Calls to demonstrate the activation of Greenfield C'ommunity College (GCC)
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| Reception Center and the emergency worker radiological monitoring and decontamination station in Greer. field, and to mobilize personnel for the traffic control point at GCC will be made in sequence; however, no personnel will actually be mobilized. Availability of reception center and emergency worker RM&D staff and their ETA were they to actually mobilize will be noted.
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| 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 staffed.
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| Subsequent calls to these locations will be logged at appropriate times but not made.
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| EOP97.VY 2 December 16,1996 1
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| 4
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| | |
| School Suoerintendents' Offices - Will contact transportation providers according to implementing procedures, will tally resources, but will not request the deployment of vehicles and drivers.
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| ARCA 67-95-01-A-27: DEM (Area III) notification will be completed in a timely manner.
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| ARCA 67-95-01-A-30: Northfield key staff as listed in the plan will participate in the exercise.
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| OBJECTIVE 2: FACILITIES-EQUIPMENT, DISPLAYS, AND WORK ENVIRONMENT Demonstrate the adequacy of facilities, equipment, displays and other materials to support emergency operations.
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| EXTENT OF PLAY: No Exceptions b
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| OBJECTIVE 3: DIRECTION AND CONTROL Demonstrate the capability to direct and control emergency operations.
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| ?
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| t EXTENT OF PLAY: No Exceptions ARCA 67-95-03-A-37: Periodic staff briefings will be held in the Warwick EOC to keep i' personnel informed of the emergency situation.
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| ARCA 67-95-03-A-38: The Warwick EMD will ensure that all charts and maps are posted i as soon as possible with the most current data available.
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| 1 1 I OBJECTIVE 4: COMMUNICATIONS Demonstrate the capability to communicate with all appropriate emergency personnel at facilities and the field.
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| EXTENT OF PLAY:
| |
| State EOC. Area III EOC - Contact with locations or organizations that are not demonstrating in -
| |
| 1997 or are demonstrating out of sequence will be simulated by logging a simulated contact at i EOP97.VY 3 December 16,1996
| |
| | |
| the appropriate time (s) in the exercise. Players will indicate to evaluators when calls are being simulated. Copies of contact lists will be shown to the evaluator.
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| Use of radio, the back-up communication system, will be demonstrated between the State and Area III EOCs and by State personnel at the EOF.
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| EPZ Town EOCs - Use of telephone, the backup communication system, will be demonstrated between the EPZ EOCs and the Area III EOC.
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| Participating schools and day care centers will continue to receive all appropriate communications. Upon completion ofinitial contacts, there will be no further communication between the EPZ Town EOCs and the nonparticipating schools. Players will indicate to evaluators when calls are being simulated. Copies of contact lists will be shown to the evaluator.
| |
| Greenfield EOC - Will demonstrate contact once with the town's mass care shelters: The Greenfield Armory, Greenfield High School, and Federal Street School. Subsequent contacts will be simulated by logging the contact at the appropriate times. Players will indicate to evaluators when calls are being simulated. Copies of contact lists will be shown to the evaluator.
| |
| School Sunerintendents' Ofiices - Upon completion ofinitial contacts, no further communications will be made to nonparticipating public schools.
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| Colrain Elementary School Gill Elementary School
| |
| * Linden Hill School, Northfield Warwick Elementary School No calls will be made to Orange Police Department to activate the Orange Armory, but simulated contact will be logged at appropriate times in the exercise.
| |
| Players will indicate to evaluators when calls are being simulated. Copies of contact lists will be shown to the evaluator.
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| Participating schools will continue to receive all appropriate commtinications:
| |
| Pioneer Vallev Recional School District:
| |
| Pioneer Valley Regional School, Northfield
| |
| * Northfield Elementary School
| |
| * Bemardston Elementary School EOP97.VY 4 December 16,1996
| |
| | |
| l
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| * Pearl Rhodes Elementary School, Leyden ARCA 67-95-04-A-22: MEMA Headquarters will notify MSP Troop B when they a::sume control of the NAS line.
| |
| OBJECTIVE 5: EMERGENCY WORKER EXPOSURE CONTROL l
| |
| Demonstrate the ability to continuously monitor and control radiation exposure of emergency l workers. 1 EXTENT OF PLAY EPZ EOCs - Dosimetry distribution will be demonstrated. KI distribution will be simulated by issuing empty bags for KI tablets with dosimetry. Stocks of KI will be available for inspection by the FEMA evaluator at the local EOCs.
| |
| ARCA 67-95-05-A-23: MSP Troop B will distribute dosimeters of the correct scale (0-200mR and 0-20R) according to their plans.
| |
| ARCA 67-95-05-A-25 Area III will follow procedures for informing emergency workers in the field of the need to take KI. Emergency workers will be reminded to review their Dosimetry /KI Briefing Sheets.
| |
| ARCA 67-95-05-A-31 Northfield emergency workers will demonstrate the proper use of dosimetry and radiological exposure control. Preparation and issuance of dosimetry will be demonstrated.
| |
| ARCA 67-95-05-A-32 The Northfield Dosimetry Coordinator's procedure (Dosimetry Trunk Inventory) has been revised to include appropriate supplies of dosimetry for Northfield Elementary School, Pioneer Valley Regional High School, Linden Hill School, and Camp Northfield.
| |
| ARCA 67-95-05-A-39 The Warwick Dosimetry Coordinator will provide adequate briefings on dosimeuy and KI to include a review of the Dosimetry /kl Briefing Sheet.
| |
| Emergency workers will be reminded to periodically review their Dosimetry /KI Briefing Sheets.
| |
| Escort vehicle drivers for Gill Elementary School will demonstrate ARCA 67-95-05-A-43 adequate use of dosimetry.
| |
| ; PRIOR ISSUES - UNRESOLVED 5 December 16,1996 EOP97.VY l
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| l l
| |
| | |
| 93 40, Bernardston EOC: Emergency workers will demonstrate knowledge of radiation control procedures including reponing intervals.
| |
| 93-41, North 5 eld EOC: Dosimetry Coordinator and appropriate EOC staff will demonstrate knowledge of procedures.
| |
| OBECTIVE 6: FIELD RADIOLOGICAL MONITORING-AMBIENT RADIATION MONITORING Demonstrate the appropriate use of equipment and procedures for determmmg field radiation
| |
| . measurements. ,
| |
| EXTENT OF PLAY:
| |
| NIAT Field Te1ms - Two field teams will each demonstrate obtammg two complete samples.
| |
| Controller messages will provide simulated radiation measurements.
| |
| ARCA 67-95-06-A-24: Field Monitoring Teams will ensure that speakers to survey
| |
| ' instruments are turned on at all times.
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| OBECTIVE 7: PLUME DOSE PROECTION Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering.
| |
| EXTENT OF PLAY:
| |
| EQE - MDPH representative at the EOF will Use utility-provided simulated data and/or simulated field team data use to develop dose projections.
| |
| OBECTIVE 8: FIELD RADIOLOGICAL MONITORING-AIRBORNE RADIGIODINE AND PARTICULATE ACTIVITY MONITORING Demonstrate the appropriate use of equipment and procedures for the measurement of airbome radiciodine concentrations as low as 104 (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:
| |
| 6 December 16,1996 EOP97.VY
| |
| | |
| NI AT Field Teams - Two field teams will each demonstrate measurement of airborne radiciodine l concentration of 104microcuries per cubic centimeter and particulate matter, Each team will collect a minimum of 2 samples. Controller injects will provide simulated monitoring data.
| |
| NIAT personnel will prepare sample media for transport and arrange for transport of the sample.
| |
| Actual transport to the designated laboratory for analysis will not be performed. No actual radiological material will be used. ,
| |
| P i
| |
| OBJECTIVE 9: PLUME PROTECTIVE ACTION DECISION MAKING l Demonstrate the capability to make timely protective action decisions (PAD).
| |
| EXTENT OF PLAY: No Exceptions i
| |
| l OBJECTIVE 10: ALERT AND NOTIFICATION )
| |
| Demonstrate the capability to promptly alen and notify the public within the 10-mile plume i
| |
| 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: .
| |
| l State EOC - Actions to demonstrate performance ofinitial notification of the public will be ;
| |
| l performed up to the point of actual transmission of the Emergency Broadcast System (EBS) message. The message will be prepared and the radio stations (WHYN, WHAI, WRSI/WGAM) ,
| |
| l will be contacted. A standard test message will be faxed to the stations and broadcast once at I '
| |
| approximately the time ofinitial notification to the public.
| |
| The Massachusetts State EOC will coordinate with the Vermont and New Hampshire State EOCs on activation of the NOAA tone alen radios. Activation will be simulated; the NOAA tone-alen l radios will not be sounded. .;
| |
| i i
| |
| The 15-minute clock will begin when the Massachusetts, New Hampshire and Vermont Directors agree on EBS, siren. and NOAA tone alen activation time. The 15-minute clock wiil end when the message is received at WHYN.
| |
| EPZ Towns - EOCs will demonstrate the 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.
| |
| Bemardston EOC - Will demonstrate primary route alerting by dispatching one route-alening ..
| |
| s 1
| |
| EOP97.VY 7 December 16,1996 ,
| |
| k
| |
| | |
| _ - . _ - - - . ~ . . . - . -
| |
| vehicle to nm one different route in the town at the time of each activation of the Public Alert & !
| |
| Notification System. The route-alerting will NOT include issuance of the emergency message ;
| |
| over loudspeakers.
| |
| Maesachusetts Denartment of Environmental Manapment (DEMT - The District 9 Fire Warden ,
| |
| will simulate dispatch of one alerting person / team to each of the following areas: {
| |
| Northfield State Forest - open Connecticut River Boat Ramp in Northfield - closed Warwick State Forest in Warwick - open Warwick State Forest in Northfield - open Leyden State Forest - open 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 arrive at District 9 Fire Warden's Office at some time during exercise )
| |
| play to conduct an interview with DEM personnel concerning communications, dosimetry distribution, equipment, maps, and prescripted messages. DEM should play along with the scenario from the beginning and be prepared to discuss actions of the day with the evaluator, i' The FEMA evaluator will accompany field personnel dispatched to the Mount Grace State Forest, which is the most accessible during the winter months. Even though some areas are officially open, road access is limited. Procedures for inaccessible areas will be discussed with the FEMA evaluator.
| |
| Massachusetts Denartment of Fisheries. Wildlife. and Environmental Law Enforcement. Division ;, '
| |
| of Law Enforcement - Will not dispatch of persons / teams to alert, notify, and clear persons from the Connecticut River, nor an access control person / team to Earton Cove. Instead, personnel at the MDFWELE Northampton Office will be interviewed by the FEMA *"aluator who will arrive at scme time during exercise play to conduct and interview conceming equipment, maps, prescripted messages, and dosimetry, and procedures. MDFWELE should play along with the scenario from the beginning and be prepared to discuss actions of the day with the evaluator. The actual alert, notification, and access control will be simulated by displaying appropriate i
| |
| equipment to the evaluator. Since no actual dispatch to will occur, members of the public in the vicinity will not be atTected; no boat will be launched.
| |
| ARCA 67-95-10-A 26: Appropriate equipment for DEM District #9 to notify exception areas has been supplied.
| |
| 8 December 16,1996 EOP97.VY r
| |
| L'
| |
| | |
| OBJECTIVE 11: PUBLIC INSTRUCTIONS AND EMERGENCY INFOIBIATION Demonstrate the capability to coordinate the formulation and. dissemination of accurate information and instructions to the public.
| |
| EXTENT OF PLAY:
| |
| State EOC - Following the initial alert and notification, subsequent contacts to the EBS station will be simulated.
| |
| The MEMA Public Affairs Officer will provide a contact person and number for WHYN to the FEMA evaluator who will interview the EBS contact person regarding the fax receipt time.
| |
| 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:
| |
| Media Center - Controllers will act as media representatives and real media personnel may be present and participate.
| |
| OBJECTIVE 13: EMERGENCY INFORMATION-RUMOR CONTROL Demonstrate the capability to establish and operate rumor control in a coordinated and timely manner.
| |
| EXTENT OF PLAY:
| |
| State EOC - Control cell personnel will make calls simulating members of the public. The rumor control personnel will demonstrate the ability to handle calls on the rumor control line. Handling at least one rumor trend (three or more calls of the same nature) will'be demonstrated. Two rumor control operators will each respond to a minimum of six calls per hour after the Pulhe l
| |
| Alert and Notification System has been activated.
| |
| Media Cerar - Rumor Control activities will be demonstrated at the Media Center by inclusion, in news briefings and advisories, ofinformation generated as a result ofincoming calls to the EOC Rtunor Control phones. Handling at least one rumor trend will be demonstrated. .
| |
| 9 December 16,1996 EOP97.VY l '
| |
| | |
| k EPZ EOCs - Control cell personnel will make calls to each EOC simulating members of the public. Each EOC will respond to some calls once the Public Alert and Notification System has been activated to demonstrate that they can refer calls to the state rumor control line or respond i L
| |
| to community-specific questions, as' appropriate.
| |
| ARCA 67-95-13-A-33: Control Cell will ensure that an adequate number of calls are made ,
| |
| to the Northfield EOC to demonstrate this objective, r
| |
| ARCA 67-95-13-A-40: Control Cell will ensure that an adequate number of calls are made i to the Warwick EOC to demonstrate this objective. t OBJECTIVE 14: IMPLEMENTATION OF PROTECTIVE ACTIONS-USE OF KI FOR !
| |
| EMERGENCY WORKERS, INSTITUTIONALIZED INDIVIDUALS, AND THE ,
| |
| GENERAL PUBLIC l l
| |
| Demonstrate the capability and resources to implement potassium iodide (KI) protective actions i 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 f included in the dosimetry packets. KI inventories will be available for inspection at each distribution location. -
| |
| There are no institutionalized individuals (prisons, nursing homes, hospitals) in the EPZ in !
| |
| Massachusetts, j Massachusetts does not provide KI to members of the general public. ;
| |
| ARCA 76-95-14-A-34: KI will be issued in the Nonhfield EOC in accordance with the l extent of play.
| |
| l i
| |
| ! OBJECTIVE 15: IMPLEMENTATION OF PROTECTIVE ACTIONS-SPECIAL '
| |
| l POPULATIONS 1
| |
| l Demonstrtte the capability and resources necessary to implement appropriate protective utions
| |
| ! for special populations.
| |
| I ,
| |
| l EOP97.VY 10 December 16,1996 l
| |
| i i
| |
| ; .i
| |
| | |
| EXTENT OF PLAY:
| |
| Massachuset+s Decartment of Environmental Management (DEMT - The District 9 Fire Warden will simulate dispatch of one alerting person / team to each of the following areas:
| |
| Nordifield State Forest - open Connecticut River Boat Ramp in Northfield - closed Warwick State Forest in Warwick - open Warwick State Forest in Northfield - open Leyden State Forest - open 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 arrive at District 9 Fire Warden's Office at some time dunng exeretse 1 play to conduct an interview with DEM personnel concerning communications, dosimetry I distnbution, equipment, maps, and prescripted messages. DEM should play along with the scenario from the beginning and be prepared to discuss actions of the day with the evaluator.
| |
| The FEMA evaluator will accompany field personnel dispatched to the Mount Grace State )
| |
| , Fcrest, which is the most accessible during the winter months. Even though some areas are officially open, road access is limited. Procedures for inaccessible areas will be discussed with the FEMA evaluator.
| |
| 1 l
| |
| ; Massachusetts Denanment of Fisheries. Wildlife. and Environmental Law Enforcement. Division of Law Enforcement - Will not dispatch of persons / teams to alert, notify, and clear persons from the Connecticut River, nor an access control person / team to Barton Cove. Instead, personnel at the MDFWELE Northampton Office will be interviewed by the FEMA evaluator who will arrive at some time during exercise play to conduct and interview concerning equipment, maps, prescripted messages, and dosimetry, and procedures. MDFWELE should play along with the scenario from the beginning and be prepared to discuss actions of the day with the evaluator. The actual alert, notification, and access control will be simulated by displaying appropriate l
| |
| equipment to the evaluator. Since no actual dispatch to will occur, members of the public in the vicinity will not be affected; no boat will be launched.
| |
| Bemardston EOC - EOC staff will contact persons on their special needs lists and verify the information on file. Each person on the list will be contacted only once; all subsequent calls will be simulated. This list of special needs individuals will be shown to the FEMA evaluator; i however the information is confidential so copies of the list will not be provided to the evaluator. I No vehicles for the transportation dependent will be mobilized. Procedures will be demonstrated through a discussion with the FEMA Evaluator. -
| |
| EOP97.VY 11 December 16,1996 L
| |
| | |
| Notification of recreational areas that are closed during the winter months will not be demonstrated or simulated.
| |
| Colrain EOC - EOC staff will contact persons on their special needs lists and verify the information on file. Each person on the list will be centacted only once; all subsequent calls will be simulated. This 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 the transportation dependent will be mobilized. Procedures will be demonstrated through a discussion with the FEMA Evaluator.
| |
| Notification of recreational areas that are closed during the winter months will not be e demonstrated or simulated.
| |
| Gill EOC - EOC staff will contact persons on their special needs lists and verify the information on file. Each person on the list will be contacted only once; all subsequent calls will be simulated. This 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 No vehicles for the transportation dependent will be mobilized. Procedures will be demonstrated through a discussion with the FEMA Evaluator. j 1
| |
| Notification of recreational areas that are closed during the winter months will not be I I
| |
| demonstrated or simulated.
| |
| Greenfield EOC - EOC staff will contact a selected individual on their special needs lists and verify the information on file. This person will be contacted only once; all subsequent calls will be simulated. This 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 Notification of Dept. of Mental Retardation (DMR) clients in the Independent Living Program !
| |
| will be called and assignments that would dispatch personnel to notify these persons will be simulated. The dispatch will be logged, but no police personnel will actually be mobilized and DMR clients will not be affected.
| |
| No vehicles for the transportation dependent will be mobilized. Procedures will be demonstrated through a discussion with the FEMA Evaluator.
| |
| Notification of recreational areas that are closed during the winter months will not be ,
| |
| demonstrated or simulated.
| |
| EOP97.VY 12 December 16,1996 L
| |
| | |
| The capability to correctly operate a TTY will be demonstrated in Greenfield by sending and receiving a test message to/from a TTY in a control cell.
| |
| Levden EOC - EOC staff will contact persons on their special needs lists and verify the information on file. Each person on the list will be contacted only once; all subsequent calls will be simulated. This 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 evahtator.
| |
| No vehicles for the transportation dependent will be mobilized. Procedures will be demonstrated through a discussion with the FEMA Evaluator.
| |
| Notification of recreational areas that are closed during the winter months will not be demonstrated or simulated.
| |
| Northfield EOC - EOC staff will contact persons on their special needs lists and verify the information on file. Each person on the list will be contacted only once; all subsequent calls will be simulated. This 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 the transportation dependent will be mobilized. Procedures will be demonstrated through a discussion with the FEMA Evaluator.
| |
| Notification of recreational areas that are closed during the winter months will not be demonstrated or simulated.
| |
| The EOC will demonstrate contacting the Northfield Mountain Recreational Area to confum notification procedures; however, no emergency message will be given and persons at Northfield Mountain will not be affected.
| |
| Warwick EOC - EOC staff will contact persons on their special needs lists and verify the information on file. Each person on the list will be contacted only once; all subsequent calls will be simulated. This 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 the transportation dependent will be mobilized. Procedures will be demonstrated through a discussion with the FEMA Evaluator.
| |
| Notification of recreational areas that are closed during the winter months will not be demonstrated or simulated.
| |
| 13 December 16,1996 EOP97 VY s
| |
| | |
| ARCI 67-95-15-A-35: Northfield EOC will demonstrate notific: tion of special alerting areas (Northfield Mountain Recreation Area) and special needs list in accordance with the extent ofplay.
| |
| ARCA 67-95-15-A- 12: Camp Lion Knoll will demonstrate knowledge of plans and procedures during the next summer exercise period.
| |
| OBJECTIVE 16: IMPLEMENTATION OF PROTECTIVE ACTIONS-SCHOOLS Demonstrate the capability and resources necessary to implement protective actions for school children within the plume pathway emergency planning zone. ;
| |
| EXTENT OF PLAY:
| |
| i FEMA evaluators will interview school principals or their designees at participating schools out of sequence. l Area III EOC - No calls will be made to the University of Massachusetts campus police to i activate the host facility, but simulated contact will be logged at appropriate times in the l exerdise.
| |
| EPZ EOCs - Initial notification will be made to all public school superintendents' offices, private schools, and day care centers. Subsequent calls will be made only to panicipating locations.
| |
| Communications with the schools concerning escort vehicles will be demonstrated but no escort vehicles will be dispatched in sequence. Escort vehicles will be dispatched out of sequence to the following locations only, at the end of exercise play:
| |
| * Bemardston Elementary School
| |
| * Gill Elementary School
| |
| * Northfield Mount Hermon School, Northfield Campus
| |
| * Warwick Elementary School Escon vehicle drivers will meet the FEMA Evaluator at the approp'rlate EOC and drive to the assigned school where they will demonstrate procedures to the FEMA Evaluator as if he/she were the bus driver. The escon vehicles will then proceed to the host facility. Upon arrival at the host facility, the escon vehicle will retum to the local EOC. Communications between the escon vehicle and the local EOC will be demonstrated.
| |
| 14 December 16,1996 EOP97.VY
| |
| | |
| l l l
| |
| l Gill-Montacue Recional School District School Surerintendent's Office - Only the initial call will be made to the Gill Elementary School and to the F. M. Kuzmeskus Bus Company. During i
| |
| the call to the bus company, vehicles and drivers will be tallied for their availability and their ETA noted. No dispatch of vehicles will occur.
| |
| Mohawk Trail Recional School District Surerintendent's Office - Only the initial call will be made to Colrain Elementary School and the Sullivan Bus Lines. During the call to the bus company, vehicles and drivers will be tallied for their availability and their ETA noted. No l dispatch of vehicles will occur.
| |
| Pioneer Vallev Recional School District esmerintendent's Office - Only the initial call will be made to the Laidlaw Transit,Inc.; dur;ng the call, vehicles and drivers will be tallied for their availability and their ETA noted. Na dispatch of vehicles will occur.
| |
| Notification and subsequent calls will be made to Pioneer Valley Regional School, Northfield Elementary School, Bemardston Elementary School, and Pearl Rhodes Elementary School in Leyden; subsequent calls will not be made to Warwick Elementary School, which is not participating in the exercise.
| |
| No calls will be made to the Orange Police Station to activate the Orange Armory, but simulated contact will be logged at appropriate times in the exercise.
| |
| Schools and Dav Care Centers - Nonparticipating schools in the EPZ towns will receive initial calls only. Students will not be involved. No vehicles will be dispatched for precautionary transfer or evacuation.
| |
| The following schools and day care centers will participate as noted below and will receive all I appropriate communications:
| |
| I Bemardston Elementary School t
| |
| Pioneer Valley Regional School, Northfield Pearl Rhodes Elementary School, Leyden Northfield Elementary School The following schools and day care centers will not participate:
| |
| Full Circle School, Bernardston Colrain Central Elementary School Gill Elementary School Otter Pond Preschool, Gill Northfield-Mount Hermon School, Gill Campus EOP97.VY 15 December 16,1996
| |
| | |
| Northfield-Mount Hennon School, Northfield Campus Linden Hill School, Northfield Warwick Elementary School ARCA 67-95-16-A a4 An escort vehicle driver for Northfield Mount Hermon School will be provided a copy of the evacuation route map and demonstrate the evacuation route without the use of an escort vehicle.
| |
| ARCA 67-95-16-A-45 A bus route Warwick Elementary School to the Orange Armory will be demonstrated by an escort vehicle driver.
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| OBJECTIVE 17: TRAFFIC AND ACCESS CONTROL Demonstrate the organizational capability and resources necessary to control evacuation trafEc 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.
| |
| Area III EOC - State Police and Highway Department liaisons will demonstrate coordination of
| |
| ! traffe and access control, but no personnel or equipment will actually be deployed.
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| EPZ EOCs - Will demonstrate the ability to direct and monitor traffic control operations within ;
| |
| their areas ofjurisdiction using information provided by controllers to simulate input from the !
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| control points. EOC staff will discuss provisions for responding to traffic impediments by l l
| |
| ! discussing resources (wreckers, traffic control personnel available, equipment ) with the FEMA evaluators. No mobilization or deployment will occur.
| |
| l l One traffic control point in each community will be demonstrated through an interview with the FEMA evaluator, who will discuss procedures for traffic control with personnel from the community's police and highway representatives in the EOC. No mobilization or moving of equipment will actually take place.
| |
| The Police representative in the Northfield EOC will discuss communications with the TCP/ACP officer with the FEMA Evaluator.
| |
| Massachusetts State Police (MSP) Troon B - MSP will demonstrate traffic and access control through an interview with the FEMA evaluator at Troop B Headquarters in Northampton. The d 16 December 16,1996 EOP97 VY l
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| 1
| |
| | |
| l interview may include demonstration of the Traffic Management Manual and dosimetry /KI .
| |
| I packets. No deployment of TCP/ACP locations will occur.
| |
| Massachusetts Richway Decartment - will not participate in the FEMA interview / evaluation of traffic / access control procedures. No personnel will dispatched to Troop B Headquarters.
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| I l
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| ARCA 67-95-17-A-36: Communications between the Northfield EOC and the TCP/ACP officer will be demonstrated.
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| l OBJECTIVE 18: RECEPTION CENTER-MONITORING, DECONTAMINATION, AND REGISTRATION i
| |
| Demonstrate the adequacy of procedures, facilities, equipment and personnel for the radiological l
| |
| monitoring, decontamination and registration of evacuees.
| |
| EXTENT OF PLAY:
| |
| This objective will be demonstrated out of sequence on a date to be determined.
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| l l
| |
| l OBJECTIVE 19: CONGREGATE CARE Demonstrate the adequacy of facilities, equipment, supplies, personnel, and procedures for l
| |
| congregate care of evacuees.
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| EXTENT OF PLAY:
| |
| This objective will be demonstrated in conjunction with demonstration of the GCC Reception Center exercise. Current shelter surveys will be provided to FEMA for review prior to the exercise.
| |
| f OBJECTIVE 20: MEDICAL SERVICES-TRANSPORTATION l
| |
| Demonstrate the adequacy of vehicles, equipment, procedures and personnel for transporting
| |
| )
| |
| contaminated, injured, or exposed individuals.
| |
| EXTENT OF PLAY:
| |
| This objective will be demonstrated out of sequence on a date to be d.etermined.
| |
| 17 December 16,1996
| |
| , EOP97.VY i
| |
| i l
| |
| | |
| ARCA: 94-2, The Radiation Emergency Area personnel will wear masks while i
| |
| performing duties in the Emergency Room as required by the hospital plan.
| |
| OBJECTIVE 21: MEDICAL SERVICES-FACILITIES Demonstrate the adequacy of the equipment, procedures, supplies, and personnel of medical facilities responsible for treatment of contaminated, injured, or exposed individuals.
| |
| ~
| |
| EXTENT OF PLAY:
| |
| This objective will be demonstrated out of sequence on a date to be determined at Franklin Medical Center, Greenfield.
| |
| OBJECTIVE 22: EMERGENCY WORKERS, EQUIPMENT, AND VEHICLES-MONITORING AND DECONTAMINATION Demonstrate the adequacy of procedures for the monitoring and decontammation of emergency -
| |
| workers, equipment, and vehicles.
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| EXTENT OF PLAY:
| |
| This objective will not be demonstrated by Colrain and Gill in 1997. .
| |
| ! This objective will be demonstrated by Greenfield out of sequence in conjunction with the GCC Reception Center Exercise on a date to be determined.
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| This objective will be demonstrated by Warwick out of sequence on March 19, using a mini-scenario and timeline that is independent of the main exercise.
| |
| Two individuals simulating emergency workers in Warwick will be processed through the facility per shift, with one emergency worker declared contaminated. Personnel decontamination demonstration will be simulated using a discussion of methods andTechniques. Vehicle !
| |
| monitoring will be performed on one vehicle per shift, and decontamination will be demonstrated through a discussior, of decontammation actions and techniques.
| |
| Two full shifts (3 persons each shift) will demonstrate both personnel and vehicle monitoring and decontamination as described above.
| |
| i
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| ! EOP97.VY 18 December 16,1996 l
| |
| | |
| _ . . _ _ . . . _ . . _ . ~ .. _ ._ _ . ._ ._. _ ._ _ . _ _.__.._ _ . _ ._.
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| l
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| :p i
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| i ARCA 67-95-22-A-41: This objective will be demonstrated at the Warwick RM&D l Station in accordance with the extent of play.
| |
| I i OBJECTIVE 23: SUPPLEMENTARY ASSISTANCE (FEDERAL /OTHER) j Demonstrate the ability to identify the need for external assistance and to request such assistance i from federal or other support organizations.
| |
| EXTENT OF PLAY:
| |
| No exceptions.
| |
| }
| |
| i OBJECTIVE 24: POST-ENERGENCY SAMPLING Demonstrate the use of equipment and procedures for the collection and transportation of l
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| j samples from areas that received deposition from the airborne plume.
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| 1 i
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| 1 EXTENT OF PLAY:
| |
| s i
| |
| i This objective will not be demonstrated in 1997.
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| 4 4 OBJECTIVE 25: LABORATORY OPERATIONS e
| |
| ,I Demonstrate laboratory operations and procedures for measuring and analyzing samples.
| |
| 4 EXTENT OF PLAY:
| |
| This objective will not be demonstrated in 1997.
| |
| 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.
| |
| 19 December 16,1996 EOP97.VY
| |
| | |
| EXTENT OF PLAY:
| |
| This objective will not be . demonstrated in 1997.
| |
| OBJECTIVE 27: INGESTION EXPOSURE PATHWAY-PROTECTIVE ACTION IMPLEMENTATION Demonstrate the capability to implement protective actions for the ingestion exposure pathway.
| |
| l EXTENT OF PLAY:
| |
| J This objective will not be demonstrated in 1997.
| |
| OBJECTIVE 28: RELOCATIONS, RE-ENTRY, AND RETURN-DECISION MAKING Demonstrate the capability to develop decisions on relocation, re-entry, and return. ,
| |
| EXTENT OF PLAY:
| |
| This objective will not be demonstrated in 1997.
| |
| OBJECTIVE 29: RELOCATION, RE-ENTRY, AND RETURN-IMPLEMENTATION Demonstrate the capability to implement appropriate measures for relocation, re-entry, and return, i EXTENT OF PLAY:
| |
| t i l
| |
| This objective will not be demonstrated in 1997.
| |
| OBJECTIVE 30: CONTINUOUS,24-HR STAFFING Demonstrate the capability to maintain staffmg on a continuous 24-hour basis through an actual shift change.
| |
| l EXTENT OF PLAY:
| |
| i 4
| |
| 20 December 16,1996 EOP97.VY 4
| |
| | |
| 1 This objective will not be demonstrated at the following locations in 1997. f State EOC Media Center EOF Area III EOC Bernardston EOC Gill EOC Northfield EOC Wanvick EOC Gill RM&D Greenfield EOC This objective will be demonstrated at the following locations:
| |
| l Colrain EOC Leyden EOC Warwick RM&D The shift change wth be prompted by a controller message and will occur at a time that will permit second shift staff to adequately demonstrate their knowledge of their assigned emergency response roles.
| |
| When the shift change is complete, the first shift will leave the play area.
| |
| , ARCA 67-95-30-A-28 The Greenfield plan has been revised to delete the Public Health
| |
| ! Officer as key staff.
| |
| l l ARCA 67-95-30-A-29 Leyden will fully demonstrate the capability to maintain staffing on a continuous 24-hour basis.
| |
| l OBJECTIVE 31: OFFSITE SUPPORT FOR THE EVACUATION OF ONSITE PERSONNEL ,
| |
| i i Demonstrate the capability to provide offsite support for the evacuation of onsite personnel. l l
| |
| EXTENT OF PLAY:
| |
| This objective does not apply to Massachusetts.
| |
| l EOP97.VY 21 December 16,1996 i
| |
| | |
| 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 will not be demonstrated in 1997. _
| |
| i OBJECTIVE 33: OFF-HOURS EXERCISE OR DRILL Demonstrate the capability to carry out emergency response functions during an off-hours exercise or drill. *
| |
| \
| |
| l EXTENT OF PLAY:
| |
| l This objective will not be demonstrated in 1997. ,
| |
| i l
| |
| i l
| |
| l l
| |
| l t
| |
| 1 I
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| 22 December 16,1996
| |
| ; EOP97.VY
| |
| (
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| | |
| Rev.0 Page 3.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 2.d EXERCISE GUIDELINES AND GROUND RULES The Vermont Yankee Emergency Preparedness Exercise will be conducted on Wednesday, March 19, 1997. 1997 is a " full-participation biennial" exercise.
| |
| The exercise will involve full participation 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 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 1997 Vermont Yankee Emergency Preparedness Exercise. It provides the framework for conducting the exercise, demonstrating emergency response capabilities, and evaluating response activities.
| |
| I. Conceots of Ooerations and Control A. Exercise Controller Ooerations An Exercise Coordinator has been appointed by Vermont Yankee management to oversee all exercise activities. The Exercise Coordinator is responsible for approving the objectives and developing the scenario time sequence.
| |
| The Exercise Coordinator is also responsible for the selection and training of the personnel required to conduct and evaluate the exercise.
| |
| Vermont Yankee will supply Controllers for major locations where an emergency response action will be demonstrated. Prior to the exercise, the controllers will be provided with the appropriate materials necessary for their assigned function. The material will include any maps and messages to be used 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 concerns that may occur. If a major exercise .
| |
| control problem arises, tne Controller should first contact the Lead Controller who will then contact the Exercise Coordinator for guidance or k
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| | |
| i
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| )
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| Rev.0 Page 3.1-2 l
| |
| resolution of the problem. All major requests for scenario modifications or holding periode must be cleared through the Exercise Coordinator.
| |
| Controllers also have the authority to resolve scenario-related problems which may occur during the exercise.
| |
| 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 which may be observed. In the event of corrective or repair activities, the Controller shall be cognizant of procedures associated 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 task within the scenario time sequence of events and constraints allowed. The controllers will critique the effectiveness of the emergency 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. Plant and reactor system parameters for the exercise will be generated by running the accident scenario on the simulator. 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 implementing procedures and emergency operating procedures. These procedures should include a determination of the 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 if.mited period of time. ,
| |
| 4
| |
| | |
| I Rev.0 Page 3.1-3 B. Avoidina violations of Laws violation of laws is not justifiable during the exercise. To implement this guideline the following actions must be taken: i
| |
| : 1. Participants must be specifically informed of the need to avoid violating any federal, state and local laws, regulations, ordinances, statutes and other legal restrictions. The orders of all police, sheriffs or other authorities shall be followed as appropriate.
| |
| : 2. Participants will not direct illegal actions to be taken by other participants or members of the general public.
| |
| : 3. Participants will not intentionally take illegal actions when responding to scenario events. Specifically, local traffic laws (i.e. speed limits) will be observed.
| |
| C. Avoidina Personnel and Pronerty Endancerment All participants will be instructed to avoid endangering property (public or private), other personnel responding to the events, members of the general public, animals and the environment.
| |
| D. Actions to Minimize Public Inconvenience
| |
| -It is not the intent, nor is it desirable, to effectively train or test the public response during the conduct of the exercise. Public inconvenience is to be avoided.
| |
| The conduct of the exercise could arouse public concern that an actual emergency is occurring. It is important 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."
| |
| II. General Guidance for the conduct of the Exercise A. Exercise Simulation 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 Some of the exercise objectives will be actions will be carried out.
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| b
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| . - - . . . . - - - - - . _ . . . . ~ - . - . . . - - . - . . . . .
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| Rev.O Page 3.1-4 s
| |
| demonstrated by simulating the associated emergency response actions.
| |
| Simulation of response activities will occur when specific actions do not have to be performed, and when actions .re 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 written directions on actions 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 action will be allowed which alters or affects the ongoing operation of the plant.
| |
| l
| |
| : 1. Prior to the start of the exercise, specific work station terminals t
| |
| ' in the TSC, EOF /RC and ESC will 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 work station terminals will remain tied to the plant process computer (ERFIS). 1
| |
| : 2. A number of individuals from the Vermont Yankee Emergency Response ,
| |
| l Organization will be pre-staged to facilitate exercise and simulator l I related logistics. Individuals that will be pre-staged include the following:
| |
| : a. The operating crew in the Simulator Control Room, and the l
| |
| crew's exercise Aos and other personnel at the plant to l.
| |
| l compliment the operating crew at the Simulator,
| |
| : b. An Chemistry technician assigned as the Chemistry Communicator in the Simulator Control Room if requested by SS/ PED.
| |
| I
| |
| ! c. An individual assigned as an Alternate Communicator in the l
| |
| Simulator control if requested by SS/ PED.
| |
| I
| |
| : d. An R&CE person assigned to the Simulator Control Room for data acquisition if requested by TSC personnel.
| |
| I
| |
| : e. An RP person assigned to the Simulator Control Room for data acquisition if requested by TSC Coordinator.
| |
| f l
| |
| : f. R&CE personnel to set up the ERFIS terminals in the SPPCS mode.
| |
| . 3. Meteorological data will be simulated through the simulator SPPCS ,
| |
| j computer.
| |
| s
| |
| | |
| Rev.O Page 3.1-5
| |
| : 4. Af ter plant evacuation and accountability have been completed, plant personnel and contractors / visitors, not directly involved in the exercise, will be allowed to return to work at the discretion of the TSC Coordinator.
| |
| : 5. Discussion of potassium iodide (KI) usage will be done if scenario conditions warrant its use. However, distribution and ingestion of KI will be simulated.
| |
| : 6. If of f-site monitoring sampling is required, charcoal cartridges will be used in place of silver zeolite cartridges.
| |
| : 7. Of f-site monitoring teams and security boundary monitoring personnel will not wear either protective clothing or respirators.
| |
| B. The inner gate and electrically controlled doors will not be left in the open position during the exercise.
| |
| : 9. The plant GalTronics is available between the simulator Control Room and the plant through the use of an interface device. Although not a complete duplication it will allow a person in the plant to talk directly to the simulator over the plant GalTronics. However, actual plant announcements will be coordinated by the controllers and made ,
| |
| from the vermont Yankee plant Main control Room.
| |
| : 10. Exercise Controllers will not be issued dosimetry unless plant access is required prior to the exercise. security will be notified of the Exercise Controllers assigned locations.
| |
| : 11. All decontamination actions associated with the scenario events may be simulated after discussion and approval by the Exercise controller.
| |
| : 12. The use of respiratory protection equipment may be simulated by plant personnel after discussion and approval by the Exercise Controller.
| |
| m.-____.-_________-___
| |
| | |
| Rev.O Page 3.1-6 B. ? laver's Guidelines and Gamesmanshio The following is a list of general guidelines and instructions 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 actions. Exercise Controllers and NRC/ FEMA
| |
| ! Evaluators will be identified by badges.
| |
| l
| |
| : 2. Always identify yourself by name and function to the Exercise Controllers. Wear a name tag if one is provided.
| |
| l
| |
| : 3. You may ask the Exercise Controller for information such ass
| |
| : a. Initial conditions of the plant and systems including:
| |
| o operating history of the core o initial coolant activity o.. general weather conditions o availability of systems according to the scenario
| |
| : b. Area radiation data at the location of emergency teams.
| |
| : c. Airborne data at the location of emergency teams after a sample has been properly obtained.
| |
| l
| |
| : d. Counting efficiency of all counting equipment.
| |
| : e. Activity from nose swabs or skin contamination surveys.
| |
| I 4. You may B21 ask the following from the Exercise Controllers:
| |
| prscedures, drawings, or
| |
| : a. Information contained in instructions.
| |
| : b. Judgments as to which procedures should be used.
| |
| l c. Data which will be made available later in the scenario. e
| |
| : d. Assistance in performing actions. +
| |
| 1
| |
| : e. Assistance in performing calculations.
| |
| i l
| |
| l l
| |
| l r
| |
| | |
| Rev.O Page 3.1-7
| |
| : 5. Play out all actions, as much as possible, in accordance with your plan and procedures as if it were an actual emergency. If an action or data is to be simulated, an Exercise Controller will provide appropriate direction.
| |
| : 6. Periodically speak out loud, identifying yocr key actions and decisions to the Exercise Controllers and NRC Evaluators, especially if present in your facility and observing your functions. This may seem artificial, but it will assist the controllers in determining the various response actions being initiated and is to your benefit.
| |
| : 7. When you are assigned to complete a response action, be sure to notify an Exercise Controller prior to performing the action. Let the Exercise Controllers decide which actions will be observed ana which ones will not. If an Exercise Controller olects to observe your activity, ensure the Exercise controller remains with you to observe the task (i.e don't lose the controller en-route to the area where the action will take place).
| |
| : 8. If you are in doubt about completing a response action, ask your Exercise controller for clarification. The Exercise Controller M1H not prompt or coach you. Emergency response actions must not place participants in any potentially hazardous situations.
| |
| : 9. The scenario has been scrutinized to anticipate as many success paths that may be initiated by the response teams. In the event you or your staff determine there may be alternative responses to scenario conditions, you may not be allowed to initjate your proposed "fix". You will however, be credited with the initiative and requested to continue your response in accordance with the proposed scenario events from the Exercise Controller. In addition, the Exercise Controller may periodically issue messages or instructions designed to initiate response actions. You aggi accept these messages immediately. They are essential to the proper ,
| |
| completion of the exercise scenario.
| |
| : 10. If an Exercise Controller intervenes in your response actions and recommends you redirect or reconsider your play actions, it is for a good reason. The Exercise controller's direction may be essential to ensure demonstration of objectives for all participating groups.
| |
| : 11. If you disagree with your Exercise Controller, discuss your concerns j in a professional manner. However, the Exercise Controller's final decisions must be followed.
| |
| 8 i L
| |
| | |
| Rev.O Page 3.1-8 i
| |
| : 12. Respond to questions in a timely manner. l
| |
| : 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 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 facility player or Exercise Controller.
| |
| : 14. You must respond as if elevated radiation levels are actually present based on the scenario information you receive. This may require you to wear protective clothing, respirators, or additional I dosimetry.
| |
| : 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 practices and procedures.
| |
| : 16. Use status boards and log books as much as possible to document and record your actions.
| |
| : 17. Always begin and end all communications with the words "THIS IS A DRILL," so that exercise-related communications are not confused with an actual emergency.
| |
| : 18. Keep a list of items which you believe will improve your plans and procedures. A player debriefing will follow the exercise. Provide i 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 that should be followed to improve gamesmanship during the exercises
| |
| : 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.
| |
| | |
| Rev.O Page 3.1-9
| |
| : 3. Hold briefings regularly, approximately every 30-45 minutes, or as conditions warrant.
| |
| : 4. Key players should wear badges which ideratify their role. Bound log books should be used in all emergency response facilities.
| |
| : 5. All announcements, including those on the GaiTronics, should state "THIS IS A DRILL."
| |
| : 6. Avoid simulation unless it has been specified. Use protective clo W ing where called for (e.g., step-off pads, etc.).
| |
| C. Simulator Control Room (SCR) Information The following describes how the SCR emergency response activities will be integrated with the plant Control Room functions during the exersises
| |
| : 1. Players reporting to the plant Control Room will be directed to an area (SS office) that will have a Control Room Controller and 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 GaiTronics system.
| |
| Although not a complete duplication it will allow a person in the plant to talk directly to the simulator over the plant GaiTronics.
| |
| 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 i the Plant. CHANNEL 1 and CHANNEL 2 will be the designated lines for ;
| |
| all other plant exercise related communications and messages. l
| |
| : 3. GaiTronics 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 actual made and repeated 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.
| |
| | |
| Rev.0 Page 3.1-10 1
| |
| I
| |
| : 5. Personnel movement in and out of the SCR will be limited to the Exercise Controllers and designated exercise participants.
| |
| i
| |
| : 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 are operable. The ;
| |
| orange Nuclear Alert System (NAS) State telephone and Federal j Telecommunications System (FTS 2000) Emergency Notification System (ENS)-NRC telephone will be operable. The orange Nuclear Alert i l
| |
| System telephone extension in the Simulator is 613. j l
| |
| D. Personnel Accountability and Particication (Exemoted Particicants)
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| Procedures require that all participants be identified. Proper i identification will not only help eliminate confusion, but is necessary for security and accountability. This requirement applies to all areas J
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| within the plant fence, Governor Hunt House, EOF /RC, simulator area, News I Media Center, and the Vermopf;, Yankee Corporate Of fice in Brattleboro.
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| Although it is expected that all personnel will respond to the declared !
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| 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 oorsonnel should be minimized. As in the past, people evacuated from the plant will be allowed to return to their normal duties upon approval from the TSC Coordinator.
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| 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 personnel will include the on-Shift Security Crew, operating Crew, n'nd Duty Chemistry and Radiation Protection Technician and other individuals identified by the Department Heads.
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| Rev.O Page 3.1-11 E. gf f-site Particioation (Federal, State and Local)
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| This year, Vermont Yankee is conducting a " full participation biennial" exercise that will involve substantial participation 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.
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| The capability to notify federal, state, and local authorities of emergency classifications in accordance with established procedures will be demonstrated as follows:
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| : 1. NRC will be notified by using the FTS 2000 ENS telephone.
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| : 2. Vermont, New Hampshire, and Massachusetts State Police dispatchers ,
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| and State Emergency Operations Centers (EOCs) will be notified through the orange Nuclear Alert System telephone.
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| : 3. Vermont, New Hampshire, and Massachusetts State officials at the EOF /RC and the News Media Center (NMC) will be notified by the appropriate Vermont Yankee personnel (if available and participating l in the exercise).
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| If any state official tries to contact the actual plant Control Room REGARDING THE EXERCISE, the Vernon switchboard should transfer the call to the Simulator Control Room in Brattleboro.
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| F. Exercise criticues The following is a brief description of the critique sessions that will be held after the exercise. The critique sessions are held to detwrmine I I
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| whether the stated exercise objectives were met, verify the effectiveness of the emergency plan and procedures, and identify areas for future improvements. The specific schedule for the critique sessions will be announced at the conclusion of the exercise.
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| E
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| _ . _ _ . _ . _ _ _ . _ _ _ _ _ ____ _ _ _ - . - _ _ ._ . _ _ - . . .. m. ._ _ _ _ _ _ _
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| Rev.0 Page 3.1-12 Emeroency Rosconse Facility Criticues The critique sessions will be conducted by the Controllers. Exercise participants will be debriefed on the findings for their particular emergency response facility (s). Four critique sessions will be hold:
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| : 1. SRM and EOF
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| : 2. TSC and simulator Control Room
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| : 3. osc and security
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| : 4. News Media Center Lead Controller Debriefina This session will be conducted by the Exercise Coordinator to compile all exercise comments and findings. Participation is limited to Lead Controllers or other Exercise Controllers as needed.
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| Exercise criticue t a
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| l This session will be conducted by the Exercise Coordinator to present a summary of major findings identified during the exercise. Participants ;
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| include Vermont Yankee management, Exercise Controllers, key players, and the NRC.
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| \
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| l H. Exercise Termination l
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| The exercise will be terminated by the Exercise Coordinator when all emergency response actions have been completed in accordance with the exercise scenaric time sequence and exercise objectives.
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| The following steps will be implemented to terminate the exercise:
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| : 1. The Exercise Coordinator will obtain information from the Lead Controllers regarding the status of player actions and the demonstration of the exercise objectives.
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| : 2. The Lead Controllers are responsible for informing the Exercise i
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| coordinator of their facility status and whether the emergency l response actions and objectives have been satisfactorily observed.
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| ! 3. Upon receipt of information from the Lead Controllers, the Exercise I Coordinator will inform the site Recovery Manager and TSC Coordinator that all exercise objectives have been completed and the
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| ; exercise can be terminated.
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| Rev.0 Page 3.1-13
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| : 4. A coordinated decision to terminate the exercise 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.
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| : 5. The Site Recovery Manager will terminate the exercise.
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| The exercise may also be terminated under the following circumstances:
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| : 1. In the event of an actual plant emergency condition should occur, l the following actions will be taken:
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| : a. The Shift Supervisor will contact the TSC Coordinator and
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| ! inform him of the plant status. The TSC Coordinator will, in turn, contact the Site Recovery Manager and inform him of the l plant status; l
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| : b. The Site Recovery Manager will immediately inform any State l representatives at the EOF of the nature of the emergency;
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| : c. Concurrent with the notification in Step b, the control Room will announce the following statement over the plant paging system "The emergency plan exercise has been terminated. I repeat.
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| The emergency plan exercise has been terminated."
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| This message may be immediately followed by the appropriate emergency announcements.
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| : d. The Exercise Coordinator will be responsible for directing the actions of all other exercise participants.
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| I l
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| : 2. In the event that actual off-site emergency impacts the response l
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| ; actions of Vermont Yankee participants, the following actions should be taken:
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| : a. The Shift Supervisor will notify the Control Room Controller who, in turn, will notify the Exercise Coordinator.
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| : b. A coordinated decision will be made in conjunction with the Site Recovery Manager and/or the TSC and EOF Coordinators concerning the completion of the exercise.
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| i 1
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| 4
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| 1 Rev.O l Page 3.1-14 I
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| : c. The Exercise Coordinator will be responsible for temporarily halting the exercise until such time a decision is made to terminate or continuing the exercise.
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| : d. If the final decision is to terminate the exercise, the 1 Exercise Coordinator will be responsible for directing the activities of all exercise participants, as well as for informing the NRC of the exercise termination.
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| l
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| : e. If the final decision is to continue the exercise, the Exercise Coordinator is responsible for informing all l Controllers of any projected changes to the expected response I action (s). f l
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| : f. The Exercise Coordinator will direct the organization as to !
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| the appropriate action required to restore the exercise scenario sequence. {
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| i
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| . . . _ _ - _ . - . .- _- - _ . . _ - - .- . . .- . . . -- _ _ _ _ - - -.~. . . . .
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| Rev. O Page 3.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE ,
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| 1997 L,2 EMERGENCY PLAN IMPLEMENTING PROCEDURE EXECUTION LIST Procedure Number Rev. No. Title AP 3125 15 Emergency Plan Classification and Action Level Scheme OP 3500 16 Unusual Event OP 3501 17 Alert OP 3502 29 Site Area Emergency i OP 3503 31 General Emergency ,
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| l OP 3504 30 Emergency Communications OP 3507 27 Emergency Radiation Exposure Control OP 3510 21 Off-site and Site Boundary Monitoring
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| ( OP 3511 10 Off-site Protective Action l
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| Recommendations OP 3513 18 Evaluation of Off-site Radiological Conditions OP 3524 13 Emergency Actions to Ensure Initial Accountability and Security Response OP 3525 7 Radiological Coordination OP 3531 10 Emergency call-In Method l OP 3533 3 Post Accident Sampling of Reactor I Coolant OP 3534 1 Post Accident Sampling of Plant Stack Gaseous Releases OP 3535 1 Post Accident. Sampling and Analysis of Primary Containment OP 3536 0 In Plant Air Sample Analysis with j
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| Abnormal Condition I
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| . - - - - . .. - _ = . ~ . . . - - - .- - . _ _ . _ . _ - . - -. - .-. - - . . . ~ . - . . - . _ . ~ _ .
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| VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 id CONTROI.LER ASSIGNMENTS NOTE: ASSIGNMENTS TO BE ISSUED UNDER SEPARATE MEMO AND REVIEWED AT THE EXERCISE CONTROLLER BRIEFING SESSION l
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| Rev. O Page 4.2 l l
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| VERMONT YANKEE EMERGENCY PREPAREDNESS EXERCISE ,
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| 1997 !
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| 1 M CONTROLLER EXERCISE GUIDANCE l Prior to the exercise, each Controller will be provided a scenario package ;
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| that correspond to their respective assignments. It is the responsibility i of the Controller to read the contents of the scenario package and understand their controller assignments. i l
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| 1 Each Controller will be requested to attend appropriate briefing sessions I prior to the exercise. Any questions regarding the scenario or assignments !
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| should be discussed at this time. Each Controller should ensure that they are familiar with location (s) required by their assignment.
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| Controllers should familiarize themselves with their assigned Lead f controller prior to the exercise. The Lead Controller is responsible to l direct Controller activities throughout the course of the exercise. At the !
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| exercise termination, each Controller is responsible to provide their j comments, observations and documentation to the Lead Controller. Each Lead I 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 l
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| 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 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 evaluation forms for documentation purposes.
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| 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 When Exercise / Drill Controller's Evaluation Form (VYOPF 3505.02).
| |
| 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 recognized weaknesses or deficiencies (inadequate performance). (Inadequate indicates that the demonstrated performance could have precluded effective implementation of plans or procedures.) For comments / recommendations and recognized f weaknesses or deficiencies (inadequate performance), the Controller should i provide a clear written description of the finding or observation. l l
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| Rev. O l
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| Page 4.2-2 controllers should H21 allow their biases to be documented as recognized
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| {
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| ; weaknesses or deficiencies. Observations and comments may be further j subdivided according to the following major headings: Facility Activation
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| ' and Organizational Control, Communications, Adherence to Plans and j Procedures, Equipment capabilities, Scenario, Training, Facility Layout, i off-Site Monitoring, Personnel . Dosimetry / Exposure Control, and General
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| ! Comments.
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| ' Facility Activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the f acility was activated; (3) when initial activities are organized; (4) whether personnel performance follows the organized arrangements specified by plant procedures; and (S) 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.
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| Communication comments should identify: (1) personnel familiarity with emergency communications use; (2) whether sufficient communications were available to ensure a timely, efficient, and effective flow of information; ,
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| (3) whether there were enough communications personnel to make use of all ,
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| available equipment; (4) the adequacy of 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 traf fic flow); (6) whether there were any recognized difficulties in use of computer systems; and (7) whether status boards are effectively used.
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| Controllers should document their comments in this area very carefully, providing sufficient details to track any recognized deficiencies.
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| Plans and Procedures comments should identify: (1) whether personnel were' i
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| f amiliar 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.
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| Eauinment Cacability comments should identify: (1) whether all necessary materials and equipment were available and , functional; (2) whether emergency response personnel checked operability of equipment prior to conducting their assignments (3) whether backup 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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| Scenario related comments should identify: (1) whether sufficient ,
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| information was available to ensure appropriate player response; (2) '
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| whether the scenario details deviated from actual procedural requirements; and (3) whether the scenario detail provided any prompts to the player.
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| Rev. O s
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| Page 4.2-3 Trainino comments should identify (1) whether plant personnel have been l
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| provided sufficient training to handle "ad hoc" procedural deviations; and j (2) whether training identifies improper procedural requirements.
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| l l
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| Facility Lavout comments should identifyt (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.
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| ( of f-site Monitorina comments should identify: (1) the adequacy of sampling
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| ! 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 ef fectiveness of methods to interpret off-site conditions; and (2) the ef fectiveness of using the dose projections in positioning off-site teams.
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| I Personnel Dosimetrv/Excosure Control coments should identify: (1) the l timeliness and effectiveness of dosimetry distribution; (2) the effectiveness of protective measures; (3) the adequacy of established l
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| contamination control access points; (4) the adequacy of exposure planning measures afforded in plant activities; and (5) the adequacy of decontamination and posting techniques.
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| Controller's evaluation and documentation forms are found in Section 4.3.
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| All documentation recorded must be provided to the Lead Controller after the exercise and prior to the critique.
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| Rev. O Page 4.3-1 VERMONT YANKEE EMERGENCY PREPAREDNESS EXERCISE 1997 M CONTROLLER EVALUATION CRITERIA As discussed in Sections 4.1 and 4.2, each controller has been assigned specific areas of 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 i Attachment A provides a form to be used to maintain an event chronology j log.
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| l Attachment B contains evaluation checklists for each emergency response facility. Each Controller should complete the appropriate checklist. i l
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| Procedural Form VYOPF 3505.02, " Emergency Exercise / Drill Controller's )
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| Evaluation Form," is provided to summarize major findings and 1 observations. THIS FORM NUST BE COMPLETED BY EACE CONTR07YRe.
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| 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 Coordinator for documentation of drill or exercise observations and findings.
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| l
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| R:v. O Pagn 4.3-2 ATTACHMENT A Vermont Yankee Nuclear Power Station Emeroency Resoonse Exercise / Drill Controller's Observations-Chronolooical Loo TIME COMMENT / OBSERVATION I
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| i Name Area Evaluated:
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| Dates l
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| ; R:v. O I Pegn 4.3-3 ATTACHMENT B Vermont Yankee Emeroency Exercise / Drill Evaluation Checklist l
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| INf%UCTIONS I
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| he following checklists are provided to assist the Controller with their evaluation of the
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| ! drill / exercise. The controller should complete the checklist (s) for their assigned locatiens(s). To complete the evaluation checklist (s), use the rating scale listed below.
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| Tne completed checklist should be used as a " road map" to document your observations and l
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| ccaments on procedural form VYOPF 3505.02. Controllers should provide a clear written d2scription of their findings and observations.
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| RatinQ Symbol Ratina Exclanation for Comments adequate A Adequate indicates that the demonstrated performance was consistent with plans and procedures. Comments may include strong positive strengths or expected actions done well.
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| Inadequate I Inadequate indicates that the demonstrated performance could have precluded effective implementation of plans and J procedures. This also may include an aspect of player's )
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| response that warrants further evaluation for improvement or '
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| corrective action. Comments should provide a clear description of finding and observation noted. This may include recommendations for improvement, if possible.
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| Not Observed or N No comments are required.
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| Not Applicable CHECKLISTS Section 2121 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 w
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| R:v. O Pags 4.3-4 I. CONTROL ROOM A. Accident Assessment /Emeroency Classification Ratino Comments
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| : 1. Did the Control Room staff demonutrate the Yes/No ability to recognize emergency initiating conditions and classify the events in accordance with AP 31257
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| : 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?
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| B. Notification and Communication
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| : 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?
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| : 2. Did the Control Room staff demonstrate the Yes/No ability to notify federal and state j authorities of emergency classifications in ;
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| accordance with established procedures? I
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| : 3. Was information flow within the Control Yes/No Room and to other appropriate emergency <
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| response facilities timely, complete, and accurate?
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| : 4. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the Control Room staff?
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| : 5. Were adequate emergency communication Yes/No I systems available in the Control Room I to transmit data and information to j other emergency response facilities?
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| : 6. Did the control Room staff maintain an Yes/No effective open line of communication with the NRC over the ENS as requested?
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| C. Activation and Response
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| : 1. Did the Contrcl Room staff demonstrate the Yes/No ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them? i l
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| : 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?
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| : 3. Did the Control Room staff interface with Yes/No the NRC site response team in an effective manner?
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| Controller Names L
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| _=
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| - . _ . . - . _ . . _ _ _ . . _ . ___._____.m .- ._._.-. _
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| R2v. O !
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| Pego 4.3-5
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| -II. TECHNICAL SUPPORT CENTER A. Accident Assessment /Emeroency Classification Ratina Comments
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| : 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? :
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| : 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?
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| : 3. Did the TSC staff demonstrate the ability Yes/No to initiate and coordinate corrective actions in an efficient and timely manner?
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| : 4. Did the TSC staff demonstrate the ability Yes/No to direct and coordinate the taking of appropriate chemistry samples to analyze plant conditions?
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| : 5. Did the TSC staff demonstrate the ability Yes/No to participate with the Centrol Room and EOF /RC in emergency classification and EAL discussion? ,,
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| B. Hgtification and Communication
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| : 1. Was information flow within the TSC and to Yes/No other appropriate emergency response facilities timely, complete, and accurate?
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| : 2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the TSC staff? i
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| : 3. Were adequate emergency communication Yes/No systems available in the TSC to transmit data and information to other emergency response facilities?
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| : 4. Was information concerning plant Yes/No conditions disseminated between the Control Room and TSC performed in a timely ,
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| manner?
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| : 5. Were status boards utilized and maintained Yes/No l to display pertinent accident information at the TSC7
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| : 6. Did the TSC staff provide technically Yes/No qualified individuals to man the open line of communications over the ENS and HPN phone j links with the NRC as requested 7 s
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| Controller Names L
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| ._.__._ _ .._ _. _ . . - . . . . . . _ _ . _ _ . _ . . . . , . . . . _ _ _ . -m. . __._
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| R:v. O PagD 4.3-6
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| 'II. TECHNICAL SUPPORT CENTER (cont'd)
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| C. Activation and Resoonse Ratina Comments
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| : 1. Did the TSC staff demonstrate the ability Yes/No to activate and staff the TSC7
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| : 2. Did the TSC staff demonstrate the ability Yes/No
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| ! to appropriately Laplement Emergency Plan l Implementing Procedures and did they follow I
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| them?
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| -3. Were initial and continuous accountability Yes/No checks of TSC and CR personnel performed?
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| I
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| ( 4. Did the TSC Coordinator establish and Yes/No coordinate access control into the Protected Area and Control Room?
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| : 5. Did the TSC Coordinator demonstrate the Yes/No
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| ! ability to maintain command and control of
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| ( TSC emergency response activities?
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| : 6. Did the TSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had developed?
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| i 7. Was the TSC organization and initiation of Yes/No
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| ! activity efficient and well organized?
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| : 8. Did the TSC staff interface with the NRC Yes/No site response team in an effective manner?
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| i controller Names f
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| }
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| Rsv. O Page 4.3-7 III. OPERATIONS SUPPORT c!NTER 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?
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| : 2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the OSC staff 7
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| : 3. Were adequate emergency communication Yes/No systems available in the OSC to transmit data and information to other emergency response facilities?
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| : 4. Were status boards utilized and maintained Yes/No to display pertinent accident information at the OSC7 B. Activation and Rosconse
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| : 1. Did the OSC staff demonstrate the ability Yes/No to activate and staff the OSC7
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| : 2. Did the OSC staff demonstrate the ability Yes/No to appropriately Omplement Emergency Plan Implementing Procedures and did they follow them?
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| : 3. Were initial and continuous accountability Yes/No checks of OSC personnel performed?
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| : 4. Did the OSC Coordinator and OSC Yes/No Coordinator's Assistant demonstrate the ability to maintain command and control of OSC emergency response activities?
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| : 5. Did the OSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had developed?
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| : 6. Was the OSC organization and initiation of Yes/No activity efficient and well organized?
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| : 7. Did the OSC staff demonstrate the Yes/No ability to provide adequate radiation protection controls for on-site emergency response personnel?
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| : 8. Did the OSC staff demonstrate the Yes/No ability to perform radiological habitablity assessments of emergency response facilities and implement appropriate habitability controls?
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| Controller Names
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| * L
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| - .. . . _ _ .- .-. . . -. - = _ _ . - - . - . - _ . ~ . . . . - - . . - .. ..~
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| .' R3v. O Pag 3 4.3-8 f III. OPERATIONS SUPPORT CENTER (cont'd) ,
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| Ratina Comments
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| : 9. Did the OSC staff demonstrate the Yes/No ability to monitor and track radiation exposure of on-site emergency response personnel?
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| : 10. Did the OSC staff demonstrate the Yes/No ability to obtain and analyze appropriate chemistry samples as directed by the TSC7
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| : 11. Did the OSC staff demonstrate the Yes/No ability to initiate, brief, and dispatch on-site assistance teams?
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| : 12. Were on-site assistance teams able to Yes/No trouble-shoot and evaluate problems with plant equipment and systems?
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| : 13. Were there adequate administrative Yes/No controle and documentation taken to perform the necessary repairs of plant equipment and systems during an emergency situation?
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| : 14. Did the OSC staff interface with the NRC Yes/No f
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| site response team in an effective manner? l controller Names t
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| L
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| - . . . . . .- ~ - - _ ~ - - . - . - - . - - . - . . _ - ---- . ,
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| R:v. O Peg 2 4.3-9 IV. EMERGENCY OPERATIONS FACILITY / RECOVERY CENTER A. Notification and Communication Ratina Comments i
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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?
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| : 2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the EOF /RC staff?
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| : 3. Were' adequate emergency communication Yes/No systems available in the EOF /RC to transmit data and information to other emergency response facilities?
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| : 4. Was information concerning plant Yes/No l conditions disseminated between the TSC and '
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| EOF /RC performed in a timely manner?
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| : 5. Were status boards utilized and maintained Yes/No l to display pertinent accident information ,
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| at the EOF /RC7
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| : 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?
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| B. Activation and Resoonse
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| : 1. Did the EOF /RC staff demonstrate the Yes/No ability to activate and staff the EOF /RC7
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| : 2. Did the EOF /RC staff demonstrate the Yes/No ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
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| : 3. Did the Corporate Security Force Yes/No esicolish access control into the EOF /RC7
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| : 4. Did the EOF Coordinator demonstrate the Yes/No ability to maintain command and control of EOF emergency response activities?
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| : 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 initiation of activity efficient and well organized?
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| : 7. Did the EOF staff demonstrate the ability Yes/No to monitor habitability conditions and establish the necessary monitoring controls at the EOF and Newr Media Center?
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| Controller Names
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| - . . . . . - _ - . . - . _ . . . - - . .. . . . - . - ~ . _ ~ . - . - - _ _ - _ _ . _ - . . . . , _ _ . .
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| Rev. O Pcgs 4.3-10 t
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| IV. EMERGENCY OPERATIONS FACILITY / RECOVERY CENTER (cont'd)
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| Ratina Comments
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| : 7. Did the Site Recovery Manager demonstrate Yes/No the ability to maintain the command and control of the overall emergency response effort and organization?
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| 8..Did the Site Recovery Manager Yes/No demonstrate the ability to de-escalate from the emergency phase into the recovery phase?
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| : 9. Were preliminary recovery plans Yes/No established and discussed between the !
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| Site Recovery Manager and appropriate personnel?
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| : 10. Did the EOF staff interface with the NRC Yes/No site response team in an effective manner 7
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| : c. Radioloaical Assessment
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| : 1. Was information concerning radiological Yes/No '
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| and meteorological data obtained by appropriate EOF personnel in a timely manner?
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| : 2. Did the EOF staff demonstrate the ability Yes/No to perform off-Site dose assessment in accordance with OP 35137
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| : 3. Did the EOF staff demonstrate the ability Yes/No to effectively track and define the plume )
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| utilizing the computerized dose assessment model (METPAC)?
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| : 4. Did the EOF staff demonstrate the ability Yes/No to coordinate off-site monitoring data with State authorities?
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| D. Protective Action Decision Makina l
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| l
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| : 1. Did the Radiological Assistant's staff Yes/No demonstrate the ability to perform timely assessment of off-site radiological conditions to support the formulation of protective action recommendations?
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| : 2. Did the EOF Coordinator obtain and ,
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| Yes/No provide the necessary information to the Site Recovery Manager concerning protective action recommendations in accordance with OP 35117
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| : 3. Did the Site Recovery Manager Yes/No 2 i
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| demonstrate the ability to make i protective action recommendations to i off-site authorities in accordance with Procedure OP 35117 i Controller Name 4
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| l a
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| f
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| R v. O P2g3 4.3-11 V. SITE AND OFF-SITE MONITORING A. Activation and Response Ratino Comments
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| : 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 35107
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| : 2. Were site and off-site monitoring Yes/No teams dispatched and deployed in a timely manner?
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| : 3. Were team members familiar with the use Yes/No of equipment, field monitoring procedures, and what was required of them?
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| : 4. Were off-site monitoring teams able to Yes/No determine and communicate their location in the field using appropriate maps and sample points (landmarks)?
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| : 5. Were off-site monitoring teams briefed Yes/No on plant conditions and changes?
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| . l controller Names
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| - .- _. . --_- .. . . . . . . . ~ . ..- . - ~.
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| R2v. O Pcg3 4.3-12 VI. SECURITY A. Activation and Resoonso Ratino CQEment,1
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| : 1. Did the security staff demonstrate Yes/No the ability to perform accountability of personnel within the Protected Area in accordance with Procedure OP 35247
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| : 2. Were access control points established Yes/No and maintained to control access at the p site and the Protected trea?
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| ) 3. Did the security staff demonstrate the Yes/No l ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
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| l Controller Names I
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| i i
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| {
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| l R3v. O l Prga 4.3-13 l
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| l VII. NEWS MEDIA CENTER A. Activation and Responsg Ratino Comments
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| : 1. Did the News Media staff demonstrate the Yes/No ability to activate and staff the News Media Center?
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| : 2. Was information flow between the News Yes/No Media Center and the EOF /RC timely, complete, and accurate?
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| ! 3. Were the News Media staff familiar with Yes/No their plans and procedures and do they follow them?
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| : 4. Did the News Media staff demonstrate the Yes/No l ability to provide accurate and timely l
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| information concerning the emergency to the public and the news media?
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| : 5. Did the News Media staff demonstrate the Yes/No ability to coordinate news releases with the state's public information representatives?
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| l 6. Did the News Media staff demonstrate the Yes/No l
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| ability to provide briefings for and to interface with public and news media? .
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| : 7. Did the News Media Center Coordinator Yes/No .
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| discuss the habitability conditions of )
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| i the News Media Center with appropriate ,
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| i State and Federal officials and assembled media staff?
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| 1 l 8. Did the News Media staf f interf ace with the Yes/No
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| ! NRC site response team in an effective manner?
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| l l
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| Controller Names f
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| L
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| l nuv. w Prg3 4.3-14 EMERGENCY EXERCISE / DRILL CONTROLLER'S EVALUATION FORM Controller's Names Exercise / Drill Date: March 19, 1997 j Ex rcise/ Drill Titles 1997 Vermont Yankee Annual Emercenev Precaredness Exercise C ntroller's Location:
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| Time Started: Time Ended:
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| Observed: Player Function ]
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| I Overall Performance and Observations: (Include the proper and effective use of procedures, cquipment and personnel)
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| I l
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| l l
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| Comments and Recommendations (Specific):
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| l l
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| l 1
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| Recognized Weaknesses and Deficiencies:
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| l l
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| l
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| ' H221 i Use additional pages as required. j Signature Title ,
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| t l
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| I l
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| VYOPF 3505.02 (Sample) l l OP 3505 Rev. 18 Page 1 of 1 RT No. 10.E06.151 I 1
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| . . _.. . - _ _ _ _ __._._m -
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| R:v. O Page 5.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 13,1 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
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| : 1. The reactor is now at approximately 1004 power. The reactor has been operating steady state for the past seventeen months with no recent shutdowns. The Rod Sequence is A-2 and the Rod Group is 242. The Solomon software is not available. All control rods are fully withdrawn.
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| 2.
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| The Operations crew turnover log provides the following updated plant informations
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| : a. The Circulating Water System is operating in Open Cycle.
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| : b. The 'C' Reactor Feedwater pump was taken out of service for Mechanical Maintenance to replace a failed bearing. The pump will .
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| not be available for the next two days. 1 l
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| : 3. The initial plant and reactor system parameters associated with the start of the exercise are shown on Table 5.1-1, " Initial Plant and Reactor I System Values" and " Vermont Yankee Daily Plant Status Report."
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| : 4. The following on-site meteorological conditions exist at 0800:
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| Wind Speed, sph (upper / lower) 5.4/4.2 Wind Direction, degrees (upper / lower) 320/307 Delta Temperature, T (upper / lower) -0.40/-0.32 Ambient Temperature, T 28.0 Precipitation, inches 0.00
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| : 5. Regional Meteorological Forecast Informations A low pressure system will move off to the east today, causing the cloud cover to diminish and a wind shift from the northwest to the north.
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| Mostly to partly cloudy this morning. Temperatures rising from current 20's into the low 40's. Northwesterly winds from 3 to 6 MPH becoming northerly around midday.
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| f 1
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| l
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| Rev. O Page 5.1-2 Table 5.1-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 159 Inches Reactor Pressure 1015 psig Reactor Coolant Temperature 526 *F Reactor Power - APRM (average) 100.0 t 17 paid Core Plate D/P Total Core Flow 47 x 10' lbm/hr Main Steam Line Flow - Total 6.4 x 10' lbm/hr Main Steam Line Radiation (average) 163 mR/hr Condenser Hotwell Level 55 4 condenser Vacuum 1.8 in. Hg(Abs)
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| Condensate Storage Tank Level 60 t Recire Drive Flow 24.3 Kgpm/ loop 6.4 x 10' lbm/hr Feedwater Flow '
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| Reactor Building D/P -1.52 in H O 2
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| Drywell Pressure 2.3 psig Drywell Temperature 140 'F Torus Water Level 11.08 ft Torus Temperature 78 *F 1.49 4 Drfwell/ Torus 0 Concentration 3 High Range Containment Monitors 3.2 R/hr containment Ges/ Particulate 590/6230 cpm Reactor Buildiag 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 itate 695 pCi/see Stack Gas 1/2 150/200 cpm High Range Noble Gas Monitor 0.1 mR/hr l
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| L
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| Rev.O Page 5.1-3 "THIS IS A DRILL - FOR DRILL PURPOSES ONLY" VERMONT YANKEE DAILY PLANT STATUS REPORT QAIyg MARCH 19,19f7 VALUE RAE EdB PLANT OPERATING STATUS
| |
| : 1. CORE THERMAL POWER (MWt)l(%) 1594l100.0 - 0700
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| : 2. GROSS MWe 550 - 0700
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| : 3. NET MWe 529 - 0700
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| : 4. GROSS MWh FOR PREVIOUS DAY 13210 - -
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| : 5. CORE FLOW (Mlb/hr)l(%) 46.5/94.8 - 0700 REACTOR COOLANT SYSTEM
| |
| : 6. CONDUC71VITY (umho/cm)(Pane!) 0.113 03/18/97 0820
| |
| : 7. UNIDENTIFIED LEAKAGE @ 0.69 - -
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| MIDNIGHT PREVIOUS DAY (spm)
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| : 8. TOTAL LEAKAGE @ 2.19 - -
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| MIDNIGHT PREVIOUS DAY (spm)
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| : 9. SPECIFIC ACTIVITY (uci/ml) 4.63X10-2 03/18/97 0820
| |
| : 10. IODINE - 131 DOSE EQUIVALENT (uCi/ml) 5.50X10 4 03/18/97 < 0820 ,
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| STACK RELEASES
| |
| : 11. PARTICULATE (ci/ period) < 1.33X10-3 03/17/97 1335
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| : 12. AVERAGE (uci/sec) < 100 03/19/97 0040
| |
| : 13. PEAK (uCi/sec) None 03/19/97 0040
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| : 14. DISCHARGE AVERAGE GAMMA 0.756 03/17/97 1335 ENERGY (E) (MeV)
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| : 15. DOSE RATE TO CRITICAL ORGANS (mrem /yr) 4.91X10-2 03/17/97 1335
| |
| : 16. IODINE - 131 (uCi/sec) < 1.62X10-5 03/17/97 1335 OFF GAS ANALYS]} ,
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| : 17. SIAE DISC. RELEASE RATE (MEASURED)(uCi/sec) 695 03/19/97 0530
| |
| : 18. SJAE DISCHARGE SLOPE OF MIXTURE -0.0300 03/19/97 0530
| |
| : 19. CONDENSER AIR INLEAKAGE (cfm) 17.7 03/19/97 0040 LIOUID RELEASES & RIVER TEMPERATURE
| |
| : 20. LIQUID RELEASE (gal) NONE - -
| |
| 4
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| : 21. LIQUID RELEASE (GROSS: B,)(uCi/ml) NONE - - I
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| : 22. LIQUID RELEASE (TRITIUM)(uci/ml) NONE - -
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| : 23. LIQUID RELEASE (DISSOLVED NOBLE GAS) (uCi/ml) NONE - -
| |
| : 24. RIVER MON. #3 HIGHEST TEMP. FOR PREVIOUS DAY (T) 38.0 - 1750 EllLHlf
| |
| : 25. CORE AVG. BURNUP FOR PREVIOUS DAY (MWD /ST) 13979.58 - - a
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| : 26. CORE CYCLE BURNUP FOR PREVIOUS DAY (MWD /ST) 1317.58 - -
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| j "THIS IS A DRILL" NOTE: INITIAL DAILY PLANT STATUS FOR DRILL PURPOSES ONLY
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| Rev. O Page 5.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 L2 EXERCISE SEQUENCE OF EVENTS The exercise begins at 0800 with the reactor (simulator) running at 100% power.
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| The reactor has been in a steady state for the past seventeen months with no recent shutdowns. The Circulating Water System is operating in Open Cycle. The rod sequence is A-2 and the rod group is 242. All control rods are fully withdrawn. The Solomon software is not available. The "C" Reactor Feedwater pump was taken out of service for Mechanical Maintenance to replace a failed bearing. The pump will not be available for the next two days.
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| Command Cards SCR-C-1 (OB00h Guidelines provided to Simulator Control Room players on the use of GaiTronics and the plant evacuation alarm during the exercise. SCR-C-2 'f08001:
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| Instructions provided to Simulator Control Room players that early in-plant actions may be controlled and performed by the Simulator Controllers.
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| Message Cards INITIAL-M-1 (start of exercise or f acility activationh Exercise scenario initial conditions provided to the Simulator Control Room players and to appropriate Emergency Facility Coordinators upon activation. Security (OB00h A list of Exercise Controllers and non-participants provided to Security Shift Supervisor who will not have to be accounted for during the exercise.
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| At approximately 0815, the "A" Recirculation pump trips due to differential overcurrent of the pump drive motor. Reactor power automatically decreases.
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| Operators will start running the plant in a single loop operation. The shift should monitor the reactor for instability and began inserting control rods to reduce power to remain outside the exclusion region of the core operating limits.
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| [ (Manual scrata of the reactor will be controlled at this time.)
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| Command Cards SCR-C-3 (0815 er when neededh instructions to prevent manual scram of the reactor.
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| At approximately 0820, the DC-2, circuit 2, breaker feeding DC-3 trips on thermal overload due to a high resistance connection on the load side of the molded case breaker. The loss of DC-3 results in the normal feed to DC-3A to be lost. Loss of DC-3A results in a loss of all front Control noom panel annunciators. (Refer to Mini-scenario 7.2.1). l
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| ._.__m _ . - _ . . _ _ . _ _ _ . . _ . . ._..-._.m______._ _ . - _ .
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| I Rev. O Page 5.2-2 i
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| i An ALERT should be declared (approximately 0835) based on AP 3125, " Loss of Systems or Equipment" (All Control Room alarms on CRP 9-3, 9-4 and 9-5 :
| |
| inoperable). The Shift Supervisor should initiate the appropriate notifications concerning the declaration of the Alert and changing plant conditions.
| |
| Command Cards SEC-C-1 (0835 or when needed): Instructicns provided to Security Shift Supervisor to simulate communications with the New England Hydro Power Station. SCR-C-4 (0845 f or when needed): Instructions to control the declaration of the Alert.
| |
| Message Cards SEC-M-1 (0835 or when needed): Guidelines provided to Security Shift Supervisor on YNSD pa0er activation. TSC-M-1 (0835 or when needed): Guidelines provided to TSC f Coordinator on assignment of TSC Communicators to Control Room.
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| Following the alee'r declaration, the Technical Support Center (TSC), Operations t I
| |
| support Center (OSC), Emergency Operations Facility /Rencovery Center (EOF /RC), knd Engineering Support Center (ESC) should be activated and staffed. The News Media Center has the option to activate at the Alert classification. State and local Emergency Operations Centers should also be activated and staffed. ;
| |
| By 0850, power for DC-3A is transferred to DC-1. Control Room panel annunciators are restored. Operators continue to monitor reactor for instability and run ,
| |
| plant in a single loop operation.
| |
| 1 At approximately 0950, a large break loss of coolant accident (LOCA) occurs.
| |
| Reactor automatically scrams. Coincident with the LOCA, the 3Tl 4160 VAC Bus 1 e to Bus 3 tie breaker suffers a gross failure that prevents the breaker from opening and the 13 breaker fails to fast transfer on the loss of the Auxiliary Transformer after the reactor scram. Significant fuel clad failure is postulated i
| |
| )
| |
| to begin due to loss of coolant and reactor water level below the top of the ;
| |
| reactor fuel (level will drop below -48" ) . Containment high-range monitor readings will start to trend up to greater than 1000 R/hr.
| |
| i i
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| By 0955, drywell pressure and radiation levels have increased significantly.
| |
| The shift should follow the appropriate procedures to mitigate the loss of coolant accident. This should include restoring reactor water, controlling drywell pressure.
| |
| The failure of the 13 breaker to fast transfer causes the loss of power on Bus '
| |
| 1 and Bus 3. The loss of Bus 3 will initiate "B" Diesel Generator (DG) to start to provide power to Bus 3. However, the "B" DG is prevented from powering Bus k
| |
| | |
| i i
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| r Rev. O l Page 5.2-3 3 due to an interlock between the "B" DG breaker and 3T1. Therefore, a loss of power to Bus 3 and Bus 1 occurs.
| |
| As a result of the power loss to Bus 1 no Reactor Feed Pumps are available as a source of high pressure feed, only the steam driven High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) systems are available.
| |
| This will drive the operators to Reactor Pressure Vessel Emergency Depressurization (RPVED) to decrease pressure for low pressure system injection.
| |
| j operators should also initiate actions to restore power to Bus 3 and Bus 1.
| |
| l (Refer to Mini-scenario 7.2.2 and Mini-seenario 7.2.3).
| |
| A SITE AREA EMERGENCY should be declared (approximately 1005) based on AP 3125,
| |
| " Loss of Systems or Equipment" (Loss of systems or equipment such that reactor l water level is below -48 inches) QB " Fuel Damage" (Containment radiation monitors l
| |
| l reading greater than 1000 R/hr). Notifications should be made to appropriate l plant personnel and off-site agencies on the escalation to the site Area l Emergency.
| |
| Command Cards EOF C-1 (1020 or when needed): Instructions to control the declaration of the Site Area Emergency.
| |
| Off-site dose assessment activities should be initiated to determine potential l of f-site dose projections and of f-site monitoring teams may be dispatched to pre-selected monitoring points based on meteorological conditions. In-plant samples l of plant systems (reactor coolant and primary containment) and radiological I surveys may be initiated to assess plant conditions and support accident l assessment activities. (Refer to Mini-scenario 7.2.6).
| |
| l Message Cards EOF-M-1 (1030 or when reauestedh Information to be provided to EOF Rad Assessment l
| |
| staff on the National Weather Service forecast or plant site meteorological conditions.
| |
| l ESC-M-1 (1030 or when reouested): Information provided to ESC meteorologist on weather forecast for the Vermont Yankee site.
| |
| 1 i
| |
| ( At approximately 1105, Electrical Maintenance has completed repairs to the 3T1 breaker and 13 breaker. Power is restored to Buses 3 and 1.
| |
| Drywell radiation levels increase. At approximately 1135, Containment high-range monitor readings are greater than 5000 R/hr. Indication of a significant inventory of radioactive material inside the primary containment.
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| i I
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| I
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| Rev. O Page 5.2-4 A GENERAL EMERGENCY should be declared (approximately 1145) based on AP 3125,
| |
| " Fuel Damage" (Loss of 2 of 3 fission product barriers with potential loss 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 conditions. Dose assessment activities should [
| |
| continue to project potential off-site doses.
| |
| t Command Cards EOF-C-2 M 200 or when neededh Instructions to control the declaration of the General Emergency.
| |
| At approximately 1220, Residual Heat Removal (RHR) Pump "D" seal failure occurs. .
| |
| RHR Pump 'D' suction valve trips when flagged to close. Southeast RHR Corner Room temperature increases. Reactor Building sump alarms and Area Radiation Monitors (ARMS) in the Reactor Building are increasing significantly. Indication of a significant release of radioactive material into the Reactor Building (secondary containment). RHR Pump "D" can not be isolated due to the suction valve Motor control center (Mcc) overload relay trip. (Refer to Mini-scenario 7.2.4 and Mini-scenario 7.2.5). ;
| |
| By 1225, Plant Vent Stack monitors are indicating a release of radioactivity to the environment. Dose assessment activities should be initiated to track plume direction and project off-site doses. ,j l
| |
| At approximately 1320, repairs to the RHR Pump "D" suction valve MCC overload relay are completed. RHR Pump "D" suction valve can be closed which isolates the i leak into the Reactor Building.
| |
| At approximately 1335, ARMS located in the Reactor Buildings and PVS monitors indicate a decreasing trend. Source of release into the environment has been isolated.
| |
| By 1350, Plant staff should complete activities to stabilize plant conditions.
| |
| Exercise objectives should have been demonstrated.
| |
| At 1415, the exercise may be terminated.
| |
| ..l il 1
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| - . . _ - - . - - - - - _ _ _ _ - . . . . - - - - . _ _ _ _ . ~ . - . . . . _
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| 4 Rev.O Page 5.31 I
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| VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 >
| |
| L2 EXERCISE SCENARIO TIME LINE '
| |
| CLOCK' SCENARIO TIME TIME DESCRIPTION 0800 0:00 <- Exercise starts with initial conditions established in the Simulator Control Room.
| |
| 0815 0:15 <- "A" Recirculation pump trips. Reactor power decreases. Operators start running plant in a single loop operation.
| |
| 0820 0:20 <- DC-2 feeder breaker to DC 3 trips. Normal feed to DC-3a is lost. Loss of DC-3a results in a loss of all front Control Room panel annunciators.
| |
| 0835 0:35 <- i ALERT (AP-3125 Less of Systems or Dament) - All Control Room alarms on CRP 9 3, )
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| 9-4 and 9-5 inoperable. 't 0850 0:50 <- Power for DC-3A is transferred, Control Room panel annunciators restored. Operators continue to monitor reactor for instability and run plant in a single loop operation.
| |
| 0950 1:50 <- Large break loss of coolant accident occurs. Reactor automatically scrams. The 3T14160 VAC Bus 1 to Bus 3 tie suffers a gross failure that prevents the breaker from opening and Breaker 13 fails to fast transfer which causes a loss of power to Bus 1 and Bus 3.
| |
| Significant fuel clad failure begins due to loss of coolant and reactor water level below the top of the reactor fuel (level will drop below -48"). Containment high-range monitor '
| |
| readings start to trend up to greater than 1000 R/hr.
| |
| 0955 1:55 <- Drywell pressure and radiation levels have increased significantly. Operators initiate actions to restore reactor water level and control drywell pressure. As a result of the power loss to Bus 1 no Reactor Feed Pumps are available as a source of high pressure feed, only the steam driven HPCI and RCIC systems are available. This will drive the Operators to RPVED to decrease pressure for low pressure system injection. Operators also initiate actions to restore power to Bus 3 and Bus 1.
| |
| ~
| |
| 1005 2:05 <- SITE AREA EMERGENCY (AP-3125. Loss of Systems or Eoulement) - Loss of systems or equipment such that reactor water level is below -48 inches QB (AP-3125. Fuel Damanal -
| |
| Containment radiation monitors reading greater than 1000 R/hr.
| |
| 1105 3:05 <- Repairs to the 3T1 breaker and 13 breaker are completed. Power is restored to Buses 3 l
| |
| and Bus 1. I 1135 3:35 <- Containment high-range monitor readings are greater than 5000 R/hr. Indication of a significant inventory of radioactive material inside the primary containment. i 1145 3:45 <- GENERAL EMERGENCY (AP-3125. FUEL DAMAGEl . Loss of 2 of 3 fission product barriers with potential loss of the third.
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| l 1
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| 1 i
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| Rev.O Page 5.3 2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 L2 EXERCISE SCENARIO TIME LINE (centinued)
| |
| CLOCK SCENARIO TIME TIME DESCRIPTION 1200 4:00 ' <- Off site protective action recommendations issued to State authorities based on plant conditions.
| |
| 1220 4:20 <- RHR Pump "D" Seal failure occurs. Southeast RHR Corner Room temperature increases and alarms. Reactor Building sump alarms and Area Radiation Monitors (ARMS) in the Reactor Building are increasing significantly. Indication of a significant release of radioactive material into the Reactor Building (secondary containment). RHR Pump "D" can not be isciated due to the suction valve MCC overload relay trip.
| |
| 1225 4:25 <- Plant Vent Stack (PVS) indicating release of radioactivity to the environment. Dose assessment activities initiated to track and project off site doses.
| |
| 1320 5:20 <- Repairs to the RHR Pump 'D' suction valve MCC overload relay are completed. RHR Pump "D" suction valve can be closed which isolates the leak into the Reactor Building.
| |
| 1335 5:35 <- ARMS located in Reactor Building and PVS monitors indicating a decreasing trend. Source of release into the environment has been isolated.
| |
| 1350 5:50 <- Plant staff complete activities to stabilize plant conditions.
| |
| 1415 6:15 <- EXERCISE MAY BE TERMINATED 9
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| 4 h
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| , . . . , - ~ . - - . . - - . . . . - - ~ . - . - - - - - - - - - . . . - - - - . . . ~ . . _ . . - . ~ . . . . . . - . . - . . . . . -
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| r t
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| P VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNES5 EXERCISE ,
| |
| t 1997 i
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| a l
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| t I
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| 6.1 COMMAND CARDS ir h
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| e t
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| i t t
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| e Y
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| P h
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| (
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| 1 e
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| p I
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| 6
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| 'I ,
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| l
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| s 1
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| I t i I
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| I .
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| +
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| - ~ _. . - ~ . . - - _ . - - .- - - . - .-.
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| 1 i
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| R v. O Page 6.1-1 VERMONT YANKEE NUCLEAR POWER STATIOM EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO COMMAND CARD FRON: Simulator CR Lead Controller COMMAND NO. SCR-C-1 TO: Shift Sunervisor CLOCK TIME: Prior to 0800 LOCATION: Simulator Control Room SCENARIO TIME: Prior to 00:00 esee.......... e.** ...eeeeee. e******* eeeeeeee***eeeeeeeeeeeee...........e**
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| THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. )
| |
| ..........eeeeee.....ee.........e..eee....eeeee.eeeeee.......e.e.ee.....e*** e
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| \
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| l l
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| Communications systems that are available in the Control Room have been 1 duplicated in the Simulator Control Room (SCR) EXCEPT for GAITRONICS/ PLANT '
| |
| EVACUATION ALARM. )
| |
| i 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 l l
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| the shift operations crew at the plant to repeat the announcements from the Main Control Room.
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| 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 I plant to talk directly to the simulator over the plant GAITRONICS. The Controller in the plant Main control Room will monitored and manually actuated j the interface, causing a slight delay between initial communications. CHANNEL 3 '
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| is the designated the line to be used for communications between the Simulator {
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| control Room and the Plant. CHANNEL 1 and CHANNEL 2 are the designated lines '
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| for all other plant exercise related communications and messages.
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| l eeeeeeeeeeeeeeeeeeeeeeeeeeeeeee***eseseeeeeeeeeeeee**eeeeee***eeeee**eeme** **
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| ^
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| THIS IS A DRILL eeee.......e.e ee....eeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeee**e*********eeme*
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| - . . . . ~. - . - . . .. . - . - . - . - . - - . . . . ._,
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| Rrv. O l Pega 6.1-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE i
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| 1997 J
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| SCENARIO COMMAND CARD FROM Simulator CR Lead Controller COMMAND NO.: SCR-C-2 To: Shift Suoervisor CLOCK TIME: 0800 or when needed
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| }
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| LOCATION: Simulator control Room SCENARIO TIME: 00:00 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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| 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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| 1 THIS IS A DRILL .
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| e e
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| R3v. O Pag 2 6.1-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO COMMAND CARD FROM: Simulator CR Lead Controller COMMAND NO.: SCR-C-3 TO: Shift Suoervisor CLOCK TIME: 0815 or when needed LOCATION: Simulator Control Room SCENARIO TIME: 00:15 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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| For scenario purposes, DO NOT manually scram the reactor at this time.
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| l THIS IS A DRILL i
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| ....................................~.- ~ ~.~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~.~ ~
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| . . . . - _. . ._ . . _ . . . _ . . - - ~ ~ . -.. - .
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| I R;v. O l Prga 6.1-4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO COMMAND CARD d
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| 1 FROM: Security Lead Controller COMMAND NO.: SEC-C-1 l
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| TO: Security shift Supervisor CLOCK TIME: 0835 or when needed LOCATION: Security Gatehouse 2 SCENARIO TIME: 00:35 l
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| )
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| THIS IS A DRILL ,
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| DO NOT initiate any actions affecting normal plant operations. j f ;
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| .............................................................................. j, ;
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| l FOR EXERCISE PURPOSES, communications with New England Hydro Power Station in Vernon will be simulated.
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| i THIS IS A DRILL 9
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| l j .i l
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| R3v. O l
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| Pego 6.1-5 VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY PREPAREDNESS EXERCISE 1997 I
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| t SCENARIO COMMAND CARD ,
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| FROM: Simulator CR Lead Controller COMMAND NO.: SCR-C-4 TO: Shift Suoervisor CLOCK TIME: 0845 LOCATION: Simulator control Room SCENARIO TIME: 00:45 I THIS IS A DRILL j DO NOT initiate any actions affecting normal plant operations.
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| l l
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| DECLARE AN ALERT BASED ON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT - All Control l Room alarms on CRP 9-3, 9-4 and 9-5 inoperable."
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| l i ..............................................................................
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| THIS IS A DRILL a
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| .- ~_ .. -- . . . _ _ . _ _ . - ~ _ . . - _ _ ~ _ - - . _ .
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| R v. O Pcg3 6.1-6 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO COMMAND CARD FROM EOF Lead Controller COMMAND NO.: EOF-C-1 TO: Site Recovery Manaaer CLOCK TIME: 1020 1
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| LOCATION: EOF SCENARIO TIME: 02120 l
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| .............................................................................. l THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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| l l
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| l DECLARE A SITE AREA EMERGENCY BASED ON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT -
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| i Loss of systems or equipment such that reactor water level is below -48 inches l l
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| QB FUEL DAMAGE - Containment radiation monitors reading greater than 1000 R/hr." l l
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| 1 R v. O Pag 3 6.1-7 (
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| VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO COMMAND CARD }
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| l FROM: EOF Lead Controller COMMAND NO.: EOF-C-2 TO: Site Recovery Manaaer CLOCK TIME: 1200 l LOCATION: EOF SCENARIO TIME: 04:00 j
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| j THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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| DECLARE A GENERAL ENERGENCY BASED ON AP 3125, " FUEL DAMAGE - Loss of 2 of 3 fission product barriers with the potential loss of the third". j l
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| i THIS IS A DRILL i i
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| - --ra __ -- ,--,. _ a- , - 4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 6.2 MESSAGE CARDS l
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| R v. O Pcg3 6.I-l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO i4ESSAGE CARD FROM: gacility Lead controller MESSAGE No.: INITIAL-M-1 TO: Facility Coordinator CLOCK TIME: Start of Exercise or LOCATION: Various ERFs SCENARIO TIME: Facility Activation THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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| For initial conditions, provide section 5.1 of the exercise manual to players.
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| NOTE TO CONTROLLERS Please make sure that the initial conditions ,are gi*en to the following individuals: Shift Supervisor, Duty call Officer, Plant Manager, Operations Manager, Assistant Operations Manager, Operations Planning coordinator, Operations Superintendent, and VP-Operations.
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| THIS IS A DRILL
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| -----.-___a
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| R0v. O Pega 6.2-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO MESSAGE CARD FROM: Security Lead controller MESSAGE NO.: SEC-M-1 TO: Security Shift Suoervisor CLOCK TIME: 0835 LOCATION: Gatehouse 2 SCENARIO TIME: 00:35 l
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| l ..........**................................ **.....***......****............ ......
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| ! THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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| j ..........................**....**..................................................
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| NOTE TO CONTROLLER: l i
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| l FOR EXERCISE PURPOSES, direct the Security Shift Supervisor when using Procedure OP l 3531, " Emergency Call- In Method" to implement the following instructions: j l
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| : 1. WEEN ACTIVATING YNSD PERSONNEL PAGER SYSTEN, use pager code as DEFINED IN TEE PROCEDURE as the appropriate emergency classification code for YNSD Pager activation during this exercise. .
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| 1 l
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| l 2. Make sure that all EXERCISE-related notifications are preceded by aid and with 1 i
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| " TRIS IS A DRILL". I l
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| THIS IS A DRILL e
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| , .......................................................... ..=**..*..*******
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| * l 1 l f
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| -. =- . . - - . . .
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| R:v. O P gs 6.2-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO MESSAGE CARD FROM: TSC Lead controller MESSAGE No.: TSC-M-1 TO: TSC Coordinator CLOCK TIME: 08:35 or uoon assianment of Communicators LOCATION: Lig SCENARIO TIME: QD 35, THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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| .................................................................**................. i l
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| l After simulating assignment of your TSC Communicators to the Control Room, the prestaged TSC communicators at the Simulator Control Room can now be used.
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| THIS IS A DRILL A
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| rov. O i
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| Page 6.2-4 i
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| VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO MESSAGE CARD FROM: Rad Assessment controller MESSAGE NO.: EOF-M-1 TO: Radioloaical Assistar.t CLOCK TIME: 1030 or as reauested LOCATION: , EOF / Dose Assessment Area SCENARIO TIME: 02:30 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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| NOTE TO CONTROLLER:
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| 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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| R:v. O Page 6.2-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 SCENARIO MESSAGE CARD FROM ESC Lead controller MESSAGE No.: ESC-M-1 TO: ESC Meteorolocist CLOCK TIME: 1030 or as reouested LOCATION: IIS SCENARIO TIME: 02:30 THIS IS A DRILL l DO NOT initiate any actions affecting normal plant operations.
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| l NOTE TO CONTROLLER: l 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: ;
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| I
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| : 1. Provide the general area NWS Forecast information contained in Section 10.2 (page 10.2-1) on ESC activation or when requested. i
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| : 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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| THIS IS A DRILL
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| . _.m-_ . _ _ . . . _ . . _ . . . . _ . _ _ _ . _ _m_.. .m_. _. . _ _ .
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| Rev. O Page 7.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1996 L.1 avuxTs stnesARY The following information and supplementary material are provided for those Controllers having . in-plant control assignments to further ensure the proper development of the scenario. 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 zust be cognizant of the actions of those players to which assignments are given 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.
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| . Approximate Mini-scenario M Event Location 7.2.1 0820 DC-2 Feeder Breaker Cable Vault Room to DC-3 Trip 7.2.2 0950 3Tl Breaker Failure SwitchGear Room '
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| to Trip on Loss of Voltage to Bus 1 and Bus 3 7.2.3 0950 13 Breaker Failure SwitchGear Room to Fast Transfer 7.2.4 1220 RHR Pump 'D' Seal Reactor Building Failure Elevation 213' and RadWaste Building Elevation 230' l 7.2.5 1220 RHR-13-D Overload Reactor Building Relay Trip Elevation 280' i l
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| 7.2.6 N/A Chemistry Samples of Various Locations l Plant Systems and around Plant In-plant Radiological i Surveys
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| auk 3Brh & 94 4- J ahumaEaM-JM A .4 G h-.k 4 A h 4d c J-4 }BhwJMe 6w4 21 Wm AF8 4 5 + +h-+hwAM-48-h h MJ44wA4 4b h-- 4+'A4M--424es.-4M++M446 '
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| 4 #1M s,A-W,24J Am ad-,s.Es a-JM ALMe b e h s a h at4 J s.A. 4 h ,
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| VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE l
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| 1997 t
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| l 7.2 EVENT MINI-SCENARIOS i
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| Rev. O Page 7.2.1-1 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 7.2.1 Mini-scenario - DC-2 Feeder Breaker to DC-3 Trio I. General Descriotion At approximately 0820 (scenario time 0:20), the DC-2, circuit 2, breaker feeding DC-3 trips on thermal overload due to a high resistance connection on the load side of the molded case breaker. The loss of DC-3 results in the normal feed to DC-3A to be lost. Loss of DC-3A results in a loss of all front Control Room panel annunciators.
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| II. DescriDtion of Player Responses / Observations / Corrective Actions By procedure the operators will request Electrical Maintenance to assist with determining the cause of the loss. Operators will also immediately direct an operator to transfer DC-3A to DC-1. Other actions as directed by '
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| ON 3161, " Loss of DC-3" will be carried out. An Alert will be declared during this event.
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| CONTROLLER NOTES ,
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| f 1
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| ! 1. Transfer of power to DC-3A will occur within 10-15 minutes from being i requested.
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| : 2. Electrical Maintenance will determine that the trip of the DC-2 breaker l
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| l feeding DC-3 was due to heat generated by a high resistance connection
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| ! between the field cable and the breaker and there does not appear to l be anything wrong with the breaker.
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| l I III. Event closeout i i This event will be closed out when power is restored to DC-3A. Normal power f from DC-2 through DC-3 to DC-3A may also be restored without further problems once the high resistance connection is repaired. .
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| IV. Messagig, All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players.
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| a Rsv. O Pcg3 7.2.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 7,2.2 Mini-scenario - 3T1 Breaker Failure to Trio on Loss of Voltace to Bus 1 and Bus 3 I. General Descriction At approximately 0950 (1:50 scenario time), a large break loss of coolant accident occurs. The JT1 breaker fails to open on loss of voltage to Buses 1 and 3. Failure of 3T1 to open prevents the Diesel Generator (DG) from providing power to Bus 3 due to an interlock between the DG breaker and 3T1.
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| II. Descriotion of Player Responses / Observations / Corrective Actions ,,
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| l The failure of the 3Tl breaker to open will cause the diesel breaker not I to close causing failure of Bus 3 to re-energize after loss of power.
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| The loss of power was caused by the failure of the fast transfer of Bus 1 l from the Auxiliary transformer to the Start-up transformer (Breaker 13 ,
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| failure to close). (Refer to e Mini-scenario 7.2.3). 1 Electricians will be sent to Bus 3 to investigate the failure of 3T1 to open. Breaker indications show that the breaker may have hung up 1 I
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| mechanically after attempting to trip. This is supported by the fact that the trip coil is burned up indicating that the trip coil energized but was not de-energized by the breaker opening. Any attempts to j i manually trip the breaker will fail, indicating that the mechanism has mechanical failed internally. The breaker indicates closed although the trip mechanism is unlatched.
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| Before the diesel breaker is closed via Control Room action, the failed ]
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| 3Tl breaker should be physically lowered in the cubicle to prevent the 1 diesel from carrying both Bus 3 and Bus I loads. j CONTROLLER NOTES:
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| : 1. There is no interlock to prevent the diesel breaker from being closed by Control Room or local breaker action onto a dead Bus 3 when the 3T1 is stuck closed. If the decision is made to re-energise the Buses (3 and 1) by closing the diesel breaker, positive steps should be taken to reduce Bus I load before clesing the diesel breaker to preclude overloading the diesel with Bus 1 loads.
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| : 2. The positive interlock prevents lowering a closed 4KV breaker. If the 3T1 breaker is to be lowered while it is still closed, both Buses 1 and 3 should be de-energized and the positive interlock mechanism removed before the breaker can be manually lowered with the hand crank.
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| : 3. The re-energizing of Bus 3 must be controlled to not occur until OSC I Lead controller is notified of the intent to re-energize and has coordinated with the Simulator controller (approximate Clock Time 1105).
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| III. Event closecut This event will be closed out when the 3Tl breaker is lowered and the diesel breaker is closed to re-energize Bus 3.
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| IV. Messaces All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players.
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| R v. O Pag 2 7.2.3-1 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 7.2.3 Mini-scenario - 13 Breaker Failure to Fast Transfer I. General Descriotion At approxLmately 0950 (1:50 scenario time), the 13 breaker fails to fast transfer on loss of the Auxiliary transformer after the reactor scram.
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| Failure of 13 breaker to close prevents the feed pumps from being available as a source of high pressure feed to maintain reactor water level.
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| II. Descrintion of Player Responses / Observations / corrective Actions The failure of the 13 breaker to close will cause the failure of Bus 1 to remain energized after loss of the Auxiliary transformer. Failure of this transfer causes loss of power on Bus 1 and Bus 3. Loss of Bus 3 will cause an LNP with subsequent diesel start. However, the diesel breaker will fail to close due to failure of the 3T1 breaker to trip.
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| (Refer to Mini-scenario 7.2.2)
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| Electricians will be sent to Bus 1 to investigate the failure of breaker 13 to close. Breaker indications show that the breaker is open with the springs charged. The'close and trip fuses are good. Any attempt to electrically close the breaker will fail due to a binding of the interlock switch arm causing the switch not to be made. Any attempts to manually close the breaker will be successful.
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| CONTROLLER NOTES:
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| : 1. Before the 13 breaker is closed, the failed 3T1 breaker should be physically lowered in the cubicle to prevent the 3T1 breaker from carrying Bus 3 load in its half tripped state.
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| : 2. There is no interlock to prevent the 13 breaker from being closed by control Room or local breaker action onto a dead Bus I when the 3T1 is stuck closed. The decision should not be made to re-energise the Buses (3 and 1) by closing breaker 13 because of the indeterminate state of the breaker 3T1 contacts due to its half tripped condition.
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| : 3. The re-energising of Bus 1 aust be controlled to not occur until OSC Lead Controller is notified of the intent to re-energise and has coordinated with the simulator control Room (approximate Clock' Time 1105). .
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| 1 III. Event closeout This event will be closed out when the 13 breaker is closed to re-energize Bus 1 from the Start-up transformer.
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| 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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| . _. _. . -_ _ - - . _ . . - . _ . -. _. . _ - . . . . - . - - _.. - - . . =
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| , Page 7.2.4-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE l 1997 L 2,d Mini-scenario - RER Pa=a "D" Seal Failure j I. General Descriotion At about 12:20 (4:20 scenario time), the 'D' RHR pump seal fails resulting in about a 100 gpm leak in the south east corner room. Due to the high radioactive contaminates in the water resulting from the large break LOCA and fuel clad failure, radiation levels in the area begin to 4 significantly increase. The corner room will begin to fill with water j causing a sump alarm to print out in the Control Room. The highly j radioactive water will begin to fill the torus area equipment sump where j it will automatically be pumped to the Waste collector Tank located in the RadWaste Building Elevation 230'. The radiation levels in this general crea of the RadWaste Building will begin to increase.
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| 3 II. Descriotion of Player Resoonses/ Observations / Corrective Actions 3 Upon recognition of the seal failure alarm in the Centrol Room, operators will attempt to isolate the leak by shutting RHR suction valve. (Refer to Mini-scenario 7.2.5). Due to the high radiation levels in the corner j room no access will be attempted to locally tighten down on the seal.
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| Operators should be dispatched to the RadWaste Building to secure Reactor
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| , Building sump pumps to prevent any further transfer of highly radioactive I
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| water from torus area to the Waste Collector Tank in the RadWaste Building Elevation 230'.
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| CONTROLLER NOTES;
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| )
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| } 1. Upon entering rad waste control room, simulate that a Reacter
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| , Building south equipment drain sump pump is running continuously and
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| ! that one of the south flour drain sump pumps periodically runs.
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| : 2. If the operator checks the level of the Waste Collector Tank tell the j operator that the tank level went up (multiply 50 gym by # of minutes j it took to secure the pumps after the start of the leak at 1220) f III. Event closeout s This event will be closed out when the reactor building sump pumps have j been secured or Mini-scenario 7.2.5 is completed.
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| ] IV. Messaces l All information will be provided verbally by the controller. Responses 1 will be appropriate to the activities of the players.
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| R:v. O Page 7.2.5-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 m Mini-scenario - RER-13-D Overload Relav Trio I. General Descriotion At about 1220 (4:20 scenario time), control Room operators should recognize the 'D' RHR pump has a seal leak that they will attempt to isolate by closang the suction valve on the 'D' RHR pump. The Motor Control Center (MCC) controller for RER-13-D trips on thermal overload resulting in the valve not being closed. The overload relay can be reset which will allow the valve to be clo9ed. Due the seal leak and the location of the MCC, the area radiation levels will be elevated. It is expected that in order for plant personnel to reset the overload relay that a planned approach to gain access to the MCC will be developed.
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| II. Descriotion of Players Response / Observations / Corrective Actions The Control Room operators will attempt to close RHR-13-D and will recognize that there is no indication of valve position on panel 9-3.
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| They should assume the overload relay has tripped and will request assistance from the TSC and OSC. The TSC will instruct the OSC to investigate the problem and do what is necessary in order to get the valve shut. A team will be formed using all the necessary precautions and procedures in order to gain access to the MCC. It is expected that the team will be fully suited up with air packs. The team should enter the Reactor Building via the north access, go to the first floor and proceed to the south and of the building. Once they locate the MCC controller, they will observe that the overload relay is in the tripped position. It is expected that the overload relay will be reset allowing the valve to be stroked close.
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| CONTROLLER NOTES:
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| : 1. Radiation levels will be provided to the team as the team proceeds through the Reactor suilding. (Refer to section 9.3)
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| : 2. Resetting of the overload relay is orpected to occur at about 1320.
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| Bowever, resetting the overload relay prior to this time will have an effect on the exercise time line. 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.
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| : 3. Once the overload relay has been simulated to be reset, this information should be passed on to the osc Lead controller who will inform the simulator Lead Controller that the overload relay is reset. At this time, the Controller can inform the team that they can inform the control Room that the overload relay is reset. This is to facilitate the timing to reset the overload relay in the simulator control Room and allow the operators to isolate the RER 'D' ,
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| )
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| pump by closing the suction valve. 1 III. Event Closecut This event will be closed out when the overload relay has been reported reset and the team has returned to the checkpoint.
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| 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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| Rov. O Page 7.2.6-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 7.2.6 Mini-scenario - Chemistry sasoles of Plant Systems and In-olggi Radiolooical Surveys I. General Description 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 demonstrated.
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| II. Descriotion of Player Responses / Observations / Corrective Actions A. Chemistry Samoles 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 and then transferred to the TSC after activation. Depending on the plant radiological conditions at the time of the sample request, samples may be taken using established routine sampling procedures or post accident sampling techniques as specified in post accident sampling procedures (OP 3533, OP 3534, OP 3535 and OP 3536) . When samples of plant systems are requested, qualified personnel from Radiation Protection and Chemistry will be 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.
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| Once the TSC and OSC is activated and staffed, all sample requests should be coordinated through the OSC. The assigned sample team should consult with the Osc coordinatar or alternate for specific instructions and obtain a dose commitment limit f-- the sampling evolution to be conducted. After the teem is briefed, the sampling team should be able to locate the required equipment and then go or simulate going to the sample location. (For 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.
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| CONTROLLER NOTES:
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| : 1. All actions to obtain and analyse the sample should be simulated.
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| No manipulaf. ion of equipment or sampling system components should be done. 2de appropriate equipment and tools should be available, but not used. No actions should be taken that will affect the safety of personnel or ongoing operation of the plant.
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| : 2. Because of the time compression of the exercise and the need for plant system sample results to be used to demonstrate the ability ;
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| to assess the data in support of accident assessment activities, the time frame to obtain and analyse the actual sample will be simulated and compressed. The assumed sampling process time will be approximately 15 minutes per sample taken unless the actual sample time is shorter. Therefore, after the assumed sampling process time of 15 minutes and the sample team briefly discusses the sampling activities to obtain and analyse the sample, the controller should provide the appropriate information on sample dose rates and sample results to the sample team. The sampling team should then report and log saeple results in accordance with the sampling procedure requirements.
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| Rev. O P gs 7.2.6-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 B. In-Plant Radiolooical Surveys 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 actual demonstrate these activities to earn information about scenario-related area radiation and airborne activity levels. Controllers ,
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| 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 of the manual.) Players should be told that they should respond as if the scenario-related radiation and airborne levels are actually present based on the information that they received.
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| CONTROLLER NOTE:
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| All actions to conduct radiological surveys should R21 be simulated .
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| unless directed by the exercise coordinator or lead controller. The i appropriate equipment should be used to obtain the information.
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| However, no actions should be taken that will affect the safety of personnel or ongoing operation of the plant.
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| III. Event closeout This event will be closed out when the sampling teams report sample results of plant system samples requested or when radiological surveys '
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| are conducted and completed throughout the exercise scenario.
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| i IV. Messaces All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players.
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| _ - - - _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ i
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| VERMONT YANKEE NUCLEAR POWER ST ATION Rev. 0 EMERGENCY PREPAREDNESS EXERCISE Page 8 0-1 1997 8.0 OPERATIONAL DATA SCENARIO TIME 00.00 00:15 00:30 00 45 01:00 01:15 INSTR. CLOCKTIME 08:00 08:15 06:30 08'45 09.00 09.15 ITEM PANEL ID DESCRIPTION UNITS 1 43 FT-23-108-1 HPCI FLOW GPM 0 0 0 0 0 0 2 43 F1-10-139A RHR A FLOW GPM i i 1 1 1 1 3 9-3 Fb101398 RHR B FLOW GPM 1 1 1 1 1 1 4 43 F1-14 50A CS A FLOW GPM 0 0 0 0 0 0 5 93 Fh14-50B CS B FLOW GPM 0 0 0 0 0 0 43 PI-16-1412A DRYWELL PRESS PSIG 2.3 2.3 2.3 1.3 1.3 1.3 6
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| 7 43 Ph16-1912B DRYWELL PRESS PSIG 2.3 2.3 2.3 1.3 1.3 1.3 8 44 F1-13-91 RCIC FLOW GPM 0 0 0 0 0 0 9 44 Fl-12-141 A RWCU FLOW GPM 65 65 0 0 0 0 10 94 F1-12-1418 RWCU FLOW GPM 65 65 0 0 0 0 11 94 2165A RX COOLANT TEMP DEG F 526 526 512 513 516 516 l 12 9-4 2-165B RX COOLANT TEMP DEG F 526 526 514 512 513 515 13 44 2-150A RECIRC A LOOP FLOW KGPM 24.3 24.3 0 0 0 0 KGPM 24.3 24.3 20.3 19.8 19.8 19.8 14 44 2-1598 RECIRC B LOOP FLOW 15 9-5 7-46A APRM/lRM A % 100 100 60 53 46 45 j 16 95 7-468 APRM/lRM B % 100 100 00 54 4fr 45 j 17 95 7-46C APRM/lRM C % 100 100 60 54 46 46 18 9-5 7-46D APRM/lRM D % 100 100 80 53 46 45 7-46E APRM/lRM E % 100 100 60 53 46 46 19 9-5 20 45 7-46F APRM/iRM F % 100 100 80 54 47 48 21 95 7-43A SRM A CPS 5 40E+05 5.49E+05 3.51E+05 2.35E+05 1.77E+05 1.73E+05 22 9-5 7-43B SRM B CPS 5.73E+05 5.72E+05 3.08E+05 2.37E+05 1.82E+05 1.78E+05 23 9-5 7-43C SRM C CPS 5.70E+05 5.00E+o5 3.65E+05 2.37E+05 1.83E+05 1.79E+05 24 95 7-43D SRM D CPS 5 35E+05 5.34E+05 3 42E+05 2.28E+05 1.75E+05 1.71 E+05 9-5 2-3-95 CORE FLOW MLB/HR 47 47 22 22 22 22 25 PSID 17 17 4 4 4 4 26 9-5 2-3-95 CORE DP GPM 53 53 53 53.1 53 53.1 27 9-5 Fh3 310 CRD FLOW PSIG 1015 1015 973 987 981 981 28 9-5 6 96 WIDE RANGE PRESS PSIG 1013 1013 971 985 950 950 29 9-5 6-96 NAR RANGE PRESS 6-97 FEEDWATER FLOW MLB/HR 6.4 6.4 3.8 3.3 2.8 2.8 30 95 MAIN STEAM FLOW MLB/HR 6.4 64 3.8 3.4 2.9 2.8 31 9-5 6-97 NAR RANGE LEVEL INCHES 150 159 150 150 15d 150 l 32 9-5 6-98 6-98 WIDE RANGE LEVEL INCHES 200 200 200 200 200 200 33 9-5 9-6 LL107-5 CST LEVEL % 80 80 50 60 60 61 34
| |
| % 56 56 68 58 55 54 35 96 Lb102-5A HOTWELL LEVEL N LI 102-58 HOTWELL LEVEL $ % 54 54 54 56 54 54 36 46 1 IN HG 1.8 1.6 1.5 1.4 1.3 1.3 l 37 97 PI-101-29 CONDENSER VACUVM '
| |
| 98 D/G A BKR OPEN OPEN OPEN OPEN OPEN OPEN 38 39 9-8 D/G B BKR OPEN DPEN ,, OPEN OPEN OPEN OPEN )
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| DEG F 78 78 78 78 78 78 40 423 16-19-33A/C TORUS TEMP _
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| FEET 11.06 11.08 11.08 11.09 11.09 11.09 41 9 25 L1-48A TORUS LEVEL FEET 11.06 11.08 11.08 11.00 11.00 11.09 42 4 25 Ll-468 TORUS LEVEL TR-16-19-44 TORUS PRESS PSIG -0.1 -0.1 0 -0.2 -0.4 C.4 43 9 25 PSIG 2.3 2.3 2.3 1.3 1.3 1.3 44 9 25 TR-16-19-44 DRYWELL PRESS PSID 1.96 1.94 1.9 2.01 2 2 4 45 9 25 PR-1-156-3 DW/ TORUS DP DEG F 140 139 139 138 138 137 I 46 9-25 TR 16-19 45 DRYWELL TEMP IN H2O -1.52 -1.51 -0.00 -1.42 -1.44 1.9 47 9-26 PI-1-125-3A RX BUILDING OP IN H2O -1.52 -1.51 -0 09 -1 42 -1.44 1.9 48 9-26 PL1-125-38 RX BUILDING DP Fk1-125-1 A SGTS FLOW CFM 0 0 0 0 0 0 49 9-26 CFM 0 0 0 0 0 0 50 9-26 FL1-12518 SGTS FLOW
| |
| % 1.49 1.49 1.49 1.49 1.49 1.49 51 CAD DWITORUS O2 CONC.
| |
| Note: The ops data is dependent on operator actions taken in response to the conditions presented within the scenario. 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 i 1997 )
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| 60 OPERATIONAL DATA SCENARIO TIME 01:30 01:45 02:00 02:15 02:30 02:45 INSTR. CLOCK TIME 09:30 09 45 10:00 10:15 10:30 10 45 l ITEM PANEL ID DESCRIPTIO;4 UNITS 1 43 FT 231061 HPCI FLOW GPM 0 0 0 0 0 0 2 43 F1-10139A RHR A FLOW GPM 1 1 117 7005 8995 6961 , j 3 43 F1-10-139B RHR B FLOW GPM 1 1 1 6778 6767 6732 l 4 43 FL14 50A CS A FLOW GPM 0 0 1596 3368 3343 3326 i 5 43 FL14508 CS B FLOW GPM 0 0 0 0 0 0 6 43 PI-161912A DRYWELL PRESS PSIG 1.3 1.3 20.3 63 6.3 63 7 93 Pi-16-19-12B DRYWELL PRESS PSIG 1.3 1.3 20 3 6.3 6.3 6.3 8 94 F1-13-91 RCIC FLOW GPM 0 0 0 0 0 0 9 9-4 Fb12141 A RWCU FLOW GPM 0 0 0 0 0 0 10 44 F1-12-141B RWCU FLOW GPM 0 0 0 0 0 0 11 94 2-165A RX COOLANT TEMP DEG F 516 517 364 363 363 362 12 9-4 2-1658 RX COOLANT TEMP DEG F 515 516 382 381 380 380 13 94 2-159A REC 4RC A LOOP FLOW KGPM 0 C 0 0 0 0 14 9-4 2-159B RECIRC B LOOP FLOW KGPM 19 8 19 8 0 0 0 0 15 95 7-46A APRWLRM A % 44 44 0 0 0 0 16 95 7 46B APRM/IRM B % 44 43 0 0 0 0 17 SS 7-46C APRM/iRM C % 45 44 0 0 0 0 18 45 7 460 APRM/lRM D % 44 44 0 0 0 0 19 9-5 7 46E APRM/lRM E % 45 44 0 0 0 0 20 9-5 7-46F APRM/lRM F % 45 45 0 0 0 0 21 9-5 7-43A SRM A CPS 1.09E+05 1.65E+05 3 41E 01 1.90E-03 1.73E-03 1.59E-03 22 9-5 7 438 SRM B CPS 174E+06 1.70E+06 3 50E 01 1.90E 03 1.73E 03 1.59E-03 23 9-5 7-43C SRM C CPS 1.75E+06 1.71E+06 3.51 E-01 1.90E 03 1.73E-03 1.59E 03 24 45 7-43D SRMD CPS 1.67E+05 163E+05 3 32E 01 190E-03 1.73E 03 159E 03 25 45 2 3-95 CORE FLOW MLB/HR 22 22 7 13 13 13 26 95 2-3 95 CORE DP PSID 4 4 0 1 1 1 27 9-5 F b3-310 CRD FLOW GPM 53 53 125 125 125 125 28 45 5 96 WIDE RANGE PRESS PSIG 980 980 44 40 44 48 29 9-5 6-96 NAR RANGE PRESS PSIG 956 958 950 950 950 950 30 95 6 97 FEEDWATER FLOW MLB/HR 2.7 27 05 16 14 1.2 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 2.8 27 0 0 0 0 32 45 6 96 NAR RANGE LEVEL INCHES 150 159 187 187 187 187 33 9-5 6-96 WIDE RANGE LEVEL INCHES 200 200 200 200 200 200 34 9-6 Ll-107-5 CST LEVEL % 61 81 53 45 36 29 35 96 U-102-5A HOTWELL LEVEL N % 55 55 4 11 1 1 36 44 Ll-102-5B HOTWELL LEVEL S % 54 54 4 11 1 1 37 9-7 Pi-101-29 CONDENSER VACUUM IN HG 1.3 1.3 64 13 8 18 6 22.1 38 98 D/G A BKR OPEN OPEN OPEN OPEN OPEN OPEN 39 48 DIG B BKR OPEN OPEN ,OPEN OPEN OPEN OPEN 40 9-23 1&i9-33A/C TORUS TEMP DEG F 78 78 109 121 124 125 41 9-25 U-46A TORUS LEVEL FEET 11.00 11 06 11.50 11 85 12.34 12.81 42 9-25 Ll-468 TORUS LEVEL FEET 11 09 11 08 11 59 11 85 12.34 1281 l 36 43 9-25 TR 16-19-44 TORUS PRESS PSlG 05 0.5 38 5.1 64 44 9-25 TR-161444 DRYWELL PRESS PSIG 1.3 13 20 3 63 63 63 45 9 25 PR-1 156 3 DW/ TORUS DP PSID 2 1 96 126 2.33 0 92 -0.37 46 9-25 TR-151945 DRYWELL TEMP DEG F 137 137 255 230 232 231 47 4 26 P6-1-125-3A RX BUILDING DP IN H2O -2 -1 de -3 69 -5.77 7.04 -7 83 48 9-26 PL1-125-38 RX BUILDING DP IN H2O -2 1 40 -3 89 -5 77 -7 04 -7 83 j 49 9-26 Fb1-1251 A SGTS FLOW CFM 0 0 1500 1500 1500 1500 50 9 26 FL1-125-1B SGTS FLOW CFM 0 0 1500 1500 1500 1500 51 CAD DW/ TORUS O2 CONC. % 1.49 1.49 0.09 1.46 1 46 1 46 Note: The ops data is dependent on operator actions taken in response to the conditions presented within the scenario. Ops data reflects plant conditions assuming certain basic operator actions being taken. Ops data taken from simulator.
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| | |
| Rev.0 VERMONT YANKEE NUCLEAR POWER STATION Page 8.0-3 EMERGENCY PREPAREDNESS EXERCISE 1997 8.0 OPERATIONAL DATA 03:15 03:30 03 45 04:00 04:15 SCENARIO TIME 03 00 11:15 11:30 11:45 12.00 12:15 INSTR. CLOCK TIME 11:00 ITEM PANEL ID - DESCRIPTION UNITS GPM 0 0 0 0 0 0 1 9-3 FT-23-1061 HPCI FLOW 10331 10504 GPM 8993 11171 11312 11441 2 93 FL10-139A RHR A FLOW 6689 GPM 6764 10837 10872 6681 6651 3 9-3 F1-101398 RHR B FLOW 2961 2957 GPM 3330 3171 3152 3196 4 93 FI-14-50A CS A FLOW 0 0 0 3141 2961 2957 5 9-3 Fi-14-508 CS B FLOW GPM PSIG 6.3 7.3 7.3 7.3 7.2 7.2 6 43 PL161412A DRYWELL PRESS 7.2 7.2 PSIG 6.3 7.3 7.3 7.3 7 9-3 Pk16-1912B DRYWELL PRESS 0 GPM 0 0 0 0 0 8 94 FI-13-91 RCIC FLOW GPM 0 0 0 0 0 0 9 94 FL12-141 A RWCU FLOW 0 GPM 0 0 0 0 0 10 94 F1-12-141B RWCU FLOW 378 381 381 380 379 379 11 9-4 2-105A RX COOLANT TEMP DEG F 379 378 378 377 377 376 12 94 2-1858 RX COOLANT TEMP DEG F 0 0 0 0 0 0 13 9-4 2-150A REclRC A LOOP FLOW KGPM KGPM 0 0 0 0 0 0 14 44 2-1598 RECIRC B LOOP FLOW
| |
| % 0 0 0 0 0 0 15 9-5 746A APRM/iRM A
| |
| % 0 0 0 0 0 0 16 45 7-468 APRMllRM B 0 0
| |
| % 0 0 0 0 17 9-5 7-46C APRMllRM C
| |
| % 0 0 0 0 0 0 18 45 7-46D APRM/1RM D
| |
| % 0 0 0 0 0 0 19 9-5 7-46E APRMllRM E
| |
| % 0 0 0 0 0 0 20 45 7 46F APRM/lRM F 21 95 7-43A SRM A CPS 1.50E-03 1.43E-03 1.37E-03 1.33E-03 1.33E43 '1.33E 03 22 9-5 7-43B SRMB CPS 1.50E43 1.43E-03 1.37E 03 1.33E43 1.33E-03 1.33E-03 23 9-5 7-43C SRM C CPS 1.50E-03 1.42E-03 1.37E 03 1.33E 03 1.33E-03 1.33E-03 24 9-5 7-43D SRM D CPS 1.50E-03 1.43E 03 1.37E 03 1.33E-03 1.33E-03 1.33E 03 13 20 19 14 14 14 25 9-5 2-3-95 CORE FLOW MLB/HR 3 3 2 2 2 26 9-5 2-3-95 CORE DP PSID 1 125 125 125 125 125 125 27 95 F L3-310 CRD FLOW GPM 47 70 73 68 68 88 28 95 6-96 WIDE RANGE PRESS PSIG 950 950 950 950 950 950 29 9-5 6-96 NAR RANGE PRESS PSIG 1.1 0 0 0 0 0 30 9-5 6-97 FEEDWATER FLOW MLB/HR 0 0 0 0 0 0 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 187 187 187 187 187 187 32 9-5 6-98 NAR RANGE LEVEL INCHES 200 200 200 200 200 200 33 9-5 6-98 WIDE RANGE LEVEL INCHES 22 18 18 18 18 18 96 LL107 5 CST LEVEL %
| |
| 34 0 0 0
| |
| % 1 0 0
| |
| ~ 35 94 Ll-102-5A HOTWELL LEVEL N 0 0 0 0
| |
| % 0 0 38 96 LI-102-5B HOTWELL LEVEL S 282 28.5 IN HG 24.5 26.2 27.3 28.1 37 9-7 PL10129 CONDENSER VACUUM OPEN OPEN OPF.N OPEN OPEN OPEN 38 9-8 D/G A BKR 30 94 D/G B BKR OPEN CLOSED . CLOSED CLOSED CLOSED CLOSED 127 128 130 130 129 129 40 9 23 16-1433A/C TORUS TEMP DEG F 13.28 13.58 13.88 13.76 13.79 13.82 41 9 25 Li46A TORUS LEVEL FEET 13.28 13.58 13.68 13 76 13.79 1382 42 9-25 LL46B TORUS LEVEL FEET 7.5 7.7 8.1 8 7.9 9 25 TR 16-19-44 TORUS PRESS PSIG 7.1 43 7.3 7.2 7.2 PSIG 6.3 7.3 7.3 44 9-25 TR 16-19-44 DRYWELL PRESS -0.33 0.33 0.33 PSID 0.4 0.31 0.32 45 9-25 PR 11563 DW/ TORUS DP 230 183 183 DEGF 231 231 231 46 9-25 TR-16-19-46 DRYWELL TEMP 12.51 12.51 IN H2O 6.34 -6.9 -12.22 -12.51 47 9-26 Pkt 125-3A RX BUILDING DP 12.51 -12.51 IN H2O -8.34 -89 -12.22 12.51 48 9-26 PI-1-125 3B RX BUILDING DP 975 975 CFM 1500 1500 1102 975 49 9-26 Fht 1251A SGTS FLOW 975 975 975 CFM 1500 1500 1102 50 9-26 FL1-1251B SGTS FLOW 1.49 1.49
| |
| % 1.47 1.48 1.48 1.49 51 CAD DW/ TORUS O2 CONC.
| |
| Note: The ops data is dependent on operator actions taken in response to the conditions presented within the scenario. Ops data reflects plant conditions assuming certain basic operator actions being taken. Ops data taken from simWtor.
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| __-__ _ _ - _ . . _m = _ _ . _ _ _ _ ~ _ _ _ _ _ _ - _ _ . ~ _ _ _ _ _ _ _ _ _ _ _
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| 3 l I
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| 1 5
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| 1 5
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| VERMONT YANKEE NUCLEAR POWER STATION Rev. O
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| < EMERGENCY PREPAREDNESS EXERCISE Page 8.0-4 i 1997 i
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| 8.0 OPERATIONAL DATA SCENARIO TIME 04 30 04 45 05'00 05:15 05-30 06 4 l INSTR. CLOCKTIME 12:30 12 4 13:00 13:15 13:30 13 46 i ITEM PANEL ID DESCRIPTION UNITS j
| |
| 1 9-3 FT-23-108-1 HPCI FLOW GPM 0 0 0 0 0 0 2 43 F1-10139A RHR A FLOW GPM 10504 10546 9646 9646 9646 9646 3 . 9-3 F6101398 RHR B FLOW GPM 8633 6545 6545 6645 6672 6663 4 43 F1-14-50A CS A FLOW GPM GPM 2923 2923 2876 2876 2976 2976 2876 2876 2676 2676 2676 2676 .
| |
| l
| |
| - 5 93 F6-14 500 CS B FLOW I
| |
| ! 6 93 Pl-16-1412A DRYWELL PRESS PSIG 7.1 7.1 7 7 6.9 69
| |
| . 7 93 Pi-16-19-12B DRYWELL PRESS PS6G 7.1 7.1 7 7 6.9 6.9 j 8 44 FI-13-91 RCIC FLOW GPM 0 0 0 0 0 0 j 9 9-4 F6-12-141 A RWCU FLOW GPM 0 0 0 0 0 0 10 N Fl.12-1418 RWCU FLOW GPM 0 0 0 0 0 0 y
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| j 11 9-4 2-165A RX COOLANT TEMP DEG F 378 377 377 376 375 355 12 44 2 1668 RX COOLANT TEMP DEG F 376 375 375 374 373 373 j
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| 1 13 94 2-150A 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 9-5 7-46A APRM/lRM A % 0 0 0 0 0 0 l
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| 16 9-5 7-488 APRM/lRM B % 0 0 0 0 0 0 1 17 9-5 7-46C .APRM/lRM C % 0 0 0 0 0 0 .
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| 18 95 7-480 APRM/lRM D % 0 0 0 0 0 0 1
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| 19 95 746E APRM/lRM E % 0 0 0 0 0 0 1 20 45 7-46F APRM/lRM F % 0 0 0 0 0 0 4 21 95 7-43A SRM A CPS 1.32E 03 1.32E 03 1.31E 03 1.31E 03 1.30E 03 1.30E-03 l 22 9-5 7-438 SRM B CPS 132E 03 1.32E43 1.31E 03 131E 03 130E 03 1.30E 03
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| ; 23 9-5 7-43C SRM C CPS 1.32E 03 1.32E-03 1.31E 03 1.31E 03 1.30E 03 1.3A 03
| |
| $ 24 9-5 7-430 SRM D CPS 132E 03 1.32E 03 1.31E 03 1.31E 03 1.30E 03 1.30E-03 25 9-5 2-3-95 CORE FLOW MLB/HR 14 14 14 14 14 14 26 45 2-3 96 CORE DP PSID 2 2 2 2 2 2 l GPM 125 125 .125 125 27 9-5 Fi-3 310 CRD FLOW 125 125 I 26 95 6-96 WIDE RANGE PRESS PSIG 68 88 88 68 68 68 J 29 95 6-96 NAR RANGE PRESS PSIG 950 950 950 950 950 950 3 30 96 6-97 FEEDWATER FLOW MLB/HR 0 0 0 0 0 0 31 9-5 6 97 MAIN STEAM FLOW MLB/HR 0 0 0 0 0 0 l 32 45 6-98 NAR RANGE LEVEL INCHES 187 187 187 187 187 187 3 33 9-5 6-96 WIDE RANGE LEVEL INCHES 200 200 200 200 200 200 34 M Ll-107-5 CST LEVEL % 18 18 18 18 18 18 l 4 35 M Li-102-5A HOTWELL LEVEL N % 0 0 0 0 0 0 38 M Ll-102-58 HOTWELL LEVEL S % 0 0 0 0 0 0 37 97 Pk10129 CONDENSER VACUUM IN HG 28 5 26.7 26 9 29 2 29.5 29 5 38 M D/G A BKR OPEN OPEN OPEN OPEN OPEN OPEN ,
| |
| 30 M D/G B BKR CLOSED CLOSED . GLOSED CLOSED CLOSED CLOSED 40 9 23 18-19-33A/C TORUS TEMP DEG F 126 126 127 127 127 126 41 9-25 L6-46A TORUS LEVEL FEET 13 85 13 88 13 89 13 93 13 97 14 2 ;
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| 42 9 25 Ll-488 TORUS LEVEL FEET 13 86 13 88 13 89 13 93 13 97 142
| |
| ] 7.7 7.6 7.5
| |
| ] 43 9-25 TR 1619 44 TORUS PRESS PSIG 7.9 7.5 7.7 j 44 9 25 TR-16-1444 DRYWELL PRESS PSIG 71 7.1 7 7 69 6.9 4 45 9-25 PR-1156-3 DW/ TORUS DP PSID 0.33 0 33 0.33 0.33 -0.33 -0 33 l 48 9-25 TR 16-1446 DRYWELL TEMP DEG F 183 183 183 183 183 183 47 9-26 PI-1 125 3A RX BUILDING DP IN H2O 12 47 12.47 12.51 12.51 -12.51 12.51
| |
| $ 48 9 26 PI-1 125-38 RX BUILDING DP IN H2O -12 47 -12 47 -12 51 12 51 12.51 12 51 49 9-26 Fh1-1251 A SGTS FLOW CFM 975 975 975 975 975 975 i
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| 50 9-26 Fi-1125-1B SGTS FLOW CFM 975 975 975 975 975 975 l
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| 4 51 CAD DW/ TORUS O2 CONC. % 1 49 1 49 1.49 1 49 1.49 1 49
| |
| )
| |
| i i Note: The ops data is dependent on operator actions taken in response to the conditions presented 1 within the scenario. Ops data reflects plant conditions assuming certain basic operator actions being
| |
| , taken. Ops data taken from simulator.
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| 1 3
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| a
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| - . - .- . . -- ~_ ._ .--
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| l Rev. 0 Page 8.0-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 6.0 OPERATIONAL DATA SCENARIO TIME 06:00 06:15 INSTR. CLOCK TIME 14.00 14:15 ITEM PANEL ID DESCRIPTION UNITS 1 43 FT-23-1061 HPCI FLOW GPM 0 0 2 93 FL10-139A RHR A FLOW GPM 9545 9545 3 9-3 FL10139B RHR 8 FLOW GPM 6681 6681 4 43 FL14-50A CS A FLOW GPM 2786 2786 ,
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| 5 9-3 FL14-50B CS B FLOW GPL1 2786 2786 6 43 PI-16-19-12A DRYWELL PRESS PSIG 6.9 6.8 7 9-3 PI-1619-128 DRYWELL PRESS PSIG 6.9 6.8 8 M FL13-91 RCIC FLOW GPM 0 0 9 M Fi-12141 A RWCU FLOW GPM 0 0 10 M FL12-141 B RWCU FLOW GPM 0 0 11 M 2-165A RX COOLANT TEMP DEG F 374 373 12 94 2-1958 RX COOLANT TEMP DEG F 372 371 13 M 2-159A RECIRC A LOOP FLOW KGPM 0 0 l t
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| 14 M 2-1598 RECIRC B LOOP FLOW KGPM 0 0 15 9-5 7-46A APRM/lRM A % 0 0 16 9-5 7-468 APRM/lRM B % 0 0 i 17 9-5 7-46C APRM/tRM C % 0 0 18 9-5 7-460 APRM/1RM D % 0 0 19 9-5 7-46E APRM/lRM E % 0 0 i 20 9-5 7-46F APRM/1RM F % 0 0 21 95 7-43A SRM A CPS 1.30E-03 1.30E 03 )
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| 1 22 9-5 7-43B SRM B CPS 1.30E43 1.30E 03 1.30E 03 1.30E 03 l 23 95 7-43C SRM C CPS 1
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| 24 95 7-43D SRM D CPS 1.30E-03 1.30E 03 25 95 2-3-95 CORE FLOW MLB/HR 14 14 26 95 2-3 95 COREDP PSID 2 2 27 95 FL3-310 CRD FLOW GPM 125 125 28 9-5 6-96 WIDE RANGE PRESS PSIG 88 68 29 95 6-96 NAR RANGE PRESS PSIG 950 950 30 9-5 6-97 FEEDWATER FLOW MLB/HR 0 0 31 95 6 97 MAIN STEAM FLOW MLB/HR 0 0 32 9-5 6-96 NAR RANGE LEVEL INCHES 187 187 33 9-5 6-96 WIDE RANGE LEVEL INCHES 200 200 34 M LL107 5 CST LEVEL % 18 18 35 M LL102-5A HOTWELL LEVEL N % 0 0 36 M LL102-58 HOTWELL LEVEL S % 0 0 37 97 PL101-29 CONDENSER VACUUM IN HG 29.8 29.8 '
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| 36 98 D/G A BKR OPEN OPEN l l
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| 30 M D/G B BKR CLOSED CLOSED
| |
| )
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| 40 9-23 16-19-33A/C TORUS TEMP DEG F 126 126 I
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| LM6A TORUS LEVEL FEET 14.3 14.3 41 9 25 9-25 LL468 TORUS LEVEL FEET 14.3 14.3 42 43 9-25 TR-16-1M4 TORUS PRESS PSIG 7.5 7.5 44 9-25 TR-16-19 44 DRYWELL PRESS PSIG 6.9 6.9 45 9-25 PR 1156 3 DW/ TORUS DP PSID -0.33 0.33 46 9-25 TR-16-14 45 DRYWELL TEMP DEG F 230 230 IN H2O -12.51 12.51 l 47 9-26 PL1-125-3A RX BUILDING OP PL1 125-3B RX BUILDING DP IN H2O 12.51 12.51 46 9-26 '
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| CFM 975 975
| |
| , 49 9 26 FL1 125-1 A SGTS FLOW i 9-26 FL1125-1B SGTS FLOW CFM 975 975
| |
| ! 50 CAD DW/ TORUS O2 CONC. % 1.49 1.49 51 Note: The ops data is dependent on operator actions taken in response to the conditions presented l
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| ! i within the scenario. 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. O EMERGENCY PREPAREDNESS EXERCISE Page 9.1 1 j 1997 9.1 AREA RADIATION MONITORS
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| ~~ ..W- me,s u , < . - -o n~ ~ --- -
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| _ SCENARIO. TIME
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| - ~ - -
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| -r . - - - - ~ ~~~~~, - --.-~,- - +~
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| . A iitosodi
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| -a m , _0215 1,r-030,,;,A, M45_0000~-- ;,,wse 01:151(R_0030M ta.::e.Elh..;ad.4..,
| |
| ,% . . c.... n . .;;-m r. . % .
| |
| ~ .
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| n ,. ..
| |
| . .r.. - . .
| |
| ~ %c_0 s. .- ~
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| . ~ + --%
| |
| - s.c. -
| |
| CLOCKTIME a 0820 w : 08:15- 08 30 - 08:47 e11990 2-- 09'16 e 09'30
| |
| * 36 L . Mi.,.
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| i, F . *
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| . i. X A
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| 'ARMNoJCPANEO BLDGELV DESCR1PTION '
| |
| Ce UNITS? 'X"J;i.dCA-Qf WJI .f V ; C C D#
| |
| . a.. ~ a -:: :Cn*:
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| E'"^^'"'
| |
| RMS 141 9-11 RS/252 RX BLDG HI RADS - N R/hr <1 <1 <1 <1 41 <1 <1 RMS 11-2 9 11 RB/252 RX BLDG HI RADS S R/hr <1 <1 <1 si ci <1 <1 RMS 11-3 9 11 RB/252 TIP RM HI RAD R/hr <1 <1 <1 <1 <1 <1 <1 1 9-11 RB/232 SUPP CHAMB RB EXT CW mR/hr 8 8 7 7 7 7 7 2 9-11 RB/252 N PERSONNEL RX BLDG mR/hr 4 4 2 2 2 2 2 ,
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| i 3 9 11 RB/252 S EQUIP RR RX BLDG mR/hr 0.3 0.3 0.25 0.25 0.25 0.25 0.25 l 4 9-11 RB/252 RX BLD NEUTRON TIP mR/hr 5 5 5 5 5 5 5 5 9 11 RB/252 PERSONNEL HATCH RX B mR/hr 520 518 310 280 240 238 235 6 9 11 RB/280 ELEV ENTR 280FT RX mR/hr 8 8 6 6 6 7 6 !
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| 7 9 11 RB/252 CRD REPAIR RX BLDG mR/hr 10 10 8 7 7 7 8 9-11 RS/303 ELEV ENTR 303FT RX mR/hr 4 4 3 3 2 2 2 9 9 11 RB/103 H2O CLEANUP RX BLDG mR/hr 5 5 4 4 4 4 4 !
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| 10 9-11 RB/318 ELEV ENTR 318FT RX mR/hr 7 7 5 5 5 5 5 11 9-11 RB/318 H2O CLEANUP RX BLDG mR/hr 4 4 3 3 3 3 3 12 9 11 RB/345 ELEV ENTR 348FT RX mR/hr 4 4 3 3 2.5 2.5 2.5 14 9-11 RB/345 WEST REFUEL RX BLOG mR/hr 5 5 3 3 3 3 3 1 1
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| 15 9 11 RBf345 SPENT FUEL POOL RX mR/hr 15 15 12 12 11.5 11.5 11.5 l 1
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| 18 9 11 RB/318 NEW FUEL VAULT RX B mR/hr 0.5 0.5 04 0.4 04 0.4 04 '
| |
| 17 9-11 RWr252 PUMP RM RADWASTE BL mR/hr 1 1 1 1 1 1 1 l 18 9 11 RW/252 RADW OPER AREA RW B mR/hr 1 1 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 1.5 20 9-11 TB/248 N ACCESS 248FT TURB mR/hr 2.5 2.5 2 2 2 2 2 29 9-11 TB/248 MAIN STM VALVE TURB mR/hr 240 240 140 115 95 92 90 22 9-11 TB/232 COND DEMIN TURB BLD mR/hr 0.5 0.5 04 0.4 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 0.15 0.15 0.15 24 9 11 TB/272 TURB STM IN TURB BL mR/hr 8 8 7 7 7 7 7 25 9-11 ABr272 VIEW GALLERY CONT RM mR/hr 0.9 0.9 0.6 0.5 0.5 0.5 0.5 26 9-11 TB/252 REAR GATE TURB WAREH mR/hr 0.2 0.2 01 0.1 0.1 0.1 01 13 9 11 TBr228 MOIST FEP AREA TURB mR/hr 135 135 77 63 52 50 50
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| .. . ._ . _ _ _ _ _ _ = _ . _ _ . _
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| l Rev.O VERMONT YANKEE NUCLEAR POWER STATION Page 9.1-2 EMERGENCY PREPAREDNESS EXERCISE 1997 9.1 AREA RADIATION MONITORS p .;u %- -e+. - % --
| |
| g r g-my yg,ww w,y g: ..,,,.
| |
| _ g' 4'1120 gy" .11:15 ,, ~"
| |
| 7
| |
| .. g j ~w1015
| |
| . - p* 'te3D
| |
| % - gP +.1te'
| |
| .c, . - _ , , 4 . .
| |
| j
| |
| .mgtg.
| |
| w ,eo
| |
| ; . e CLOCKTIME N OR4-.9~ ^ 10-00
| |
| ,.,rywam.a ng. .n + -
| |
| a . n ,m a
| |
| ', usenu ' <i
| |
| :; PANEL
| |
| _s... DESCRIPTION ,
| |
| , -ym ~;xw mg.ggg .. wn, ' garmyyng.
| |
| y g+ "3 g- -gp; yg_gy.ym
| |
| - - - Fgg. m , y UNITS 2 ~
| |
| t C BLDGELV .- -
| |
| ' ARM
| |
| <1 <1 <1 <1 <1 <1 RMS 11-1 9-11 RB/252 RX BLOG HI RADS - N RMr <1 ci <1 ci ci <1 <1 RMS !!-2 9-11 RB/252 RX BLDG HI RADS S R/hr <1
| |
| <1 <1 <1 <1 <1 <1 <1 RMS 11-3 9-11 RB/252 TIP RM HI RAD RMr l 250 750 800 850 900 1200
| |
| ! 1 9 11 RB/232 SUPP CHAMB RB EXT CW mR/hr 7 2 05 0.5 04 04 0.4 0.3 3 9 11 RB/252 N PERSONNEL RX BLDG mRMr S EQUlP RR RX BLDG mRMr 0.25 04 04 04 04 03 0.3 3 9-11 RB/252 5
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| mRMr 5 5 5 5 5 5 l 4 9-11 RB/252 RX BLD NEUTRON TIP mRMr 230 5000 OSH>1E4 OSH OSH OSH OSH 5 9 11 RB/252 PERSONNEL HATCH RX B mRMr 6 5 5 5 5 5 5 6 9 11 RB/200 ELEV ENTR 200FT RX B mRMr 7 4 4 4 4 4 4 7 9 11 RB/252 CRD REPAIR RX BLDG 1 1 1 8 S11 RB/303 ELEV ENTR 303FT RX B mRMr 2 1 1 1 mRMr 4 4 4 4 4 4 4 9 9 11 RB/303 H2O CLEANUP RX BLDG mRMr 5 3 3 3 3 3 3 10 9 11 RB/318 ELEV ENTR 318FT RX B mR/hr 3 2' 2 2 2 2 2 11 9-11 RB/318 H2O CLEANUP RX BLOG 1 1 1 13 9-11 RB/345 ELEV ENTR 348FT RX B rnRMr 2.5 1 1 1 1 1 1 ;
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| l 14 411 RB/345 WEST REFUEL RX BLOG mRMr 3 1 1 1 mRMr 11.5 8 8 8 8 8 8 15 9 11 RB/345 SPENT FUEL POOL RX B mRMr 04 03 0.3 03 03 0.3 03 16 411 RB/318 NEW FUEL VAULT RX B mRMr 1 1 1 1, i 1 17 9-11 RW/252 PUMP RM RADWASTE BLD 1 1 1 1 1 18 9-11 RW/252 RADW OPER AREA RW B mRMr i 1 1 mRMr 1.5 1.5 1.5 1.5 1.5 1.5 1.5 l 19 9 11 RW/230 PUMP / TANK AREA RW B 2 1.5 15 15 1.5 1.5 1.5 20 9-11 TB/248 N ACCESS 248FT TURB mR/hr l
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| mRMr 87 16 9 6 5 5 5 l
| |
| 37 9 11 TB/248 MAIN STM VALVE TURB l
| |
| mR/hr 03 01 01 01 01 01 0.1 22 9-11 TB/232 COND DEMIN TURB 3LDG mRMr 015 0.15 0 15 015 015 0.15 0.15 33 9 11 TB/252 DECONTAM TURB BLDG mR/hr 7 7 '7 7 7 7 7 24 9 11 TB/272 TURB STM IN TURB BLD mRMr 04 0.1 0.1 0.1 0.1 0.1 01 25 9 11 AB/272 VIEW GALLERY CONT RM 0 01 0 01 mR/hr 01 0 01 0 01 0 01 0 01 26 9 11 TB/252 REAR GATE TURB WAREH 1 1 1 13 9-11 TB/228 MOIST SEP AREA TURB mR!hr 48 1 1 1 J
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| a 1
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| e
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| . _ . - _ _ _ _ _ __ . . _ . . _ , ._. . . _ . . _ _ . ___..m _. _ _ . _ _ . . _ _ . _ _ _ . .
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| VERMONT YANKEE NUCLEAR POWER STATION Rev. 0 EMERGENCY PREPAREDNESS EXERCISE Page 9.1-3 1997 9.1 AREA RADIATION MONITORS EY ' ;d.222I $..f siEWO.TRECOBW70E47 249t00 4 Ot15 T T 3 30h0tef5h7 B h q q:,9 s: g ~~*." x" =~~~~**fg g y y Q W 4([ W.?gg W4Q QT Q"iV Q .24? g ?
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| 'y%%n.
| |
| ARM -PANEL $WM56%FMTi%
| |
| ' NV DESCRFTK)N MbWlGff?;WIkiQf%%$QQQQW&"''
| |
| " i ~ USNTS - .-s- - -- - * ' - - - " "- ~- Q"Q-}Q'RQ' RMr <1 *1 <1 <1 <1 <1 <1 RMS Il-1 9-11 RB/252 RX BLDG HI RADS N RX BLOG HI RADS .S RMr <1 <1 <1 <1 <1 <1 1.5
| |
| - RMS Il-2 9 11 RS/252 '
| |
| RMr <1 <1 <1 <1 <1 <1 <1 RMS 18-3 9 11 RS/252 TIP RM HI RAD 9 11 SUPP CHAMS RB EXT CW mRMr 2000 2000 2000 2000 2000 2000 2000 1 RS/232 mRMr 0.3 0.3 0.3 0.3 170 300 850 3 9-11 RB/252 N PERSONNEL RX BLDG 3 9 11 RB/252 S EQUIP RR RX BLDG mRMr 0.3 0.3 0.3 0.3 880 OSHz1E3 OSH 9 11 RX BLD NEUTRON TIP mRMr 5 5 5 5 100 - 180 300 O RB/252 5 9 11 RB/252 PERSONNEL HATCH RX B mRMr OSHm1E4 OSH OSH OSH OSH OSH OSH 8 9 11 RS/200 ELEV ENTR 200FT RX B mRMr 5 5 5 5 50 125 200 7 9 11 R8/252 CRD REPAIR RX BLDG mRMr 4 4 4 4 4 4 4 8 9 11 RB/303 ELEV ENTR 303FT RX 8 mRMr 1 1 1 1 50 125 200 9 9 11 RS/303 H2O CLEANUP RX BLDG mRMr 4 4 4 4 120 300 ' 480 10 9 11 RB/318 ELEV ENTR 318FT RX B mRMr 3 3 3 3 10 20 40 11 9 11 RS/318 H2O CLEANUP RX BLDG mRMr 2 2 2 2 20 40 80 .
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| 12 9 11 RB/345 ELEV ENTR 348FT RX B mRMr 1 1 1 1 10 20 40 14 9-11 RB/345 WEST REFUEL RX BLDG mRMr 1 1 1 1 10 20 40 RB/345 SPENT FUEL POOL RX B mRMr 8 8 8 8 15 25 50 15 9-11 9 11 R8/318 NEW FUEL VAULT RX 8 mRMr 0.3 0.3 0.3 0.3 10 20 40 18 1 1 17 9 11 RW/252 PUMP RM RADWASTE BLD mRMr 1 1 1 1 1 1 1 18 9 11 RW/252 RADW OPER AREA RW B mRMr 1 1 1 1 1 mRMr 1.5 1.5 1.5 1.5 70 100 150 19 9 11 RW/230 PUMP / TANK AREA RW B ,
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| 1.5 1 20 9 11 TB/248 N ACCESS 240FTTURS mRMr 1.5 1 1 1 1 MAIN STM VALVE TURB mRMr 4 4 4 4 4 4 4 31 9 11 TB/248 COND DEMtN TURB BLDG mRMr 0.12 0.12 0.1 0.1 0.1 0.1 0.1 22 9-11 TB/232 9 11 T8/252 DECONTAM TURB BLDG mRMr 0.15 0.15 0.15 0.15 0.15 0.15 0.15 33 TURB STM IN TURB BLD mRMr 7 7 .*7 7 7 7 7
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| , 24 9 11 TB/272 mRMr 0.1 0.1 0.1 0.1 0.1 0.1 0.1 25 9-11 AS/272 VIEV' GALLERY CONT RM RIA8t GATE TURS WAREM mRMr 0.01 0.01 0.01 0.01 0.01 0.01 0.01 j 28 9 11 T8/252 mRMr 1 1 1 1 1 l 13 9 11 TB/228 MOIST SEP AREA TURB 1 1 OSH = Off-ecele High 4
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| 1 VERMONT YANKEE NUCLEAR POWER STATION Rev. O EMERGENCY PREPAREDNESS EXERCISE Page 9.1-4 1997 l i
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| 9.1 AREA RADIATION MONITORS
| |
| : y. m,_m,g_*
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| 3_m_- !
| |
| em.- m etzp m m wra %,c,~.- - g r'1*15t.m__,
| |
| 2 CLOCK TIME
| |
| _ - '-1130m. #p'
| |
| _. s- ' 14 .~
| |
| -1345 - 00 F1415 x*- - >
| |
| -m#u. - ,c. m w " m "~-u a h5hhkY?.? fha %8&'?i.?lTHE&,$&Sh555
| |
| * f"fhi'&' < ~ "$5kf}}&&+l*l t@fR'- ' k,,j;Qffggfl
| |
| - UNfTS ~ ' >- " -- - -- - '- - - -
| |
| i ARM No. - PANEL
| |
| * BLDG /ELV DESCRPTION .
| |
| RMS 11-1 9-11 RS/252 RX BLDG HI RADS . N Rh <1 <1 <1 <1 <1 RMS Il-2 9 11 RBr252 RX BLDG HI RADS . S Rh 2 1 <1 <1 <1 RMS Il-3 9 11 RB/252 TIP RM HI RAD Rh si <1 <1 <1 <1 1 9 11 RB/232 SUPP CHAMB RB EXT CW mRh 2000 2000 2000 2000 2000 2 9-11 RB/252 N PERSONNEL RX BLDG mRh 850 800 530 500 400 3 9 11 R8/252 S EQUIP RR RX BLOG mRh OSH>1E3 OSH OSH OSH OSH O 9-11 RO/252 RX BLD NEUTRON TIP mRN 500 350 300 290 240 ,
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| 5 9 11 RB/252 PERSONNEL HATCH RX B mRN OSH>iE4 OSH OSH OSH OSH 6 9 11 RB/200 ELEV ENTR 200FT RX B mRh 400 280 250 230 200 l 7 9-11 RB/252 CRD REPAIR RX BLDG mRh 4 4 4 4 4 8 9 11 RB/303 ELEV ENTR 303FT RX B mRh 400 280 250 230 200 9 9-11 RB/303 H2O CLEANUP RX BLDG mRh 980 670 800 580 450 10 9-11 RB/318 ELEV ENTR 318FT RX B mRh 80 75 70 80 50 11 9-11 RB/318 H2O CLEANUP RX BLDG mRW 200 150 140 120 50 12 9-11 RB/345 ELEV ENTR 348FT RX B mRN 80 75 70 80 50 14 9-11 RB/345 WEST REFUEL RX BLOG mRN 80 75 70 60 50 15 9-11 RB/345 SPENT FUEL POOL RX B mRN 120 100 80 70 80 16 9 11 RB/318 NEW FUEL VAULT RX B mRh 80 75 70 80 50 17 9-11 RW/252 PUMP RM RADWASTE BLD mRW 1 1 1 1 1 18 9-11 RWr252 RADW OPER AREA RW B mRN 1 1 1 1 1 19 9-11 RW/230 PUMP / TANK AREA RW B mRh 150 150 150 150 150 20 9-11 TB/248 N ACCESS 248FT TURB mRh 1 1 1 1 1 9-11 TB/246 MAIN STM VALVE TURB mRh 4 4 4 4 4 31 22 9 11 TB/232 COND DEMIN TURB BLDG mRh 01 01 0.1 01 01 23 9 11 TB/252 DECONTAM TURB BLOG mRM 0.15 0.15 0.15 0.15 0.15 9 11 TB/272 TURB STM IN TURB BLD mRh 7 7 7 7 7 24 9 11 AB/272 VIEW GALLERY CONT RM mRN 0.1 0.1 0.1 0.1 0.1 25 9-11 TB/252 REAR GATE TURB WAREH mRN 0 01 0 01 0 01 0 01 0 01 26 13 9-11 TB/228 MOtST SEP AREA TURB mRh 1 1 1 1 1 l
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| OSH = Off-scale Hugh i
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| e I
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| .-.,. - - ~. . ~ - - - - - . - . . - ~ _ . . - _ - . - - . _ . - . - - ~ . . - . - _ ~ . - - - - - . ,
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| J VERMONT YANKEE NUCLEAR POWER STATION Rev. 0 j
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| Page 9.21 EMERGENCY PREPAREDNESS EXERCISE
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| ; 1997 1
| |
| 1* i 9.2 PROCESS MONITORS 1
| |
| kMN5M#
| |
| .~e i
| |
| me*+49mn:wra**t e -,c , t"a"
| |
| '" - ~ - - - -
| |
| "ver w -w^ SCE -.~ . m; M t5 0030. , ..?%
| |
| mm.tS*N. m,.55,F-
| |
| ; ,CRM yVy" =c4 m;p y~aer-mgwyy.NARIO CLOCKTIME*n* F cest TRE*7,=f7m p+-'0815'g" p % w- -.' 3...i.O. 1R3bgp.,M3'E~M.
| |
| W~00 U 0815*'*CR00+wtRt5 P- (R30' . ,,g~,%
| |
| DESCRIPTION : " UNIT 8 ?- M '4s 5.hC-%"E-h! TNA J & 3.y.r ;.-j ::x r.n e me _ l
| |
| #NO ' PAGEL BLDGELV . .
| |
| cpm 150 150 150 150 150 150 150 9-2 ST/257 STACK GAS MON-GAS 1 cpm 200 200 200 200 200 200 200 92 ST/257 STACK GAS MON-GAS 2 ST/257 STACK HI RANGE mR/hr 0.1 0.1 0.1 0.1 01 0.1 0.1 9-2 589 558 383 338 289 268 250 9-2 RBr200 CONTAINMENT MON GAS com cpm 6227 6222 5697 5623 5519 5506 5493 92 RB/200 CONTAINMENT MON-PART 27 9-2 DW/252 DRYWELL CH A R/hr 32 31 1.3 1.1 1 1 1 26 9-2 DW/252 DRYWELL CH B R/hr 3.2 31 1.3 1.1 1 1 1 150 150 150 150 150 150 150 9-2 RBr280 RX BLDG VENT GAS com cpm 1500 1500 1500 1500 1500 1500 1500 9-2 RB/200 RX BLDG VENT PART 31 9-10 RB/200 RX BLDG VENT NORTH mR/hr 2 2 1 1 09 09 09 9-10 RB/200 RX BLDG VENT SOUTH mR/hr 2 2 1 1 0.9 09 09 32 mR/hr 3 3 3 3 3 3 3 463A 9-10 RB/345 SPENT FUEL POOL WEST mR/hr 3 3 3 3 3 3 3 453B 9-10 RBfM6 SPENT FUEL POOL EAST mR/hr 162 162 94 78 64 62 60 9 10 RB/256 MAIN STM LINE A mR/hr 163 163 95 79 64 62 61 9-10 RB/256 MAIN STM LINE B mR/hr 161 161 93 77 63 61 60 9-10 RB/256 MAIN STM LINE C mR/hr 166 166 96 80 65 63 62 !
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| 9 10 RB/256 MAIN STM LINE D mR/hr 76 76 44 36 30 29 26 38 9-10 TB/248 SJAE(AIR EJECTOR) i i
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| l l VERMONT YANKEE NUCLEAR POWER STATION Rev. 0 l EMERGENCY PREPAPEDNESS EXERCISE Page 9.2-2 1997
| |
| (
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| 9 2 PROCESS MONITORS E #! d Cd hT A ~02365 7I d F f~ M ''IT E F hAnu,
| |
| ,nE;$hlMf9%[h.15CENMIdC,TEEOhMC90tdY4hI$ciSNiiE0'
| |
| ' "tM : rar chiOlidiE DINS$$5Y5iin0 N$MM@.d[j
| |
| !NOf! PANEL ELDGELV 5.e! i DESCRIPTIONi s'*J UNfTS 2. '.MMi* *0-L,i"yliYD t M ; *y 2r 2 3.- ;,
| |
| 9-2 ST/257 STACK GAS MON-GAS 1 com 150 20 20 20 20 20 20 9-2 ST/257 STACK GAS MON-GAS 2 com 200 20 20 20 20 20 20 9-2 ST/257 STACK HI RANGE mR/hr 0.1 0.1 0.1 01 0.1 01 0.1 9-2 RB/200 CONTAINMENT MON GAS cpm 234 DSL DSL DSL DSL DSL DSL 92 RB/200 CONTAINMENT MON-PART cpm 5481 10180 9385 8655 7900 7360 6790 l
| |
| l 27 9-2 DW/252 DRYWELL CH A R/hr 1 500 1500 1800 1700 1800 1900 28 9-2 DW/252 DRYWELL CH B Res 1 500 1500 1800 1700 1800 1900 92 RB/280 RX BLDG VENT GAS cpm 150 150 150 150 150 150 150 l 9-2 RB/200 RX BLDG VENT - PART cpm 1500 1500 1500 1500 1500 1500 1500 31 910 RB'280 RX BLDG VENT NORTH mR/hr O9 01 01 01 0.1 01 0.1 32 9 10 RB/200 RX CLOG VENT SOUTH mR/hr 0.9 0.1 0.1 01 0.1 0.1 01 l 453A 9-10 RB/345 SPENT FUEL POOL WEST mR/hr 3 3 3 3 3 3 3 )
| |
| 453B 9-10 RB/345 SPENT FUEL POOL EAST mR/hr 3 3 3 3 3 3 3 !
| |
| 9 10 RB/256 MAIN STM LINE A mR/hr 59 8 4 2 1 1 1 l
| |
| 9-10 RB/256 MAIN STM LINE B mR/hr 60 8 4 2 1 1 1 9-10 RB/256 MAIN STM LINE C mR/hr 59 8 4 2 1 1 1 9-10 RB/256 MAIN STM LINE D mR!hr 61 8 4 2 1 1 1 38 9-10 TBf248 SJAE(AIR EJECTOR) mR/hr 27 <1 <1 <1 <1 <1 <1 NOTE: DSL = Down Sem Low l
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| l VERMONT YANKEE NUCLEAR POWER STATION Rev. O EMERGENCY PREPAREDNESS EXERCISE Page 9.2-3 1997 9.2 PROCESS MONITORS ET0 may M -~ 8E UM.59 nw . ~
| |
| f7Fft@.dOOTS9fM*iD.VITWh~T,iN.NEUTM,g<
| |
| my egg,irg, ,,ggy-pye~~m$.%.i
| |
| .QF ms., v - w n ww
| |
| #%suivggg Q.p%g~.j 4 **'f mw 5iM'IEN,n~~o$EY.~tf,s.m"fM.vm d
| |
| m-p g M6kg?put215 MM2WMt2@ *13904 a
| |
| -M?"PANEt BLDGIELVv2N DESCRPT10N AWUNITSiM *d ''a5 -$ h''< :"'4 M&Wi W ' 2 ** * *> * * * % ' -
| |
| 9-2 ST/257 STACK GAS MON-GAS 1 cpm 20 20 20 20 CSH(>1E6) OSH OSH 9-2 ST/257 STACK GAS MON-GAS 2 com 20 20 20 20 OSH(*1E6) OSH OSH I 9-2 ST/257 STACK HI RANGE mR/hr 0.1 0.1 0.1 0.1 40 80 120 l 9-2 RB/200 CONTAINMENT MON GAS com DSL DSL DSL DSL DSL DSL DSL j I
| |
| 9-2 RB/200 CONTAINMENT MON-PART cpm 6260 5775 5275 4775 4700 4600 4600 27 92 DW/252 DRYWELL CH A R/hr 4000 7500 7500 7500 7000 6500 6000 l 28 97 DW/252 DRYWELL CH B R/hr 4000 7500 7500 7500 7000 6500 6000 l 9-2 RB/200 RX BLDG VENT GAS com 150 150 150 150 OSHz1E6 OSH OSH f 9-2 RB/200 RX BLDG VENT. PART cpm 1500 1500 1500 1500 OSH>1 E6 OSH OSH -
| |
| 31 9-10 RB/280 RX BLDG VENT NORTH mR/hr 0.1 0.1 0.1 0.1 200 500 OSH>1 E3 j 32 9-10 RB/200 RX BLDG VENT SOUTH mR/hr 0.1 0.1 0.1 0.1 200 500 OSH>1 E3 l
| |
| 453A 9 10 RB/345 SPENT FUEL POOL WEST mRMr 3 3 3 3 10 20 40 )
| |
| l 4538 9-10 RB/345 SPENT FUEL POOL EAST mR/hr 3 3 3 3 45 90 160 9-10 RB/256 MAIN STM LINE A mR/hr 1 1 <1 <1 <1 <1 <1 l <1 <1 9-10 RB/256 MAIN STM LINE B mR/hr 1 1 <1 <1 ci 9-10 RB/256 MAIN STM LINE C mR/hr 1 1 <1 <1 <1 <1 <1 9-10 RB/256 MAIN STM LINE D mR/hr i 1 <1 <1 <1 <1 <1 j l
| |
| 38 9 10 TB/248 SJAE(AIR EJECTOR) mR/hr <1 <1 <1 <1 <1 <1 <1 l NOTE: OSH = Off Sce6e Hgh DSL = Down Scase Low 1
| |
| l l
| |
| l l
| |
| l l
| |
| 6
| |
| . l l
| |
| 4
| |
| | |
| ._. . _ .- __ __ . - . - . . - - - - - . . _ . . . . = . -
| |
| VERMONT YANKEE NUCLEAR POWER STATION Rev. 0 N EMERGENCY PREPAREDNESS EXERCISE Page 9.2-4 1997 9.2 PROCESS MONITORS per - -~ .m-~~ v - -
| |
| st.vm.s-~n,-w-rw w w.~.,.nn,, .x
| |
| . i. SCENARIOTIME w ,s--- ~-- , C - :y 06:15.:g#*0010. . ~ ~yg - - 5:4,n~O,t00
| |
| --- 0 .: p +.yU*'.OR15 nra
| |
| 'd,m -+..L s
| |
| . .- .u -m:, :
| |
| < r u. rwu. .v><e*4;,,..a.,,.x.~...
| |
| . Apg -
| |
| ..v. *
| |
| . - CLOCKTIMEnn ,r"s - ~ gn-' -1316 L o-- 13 30 '* m'13:45 2 1400' e 1*15 c ~' '
| |
| 'c*.'N.*'- L'ed *
| |
| <NO; ~ PANEL BLDG /ELV + t DESCRIPTION '-:fi-UNfTS ri' N '* **&#a- w -A 9-2 ST/257 STACK GAS MON-GAS 1 cpm OSH>1 E6 OSH OSH OSH OSH 9-2 STC57 STACK GAS MON-GAS 2 com OSH>1E6 OSH OSH OSH OSH 9-2 ST/257 STACK HI RANGE mRMr 140 135 130 120 110 l
| |
| 92 RB/200 CONTAINMENT MON GAS cpm DSL DSL DSL DSL DSL I 9-2 RB/200 CONTAINMENT MON-PART cpm 4550 4550 4400 4400 4400 27 9-2 DW/252 DRYWELL CH A RMr 5000 5000 5000 5000 5000 28 9-2 DW/252 DRYWELL CH B R/hr 5900 5000 5900 5900 5900 9-2 RB/200 RX BLDG VENT GAS com OSH>1 E6 OSH OSH OSH OSH 9-2 RB/200 RX BLDG VENT - PART cpm OSH21E6 OSH OSH OSH OSH 31 9-10 RB/200 RX BLDG VENT NORTH mRMr OSH>1E3 OSH OSH OSH OSH I 32 9 10 RB/200 RX BLDG VENT SOUTH mRMr OSH21E3 OSH OSH OSH OSH 453A 9-10 RS/345 SPENT FUEL POOL WEST mRMr 80 75 70 60 50 4538 9-10 RB/345 SPENT FUEL POOL EAST mRMr 400 300 270 250 200 l l I l 9 10 RB/256 MAIN STM LINE A mRMr <1 <1 <1 <1 c1 9-10 RB/256 MAIN STM LINE B mRMr <1 <1 <1 <1 <1 9 10 RB/256 MAIN STM LINE C mR/hr <1 <1 <1 <1 <1 9 10 RB/256 MAIN STM LINE D mRMr <1 <1 <1 <1 <1 38 9-10 TB/248 SJAE(AIR EJECTOR) mRMr <1 <1 <1 <1 <1 NOTE: OSH = Off Scak Hgh DSL = Down Scale Low i
| |
| 1 I
| |
| 4 l
| |
| 1 k
| |
| | |
| 4 l
| |
| l
| |
| .i VERMONT YANKEE NUCLEAR POWER STATION d
| |
| EMERGENCY PREPAREDNESS EXERCISE 1997 J
| |
| 2 9.3 IN- PLANT RADIATION LEVELS i 1 J
| |
| 1 t
| |
| d 4
| |
| i i
| |
| I J
| |
| l 4
| |
| 1 l
| |
| 1 1 l
| |
| : l 1
| |
| 1 I
| |
| a
| |
| - . - , - n --
| |
| | |
| i TABLE 9.3-1 Rev.O Reactor Building, Elevation 345' Page 9.3-1 (mR/hr unless otherwise noted)
| |
| : 3. Clocks : ARM ARMS "
| |
| -ARMe
| |
| '' ~
| |
| .: ARM - 7 ARM; '
| |
| Zone:'.'A':
| |
| v :n
| |
| - JZone:
| |
| Zone:
| |
| i Zone..
| |
| . - . - - v,,
| |
| ilV '
| |
| t- il A.
| |
| J12, J14r F153 /453 AT . . . ."453 B l/- -:111 2..
| |
| s Time :
| |
| 4 5 15 3 3 5 3 3 3 08:00 3 12 3 3 3 3 3 3 4
| |
| 08:30 3 2.5 3 11.5 3 3 3 3 3 3 09:00 8 3 3 1 3 3 3 10:00 1 1 10 15 10 45 10 20 45 10 12:30 10 20 20 25 20 90 20 40 90 20 l 12:45 40 40 50 40 160 40 80 160 40 13:00 80 120 80 400 80 160 400 80
| |
| ,, 13:15 80
| |
| ' 75 75 100 75 300 75 150 300 75 13:30 70 70 80 70 270 70 140 270 70 13:45 60 60 70 60 250 60 120 250 60 14:00 50 60 50 200 50 100 200 50 i 14:15 50 l
| |
| ; Zone Readings are average throughout zone. '
| |
| General area contamination levels increase to SK dpm/100 cm2 after 1230.
| |
| e i
| |
| REACTOR BUILDING 1
| |
| : N= ELEVATION 345' 1
| |
| #C'' ^
| |
| h , OPEN
| |
| ; =
| |
| l =
| |
| = c" II l 2
| |
| MONITORS n i
| |
| \ 'III I 5
| |
| !. c
| |
| @ a...,o,
| |
| ._e .m_. _
| |
| - i a e ~~__,. e a
| |
| 4 a:
| |
| i .9 a'~ ~ ~ ~ ~ ~ -
| |
| 10, w
| |
| 3 Spen 1 Fuel Poci ; ...........
| |
| gg ,,pg ,
| |
| Ecpoment Poot s', C.vdy ,
| |
| j0 g,,,,,,,,
| |
| .........................g .
| |
| / ;
| |
| ! i
| |
| _ \, -
| |
| 0 i0 n I . a
| |
| : @ . p i N @
| |
| 1&C 4C tD 8esa. AC1C
| |
| .isv. y' 14 Tool 453 I i foot Cre Cno
| |
| | |
| TABLE 9.3-2 Rev.O Reactor Building, Elevation 318' Page 9.3-2 (mR/hr unless otherwise noted)
| |
| I RClock%P FARM 1 SARM.;4 TARMe , sZoner JZoneh iZoner EZoneSs;;Zonef. 2 Zones FZoner l?jj yij'Wi ffp s/NT'' NS$l C M d6If" M8 MM O$@03%kMM$Ni[
| |
| 08:00 7 4 0.5 7 4 300 4 80 0.5 0.5 08:30 5 3 0.4 5 3 300 3 80 0.4 0.4 10:00 3 2 0.3 3 2 300 2 80 0.3 0.3 12:30 10 20 10 10 20 100 45 60 10 10 12:45 20 40 20 20 40 100 90 60 20 20 13:00 40 80 40 40 80 100 160 60 40 40 13:15 80 200 80 80 200 150 400 100 80 80 13:30 75 150 75 75 150 150 300 75 75 75 13:45 70 140 70 70 140 150 270 70 70 70 14:00 ,60 120 60 60 120 150 250 70 60 60 14:15 50 50 50 50 50 150 200 70 50 50 Zone Readings are average throughout zone. ,
| |
| General area contamination levels increase to SK dpm/100 cm2 after 1230.
| |
| REACTOR BUILDING
| |
| = N= ELEVATION 318' s a g gc_2 u
| |
| ? '
| |
| _ s a:o a 8 sassy heks I a
| |
| :[Q c 2aaa i E!?1 l , NI MONITORS ]
| |
| O
| |
| " O gy;gd i G ''''''''t i
| |
| , ,0 "Ta "'' l yy a g a.. i . II IIIr 0 e.... %.-. c g n.-o
| |
| : a. ..m. , c=
| |
| 3_ %]g .
| |
| _ _ _~~ _
| |
| O_
| |
| ,l g el
| |
| ___a y=
| |
| ~
| |
| I
| |
| -~~~
| |
| 5 w ''~ ~ ~ ~ ~ ~ ~ ~ ~ .l - ~i y 6, 5
| |
| __________z___L p (I-y l 9 g a.--. m .
| |
| - t- ~
| |
| ,~,,
| |
| ;g l
| |
| l N
| |
| ~ i ls l i
| |
| ._.._____________e_s l3) coa.ng w ,
| |
| %N-________ _
| |
| _ r lt i. ,..i
| |
| ? l i
| |
| Surge Tann Oc -
| |
| 8 i J@
| |
| e- a_s
| |
| ,y: I Ts F_ o cu'6cl w w.
| |
| :r------
| |
| s VII 9 F em ri ri rm e9 e
| |
| | |
| 1 TABLE 9.3-3 Rev.O Reactor Building, Elevation 303' Page 9.3-3
| |
| : (mR/hr unless otherwise noted) iClock: SARM; cARM 'iZone ' < ': Zone < ::. Zone 1 Zone, ~; Zoner iZone: EZoneii dTimei 585 ' 19I. ?l' !!U ? tile IVI ?Zorie V UViI ~ Will I 08:00 4 5 5 3 600 3 60 0.1 0.2 08:30 3 4 4 3 600 3 60 0.1 0.2 10:00 1 4 4 3 600 3 60 0.1 0.2 12:30 50 120 120 180 720 180 150 30 20 12:45 125 300 300 450 900 450 375 75 50 13:00 200 480 480 720 1080 720 600 120 80 13:15 400 960 960 1400 1560 1400 1200 240 160 13:30 280 670 670 1000 1270 1000 800 168 110 13:45 250 600 600 900 1200 900 750 150 100 14:00 230 560 560 840 1160 840 700 138 90 14:15 200 450 450 675 1050 675 560 120 80 Zone Readings are average throughout zone.
| |
| General area contamination levels increase to 10K dpm/100 cm2 after 1230.
| |
| REACTOR BUILDING
| |
| = N= ELEVATION 303' l g toooocy u
| |
| _f i
| |
| O O
| |
| - II l Iy E
| |
| ==
| |
| l
| |
| ' ' lw-7Z -
| |
| ---------- D-% EllE EiE? _ _ _ _1_ _ _ _ _ _ _ _9_''FT"g
| |
| = = s-a ,,.cu ,,, - ;-
| |
| a [g MONITORS g I S" "" Vg ,
| |
| g m %.
| |
| ],y,,,_____________c _ _ _ _ _ _ _ 7, _
| |
| A e '
| |
| i g
| |
| @ n..cw emy,7 "~ ~ ~~ (</ "
| |
| m so. . ,.
| |
| l i
| |
| VI I o% i, aa=
| |
| l JL Q s l
| |
| 5'*a
| |
| \% l 1
| |
| C g 3 0-------_ 4 ___________________1.____y _
| |
| T
| |
| , m o o oom VII n n n c
| |
| | |
| Rev. O TABLE 9.3-4 Reactor Building, Elevation 280' Page 9.3-4 (mR/hr unless otherwise noted)
| |
| ~
| |
| uRBVent NpRBVentSK ?Zonen jZone;A 'sm' ?ZoneA =M %Zonei 4Zoney s^ =.c s. :-; Zoner EZones e w' sZoney
| |
| >w w wywe?i w.
| |
| w@a mme J Cloc h ~* ww = x: w .. . : / WjiM MVih , 6Vilim $ Villi iTimeh$t; #ra.a.+PiARM ARM 6 e..;s 311 IARM 321 ill 7 411 MIR !!V8 6 25 5 4 3 1 2 2 08:00 8 2 2 20 4 3 2 1 2 2 08:30 6 1 1 5 0.1 4 150 3 2 2 1 1 1 10:00 5 0.1 200 200 200 200 160 200 50 12:30 50 200 200 50 275 500 500 500 400 500 125 12:45 125 500 500 125 350 800 800 800 640 1200 200 13:00 200 OSH>1E3 OSH>1E3 200 l
| |
| 550 1500 1500 1500 1200 2400 400 13:15 400 OSH OSH 400 280 430 1200 1200 1200 960 2200 280 13:30 280 OSH OSH 400 750 750 750 600 2000 250 13:45 250 OSH OSH 250 380 900 900 900 720 2000 230 14:00 230 OSH OSH 230 350 800 800 800 640 2000 200 I 14:15 200 OSH OSH 200 Zone Readings are average throughout zone.
| |
| General area contamination levels increase to 10K dpm/100 cm2 after 1230.
| |
| OSH = Off Scale High REACTOR BUILDING l
| |
| = N= ELEVATION 280' i J
| |
| 6.J WG H L-.J jJ bJ J i J 'MC Hz 0000 . .
| |
| 0000 i o,,e. se r,- 00 Mc ca" 00 rm. l D 1
| |
| @n ""=9IV@ 7 n
| |
| if @,4.,
| |
| a m- Q l ,,,,,
| |
| g g '
| |
| MONITORS iiiis
| |
| > i a ui,- i--~~~u uT ; uc "s ,,,O III .i m
| |
| '. V o C
| |
| O,.....- Eevaior Enirance ..... __.__..__.g i
| |
| )
| |
| s
| |
| ] ooneegen Hs s. ~
| |
| B.mfaa
| |
| _ _ _ _ , , rn O .... .-
| |
| 6 'i [ \ N. Taisu (D 1 l: ~ / ,' ' ' , gnme- 4 y
| |
| . 11 i Cone Gan/Part Men g i ) ,
| |
| 1 1 l VI
| |
| , Waal MC 5et aP hhei
| |
| : i. . ' Mer.L AM RWCU g U Pgp huens 1 % / Mt.nl MC $
| |
| - en fa
| |
| %"g % j M- -
| |
| . i cm ,__/ A -
| |
| 33 4 _ N -- - .. ..<msm=x ,
| |
| s 7 /!!j caVIII ,.,
| |
| lVII mi
| |
| [( ,l ?
| |
| | |
| TABLE 9.3-5 rtev. w RIactor Bu%ng, Elwetion 252' Pag 3 9.3 5 (mR/hr unless otherwise noted) rj Clocke i- ARML AARM cpARM W ARMc xARM{ - RMm s Zoner NZone %Zonee74 Zone +ceZoneaZone w Zone -
| |
| $WYNi?2T 19dFE: h di ^Y E7 NT ?t S29f" fi d ' N N # $ HI Y C N V E W U VI1 ' ' Vil ~
| |
| 8.00 4 0.3 5 520 10 100 5 4 0.3 50 0.3 10 25 s8:30 2 0.25 5 310 8 100 5 2 0.25 50 0.25 8 25 10.00 0.5 04 5 $000 4 100 5 0.5 0.4 3000 0.4 4 150 10:15 0.5 04 5 OSH>1E4 4 100 5 0.5 0.4 12000 0.4 4 700 11:30 0.3 0.3 5 OSH 4 100 5 0.3 0.3 75000 0.3 4 4000 12:30 170 680 100 OSH 4 100 100 170 660 70000 680 4 3500 12.45 300 OSH)1E3 180 OSH 4 100 180 300 1300 65000 1300 4 3000 13.00 650 OSH 380 OSH 4 100 380 650 2600 60000 2600 4 3000 13:15 850 OSH 500 OSH 4 100 500 850 3400 60000 3400 4 3000 13.30 600 OSH 350 OSH 4 100 350 600 3000 60000 3000 4 3000 I
| |
| 13 45 530 OSH 300 OSH 4 100 300 530 2500 60000 2500 4 3000 I
| |
| 14.00 500 OSH 290 OSH 4 100 290 500 2200 60000 2200 4 3000 l 14:15 400 OSH 240 OSH 4 100 240 400 2000 60000 2000 4 3000
| |
| ]
| |
| l RHR A" ' . RHR B" ' RCIC" ? HPCl* I l i Clock NORTH " i SOtJTH" : TIP "'
| |
| qQtFJggg jp{e RN2 ' RMS t thN UAD Q IQUADNQUAD>IOUAD I 08.00 <1 <1 <1 5 5 1 5 10:15 <1 <1 <1 800 800 1 5 11:30 <1 <1 <1 2000 2000 1 5 12:30 <1 <1 <1 3500 7000 1 5 1
| |
| 12:45 <1 <1 <1 3500 10000 1 5 13.00 <1 1.5 <1 3500 12000 1 5 13 15 <1 2 <1 3500 16000 1 5 13:30 <1 1 <1 3200 14000 1 5 14:15 <1 <1 <1 3000 10000 1 5 Zone Readings are average throughout zone.
| |
| I General area contamination levels increase to 15K dprn/100 crn2 aner 1230.
| |
| " RMS 11 Readings in R/hr (High-Range Accident ARMS - 1R/hr to 10,000 R/hr)
| |
| * Zone Readings are average dose rates throughout the RHR, RCIC and HPCI Quad elevation areas.
| |
| REACTOR BUILDING c N= ELEVATION 252'
| |
| ~' " tennaeL gilttti
| |
| =
| |
| -~
| |
| III @ ,a; ToLa Aco " * ' {_ _ _ _ ,
| |
| MONITORS 3 'L, IV we aMS ,, t (NW Aniott) l aus ,,us m> ~-----------
| |
| gg ---
| |
| ,,4 ________;_
| |
| $7 g g
| |
| ,e
| |
| -, ,, m1-,
| |
| ~~ -j T ,' CRo Ch.e s L E o
| |
| O, ~Perunnelausong Access _
| |
| j f (g
| |
| )
| |
| Seern Dmsaarge vehnme t
| |
| - - i
| |
| * acac,or sudding Souen ' i g
| |
| i 3 Eq.pmers Radroad Accesa .
| |
| m b a::
| |
| c _"
| |
| ! n. aaciar o den,new on II 's g d
| |
| U Morwor TIP warusrawas Q n8~ - s noa. - G ,,.,
| |
| .' /
| |
| / l I
| |
| *L _..
| |
| M@ XX pm
| |
| \_/ Personnel Accus Hatch '
| |
| l
| |
| - c.o l ae O,aa.c,en,em o-a a- ,,,g1 V :
| |
| L*. I "E Bf:: I ,on i
| |
| .. ._ l %. d,E-i i VII i
| |
| , 2"'M_!
| |
| O _
| |
| ( ,
| |
| l Oa m,. . . -
| |
| "q nus ii-a -
| |
| ; & _____.a j T* B9'c 000
| |
| " ' " ~ '
| |
| i aav l -
| |
| I >
| |
| '% *\ r w l -
| |
| l (3 ;
| |
| ~: @"' @"' sL_-
| |
| i o
| |
| | |
| TABLE 9.3-6 Rev.O Turbine Deck, Elevation 272' Page 9.3-6 (mR/hr unless otherwise noted) f M ' EClock & 7 ARM'~ m2one' +: ' MZone <f o - Zone- ~ Turbine: Deck CAM (s.v.ii)!K!N W lhTime aO O ' ARM 24 ~ 'u >' t,''''/ /~^ " li' '''f4 "''. til 6 <~< N, c'NGNW&nRParticulatey*
| |
| 08:00 8 100 150 8 250 900 08:30 7 80 100 8 250 900 08:45 7 50 80 8 250 900 10:00 to End 7 10 20 8 250 900 l
| |
| I l
| |
| Zone Readings are average dose rates throughout zone.
| |
| General area contamination levels <1K dpm/100 cm2.
| |
| 1 l
| |
| 1 TURBINE DECK ELEVATION 272' l
| |
| open .~
| |
| i 3E *""* f#' I
| |
| ,Y$ h _ _ _ _ _ ac
| |
| ~~~~~~]l _
| |
| L
| |
| +
| |
| t
| |
| : j. ~ ) m
| |
| ! 'l-C[__eM__&-- h ;g l l @
| |
| r- ; 2
| |
| : l. .
| |
| i i m l el U** l l so
| |
| ; e >______U__III' _____________i " 'I ; y m
| |
| , e II i imi P d d
| |
| + + +
| |
| i y + + +
| |
| l MONITOR Tureene Swdeng Tm Seem inal
| |
| | |
| Rev.O TABLE 9.3-7 Page 9.3-7 Turbine Building Truck Bay, Make-Up Demineralization Cond.
| |
| Demineralization Areas, Elevation 252' (mR/hr unless otherwise noted)
| |
| GWClock?@ SRM-14-23AY AARMiMRM;.1446fW1!Zonette ? Zone %w&Zonej 4WEZoned safMimeiPS$WMR(cpm)3 F* t20kWW(cpm)T*AbMieh A IllF*%fM@elllMEREMMIVFm 0.5 0.5 0.4 0.2 08:00 150 0.2 150 0.4 0.4 0.3 0.2 08:30 150 0.1 150 0.2 0.2 0.2 0.2 150 0.01 150 10:00 to End 1
| |
| I Zone Readings are average dose rates throughout zone.
| |
| General area contamination levels <1K dpm/100 cm2.
| |
| l l
| |
| l l
| |
| i l
| |
| PRETREATMENT ROOM, BOILER ROOM, TURBINE LOADING BAY, MUDS, DIESELS, COND. DEMIN. HATCH ELEVATION 252' N- ; ; gjg mmw .n .i l
| |
| l-
| |
| : l i i' r I '
| |
| 11 i
| |
| =
| |
| 6 -l -
| |
| *=*
| |
| ,- O a
| |
| j g g
| |
| g m
| |
| ac-Q li gg 0 r '"*"-! ! n 8 9? E$3 -
| |
| II ci w.- l 5 l2- "'#E 7 c hC @ l! l8 I
| |
| . i o - l III H -
| |
| O 0 n
| |
| 0 lilli: 0! U i i_j 5 U
| |
| 5! [,____4________
| |
| g
| |
| , e 'u '
| |
| i ,
| |
| C-
| |
| -----~E '
| |
| SJAE ROOM C-MONITORS 3
| |
| o 0
| |
| o l
| |
| [
| |
| ,j -
| |
| L_.. a
| |
| @,a_a_raa l l l [ i RM-14'S s.........--..,__.-__
| |
| l
| |
| @ == ' m o
| |
| = c ee@@@
| |
| g ,_ %
| |
| 0 0 g - o N
| |
| ' O . hO .o 6 e m i
| |
| | |
| TABLE 9.3-8 Rev.O Turbine Building Cond. Bay, Elevation 248' Page 9.3-8 l
| |
| (mR/hr unless otherwise noted) v gfARMggg2ZonenpgZonskygZonejgMZoggZonejjsjig2cnew d d hajlARMg %YNA*iWAWW$eMWshadiWMMhF
| |
| _b_plllgClock"'JW;ni61 08:00 2.5 240 2 2 4 8 240 2 ;
| |
| 08:30 2 140 2 2 3 4 140 2
| |
| ]
| |
| 08:45 2 115 2 2 3 4 115 2 ;
| |
| 09:00 2 95 2 2 3 4 95 2 09:15 2 92 2 2 3 3 92 2 00:30 2 90 2 2 2 3 90 2 0545 2 87 2 2 2 2 87 2 !
| |
| 10:00 1.5 16 1 1 1 2 16 1 10:15 1.5 9 1 1 1 1 9 1 10:30 1.5 6 1 1 1 1 6 1 j 10:45 to End 1.5 5 1 1 1 1 5 1 l
| |
| Zone Readings are average dose rates throughout zone. ,
| |
| General area contamination levels <1K dpm/100 cm2.
| |
| TURBINE BUILDING l c N~ ELEVATION 248' l dr - - -
| |
| _g l e .
| |
| IV MONITORS i
| |
| o ~ o Io .. o i"; -
| |
| ))))h T ; ;;_; - ', (
| |
| o-~~o o-~~o i E !\m 21 OVIII @ l l l i l = ' steam Pachmg , h '
| |
| P 1 -*8 O O O O
| |
| -___l '
| |
| @1-.ms..m s. v ~-
| |
| F R$
| |
| ,s= _J L_
| |
| l
| |
| ; j-- - % g rn g
| |
| i - - ' ; %,. , t. % Y In -
| |
| T f-- lf- III g l -
| |
| y t-c o.
| |
| - l, 00 99 VVVVj .______________
| |
| j!,
| |
| !E=- n #!
| |
| l \ \
| |
| : l l 1
| |
| 1
| |
| | |
| - _ _ - -_ ._. ._~ _ -- - _ _ . - - . .
| |
| 1 RQv. O TABLE 9.3-9 Turbine Building, Demineralization /OG Areas, Elevation 232' Page 9.3-9
| |
| : (mR/hr unless otherwise noted)
| |
| P 2 i ?
| |
| 0.5 76 0.2 0.5 0.2 ,
| |
| 08:00 '
| |
| 0.4 44 0.2 0.5 0.2 08:30 0.4 36 0.2 0.5 0.2 ;
| |
| 08:45 0.3 30 0.2 0.5 0.2 09:00 l 29 0.2 0.5 0.2 09:15 0.3 0.3 28 0.2 0.5 0.2 l
| |
| ; 09:30 0.2 i 09:45 0.3 27 0.2 0.5 0.1 <1 0.2 0.5 0.2 ;
| |
| 4 10:00 to End 1 Zone Readings are average dose rates throughout zone.
| |
| l General area contamination levels <1K dpm/100 cm2. l 3
| |
| 4 I
| |
| l i
| |
| 4 TURBINE BUILDING ELEVATION 232'
| |
| ""%L"a cc3 i +,.t gg@a @o q
| |
| ,= i MONITORS 0I =_
| |
| { {
| |
| u]
| |
| o g, ,_______________
| |
| 1
| |
| ^ $
| |
| @ o.--,_ 'a " *. @
| |
| gg 3 l ! g e, - . ,
| |
| i
| |
| , , iTe - _,,_, m 1
| |
| !b {
| |
| g]
| |
| f' *
| |
| @ 1" f v t= O e
| |
| S
| |
| ;"'[
| |
| ~
| |
| III -
| |
| ! , i
| |
| * rLfiil 4 l li - : e.,w
| |
| !' @ Dmmu n 61' $
| |
| l -
| |
| i
| |
| | |
| TABLE 9.3-10 Rev. O Turbine Building Cond. Bay, Elevation 222'6" 228'6" Page 9.3-10 (mR/hr unless otherwise noted) 9?fRClock - /'' ARM ^: Zone ; Zone ' ,,'-l' Zone '^ 72 / < Zones' ', , Zone ( '; Zone .
| |
| fj%%iQu'm , 33 -l,'injf'3-%',''~,
| |
| D Cgg c, L;',,;ggg >W y ; gg,Ja!- ',^ g ,';'; yg }
| |
| 08:00 135 3 1 50 140 2 75 08:30 77 3 1 50 80 2 75 08:45 63 3 1 50 70 2 75 09:00 52 3 1 50 60 2 75 50 3 1 50 55 2 75 09:15 09:30 50 3 1 50 55 2 75 09:45 48 3 1 50 50 2 75 3 5 15 2 10 10:00 to End 1 1 Zone Readings are average dose rates throughout zone.
| |
| General area contamination levels <1K dpm/100 cm2.
| |
| TURBINE BUILDING ELEVATIONS 222' AND 228'
| |
| 'N+ , ,
| |
| I
| |
| : III !
| |
| MONITOR 3 , a o 10
| |
| * umw'vu 0" '. .
| |
| ,:gmare i
| |
| o gg m; (1
| |
| g ,=_---.- non noni gg o
| |
| i rm m i O 925m 4
| |
| 'J
| |
| ,- l_ @ lv *n @
| |
| ll
| |
| ] v " " " -
| |
| ! IV ! y9a ?
| |
| ; :, r :
| |
| g a%Ile f ku t vvvv 99 [l !
| |
| ; I, 5 .I i ., w M 8i y 00 =...r-- I:
| |
| 5; <....e : l 'a g
| |
| i_----------- ! rp
| |
| -,--,--- ,- - :y7 Qj i
| |
| l o < , ~ ~ >
| |
| < . . . . o lg l J
| |
| i
| |
| | |
| t l
| |
| TABLE 9.311 ,
| |
| Rev. O Torus Area (Catwalk and Torus Elevation Areas) . Page 9.3-11 (mR/hr unless otherwise noted)
| |
| Ii h ' $' '! ' ? '
| |
| k 3 08:00 8 8 08:30 7 7 10:00 250 250 10:15 750 750 10:30 800 800 10:45 850 850 11:00 900 900 11:1 5 1200 1200 11:30 to End 2000 2000 Zone readings are average dose rates throughout the Torus Catwalk and Torus elevation areas.
| |
| l TORUS CATWALK
| |
| +
| |
| /
| |
| O MONITOR
| |
| = = = m ~
| |
| n..c.
| |
| N C
| |
| Oi ssaecm%aen 22 rn to
| |
| < U
| |
| <I h H
| |
| SE Ms e Macn 4
| |
| | |
| Rev.O TABLE 9.3-12 Page 9.3-12 RadWaste Building, Elevation 252' (mR/hr unless otherwise noted) 5: Zone:; sZonet zZoner
| |
| ? ARM:''i:ARMJ Zone < ? Zone:::
| |
| 9 Clocki llil:i EZoneV; 21f E18f 3* 2 1! ' ' lill ! SIVi '
| |
| OTime: 5 0.5 1 1 1 0.5 0.5 08:00 to END Zone Readings are average throughout zone.
| |
| General area contamination levels <1K dpm/100 cm2.
| |
| FIGURE 9.3-12 i MONITORS to (pl [Ol lll m e . ... . ..
| |
| _ _ _= _,,,' gg g e. ... o..o .
| |
| "s _. d tg c
| |
| _. _; c 141 gg i-
| |
| , i o i
| |
| _f j f. v cf 3
| |
| Nm c,yy n
| |
| i_
| |
| ~ lgh M
| |
| | |
| TABLE 9.3-13 Rev.O RadWastre Building, Elevation 230' Page 9.3-13 (mR/hr uti;ess otherwise noted)
| |
| ARM Zone. sZonec :Zo e?
| |
| ;Z : Zn Clock 0.8 30 100 5 150 08:00 to 12:30 1.5 100 30 100 250 1000 1230 70 150 30 100 750 3000 1245 100 200 30 100 1200 5000 13:00 to,_End 150 Zone Readings are average throughout zone.
| |
| General area contamination levels <1K dpm/100 cm2.
| |
| - c N=
| |
| - [' g ure L
| |
| ''''''' I B ==.
| |
| ara sms %-
| |
| & ==j ,
| |
| ~'
| |
| y 230 om i
| |
| lll FIGURE 9.313 3
| |
| ()
| |
| V E A '' "o"'To"S
| |
| ~
| |
| J E-q ..=;, a ''- @ ...,
| |
| .....n..
| |
| . u..
| |
| g= ,
| |
| {
| |
| 3, u m=a
| |
| =r 13
| |
| "' Og M ~
| |
| E --
| |
| E
| |
| " " * " II i
| |
| l g .
| |
| E -
| |
| | |
| VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAR.EDNESS EXERCISE 1997 9.4 PLANT CHEMISTRY DATA SECTION 9.4.1 Reactor Coolant Data 9.4.2 Primary Containment Data 9.4.3 Reactor Building Data f
| |
| | |
| ..- - - - - - - - . -.... . _ . . - . _ ~ _ . . _ _ - - . . - . - . . - . . - .
| |
| 4 1
| |
| j Rev0 ,
| |
| Page 9.4.1-1 i
| |
| i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE i j
| |
| 1997 i !
| |
| 9.4.1 REACTOR COOLANT DATA !
| |
| / :
| |
| A. Reactor Coolant Activity Concentrations (uCi/ml) i I !
| |
| isotope Prior to 0950 0950-1030 1030 -1100 1100- 1130 i h l-131 3.5E-04 4.3E+02 4.3E+02 4.2E+02 l-132 2.8E-04 5.6E+02 4.8E+02 4.1E+02 !
| |
| , 1-133 5.2E-04 8.4E+02 i
| |
| 8.3E+02 8.1 E+02 1-134 4.1 E-04 7.0E+02 4.7E+02 3.2E+02 j l-135 4.5E-04 7.6E+02 7.3E+02 6.9E+02 Totallodine l
| |
| 2.0E-03 3.3E+03 2.9E+03 2.7E+03 '
| |
| l l-131 D.E. 5.5E-04 7.5E+02 7.3E+02 i
| |
| 7.2G+02
| |
| ! Kr-83m 1.2E-03 2.3E+00 1.9E+00 2.3E+00
| |
| ! Kr-85m 2.5E-02 4.9E+00 4.5E+00 4.9E+00 i
| |
| ! Kr-85 4.8E-03 2.4E-01 2.4E-01 2.4E-01 l Kr-87 2.9E-03 7.7E+00 5.9E+00 7.7E+00 l Kr-88 1.0E-03 1.2E+01 1.1 E+01 1.2E+01 l Xe-131m 9.1 E-05 1.4E-01 1.4E-01 1.4E-01 j Xe-133m 7.3E-04 1.3E+00 1.3E+00 1.3E+00 j Xe-133 5.3E-03 4.3E+01 4.3E+01 F
| |
| 4.3E+01
| |
| ! Xe-135m 5.8E-03 7.2E+00 1.9E+00 7.2E+00 ;
| |
| Xe-135 2.2E-03 1.0E+01 9.9E+00 1.0E+01
| |
| ) Xe-138 3.8E-03 1.3E+01 1.2E+01 1.3E+01 Total Gas 5.3E-02 1.0E+02 9.1E+01 1.0E+02 '
| |
| r I
| |
| | |
| .- . - . _ _ . _ . . _ . _ . - . _ _ _ . ~ _ - _ _ - - - _ _ . _ -. . . - . ~ . . . _ . - .
| |
| R:.y 0 Pagn 9.4.12 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.4.1 REACTOR COOLANT DATA ,
| |
| l A. Reactor Coolant Activity Concentrations (uCi/ml) i isotope 1130- 1200 1200-1300 1300-1400 1400-1415 l-131 4.2E+02 4.2E+02 4.2E+02 4.2E+02 ;
| |
| l i 1-132 3.5E+02 2.6E+02 1.9E+02 1.9E+02 l r
| |
| l-133 8.0E+02 7.7E+02 7.5E+02 7.5E+02 l-134 2.1E+02 9.5E+01 4.3E+02 4.3E+01 l
| |
| l-135 6.5E+02 5.9E+02 5.3E+02 5.3E+02 -
| |
| l Totallodine 2.4E+03 2.1 E+03 2.3E+03 1.9E+03 1-131 D.E. 7.1 E+02 6.9E+02 6.8E+02 6.8E+02 r
| |
| I i
| |
| l Kr-83m 1.9E+00 1.3E+00 9.2E-01 5.8E-01 Kr-85m 4.5E+00 3.8E+00 3.3E+00 2.7E+00 Kr-85 2.4E-01 2.4E-01 2.4E-01 2.4E-01 ;
| |
| Kr-87 5.9E+00 3.4E+00 2.0E+00 9.9E-01 Kr-88 1.1E+01 8.3E+00 6.5E+00 4.7E+00 !
| |
| Xe-131m 1.4E-01 1.4E-01 1.4E-01 1.4E-01 ,
| |
| 1.2E+00 1.2E+00 1.2E+00 I Xe-133m 1.3E+00 Xe-133 4.3E+01 4.3E+01 4.2E+01 4.2E+01 Xe-135m 1.9E+00 1.3E-01 9.1E-03 3.3E-04 Xe-135 9.9E+00 9.1 E+00 8.5E+00 7.7E+00 Xe-138 1.2E+01 1.2E+01 1.1E+01 1.1E+01 Total Gas 9.1 E+01 8.2E+01 7.6E+01 7.1 E+01 l
| |
| l T
| |
| I I
| |
| Ll
| |
| | |
| Rev 0 Pag 3 9.4.13 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.4.1 REACTOR COOLANT DATA B. Reactor Coolant Gas Sample Dose Rates Unshielded W:,* i
| |
| ~,, e 4 Shielded (1 inch lead)
| |
| (mR/hr per cc)* 6.s;Q (mR/hr per cc)*
| |
| Time Contact 1 ft [h il Contact 1 ft Prior to 0950 1.5E-02 1.1 E-04 l'" , y, i 1.9E-04 1.3E-06 0950-1030 2.9E+01 2.0E-01 h ^i
| |
| ~ 3.6E-01 2.5E-03 1030 1100 2.7E+01 1.8E-01 Esi@M 3.2E-01 2.3E-03 1100-1130 2.9E+01 2.0E-01 lMifE3 3.6E-01 2.5E-03 1130-1200 2.7E+01 1.8E-01 $$$$?{ 3.2E-01 2.3E-03 1200- 1300 2.4E+01 1.6E-01 Fe2EG 2.9E-01 2.1E-03 1300- 1400 2.2E+01 1.5E-01 $5Tiil 2.7E-01 1.9E-03 1400-1415 2.1E+01 1.4E-01 FR$1 2.5E-01 1.8E-03 l
| |
| * Values must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rate in mR/hr.
| |
| 6
| |
| | |
| l Rev 0 '
| |
| Page 9.4.1-4
| |
| )
| |
| VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCIOE 1997 i
| |
| 9.4.1 REACTOR COOLANT DATA 1
| |
| C. Reactor Coolant Liquid (lodine) Sample Dose Rates j Unshielded $?$$ Shielded (1 inch lead)
| |
| (mR/hr per cc)* hhkh (mR/hr per cc)*
| |
| Time Contact 1 ft j@if$$ Contact i ft i Prior to 0950 1.6E-03 1.1E-05 IfnMM 2.0E 05 1.3E-07 0950-1030 2.6E+03 1.8E+01 ll$$%3j] 3.2E+01 2.2E-01 !
| |
| 1030-1100 2.3E+03 1.6E+01 l@fd 2.9E+61 1.9E-01 1100- 1130 2.1E+03 1.4E+01 $$disi 2.6E+01 1.8E-01 1130-1200 1.9E+03 1.3E+01 f.Gh~j 2.4E+ 01 1.6E-01 1200-1300 1.7E+03 1.2E+01 b :T' 1 2.1E+01 1.4E-01 I 1300-1400 1.8E+03 1.3E+01 EsTJd 2.3E+01 1.5E-01 1400-1415 1.5E+03 1.0E+01 payf8 1.9E+01 1.3E-01
| |
| * Values rr.ust be multiplied by the sample volume in milliliters to obtain the sample dose rate in mR/hr.
| |
| e l
| |
| t s
| |
| | |
| 2 R $v 0 Pag 3 9.4.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE l 1997 ,
| |
| 9.4.2 PRIMARY CONTAINMENT DATA A. Primary Containment Air Concentrations (uCi/cc)
| |
| Isotope Prior to 0950 0950-1000 1000-1045 1045-1115 i 2.0E-11 3.9E-10 2.0E-03 9.8E-03 ,
| |
| 1-131 ;
| |
| 1.6E-11 3.1E-10 1.5E-03 7.7E-03 ;
| |
| l-132 3.8E-11 7.3E-10 8.4E-03 4.2E-02 l-133 8.8E-12 1.7E-10 8.1 E-04 4.1 E-03 1-134 3.0E-11 5.9E-10 2.9E-03 1.5E-02 l 1-135 2.2E-09 1.6E-02 7.8E-02 l Totallodine 1.1E-10 3.3E 11 6.5E-10 4.5E-03 2.3E-02 1-131 D.E.
| |
| l l
| |
| KR-83M 5.1E-07 7.8E-06 1.1E+00 5.3E+00 1.6E-06 2.4E-05 3.3E+00 1.6E+01 KR-85M 1.0E-07 1.5E-06 2.1E-01 1.1E+00 f KR-85 1.3E-06 2.0E-05 2.6E+00 1.3E+01 KR 87 3.3E-06 5.1E-05 6.9E+00 3.4E+01 KR-88 5.7E-08 8.7E-07 1.2E-01 6.1 E-01 XE-131M 5.2E-07 8.0E-06 1.1E+00 5.6E+00 XE-133M 1.8E-05 2.7E-04 3.8E+01 1.9E+02 XE-133 2.1E-06 3.3E-05 4.5E+00 2.2E+01 XE-135M 5.5E-06 8.4E-05 1.2E+01 5.9E+01 l XE-135 3.9E-08 6.0E-07 6.5E-02 3.3E-01 XE-138 3.3E-05 5.0E-04 6.9E+01 3.5E+02 l Total Gas l
| |
| $ I
| |
| )
| |
| i )
| |
| l l
| |
| | |
| - . - ._.-.. .. - . .- .. . . - ... - - .... - - .- - --. - _.. - - .- -.._.-_..-.~. - -
| |
| Riv 0 Page 9.4.2-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.4.2 PRIMARY CONTAINMENT DATA i
| |
| A. Primary Containment Air Concentratione (uCi/cc) ,
| |
| Isotope 1115-1215 1215-1315 1315-1415 l-131 1.4E-02 1.4E-02 1.4E-02 1-132 1.1 E-02 9.2E-03 6.8E-03 1-133 5.9E-02 5.8E-02 5.6E-02 1-134 5.7E-03 3.8E-03 1.7E-03 1-135 2.1E-02 2.0E-02 1.8E-02 .-
| |
| Total lodine 1.1 E-01 1.0E-01 9.6E-02 1-131 D.E. 3.2E-02 3.1 E-02 3.1E-02 KR-83M 7.4E+00 6.2E&OO 4.2E+00 -
| |
| KR-85M 2.3E+01 2.1 E+01 1.8E+01 KR-85 1.5E+00 1.5E+00 1.5E+00 KR-87 1.9E+01 1.4E+01 8.1E+00 ,
| |
| KR-88 4.9E+01 4.3E+01 3.4E+01 XE-131M 8.5E-01 8.5E-01 8.5E-01 XE-133M 7.8E+00 7.8E+00 7.7E+00 XE-133 2.7E+02 2.6E+02 2.6E+02 XE-135M 3.2E+01 8.3E+00 5.8E-01 l
| |
| XE-135 8.3E+01 8.0E+01 7.4E+01 XE-138 4.6E-01 4.5E-01 4.3E-01 Total Gas 4.9E+02 4.5E+02 4.1 E+02 I
| |
| | |
| Rev 0 l
| |
| f Prg3 9.4.2-3 l
| |
| VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 l 9.4.2 PRIMARY CONTAINMENT DATA
| |
| : 8. Primary Containment Sample Dose Rates i
| |
| Unshielded Shielded (1 inch lead)
| |
| (mR/hr per ec)* (mR/hr per cc)*
| |
| l Time Contact i ft Contact i ft l
| |
| Prior to 0950 9.4E-06 6.5E-08 _1 1.2E-07 8.2E-10 l
| |
| 0950-1000 1.4E-04 1.0E-06
| |
| #Jij68 1.8E-06 1.3E-08 1000-1045 2.0E+01 1.4E-01 %$$ ' 5E-01
| |
| .. 1.7E-03 1045-1115 1.0E+02 6.9E-01 55115 1.2E+00 8.7E-03 1115-1215 1.4E+02 9.7E-01 [N!N! 1.7E+00 -
| |
| 1.2E-02 ;
| |
| 1215-1315 1.3E+02 8.9E-01 I . M 1.6E+00 1.1E-02 1315-1415 1.2E+02 8.2E-01 ! $ll@[$ 1.5E+00 1.0E-02 Values must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rate in mR/hr.
| |
| l l
| |
| l I
| |
| 4 i
| |
| r l
| |
| l a 7- __ ___ +~+
| |
| | |
| . . _ . . . . . _ _ . . _ _ . _ _ . . . _ ~ . . _ . _ _ ._. .m . . . - - . _ _ -
| |
| R:VO Page 9.4.3.A 1 i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.4.3 REACTOR BUILDING DATA A. Building Air Concentrations (uCl/cc): 218' and 232' Elevations Isotope Prior to 1220 1220- 1230 1230-1245 1245- 1300
| |
| ( l-131 2.5E-03 5.9E-03 7.7E-03 1-132 1.9E-03 '4.6E-03 5.9E-03 1-133 4.7E-03 1.1 E-02 1.4E-02 1-134 1.0E-03 2.4E-03 3.1 E-03 1-135 3.8E-03 8.9E-03 1.2E-02 i
| |
| Totallodine
| |
| * 1.4E-02 3.3E-02 4.3E-02 1-131 D.E. 4.2E-03 9.8E-03 1.3E-02 Kr-83m 1.0E-02 2.4E-02 3.2E-02 ~
| |
| Kr-85m 2.6E-02 6.0E-02 7.8E-02 Kr-85 1.4E-03 3.4E-03 4.4E-03 Kr-87 3.0E-02 7.1 E-02 9.3E-02 Kr-88 5.9E-02 1.4E-01 1.8E-01 Xe-131m 8.1 E-04 1.9E-03 2.5E-03 Xe-133m 7.4E-03 1.7E-02 2.3E-02 l Xe-133 2.5E-01 5.9E-01 7.7E-01 Xe-135m 5.8E-03 1.4E-02 1.8E-02 Xe-135 5.7E-02 1.3E-01 1.8E-01 Xe-138 7.3E-02 1.7E-01 2.2E-01 Total Noble Gas 5.3E-01 1.2E+00 1.6E+00 l l
| |
| \
| |
| l '
| |
| l l
| |
| (*) Indicates activity concentration below MDL i
| |
| l
| |
| | |
| Rav 0 Page 9.4.3.A-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.4.3 REACTOR BUILDING DATA A. Building Air Concentrations (uCl/cc); 218' and 232' Elevations isotope 1300-1320 1320-1330 1330-1415 l-131 8.3E-03 8.1 E-03 7.4E-03 1-132 6.5E-03 6.3E-03 5.7E-03 1-133 1.6E-02 1.5E-02 1.4E-02 1-134 3.4E-03 3.3E-03 3.0E-03 1-135 1.3E-02 1.2E-02 1.1 E-02 Totallodine 4.6E-02 4.5E-02 4.1E-02 1-131 D.E. 1.4E 02 1.3E-02 1.2E-02 Kr-83m 3.5E-02 4.6E-03 3.1E-02 -
| |
| Kr-85m 8.5E-02 9.8E-02 7.6E-02 Kr-85 4.7E-03 1.9E-01 4.2E-03 l Kr-87 1.0E-01 2.6E-03 8.9E-02 l Kr-88 2.0E-01 2.4E-02 1.7E-01 Xe-131m 2.7E-03 8.2E-01 2.4E-03 Xe-133m 2.5E-02 1.9E-02 2.2E-02 Xe 133 8.4E-01 1.8E-01 7.5E-01 Xe-135m 1.9E-02 2.3E-01 1.7E-02 Xe-135 1.9E-01 1.7E+00 1.7E-01 Xe-138 2.4E-01 2.3E-01 2.1E-01 Total Noble Gas 1.7E+00 3.5E+00 1.5E+00 l
| |
| (*) Indicates activity concentration below MDL l j
| |
| s O I
| |
| | |
| , . _ _ _. __ -.. ...m -_ . _ . _ _ . _ _ _ _ - . _ _ _ . _ _ _ . _ . . _ . - m _ . _ . _ . . . . _ _ _ . _ . . _ _ _ . . _ . - . _ .
| |
| Riv 0 Pags 9.4.3.B 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 l 9.4.3 REACTOR BUILDING DATA B. Building Air Concentrations (uCl/cc): 252' Elevation l Isotope Prior to 1220 1220-1230 1230-1245 1245-1300 i 1-131 7.5E-05 3.2E-04 5.7E-04 1-132 5.8E-05 2.4E-04 4.4E-04 l-133 1.4E-04 5.9E-04 1.1E-03 1-134 3.0E-05 1.3E-04 2.3E-04 l-135 1.1E-04 4.7E-04 8.5E-04 Totallodine 4.1E-04 1.8E-03 3.1 E-03 1-131 D.E.
| |
| 1.2E-04 5.3E-04 9.4E-04 l
| |
| l Kr-83m 3.1E-04 1.3E-03 2.4E-03 Kr-85m 7.6E-04 3.2E-03 5.8E-03 Kr-85 4.2E-05 1.8E-04 3.2E-04 Kr-87 9.0E-04 3.8E-03 6.8E-03 Kr-88 1.8E-03 7.4E-03 1.3E-02 Xe-131m 2.4E-05 1.0E-04 1.8E-04 Xe-133m 2.2E-04 9.3E-04 1.7E-03 ;
| |
| Xe-133 7.5E-03 3.2E-02 5.7E-02 Xe-135m 1.7E-04 7.2E-04 1.3E-03 Xe-135 1.7E-03 7.2E-03 1.3E-02 Xe-138 2.2E-03 9.1E-03 1.6E-02 Total Noble Gas 1.6E-02 6.6E-02 1.2E-01 i
| |
| I
| |
| ! (*) Indicates activity concentration below MOL.
| |
| l l
| |
| t i
| |
| | |
| - - .__ ~ _ . . .
| |
| Riv 0 Page 9.4.3.B-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.4.3 REACTOR BUILDING DATA B. Building Air Concentrations (uCl/cc): 252' Elevation Isotope 1300-1320 1320-1330 1330-1415 l-131 6.7E-04 6.5E-04 6.0F-04 l-132 5.2E-04 5.1 E-04 4.6E-04 2 1-133 1.3E-03 1.2E-03 1.1 E-03 l-134 2.8E-04 2.7E-04 2.4E-04
| |
| < 1-135 1.0E-03 9.8E-04 9.0E-04 Tote iodine 3.7E-03 3.6E-03 3.3E-03 i 1.1 E-03 1.1 E-03 1.0E-03
| |
| _ _'_'' 1 D.E.
| |
| Kr-83m 2.8E-03 2.7E-03 2.5E-03 4 Kr-85m 6.9E-03 6.7E-03 6.1 E-03 Kr-85 3.8E-04 3.7E-04 3.4E-04 Kr-87 8.1 E-03 7.9E-03 7.2E-03 Kr-88 1.6E-02 1.5E-02 1.4E-02 Xe-131m 2.2E-04 2.1 E-04 1.9E-04 Xe-133m 2.0E 03 1.9E-03 1.8E-03 Xe-133 6.8E-02 6.6E-02 6.0E-02 Xe-135m 1.5E-03 1.5E-03 1.4E-03 Xe-135 1.5E-02 1.5E-02 1.4E-02 Xe-138 1.9E-02 1.9E-02 1.7E-02 Total Noble Gas 1.4E-01 1.4E-01 1.2E-01
| |
| (*) Indicates activity concentration below MDL.
| |
| | |
| i Rev0 Page 9.4.3.C-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.4.3 REACTOR BUILDING DATA l C. Building Air Concentrations (uCi/cc): 280' and 303' Elevations Isotope Prior to 1220 1220-1230 1230-1245 1245-1300 1-131 1.2E-04 5.4E-04 1.1 E-03 1-132 9.6E-05 4.2E-04 8.7E-04 1-133 2.3E-04 1.0E-03 2.1 E-03 )
| |
| 1-134 5.1 E-05 2.2E-04 4.6E-04 l l-135 1.9E-04 8.2E-04 1.7E-03 i t Totallodine
| |
| * 6.9E-04 3.0E-03 6.2E-03 I-131 D.E. 2.1 E-04 9.1 E-04 1.9E-03 Kr-83m 5.1 E-04 2.3E-03 4.7E-03 Kr-85m 1.3E-03 5.6E-03 1.1 E-02 Kr-85 7.0E-05 3.1 E-04 6.4E-04 ;
| |
| Kr-87 1.5E-03 6.6E-03 1.4E-02 Kr-88 2.9E-03 1.3E-02 2.6E-02 i Xe-131m 4.0E-05 1.8E-04 3.6E-04 Xe-133m 3.7E 04 1.6E-03 3.3E-03 Xe-133 1.2E-02 5.5E-02 1.1 E-01 j Xe-135m 2.8E-04 1.2E-03 2.6E-03 Xe-135 2.8E-03 1.2E-02 2.6E-02 Xe-138 3.6E-03 1.6E-02 3.2E-02
| |
| ]
| |
| Total Noble Gas 2.6E-02 1.1E-01 2.3E-01 i l
| |
| l l
| |
| (*) Indicates activity concentration below MDL. ,
| |
| I 1
| |
| l l
| |
| i i
| |
| l l
| |
| | |
| ._.. - ...- --.-..- .. -__ . . . . ~ . _ - ~ . - . - ~ . . . - . - - - - ~ . - - . . - - . - .
| |
| 1 l
| |
| e i '
| |
| 4
| |
| ' RGv 0 Page 9.4.3.C-2 VERMONT YANKEE NUCLEAR POWER STATION 4 EMERGENCY PREPAREDNESS EXERCISE 1997 1
| |
| 9.4.3 REACTOR BUILDING DATA l C. Building Air Concentrations (uCi/cc): 280' and 303' Elevations Isotope 1300-1320 1320- 1330 1330-1415 3 1-131 1.4E-03 1.4E-03 1.2E-03 4
| |
| 1-132 1.1E-03 1.0E-03 9.6E-04
| |
| ; l-133 2.6E-03 2.5E-03 2.3E-03 I 1
| |
| 3 1-134 i
| |
| 5.7E-04 5.5E-04 5.1 E-04 I
| |
| ; l-135 2.1E-03 2.0E-03 1.9E-03 j Totallodine 7.8E-03 7.5E-03 6.9E-03 i
| |
| j 1-131 D.E. 2.3E-03 2.3E-03 2.1E-03 l t
| |
| i
| |
| ; Kr-83m 5.8E-03 5.6E-03 5.1E-03 Kr-85m 1.4E-02 1.4E-02 1.3E-02 Kr-85 7.9E-04 7.7E-04 7.0E-04 Kr-87 1.7E-02 1.6E-02 1.5E-02 i Kr-88
| |
| )
| |
| 3.3E-02 3.2E-02 2.9E-02 s
| |
| i Xe-131m 4.5E-04 4.4E-04 4.0E-04 Xe-133m 4.1E-03 4.0E-03 3.7E-03 jl Xe-133 1.4E-01 1.4E-01 1.2E-01 1 Xe-135m 3.2E-03 3.1 E-03 2.8E-03 Xe-135 3.2E-02 3.1E-02 2.8E-02 Xe-138 4.0E-02 3.9E-02 3.6E-02 3 Total Noble Gas 2.9E-01 2.8E-01 2.6E-01 l
| |
| }
| |
| I i
| |
| C) Indicates activity concentration below MDL 1
| |
| | |
| . . _ . . . .. -. - _ - . - _ - . - - _ . - _ . . - . . . . _ _ - _ _ . - ~ .
| |
| R:v 0 Pagn 9.4.3.D-1
| |
| ! VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY PREPAREDNESS EXERCISE
| |
| ( 1997 l
| |
| I 9.4.3 REACTOR BUILDING DATA l
| |
| D. Building Air Concentrations (uCl/cc): 318' and 345' Elevations Isotope Prior to 1220 1220-1230 1230-1245 1245-1300 1-131 1.4E-05 5.7E-05 1.5E-04 l-132 1.1E-05 4.4E-05 1.2E-04 l-133 2.7E-05 1.1 E-04 2.9E-04 l-134 5.9E-06 2.3E-05 6.3E-05 l-135 2.2E-05 8.5E-05 2.3E-04 Total lodine 8.0E-05 3.1E-04 8.5E-04 l-131 D.E. 2.4E-05 9.4E-05 2.6E-04 i
| |
| l Kr-83m 6.0E-05 2.4E-04 6.4E-04 Kr-85m 1.5E-04 5.8E-04 1.6E-03 Kr-85 8.2E-06 3.2E-05 8.7E-05 Kr-87 1.8E-04 6.8E-04 1.9E-03 Kr-88 3.4E-04 1.3E-03 3.6E-03 Xe-131m 4.7E-06 1.8E-05 5.0E-05 Xe-133m 4.3E-05 1.7E-04 4.5E-04 Xe-133 1.5E-03 5.7E-03 1.5E-02 Xe-135m 3.3E-05 1.3E-04 3.5E-04 Xe-135 3.3E-04 1.3E-03 3.5E-03 Xe-138 4.2E-04 1.6E-03 4.4E-03 Total Noble Gas 3.0E-03 1.2E-02 3.2E-02 I (*) Indicates activity concentration below MDL.
| |
| i
| |
| | |
| Riv 0 Page 9.4.3.D-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.4.3 REACTOR BUILDING DATA D. Building Air Concentrations (uCl/cc): 318' and 345' Elevations isotope 1300-1320 1320-1330 1330-1415 l-131 2.2E-04 2.1E-04 2.0E-04
| |
| * l-132 1.7E-04 1.7E-04 1.5E-04 l-133 4.1 E-04 4.0E-04 3.7E-04 l-134 9.0E-05 8.8E-05 8.0E-05 -
| |
| l-135 3.3E-04 3.2E-04 2.9E-04 Totallodine 1.2E-03 1.2E-03 1.1E-03 1-131 D.E. 3.7E-04 3.6E-04 3.3E-04 Kr-83m 9.2E-04 8.9E-04 8.1 E-04 ,
| |
| Kr-85m 2.3E-03 2.2E-03 2.0E-03 Kr-85 1.3E-04 1.2E-04 1.1 E-04 Kr-87 2.7E-03 2.6E-03 2.4E-03 Kr-88 5.2E-03 5.0E-03 4.6E-03 Xe-131m 7.1 E-05 6.9E-05 6.3E-05 Xe-133m 6.5E-04 6.3E-04 5.8E-04 Xe-133 2.2E-02 2.2E-02 2.0E-02 Xe-135m 5.1 E-04 4.9E-04 4.5E-04 Xe-135 5.0E-03 4.9E-03 4.5E-03 Xe-138 6.4E-03 6.2E-03 5.7E-03 Total Noble Gas 4.6E-02 4.5E-02 4.1 E-02 i
| |
| j
| |
| (*) Indicates activity concentration below MDL I
| |
| O k
| |
| l L
| |
| l
| |
| | |
| - - . . . _ - - - - _ -.___ .__- .- -._---- . - . . - ~ _- ...-. - . . -
| |
| I RIv 0 Paga 9.4.3.D-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.4.3 REACTOR BUILDING DATA l D. Building Air Concentrations (uCi/cc): 318' and 345' Elevations Isotope 1300-1320 1320-1330 1330-1415 i 1-131 2.2E-04 2.1E-04 2.0E-04 !
| |
| l-132 1.7E-04 1.7E-04 1.5E-04 '
| |
| l-133 4.1 E-04 4.0E-04 3.7E-04 l-134 9.0E-05 8.8E-05 8.0E-05 l
| |
| l l-135 3.3E-04 3.2E-04 2.9E-04 l Totallodine 1.2E-03 1.2E-03 1.1E-03 1-131 D.E. 3.7E-04 3.6E-04 3.3E-04 I
| |
| Kr-83m 9.2E-04 8.9E-04 8.1E-04 ,
| |
| Kr-85m 2.3E-03 2.2E-03 2.0E-03 Kr-85 1.3E-04 1.2E-04 1.1 E-04 Kr-87 2.7E-03 2.6E-03 2.4E-03 Kr-88 5.2E-03 5.0E-03 4.6E-03 Xe-131m 7.1 E-05 6.9E-05 6.3E-05 Xe-133m 6.5E-04 6.3E-04 5.8E-04 i
| |
| ! Xe-133 2.2E-02 2.2E-02 2.0E-02 l Xe-135m 5.1 E-04 4.9E-04 4.5E-04 l '
| |
| Xe-135 5.0E-03 4.9E-03 4.5E-03 i
| |
| ! Xe-138 6.4E-03 6.2E-03 5.7E-03 j Total Noble Gas 4.6E-02 4.5E-02 4.1 E-02 j l
| |
| I
| |
| (*) Indicates activity concentration below MDL
| |
| 'i L
| |
| i --. _ .
| |
| | |
| Rev.O Page 9.4.3.E-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE I 1997 I
| |
| l 9.4.3 REACTOR BUILDING DATA 1
| |
| E. Reactor Building Sample Dose Rates (lodine Cartridge Only) 1 Unshielded g Shielded (1 inch lead)
| |
| (mR/hr per cc)* W (mR/hr per cc)*
| |
| Time Elevation Contact 1 ft '
| |
| , Contact 1 ft Prior to 1220 213'/232' As Read As Read & As Read As Read !
| |
| 252' As Read As Read - E As Read As Read i 280'/303' As Read As Read W As Read As Read i 318'/345' As Read As Read Y As Read As Read 1220- 1330 213'/232' 4.61E-01 3.20E-03 .... 5.69E-03 4.01E-05 252' 3.40E-02 2.36E-04 3 4.20E-04 2.96E-06 280'/303' 6.74E-02 4.68E-04 2 8.32E-04 5.86E-06 1 318'/345' 9.21E-03 6.40E-05 7 1.14E-04 8.01E-07 1330-1415 213'/232' 4.44E-01 3.09E-03 g 5.49E-03 3.86E-05 252' 3.59E-02 2.49E-04 g 4.43E-04 3.12E-06 280'/303' 7.44E-02 5.17E-04 9.19E-04 6.47E-06 318'/345' 1.18E-02 8.18E-05 3 1.45E-04 1.02E-06
| |
| * Value must be multiplied by the sample volume in cc to obtain the sample dose rate in mR/hr.
| |
| i l
| |
| 1 l
| |
| | |
| l I
| |
| l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.5 PLANT VENT STACK DATA l
| |
| k
| |
| | |
| . . - - . - . . _ - . _ . - . - - . . ~ . - ~ ~ - . _ - _ - . - . _ - - - _ _ _ . - . . - . - _ - . .
| |
| Rev 0 Page 9.5.-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.5 PLANT VENT STACK DATA
| |
| \
| |
| l A. Plant Vent Stack Activity Concentrations (uCi/cc)*
| |
| l Isotope Prior to 1225 1225-1230 1230-1245 1245-1300 1300-1325 1325-1530 1330-1415 l-131 3.3E-13 8.3E-08 2.1 E-07 2.9E-07 3.2E-07 3.1E-07 2.9E-07 l-132 4.8E-13 6.4E-08 1.6E-07 2.2E-07 2.5E-07 2.4E-07 2.2E-07 l-133 7.5E-13 1.6E-07 3.9E-07 5.4E-07 6.1 E-07 5.9E-07 5.4E-07 l-134 6.6E-13 3.4E 8.5E-08 1.2E-07 1.3E-07 1.3E-07 1.2E-07 l-135 6.3E-13 1.2E-07 3.1 E-07 4.4E-07 4.9E-07 4.7E-07 4.3E-07
| |
| ! Totallodine 2.9E-12 4.6E-07 1.2E-06 1.6E-06 1.8E-06 1.7E-06 1.6E-06
| |
| ! l-131 D.E. 6.1 E-13 1.4E-07 3.5E-07 4.8E-07 5.4E-07 5.2E-07 4.8E-07 Kr-83m "
| |
| 3.4E-04 8.6E-04 1.2E-03 1.3E-03 1.3E-03 1.2E-03 Kr-85m "
| |
| 8.5E-04 2.1 E-03 3.0E-03 3.3E-03 3.2E-03 2.9E-03 l
| |
| l- Kr-85 "
| |
| 4.7E-05 1.2E-04 1.6E-04 1.8E-04 1.8E-04 1.6E-04 Kr-87 "
| |
| 1.0E-03 2.5E-03 3.5E-03 3.9E-03 3.8E-03 3.5E-03 Kr-88 "
| |
| 2.0E-03 ' 4.9E-03 6.8E-03 7.6E-03 7.4E-03 6.7E-03 Xe-131m "
| |
| 2.7E-05 6.7E-05 9.3E-05 1.0E-04 1.0E-04 9.3E-05 l
| |
| i Xe-133m "
| |
| 2.5E-04 6.1 E-04 8.6E-04 9.6E-04 9.3E-04 8.5E-04 Xe-133 "
| |
| 8.4E-03 2.1E-02 2.9E-02 3.3E-02 3.2E-02 2.9E-02 Xe-135m "
| |
| 1.9E-04 4.8E-04 6.6E-04 7.4E-04 7.2E-04 6.6E-04 Xe-135 "
| |
| 1.9E-03 4.7E-03 6.6E-03 7.4E-03 7.2E-03 6.5E-03 Xe-138 2.4E-03 6.0E-03 8.4E-03 9.4E-03 9.1 E-03 8.3E-03 )
| |
| ! Total Gas "
| |
| 1.7E-02 4.3E-02 6.0E-02 6.7E-02 6.5E-02 6.0E-02 l
| |
| I l
| |
| l 4
| |
| i
| |
| :
| |
| * To convert concentration (uCl/cc) to release rate (uCi/sec) multiply by l the assumed stack flow rate.
| |
| l (0800 to 0950 - 6.6E+07cc/sec)
| |
| ' (0950 to END - 3.5E+07 cc/sec) l
| |
| " Indicates activity concentration below MDL. l l
| |
| t 4
| |
| y -++ - e e .,
| |
| | |
| Rev.0 Page 9.5-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 9.5 PLANT VENT STACK DATA B. PVS Gas sample Dose Rates (Grab Sample)
| |
| Unshielded Shielded (1 inch k-ad)
| |
| (mR/hr per ec)* (mR/hr per cc)'
| |
| Time Contact 1 ft Contact 1 ft Prior to 1225 As Read As Read z.r - As Read As Read 1225-1230 4.9E-03 3.5E-05 -. 6.1 E-05 4.4E-07 1230-1245 1.2E-02 8.6E-05 e- 1.5E-04 1.1 E-06
| |
| _ 1245-1300 1.7E-02 1.2E-04 =: 2.1E 04 1.5E-06 1.9E-02 1.3E-04 -, a 2.4E-04 1.7E-06
| |
| _ 1300-1325 1325-1330 1.9E-02 1.3E-04 -
| |
| 2.3E-04 1.6E-06 1.7E-02 1.2E-04
| |
| ~
| |
| 2.1 E-04 1.5E-06
| |
| __--- 1330-1415 C. PVS Air Sample Dose Rates (lodine Cartridge)
| |
| Unshielded Shielded (1 inch lead)
| |
| (mR/hr per cc)* (mR/hr per ec)* l Time Contact 1 ft Contact i ft Prior to 1225 As Read As Read As Read As Read 1225-1230 3.5E-07 2.5E-09 - 4.4E-09 3.1 E-11 1230-1245 8.8E-07 6.2E-09 --
| |
| 1.1 E-08 7.8E-11 1245-1300 1.2E-06 8.6E-09 1.5E-08 1.1 E-10 1300-1325 1.4E-06 9.6E-09 1.7E-08 1.2E-10 1325-1330 1.3E-06 9.4E-09 -
| |
| 1.7E-08 1.2E-10 1330-1415 1.2E-06 8.5E-09 .- 1.5E-08 1.1 E-10 D. General Area Exposure Rates at Stack (mR/hr)
| |
| Time At Stack Door inside Prior to 1225 As Read smittb iW"td As Read 1225-1230 2 MMN%sAAsda 5 1230-1245 3 emmmweteede 8 1245-1300 3 WSMJetWTTRW 10 1300-1325 5 ARNDemeu 15 1325-1330 3 E5efSENSMFMMt 10 1330-1415 3 [EQMEMQgd?O 8
| |
| * Values must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rates in mR/hr.
| |
| | |
| -2 -> - a - -~.a-.-.sw.-a .- s.-a-- - ..-.~.-re---- - - . . -- - -n --+aun+- . . -
| |
| I i j VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY PREPAREDNESS EXERCISE 1997 1 9.6 FIELD MONITORING MAPS AND DATA
| |
| | |
| Rev. O Page 9.6-1 )
| |
| l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1997 l
| |
| l M FIntB MONITORING MAPS AND DATA Plume gn=na 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 (HETPAC). Geographical representations l of the plume are provided in this section for each 15 minute average of the meteorological conditions, starting at clock time 1230 (scenario time 04'30).
| |
| : 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 which is equivalent to a 3-sigma value of the centerline conditions.
| |
| 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 Conunonwealth 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 the figure for a given scenario time period.)
| |
| Radiological data on 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.
| |
| F
| |
| | |
| _ m _ _ _ . - _ __ _ . . _ . _ _ _ _ _ _ _ . _ . . . .____ _-__ . _ _ _
| |
| 1 l
| |
| I f
| |
| Rev. O Page 9.6-2 Prior to the exercise, training will be provided to Controllers on the use of the figures and tables. The Controllers should use the following specific instructions:
| |
| l
| |
| : 1. As field monitoring teams are designated , check that the appropriate procedures are followed by team members. This will include the initial equipment check.
| |
| : 2. While traveling to assigned 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 opent in an affected area. Use the values provided for the PIC-6 or the closed window, waist level reading for the gamma dose rate. Do not issue pocket dosimeter results to team meinbers, j unless they actually simulate checking their dosimeter reading. The pocket dosimeters have specific ranges and intervals in mR or R l
| |
| 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 their use. Ask them the scales associated with the equipment; log the l
| |
| i answers to ensure that you do not provide them with data which is not consistent with the range of the equipment. If a situation occurs where the lower range or upper range of the equipment is exceeded, issue them an "off-scale low" value and "off-scale high" value, l
| |
| I respectively.
| |
| : 5. For gamma (dose rates) survey readings taken by field monitoring teams, the following information should be uses
| |
| : a. If an RM-14/HP-210 is used to track the plume, the meter count ,
| |
| rate of 3,500 cpm on the RM-14/HP-210 is equivalent to )
| |
| I approximately 1.0 mR/hr. Therefore, 14 mR/hr will cause the l RM-14/HP-210 to read "off-scale high." The upper range of the RM-14/HP-210 is 50,000 cym.
| |
| 1 i
| |
| 1
| |
| [
| |
| | |
| Rev. O Page 9.6-3
| |
| : b. Whenever a team takes a " ground level" survey, the results should be the same as the " waist level" survey.
| |
| l l c. Certain field monitoring teams may take open window mig closed l window readings with their dose rate survey meters. If a team is
| |
| ! located in the plume and air 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 uses
| |
| : a. The field monitoring teams will substitute a charcoal cartridge instead of the absorber media cartridge (silver zeolite) l I
| |
| contained in the field monitoring kits. All air sample data will )
| |
| l be given as though the absorber media cartridges (silver zholite) )
| |
| were being used in the kits. )
| |
| l
| |
| [ b. Air sample volume assumptions have been used in the calculation of the not count rates for the air sample results. The sample I volume was assumed to be 100 liters and 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 different volumes are collected, the air sample data provided in the tables should be adjusted proportionally.
| |
| : c. Air sample not count rates for the adsorber media cartridges (silver zeolite) provided in the field data tables have been developed using METPAC thyroid dose rate projections. The i
| |
| formula used is as follows: ,
| |
| Conc. (uCi/cc), netcpmxC nversi nFactor ExFxT where: E= Instrument Detector Efficiency in cpm /dpm (counts per I disintegration)
| |
| I F= Flow rate of sample in Ipm or efm T= sample collection time in minutes
| |
| . CF = Conversion Factor (4.5 E-10 pCi-liter /dpm-ce for flow
| |
| ! rate in Ipm QB 1.6 E-11 pCI-f t /dpe-cc for flow rate in 3
| |
| cfm
| |
| | |
| . . . . __ .. - . . . . ._ ~ . . _ - . _ . ... ._-
| |
| Rev. O Parf: 9.6-4
| |
| : 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 f sample count rates. Filter count rates (cpm) were estimated from l the radioiodine 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 i
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| O l
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| i 2
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| L_-____-.-.__
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| PAGE 9.6-5
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| TABLE 9.6.1 Rev.O Page 9.6-5a ON SITE VERMONT YANKEE FIELD DATA AIR SAMPLE DATA * (RM-14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE CONC. 100 L 10 CF FILTER"'
| |
| MAP PIC-6 RM-14 1-131 SILVER ZEOLITE CLOCK (CPM) (uCl/cc) (NET CPM) (NET CPM) (NET CPM)
| |
| TIME ARGA (mR/hr) 1054 0.00E+00 <40 <40 <40 1230-1245 BLUE <1 0.00E+00 <40 <40 ~< 40 YELLOW <1 AS READ AS READ 0.00E+00 <40 <40 <40 GREEN <1 1964 0.00E+00 <40 <40 <40 1245 .300 BLUE <1 f YELLOW <1 196 0.00E+00 <40 <40 <40 AS READ 0.00E+00 <40 <40 <40 GREEN <1
| |
| <1 3035 0.00E+00 <40 <40 <40 1300-1315 BLUE 303 0.00E+00 <40 <40 <40 YELLOW <1
| |
| <1 AS READ 0.00E+00 <40 <40 <40 GREEN 3850 0.00E+00 <40 <40 <40 1315-1330 BLUE 1
| |
| <1 385 0.00E+00 <40 <40 <40 YELLOW AS READ 0.00E+00 <40 <40 <40 GREEN <1 3780 0.00E+00 <40 <40 <40 1330-1345 BLUE 1
| |
| <1 378 0.00E+00 <40 <40 <40 YELLOW AS READ 0.00E+00 <40 <40 <40 GREEN <1 3710 0.00E400 <40 <40 <40 1345-1400 BLUE 1 371 0.00E+00 <40 <40 <40 YELLOW <1 AS READ 0.00E+00 <40 <40 <40 GREEN <1 3675 0.00E+00 <40 <40 <40 1400 1415 BLUE 1
| |
| <1 36'8 0.00E+00 <40 <40 <40 YELLOW
| |
| <1 37 0.00E+00 <40 <40 <40 GREEN 3640 0.00E+00 <40 <40 <40 1415-1430 BLUE 1
| |
| <1 364 0.03E+00 <40 <40 <40 YELLOW 36 0.COE+00 <40 <40 <40 GREEN <1 NOTES:
| |
| * Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, 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 0.025 cpm /dpm with the silver zoollte cartridge.
| |
| '" The particulate filter sample count rate (cpm) was estimated in. .i the I 131 air concentrations for a 100 liter sample.
| |
| | |
| Rev. O Page 9.6-5b/c/d PAGES INTENTIONALLY LEFT BLA K NOTE: VERMONT, MASSACHUSETTS AND NEW HAMPSHIRE FIELD TEAM MONITORING DATA IS NOT REQUIRED FOR ONSITE (PROTECTED AREA) PLANT SURVEYS.
| |
| 9 l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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| TABLE 9.6.22 Rev.O P ge 9.6-62 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1230-1245 (SCENARIO TIME 0430-0445)
| |
| AIR SAMPLE DATA * (RM-14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER *"
| |
| SEGMENT DISTANCE MAP PIC-6 RM 14 I-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCl/cc) (NET CPM) (NET CPM) (NET CPM) 1.00 SITE BLUE <1 1159 4.60E-21 <40 <40 <40 BOUNDARY YELLOW <1 116 4.60E 22 <40 <40 <40 GREEN <1 12 4.60E-23 <40 <40 <40 2.00 0.80 BLUE <1 1841 5.42E 11 <40 <40 <40 YELLOW <1 184 5.42E-12 <40 <40 <40 GREEN <1 18 5.42E-13 <40 <40 <40 3.00 1.50 BLUE <1 1855 4.34E 10 <40 <40 <40 YELLOW <1 186 4.34E-11 <40 <40 ,
| |
| <40 GREEN <1 19 4.34E 12 <40 <40 <40 l
| |
| NOTES:
| |
| * Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionalty. For example, if a 50 liter sample was collected instead of 100 liters, 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 0.025 cpm /dpm with the silver zeolite cartridge.
| |
| '" The particulate filter sample count rate (cpm) was estimated from the I-131 air concentrations for a 100 liter sample.
| |
| I L
| |
| l
| |
| | |
| I TABLE 9.6.2b Rev.O !
| |
| PCge 9.6-6b l
| |
| STATE OF VERMONT FIELD DATA AT CLOCK TIME 1230-1245 (SCENARIO TIME 0430-0445) j GAMMA SURVEY DATA l 7
| |
| AIR SAMPLE DATA (354 LITERS)*
| |
| WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G-M METER PLUME CLOSED OoEN CONC. AGX-2" PARTICULATE" SEGMENT DISTANCE MAP WINDOW WINDOW 1-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCi/cc) (NET CPM) (NET CPM) 4 1.00 SITE BLUE 0.33 0.66 4.60E-21 AS READ AS P.EAD ;
| |
| ; BOUNDARY YELLOW 0.03 0.07 4.60E-22 AS READ AS READ GREEN AS READ AS READ 4.60E-23 AS READ AS READ l l
| |
| AS READ AS READ !
| |
| 2.00 0.80 BLUE 0.53 1.05 5.42E-11 YELLOW 0.05 0.11 5.42E-12 AS READ AS READ f j GREEN AS READ AS READ 5.42E 13 AS READ AS READ i
| |
| 3.00 1.50 BLUE 0.53 1.06 4.34E 10 AS READ AS READ YELLOW 0.05 0.11 4.34E 11 AS READ AS READ GREEN AS READ AS READ 4.34E 12 AS READ "
| |
| AS READ NOTES:
| |
| Air sample data are based on a sample volume of 354 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was collected instead of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The Ludlum 2220 detector efficiency for 1-131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge.
| |
| * Fcr analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the I-131 air concentrations for a 354 liter sample volume.
| |
| | |
| TABLE 9.6.2c Rev.O Page 9.6-6c STATE OF MA FIELD DATA AT CLOCK TIME 1230-1245 (SCENARIO TIME 0430-0445) g GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP 210 G-M METER
| |
| _ PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE"*
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW I-131 CARTRIDGE FILTER NO. (M!LES) AREA (mR/hr) (mR/hr) (uCi/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 0.33 0.66 4.60E 21 AS READ AS READ BOUNDARY YELLOW AS READ AS READ 4.60E-22 AS READ AS READ GREEN AS READ AS READ 4.60E 23 AS READ AS READ 2.00 0.80 BLUE 0.53 1.05 5.42E 11 AS READ AS READ YELLOW 0.05 0.11 5.42E 12 AS READ AS READ GREEN AS READ AS READ 5.42E 13 AS READ AS READ 3.00 1.50 BLUE 0.53 1.06 4.34E 10 AS READ AS READ YELLOW 0.05 0.11 4.34E 11 AS READ AS READ GREEN AS READ AS READ 4.34E-12 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 20 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For exarrple, if a 10 cu ft, sample was collected instead of 20 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| The E 140/HP-210 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The fitter count rate was estimated from the I-131 air concentrations for a 20 cubic foot sample volume.
| |
| | |
| I TABLE 9.6.2d Rev. O Page 9.6-6d STATE OF NH FIELD DATA AT CLOCK TIME 1230-1245 (SCENARIO TIME 0430-0445)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP-210 G-M METER PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| f SEGMENT DISTANCE MAP WINDOW WINDOW l-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) l l
| |
| 1.00 SITE BLUE 0.33 0.66 4.60E-21 AS READ AS READ l BOUNDARY YELLOW AS READ AS READ 4.60E-22 AS READ AS READ GREEN AS READ AS READ 4.60E 23 AS READ AS READ 2.00 0.80 BLUE 0.53 1.05 5.42E-11 AS READ AS READ YELLOW 0.05 0.11 5.42E-12 AS READ AS READ GREEN AS READ AS READ 5.42E 13 AS READ AS READ I
| |
| l 3.00 1.50 BLUE 0.53 1.06 4.34E-10 AS READ AS READ l YELLOW 0.05 0.11 4.34E 11 AS READ AS READ f GREEN AS READ AS READ 4.34E-12 AS READ AS READ l
| |
| NOTES:
| |
| Air sample data are based on a sample volume of 10 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example,if a 5'cu ft. sample was collected instead of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E 140/HP 210 detector efficiency for l 131 was assumed to be 0.0025 cpm /dpm with the AGX-2 cartridge.
| |
| "* For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| l The filter count rate was estimated from the 1-131 air concentrations for a 10 cubic foot sample volume.
| |
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| |
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| |
| /
| |
| > '' h g g 4
| |
| , . I'go -;s s %. 3
| |
| . g' 've **
| |
| CLOCK TIME: 1245 to 1300 y . ,,
| |
| ""/f, f')
| |
| | |
| R;v. O TABLE 9.6.32 Page 9.6-7a VERMONT YANKEE FIELD DATA AT CLOCK TIME 1245-130'0 (SCENARIO TIME 0445-0500)
| |
| AIR SAMPLE DATA' (RM-14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE CONC. 100 L 10 CF FILTER *"
| |
| PLUME SEGMENT DISTANCE MAP PIC-6 RM 14 l-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCl/cc) (NET CPM) (NET CPM) (NET CPM) ;
| |
| l
| |
| <1 2160 1.22E-20 <40 <40 <40 1.00 SITE BLUE
| |
| <1 216 1.22E-21 <40 <40 <40 BOUNDARY YELLOW
| |
| <1 22 1.22E-22 <40 <40 <40 l GREEN l
| |
| <1 3423 1.17E-10 <40 <40 <40 2.00 0.80 BLUE
| |
| <1 342 1.17E 11 <40 <40 <40 YELLOW 34 1.17E-12 <40 <40 <40 GREEN <1 3385 8.00E 10 <40 <40 <40 3.00 1.60 BLUE <1 338 8.00E-11 <40 <40 <40 YELLOW <1 34 8.00E-12 <40 <40 <40 GREEN <1 BLUE <1 1236 2.95E 10 <40 <40 <40 4.00 2.40 YELLOW <1 124 2.95E 11 <40 <40 <40 GREEN <1 12 2.95E 12 <40 <40 <40
| |
| <1 942 2.45E-10 <40 <40 <40 5.00 3.10 BLUE YELLOW <1 94 2.45E 11 <40 <40 <40
| |
| <1 9 2.45E 12 <40 <40 <40 GREEN 1
| |
| NOTES:
| |
| * Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sr.xipler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, '
| |
| 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 0.025 cpm /dpm with the silver zeolite cartridge.
| |
| "* The particulate filter sample count rate (cper) was estimated from the 1 131 air concentrations for a 100 liter sample, t
| |
| b l
| |
| | |
| TABLE 9.6.3b Rev. O Page 9.6-7b STATE OF VERMONT FIELD DATA AT CLOCK TIME 1245-1300 (SCENARIO TIME 0445-0500)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)*
| |
| LUDLUM 2220 G-M METER WAIST AND GROUND LEVEL READINGS CLOSED OPEN CONC. AGX-2" PARTICULATE"'
| |
| PLUME WINDOW WINDOW 1-131 CARTRlDGE FILTER SEGMENT DISTANCE MAP NO. AREA (mR/hr) (mR/hr) (uCi/cc) (NET CPM) (NET CPM)
| |
| (MILES) 0.62 1.23 1.22E 20 AS READ AS READ 1.00 SITE BLUE 0.06 0.12 1.22E-21 AS READ AS READ BOUNDARY YELLOW AS READ AS READ 1.22E 22 AS READ AS READ GREEN 0.98 1.96 1.17E 10 AS READ AS READ 2.00 0.80 BLUE 0.10 0.20 1.17E 11 AS READ AS READ YELLOW AS READ AS READ 1.17E 12 AS READ AS READ GREEN 0.97 1.93 8.00E 10 50 AS READ 3.00 1.60 BLUE 0.10 0.19 8.00E 11 AS READ AS READ YELLOW AS READ AS READ 8.00E 12 AS READ AS READ GREEN l
| |
| BLUE 0.35 0.71 2.95E 10 AS READ AS READ 4.00 2.40 YELLOW 0.04 0.07 2.95E 11 AS READ AS READ AS READ AS READ 2.95E 12 AS READ AS READ GREEN 0.27 0.54 2.45E 10 AS READ AS READ 5.00 3.10 BLUE 0.03 0.05 2.45E-11 AS READ AS READ YELLOW AS READ AS READ 2.45E-12 AS READ AS READ GREEN 4
| |
| NOTES:
| |
| * Air sample data are based on a sample volume of 354 liters.11 different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was collected instead of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The Ludlum 2220 detector efficiency for I 131 was assurned to be 0.080 cpm /dpm with the AGX-2 cartridge.
| |
| '" For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The fitter count rate was estimated from the 1 131 air concentrations for a 354 liter sample volume.
| |
| | |
| TABLE 9.6.3c R;v. O PIge 9.6-7c STATE OF MA FlELD DATA AT CLOCK TIME 1245-1300 (SCENARIO TIME 0445-0500)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| E 140/HP-210 G-M METER WAIST AND GROUND LEVEL READINGS CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| PLUME MAP WINDOW WINDOW 1-131 CARTRIDGE FILTER SEGMENT DISTANCE AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| NO. (MILES)
| |
| BLUE 0.62 1.23 1.22E-20 AS READ AS READ 1.00 SITE 0.06 AS READ 1.22E-21 AS READ AS READ BOUNDAR1' YELLOW AS READ AS READ 1.22E-22 AS READ AS READ GREEN BLUE 0.98 1.96 1.17E 10 AS READ AS READ 2.00 0.80 YELLOW 0.10 AS READ 1.17E 11 AS READ AS READ GREEN AS READ AS READ 1.17E 12 AS READ AS READ 0.97 1.93 8.00E-10 AS READ AS READ 3.00 1.60 BLUE YELLOW 0.10 AS READ 8.00E-11 AS READ AS READ GREEN AS READ AS READ 8.00E-12 AS READ AS READ BLUE 0.35 0.71 2.95E 10 AS READ AS READ 4.00 2.40 YELLOW AS READ AS READ 2.95E 11 AS READ AS READ GREEN AS READ AS READ 2.95E-12 AS READ AS READ BLUE 0.27 0.54 2.45E-10 AS READ AS READ 5.00 3.10 YELLt J AS READ AS READ 2.45E-11 AS READ AS READ GREEN AS READ AS READ 2.45E-12 AS READ AS READ l
| |
| l l
| |
| NOTES:
| |
| Air sample data are based on a sample volume of 20 cu ft. If different . c'umes are collected, the air sample data
| |
| ^
| |
| provided in the tables should be adjusted proportionally. For example,if a 10 ;u ft. sample was collected instead of 20 cu ft, divide the value given in the table by two (2) and provide the resut.ing value to the players.
| |
| " The E 140/HP 210 detector efficiency for I-131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| '" For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 20 cubic foot sample volume.
| |
| | |
| - + . . u a +.-.- 2s _
| |
| TABLE 9.6.3d Rev. O Pzge 9.6-7d STATE OF NH FIELD DATA AT CLOCK TIME 1245-1300 (SCENARIO TIME 0445-0500) 4 GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP 210 G-M METER
| |
| $ PLUME CLOSED OPEN CONC. AGX-2** PARTICULATE *"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW l-131 CARTRIDGE FILTER
| |
| , NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/ce) (NET CPM) (NET CPM) 1.00 SITE BLUE 0.62 1.23 1.22E-20 AS READ AS READ BOUNDARY YELLOW 0.06 AS READ 1.22E 21 AS READ AS READ GREEN AS READ AS READ 1.22E 22 AS READ AS READ 2.00 0.80 BLUE 0.98 1.96 1.17E 10 AS READ AS READ
| |
| . YELLOW 0.10 AS READ 1.17E 11 AS READ AS READ GREEN AS READ AS READ 1.17E-12 AS READ AS READ I
| |
| 3.00 1.60 BLUE 0.97 1.93 8.00E-10 AS READ AS READ YELLOW 0.10 AS READ 8.00E 11 AS READ AS READ GREEN AS READ AS READ 8.00E 12 AS READ AS READ i
| |
| - l 4.00 2.40 BLUE 0.35 0.71 2.95E-10 AS READ AS READ l I
| |
| YELLOW AS READ AS READ 2.95E 11 AS READ AS READ GREEN AS READ AS READ 2.95E-12 AS READ AS READ 5.00 3.10 BLUE 0.27 0.54 2.45E 10 AS READ AS READ YELLOW AS READ AS READ 2.45E-11 AS READ AS READ GREEN AS READ AS READ 2.45E-12 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 10 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cu ft sample was collected instead of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E-140/HP 210 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates. l The filter count rate was estimated from the 1131 air concentrations for a 10 cubic foot sample volume.
| |
| l 4
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| = 5-
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| FIGURE 9.6-4
| |
| ,* 1*
| |
| m .e ( '~,I r- :,,
| |
| \
| |
| : g. s s .. . ::. -
| |
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| ? I 1~ ,e %, ~.--< , , , CLOCK TIME: 1300 to 1315 i- J 1
| |
| ,,- G ill ," ..
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| % ,, . , .r.? . ?! ... c " Al;f . -
| |
| +- ?- i
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| - . . - - . - . .~. . . . - - . . _ _ . . _ . . _ , . . _ _ _ ,
| |
| TABLE 9.6.4a Rev. O Page 9.6-8a J
| |
| VERMONT YANKEE FIELD DATA AT CLOCK TIME 13001315 (SCENARIO TIME 0500-0515) l AIR SAMPLE DATA * (RM 14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE {
| |
| CONC. 100 L 10 CF FILTER *" )
| |
| PLUME MAP PIC-6 RM 14 l131 SILVER ZEOLITE SEGMENT . DISTANCE NO. (MILES) AREA (mRMr) (CPM) (uCi/oc) (NET CPM) (NET CPM) (NET CPM) 1
| |
| <1 3336 2.18E-20 <40 <40 <40 '
| |
| 1.00 SITE BLUE
| |
| <1 334 2.18E 21 <40 <40 <40 BOUNDARY YELLOW
| |
| <1 33 2.18E-22 <40 <40 <40 l GREEN 1 l
| |
| BLUE 2 5285 1.94E 10 <40 <40 .:40 l 2.00 0.80 YELLOW <1 529 1.94E 11 <40 <40 <40 GREEN <1 53 1.94E-12 <40 <40 <40 2
| |
| BLUE 5110 1.21 E-03 <40 <40 <40 l 3.00 1.60 1 YELLOW <1 511 1.21E 10 <40 <40 <40 GREEN <1 51 1.21E 11 <40 <40 <40 4.00 2.40 BLUE <1 2226 5.33E-10 <40 <40 <40 f YELLOW <1 223 5.33E 11 <40 <40 <40 GREEN <1 22 5.33E-12 <40 <40 <40 l
| |
| J 1712 4.44E 10 <40 <40 <40 5.00 320 BLUE <1 YELLOW <1 171 4.44E 11 <40 <40 <40 GREEN <1 17 4.44E 12 <40 <40 <40 BLUE <1 676 1.45E 10 <40 <40 <40 6.00 4.00 YELLOW <1 68 1.45E-11 <40 <40 <40 GREEN <1 7 1.45E-12 <40 <40 <40 BLUE <1 557 1.23E-10 <40 <40 <40 7.00 4.80 YELLOW <1 56 1.23E-11 <40 <40 <40 GREEN <1 6 1.23E-12 <40 <40 <40 NOTES:
| |
| * Air sample data are based on a sample volume of 100 hters for the Monroe sampler and 10 cubic feet for the Radeco sampler.11 different volumes are collected, the air sartple data provided in the tables should be adjusted proportionally. Foi example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The RM 14 detector officiency for I 131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge.
| |
| I
| |
| "* The particulate filter sample count rate (epm) was estimated from the I-131 air concentrations for a 100 liter sample.
| |
| | |
| TABLE 9.6.4b Rav. O PIge 9.6-8b STATE OF VERMONT FIELD DATA AT CLOCK TIME 13001315 (SCENARIO TIME 0500-0515) i GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)* f LUDLUM 2220 G-M METER l WAIST AND GROUND LEVEL READINGS CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| PLUME WINDOW WINDOW I131 CARTRIDGE FILTER SEGMENT DISTANCE MAP AREA (mR/hr) (mR/hr) (uCi/cc) (NET CPM) (NET CPM)
| |
| NO. (MILES) 1 0.95 1.91 2.18E-20 AS READ AS READ 1.00 SITE BLUE 0.10 0.19 2.18E-21 AS READ AS READ BOUNDARY YELLOW AS READ AS READ 2.18E 22 AS READ AS READ GREEN 1
| |
| 1.51 3.02 1.94E-10 AS READ AS READ 2.00 0.80 BLUE 0.15 0.30 1.94E 11 AS READ AS READ l YELLOW GREEN AS READ AS READ 1.94E 12 AS READ AS READ t
| |
| 1.46 2.92 1.21 E-09 76 AS READ 3.00 1.60 BLUE 0.15 0.29 1.21E 10 AS READ AS READ YEU OW AS READ AS READ 1.21 E-11 AS READ AS READ GREEN BLUE 0.64 1.27 5.33E 10 AS READ AS READ 4.00 2.40 0.06 0.13 S.33E 11 AS READ AS READ YELLOW l GREEN AS READ AS READ 5.33E 12 AS READ AS READ BLUE 0.49 0.98 4.44E 10 AS READ AS READ 5.00 3.20 YELLOW 0.05 0.10 4.44c 11 AS READ AS READ GREEN AS READ AS READ 4.44E 12 AS READ AS READ BLUE 0.19 0.39 1.45E-10 AS READ AS READ 6.00 4.00 YELLOW 0.02 0.04 1.45E-11 AS READ AS READ GREEN AS READ AS READ 1.45E-12 AS READ AS READ BLUE 0.16 0.32 1.23E 10 AS READ AS READ 7.00 4.80 0.02 0.03 1.23E-11 AS READ AS READ YELLOW GREEN AS READ AS READ 1.23E 12 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 354 liters, if different volumes are collected, the air sarrple data provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was collected instead of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The Ludlum 2220 detector efficiency for l-131 was assumed to be 0.080 cpm / dom with the AGX-2 cartridge.
| |
| '" For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rats was estimated from the 1-131 air concentrations for a 354 liter sample volume.
| |
| | |
| TABLE 9.6.4c Rev.O Pige 9.6-8c STATE OF MA FIELD DATA AT CLOCK TIME 1300-1315 (SCENARIO TIME 0500-0515) l GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E-140/HP 210 G-M METER l PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE *" )
| |
| FILTER I SEGMENT DISTANCE MAP WINDOW WINDOW 1-131 CARTRIDGE NO. (MILES) AREA (mR/hr) (mR/hr) (uCi/cc) (NET CPM) (NET CPM) 1 1.00 SITE BLUE 0.95 1.91 2.18E-20 AS READ AS READ l
| |
| BOUNDARY YELLOW 0.10 0.19 2.18E-21 AS READ AS READ ;
| |
| GREEN AS READ AS READ 2.18E 22 AS READ AS READ
| |
| {
| |
| 2.00 0.80 BLUE 1.51 3.02 1.94E-10 AS READ AS READ YELLOW 0.15 0.30 1.94E 11 AS READ AS READ GREEN AS READ AS READ 1.94E 12 AS READ AS READ l 3.00 1.60 BLUE 1.46 2.92 1.21 E-09 AS READ AS READ YELLOW 0.15 0.29 1.21 E-10 AS READ AS READ GREEN AS READ AS READ 1.21E 11 AS READ AS READ 4.00 2.40 BLUE 0.64 1.27 5.33E-10 AS READ AS READ YELLOW 0.06 0.13 5.33E-11 AS READ AS READ GREEN AS READ AS READ 5.33E 12 AS READ AS READ 5.00 3.20 BLUE 0.49 0.98 4.44E-10 AS READ AS READ YELLOW AS READ AS READ 4.44E 11 AS READ AS READ GREEN AS READ AS READ 4.44E-12 AS READ AS READ l l
| |
| 6.00 4.00 BLUE 0.19 0.39 1.45E-10 AS READ AS READ l YELLOW AS READ AS READ 1.45E-11 AS READ AS READ GREEN AS READ AS READ 1.45E-12 AS READ AS READ 4.80 BLUE 0.16 0.32 1.23E-10 AS READ AS READ 7.00 YELLOW AS READ AS READ 1.23E-11 AS READ AS READ GREEN AS READ AS READ 1.23E 12 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 20 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 10 cu ft. sample was collected instead of 20 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E 140/HP 210 detector efficiency for 1131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| "* For armlysis of the particulate filter, it is assumed that a G.M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 20 cubic foot sample volume.
| |
| | |
| \
| |
| TABLE 9.6.4d Rev. O pgge 9.6-8d STATE OF NH FIELD DATA AT CLOCK TIME 1300-1315 (SCENARIO TIME 0500-0515)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP-210 G M METER CLOSED OPEN CONC. AGX-2" PARTICULATE'"
| |
| PLUME MAP WINDOW WINDOW 1131 CARTRfDGE FILTER SEGMENT DISTANCE NO. AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| (MILES)
| |
| BLUE 0.95 1.91 2.18E-20 AS READ AS READ 1.00 SITE 0.10 0.19 2.18E-21 AS READ AS READ BOUNDARY YELLOW AS READ AS READ 2.18E 22 AS READ AS READ GREEN BLUE 1.51 3.02 1.94E-10 AS READ AS READ 2.00 0.80 0.15 0.30 1.94E-11 AS READ AS READ YELLOW GREEN AS READ AS READ 1.94E 12 AS READ AS READ 1.46 2.92 1.21 E-09 AS READ AS READ 3.00 1.60 BLUE 0.15 0.29 1.21E-10 AS READ AS READ YELLOW AS READ AS READ 1.21E 11 AS READ AS READ GREEN 0.64 1.27 5.33E 10 AS READ AS READ 4.00 2.40 BLUE 0.06 0.13 5.33E-11 AS READ AS READ YELLOW AS READ AS READ 5.33E-12 AS READ AS READ GREEN 0.49 0.98 4.44E 10 AS READ AS READ 5.00 3.20 BLUE AS READ AS READ 4.44E 11 AS READ AS READ YELLOW AS READ AS READ 4.44E 12 AS READ AS READ GREEN 0.19 0.39 1.45E-10 AS READ AS READ 6.00 4.00 BLUE AS READ AS READ 1.45E 11 AS READ AS READ YELLOW AS READ AS READ 1.45E 12 AS READ AS READ GREEN 0.32 1.23E-10 AS READ AS READ 7.00 4.80 BLUE 0.16 AS READ 1.23E 11 AS READ AS HEAD YELLOW AS READ AS READ 1.23E 12 AS READ AS READ - i GREEN AS READ NOTES:
| |
| * Air sample data are based on a sample volume of 10 cu ft. It different volumes are collected, the air sample data '
| |
| provided in the tables should be adjusted proportionally. For example,if a 5 cu ft. sample was collected instead of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E-140/HP-210 detector efficiency for 1131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| '" For analysis of the particulate filter,it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1131 air concentrations for a 10 cubic foot sample volume.
| |
| | |
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| g i ,' % 6 ,o
| |
| ' ~ ~'
| |
| t 's '
| |
| / , -
| |
| 4ym,, v - s di <
| |
| norinei -
| |
| 3 .. ,
| |
| _ _ 4 -.
| |
| 'e o
| |
| = =. --
| |
| , , .,, & 4
| |
| \, ,< ,
| |
| u
| |
| * ,' s,$ ** * /
| |
| * yS / 'E
| |
| * e % t
| |
| , ' ~sl( -
| |
| . - - ,' g
| |
| ,y !(r ., .
| |
| ~.
| |
| ,] m g,,.
| |
| . . - - # : ., *.s k FIGURE 9.6-5 p 1 s , g, # ., \: '~!'
| |
| CLOCK TmfE: 1315 to 1330 i,
| |
| ]
| |
| f ,' .,. ,- n;,gl >
| |
| ~~
| |
| \
| |
| /sr -
| |
| Of ;
| |
| S \
| |
| \
| |
| \
| |
| W '
| |
| , ,,'.r.~. !! . c ~ .J .
| |
| ~"
| |
| s.
| |
| | |
| TABLE 9.6.5a Rev,O Page 9.6-9a1 VERMONT YANKEE F: ELD DATA A'i(CLOCK TIME 13151330 (SCENARI'O TIME 0515-0530)
| |
| AIR SAMPLE DATA * (RM-14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER *"
| |
| SEGMENT DISTANCE MAP PIC-6 RM 14 I-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCi/cc) (NET CPM) (NET CPM) (NET CPM)
| |
| I 1.00 SITE BLUE 1 4200 3.28E-20 <40 <40 <40 BOUNDARY YELLOW <1 420 3.28E-21 <40 <40 <40 GREEN <1 42 3.28E-22 <40 <40 <40 2.00 0.80 BLUE 2 6650 2.62E 10 <40 <40 <40 l YELLOW <1 665 2.62E-11 <40 <40 <40 GREEN <1 67 2.62E-12 <40 <40 <40 3.00 1.60 BLUE 2 6300 1.51 E-09 <40 <40 <40 ,
| |
| YELLOW <1 630 1.51E 10 <40 <40 <40 ii GREEN <1 63 1.51E 11 <40 <40 <40 l
| |
| 4.00 2.50 BLUE <1 3364 8.06E-10 <40 <40 <40 YELLOW <1 336 8.08E-11 <40 <40 <40 GREEN <1 34 8.08E 12 <40 <40 <40 5.00 3.30 BLUE <1 2562 6.61E 10 <40 <40 <40 ,
| |
| YELLOW <1 256 6.61E 11 <40 <40 <40 GREEN <1 26 6.61E 12 <40 <40 <40 6.00 4.10 BLUE <1 1216 2.62E 10 <40 <40 <40 YELLOW <1 122 2.62E 11 <40 <40 <40 GREEN <1 12 2.62E 12 <40 <40 <40 7.00 4.90 BLUE <1 1012 2.24E-10 <40 <40 <40 YELLOW <1 101 2.24E 11 <40 <40 <40 GREEN <1 10 2.24E 12 <40 <40 <40 )
| |
| NOTES Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampier. Il different volumes are collected, the air sample data provided in the tables I should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, i!
| |
| divide the value given in the table by two (2) and provide the resultmg value to the players.
| |
| The RM 14 detector efficiency for 1-131 was assumed to be 0.025 + .'4,,r. with the silver zeolite cartridge.
| |
| The particulate filter sample count rate (cpm) was estimated from the I-131 air concentrations for a 100 liter sample.
| |
| L
| |
| | |
| TABLE 9.6.Sa R;v.O Page 9.6-9a2
| |
| . VERMONT YANKEE FIELD DATA AT CLOCK TIME 1315-1330 (SCENARIO TIME 0515-0530)
| |
| AIR SAMPLE DATA * (RM 14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 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) (NET CPM) 8.00 5.60 BLUE <1 438 8.69E 11 <40 <40 <40 YELLOW <1 44 8.69E 12 <40 <40 <40 GREEN <1 4 8.69E 13 <40 <40 <40 9.00 6.40 BLUE <1 378 7.52E 11 <40 <40 <40 YELLOW <1 38 7.52E-12 <40 <40 <40 GREEN <1 4 7.52E 13 <40 <40 <40 NOTES:
| |
| * Air sample ditta are ued on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco ' ampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, 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 0.025 cptn/dpm with the silver zeolite cartridge.
| |
| '" The particulate filter sample count rate (cpm) was estimated from the I-131 air concentrations for a 100 liter sample.
| |
| | |
| . _ _ _ ..___ _ __ _ _ . . _ . - _ _ _ . - _ _ _ _ . -______.-_.___.-_.m.__
| |
| TABLE 9.6.5b Rev.O PIge 9.6-9b1 STATE OF VERMONT FIELD DATA AT CLOCK TIME 13151330 (SCENARIO TIME 0515-0530)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)*
| |
| WAIST AND GROUND LEVEL READINGS LUOLUM 2220 G-M METER l
| |
| l PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1131 CARTRlDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) l 1.00 SITE BLUE 1.20 2.40 3.28E-20 AS READ AS READ BOUNDARY YELLOW 0.12 0.24 3.28E-21 AS READ AS READ GREEN AS READ AS READ 3.28E-22 AS READ AS READ 2.00 0.80 BLUE 1.90 3.80 2.62E 10 AS READ AS READ YELLOW 0.19 0.38 2.62E-11 AS READ AS READ GREEN AS READ AS READ 2.62E 12 AS READ AS READ 3.00 1.60 BLUE 1.80 3.60 1.51 E-09 95 AS READ YELLOW 0.18 0.36 1.51 E-10 AS READ AS READ i AS READ 1.51 E-11 AS READ AS READ l GREEN AS READ f
| |
| 4.00 2.50 BLUE 0.96 1.92 8.08E 10 51 AS READ YELLOW 0.10 0.19 8.08E 11 AS READ AS READ GREEN AS READ AS READ 8.08E 12 AS READ AS READ 5.00 3.30 BLUE 0.73 1.46 6.61E 10 AS READ AS READ YELLOW 0.07 0.15 6.61E 11 AS READ AS READ GREEN AS READ AS READ 6.61E 12 AS READ AS READ 4.10 BLUE 0.35 0.70 2.62E 10 AS READ AS READ 6.00 YELLOW 0.03 0.07 2.62E 11 AS READ AS READ GREEN AS READ AS READ 2.62E 12 AS READ AS READ BLUE 0.29 0.58 2.24E 10 AS READ AS READ 7.00 4.90 YELLOW 0.03 0.06 2.24E 11 AS READ AS READ GREEN AS READ AS READ 2.2EE 12 AS READ AS READ NOTES:
| |
| * Air sample data are based on a sarnple volume of 354 liters. If different volumes are c.ouected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was coHocted instead of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| i
| |
| " The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.000 cpm /dpm with the AGX-2 cartridge.
| |
| *" For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| ' The filter count rate was estimated from the 1-131 air concentrations for a 354 liter sample volume.
| |
| | |
| TABLE 9.6.5b Rev. O PIge 9.6-9b2 STATE OF VERMONT FIELD DATA AT CLOCK TIME 1315-1330 (SCENARIO TIME 0515-0530)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)*
| |
| LUDLUM 2220 G-M METER WAlST AND GROUND LEVEL READINGS CLOSED OPEN CONC. AGX 2" PARTICULATE *"
| |
| PLUME WINDOW WINDOW I131 CARTRIDGE FILTER SEGMENT DISTANCE MAP AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| NO. (MILES) 0.13 0.25 8.69E-11 AS READ AS READ 8.00 5.60 BLUE 0.01 0.03 8.69E-12 AS READ AS READ YELLOW AS READ AS READ 8.69E 13 AS READ AS READ GREEN 0.11 0.22 7.52E-11 AS READ AS READ 9.00 6.40 BLUE YELLOW 0.01 0.02 7.52E-12 AS READ AS READ AS READ AS READ 7.52E 13 AS READ AS READ GREEN i
| |
| I l
| |
| l l
| |
| NOTES:
| |
| Air sample data are based on a sample volume of 354 liters, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was collected instead ,i of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players. l
| |
| " The Ludlum 2220 detector efficiency for 1-131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge.
| |
| *" For analysis of the particulate fitter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 354 liter sample volume.
| |
| | |
| 1 TABLE 9.6.5c Rev.0 l PIge 9.6-9c1 1
| |
| ; STATE OF MA FIELD DATA AT CLOCK TIME 1315-1330 (SCENARIO TIME 0515-0530)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| I WAIST AND GROUND LEVEL READINGS E 140/HP-210 G-M METER PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE"*
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1.20 2.40 3.28E-20 AS READ AS READ l BOUNDARY YELLOW 0.12 0.24 3.28E 21 AS READ AS READ l GREEN AS READ AS READ 3.28E 22 AS READ AS READ l
| |
| [ 2.00 0.80 BLUE 1.90 3.80 2.62E-10 AS READ AS READ i YELLOW 0.19 0.38 2.62E 11 AS READ AS READ GREEN AS READ AS READ 2.62E 12 AS READ AS READ l 3.00 1.60 BLUE 1.80 3.60 1.51 E-09 AS READ AS READ l, 1
| |
| YELLOW 0.18 0.36 1.51E 10 AS READ AS READ l 3 '
| |
| GREEN AS READ AS READ 1.51E-11 AS READ AS READ 4.00 2.50 BLUE 0.96 1.92 8.08E-10 AS READ AS READ YELLOW 0.10 0.19 8.08E-11 AS READ AS READ GREEN AS READ AS READ 8.08E 12 AS READ AS READ 5.00 3.30 BLUE 0.73 1.46 6.61 E-10 AS READ AS READ YELLOW 0.07 0.15 6.61E 11 AS READ AS READ GREEN AS READ AS READ 6.61E 12 AS READ AS READ 6.00 4.10 BLUE 0.35 0.70 2.62E 10 AS READ AS READ YELLOW AS READ AS READ 2.62E 11 AS READ AS READ GREEN AS READ AS READ 2.62E 12 AS READ AS READ 7.00 4.90 BLUE 0.29 0.58 2.24E 10 AS READ AS READ YELLOW AS READ AS READ 2.24E 11 AS READ AS READ GREEN AS READ AS READ 2.24E 12 AS READ AS READ l
| |
| NOTES: l A!r sample data are based on a sample volume of 20 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example,if a 10 cu ft, sample was collected instead j of 20 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E 140/HP-210 detector efficiency for I-131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| "* For analysis of the particulate filter, it is assumed that a G M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 20 cubic foot sample volume.
| |
| | |
| TABLE 9.6.5c Rev. O Pige 9.6-9c2 STATE OF MA FIELD DATA AT CLOCK TIME 1315-1330 (SCENARIO TIME 0515-0530)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FTy WAIST AND GROUND LEVEL READINGS E-140/HP-210 G-M METER PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) 8.00 5.60 BLUE 0.13 0.25 8.69E 11 AS READ AS READ l AS READ AS READ 8.69E-12 AS READ AS READ I YELLOW GREEN AS READ AS READ 8.69E-13 AS READ AS READ 9.00 6.40 BLUE 0.11 0.22 7.52E 11 AS READ AS READ YELLOW AS READ AS READ 7.52E 12 AS READ AS READ GREEN AS READ AS READ 7.52E-13 AS READ AS READ l
| |
| 4 1
| |
| l l
| |
| l I
| |
| i l
| |
| NOTES:
| |
| Air sample data are based on a sample volume of 20 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 10 cu ft. sample was collected instead of 20 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E 140/HP-210 detector efficiency for 1131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| "* For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the I 131 air concentrations for a 20 cubic foot sample volume.
| |
| | |
| TABLE 9.6.5d Rev.O P:ge 9.6-9d1 STATE OF NH FIELD DATA AT CLOCK TIME 1315-1330 (SCENARIO TIME 0515-0530)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP-210 G-M METER CLOSED OPEN CONC. AGX-2" PARTICULATE"'
| |
| PLUME MAP WINDOW WINDOW 1131 CARTRIDGE FILTER SEGMENT DISTANCE NO. AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| (MILES)
| |
| BLUE 1.20 2.40 3.28E-20 AS READ AS READ 1.00 SITE 0.12 0.24 3.28E-21 AS READ AS READ BOUNDARY YELLOW GREEN AS READ AS READ 3.28E 22 AS READ AS READ BLUE 1.90 3.80 2.62E-10 AS READ AS READ 2.00 0.80 YELLOW 0.19 0.38 2.62E-11 AS READ AS READ GREEN AS READ AS READ 2.62E 12 AS READ AS READ 1.60 BLUE 1.80 3.60 1.51 E-09 AS READ AS READ 3.00 YELLOW 0.18 0.36 1.51 E-10 AS READ AS READ GREEN AS READ AS READ 1.51E 11 AS READ AS READ BLUE 0.96 1.92 8.08E 10 AS READ AS READ 4.00 2.50 YELLOW 0.10 0.19 8.08E 11 AS READ AS READ GREEN AS READ AS READ 8.08E-12 AS READ AS READ 3.30 BLUE 0.73 1.46 6.61E 10 AS READ AS READ 5.00 YELLOW 0.07 0.15 6.61E 11 AS READ AS READ GREEN AS READ AS READ 6.61E 12 AS READ AS READ BLUE 0.35 0.70 2.62E 10 AS READ AS READ 6.00 4.10 YELLOW AS READ AS READ 2.62E-11 AS READ AS READ GREEN AS READ AS READ 2.62E-12 AS READ AS READ BLUE 0.29 0.58 2.24E 10 AS READ AS READ 7.00 4.90 YELLOW AS READ AS READ 2.24E 11 AS READ AS READ GREEN AS READ AS READ 2.24E 12 AS READ AS READ NOTES:
| |
| ! Air sample data are based on a sample volume of 10 cu ft. It different volumes are collected. the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cu ft. sample was collected instead l
| |
| of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E.140/HP 210 detector efficiency for I-131 was assumed to be 0.0025 cpm /dpm with the AGX-2 cartridge.
| |
| ' "* For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 10 cubic foot sample volume.
| |
| l
| |
| | |
| _ _ . _ _ __ _.._ . _ . _ _ - - _ _ _ . . . _ . _ _ _ _ . . _ . _ _ _ . . _ _ . . _ - ~ _ _ _ . . _ _ _ - _ _ . -
| |
| TABLE 9.6.5d Rev. O pige 9.6-9d2 STATE OF NH FIELD DATA AT CLOCK TIME 1315-1330 (SCENARIO TIME 0515-0530)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP-210 G-M METER PLUME CLOSED OPEN CONC. AGX 2" PARTICULATE *"
| |
| MAP WINDOW WINDOW 1131 CARTRIDGE FILTER SEGMENT DISTANCE NO. AREA (mRMr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| (MILES)
| |
| BLUE 0.13 0.25 8.69E-11 AS READ AS READ 8.00 5.60 YELLOW AS READ AS READ 8.69E-12 AS READ AS READ GREEN AS READ AS READ 8.69E 13 AS READ - AS READ ,
| |
| \
| |
| BLUE 0.11 0.22 7.52E-11 AS READ AS READ 9.00 6.40 YELLOW AS READ AS READ 7.52E-12 AS READ AS READ '
| |
| GREEN AS READ AS READ 7.52E 13 AS READ AS READ 1
| |
| I i
| |
| l l
| |
| 9 NOTES:
| |
| * Air sample data are based on a sample volume of 10 cu ft. If different volumes are collected, the air sample data f provided in the tables should be adjusted proportionally. For example, if a 5 cu ft. sample was collected instead of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E 140/HP-210 detector efficiency for 1 131 was assumed to be 0.0025 cpm /dpm with the AGX-2 cartridge.
| |
| i '
| |
| "* For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| l i The filter count rate was estimated from the 1131 air concentrations for a 10 cubic foot sample volume.
| |
| 4 l
| |
| i
| |
| | |
| Grd n; .- 4; FW', :-A f
| |
| 'c'.S g '~'
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| (
| |
| y 1 fe .. $, r .
| |
| > V. i. . Eh.1lc;.p
| |
| ., n %
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| |
| Yk .U z . 4 .
| |
| )
| |
| l c v $1 S ** "b sl g w -
| |
| ,, j s f'f. * /a= <f I - - s ,
| |
| 'A.; -
| |
| 4 .
| |
| < 4 m${QEt-s % l'as %
| |
| 1 2_ s' l ""4 -
| |
| e le e
| |
| 4!I s
| |
| [ g R I g
| |
| *M i varmon 5 i n - a -*
| |
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| |
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| |
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| |
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| |
| N s TN N' CHEST N
| |
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| |
| ( ,,. ..~ ,.
| |
| e 5-# c/' f Warwick .
| |
| 4 /,,4,;
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| |
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| |
| \ i N
| |
| 1,
| |
| * i ,
| |
| : 10. '
| |
| a ! i Bernardsto.'.h '.,"y,I ; /,'
| |
| /) / .
| |
| I N
| |
| # T. .
| |
| I \ N Eu s. **
| |
| I % s) , ({
| |
| \, '
| |
| * Y d ' ri3}' $ **
| |
| : t. $
| |
| [* F; \
| |
| h Northfi ^'' / . - "
| |
| s,
| |
| , , , , , , , , , i e ,s ;/ . . ,
| |
| '% 1
| |
| ,e% O I 2 5 d 90Bometers g ,,
| |
| 9 ,#+.,
| |
| 3, ( ,3
| |
| [, s 4 ,e ,
| |
| r T
| |
| *g* . I y no *
| |
| * g g %
| |
| *'g . 'n.
| |
| /r%. . . . . .k f I ,I
| |
| . C 3
| |
| =v ( s
| |
| ~
| |
| %;s ~
| |
| s rn D' '
| |
| ^
| |
| . # # : g FIGURE 9.6-6 to 1
| |
| 'Y M
| |
| e'
| |
| ,51 0 ''
| |
| \ $
| |
| l ''
| |
| In i
| |
| /
| |
| t' .
| |
| *."$ g p 3 \ >
| |
| . \. 'a y 's - CLOCK TIME: 1330 to 1345 o I
| |
| %- - ** $$f ,t" s._
| |
| e ~ ,
| |
| g b
| |
| | |
| TABLE 9.6.62 Rev.O Page 9.610a1 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1330-1345 (SCENARIO TIME 0530-0545)
| |
| AIR SAMPLE DATA * (RM 14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE CONC. 100 L 10 CF FILTER *"
| |
| PLUME MAP PIC-6 RM-14 l131 SILVER ZEOLITE SEGMENT DISTANCE NO. (MILES) AREA (mR/hr) (CPM) (uCl/cc) (NET CPM) (NET CPM) (NET CPM) 4165 2.75E-20 <40 <40 <40 1.00 SITE BLUE 1
| |
| <1 417 2.75E-21 <40 <40 <40 BOUNDARY YELLOW
| |
| <1 42 2.75E-22 <40 <40 <40 GREEN BLUE 2 6580 2.42E 10 <40 <40 <40 2.00 0.80
| |
| <1 658 2.42E-11 <40 <40 <40 YELLOW GREEN <1 66 2.42E 12 <40 <40 <40 2 6230 1.48E-09 <40 <40 <40 3.00 1.60 BLUE
| |
| <1 623 1.48E 10 <40 <40 <40 YELLOW GREEN <1 62 1.48E 11 <40 <40 <40 BLUE 4270 1.02E-09 <40 <40 <40 4.00 2.40 1 YELLOW <1 427 1.02E 10 <40 <40 <40 GREEN <1 43 1.02E 11 <40 <40 <40 BLUE <1 3217 8.31E 10 <40 <40 <40 5.00 3.30 YELLOW <1 322 8.31E 11 <40 <40 <40 GREEN .. 32 8.31E 12 <40 <40 <40 BLUE <1 1866 4.02E 10 <40 <40 <40 6.00 4.10 YELLOW <1 187 4.02E 11 <40 <40 <40 GREEN <1 19 4.02E 12 <40 <40 <40 4.90 BLUE <1 1533 3.39E 10 <40 <40 <40 7.00 YELLOW <1 153 3.39E 11 .<40 <40 <40 GREEN <1 15 3.39E-12 <40 <40 <40 NOTES:
| |
| * Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted propeitcas.::y. For example, if a 50 liter sample was collected instead of 100 liters, 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 0.025 cpm /dpm with the silver zeolite cartridge
| |
| *" The particulate filter sample count rate (cpm) was estimated from the I-131 air concentrations for a 100 liter sample.
| |
| | |
| TABLE 9.6.62 Rev. O Pige 9.6-10a2
| |
| . . VERMONT YANKEE FIELD DATA AT CLOCK TIME 13301345 (CCENARIO TIME 0530-0545)
| |
| AIR SAMPLE DATA * (RM-14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE CONC. 100 L 10 CF FILTER"*
| |
| PLUME MAP PIC-6 RM 14 l-131 SILVER ZEOLITE SEGMENT DISTANCE NO. (MILES) AREA (mR/hr) (CPM) (uCl/cc) (NET CPM) (NET CPM) (NET CPM)
| |
| <1 798 1.58E 10 <40 <40 <40 8.00 5.70 BLUE
| |
| <1 80 1.58E 11 <40 <40 <40 YELLOW 8 1.58E.12 <40 <40 <40 GREEN <1
| |
| <1 693 1.38E-10 <40 <40 <40 9.00 6.50 BLUE
| |
| <1 69 1.38E-11 <40 <40 <40 YELLOW
| |
| <1 7 1.38E-12 <40 <40 <40 i GREEN
| |
| <1 315 5.88E-11 <40 <40 <40 10.00 7.30 BLUE
| |
| <1 32 5.88E 12 <40 <40 <40 YELLOW
| |
| <1 3 5.88E-13 <40 <40 440 GREEN
| |
| <1 278 5.15E 11 <40 <40 <40 11.00 8.00 BLUE
| |
| <1 28 5.15E-12 <40 <40 c40 YELLOW 3 5.15E 13 <40 <40 <40 GREEN <1 f
| |
| NOTES:
| |
| * ^ 1r sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet te the Radeco sampler. If different volurnes are collected, the air sample data provided in the tables Wuld be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, 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 0.025 cpm /dpm with the silver zeolite cartridge.
| |
| "* The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 100 liter sample.
| |
| | |
| TABLE 9.6.6b Rev.O P:ge 9.6-10b1 STATE OF VERMONT FIELD DATA AT CLOCK TIME 1330-1345 (SCENARIO TIME 0530-0545)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)*
| |
| LUDLUM 2220 G-M METER WAIST AND GROUND LEVEL READINGS CLOSED OPEN CONC. AGX 2" PARTICULATE *"
| |
| PLUME MAP WINDOW WINDOW 1131 CARTRIDGE FILTER SEGMENT DISTANCE NO. AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| (MILES)
| |
| BLUE 1.19 2.38 2.75E-20 AS READ AS READ 1.00 SITE YELLOW 0.12 0.24 2.75E 21 AS READ AS READ BC'JNDARY GREEN AS READ AS READ 2.75E-22 AS READ AS READ BLUE 1.88 3.76 2.42E-10 AS READ AS READ 2.00 0.80 YELLOW 0.19 0.38 2.42E-11 AS READ AS READ GREEN AS READ AS READ 2.42E 12 AS READ AS READ BLUE 1,78 3.f.8 1.48E-09 94 AS READ 3.00 1.60 YELLOW 0.18 0.36 1.48E 10 AS READ AS READ GREEN AS READ AS READ 1.48E 11 AS READ AS READ 4 00 BLUE 1.22 2.44 1.02E-09 64 AS READ 2.40 YELLOW 0.12 0.24 1.02E 10 AS READ AS READ GREEN AS READ AS READ 1.02E-11 AS READ AS READ 3.30 BLUE 0.92 1.84 8.31E 10 52 AS READ 5.00 YELLOW 0.09 0.18 8.31 E-11 AS READ AS READ GREEN AS READ AS READ 8.31E 12 AS READ AS READ 6.00 4.10 BLUE 0.53 1.07 4.02E-10 AS READ AS READ YELLOW 0.05 0.11 4.02E 11 AS READ AS READ GREEN AS READ AS READ 4.02E 12 AS READ AS READ 4.90 BLUE 0.44 0.88 3.39E 10 AS READ AS READ 7.00 YELLOW 0.04 0.09 3.39E 11 AS READ AS READ GREEN AS READ AS READ 3.39E-12 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 354 liters. if different volumes are collected, the air sample data ]
| |
| provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was collected instead l of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The Ludlum 2220 detector efficiency for 1-131 was assumed to be 0.080 cpm /dpm with the AGX 2 cartridge.
| |
| "* For analysis of the particulate filter, it is assumert that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 354 liter sample volume.
| |
| | |
| TABLE 9.6.6b Rev.O P:ge 9.6-10b2 STATE OF VERMONT FIELD DATA AT CLOCK TIME 1330-1345 (SCENARIO TIME 0530-0545)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)*
| |
| LUDLUM 2220 G-M METER WAIST AND GROUND LEVEL READINGS CLOSED OPEN CONC. AGX 2" PARTICULATE *"
| |
| PLUME WINDOW WINDOW 1131 CARTRIDGE FILTER SEGMENT DISTANCE MAP (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| NO. (MILES) AREA 0.46 1.58E-10 AS READ AS READ 8.00 5.70 BLUE 0.23 0.05 1.58E 11 AS READ AS READ YELLOW 0.02 AS READ 1.58E 12 AS READ AS READ GREEN AS READ 0.20 0.40 1.38E 10 AS READ AS READ 9.00 6.50 BLUE 0.02 0.04 1.38E-11 AS READ AS READ YELLOW AS READ AS READ 1.38E-12 AS READ AS READ GREEN 0.18 5.88E 11 AS READ AS READ
| |
| ; 10.00 7.30 BLUE 0.09 AS READ AS READ 5.88E 12 AS READ AS READ YELLOW AS READ 5.88E-13 AS READ AS READ i GREEN AS READ i
| |
| " 0.08 0.16 5.15E 11 AS READ AS READ
| |
| . 11.00 8.00 BLUE AS READ AS READ 5.15E 12 AS READ AS READ YELLOW AS READ 5.15E 13 AS READ AS READ ;
| |
| GREEN AS READ I
| |
| i NOTES:
| |
| * Air sample data are based on a sample volume of 354 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was collected instead
| |
| ' of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The Ludlum 2220 detector efficiency for 1 131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge.
| |
| '" For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| j The filter count rate was estimated from the 1-131 air concentrations for a 354 liter sample volume.
| |
| e
| |
| | |
| TABLE 9.6.6c Rev.O P ge 9.610c1 i j
| |
| STATE OF MA FIELD DATA AT CLOCK TIME 1330-1345 (SCENARIO TIME 0530-0545)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| G-M METER l WAIST AND GROUND LEVEL READINGS E-140/HP 210
| |
| (
| |
| CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| PLUME MAP WINDOW WINDOW I131 CARTRfDGE FILTER SEGMENT DISTANCE NO. AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| (MILES) l 1.19 2.38 2.75E-20 AS READ AS READ 1.00 SITE BLUE 0.12 0.24 2.75E-21 AS READ AS READ BOUNDARY YELLOW GREEN AS READ AS READ 2.75E 22 AS READ AS READ i AS READ 0.80 BLUE 1.88 3.76 2.42E-10 AS READ 2.00 YELLOW 0.19 0.38 2.42E 11 AS READ AS READ GREEN AS READ AS READ 2.42E-12 AS READ AS READ BLUE 1.78 3.56 1.48E-09 AS READ AS READ 3.00 1.60 0.18 0.36 1.48E 10 AS READ AS READ l
| |
| ' YELLOW GREEN AS READ AS READ 1.48E 11 AS READ AS READ 4
| |
| BLUE 1.22 2.44 1.02E 09 AS READ AS READ 4.00 2.40 YELLOW 0.12 0.24 1.02E-10 AS READ AS READ GREEN AS READ AS READ 1.02E-11 AS READ AS READ BLUE 0.92 1.84 8.31 E-10 AS READ AS . 2.AD 5.00 3.30 YELLOW 0.09 0.18 8.31E 11 AS READ AS READ GREEN AS READ AS READ B.31 E-12 AS READ AS READ BLUE 0.53 1.07 4.02E 10 AS READ AS READ 6.00 4.10 YELLOW 0.05 0.11 4.02E-11 AS READ AS READ GREEN AS READ AS READ 4.02E-12 AS READ AS READ 0.44 0.88 3.39E 10 AS READ AS READ 7.00 4.90 BLUE AS READ AS READ 3.39E-11 AS READ AS READ YELLOW GREEN AS READ AS READ 3.39E 12 AS READ AS READ
| |
| ! NOTES:
| |
| Air sample data are based on a sample volume of 20 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example,if a 10 cu ft. sample was collected instead
| |
| ; of 20 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E 140/HP-210 detector efficiency for 1-131 was assumed to be 0.0025 epm /dpm with the AGX-2 cartridge.
| |
| "* For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter cwn! rate was estimated from the I 131 air concentrations for a 20 cubic foot sample volume.
| |
| t
| |
| | |
| l l l
| |
| TABLE 9.6.6c Rev.0 l
| |
| PJtge 9.6-10c2 STATE OF MA FIELD DATA AT CLOCK TIME 1330-1345 (SCENARIO TIME 0530-0545)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| i WAIST AND GROUND LEVEL READINGS E 140/HP 210 G-M METER
| |
| ; PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE
| |
| * SEGMENT DISTANCE MAP WINDOW WINDOW I131 CARTRIDGE FILTER j NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| ; 8.00 5.70 BLUE 0.23 0.46 1.58E 10 AS READ AS READ ;
| |
| ; YELLOW AS READ AS READ 1.58E 11 AS READ AS READ
| |
| ; GREEN AS READ AS READ 1.58E-12 AS READ AS READ i
| |
| i 9.00 6.50 BLUE 0.20 0.40 1.38E 10 AS READ AS READ i YELLOW AS READ AS READ 1.38E-11 AS READ AS READ j GREEN AS READ AS READ 1.38E 12 AS PEAD AS READ
| |
| .i 10.00 7.30 BLUE 0.09 0.18 5.88E 11 AS READ AS READ YELLOW AS READ AS READ 5.88E-12 fisREAD AS READ j GREEN AS READ AS READ 5.88E 13 AS READ AS READ t
| |
| 11.00 8.00 BLUE 0.08 0.16 5.15E 11 AS READ AS READ YELLOW AS READ AS READ 5.15E 17 AS READ AS READ ;
| |
| GREEN AS READ AS READ 5.15E 13 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 20 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 10 cu ft. sample was collected instead of 20 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " I The E 140/HP-210 detector efficiency for 1-131 was assumed to be 0.0025 v ,4,, with the AGX-2 cartridge.
| |
| i
| |
| ~
| |
| For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1 131 air concentrations for a 20 cubic foot sample volume. l I
| |
| | |
| TABLE 9.6.6d Rev. O Pzge 9.6-10d1 STATE OF NH FIELD DATA AT CLOCK TIME 1330-1345 (SCENARIO TIME 0530-0545)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP-210 G-M METER PLUME CLOSED OPEN CONC. AGX 2" PARTICULATE *"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uC1/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1.19 2.38 2.75E 20 AS READ AS READ BOUNDARY YELLOW 0.12 0.24 2.75E 21 AS READ AS READ GREEN AS READ AS READ 2.75E 22 AS READ AS READ ,
| |
| 2.00 0.80 BLUE 1.88 3.76 2.42E 10 AS READ AS READ YELLOW 0.19 C.38 2.42E-11 AS READ AS READ GREEN AS READ AS READ 2.42E 12 AS READ AS READ 3.00 1.60 BLUE 1.78 3.56 1.48E-09 AS READ AS READ YELLOW 0.18 0.36 1.48E 10 AS READ AS READ GREEN AS READ AS READ 1.48E 11 AS READ AS READ 4.00 2.40 BLUE 1.22 2.44 1.02E-09 AS READ AS READ YELLOW 0.12 0.24 1.02E 10 AS READ AS READ GREEN AS READ AS READ 1.02E 11 AE, READ AS READ 5.00 3.30 BLUE 0.92 1.34 8.31E 10 AS READ AS READ YELLOW 0.09 0.18 8.31 E-11 AS READ AS READ GREEN AS READ AS READ 8.31E 12 AS READ AS READ 6.00 4.10 BLUE 0.53 1.07 4.02E 10 AS READ AS READ YELLOW 0.05 0.11 4.02E 11 AS READ AS READ GREEN AS READ AS READ 4.02E 12 AS READ AS READ 7.00 4.90 BLUE 0.44 0.88 3.39E-10 AS READ AS READ YELLOW AS READ AS READ 3.39E 11 AS READ AS READ GREEN AS READ AS READ 3.39E 12 . AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 10 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cu ft. sample was collected instead !
| |
| of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| ** The E 140/HP-210 detector efficiency for 1-131 was assumed to be 0 0025 cpm /dpm with the AGX 2 cartridge. j
| |
| *" For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 10 cubic foot sample volume.
| |
| l
| |
| | |
| TABLE 9.6.6d Rev. O Prge 9.6-10d2 STATE OF NH FIELD DATA AT CLOCK TIME 13301345 (SCENARIO TIME 0530-0545)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP 210 G M METER PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW l-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) 8.00 5.70 BLUE 0.23 0.46 1.58E 10 AS READ AS READ YELLOW AS READ AS READ 1.58E 11 AS READ AS READ GREEN AS READ AS READ 1.58E 12 AS READ AS READ 9.00 6.50 BLUE 0.20 0.40 1.38E-10 AS READ AS READ YELLOW AS READ AS READ 1.38E 11 AS READ AS READ GREEN AS READ AS READ 1.3SE 12 AS READ AS READ 10.00 7.30 BLUE 0.09 0.18 5.88E-11 AS READ AS READ YELLOW AS READ AS READ 5.88E 12 AS READ AS READ GREEN AS READ AS READ 5.88E 13 AS READ AS READ 11.00 8.00 BLUE 0.08 0.16 5.15E 11 AS READ AS READ YELLOW AS READ AS READ 5.15E 12 AS READ AS READ GREEN AS READ AS READ 5.15E 13 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 10 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cu ft. sample was collected Instead of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E-140/HP-210 detector efficiency for 1131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| For analysis of the particulate filter,it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 10 cubic foot sample volume.
| |
| | |
| ?N k?{+k,?fNr
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
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| |
| y 5 < m2 .' r - 5 i Wrreierrt c fh ,, se cervtera,,b 6 ' <
| |
| N l~
| |
| "7 ( t M f
| |
| ,t ; Warw{C ,,
| |
| - J.L \ i 4 4 ,E. -
| |
| is .i. _
| |
| i
| |
| ! E#
| |
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| |
| *. i r/ ) - !'/ "
| |
| B:rnardstors , k g ,,/g I
| |
| ]c
| |
| !\;d .g," ~"
| |
| " f tj 3A I2E k k I, 3
| |
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| |
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| |
| : i. _ ,y .. h.. _ _ R .
| |
| #87 V
| |
| ~s_.
| |
| i i,ll '
| |
| Northfi '**, ~
| |
| ,' o , , , . . , ,
| |
| ,7,.
| |
| s _. o t
| |
| i c- - .
| |
| j
| |
| .y g
| |
| ,,\ **e i a a 4 .a g l
| |
| ( ( .
| |
| y F ./ . d"* , 3 ej g */ ** rN ,
| |
| ?,,
| |
| 3
| |
| = =
| |
| l 4 ,, '
| |
| ~
| |
| , '2 -
| |
| .s k FIGURE 9.6-7 l ., ! N y '' I' i
| |
| '2- T ,, '# 1 \ '', 2~ ,,. CLOCK TIME: 1345 to 1400 $
| |
| .w b . ^$ - ik ,
| |
| * [, MM .. .,
| |
| | |
| TABLE 9.6.7a Rev.O Page 9.6-11a1 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1345-1400 (SCENARIO TIME 0545 0600)
| |
| AIR SAMPLE DATA' (RM-14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER *"
| |
| SEGMENT DISTANCE MAP PIC-6 RM-14 6-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCl/cc) (NET CPM) (NET CPM) (NET CPM) 1.00 SITE BLUE 1 4095 3.70E-20 <40 <40 <40 BOUNDARY YELLOW <1 410 3.70E-21 <40 <40 <40 GREEN <1 41 3.70E 22 <40 <40 <40 2.00 0.80 BLUE 2 6440 2.69E 10 <40 <40 <40 YELLOW <1 644 2.69E-11 <40 <40 <40 GREEN <1 64 2.69E 12 <40 <40 <40 3.00 1.70 BLUE 2 6055 1.45E-09 <40 <40 <40 YELLOW <1 606 1.45E 10 <40 <40 <40 GREEN <1 61 1.45E 11 <40 <40 <40 4.00 2.50 BLUE 1 4130 9.92E 10 <40 <40 <40 YELLOW <1 413 9.92E 11 <40 <40 <40 GREEN <1 41 9.92E-12 <40 <40 <40 5.00 3.30 BLUE <1 3112 8.00E-10 <40 <40 <40 YELLOW <1 311 8.00E-11 <40 <40 <40 GREEN <1 31 8.00E 12 <40 <40 <40 6.00 4.10 BLUE <1 2317 4.98E 10 <40 <40 <40 YELLOW <1 232 4.98E-11 <40 <40 <40 GREEN <1 23 4.98E-12 <40 <40 <40 7.00 4.90 BLUE <1 1904 ,
| |
| 4.19E 10 <40 <40 <40 YELLOW <1 190 4.19E 11 <40 <40 <40 GREEN <1 19 4.19E-12 <40 <40 <40 NOTES:
| |
| Air samplo data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The RM 14 detector efficiency Ior 1-131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge.
| |
| The particulate filter sample count rate (cpm) was estimated from the 1 131 air concentrations for a 100 !;ter sample.
| |
| | |
| l l TABLE 9.6.7a Rzv. O Page 9.611a2 VEF MONT YA'NKEE FIELD DATA AT CLOCK TIME 1345-1400 (SCENARib TIME 0545-0600) 9 AIR SAMPLE DATA * (RM-14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER
| |
| * SEGMENT DISTANCE MAP PIC-6 RM-14 l131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCl/cc) (NET CPM) (NET CPM) (NET CPM) 8.00 5.80 BLUE <1 1211 2.41E 10 <40 <40 <40 YELLOW <1 121 2.41E 11 <40 <40 <40 GREEN <1 12 2.41E 12 <40 <40 <40 l
| |
| )
| |
| 9.00 6.60 BLUE <1 1040 2.08E 10 <40 <40 <40 YELLOW <1 104 2.08E 11 <40 <40 <40 GREEN <1 to 2.08E 12 <40 <40 <40
| |
| ]
| |
| 1 j 10.00 7.40 BLUE <1 571 1.06E-10 <40 <40 <40 I YELLOW <1 57 1.06E-11 <40 <40 <40 *'
| |
| GREEN <1 6 1.06E 12 <40 <40 <40 1
| |
| 11.00 8.20 BLUE <1 508 9.46E 11 <40 <40 <40 YELLOW <1 51 9.46E 12 <40 <40 <40 GREEN <1 5 9.46E 13 <40 <40 <40 12.00 8.90 BLUE <1 239 4.23E 11 <40 <40 <40 ,
| |
| YELLOW <1 24 4.23E 12 <40 <40 <40 GREEN <1 2 4.23E 13 <40 <40 <40 l
| |
| 13.00 9.70 BLUE <1 215 3.74E 11 <40 <40 <40
| |
| ; YELLOW <1 21 3.74E 12 <40 <40 <40 GREEN <1 2 3.74E-13 <40 <40 <40 l
| |
| j NOTES: ,
| |
| Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet )
| |
| for the Radeco sampler, if different volumes are collected, the air sample data provided in the tables I should be adjusted proportionally. For example,if a 50 liter sample was collected instead of 100 liters. .
| |
| 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 1-131 was assumed to be 0.025 cpm /dpm with the sil'ver zeolite cartridge. ,
| |
| * The particulate fitter sample count rate (cpm) was estimated from the I-131 air concentrations for a 100 liter sample.
| |
| L
| |
| | |
| TABLE 9.6.7b Rev.O P ge 9.6-11b1 l 4
| |
| i STATE OF VERMONT FIELD DATA AT CLOCK TIME 1345-1400 (SCENARIO TIME 0545-0600)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)*
| |
| WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G-M METEP H.UME CLOSED OPEN CONC. AGX-2" PARTICULATE'"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1-131 CARTRIDGI FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1.17 2.34 3.70E 20 AS READ AS READ BOUNDARY YELLOW 0.12 0.23 3.70E 21 AS READ AS READ ;
| |
| GREEN AS READ AS READ 3.70E-22 AS READ AS READ 2.00 0.80 BLUE 1.84 3.68 2.69E 10 AS READ AS READ YELLOW 0.18 0.37 2.69E-11 AS READ AS READ GREEN AS READ AS READ 2.69E 12 AS READ AS READ 3.00 1.70 BLUE 1.73 3.46 1.45E-09 92 AS READ YELLOW 0.17 0.35 1.45E-10 AS READ AS READ GREEN AS READ AS READ 1.45E-11 AS READ - AS READ 4.00 2.50 BLUE 1.18 2.36 9.92E 10 63 AS READ YELLOW 0.12 0.24 9.92E-11 AS READ AS READ GREEN AS READ AS READ 9.92E-12 AS READ AS READ 5.00 3.30 BLUE 0.89 1.78 8.00E 10 50 AS READ YELLOW 0.09 0.18 8.00E-11 AS READ AS READ GREEN AS READ AS READ 8.00E 12 AS READ AS READ i
| |
| 6.00 4.10 BLUE 0.66 1.32 4.98E-10 AS READ AS READ YELLOW 0.07 0.13 4.98E-11 AS READ AS READ GREEN AS READ AS READ 4.98E-12 AS READ AS READ 7.00 4.90 BLUE 0.54 1.09 4.19E 10 AS READ AS READ YELLOW 0.05 0.11 4.19E-11 AS READ AS READ GREEN AS READ AS READ 4.19E-12 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 354 liters.11 different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was collected instead of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The Ludlum 2220 detector efficiency for 1 131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge.
| |
| '" For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the I-131 air concentrations for a 354 liter sample volume.
| |
| 1 3
| |
| f-
| |
| | |
| TABLE 9.6.7b Rev.O Pige 9.6-11b2 STATE OF VERMONT FIELD DATA AT CLOCK TIME 1345-1400 (SCENARIO TIME 0545-0600)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)*
| |
| LUDLUM 2220 G-M METER WAIST AND GROUND LEVEL READINGS CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| PLUME WINDOW WINDOW 1131 CARTRIDGE FILTER SEGMENT DISTANCE MAP AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM)
| |
| NO. (MILES) 0.35 0.69 2.41E 10 AS READ AS READ 8.00 S.80 BLUE 0.03 0.07 2.41E 11 AS READ AS READ YELLOW AS READ AS READ 2.41E 12 AS READ AS READ GREEN 0.30 0.59 2.08E 10 AS READ AS READ 9.00 6.60 BLUE 0.03 0.06 2.08E-11 AS READ AS READ YELLOW AS READ AS READ 2.08E 12 AS READ AS READ GREEN BLUE 0.16 0.33 1.06E 10 AS READ AS READ 10.00 7.40 0.02 0.03 1.06E 11 AS READ AS READ YELLOW AS READ AS READ 1.06E 12 AS READ AS READ GREEN BLUE 0.15 0.29 9.46E 11 AS READ AS READ 11.00 8.20 YELLOW 0.01 0.03 9.46E 12 AS READ AS READ AS READ AS READ 9.46E 13 AS READ AS READ GREEN 0.07 0.14 4.23E 11 AS READ AS READ 12.00 8.90 BLUE AS READ AS READ 4.23E-12 AS READ AS READ YELLOW AS READ AS READ 4.23E 13 AS READ AS READ GREEN 0.06 0.12 3.74E-11 AS READ AS READ 13.00 9.70 BLUE AS READ AS READ 3.74E-12 AS READ AS READ YELLOW AS READ AS READ 3.74E 13 AS READ AS READ GREEN I
| |
| )
| |
| NOTES:
| |
| * Air sample data are based on a sample volume of 354 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was collected instead of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 cpm /dpm with the AGX 2 cartridge.
| |
| l
| |
| "* For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the I-131 air concentrations for a 354 liter sample volume.
| |
| | |
| -.- .. .. - _ _ - . _. ~ . . __ .. . . . - . - . . -
| |
| TABLE 9.6.7c Rev.O STATE OF MA FIELD DATA AT CLOCK TIME 1345-1400 (SCENARIO TIME 0545-0600) l l
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)* j WAIST AND GROUND LEVEL READINGS E 140/HP-210 G-M METER ;
| |
| PLUME CLOSED OPEN CONC. AGX 2" PARTICULATE"' I GEGMENT DISTANCE MAP WINDOW WINDOW I131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uC1/cc) (NET CPM) (NET CPM) i 1.00 SITE BLUE 1.17 2.34 3.70E-20 AS READ AS READ BOUNDARY YELLOW 0.12 0.23 3.70E-21 AS READ AS READ GREEN AS READ AS READ 3.70E 22 AS READ AS READ 2.00 0.80 BLUE 1.84 3.68 2.69E 10 AS READ AS READ YELLOW 0.18 0.37 2.69E 11 AS READ .AS READ GREEN AS READ AS READ 2.69E 12 AS READ AS READ 3.00 1.70 BLUE 1.73 3.46 1.45E-09 AS READ AS READ YELLOW 0.17 0.35 1.45E 10 AS READ AS READ GREEN AS READ AS READ 1.45E-11 AS READ AS READ 4.00 2.50 BLUE 1.18 2.36 9.92E-10 AS READ AS READ YELLOW 0.12 0.24 9.92E-11 AS READ AS READ GREEN AS READ AS READ 9.92E-12 AS READ AS READ 5.00 3.30 BLUE 0.89 1.78 8.00E 10 AS READ AS READ YELLOW 0.09 0.18 8.00E 11 AS READ AS READ GREEN AS READ AS READ 8.00E 12 AS READ AS READ 6.00 4.10 BLUE 0.66 1.32 4.98E 10 AS READ AS READ YELLOW 0.07 0.13 4.98E 11 AS READ AS READ GREEN AS READ AS READ 4.98E 12 AS READ AS READ 7.00 4.90 BLUE 0.54 1.09 4.19E 10 AS READ AS READ YELLOW 0.05 0.11 4.19E 11 AS READ AS READ GREEN AS READ AS READ 4.19E-12 AS READ AS READ NOTES: ,
| |
| Air sample data are based on a sample volume of 20 cu ft. If different volumes are collected, the air sample data l provided in the tables should be adjusted proportionally For example, if a to eu ft. sample was collected instead I of 20 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players. l The E 140/HP-210 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the AGX-2 cartridge.
| |
| For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the I-131 air concentrations for a 20 cubic foot sample volume.
| |
| | |
| 1 l
| |
| 4 TABLE 9.6.7c Rev. O Prge 9.6-11c2 i STATE OF MA FIELD DATA AT CLOCK TIME 1345-1400 (SCENARIO TIME 0545-0600)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| E 140/HP-210 G-M METER WAIST AND GROUND LEVEL READINGS CLOSED OPEN CONC. AGX 2" PARTICULATE"*
| |
| PLUME MAP WINDOW WINDOW l-131 CARTRIDGE FILTER SEGMENT DISTANCE NO. AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) j (MILES)
| |
| BLUE 0.35 0.69 2.41E 10 AS READ AS READ 8.00 5.80 YELLOW AS READ AS READ 2.41E 11 AS READ AS READ GREEN AS READ AS READ 2.41E 12 AS READ AS READ l
| |
| 1 BLUE 0.30 0.59 2.08E-10 AS READ AS READ l 9.00 6.60 2.08E 11 AS READ AS READ !
| |
| YELLOW AS READ AS READ GREEN AS READ AS READ 2.08E 12 AS READ AS READ BLUE 0.16 0.33 1.06E-10 AS READ AS READ 10.00 7.40 YELLOW AS READ AS READ 1.06E-11 AS READ AS READ GREEN AS READ AS READ 1.06E-12 AS READ AS READ BLUE 0.15 0.29 9.46E 11 AS READ AS READ 11.00 8.20 I
| |
| YELLOW AS READ AS READ 9.46E-12 AS READ AS READ GREEN AS READ AS READ 9.46E-13 AS READ AS READ 8.90 BLUE 0.07 0.14 4.23E 11 AS READ AS READ 12.00 4.23E 12 AS READ AS READ l YELLOW AS READ AS READ GREEN AS READ AS READ 4.23E 13 AS READ AS READ 0.06 0.12 3.74E 11 AS READ AS READ ,
| |
| 13.00 9.70 BLUE AS READ AS READ !
| |
| YELLOW AS READ AS READ 3.74E 12 AS READ AS READ 3.74E-13 AS READ AS READ GREEN l
| |
| l l
| |
| NOTES:
| |
| Air sample data are based on a sample volume of 20 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 10 cu ft. sample was collected instead of 20 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E 140/HP-210 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the AGX-2 cartridge.
| |
| "* For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the I 131 air concentrations for a 20 cubic foot sample volume.
| |
| | |
| TABLE 9.6.7d Rev.O P ge 9.6-11d1 STATE OF NH FIELD DATA AT CLOCK TIME 1345-1400 (SCENARIO TIME 0545-0600)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E-140/HP 210 G-M METER PLUME CLOSED OPEN CONC. AGX 2" PARTICULATE *"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1.17 2.34 3.70E-20 AS READ AS READ BOUNDARY YELLOW 0.12 0.23 3.70E 21 AS READ AS READ GREEN AS READ AS READ 3.70E-22 AS READ AS READ 2.00 0.80 BLUE 1.84 3.68 2.69E 10 AS READ AS READ YELLOW 0.18 0.37 2.69E-11 AS READ AS READ GREEN AS READ AS READ 2.69E 12 AS READ AS READ 3.00 1.70 BLUE 1.73 3.46 1.45E-09 AS READ AS READ YELLOW 0.17 0.35 1.45E-10 AS READ AS READ GREEN AS READ AS READ 1.45E 11 AS READ AS READ 4.00 2.50 BLUE 1.18 2.36 9.92E 10 AS READ AS READ YELLOW 0.12 0.24 9.92E-11 AS READ AS READ GREEN AS READ AS READ 9.92E 12 AS READ AS READ 5.00 3.30 BLUE 0.89 1,78 8.00E 10 AS READ AS READ YELLOW 0.09 0.18 8.00E 11 AS READ AS READ GREEN AS READ AS READ 8.00E 12 AS READ AS READ 6.00 4.10 BLUE 0.66 1.32 4.98E 10 AS READ AS READ YELLOW 0.07 0.13 4.98E 11 AS READ AS READ GREEN AS READ AS READ 4.98E 12 AS READ AS READ 7.00 4.90 BLUE 0.54 1.09 4.19E 10 AS READ AS READ YELLOW 0.05 0.11 4.19E 11 AS READ AS READ GREEN AS READ AS READ 4.19E-12 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 10 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cu ft. sample was collected instead of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| The E 140/HP-210 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the AGX-2 cartridge.
| |
| For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 10 cubic foot sample volume.
| |
| | |
| TABLE 9.6.7d Rev. O Prge 9.611d2 STATE OF NH FIELD DATA AT CLOCK TIME 13451400 (SCENARIO TIME 0545-0600)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP-210 G-M METER PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1131 CARTRIDGE FILTER NO. (MILE!!) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) 8.00 5.80 BLUE 0.35 0.69 2.41E 10 AS READ AS READ YELLOW AS READ AS READ 2.41E 11 AS READ AS READ GREEN AS READ AS READ 2.41 E-12 AS READ AS READ 9.00 6.60 BLUE 0.30 0.59 2.08E-10 AS READ AS READ YELLOW AS READ AS READ 2.08E 11 AS' READ AS READ GREEN AS READ AS READ 2.08E 12 AS READ AS READ 10.00 7.40 BLUE 0.16 0.33 1.06E-10 AS READ AS READ YELLOW AS READ AS READ 1.06E-11 AS READ AS READ GREEN AS READ AS READ 1.06E-12 AS READ AS READ 11.00 f3.20 BLUE 0.15 0.29 9.46E-11 AS READ AS READ YELLOW AS READ AS READ 9.46E 12 AS READ AS READ GREEN AS READ AS READ 9.46E-13 AS READ AS READ 12.00 8.90 BLUE 0.07 0.14 4.23E-11 AS READ AS READ YELLOW AS READ AS READ 4.23E-12 AS READ AS READ GREEN AS READ AS READ 4.23E 13 AS READ AS READ 13.00 9.70 BLUE 0.06 0.12 3.74E 11 AS READ AS READ YELLOW AS READ AS READ 3.74E 12 AS READ AS READ GREEN AS READ AS READ 3.74E 13 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 10 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cu ft. sample was collected instead of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| The E 140/HP-210 detectur efficiency for 1131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 10 cubic foot sample volume.
| |
| | |
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| | |
| TABLE 9.6.83 Rev.O Page 9.6-12a1 VERMONT YANKEE FIELD DATA AT CLOCK TIME 14001415 (SCENARIO TIME 0600@15)
| |
| AIR SAMPLE DATA'(RM-14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER *"
| |
| SEG'AENT DISTANCE MAP PlC-6 RM-14 l-131 SILVER ZEOLITE NO (MILES) AREA (mR/hr) (CPM) (uCl/cc) (NET CPM) (NET CPM) (NET CPM) 1.00 SITE BLUE 1 4025 4.90E 20 <40 <40 <40 BOUNDARY YELLOW <1 403 4.90E 21 <40 <40 <40 GREEN <1 40 4.90E 22 <40 <40 <40 1
| |
| 2.00 0.90 BLUE 2 6335 2.97E 10 <40 <40 <40 l YELLOW <1 634 2.97E 11 <40 <40 <40 l GREEN <1 63 2.97E-12 <40 <40 <40 1
| |
| 1 3.00 1.70 BLUE 2 5775 1.39E-09 <40 <40 <40 YELLOW <1 578 1.39E 10 <40 <40 - <40 GREEN <1 58 1.39E 11 <40 <40 <40 j l
| |
| 4.00 2.60 BLUE 1 3885 9.31 E-10 <40 <40 <40 YELLOW <1 389 9.31 E-11 <40 <40 <40 GREEN <1 39 9.31E 12 <40 <40 <40 5.00 3.40 BLUE <1 2982 7.62E-10 <40 <40 <40 YELLOW <1 298 7.62E-11 <40 <40 <40 GREEN <1 30 7.62E 12 <40 <40 <40 6.00 4.20 BLUE <1 2237 4.81E 10 <40 <40 <40 YELLOW <1 224 4.81E 11 <40 <40 <40 GREEN <1 22 4.81 E-12 <40 <40 <40 7.00 5.00 BLUE <1 1820 4.01 E-10 <40 <40 <40 YELLOW <1 182 4.01E 11 <40 <40 <40 GREEN <1 18 4.01 E-12 <40 <40 <40 NOTES:
| |
| Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, 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 0.025 cpm /dpm with the silver zeolite cartridge.
| |
| *" The particulate filter sample count rate (cpm) was estimated from the 1-131 air concentrations for a 100 liter sample.
| |
| | |
| TABLE 9.6.8a Rev.O P ge 9.6-12a2 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1400-1415 (SCENARIO TIME 0600-0615)
| |
| AIR SAMPLE DATA * (RM-14)"
| |
| GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER"*
| |
| SEGMENT DISTANCE MAP PIC-6 RM-14 l131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) (uCl/cc) (NET CPM) (NET CPM) (NET CPM) 8.00 5.80 BLUE <1 1491 2.96E 10 <40 <40 <40 YELLOW <1 149 2.96E 11 <40 <40 <40 GREEN <1 15 2.96E 12 <40 <40 <40 9.00 6.70 BLUE <1 1281 2.55E 10 <40 <40 <40 YELLOW <1 128 2.55E 11 <40 <40 <40 GREEN <1 13 2.55E 12 <40 <40 <40 10.00 7.50 BLUE <1 858 1.60E-10 <40 <40 <40 YELLOW <1 86 1.60E 11 <40 <40 <40 GREEN <1 9 1.60E 12 <40 <40 , <40 11.00 8.30 BLUE <1 760 1.41E 10 <40 <40 <40 YELLOW <1 76 1.41E 11 <40 <40 <40 GREEN <1 8 1.41E 12 <40 <40 <40 12.00 9.10 BLUE <1 431 7.62E-11 <40 <40 <40 YELLOW <1 43 7.62E-12 <40 <40 <40 GREEN <1 4 7.62E 13 <40 <40 <40 13.00 9.90 BLUE <1 392 6.82E 11 <40 <40 <40 YELLOW <1 39 6.82E 12 <40 <40 <40 GREEN <1 4 6.82E 13 <40 <40 <40 14.00 10.70 BLUE <1 189 3.18E 11 <40 <40 <40 YELLOW <1 19 3.18E-12 <40 <40 <40 GREEN <1 2 3.18E-13 <40 <40 <40 NOTES:
| |
| Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted prooortionally. For example, if a 50 liter sample was collected instead of 100 liters, 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 0.025 cpm /dpm with the silver zeolite cartridge.
| |
| "* The particulate Otter sample count rats (cpm) was estimated from the 1 131 air concentrations for a 100 liter sample.
| |
| | |
| TABLE 9.6.8b Rev.0 l Prge 9.6-12b1 STATE OF VERMONT FIELD DATA AT CLOCK TIME 1400-1415 (SCENARIO TIME 0600-0615) l j
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)*
| |
| WAlST AND GROUND LEVEL READINGS LUDLUM 2220 G-M METER PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE *" !
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1-131 CARTRIDGE FILTER l NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1.15 2.30 4.90E 20 AS READ AS READ BOUNDARY YELLOW 0.12 0.23 4.90E-21 AS READ AS READ i GREEN AS READ AS READ 4.90E-22 AS READ AS READ 2.00 0.90 BLUE 1.81 3.62 2.97E 10 AS READ AS READ YELLOW 0.18 0.36 2.97E 11 AS READ AS READ GREEN AS READ AS READ 2.97E 12 AS READ AS READ 3.00 1.70 BLUE 1.65 3.30 1.39E 09 88 AS READ YELLOW 0.17 0.33 1.39E 10 AS READ AS READ GREEN AS READ AS READ 1.39E 11 AS READ AS READ l
| |
| 4.00 2.60 BLUE 1.11 2.22 9.31E 10 59 AS READ l I
| |
| YELLOW 0.11 0.22 9.31E 11 AS READ AS READ GREEN AS READ AS READ 9.31E 12 AS READ AS READ 5.00 3.40 BLUE 0.85 1.70 7.62E 10 AS READ AS READ YELLOW 0.09 0.17 7.62E 11 AS READ AS READ GREEN AS READ AS READ 7.62E 12 AS READ AS READ 6.00 4.20 BLUE 0.64 1.28 4.81E 10 AS READ AS READ YELLOW 0.06 0.13 4.81E 11 AS READ AS READ GREEN AS READ AS READ 4.81E 12 AS READ AS READ 7.00 5.00 BLUE 0.52 1.04 4.01E 10 AS READ AS READ YELLOW 0.05 0.10 4.01 E-11 AS READ AS READ GREEN AS READ AS READ 4.01E 12 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 354 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example,if a 177 liter sample was collected instead of 354 liters, divide the value geven in the table by two (2) and provide the resulting value to the players.
| |
| " The Ludlum 2220 detector efficiency for 1 131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge.
| |
| '" For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 354 liter sample volume.
| |
| | |
| TABLE 9.6.8b Rev. O Pige 9.6-12b2 J
| |
| ; STATE OF WRMONT FIELD DATA AT CLOCK TIME 1400-1415 (SCENARIO TIME 0600-0615)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (354 LITERS)*
| |
| WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G-M METER PLUME CLOSED OPEN CONC. AGX 2" PARTICULATE *"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCi'cc) (NET CPM) (NET CPM) 8.00 5.80 BLUE 0.43 0.85 2.96E 10 AS READ AS READ YELLOW 0.04 0.09 2.96E 11 AS READ AS READ GREEN AS READ AS READ 2.96E-12 AS READ AS READ 9.00 6.70 BLUE 0.37 0.73 2.55E 10 AS READ AS READ YELLOW 0.04 0.07 2.55E-11 AS READ AS READ GREEN AS READ AS READ 2.55E-12 AS READ AS READ 10.00 7.50 BLUE 0.25 0.49 1.60E-10 AS READ AS READ YELLOW 0.02 0.05 1.60E-11 AS READ AS READ GREEN AS READ AS READ 1.60E 12 AS READ AS READ 11.00 8.30 BLUE 0.22 0.43 1.41E 10 AS READ AS READ YELLOW 0.02 0.04 1.41 E-11 AS READ AS READ GREEN AS READ AS READ 1.41 E-12 AS READ AS READ 12.00 9.10 BLUE 0.12 0.25 7.62E-11 AS READ AS READ YELLOW 0.01 AS READ 7.62E-12 AS READ AS READ GREEN AS READ AS READ 7.62E-13 AS READ AS READ 13.00 9.90 BLUE 0.11 0.22 6.82E-11 AS READ AS READ YELLOW 0.01 AS READ 6.82E 12 AS READ AS READ GREEN AS READ AS READ 6.82E-13 AS READ AS READ 14.00 10.70 BLUE 0.05 0.11 3.18E 11 AS READ AS READ YELLOW AS READ AS READ 3.18E-12 AS READ AS READ GREEN AS READ AS READ 3.18E-13 AS READ AS READ j NOTES:
| |
| Air sample data are based on a sample volume of 354 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 177 liter sample was collected instead of 354 liters, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The Ludlum 2220 detector efficiency for 1-131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge.
| |
| For analysis of the particulate filter,it is assumed that a G M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the I 131 air concentrations for a 354 liter sample volume.
| |
| | |
| TABLE 9.6.8c Rev. O Page 9.6-12c1 STATE OF MA FIELD DATA AT CLOCK TIME 1400-1415 (SCENARIO TIME 0600-0615) 4 GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E-140/HP-210 G-M METER PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE *"
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) 1.00 SITE BLUE 1.15 2.30 4.90E 20 AS READ AS READ BOUNDARY YELLOW 0.12 0.23 4.90E-21 AS READ AS READ GREEN AS READ AS READ 4.90E 22 AS READ AS READ 2.00 0.90 BLUE 1.81 3.62 2.97E 10 AS READ AS READ YELLOW 0.18 0.36 2.97E 11 AS READ AS READ l GREEN AS READ AS READ 2.97E 12 AS READ AS READ
| |
| . 3.00 1.70 BLUE 1.65 3.30 1.39E-09 AS READ AS READ YELLOW 0.17 0.33 1.39E 10 AS READ AS READ GREEN AS READ AS READ 1.39E-11 AS READ AS READ 4.00 2.60 BLUE 1.11 2.22 9.31 E-10 AS READ AS READ I
| |
| YELLOW 0.11 0.22 9.31E 11 AS READ AS READ 4 GREEN AS READ AS READ 9.31E 12 AS READ AS READ 5.00 3.40 BLUE 0.85 1.70 7.62E-10 AS READ AS READ
| |
| : YELLOW 0.09 0.17 7.62E 11 AS READ AS READ i GREEN AS READ AS READ 7.62E-12 AS READ AS READ i
| |
| 6.00 4.20 BLUE 0.64 1.28 4.81E 10 AS READ AS READ YELLOW 0.06 0.13 4.81E 11 AS READ AS READ GREEN AS READ AS READ 4.81 E-12 AS READ AS READ 7.00 5.00 BLUE 0.52 1.04 4.01 E-10 AS READ AS READ YELLOW 0.05 0.10 4.01 E-11 AS READ AS READ GREEN AS READ AS READ 4.01 E-12 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 20 cu it. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 10 cu ft. sample was collected instead of 20 cu ft, divide the value given in the table by two (2) and provide the resulting va;ue to the players.
| |
| " The E 140/HP-210 detector efficiency for 1131 was assumed to be 0.0025 cpm /dpm with the AGX-2 cartridge.
| |
| I
| |
| "* For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates. ,
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 20 cubic foot sample volume. l
| |
| | |
| TABLE 9.6.8c Rev 0 Page 9.612c2 STATE OF MA FIELD DATA AT CLOCK TIME 1400-1415 (SCENARIO TIME 0600-0615)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E-140/HP 210 G-M METER l
| |
| PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE"* '
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW l131 CARTRIDGE FILTER )
| |
| NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) l 8.00 5.80 BLUE 0.43 0.85 2.96E 10 AS READ AS READ YELLOW AS READ AS READ 2.96E 11 AS READ AS READ j GREEN AS READ AS READ 2.96E 12 AS READ AS READ 1 9.00 6.70 BLUE 0.37 0.73 2.55E-10 .\S READ AS READ YELLOW AS READ AS READ 2.55E 11 AS READ AS READ GREEN AS READ AS READ 2.55E 12 AS READ AS READ 10.00 7.50 BLUE 0.25 0.49 1.60E 10 AS READ AS READ YELLOW AS READ AS READ 1.60E-11 AS READ AS READ GREEN AS READ AS READ 1.60E-12 AS READ AS READ 11.00 8.30 BLUE 0.22 0.43 1.41 E-10 AS READ AS READ YELLOW AS READ AS READ 1.41 E-11 AS READ AS READ l
| |
| GREEN AS READ AS READ 1.41E 12 AS READ AS READ 12.00 9.10 BLUE 0.12 0.25 7.62E-11 AS READ AS READ YELLOW AS READ AS READ 7.62E-12 AS READ AS READ GREEN AS READ AS READ 7.62E 13 AS READ AS READ 13.00 9.90 BLUE 0.11 0.22 6.82E-11 AS READ AS READ YELLOW AS READ AS READ 6.82E 12 AS READ AS READ GREEN AS READ AS READ 6.82E 13 AS READ AS READ 14.00 10.70 BLUE 0.05 0.11 3.18E 11 AS READ AS READ YELLOW AS READ AS READ 1.14E-12 AS READ AS READ GREEN AS READ AS READ 2.49E 13 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 20 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 10 cu ft. sample was collected instead of 20 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E-140/HP-210 detector efficiency for 1-131 was assumed to be 0.0025 cpm /dpm with the AGX 2 cartridge.
| |
| '" For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the I-131 air concentrations for a 20 cubic foot sample volume.
| |
| | |
| I TABLE 9.6.8d Rev. O P ge 9.6-12d1 1 STATE OF NH FIELD DATA AT CLOCK TIME 1400-1415 (SCENARIO TIME 0600-0615)
| |
| GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E-140/HP 210 G-M METER PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE"*
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCLfec) (NET CPM) (NET CPM) 1.00 SITE BLUE 1.15 2.30 4.90E 20 AS READ AS READ BOUNDARY YELLOW 0.12 0.23 4.90E-21 AS READ AS READ GREEN AS READ AS READ 4.90E 22 AS READ AS READ 2.00 0.90 BLUE 1.81 3.62 2.97E-10 AS READ AS READ !
| |
| YELLOW 0.18 0.36 2.97E 11 AS READ AS READ GREEN AS READ AS READ 2.97E 12 AS READ AS READ 3.00 1.70 BLUE 1.65 3.30 1.39E-09 AS READ AS READ YELLOW 0.17 0.33 1.39E 10 AS READ AS READ
| |
| ]
| |
| GREEN AS READ AS READ 1.39E 11 AS READ AS READ l
| |
| 4.00 2.60 BLUE 1.11 2.22 9.31E 10 AS READ AS READ YELLOW 0.11 0.22 9.31 E-11 AS READ AS READ !
| |
| GREEN AS READ AS READ 9.31 E-12 AS READ AS READ 5.00 3.40 BLUE 0.85 1.70 7.62E 10 . AS READ AS READ l YELLOW 0.09 0.17 7.62E-11 AS READ AS READ GREEN AS READ AS READ 7.62E 12 AS READ AS READ 6.00 4.20 BLUE 0.64 1.28 4.81E 10 AS READ AS READ YELLOW 0.06 0.13 4.81 E-11 AS READ AS READ GREEN AS READ AS READ 4.81 E-12 AS READ AS READ 7.00 5.00 BLUE 0.52 1.04 4.01E 10 AS READ AS READ YELLOW 0.05 0.10 4.01E 11 AS READ AS READ GREEN AS READ AS READ 4.01E 12 AS READ AS READ ,
| |
| NOTES:
| |
| Air sample data are based on a sample volume of 10 cu ft. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 5 cu ft. sample was collected instead of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| " The E 140/HP-210 detector efficiency for 1-131 was assumed to be 0.0025 cpm / dom with the AGX-2 cartridge.
| |
| For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the I-131 air concentrations for a 10 cubic foot sample volume. l
| |
| | |
| - -_ _ . _ _ - . - ~ . -
| |
| l TABLE 9.6.8d Rev. O Page 9.612d2 STATE OF NH FIELD DATA AT CLOCK TIME 1400-1415 (SCENARIO TIME 0600-0615)
| |
| I GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)*
| |
| WAIST AND GROUND LEVEL READINGS E 140/HP 210 G-M METER PLUME CLOSED OPEN CONC. AGX-2" PARTICULATE"'
| |
| SEGMENT DISTANCE MAP WINDOW WINDOW 1131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) (uCl/cc) (NET CPM) (NET CPM) 8.00 5.80 BLUE 0.43 0.85 2.96E-10 AS READ AS READ YELLOW AS READ AS READ 2.96E 11 AS READ AS READ GREEN AS READ AS READ 2.96E-12 AS READ AS READ 9.00 6.70 BLUE 0.37 0.73 2.55E 10 AS READ AS READ YELLOW AS READ AS READ 2.55E-11 AS READ AS READ GREEN AS READ AS READ 2.55E 12 AS READ AS READ l l
| |
| 10.00 7.50 BLUE 0.25 0.49 1.60E 10 AS READ AS READ
| |
| )
| |
| YELLOW AS READ AS READ 1.60E-11 AS READ AS READ
| |
| ~
| |
| GREEN AS READ AS READ 1.60E-12 AS READ AS READ 11.00 8.30 BLUE 0.22 0.43 1.41E 10 AS READ AS READ !
| |
| YELLOW AS READ AS READ 1.41E 11 AS READ AS READ GREEN AS READ AS READ 1.41E 12 AS READ AS READ 12.00 9.10 BLUE 0.12 0.25 7.62E-11 AS READ AS READ YELLOW AS READ AS READ 7.62E 12 AS READ AS READ GREEN AS READ AS READ 7.62E 13 AS READ AS READ 13.00 9.90 BLUE 0.11 0.22 6.82E 11 AS READ AS READ YELLOW AS READ AS READ 6.82E 12 AS READ AS READ GREEN AS READ AS READ 6.82E 13 AS READ AS READ 14.00 10.70 BLUE 0.05 0.11 3.18E-11 AS READ AS READ YELLOW AS READ AS READ 1.14E 12 AS READ AS READ GREEN AS READ AS READ 2.49E 13 AS READ AS READ NOTES:
| |
| Air sample data are based on a sample volume of 10 cu it. If different volumes are collected, the alt sample data l provided in the tables should be adjusted proportionally. For example, if a 5 cu ft. sample was collected instead of 10 cu ft, divide the value given in the table by two (2) and provide the resulting value to the players.
| |
| The E-140/HP 210 detector efficiency for 6131 was assumed to be 0.0025 cpm /dpm with the AGX-2 cartridge.
| |
| For analysis of the particulate filter, it is assumed that a G-M survey meter is used to obtain the sample count rates.
| |
| The filter count rate was estimated from the 1-131 air concentrations for a 10 cubic foot sample volume.
| |
| u__
| |
| | |
| Rev. O Paga 10.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1997 10.1 ON-SITE METEOROLOGICAL DATA LOWER LOWER LOWER RAIN LOWER A771 PRESS CLOCK UPPER UPPER UPPER SPEED DIR DELTAT INCHES TEMP ' INCHES TIME SPEED DIR DELTAT DEGF MPH DEGREES DEGF 1/4 HR DEGF MERCURY MPH DEGREES (Note 1) (Note 2)
| |
| -0.40 4.20 307.00 -0.32 0.00 28.00 30.00 08:00 5.40 320.00 309.00 -0.40 0.00 28.30 30.10 08:15 5.30 322.00 -0.50 4.00
| |
| -0.40 4.00 312.00 -0.32 0.00 28.50 30.10 08:30 5.20 326.00 330.00 -0.60 4.00 316.00 -0.48 0.00 28.70 30.20 08:45 5.20 331.00 -0.50 4.00 317.00 -0.40 0.00 28.80 30.20 09:00 5.30 5.10 329.00 -0.60 4.30 315.00 -0.48 0.00 29.40 30.20 09:15
| |
| -0.60 4.30 319.00 -0.48 0.00 29.90 30.30 09:30 5.10 333.00
| |
| -0.50 4.30 321.00 -0.40 0.00 31.00 30.30 09:45 5.20 335.00 10:00 5.10 340.00 -0.60 4.20 326.00 -0.48 0.00 33.00 30.40 10:15 5.20 345.00 -0.00 4.20 331.00 -0.64 0.00 35.00 30.40 10:30 5.30 352.00 -0.90 3.40 337.00 -0.72 0.00 37.00 30.30 10:45 5.40 357.00 -1.00 3.00 342.00 -0.80 0.00 37.50 30.30 11:00 5.60 355.00 -1.10 2.60 340.00 -0.88 0.00 38.20 30.30 11:15 5.60 2.00 -1.10 3.00 1.00 -0.88 0.00 38.60 30.20 11:30 5.80 5.00 -1.10 4.00 4.00 -0.88 0.00 38.90 30.20 11:45 5.80 3.00 -1.00 5.00 2.00 -0.80 0.00 39.20 30.20 12:00 6.00 4.00 -1.20 4.00 3.00 -0.96 0.00 39.50 30.20 12:15 6.10 6.00 -1.10 3.60 5.00 -0.88 0.00 40.00 30.20 12:30 6.20 10.00 -1.00 2.60 9.00 -0.80 0.00 41.00 30.10 12:45 6.40 7.00 -1.00 2.70 6.00 -0.80 0.00 43.00 30.10 13:00 6.50 4.00 -0.90 2.60 3.00 -0.72 0.00 41.70 30.10 13:15 6.60 6.00 -0.90 2.60 5.00 -0.72 0.00 40.60 30.10 13:30 6.50 5.00 -0.80 2.40 4.00 -0.64 0.00 39.90 30.10 13:45 6.70 7.00 -0.80 2.70 6.00 -0.64 0.00 39.40 30.10 ;
| |
| 14:00 6.90 9.00 -0.90 2.90 8.00 -0.72 0.00 38.80 30.10 14:15 7.00 11.00 -0.80 2.80 10.00 -0.64 0.00 37.90 30.10 14:30 7.20 12.00 -0.80 2.70 11.00 -0.64 0.00 37.30 30.10 14:45 7.50 14.00 -0.80 2.80 13.00 -0.64 0.00 36.90 30.10 15:00 7.10 15.00 -0.80 2.60 14.00 -0.64 0.00 36.50 30.10 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.
| |
| | |
| -- ._ . -. . . ~ - . -- . _ _ - -
| |
| Rev. O Page 10.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1997 10.2 GENERAL AREA NWS FORECASTS (See Note) -
| |
| Synopsis (08:00)
| |
| A low pressure system will move off to the east today, causing the cloud cover to diminish and a wind shift from the northwest to the north.
| |
| Valid (08:00-12:00)_
| |
| Mostly to partly cloudy this morning. Temperatures rising from current 20's into the low 40's. Northwesterly winds from 3 to 6 MPH becoming northerly around midday.
| |
| Valid (12:00-16:00)
| |
| Partly cloudy. High temperature 40-45 then fallin5 to the mid 30's.
| |
| Northerly winds from 4 to 8 MPH.
| |
| Valid (16:00-23:00)
| |
| Partly cloudy. Low temperatures in the upper 20's. Light northerly winds.
| |
| PLANT / EOF WEATHER OBSERVATIONS (See Note) - Valid (08:00-17:00)
| |
| Time General Observations 08:00-11:00 Partly cloudy with light to moderate winds.
| |
| 11:00-14:00 Partly cloudy with light to moderate winds.
| |
| 14:00-17:00 Partly cloudy with light winds.
| |
| NOTE: GENERAL AREA NWS FORECASTS SHOULD BE PROVIDED UPON REQUEST. PIANT/ EOF WEATHER OBSERVATIONS WILL BE POSTED AS APPROPRIATE.
| |
| | |
| Rev. O Page 10.2 2 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1997 10.2 VERMONT YANKEE SITE FORECAST To be provided to the ESC Meteorologist by the ESC Controller at 08:15.
| |
| i WEATHER FORECAST FOR SITE: VY - VERNON Date of Forecast: 03-19-97 Time of Forecast: 08:15 Current Site Meteorology (as of 08:15 ):
| |
| 13aggr, Wind Sneed Wind Direction Qg113 h Preefoltation Tenmerature class Lower 4.2 MPM 309 DEG FROM 0.4 DEG F E 0.00 IN/15 MIM Upper 5.3 MPH 322 DEG FROM 0.5 DEG F E Forecast $lte Meteorology:
| |
| Ijm Sensor Wind Snead Wind D{rection gg113 h Praefoffation Terroerature class 08:15- Lower 4.0 MPH 320 DEG FROM 0.4 DEG F E 10:00 0.00 IN/15 MIN upper 5.0 MPH 330 DEG FROM 0.6 DEG F E 10:00- Lower 4.5 MPH 0 DEG FROM 0.9 DEG F 0 .
| |
| 12:00 0.00 IN/15 MIN Upper 5.5 MPH 5 DEC FROM 1.2 DEC F 0 12:00- Lower 3.0 MPH 7 DEG FROM 0.8 DEC F D 14:00 0.00 IN/15 MIN l
| |
| Upper 6.5 MPH 10 DEG FROM 0.9 DEC F 0 Nation.- ? sather Service Forecast for site region:
| |
| Mostly to partly cloudy this morning. Temperatures rising from current 20's into the low 40's. Northwesterly winds from 3 to 6 MPH becoming northerly around midday.
| |
| Special Weather Statements:
| |
| None 9
| |
| | |
| Rev. O Page 10.2-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1997 10.2 VERMONT YANKEE SITE FORECAST To be provided to the ESC Meteorologist by the ESC Controller at 10:00.
| |
| WEATHER FORECAST FOR SITE: VY - VERNON Date of Forecast: 03-19-97 Time of Forecast: 10:00 Current Site Meteorology (as of 10:00 ):
| |
| $ggggt Wind Snead Wind Direction Ogi13 h Precinitation T - rature clama tower 4.2 MPH 326 DEG FROM 0.5 DEG F D 0.00 IN/15 MIN upper 5.1 MPH 343 DEC FROM 0.6 DEC F E Forecast Site Meteorology:
| |
| h $gggt Wind Enned Wind Direction 33118 h Precinitation T - rature clama es 10:00- " " " " ~ ~
| |
| - m er
| |
| . 4.5 MPN 0 DEe. FROM -0.9 DEC F 0 12:00 0.00 IN/15 MIN upper 5.5 MPH 5 DEG FROM 1.2 DEG F 0 12:00- Lower 3.0 MPH 7 DEG FRON *0.8 DEC F 0 14:00 0.00 IN/15 MIN upper 6.5 MPN 10 DEC FROM 0.9 DEC F D 14:00- Lower 2.7 WM 12 DEG FRGE 0.5 DEC F 0 ;
| |
| 16:00 0.00 IN/15 MIN upper 7.0 MPH 15 DEG FROM 0.6 DEG F E National Weather Service Forecast for site region:
| |
| l Mostly to partly cloudy this morning. Temperatures rising from current 20's into the low 40's. Northwesterly winds from 3 to 6 MPH becoming northerly around midday.
| |
| Special Weather Statements:
| |
| None
| |
| | |
| Rev. O Page 10.2-4 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1997 10.2 VERMONT YANKEE SITE FORECAST To be provided to the ESC Meteorologist by the ESC Controller at 12:00.
| |
| 3 WEATHER FORECAST FOR SITE: VY - VERNON Date of Forecast: 03-19-97 Time of Forecast: 12:00 Current Site Meteorology (as of 12:00 ):
| |
| Wirrf Direction h Precinital190 igaggt M Q3113 Temerature Ctass inmed 4 DEG FROM 1.0 DEG F 0 Lower 4.0 MPH 0.00 IN/15 MIN Upper 6.0 MPH 4 DEG FROM 1.2 DEG F D Forecast Site Meteorology:
| |
| gig l Wind Direction Q3113 h Precinitation h jggggg tamed Temnerature class 3.0 MPM 7 DEG FRWI 0.8 DEC F 0 12:00- Lower 0.00 IN/15 MIN 14:00 -0.9 OEG F D Upper 6.5 MPH 10 DEC FROM 12 DEG FROM 0.5 DEG F D 14:00- Lower 2.7 MPH 0.00 IN/15 MIN 16:00 -0.6 DEG F E Upper 7.0 MPH 15 DEG FROM tower 2.0 MPH 20 DEG FROM 0.0 DEC F E 16:00- 0.00 IN/15 MIN 18:00 0.4 DEC F E l upper 5.5 MPH 25 DEG FROM National Weather Service Forecast for site region:
| |
| Mostly to partly cloudy this morning. Temperatures rising from current 20's into the low 40's. Northwesterly winds from 3 to 6 MPH becoming northerly around midday.
| |
| Special Weather Statements:
| |
| None
| |
| ---_}}
| |
