Text

Emergency Response Preparedness Exercise;1993 Plume Pathway Exercise Manual.
	ML20046C876
Person / Time
Site:	Vermont Yankee
Issue date:	01/22/1993
From:	; VERMONT YANKEE NUCLEAR POWER CORP.
To:	;
Shared Package
ML20046C874	List: ML20046C873; ML20046C876;
References
	PROC-930122-01, NUDOCS 9308120348
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                                  ' EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 TABLE OF CONTENTS                                                   1 i

Section Title R ev... 1.0 INTP,0 DUCTION 1.1 Exercise Schedule 0 1.2 Participating Centers / Agencies 0 1.3 Abbreviations and Definitions 0 1.4 References 0 2.0 EXERCISE OBJECTIVES AND EXTENT OF PIAY 2.1 Vermont Yankee 0-2.2 State of Vermont 0 2.3 State of New Hampshire 0 i 2.4 Commonwealth of Massachusetts 0 3.0 EXERCISE GUIDELINES AND SCOPE 3.1 Exercise Guidelines 0 3.2 Player Instructions and Ground Rules 0 3.3 Procedure Execution List 0 4.0 CONTROLLER AND OBSERVER INFORMATION 4.1 Assignments 0 4.2 Controller and Observer Exercise Guidance.. 0-4.3 Controller and Observer Evaluation Criteria 0 5.0 EXERCISE SCENARIO 5.1 Initial Conditions 0 5.2 Narrative Summary 0-5.3 Scenario Timeline 0 5.4 Detailed Sequence of Events 0 6.0 EXERCISE MESSACES 6.1 Command Cards 0 6.2 Message Cards 0 7.0 STATION EVENT DATA l 71 Events Summary 0 7.2 Event Miniscenarios 0 i

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i i f VERMONT YANKEE NUCLEAR POWER STATION ; EMERGENCY RESPONSE PREPAREDNESS EXERCISE [ 1993 ( TABLE OF CONTENTS t Section Title Rev. . F 8.0 OPERATIONAL DATA 0 l' 9.0 RADIOLOGICAL DATA 0 f 9.1 Area Radiation Monitors 0 ; 9.2 Process Monitors 0 9.3 In-Plant Radiation Levels 0 9.4 Plant Chemistry Data 0 ; 9.5 Radiological Sample Dose Rates 0 9.6 Plant Vent Stack Release Data 0 9.7 Field Monitoring Maps and Data 0 10.0 METEQROLOGICAL DATA 10.1 On-Site Meteorological Data 0 10.2 General Area NWS Forecasts 0

10.3 NWS Surface Maps 0 7

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L. J. - . . - - 6 e a a . .a, VERMONT YANKEE NUCLEAR POWER STATION ; EMERGENCY RESPONSE PREPAREDNESS EXERCISE , 1993 i I P 4

1.0 INTRODUCTION

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Rev. O Page 1.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993 1.1 EXERCISE SCHEDULE A. On-Site Controller and Observer Briefine .I Date: To be Determined Time: To be Determined j Location: Vermont Yankee Corporate Office, Brattleboro, Vermont

Purpose:

Briefing on Exercise Activities and Assignments Attendees: On-Site Controllers and Observers ; B. Off-Site Controller and Observer Briefine Date: .To Be Determined Time: To Be Determined Location: To Be Determined

Purpose:

Briefing on Exercise Activities and Assignments Attendees: Off-Site Controllers and Observers C. NRC Entrance and Exercise Briefine Date: To Be Determined Time: To Be Determined Location: Vermont Yankee Corporate Office, Brattleboro, Vermont

Purpose:

NRC Briefing and Review of Exercise Scenario Attendees: NRC Evaluators, Vermont Yankee Management and Controllers D. FEMA Entrance and Exercise Briefine Date: To Be Determined Time: To Be Determined Location: Vermont Yankee Corporate Office, Brattleboro, Vermont

Purpose:

FEMA Briefing and Review of Exercise Scenario Attendees: FEMA Evaluators, Vermont Yankee and State Representatives E. Exercise Date: To Be Determined (Week of April 25, 1993) , Time: Unannounced and Off-hours Location: Vermont Yankee Emergency Response Centers and Designated State and Local Emergency Response Centers ;

Purpose:

Emergency Response Preparedness Exercise , Attendees: Vermont Yankee Emergency Response Organization, State and Local Emergency Response Organizations from Vermont, New Hampshire and Massachusetts, Controllers and Observers, NRC and FEMA Evaluators and Yankee Atomic Engineering Support Center Staff l

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Rev. 0 Page 1.1-2 ; VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993 1.1 EXERCISE SCHEDULE (continued) F. Exercise Debriefine Date: Day of Exercise Time: To be announced during or immediately following the exercise Location: To be determined by the respective Emergency Response Facility Controller

Purpose:

Debrief Players, Observers and Controllers , Attendees: Controllers, Observers and Key Participants C. Controller Debriefinc Date: To Be Determined Time: To Be Determined Location: To Be Determined

Purpose:

Exercise Debriefing Attendees: Exercise Coordinator and Controllers H. Exercise Criticue Date: To Be Determined l Time: To Be Determined Location: Vermont Yankee Corporate Office, Brattleboro, Vermont

Purpose:

Utility Self-Critique /NRC Preliminary Findings Attendees: Vermont Yankee Management, NRC Evaluators, Exercise - Controllers (Observers as needed) and Vermont Yankee Key ' Participants I. FEMA State Debriefine Date: To Be Determined i Time: To Be Determined I Location: To Be Determined

Purpose:

Debrief State Representatives Attendees: State Representatives, FEMA and Vermont Yankee l I l l 1 a .

Rev. O Page 1.1-3 I VERMONT YANKEE NUCLEAR PCWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE - 1993 1.1 EXERCISE SCHEDULE (continued) J. FEMA Public Meetinc Date: To Be Determined Time: To Be Determined Location: To Be Determined -

Purpose:

Present FEMA Preliminary Exercise Findings and Assessment , Attendees: State Representatives, FEMA, Vermont Yankee and General l I Public t

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I i b Rev. 0' Page 1,2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE . 1993 l 1.2 PARTICIPATING CENTERS / AGENCIES ,

VERMONT YANKEE NUCLEAR POWER CORPORATION { Vermont Yankee Emergency Response Organization

Facilities ,

Vermont Yankee Nuclear Power Station - Vernon, Vermont

Control Room (notification and communications functions only) e Technical Support Center (2nd floor of Administration Building)
Operations Support Center (1st floor of Administration Building)
Energy Information Center (Covernor Hunt House). 1 Vermont Yankee Training Center - Brattleboro, Vermont t
Simulator Room (Control Room functions, 1st floor of Training Building) l r

e Emergency Operations Facility / Recovery Center (1st floor of Training Building)

News Media Center (1st and 2nd floor of Training Building) ,

YANKEE ATOMIC ELECTRIC COMPANY Yankee Nuclear Services Division - Bolton, Massachusetts i Facility

Engineering Support Center l

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Rev. O Page 1.2-2 l STATE OF VERMONT Kev Particinatinc State Acencies e e Vermont Emergency Management e Vermont State Health Department 1 Facilities 1 l e State Varning Point, Vermont State Police - Vaterbury, Vermont

Emergency Operations Center - Waterbury, Vermont incident Field Office Dummerston, Vermont 1 e -

l e Department of Health Laboratory - Burlington, Vermont l

Emergency Operations Facility / Recovery Center - Brattleboro, Vermont e News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont Kev Participatine Local Arencies e Brattleboro, Dummerston, Guilford, Halifax and Vernon Emergency Management i Agencies l

Facilities j e Brattleboro Emergency Operations Center (EOC) - Brattleboro Town Hall e Dummerston EOC - Dummerston Town Office Building e Guilford EOC - Guilford Fire Station !

       . Halifax EOC - Halifax Fire Station                                            j 2

e Vernon EOC - Vernon Fire Station ) l STATE OF NEW HAMPSHIRE 1

Kev Participatinc State Acencies j e New Hampshire Office of Emergency Management

Department of Pdblic Health Service j l

Facilities j e State Police Communications Center and Troop C - Concord, New Hampshire and

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Rev. O Page 1,2-3 Keene, New Hampshire e Southwestern Fire Mutual Aid Dispatch Center - Keene, New Hampshire e Emergency Operations Center - Concord, New Hampshire e Incident Field Office - Keene, New Hampshire e Emergency Operations Facility / Recovery Center - Brattleboro, Vermont

News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont Kev Participatine Local Agencies e Chesterfield, Hinsdale, Richmond, Swanzey and Winchester Emergency ;

Management Agencies Facilities e Chesterfield Emergency Operations Center (EOC) - Chesterfield Town Office e Hinsdale EOC - Hinsdale Fire Station / Town Hall e Richmond EOC - Richmond Civil Defense Building e Swanzey EOC - Swanzey Center Fire Station e Winchester EOC - Winchester Emergency Service Building , b COMMONWEALTH OF MASSACHUSETTS Kev Participatine State Agencies and Radio Stations e Massachusetts Emergency Management Agency e Massachusetts Department of Public Health e WRSI/WGAM Radio, Creenfield e WHYN Radio, Springfield e WHAI Radio, Creenfield 9 Facilities e Emergency Operations Center - Framingham, Massachusetts -

Area IV Emergency Operations Center - Belchertown, Massachusetts e Emergency Operations Facility / Recovery Center - Brattleboro, Vermont
News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont i

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Kev Participatine Local Agencies /Oreanizations l

Bernardston, Colrain, Gill, Greenfield. Leyden, Northfield and.Warwick Emergency Management Agencies ;

e Franklin County Dispatch l Facilities e Bernardston Emergency Operations Center (EOC) - Bernardston Fire Station - e Colrain EOC - Colrain Fire Station e Gill EOC - Gill Fire Station e Greenfield EOC - Greenfield Fire Station

      .      Leyden EOC - Leyden Fire Station e      Northfield EOC - Town Hall                                                            >

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I b e b VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPARE 0 NESS EXERCISE F 1993

                                                     . .                                                          I 1.3 ABBREVIATIONS AND DEFINITIONS                                                              ,

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Rev. O Page 1.3-1 VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 1.3 ABBREVIATIONS AND DEFINITIONS A. Abbreviations

                  .      AO           -

Auxiliary Operator

                  .      A0G          -   Advanced Off-Gas System Average Power Range Monitor
                  .      APRM         -
                  .      ARM          -

Area Radiation Monitor

                  .      ATWS         -

Anticipated Transient Without Scram

                  .      CR           -

Control Room / Control Rod

                  .      CRD          -

Control Rod Drive

                   . CRP           -

Control Room Panel

                   . CS            -

Core Spray

                   . DC0           -

Duty and Call Officers

                   . DW            -

Drywell ,

                   . EAL           -

Emergency Action Level

                   . ECCS          -

Emergency Core Cooling System

                   . ENS           -

Emergency Notification System

                   . EOC           -

Emergency Operations Center

                   . E0F           -

Emergency Operations facility

                   . EPR            - Electric Pressure Regulator
                   . EPZ            -

Emergency Planning Zone ]

                   . ERF            -

Emergency Response Facility

                   . ESC            -

Engineering Support Center

                    . FCV           -

Flow Control Valve

                    . FEMA          -

Federal Emergency Management Agency R15\128 I e

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           .        FW           -

Feedwater

           .        GE           -    General Emergency
           .        HPCI         -

High Pressure Coolant Injection

           .        HPN          -

Health Physics Network

           .        HRNG         -

High Range Noble Gas :

           .        LNP          -

Loss of Normal Power

           .        LPCI         -    Low Pressure Coolant Injection
           .        MCC          -

Motor Control Center

           .        MPR          -    Mechanic . Pressure Regulator
           .        MSIV         -

Main Steam Isolation Valve

           .        NAS          -

Nuclear Alert System

           .        NG            -

Noble Gases ,

           .        NRC           -

Nuclear Regulatory Commission

           .        NWS           -

National Weather Service

            .       OBE           -

Operating Basis Earthquake <

            .       OSC           -

Operations Support Center

            .       PASS          -   Post-Accident Sampling System
            .       PCIS          -

Primary Containment Isolation System

            .       PED            -

Plant Emergency Director

            .       PVS           -

Plant Vent Stack

            .       RA             -

Radiological Assistant

            .       RCIC           -  Reactor Core Isolation Cooling Rhode Island, Eastern Massachusetts, and Vermont
                                                    ~
            .        REMVEC -

Energy Control.

             .       RPS           -  Reactor Protection System
             .       RR            -  Reactor Recirculation System
             .       RRU           -

Reactor Rec'irculation Unit .

             .       RWCU          -  Reactor Water Clean-Up
             .       Rx             -

Reactor

             .       SBGTS          -

Standby Gas Treatment System R15\128 i

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                         .             SCR       ' -

Simulator Control Room -1

                         .             SDI         -

Seismic Damage Indication

                         .             SJAE        -

Steam Jet Air Ejector

                         .             SLC         -

Standby Liquid Control

                         .             SRM         -

Site Recovery Manager / Source Range. Monitor ;

                         .             TSC         -

Technical Support Center.

                         .             VY          -

Vermont Yankee ,

                         .             VYNPC       -

Vermont Yankee Nuclear Power Corporation ;

                         .             VYNPS       -

Vermont Yankee Nuclear Power Station , . YNSD - Yankee Nuclear Services Division P 5 1

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Rev. O ; Page 1.3-4 i B. Definitions , I

                . Al ert                 - An emergency classification which is defined as an actual or                    l potential substantial degradation             '

of the level of safety of the- , plant.

                . Controller             -

A member of an exercise control i group. Each Controller may.be i assigned to one or more activities or functions for the purpose of keeping the action going according l to a scenario, resolving differences, supervising and: assisting as needed.

                . Controller Message     -

Controller messages provide supplemental information pertinent to the anticipated player response actions. These may direct ' specific i actions (" command cards") or ; provide clarification to an existing condition (* message cards").

                . Critique               - A meeting of key participants in an            '

exercise, usually held shortly af ter its conclusion, to identify weaknesses and deficiencies in emergency response capabilities . l R15\128

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         . Emergency Action     - Specific instrument readings, Levels                  system levels or event observation and/or radiological levels which       .

initiate event classification, 1 notification procedures, protective actions, and/or the mobilization of the emergency response organization. These are specific threshold readings or observations indicating system failures or abnormalities.

         . Emergency Assistance - General term used to refer to the Personnel               radiation monitoring teams, sample analysis team, and in-plant search and rescue teams.
         . Emergency Operations - Areas designated by state / local       ),

Center representatives as Emergency Plan assembly areas for their respective staffs.

         . Emergency Operations - An emergency response facility Facility / Recovery     (Vermont Yankee Training Center,        i Center                  Brattleboro, Vermont) which             I evaluates off-site accident             !

consequences and coordinates emergency response and assistance .! with all off-site agencies. R15\128 i l

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       . Emergency Planning  -

The areas for which planning is , Zones recommended to assure that prompt and effective actions can be taken to protect the public in the event of an accident. The two zones are the 10-mile radius plume inhalation-exposure pathway zone and the 50 mile radius ingestion exposure pathway zone.

       . Engineering Support -

A YNSD emergency support facility Center (Yankee Atomic Electric Corporate Headquarters) established to provide aoditional engineering support to the affected site in ] plant assessment and recovery ; operations.

       . Exercise            -

A demonstration of the adequacy.and content of the emergency plan, implementing procedures, methods, and equipment.

       . Full Participation  - An exercise which tests as much of Exercise               the licensee, state, and local plans as is. reasonably achievable without mandatory public                 :

participation and inconvenience. R15\128

Rev. O Page 1.3-7

            . General Emergency  -

An emergency classification which is defined as actual or imminent substantial core degradation or. melting with potential for. loss of containment integrity.

            . News Media Center  - An emergency response facility.

(VYNPC Corporate Offices, Brattleboro, Vermont) dedicated to the news media for the purpose of disseminating and coordinating information concerning accident conditions. All activities conducted within this center will be the responsibility of the Vermont Yankee Nuclear Information Director.

            . Observer           - A member of an exercise control group. Each Observer may be assigned to one or more activities or functions for the purpose of evaluating, recording, and reporting the strengths and weaknesses, and making recommendations for improvement.

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             . Operations Support  - An emergency response facility                          l Center                  (1st floor. Administration                           1 Building) established to muster 1

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l l Rev. O Page 1.3-8 skilled emergency response- ; personnel to perform activities in the plant.

              . Protective Action - Those emergency measures taken to effectively mitigate the consequences of an accident by minimizing.the radiological exposure.that would likely occur if' such actions were not undertaken.
              . Protective Action - Projected radiological dose Guides                 values to the public which warrant     ,

protective actions following an uncontrolled release of radioactive material. Protective actions would be warranted provided the reduction in the individual dose is not offset by excessive risks to individual safety in implementing such action.

              . Scenario          --

The hypothetical situation, from start to finish, in an exercise or drill which is the theme or basis upon which the action or play of the events follow.

              . Site              - That property within the fenced boundary of Vermont Yankee which is R15\128

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                                                              -Page 1.3-9 owned by the Vertnont' Yankee Nuclear Power Corporation.
        . Site Area Emergency  - An emergency. Classification that indicates an event which involves likely or actual major failures of plant functions needed for the protection of the public.
        . Small-Scale Exercise - An exercise which tests as much of the licensee emergency plan and procedures with minimal, voluntary participation of state and local government agencies.
        . Technical Support    - An emergency response facility Center                  (2nd floor, Administration Building) with the capability to          ,

assess and mitigate the accident l using plant parameters and highly qualified technical personnel. Also, assists in accident recovery operations.

         . Unusual Event        -

An emergency classification that ! 1 indicates a potential degradation j of plant safety margins which is not likely to affect personnel on-site or the public off-site or R15\128 l l l l

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                                                                                                           .Page 1.3-10 result in radioactive releases-requiring off-site monitoring.

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                           . Yankee Nuclear                   - A division of Yankee Atomic                                  !

Services Division Electric Company. An Engineering I (YNSD) support organization'which provides emergency response support to Vermont Yankee upon request. R15\128

I l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 l J

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1.4 REFERENCES

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                                                                                                                           .1 VERMONT YANKEE NUCLEAR POTTER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 4-

1.4 REFERENCES

1. Vermont Yankee Nuclear Power Station Emergency Plan

2. Vermont Yankee Nuclear Power Station Emergency Plan Implementing Procedures

3. Vermont Yankee Nuclear Power Station Final Safety Analysis Report

4. Vermont Yankee Nuclear Power Corporation - Communications Department Emergency Rc9ponse Plan and Procedures

5. Vermont Yankee Nuclear Power Station Emergency Operating Procedures j

6. Vermont Yankee Nuclear Power Station Core Damage Assessment Methodology .

7. Yankee Atomic Electric Company

a. " RASCAL" Computer Model, Version 1, Modification 2

b. "M:.rPAC" (METeoro?ogical Package) Dose Assessment Computer Model, Version 4.1

8. Martin, G.F., et al., " Report to the NRC on Guidance for preparing ,

Scenarios for Emergency ' Preparedness Exercises at Nuclear Generating ' Stations," March 1986, USNRC, NUREC/CR-3365 l i

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VERMON* YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1951

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2.0 EXERCISE OBJECTIVES AND EXTENT OF PIAY 9 I L e 4 s e

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2.1 OBJECTIVES AND EXTENT OF PLAY - VERMONT YANKEE Extent of Play A. Emeroency Classification and Accident Assessment

1. Demonstrate the ability of Control Room A.1 The scenario events initiated on the simulator personnel to recognize emergency will provide the operational and radiological data initiating events and properly classify to allow personnel to demonstrate this objective the condition in accordance with by implementing Procedure A.P. 3125. Emergency pre-established emergency action levels. Plan Classification and Action Level Scheme.

2. Demonstrate the ability of Control Room A.2 The scenario will provide technical information to personnel and TSC staff to coordinate the players which will allow them to analyze plant assessment of plant conditions and conditions and initiate corrective actions in corrective actions to mitigate accident accordance with established procedures.

conditions.

3. Demonstrate that information concerning A.3 Telephone communications links will be established plant conditions can be transmitted by communicators between the Simulator Control between the Control Room and TSC in a Room (SCR) and the various Emergency Response timely manner. Facilities in order to transmit key information and data.

4. Demonstrate the ability of the TSC staff A.4 The scenario events will enable the TSC to to initiate and coordinate correctiva coordinate in-plant corrective actions through the actions in an efficient and timely manner. use of OSC personnel.

I

5. Demonstrate the ability of appropriate TSC- A.5 The scenario includes events which allow for staff to participate with the Control Room discussion between the Control Room, TSC. and and the EOF /RC in emergency classification EOF /RC staff on classification.

and EAL discussions.

Indicates NRC identified item from the 1992 exercise.

R15\211

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Rev. O Page 2.1-2 Extent of Play

6. Demonstrate the ability to assess data A.6 Scenario events will require Chemistry and from appropriate chem:stry samples in Radiation Protection Technicians to obtain samples support of accident assessment activities from the Reactor Coolant System. Containment

, and plant conditions. Atmosphere or the Plant Vent Stack. ACTUAL SAMPLING AND ACTUAL MANIPULATION OF SAMPLING . SYSTEM COMPONENTS WILL BE SIMULATED. However, sampling activities to obtain and analyze samples will be discussed and sample results will be provided by the Observer. i

7. Demonstrate the ability to effectively use A.7 Emergency Response Facility Information System the ERFIS in the assessment and trending (ERFIS) terminals at the TSC and EOF /RC will be linked to the SCR to receive and transmit scenario

of plant conditions. data. This will allow Emergency Response Facility staff personnel the opportunity to-demonstrate the effectiveness of ERFIS under simulated emergency conditions. B. Notification and Communication

1. Demonstrate that messages are transmitted B.1 Various communications links will be established in an accurate and timely manner and that between emergency response facilities in order to decisions, information, and messages are- transmit information and data. Record keeping and properly logged and documented.* documentation will be demonstrated in accordance with Procedure OP-3504. " Emergency Communications."

Communications and transfer of data between facilities will be evaluated-for timeliness and completeness.

Indicates NRC identified item from the 1992 exercise.

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Rev. O Page 2.1-3 Extent of Play

2. Demonstrate the capability to notify B.2 Vermont Yankee staff. NRC. and state authorities federdl and state authorities of emergency shall be notified in accordance with established

,i classifications and significant changes in procedures. NRC will be notified by utilizing the - plant status in accordance with FTS 2000 ENS phone. The State authorities will be established procedures. notified through the Nuclear Alert System (0 range Phone). ; i' 3. Demonstrate that appropriate status boards B.3 Status Boards (where provided) will be utilized by " are utilized to display pertinent accident response personnel to display pertinent information at the various emergency information. Status Board Caretakers will be response facilities. assigned by facility coordinators to. maintain the status boards with current information.

4. Demonstrate that adequate emergency B.4 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 Communications."

and state authorities.

5. Demonstrate that Off-Site' Monitoring Teams B.5 Off-Site Monitoring Teams will be dispatched to can' appropriately identify their location the field and directed to specific sample points when reporting sample results to the EOF. for monitoring activitie,s.

6. Demonstrate the ability to provide B.6 During the period that the Off-Site Monitoring adequate briefings to Off-Site Monitoring Tedms will be in the. field. scenario events may Teams as conditions and.information requirc that periodic updates be transmitted to change. the te3ms in the field.

Indicates NRC. identified item from.the 1992. exercise.

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Rev. O Page 2.1-4 Extent of Play C. Direction and Control

1. Demonstrate the proper transfer of C.1 Scenario events require the activation of the responsibilities from the SS/ PED to the Emergency Response Organization. As each position Duty Call Officer and subsequently to the of authority is activated, responsibilities TSC Coordinator and Site Recovery Manager associated with that position will be assumed from as appropriate, the SS/ PED up to the Site Recovery Manager.

2. Demonstrate the capability of key C.2 All emergency response facilities have designated emergency response facility management coordinators who will direct and coordinate personnel to direct and coordinate their emergency response activities in their particular respective emergency response activities area of responsibility.

in an efficient and timely manner.

3. Demonstrate appropriate coordination of C.3 The SCR will initially contact the federal and activities with federal and state ctate agencies, providing them with appropriate government agencies. information on plant conditions and emergency status. This function will pass to the TSC and EDF/RC after the facilities are activated.

D. Emergency Response Facilities f

1. Demonstrate the ability of station and D.1 Scenario events will require activation corporate personnel to activate and staff D.2 and operation of Vermont Yankee emergency response the emergency response facilities in a facilities. The SCR, Control Room (communication timely manner. functions only) TSC, OSC, EOF /RC, News Media Center and Engineering Support Center will be

2. Demonstrate and test the adequacy and activated in accordance with established effectiveness of emergency response ,

procedures. Designated plant and corporate facilities. operations, and equipment. emergency response personnel will participate in the exercise. Indicates NRC identified item from the 1992 exercise. RIM 231

Rev. O Page 2.1-5 Extent of Plav I E. Plant Augmentation and Staffing , a

1. Demonstrate the adequacy of plant E.1 Shift personnel should demonstrate the use of the '

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. I resources.

2. Demonstrate the ability to utilize outside E.2 The Yankee Nuclear Services Division's Engineering resources to provide technical assistance Support Center (ESC) will be contacted and and logistical support. activated for this exercise. The ESC will provide l technical and logistical support as requested by Vermont Yankee.

3. Demonstrate the ability to maintain shift E.3 Available resources will be evaluated and assigned staffing and manpower to provide for, to support extended operations.

future manpower and logistics needs. F. Radiological Exposure Control

1. Demonstrate the ability to provide F.1 Scenario events will require OSC On-Site l adequate radiation protection controls for F.2 Assistance' Teams to be dispatched to investigate on-site emergency response personnel problems associated with plant equipment.

dosimetry, equipment, and protective Investigation and repair activities in the plant clothing, will require implementation of radiation protection controls which include monitoring and

2. Demonstrate the ability to monitor and tracking of radiation exposure of OSC On-Site track radiation exposure of on-site Assistance Teams. (Refer to Procedure OP-3507, emergency response personnel. " Emergency Radiation Exposure Control.") In addition, the exposure of the Off-Site Monitoring Teams will be monitored and tracked in the EOF.

    !ndicates NRC identified item from the 1992 exercise.

RI % 211 i

          . _ . ,   -                _    m .                ..._.. - - _ - - . . .            ,     ..   . m.  ._, .

1 Rev. O Page 2.1-6 Extent of Play G. In-Plant Corrective and Repair Actions

1. Demonstrate the ability to assemble and G.1 OSC On-Site Assistance Teams should be dispatched dispatch On-Site Assistance Teams in a G.2 to investigate problems associated with plant timely fashion, consistent with plant G.3 equipment. For established exercise conditions and assigned function. miniscenarios, briefings should be e sucted with On-Site Assistance Teams to ensure that responsibilities are clear and understood.

Briefing sheets (refer to VYOPF 3507.02) should be used to brief and debrief teams on work assignments conducted. On-Site Assistance Team personnel will demonstrate implementation of corrective actions (including obtaining necessary approvals, tools, procedures, replacement parts. etc.) on mockups of damaged plant equipment in accordance with established exercise miniscenarios.

2. Demonstrate the ability to provide adequate briefings to ERF staff and On-Site Assistance Teams as conditions and information change.

3. Demonstrate the ability of On-Site Assistance Teams to perform corrective actions on plant equi emergency conditions.pment during Indicates NRC identified item from the.1992 exercise.

R15\211 i

Rev. O Page 2.1-7 Extent of Play

4. Demonstrate the ability to provide G.4 The exercise miniscenarios will allow players to adequate administrative controls and implement the appropriate emergency work controls documentation for necessary repairs of in accordance with established procedures. (Refer plant equipment and gystems during an to Procedure OP-3507. " Emergency Radiation emergency situation. Exposure Control" and Procedure AP-0021, " Work Orders.")

H. Radiological Assessment

1. Demonstrate that adequate dose assessment H.1 The scenario will provide information on plant i activities can be performed to determine H.2 conditions and in-plant radiological conditions off-site radiological consequences. H.3 to players which will allow them to evaluate H.4 potential off-site radiological consequences.

2. Demonstrate that radiological assessment H.S Players will implement appropriate sections of personnel at the EOF can obtain Procedures OP-3513. " Evaluation of Off-Site radiological and meteorological data in a Radiological Conditions" and OP-3511. "Off-Site timely manner. Protective Actions Recommendations," as may be' required by scenario events.

3. Demonstrate the ability to perform timely assessment of off-site radiological conditions-to support'the formulation of protective action recommendations for the plume exposure pathway.

4. Demonstrate the ability to assess potential off-site radiological consequences based on plant conditions.

5. Demonstrate the ability to project the plume trajectory:and potentially affected downwind sectors utilizing the computer dose assessment model (METPAC).

l Indicates'NRC' identified item from the 1992 exercise. R15\tli

Rev. O Page 2.1-8 , t Extent of Play

6. Demonstrate adequate staffing, equipment H.6 Off-Site Monitoring Teams will be assigned at readiness check and deployment (if H.7 the OSC. Players will implement appropriate necessary) of Off-Site Monitoring Teams. sections of Procedure OP-3510. "Off-Site and Site Boundary Monitoring" in the field.

7. Demonstrate the use of appropriate <

equipment and procedures to perform off-site radiological monitoring. I. Protective Action Decision Making

1. -Demonstrate the ability to implement I.1 On-site protective action measures will include appropriate on-site protective measures radiation exposure control and plant evacuation of for emergency response personnel, nonessential personnel. After plant evacuation and accountability has been completed, all plant personnel and contractors not directly involved in the exercise may be allowed to return to work. ,

2. Demonstrate the adequacy of the protective I.2 Protective action decision making will be action decision making process to make demonstrated in accordance with Procedure OP-3511.

appropriate recommendations concerning "Off-Site Protective Actions Recommendations". , off-site radiological consequences.

Indicates NRC identified item from the.1992 exercise.

R15y11

t Rev. O Page 2.1-9 Extent of Play J. Public Information

1. Demonstrate the ability to develop and J.1 The News Media Center (NMC) will be fully periodically disseminate timely and J.2 activated. Information on the simulated events accurate press releases to the public and J.3 occurring at the plant will be ga'hered. verified, the news media. incorporated into a news release, and disseminated to key players. After approval, this information

2. Demonstrate the ability to provide will be discussed at the NMC.

briefings and to interface with the public and news media.

3. Demonstrate the ability to communicate and coordinate news releases between the EOF and the News Media Center.

4. Demonstrate the ability to provide rumor J.4 A communication line will be established to control. provide rumor control for questions concerning the simulated accident.

5. Demonstrate the ability to coordinate news J.5 State public information representatives from releases with tie state's public Vermont, New Hampshire, and Massachusetts should information representatives, if available. be present at the NMC. Information concerning news releases will be' coordinated with appropriate states' public information representatives.

Indicates NRC l'dentified item f om the 1992 exercise. R15\211

Rev. O Page 2.1-10' Extent of Play K. Parallel and Other Actions

1. Test and evaluate the adequacy of methods K.1 Security activities will be implemented in to establish and maintain access control accordance with established procedures to control and personnel accountability within the access to the protected area. Assembly of protected area, emergency response personnel and evacuation of contractor / visitors will be implemer.ted in order to test personnel accountability within the protected area. However, after the plant evacuation accountability checks have been completed, contractors and visitors will be exempted from additional personnel accountability checks.

2. Demonstrate the licensee *s capability for K.2 Exercise critique will be conducted with exercise self-critique and ability to identify controllers, observers, and players. C itique areas needing improvement. items will be compiled and documented by the Exercise Coordinator.

Note: The annual Radiological Monitoring drill and semiannual 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). Indicates NRC identified item from the 1992 exercise. R15\211

f I t VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE. PREPAREDNESS EXERCISE -p 1993 ,. 6 9

                                                                                                            .4 a

2.2 EXERCISE OBJECTIVES AND EXTENT OF PLAY- STATE OF VERM0?rr 4 h W

f e r- - , . . . , , .. . . ~ . . - - -- . , . - . - - - . . -

VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION REP-14 Obiectives State Local ; 91 Vermont Jurisdiction

1. MOBILIZATION OF EMERGENCY yes yes 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. l l Extent 91 Plav: State and local jurisdictions will be alerted and notified at each ECL. Mobilization of i State and local emergency facilities and field operations personnel will be in accordance with state and local plans. The following facilities will be activated and staffed: Vermont State EOC l State Warning Point { Emergency Operations Facility l Department of Health Laboratory ! Local EOC's in the Towns of* 1 Brattleboro Vernon ]' Guilford ! Halifax Dummerston ARCA: None 1

2. FACILITIES - EQUIPMENT, DISPLAYS, AND WORK 1 ENVIRONMENT. Demonstrate yes yes the adequacy of facilities, equipment, displays, and l other materials to support ,

emergency operations. l l 1

i

 ,    ,     ,                                                                         i VERMONT 1993 FULL SCALE EXERCISE             !

VERMONT YANKEE NUCLEAR POWER STATION 'i State Local- ' sd Vermont Jurisdiction Extent gf Plav: ! 4 Facilities, equipment, maps, and displays will be used to support response operations. ! Access to facilities will be controlled. l ARCA: None 1

3. DIRECTION AND CONTROL.

Demonstrate the capability yes yes ; to direct and control " emergency operations. Extent 91 Plav: Direction and control for all state and local emergency operations will txa demonstrated by the appropriate ORO member in accordance with state and local plans. ARCA: None

4. COKMUNICATIONS. Demonstrate the capability to communicate yes yes with all appropriate emergency personnel at facilities and in i the field.

Extent of Play: ) I state and local emergency response personnel, including field teams will demonstrate the { capability to communicate with appropriate ! locations. This includes communications , between utility and state facilities personnel l and state and local facilities personnel. l ARCA: 91-21, 91-23, 91-31 l l 2

VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local of Vermont Jurisdiction

5. EMERGENCY WORKER EXPOSURE CONTROL. Demonstrate the yes yes capability to continuously ,

monitor and control radiation exposure to emergency workers. Extent gf Plav: Each off-site organization having a responsi-bility for emergency workers will utilize appropriate dosimetry to control radiation exposure. :ORO's will demonstrate the capability to issue, zero, and read dosimeters and record readings. Each Emergency Worker will be issued a (TLD). Procedures will be demonstrated to manage exposure of emergency workers. Ap-propriate decisions will be made for EW's who may enter areas of higher dose limits. ARCA: 91-22

6. FIELD RADIOLOGICAL MONITORING -

AMBIENT RADIATION MONITORING. yes no Demonstrate the appropriate use of equipment and procedures for determining field radiation measurements. Extent gf Plav: Field Teams will be provided proper equipment to perform field operations. Operational checks of equipment are performed prior to deployment. Each team will demonstrate proper deployment cnd knowledge of assigned locations. Proper monitoring procedures will be performed and data will be promptly relayed to the Health Services Coordinator. The State Health Depart-ment will follow all standard operating procedures. ARCA: 87-8, 87-10, 87-11. L' 3

VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local

                            ,                              of Vermont       Jurisdiction

7. PLUME DOSE PROJECTION.

Demonstrate the capability yes no to develop dose projections and protective action recommendations regarding evacuation and sheltering. Extent 21 Plav: The state will demonstrate the capability to locate 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. ARCAi None

8. FIELD RADIOLOGICAL MONITORING -

AIRBORNE RADIOIODINE AND yes no PARTICULATE ACTIVITY MONITORING. Demonstrate ~ the appropriate use of equipment and procedures for the measurement of airborne radiciodine concentrations as low

        'as (10-7) 0.0000001 microcuries per cubic centimeter in the presence of noble gases and obtain samples of particulate activity in the airborne plume.

Extent 21 Plav: Field teams perform operational checks of equipment prior to deployment. Calibration of equipment is within 12 months. Airborne radiciodine and particulate samples are taken in accordance with procedures. Field teams will measure radiciodine'and particulate matter outside of plume . Field teams will transmit 4 me wse me- me-- m ****mm ^* = .

1 VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKE2 NUCLEAR POWER STATION State Local 21 Vermont Jurisdiction i data to the Health Services Coordinator in accordance with procedures. Samples are properly bagged and delivered to designated locations. ARCA: 87-10

9. PLUME PROTECTIVE ACTION '

DECISION MAKING. Demonstrate yes no the capability to make timely and appropriate protective a action decisions (PAD).

j Extent 91 Plav: l State decision makers will demonstrate the i ability to make initial and subsequent PADS. - Distribution and issuance of KI will be consi-dered. Coordination with other jurisdictions, , (i.e., N.H. and MA) will be demonstrated. 1 ARCA: None

10. ALERT & NOTIFICATION.

Demonstrate the capability yes yes l to promptly alert and notify j the public within the 10-mile i plume pathway emergency planning zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials. Extent 21 Plav: l i Initial public notification will be demonstrated actually in all its parts once during the ] i exercises. Subsequent notifications will be j simulated. Initial notification will be coordi- l nated with NH & MA. All response facilities will be provided copies of messages. NWS will tone out weather alert receivers. NTSA-Brattleboro will transmit initial EBS message. , i 5

1 VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE-NUCLEAR POWER STATION State Local of Vermont Jurisdiction once Coordination has been~ completed by responsible ORO's as to contact and time of message initiation; an initf.al instructional message will be sent throughout the 10-mile EPZ within 15 minutes. NWS, Burlington, VT., will be notified of timing schedule for-activation of weather alert' radios. Local EPZ communities.will be instructed to sound sirens within the 15 minute time' frame; and EBS WTSA-Brattleboro will begin initiation of instructional messages to the public. Local. towns will simulate backup route' alerting. A single supplementary alerting and notification route will be demonstrated. There are no exception areas in local plans. ARCA: None

11. PUBLIC INSTRUCTISNS AND EKERGENCY INFORMATION. yes partial Demenstrate the capability te coordinate the formulation and dissemination of accurate information and instructions to the public.

Extent of Plav: The State will demonstrate the capability to formulate and disseminate the accurate information and instructions to the public. The Stara will demonstrate coordin'ation of message content with other appropriate staff jurisdictions, organizations, facilities and ' States'(N.H., MA). The State will demonstrate the capability to provide instructions to the public including information on the initiation and impl'ementa-tion of protective actions. Information should delineate local government jurisdic- ' tions affected by the message. 6 su m et **=W 9 @ *9

VERMONT 1993 FULL SCALE EXERCISE VERMONT TiNKEE NUCLEAR POWER STATION State Local gi Vermont Jurisdiction Local Towns have designated public information officers. Towns may simulate instructional and emergency information pertinent to their jurisdictions. ,

For ingestion measures, pre printed information and instructions are available. ARCA: 87-73, 91-25, 91-27.

12. EMERGENCY INFORMATION - MEDIA.

Demonstrate the capability . yes no to coordinate the development and dissemination of clear, . accurate, and timely information to the news media. Extent of Plavi The State designated spokesman will coordinate activities and briefings with the media at the News Media Center at the Vermont Yankee corporate office in Brattleboro. ' All emergency and public information will be i discussed from this location. The State vill provide updated information to the. News Media Center. The Local ORO's refer media questions d to the News Media Center. ARCA: 89-12, 91-24, 91-26, 91-27, 91-28, 91-32, 91-33, 91-34, 91-35.

13. EMERGENCY INFORMATION - 1 RUMOR CONTROL. Demonstrate yes yes j the capability to establish ;

and operate rumor control in a j coordinated and timely manner. l Extent of Plav: The state EOC has a rumor control number ' publicized in mailings to the 10-mile EPZ. I l 7 ! I

VERNON! 1993 FULL SCAZE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local gf yermont Jurisdiction Local ORO' will refer rumor calls to the News Media Center. The Vermont-representative at the News Media Center will exchange messaging with NH and MA representatives. ARCA: 91-24, 91-25, 91-26, 91-29, 91-34, 91-35.

14. IMPLEMENTATION OF PROTECTIVE ACTIONS - USE OF KI FOR yes yes EMERGENCY WORKERS, INSTITUTIONALI2ED INDIVIDUALS AND THE GENERAL PUBLIC.

Demonstrate the capability and - resources to implement potassium iodide (KI) protective actions for emergency workers, institutionalized individuals, and, if the State plan specifies, the general public. Extent 21 Play: The State will make the determination to issue KI to emergency workers, and insti-tutionalized individuals. Local ORO's will , simulate access and distribute KI according 1 to plans. Local ORO's have instructions available for those advised to take KI. No KI will actually be distributed or taken. ARCA: 91-27, 91-32, 91-33 l 1

15. IMPLEMENTATION OF PROTECTIVE l ACTIONS - SPECIAL POPULATIONS. yes yes Demonstrate the capability and i resources.necessary to implement I appropriate protective actions i for special populations. l Extent 21 Plav:

The state will notify Local ORO's to alert ] special populations within the areas identified ~ J 8 o e se 41 5 ,g @ N h9 6 N3 'O ga a N

VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local 21 Vermont Jurisdiction for protective actions. Local ORO's will identify special population groups. Actual contact simulated. ARCA: None

16. IMPLEMENTATION OF PROTECTIVE .

ACTIONS - SCHOOLB. Demonstrate not an objective the capability and resources necessary to implement protective actions for school children within the plume pathway emergency planning zone (EPZ). ARCA: 89-15.

17. TRAFFIC AND ACCESS CONTROL. .

Demonstrate the organizational yes yes capability and resources necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas. Extent af Plav: State and local ORO's consistent ' with developing scenario events and PARS will determine the location of TCP/ACP 's . Each local town impacted by scenario events.will deploy person-nel to,a single TCP/ACP. Deployed EW's and activated facilities wi'11 demonstrate emergency worker exposure control procedures. ARCA: None ,

18. RECEPTION CENTER - MONITORING DECONTAMINATION, AND Not an objective REGISTRATION. Demonstrate the ' adequacy of procedures, facilities, equipment, and 9

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                                             . - . .           m w

VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local 21 Vermont Jurisdiction personnel for the radiological monitoring, decontamination, and registration of evacuees. Extent 21 Plav: Extent of play specific to tNis ARCA at the Bellows Falls Reception Center will be demonstrated. Outstanding issue remaining is demonstration of " Recovery and Reentry" decision making. Local ORO will tabletop this discussion. Reception Center will simulate activation for monitoring, demonstra-tion and registration of evacuees. This tabletop exercise will be demonstrated out of sequence to regular exercise activities. Actual time to be negotiated with FEMA. ARCA: 82-15

19. CONGREGATE CARE. Demonstrate the adequacy of facilities, Not an objective equipment, supplies, personnel, and procedures for congregate care of evacuees.

ARCA: None

20. MEDICAL SERVICES - TRANSPORTATION.

Demonstrate the adequacy of Not an objective ; vehicles, equipment, procedures, and personnel for transporting contaminated, injured, or exposed individuals. ARCA: None l 1 i l 10 4 em m 1 w e

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P VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local gf Vermont Jurisdiction

21. MEDICAL SERVICES - FACILITIES.

Demonstrate the adequacy of the Not an objective equipment, procedures, supplies, and personnel of medical facilities responsible for treatment of' contaminated, injured, or exposed individuals. ARCA: None

22. EMERGENCY WORKERS, EQUIPMENT, AND VIHICLES - MONITORING AND .

                                                   .         Not an objective DECONTAMINATION.      Demonstrate the adequacy of procedures for the monitoring and decontamination of emergency workers, equipment,.

and vehicles. ARCA: None

23. SUPPLEMENTARY ASSISTANCE' (FEDERAL /OTHER) . Demonstrate yes no the capability to identify the need for external assistance and to request such assistance from Federal or other support organizations.

Extent 21 Plav: Certain Federal and private response

organizations, i.e., American Red Cross, Civil Air Patrol, U.S. Dept. of Agriculture, will be represented at the State EOC during .

the plume and ingestion phases of the exercise. The State ORO will simulate calls to FEMA Region I during the plume and ingestion exercise phases to activate federa'l response. ARCA: ' None 11

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POST EMERGENCY PHASE INGESTION PLUME PATHWAY VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION

24. POST-EMERGENCY SAMPLING.

Demonstrate the use of equipment and procedures for the collection and transportation of samples from areas that received deposition from the airborne plume. Extent QI Plav: . The sampling teams will demonstrate all sample collection procedures as well as procedures for preventing cross contamination. The particular types of samples to be collected and the areas from which they are collected may be determined in advance. Prior contact will be made to secure access to properties. Teams will demonstrate the proper equipment to collect samples of soil, grass, forage, stored feed, leafy vegetables, local produce, milk and surface water. All activities related to sample transportation, storage and record maintenance and documentation will be demonstrated for a representative number of samples. The Department of Health in coordination with the state Office of Emergency Management and state response agencies will provide direction on where field sampling should take place. The teams'will demonstrate equipment and supplies used for field sampling (e.g. scoops, shovels, collection bags, containers, ID labels, etc). They will demonstrate equipment-used for measuring background radiation for field personnel, sample location and individual samples. Each team will take at least one sample from predetermined sampling locations. These samples will be delivered to the muster and collection point for teams and then to the State of Vermont Health Laboratory for analysis. Actual sample transport from the muster / collection point to the health laboratory will occur one time only. ARCA 87-8, 87-10, 87-11

25. LABORATORY OPERATIONS.

Demonstrate laboratory operations and procedures for measuring and analyzing samples. 12

                                     - . = - - _ _ - - - - - - - - . - - - - - - - - - - - - , - - - - - - - - - - - - - - - - - , - - , - - - _ - - - - - - - - - - - . - - . - - - - - . ~ . - - _ - - - - - - - - - . . . - - - - - - - - - , - - -

POST EMERGENCY PEASE INGESTION PLUME-PATHWAY VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION The laboratories' capability to process samples will be demonstrated. The use of laboratory equipment, laboratory grade analytical instruments suitable for determining radioisotopes present and levels of radioactivity in samples, as well as the training of personnel to use the equipment will be demonstrated by analyzing prepackaged environmental samples. The State of Vermont Health Laboratory will receive and identify all. incoming ingestion samples for analysis. The results will be transmitted to the Department of Health staff located at the state EOC.. ARCA: 87-12, 87-13, 87-14

26. INGESTION EXPOSURE PATHWAY -

DOSE PROJECTION AND PROTECTIVE ACTION DECISION MAKING. Demonstrate the capability to project dose to the public for the ingestion pathway and to recommend protective measures. The State Department of Health, with other state agencies will demonstrate the capability to make appropriate Protective Action Decisions (PADS) using data provided by exercise controllers. The data consists of meteorologic conditions from the emergency phase, release isotopic composition and radiation levels found in field monitoring samples and DOE flyover results. All data will be in the form normally available either from the field monitoring teams, the laboratory and DOE. PADS will also be developed using the laboratory sample analysis results of the food and agricultural. ARCA: None

27. INGESTION EXPOSURE PATHWAY - PROTECTIVE ACTION IMPLEMENTATION.

Demonstrate the capability ' to implement protective actions for ingestion exposure pathway. 13 g w .m m =*N h@O e

POST EMERGENCY PHASE INGESTION PLUME PATHWAY VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION Extent p1 Plav: The_ State will identify and ut'ilize current information regarding dairy and' agricultural food producers / processors within the ingestion pathway for the implementation of protective actions. Development of measures and strategies'for the implementation of ingestion pathway EPZ protective actions will be demonstrated by protective action messages to.the general public and food producers and processors. Actual broadcast of messages will be simulated. Demonstration of this objective will also include selection of appropriate' instructional material.(preprinted and to be printed) for distribution within the ingestion pathway EPZ at the time of the emergency. Actual printing and distribution of materials will be simulated. State agencies will demonstrate the capability to control, restrict or prevent distribution of contaminated foodstuffs by commercial-businesses by issuing administrative orders through health or agricultural agencies. Communications and coordination with agencies responsible for enforcing food controls within the ingestion pathway EPZ will be demonstrated, but actual communications with food producers and processors will be simulated.

28. RELOCATION, RE-ENTRY, AND RETURN - DECISION MAKING. Demonstrate the capability to develop decisions on relocation, re-entry, and return.

The identification of areas requiring Relocation of the general public will be demonstrated by co'mparing simulated measurements to decision criteria. Assessmo.nts will be made based on Doe Flyover data provided by controllers and field monitoring exposure rate readings. State personnel responsible for accident assessment will demonstrate the capability to use this data to plot on a map the location of the area from which the population should be Relocated (the Restricted zone). The decision criteria and strategies that are followed to allow Re-entry into controlled areas will be demonstrated at the State EOC in a group setting discussion with representatives from all major state organizations. Decisions will be made regarding the location of l control points and policies. l l 14

                                                                      .w a nmu pe s w wo me n s M

l 1 POST EMERGENCY PHASE I INGESTION PLUME PATHWAY VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION Responsible agencies will use simulated environmental measurements provided by controllers to identify the location of the boundaries of I areas to which Return is permitted. Demonstrated decision making regarding assistance to individuals who are affected by the emergency will be demonstrated at the state EOC in a group setting discussion with representatives from all major state ' organizations. Discussions will be held regarding priorities, necessary actions and implementation. The coordination of decision making with the various state organizations and the other states will be demonstrated.

29. RELOCATION, RE-ENTRY, AND RETURN - IMPLEMENTATION.

Demonstrate the capability to implement relocation, re-entry, and return. Extent 91 Plav: Relocation efforts will focus on those individuals not previously evacuated from the restricted zone and those evacuated populations unable to return because of contamination. Relocation activities will be demonstrated through internal meetings, briefings, discussions and coordination with various state organizations in a group setting. The State will demonstrate control of Emergency Workers and the public who re-enter the restricted zone. Actions required for the implementation of reentry will be demonstrated through discussions with state agencies at the EOC. The State will demonstrate the capability to return populations that were evacuated during the emergency phase. Return activities will be demonstrated through internal meetings, briefings, discussions and coordination with various state organizations in a group setting.,

The State will' demonstrat'e the coordination of this implementation with , the other states. 9 6 15

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POST EMERGENCY PHASE INGESTION PLUME PATHWAY VERMONT 1993 FULL SCALE EXE.RCISE VERMONT YANKEE NUCLEAR POWER STATION State: Local gi Vermont Jurisdiction Activities demonstrated in this objective will be in accord with the State Plan. ARCA: 82-15

30. CONTINUOUS, 24-HOUR STAFFING. Demonstrate Not an objective the capability to maintain staffing on a continuous, 24-hour basis through an actual shift change.

31. OFFSITE SUPPORT FOR THE EVACUATION OF ONSITE Not an objective PERSONNEL. Demonstrate the capability to provide offsite support for the evacuation of onsite personnel.

32. UNANNOUNCED EXERCISE OR DRILL. Demonstrate the capability to yes yes ,

carry out emergency response functions in an unannounced exercise or drill. Extent 21 Plav: This objective will be demonstrated , during the plume exposure pathway exercise. ARCA: None

33. OFF-HOURS EXERCISE OR DRILL. Demonstrate the yes yer, capability to carry out emergency response functions during an off-hours exercise or drill.

16

POST EMERGENCY PHASE INGESTION PLUME PATHWAY VERMONT 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local pl Vermont Jurisdiction Extent pl Plav: This objective will be demonstrated during the plume exposure pathway exercise. ARCA: None

34. LICENSEE OFFBITE REPPONSE ORGANIZATIONS. ' Demonstrate Not an objective the capability of licensee offsite response crganization

[ licensee (ORO)] personnel to interface with non-participating organizations and accomplish coordination essential for emergency response. l 17 I

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VERMONT YANKEE NUCLEAR POWER STATION ! P EMERGENCY. RESPONSE PREPAREDNESS EXERCISE 1993 . 2.3 EXERCISE OBJECTIVES AND EXTENT OF PIAY - STATE OF NEW HAMPSHIRE' l i i t 6 h i F r i i t [

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STATE OF NEW HAMPSHIRE 1993 PLUME EXPOSURE AND INGESTION PATHWAY EXERCISE VERHONT YANKEE 12/4/92 OBJECTIVES AND EXTENT OF PLAY OBJECTIVE 4# 1 ( 2) : HOBILIZATION OF EHERGENCY PERSONNEL i Demonstrate the capability to alert and fully mobilize personnel for both emergency facilities and field operations. Demonstrate the caphbility to activac.e and staf f emergency f acilities f or emergency operations. 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 accordinglv. 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. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE STATE EOC, EOP, IFO, JOINT HEDIA CENTER, LOCAL EOC'S, STATE WARNING POINT, SOUTH WEST _ FIRE HUTUAL AID. EXTENT OF PLAY INGESTION PATHWAY PHASE Facilities will be staged independently at predetermined times. Controllers at each facility will support participating f acilities by managing the flow of communications and data to support exercise play and objective demonstration. FACILITIES DEMONSTRATING TBS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : STATE EOC. - AREAS REOUIRING CORRECTIVE ACTION , None cited. 1 ue

1 l OBJECTIVE #2 ( 5) - FACILITIES-EOUIPMENT. DISPLAYS AND WORK ENVIRONMENT : Demonstrate the adequacy of facilities and equipment, displays, and other materials to support emergency operations. EXTENT OF PLAY PLUME EXPOSURE PATHWAY PHASE : Each participating facility will demonstrate its capabilities in accordance with this objective. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : STATE EOC, EOF, IFO, JOINT HEDIA CENTER, LOCAL EOC'S, STATE WARNING POINT, SOUTH WEST FIRE HUTUAL AID. EXTENT OF PLAY INGESTION PATHWAY PHASE : Each participating facility will demonstrate its - capabilities in accordance with this objective. ; FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTI_O,N, PATHWAY PHASE : STATE EOC. AREAS REOUIRING CORRECTIVE ACTION : None cited. , OBJECTCVE #3 (3} = DIRECTION AND CONTROL Demonstrate the capability to direct and control emergency operations. EXTENT OF PLAY PLUME EXPOSURE PATHWAY PHASE P a rti cip a tin e' state and local facilities will demonstrate their ability to direct and control emergency operations in accordance with the NHRERP. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : STATE EOC, EOF, IFO, JOINT HEDIA CENTER, LOCAL EOC'S, STATE WARNING POINT, SOUTH WEST FIRE HUTUAL AID. 2 t

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EXTENT OF PLAY INGESTION PATHWAY PHASE i Participating state and local facilities will demonstrate their ability to direct and control emergency operations in accordance with the NHRERP. FACILITIES DEMONSTRATING THIS OBJECTIVE IN THE INGESTION PATHWAY PHASE : STATE EOC. AREAS REOUIRING CORRECTIVE ACTION : None cited. OBJECTIVE #4 (4) : COHHUNICATIONS i Demonstrate the capability to communicate with all appropriate emergency personnel at f acilities and in the field. EXTENT OF PLAY PLUME EXPOSURE PATHWAY PHASE : Facilities participating in the exercise will demonstrate the primary and a back up communications resource per facility. FACILITIES nEHONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PH E i STATE EOC, EOF, IFO, JOINT HEDIA CENTER, LOCAL EOC'S, STATE WARNING POINT, SOUTH WEST FIRE HUTUAL AID, HONITORING TEAHS. EXTENT OF PLAY INGESTION PATHWAY PHASE : This objective will be demonstrated during the plume phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE N/A. AREAS REOUIRING CORRECTIVE ACTION : I Hinsdale EOC will demonstrate improvements to its l radio system. (SEE ARCA 91-1). ! Field monitoring teams wi31 demonstrate their i capability to communicate with the IFO. ' (SEE ARCA 91-2). 3

L 5 OBJECTIVE #5 (G1 : EMERGENCY WORKER EXPOSURE CONTROL i Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers. EXTENT OF PLAY PLUME EXPOSURE PATHWAY This objective will be demonstrated in accordance with the NHRERP by facilities that participate in the exercise. An emergency worker in Richmond, at Troop C and in Hinsdale will discuss appropriate actions to be taken in the event he has a dosimeter reading that indicates that exposure limits have been exceeded. This action will be , initiated by a controller message. Upon completing this demonstration the controller will direct the emergency worker to resume exercise play as appropriate. FACILITIES DEHONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : , LOCAL EOC'S, FIELD TEAHS, EPZ EHERGENCY WORKERS (Traffic and Access Control). EXTENT OF PLAY INGESTION PATHWAY : This objective will be demonstrated in conjunction with the plume exposure pathway portion of the exercise. OBJECTIVE DURING THE INGESTION FACILITIES DEMONSTRATING' THIS PATHWAY PHASE : N/A. AREAS REOUIRING CORRECTIVE ACTION e Richmond EOC will demonstrate the capability to brief emergency workers on the use of dosimetry, exposure limits and reporting procedures. (SEE ARCA 91-3,91-4). New Hampshire State Police Troop C access control personnel will demonstrate the distribution and proper use of dosimetry. (SEE ARCA 91-5).

      .            Hinsdale EOC will demo,nstrate the capability to issue emergency workers the appropriate dosimetry per the NHRERP.

(SEE ARCA 91-6). 4

k OBJECTIVE #6 (7) : FIELD RADIOLOGICAL HONITORING-AMBIENT RADIATION HONITORING Demonstrate the appropriate use of equipment and procedures f or determining field radiation measurements. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : Two NHDPHS radiological monitoring teams will be dispatched. At least six monitoring points per team will be monitored. < FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : , FIELD MONITORING TEAMS EXTENT OF PLAY INGESTION PATHWAY - This objective will be demonstrated during the plume phase. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE - INGESTION PATHWAY PHASE : N/A. AREAS REOUIRING CORRECTIVE ACTION None cited. OBJECTIVE 4t 7 ( 10) ! PLUME DOSE PROJECTION: Demonstrate the capability to develop dose projections and protective action recommendations regarding evacuation and sheltering. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : This objective will be demonstrated in accordance with the NHRERP in the context of the exercise scenario. METPAC and other accident assessment programs will be used. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE

PATHWAY PHASE s STATE EOC.

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EXTENT OF PLAY INGESTION PATHWAY : N/A. FACILITIES DEHONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. AREAS REOUIRING CORRECTIVE ACTION i None cited. OBJECTIVE #8 (8.9) : FIELD R ADIOLOGICAL HONITORING- AIRBORNE RADIOIODINE AND P ARTICULATE ACTIVITY HONITORING - Demonstrate the appropriate use of equipment and procedures for the measurement of airborne radiciodine I concentrations as low as 10 ^-7 ( 0. 000 0001 ) Hierocurie per cubic centimeter in the presence of noble gasses and obtain samples of particulate activity in the airborne plume. , EXTENT OF PLAY PLUME EXPOSURE PATHWAY , ; This objective will be demonstrated in accordance with the NHRERP. Use of Silver Zeolite filter media will be simulated by charcoal filter cartridges. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : FIELD MONITORING TEAMS. EXTENT OF PLAY INGESTION PATHNAY : This objective will be demonstrated as part of the f plume exposure phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE N/A. AREAS REOUIRING CORRECTIVE ACTION : 4 Field monitoring teams will demonstrate the mechanisms for obtaining back up equipment and Silver Zeolite air sampling media per the NHRERP. (SEE ARCAS 91-7,91-8). 6

1 OBJECTIVE #9 ( 11) = PLUME PROTECTIVE ACTION DECISION HAKING Demonstrate the capability to make timely and' appropriate protective action decisions (PAD). EXTENT OF PLAY PLUME EXPOSURE PATHWAY : This objective will be demonstrated by the state ', decision making team in accordance with the NHRERP.

Local organizations will be notified and respond in ,

accordance with their plans and procedures according to , the recommended protective action. The New Hampshire decision making team will coordinate with the decision making teams of Vermont and Hassachusetts. FACILITIES DEHONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE STATE EOC. ,

     -EXTENT OF PLAY INGESTION PATHWAY       :

This objective will be demonstrated by the state decision making team at the State EOC in accordance with the NHRERP during the plume phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION ' PATHWAY PHASE : N/A. AREAS REOUIRING CORRECTIVE ACTION e None cited. I t

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OBJECTTVE #10 ( 12) : ALERT AND NOTIFICATION: Demonstrate the capability to promptly . alert and notify the public within the 10-mile Plume Pathway Emergency Planning Zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate state or local officials. EXTENT OF PLAY PLUME EXPOSURE :

Sounding of sirens and broadcast of NOAA and EBS messages will be simulated. EBS messages will be formulated and distributed by the New Hampshire EOC. Simulation of the activation of the NOAA weather radio and EBS messages will be coordinated with Hassachusetts and Vermont officials. EPZ communities will demonstrate this objective : through the receipt of activation times f rom their local liaisons and will demonstrate their capability to monitor NOAA and EBS station,s. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : STATE EOC, WKNE, SWFMA, LOCAL EOC'S. EXTENT OF PLAY INGESTION PATHWAY , This objective will be demonstrated during .the plume exposure phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE e N/A. AREAS REOUIRING CORRECTIVE ACTION : EBS station WKNE will demonstrate the ability to receive an activation message from the State. EBS activation will be simulated. (SEE ARCA 91-9). Hinsdale EOC will demonstrate its ability to monitor NOAA tone alert radios. ' ( SL'E ARCA 91-10 ) . , Richmond EOC will demonstrate its ability to activate sirens if the primary activation mechanism fails. (SEE ARCA 91-11). B

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OBJECTIVE #11 ( 13) : PUBLIC INSTRUCTIONS AND EMERGENCY INFORMATION : - Demonstrate the capability to coordinate the f ormulation and-dissemination of accurate inf ormation and instructions to the public. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : r Public information messages will- be developed periodically. Messages will be developed based upon 5 scenario information. Broadcast of these messages will be simulated. The messages will be distributed to the ! EOF, IFO, Media Center, and the State EOC. Communities will receive information concerning r t protective action recommendations from their respective local liaison. Communities do not prepare public information messages and do not have a representative at the Media Center. Communities will monitor NOAA and EBS - radio at their EOC's. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE STATE EOC, JOINT MEDIA CENTER. EXTENT OF PLAY INGESTION PATHWAY Public information messages will be developed _ periodically. Messages will be developed based upon scenario information. Broadcast of these messages will be simulated. The message distribution will be simulated. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE STATE EOC. l AREAS REOUIRING CORRECTIVE ACTION ; State EOC-media center will demonstrate the ability to develop messages to provide the public accurate emergency information. (SEE ARCA 91-12). , 9

OBJECTIVE #12 ( 14 ) : 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 PLUME EXPOSURE i , The demonstration of this objective occurs at the state EOC and the Media Center. Controllers will simulate media response. The primary responsibility for briefing the media with respect to of f site activities in New Hampshire lies with the State. New Hampshire will coordinate its' response actions and media advisories with Vermont, Massachusetts and Vermont Yankee at the joint media center in accordance with the NHRERP.

EPZ communities may respond to questions about local emergency response but are encouraged to refer press inquires to the Media Center. A controller message will be generated for each community to initiate a response and referral to media inquiries.

FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE + STATE EOC, JOINT MEDIA CENTER, LOCAL EOC'S. EXTENT OF PLAY INGESTION PATHWAY: The demonstration of this objective will occur at the State EOC. Messages and news advisories will be developed at the EOC, but their distribution will be simulated. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : STATE EOC. AREAS REOUTRING CORRECTIVE ACTION The State EOC will demonstrate its ability to exchange media inf ormation with Vermont and Massachusetts in accordance with the NHRERP at the Joint Media Center. (SEE ARCA 91-13). . 10

f OBJECTIVE 4t 1 3 ( 15)

EMERGENCY INFORMATION-RUMOR CONTROL

Demonstrate the capability to establish and operate rumor control in a coordinated and timely manner.

3 EXTENT OF PLAY PLUME EXPOSURE PATHWAY : In accordance with the NHRERP, demonstration of this objective will occur .at the Joint Media Center. Incoming calls will be provided by controllers. At least one false or misleading rumor relating to PARS will be provided by the controllers. Calls to the rumor control center will occur at a rate of at least six per hour per operator during the Site Area Emergency and General Emergency levels. Rumor control personnel will screen messages for trends. Communities will refer calls which address issues beyond local jurisdiction to the rumor control number. A controller message will be generated f or each community to initiate a response and referral of information. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PL'UME EXPOSURE PATHWAY PHASE : JOINT HEDIA CENTER. EXTENT OF PLAY INGESTION PATHWAY : ' This objective will be demonstrated during the plume . exposure phase of the exercise. , FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. AREAS REOUIRING CORRECTIVE ACTION : None cited. 4 4 11

O B J E C T "I V E #14 ( 16. 17) = IMPLEMENTATION OF PROTECTIVE ACTION-USE OF KI FOR EHERGENCY WORKERS. INSTITUTIONALIZED INDIVIDUALS.AND THE GENERAL PUBLIC Demonstrate the capability and resources to. implement. Potassium Iodide (KI) protective actions for emergency workers, institutionalized individuals,and if the state plan specifies the general public. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : The decision to use or not use KI for emergency workers and institutional 1 zed individuals will be demonstrated at the State EOC. The capability 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. Quantities of KI are stored at local EOC's and the IFO. The NHRERP does not provide for the issuance of KI to the general public. . FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : STATE EOC, LOCAL EOC'S, IFO, MONITORING TEAMS. EXTENT OF PLAY INGESTION PATHWAY : This objective will be demonstrated during .the plume exposure pathway phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. AREAS REOUIRING CORRECTIVE ACTION : None cited. 12 I l i

OBJECTIVE- 4#15 ( 18) : IMPLEMENTATION OF PROTECTIVE ACTIONS-SPECIAL POPULATIONS : Demonstrate the capability and resources necessary to implement appropriate protective actions for special populations. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : The ability and resources to implement protective actions for special populations will be demonstrated in accordance with the NHRERP. Each local EOC will simulate calls to special needs populations per their special needs call lists and arrange for appropriate resources to meet the special needs. Controller messages will simulate requests for assistance. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE i LOCAL EOC'S. - EXTENT OF PLAY INGESTION PATHWAY : , This objective will be demonstrated during the plume , phase of the exercise. . FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. r 2 AREAS REOUIRING CORRECTIVE ACTION None cited. OBJECTIVE 4t 1 6 ( 19) : IMPLEHENTATION OF PROTECTIVE ACTION-SCHOOLS : Demonstrate the capability and resources necessary to implement protective actions for school children within the plume Pathway Emergency Planning Zone (EPZ). EXTENT OF PLAY PLUME EXPOSURE PATHWAY Calls will be made to each school to verify transportation resource requirements. Calls will be made to transportation providers to verify resource capabilities. Mobilization of actual transportation resources will be simulated. s 13

FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE ^ STATE EOC, LOCAL EOC'S, SCHOOLS, EXTENT OF PLAY INGESTION PATHWAY i This objective will be demonstrated during the plume exposure phase of the exercise. PACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. AREAS REOUIRING CORRECTIVE ACTION : None cited. OBJECTIVE **1 7 ( 20) : TRAFFIC AND ACCESS CONTROL - Demonstrate the organizational capability and resources to control evacuation traffic flow and to control access to evacuated and sheltered areas. EXTENT OF PLAY PLUME EXPOSURE PATHWAY Local police will be asked to demonstrate the , staffing of one traffic control point in their jurisdiction. One access control point and the ability to handle a traf fic impediment will be demonstrated by Troop C New Hampshire State Police. Demonstrations will occur during the plume exposure pathway phase of the exercise at times to be coordinated between facility controllers and FEHA evaluators. The demonstration will consist of a talk through of actions at the selected ACP, TCP, or impediment site. Traffic will not be disrupted. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE

   ' PATHWAY PHASE :

LOCAL EOC'S, TROOP C.

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EXTENT OF PLAY INGESTION PATHWAY : This objective will be demonstrated during the plume phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE N/A. ; AREAS REOUIRING CORRECTIVE ACTION : Hinsdale EOC will demonstrate the ability to set up and man a traffic control point. (SEE ARCA 91-14). O B J E C T I V E: #18 (21) : RECEPTION CENTER-HONITORING. DECONTAMINATION. AND REGISTRATION : ] Demonstrate the adequacy of procedures facilities, equipment, and personnel f or the radiological monitoring, ! decontamination, and registration of evacuees. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : A tour of the reception / monitoring /decon center 'I facilities will take place out of sequence on day two of l the exercise. The tour will be conducted in conjunction i with the demonstration of objectives 19 and 22.

FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : RECEPTION /DECON CENTER (KEENE STATE COLLEGE). EXTENT OF PLAY INGESTION PATHWAY : Demonstration of this objective will occur in conjunction with the plume exposure phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION j PATHWAY PHASE : 1 l N/A. - l 1 AREAS REOUIRING CORRECTIVE ACTION : None cited. 15 !

OBJECTIVE 4#19 (22) : CONGREGATE CAPE : Demonstrate the adequacy of facilities, equipment, supplies, personnel, and procedures for congregate care of evacuees. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : A tour of selected congregate care facilities will

be conducted out of sequence on day two of the exercise.

The tour for this objective will be conducted in conjunction with the tours for objective 18 and 22. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE i SELECTED CONGREGATE CARE FACILITIES. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE i , N/A. AREAS REOUIRING CORRECTIVE ACTION i None cited. OBJECTIVE 4# 2 O ( 23) : HEDICAL SERVICES-TRANSPORTATION Demonstrate the adequacy of vehicles, equipment, procedures, and personnel for transporting contaminated, injured or exposed individuals. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : This objective will be demonstrated out of sequence as part of the next scheduled MS-1 drill scheduled for the Cheshire Medical Center. (June or July 93 ?). FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE CHESHIRE HEDICAL CENTER, SELECTED EMS TRANSPORT CO. . EXTENT OF PLAY INGESTION PATHWAY : This objective will be demonstrated in conjunction with the plume exposure phase of the exercise. ' N 16

FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. [ AREAS REOUIRING CORRECTIVE ACTION : None cited. OBJECTIVE 4A 2 1 (24) : HEDICAL SERVICES-FACILITIES : Demonstrate the adequacy of the equipment procedures, supplies, and personnel of medical f acilities responsible for treatment of contaminated, injured, o r-exposed individuals. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : This objective will be demonstrated out of sequence as part of the next scheduled MS-1 drill scheduled for the Cheshire Medical Center. (June or July 93 ?). FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : ' CHESHIRE MEDICAL CENTER. t EXTENT OF PLAY INGESTION PATHWAY : This objective will be demonstrated in conjunction with the plume exposure exercise phase. . FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. AREAS REOUIRING CORRECTI7E ACTION : None cited. OBJECTIVE ## 2 2 (25) : EMERGENCY WORKERS. EOUIPMENT. AND VEHICLES- HONITORING AND DECONTAMINATION : Demonstrate the adequacy of procedures for the monitoring and decontamination of emergency workers, equipment and vehicles. 17 N

EXTENT OF PLAY PLUME EXPOSURE PATHWAY : A tour of the emergency worker monitoring /decon f acility will be conducted- out of sequence in conjunction with the extent of play for objective 18 and 19 on day two of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE ; PATHWAY PHASE : EHERGENCY WORKER HONITORING/DECON FACILITY (KEENE STATE COLLEGE). EXTENT OF PLAY INGESTION PATHWAY : This objective will be demonstrated in conjunction with the plume exposure phase of the exercise. FACILITIES DEHONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE N/A. AREAS REOUIRING CORRECTIVE ACTION : None cited. OBJECTTVE 4*23 (26) : 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. EXTENT OF' PLAY PLUHE EXPOSURE PATHWAY American Red Cross and Civil Air Patrol will' send representatives to facilities in accordance with the NHRERP. New Hampshirc will coordinate its requests for supplementary assistance with Vermont and Hassachusetts pursuant to the NHRERP. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : , STATE EOC. 18

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i i l EXTENT OF PLAY INGESTION PATHWAY : ! i This objective will be demonstrated as part of the j discussion that takes place in the State EOC. l Supplementary assistance and response by Federal and 1 other agencies will be simulated. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : i l STATE EOC. AREAS REOUTRING CORRECTIVE ACTION e None cited. l l OBJECTTVE #24 ( 27) : 'I POST EHERGENCY SAMPLING Demonstrate the use of equipment and procedures for the collection and transportation of samples from areas that received deposition from the airborne plume. EXTENT OF PLAY PLUHE EXPOSURE : , j This objective will be demonstrated in conjunction with the ingestion phase of the exercise. I FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : N/A. EXTENT OF PLAY INGESTION PATHWAY : This objective will be demonstrated at the State EOC by a discussion of sampling strategy. A late Hay /early June sampling time frame will be imposed for exercise purposes by a controller message. Deployment of sampling teams will be simulated. Actual deployment of sampling teams will occur in conjunction with the Seabrook Station ingestion pathway exercise to be conducted in December, 1994. The sampling procedures and personnel for both Seabrook Station and Vermont Yankee are the same. , 19

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FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : State EOC. AREAS REOUIRING CORRECTIVE ACTION : The State EOC will demonstrate the ability to develop data f rom plume monitoring activities f or sample collection team dispatch. Transmission of this. data to the IFO will be simulated. Use of plume monitoring data as a basis for dispatching New Hampshire sampling teams will be demonstrated in this manner. l (SEE ARCAS 87-29,87-44,87-46). ; i The ARCAs listed below will be addressed in the 1994 l Ingestion Pathway exercise for Seabrook Station. l Sampling team equipment which requires calibration will be marked to indicate currency of calibration. (SEE ARCA 87-39). Sampling teams will be provided complete sampling kits per the NHRERP. , (SEE ARCA 87-40). l Sampling teams will demonstrate f amiliarity with the set-up and operation of sampling equipment. (SEE ARCA 87-41). Sampling teams will demonstrate familiarity with procedures for taking water samples. (SEE ARCA 87-42). Sampling team will demonstrate familiarity with taking radiation ground-level readings. .. (SEE ARCA 87-43). Sampling teams will demonstrate the ability to read dosimeters at prescribed intervals per the NHRERP. (SEE ARCA 87-45). OBJECTIVE #25 ( 28) : LABORATORY OPERATIONS: Demonstrate laboratory operations and procedures f or measuring and analyzing samples.

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EXTENT OF PLAY PLUME EXPOSURE PATHWAY : > The State Laboratory in Concord will demonstrate this objective in conjunction with the ingestion pathway phase of the exercise. I 20 J

FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : N/A. EXTENT OF PLAY INGESTION PATHWAY : The State Laboratory in Concord will simulate this objective. A discussion of laboratory procedures and capabilities will be held at the State EOC during the Ingestion Pathway portion of the exercise. 'A late Hay early June time frame will be assumed for exercise purposes. Demonstration of laboratory capabilities will occur in conjunction with the Seabrook Station ingestion pathway exercise to be conducted in December, 1994. The laboratory procedures and personnel for both Seabrook Station and Vermont Yankee are the same. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE N/A AREAS REOUIRING CORRECTIVE ACTION : None cited. OBJECTIVE ## 2 6 ( 29) : INGESTION EXPOSURE PATHWAY-DOSE PROJECTION AND PROTECTIVE ACTION DECISION MAKING Demonstrate the capability to project dose to the public for the Ingestion Pathway and to recommend protective measures. EXTENT OF PLAY PLUME EXPOSURE PATHWAY The activity required to demonstrate this objective will occur during the Ingestion Pathway phase of the exercise. . FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE i N/A. 21

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EXTENT OF PLAY INGESTION PATHWAY : The activity required to demonstrate this objective will occur during three separate phases of the exercise. The State EOC ' Accident Assessment Team will develop a post accident monitoring plan to identif y the plume foot print. This will occur at the end of the plume exposure pathway phase of the exercise on Day one.of the exercise. A late Hay /early June time frame will be assumed for exercise purposes. On day Two of the exercise the DPHS Accident Assessment Team will convene at the State EOC. DOE fly over results, one meter dose rates, monitoring team data and some preliminary laboratory results (soil samples) will be available for them to determine projected milk concentration / response levels and 1, 2, and 50 year dose projections. A summary table will then be provided for remaining samples. The table will compare the samples against the PAR limits already determined. With the aid of this data the accident assessment rtaff will develop milk pathway protective action recommendations and Relocation / Return protective action recommendations. An agricultural sampling plan will be completed for days 2-3. This will conclude exercise activity on Day Two. Play will continue at the State EOC on Day Three simulating days 2 and 4 using a time jump. The State EOC will be fully staf f ed for an ingestion pathway scenario. Play will begin with a discussion of the implementation of previously determined milk. relocation / return protective. actions. A discussion will also be initiated to identify requirements .for emergency re-entry. Appropriate news releases will be developed which reflects the actions taken. Upon completion of these activities a time jump will occur to exercise day four. Day three laboratory results will be provided to the accident assessment team for analysis. Various agricultural sample data including water milk vegetables and soil will be included. Once the accident assessment team has demonstrated the ability to evaluate this data, summary tables will be provided with results already compiled and agricultural PARS will be developed and implemented. Appropriate news releases will be developed., A long term sampling plan will be discussed and an appropriate media releare will be developed. This will end exercise play. 22

FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : STATE EOC. AREAS REOUIRING CORRECTIVE ACTION : None cited. OBJECTIVE 4A 2 7 (30) : INGESTION EXPOSURE PATHWAY-PROTECTIVE ACTION IMPLEMENTATION : Demonstrate the capability to implement protective actions for Ingestion Exposure Pathway. EXTENT OF PLAY PLUME EXPOSURE PATHWAY: This objective will be demonstrated in conjunction with the Ingestion Pathway phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : N/A. EXTENT OF PLAY INGESTION PATHWAY : See extent of play for objective #26. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE STATE EOC. AREAS REOUIRING CORRECTIVE ACTION : I l None cited. OBJECTIVE 4t 28 (32) : RELOCATION. RE-ENTRY, AND RETURN-DECISION HAKING : Demonstrate the capability to develop decisions on relocation, re-entry, and return. 23

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t EXTENT OF PLAY : This objective will be demonstrated in conjunction with the Ingestion Pathway phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : N/A. EXTENT OF PLAY INGESTION PATHWAY PHASE See extent of play for objective #26. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : STATE EOC. AREAS REOUIRING CORRECTIVE ACTION : None cited. OBJECTIVE 4*29 ( 33) : RELOCATION, RE-ENTRY. AND RETURN-IMPLEMENTATION : Demonstrate the capability to implement relocation, re-entry, and return. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : This objective will be demonstrated in conjunction with the Ingestion Pathway phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : N/A. EXTENT OF PLAY INGESTION PATHWAY : See extent of play for objective #26. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : STATE EOC. AREAS REOUIRING CORRECTIVE ACTION : j i None cited. ] 1 24

e # OBJECTIVE #30 (34) : 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 : Second shift staffing rosters will~be provided at - each facility. An actual shift turnover will not be demonstrated. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE N/A. EXTENT OF PLAY INGESTION PATHWAY : This objective will be demonstrated in conjunction with the Plume Phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. AREAS REQUIRING CORRECTIVE ACTION : None cited. OBJECTIVE #31 (35) 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 EXPOSURE PATHWAY PHASE i N/A. EXTENT OF PLAY INGESTION PATHWAY N/A. ; 25 l l i

FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. AREAS REOUIRING CORRECTIVE ACTION : None cited. OBJECTIVE #32 ( 36) : UNANNOUNCED EXERCISE OR DRILL : Demonstrate the capability to carry out emergency , response functions in an unannounced exercise or drill. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : The exercise will be unannounced. . FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : ALL PARTICIPATING FACILITIES: STATE EOC, EOF, IFO, JOINT HEDIA CENTER, LOCAL EOC'S, STATE WARNING POINT, SOUTH WEST FIRE HUTUAL AID. EXTENT OF PLAY INGESTION PATHWAY I Demonstration of this objective will occur in conjunction with'the Plume Phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION , PATHWAY PHASE : N/A. , AREAS REOUIRING CORRECTIVE ACTION : None cited. , OBJECTIVE #33 ( 36) : OFF-HOURS EXERCISE OR DRILL Demonstrate the capability to carry out emergency response functions during'an of f-hours exercise or drill. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : The exercise will be off hours. 26

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FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE. PATHWAY PHASE : ALL PARTICIPATING FACILITIES: STATE EOC. EOF , IFO, JOINT HEDIA CENTER, LOCAL EOC'S, STATE WARNING POINT, SOUTH WEST FIRE HUTUAL AID. EXTENT OF PLAY INGESTION PATHWAY Demonstration of this objective will occur in conjunction with the Plume Phase of the exercise. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION PATHWAY PHASE : N/A. AREAS REQUIRING CORRECTIVE ACTION : None cited. i OBJECTIVE 4t 3 4 : 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 f or emergency response. EXTENT OF PLAY PLUME EXPOSURE PATHWAY : N/A. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE PLUME EXPOSURE PATHWAY PHASE : N/A. EXTENT OF PLAY INGESTION PATHWAY : N/A. FACILITIES DEMONSTRATING THIS OBJECTIVE DURING THE INGESTION , PATHWAY PHASE N/A.

l AREAS REQUIRING CORRECTIVE ACTION t None cited.

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e VERMONT YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE , 1993 , i

2.4 EXERCISE OBJECTIVES AND EXTENT OF PLAY - COMMONWEALTH OF MASSACHUSETTS ~ l f b b d J 2

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MASSACHUSE'1"rS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VEltMONT YANKEE NUCLEAR POWER STATION REP-14 Ubiectives State Local of Masp_achusetts Jurisdictiori 1.(2) MODILIZATION OF EMERGENCY yes yes P E R S O N N P.L . Demonstrate the capabl]ity to alert and fully mobillzo personnel for both emergency facilities and field operations. Demonstrate the capability to activate and staff emergency facilities for emergency operations. EXTENT _OF PLAY: State and local jurisdictions will be alerted and notified at each ECL according to plan. State and local mobilization of emergency and field operations in accordance with state and local plans. Facility activations are: Mansachusetts State EOC Mancachusetts State Police, Troop B, Northampton Emergency-Operations Facility MEMA Area IV EOC Joint Information Center Franklin County Dispatch Lm *n l EOCs to include Towns of: Bernardston Colrain Gill Greenfield Leyden Northfield Warwick d.RCA: None 2.(5) FACILITIES - EQUIPMENT, DISPLAYS, yes yes AND WORK ENVIRONMENT. Demonstrate the adequacy of facilities, equipment, displayn, and other materials to support emergency operations. , I 1-13-93

4 MASSACHUSETTS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdiction EXTENT OF PLAY: Facilities, equipment, maps, and displays at all facilities be adequate to support response ~ operations. Access to facilities will be controlled. ARCA: None 3.(3) DIRECTION AND CONTROL.

 -                   Demonstrate the capability                yes             yes to direct and control emergency operations.

EXTENT OF PLAY:

Each operational facility and its ORO will provide direction and control according to plan.

ARCA: MEMA Area IV will demonstrate improvement-in transmission of messages to local communities (See ARCA 91-15)-

4. (4) COMMUNICATIONS, Demonstrate the capability to communicate yes yes with all appropriate emergency personnel at facilities and in the field.

EXTENT OF PLAY: State and local facilities and field teams will , demonstrate the capability to communicate with appropriate locations. This includes systems between utility and state, state and local organizations. ARCA: None l l 2 1-13-93 ; l 1 l

MASSACHUSETTS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdiction 5.(6) EMERGENCY WORKER EXPOSURE yes yes CONTROL. Demonstrate the capability to continuously monitor and control radiation exposure to emergency workers. ,. EXTENT OF PLAY: Each off-site organization having a responsibility for emergency workers will utilize appropriate dosimetry to control radiation exposure. ORos will demonstrate the capability to issue, zero, read, record, accepted direct reading dosimetry. Each EW will be issued a non-self reading dosimeter (TLD) prior to service. Procedures will be demonstrated to manage exposure by EWs. Appropriate decisions will be made for EWs who may enter areas of higher dose limits. ARCA: None 6.(7) FIELD RADIOLOGICAL MONITORING - _ AMBIENT RADIATION MONITORING. yes no Demonstrate the appropriate use of equipment and procedures for determining field radiation measurements. EXTENT OF PLAY: Field Teams will be provided proper. equipment to perform field operations. Operational checks of equipment is performed prior to deployment. Each team demonstrates proper deployment and-knowledge of assigned locations. Proper monitoring procedures are performed, data promptly relayed to radiological Coordinator. Health Department will follow all standard operating procedures. ARCA: None 3 1-13-93

MASSACHUSETTS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdiction 7.(10) PLUME DOSE PROJECTION. Demonstrate the capability yes no to develop dose projections and protective action recommendations regarding evacuation and sheltering. State will develop appropriate protective actions based upon originating data supplied by licensee, available field data. EXTENT OF PLAY: The state will demonstrate location of plume and projected dose based on utility information and field team data. From this information the state will apply appropriate protective actions recommendations. Initial PARS may be derived based solely on utility information. Additional field team data may be utilized to adjust initial PARS. ARCA: None , 8.(8,9) FIELD RADIOLOGICAL MONITORING - AIRBORNE RADIOIODINE AND yes no PARTICULATE ACTIVITY MONITORING. Demonstrate the appropriate use of equipment and procedures for the measurement of airborne radiciodine concentrations as low as 0.0000001 microcuries per cubic centimeter in the presence of noble gases and obtain samples of. particulate activity in the airborne plume. EXTENT OF PLAY: Field teams perform operational checks of equipment prior to deployment. Calibration of equipment is within 12 months. Samples of radiciodine and particulate are in accordance with procedures. Field teams will measure radiciodine and particulate matter outside of plume location. Field teams will transmit data to radiological coordinator in accordance with its procedures. Samples are properly bagged and delivered to designated locations. ARCA: NIAT personnel will be trained with updated procedures for gaining reproducible counting geometry for air samples (see ARCA 91-16) 4 1-13-93

MASSACHUSETTS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdiction 9.(11) PLUME PROTECTIVE ACTION DECISION MAKING. Demonstrate yes no the capability to make timely and appropriate protective action decisions (PAD). EXTENT OF PLAY: This objective will be demonstrated by the state decision making team in accordance with the MARERP. Local organizations will be notified and respond in accordance with their plans and procedures according to their recommended protective action. The Massachusetts decision making team will coordinate with the decision making teams of Vermont and New Hampshire. ARCA: The State EOC will demonstrate improvement in promptly informing Area IV EOC and local EOCs of any radioactive release (See ARCA 91-17). 10.(12) ALERT AND NOTIFICATION. Demonstrate the capability yes yes to promptly alert and notify the public within the 10-mile plume pathway emergency planning zone (EPZ) and disseminate instructional messages to the public on the basis of decisions by appropriate State or local officials. EXTENT OF PLAY: The Massachusetts EOC will demonstrate coordination with the States of Vermont and New Hampshire regarding the t sounding of sirens, NOAA tone-alert radios, and EBS radio. Activation of the NOAA tone-alert radio system will be < demonstrated once, at the time of initial public alert and notification, through the State of Vermont using a test message. 5 1-13-93

MASSACilUSETTS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VERMOhT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdictio_r1 Sounding of sirens will be simulated. EBS activation will be demonstrated once, at the time of initial notification of the public, using a test message.

             "Real" EBS messages will be formulated and distributed by the Massachusetts EOC to the Media Center and Area IV, but not to the radio stations.
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EPZ communities will demonstrate this objective through the receipt of activation times from Area IV and will demonstrate their capability to monitor NOAA and EBS radio. ARCA: The ~rv~ r .' Vt. 'i :V V::: 6errnr:rcts crr:sr* s

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JCiw. une a art cad a gJee rulCA Ji 2d j . 11.(13) PUDLIC INSTRUCTIONS AND EMERGENCY INFORMATION. yes partial Demonstrate the capability to coordinate the formulation and dissemination of accurate information and instructions to the public. EXTENT ___ OF PLAY : The State will demonstrate the capability to formulate and disseminate to the public accurate information and instructions for the public. State will demonstrate coordination of message content with the States of Vermont and New Hampshire. The State will demonstrate the capability to provide instructions to the public and what. actions should be taken to protect themselves. Information should delineate local government jurisdictions affected by the message. ARCA: None 6 1-13-93

MASSACilUSETTS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION

State Local i of Massachusetts Jurisdiction 12.(14) EMERGENCY INFORMATION - MEDIA Demonstrate the capability to yes no coordinnte the development and dissemination of clear, accurate, and timoly information to the news media. EXTENT _O.F PLAY: The domonstration of this objective occurs primarily at the Media Center. The primary responsibility for briefing the media with respect to off site activities in Massachusetts lies with the State. Massachusetts will coordinate its news briefings and releases with Vermont, New Ilarnpshire and Vermont Yankee at the Media Center in accordance with the MARERP. l l The State EOC will provide information and periodic updates to the Media Center staff for use in preparing news briefings and news releases.

   -                                  EPZ communities may respond to questions about local l                                      emergency response but are encouraged to refer press inquires to the Media Center.

ARCA: Massachusetts will demonstrate exchange of public information with Vermont and New Hampshire i (See ARCA 91-19). i 13.(15) EMERGENCY INFORMATION - l RUMOR CONTROL. Demonstrate yes yes ! the capability to establish l and operate rumor control in a coordinated and timely manner. l l [~* l l

tubbnUnUdta l d vos t,Cr1VES AND EXTEN 1-Or-PLAY F OR 'AHE - 1993 FLLL SCALE EXERCISE VEllMONT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdiction EXTENT OF PLAY: In accordance with the MARERP, demonstration of this objective will occur primarily at the MA EOC, Incoming calln will be provided by controllers. At least one falso or misleading rumor relating to PARS will be provided by the controllers. Calls to the rumor control center will occur at a rate of at least six per hour per operntor during the Site Area Emergency and General Emergency levels. Rumor control personnel will screen messages for trends. Identified rumors (3 or more similar calls) will be addressed through an EBS message if the rumor af fects a PAD or through a news release from the Media Center if the rumor relates to general information. Communities will refer calls which address issues beyond loca] jurisdiction to the rumor control number. A contro))er message will be generated for each community tr irit iete e rerpense en:' ref errel r! ir.!rrretirr. ARCA: None IMPLEMENTATION OF PROTECTIVE ! ACTIONn - USE OF KI FOR yes yes EMERGF:NCY WORKERS, INSTITUTIONALIZED INDIVIDUALS AND THE GENERAL PUBLIC. Demonstrate the capability and resourcen to implement potassium iodido (MI) protective actions for emergency workers, institutionalized individuals, and, if the NLate plan specifies, the general public. EXTENT _QF PLAY: State will make determination for the issuance of KI to emergency workers. There are no institutions in the EPZ. Local OHos will simulate access and distribution of KI according to plans. Local OROs have lists of instructions available for those advised to take KI. No KI will actually be distributed or taken. ARCA: Area JV staff will demonstrate proper notification to local EUCs regarding use of KI (See ARCA 91-20). 4 8 OT 1-13-93

MASSACilUSETTS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION . State Local of Massachusetts Jurisdiction , 15.(18) IMPLEMENTATION OF PROTECTIVE ACTIONS - SPECIAL POPULATIONS. yes yes ' Demonstrate the capability and resources necessary to implement appropriate protective actions for spncial populations. EXTENT OF PLAY: This objective is plume dependent and will be demonstrated if necessary by the towns showing a list of special populations and a list of the resources necessary to support it. ARCA: None 16.(19) IMPLEMENTATION OF PROTECTIVE ACTIONS - SCHOOLS. Demonstrate yes yes the capability and resources necessary to implement protective actionn for school children within the plume pathway emergency planning zone (EPZ). EXTENT OF PLAY: The Colrain Elementary School, Colrain EOC and the Buckland, Colrain, Shelburne Regional School District Superintendent's Office will demonstrate this objective. l Actual response, including deployment of one school bus and escort to drive the route to Greenfield Community College Reception Center,-is scenario time dependent. i ARCA: None .l j 17.(20) TRAFFIC AND ACCESS CONTROL. Demonstrate the organizational yes yes ; capabillt.y and resources . I necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas. EXI.FET_OF PLAY: ] l State nnd local ORos consistent with developing scenarios and PADn will determine location of TCP/ACPs. Each local f acility impacted by the scenario will deploy to a single control point. Deployed EWs and activated facilities will demonstrate EW exposure control procedures. 9 1-13-93 l i j

MASSAcilUSETTS OBJECTIVES AMD EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdiction If the plume does not impact the towns of Bernardston, Greenfinid, Leyden and Warwick, they will demonstrate this objective by showing . the evaluator the traffic control points in their town and having the personnel and equipmont evaluated at the EOC at a convenient time. ARCA: None 18.(21) RECEPTION CENTER - MONITORING DECONTAMINATION, AND REGISTRATION. Demonstrate the no yes adequacy of procedures, facilities, equipment, and personnel for the radiological monitoring, decontamination, and registration of evacuees. EXTENT OF PLAY: This objective is plume-dependent. If necessary, Greenfjeld Community College will. demonstrate this objective through an interview with the Reception Center Manager. ARCA; None ' 19.(22) CONGREGATE CARE. Demonstrate the adequacy of facilities, no yes equipment, supplies, personnel, and procedures for congregate care of evacuees. EXTEN'I'_O.I' PLAY : This objective is plume-dependent. If necessary, a tour-of one of the facilities will be conducted out-of-sequence by the American Red Cross. 4dcA. .lene 10 1-13-93

APPJ KUbb OwnLL LALXLADL VERMONT YANKEE NUCLEAR' POWER STATION State Local of Massachusetts Jurisdiction 20.(23) MEDICAL SERVICES - TRANSPORTATION. Demonstrate the adequacy of vehicles, equipment, procedures, Not an objective and personnel for transporting (out-of-sequence contaminated, injured, or exposed annually) individuals. ARCA: None 21.(24) MEDICAL SERVICES - FACILITIES. Demonstrate the adequacy of the Not an objective equipmont, procedures, supplies, (out-of-sequence and poinonnel of medical facilities annually) responnible for treatment of contaminated, injured, or exposed individuals. 22.(25) EMERGENCY WORKERS, EQUIPMENT, AND VEllICI.En - MONITORING AND DECONTAMINATION. Demonstrate the no yes adequacy of procedures for the monitoi'ing and decontamination of emergency workers, equipment, and vehicles. This objective is plume-dependent. If necessary, the RM & D operation will be demonstrated out-of-sequence. However, Colrain will demonstrate this objective out-of-sequence at a convenient time. ARCA: None 23.(26) BUPPLEMENTARY ASSISTANCE (FEDERAL /OTHER). Demonstrate yes no the capability to identify the need for external assistance and to request such assistance from Federal or other support organizntions. EXTENT _QF PLAY: Massachusetts will coordinate its requests for supplementary assistance with Vermont and New Hampshire pursuant to the MARERP and the New England Rad Health Conference. ABEb None 11 1-13-93

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1993 FULL SCALE EXERCISE VERMONT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdiction 24.(27) POST-EMERGENCY SAMPLING. 7 Demonstrate the use~of no_ no equipment and procedures .. for the collection and ' transportation of samples from nrons that received-deposi.tlon from the airbornn plume. EXTENT _OF PLAY: None ARCA: None 25.(28) LABORATORY OPERATIONS. , Demonntrate laboratory no no operations and procedures for measuring and analyzing samples. EXTENT _pF PLAY: None bRCA: None 26.(29) INGESTION EXPOSURE PATHWAY - DOBE PHO.1ECTION AND PROTEOTIVE ACTION DECISION :t MAKING. Demonstrate the yes no-capability to project dose to the public for the , ingestion pathway and to recommonci protective measures. EXTENT Ol' _ PLAY: On day two of the exercise the MDPH Accident Assessment. c Team will convene at' the State EOC. - DOE ' fly over~

                                                                                                                      'i resultn, one meter dose' rates, monitoring team data and i                           some preliminary laboratory results (soil samples) will be available for. them to determine. projected;. milk                                        ,

concentration / response levels and 1, 2, and 50 year dose projections. A summary table will then be provided for : remaining samples. The tableLwill compare the. samples against the PAR limits already determined. With'the aid of this data the accident assessment' staff will develop milk pathway. protective action recommendations and-Relocation'/ Return protective action recommendations. : This will conclude exercise activity on Day Two. . ARCA: None - 12 1-13-93

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MASSACilUSF.TTS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VEllMONT YANKEE NUCLEAR POWER STATION ~ State Local of Massachusetts Jurisdiction 27.(30) INGESTION EXPOBURE PATIlWAY - PROTECTIVE ACTION IMPLEMENTATION. yes no Demonstrate the capability to implement. protective actionn for ingestion exponurn pathway. - EXTENT OF PLAY: Play will continue at the state EOC on Day Three simulating days 2, 4, and 8 using time jumps. The state EOC will be fully staffed for an ingestion pathway scennrlo. Play will begin with a discussion of the implomontation of previously determined milk, relot at lon/ return protective actions. A discussion will also bn initiated to identify requirements for emergency re-entey. An agricultural sampling plan will be completed for days 2-3 and appropriate news releases will be developed which reflect the actions taken. Upon complet.lon of these activities a time jump will occur to exercine day four. ARCA: None 28.(32) RELOCATION, RE-ENTRY, AND RETURN - DECIBION MAKING. Demonstrate the yes no capability to develop decisions on relocation, re-entry, and return. EXTENT Of PLAY: til activities associated with the identification of areas requiring Relocation by comparing simulated measurements to decision criteria, will be completed as they would in an actual emergency. Assessments will be made bnned on simulated data developed as part of the scenarlo. 13 1-13-93

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MASSACilUSETTS OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VI:llMONT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdiction Demonnt.: ntion of the decision making regarding assistance to inillviduals who are affected by the emergency will be accompiinhed at the state EOC in a group setting with reprenent ntives of all major state organizations. The conditlonn facing individuals will be determined by decisionn made under the above criteria. Discussions will he held regarding the actions that will be needed, priorItIen, and the processes for implementation. Demonntration of the coordination of decision making with other organizations will be accomplished with reprenentatives of all major state organizations. Based on fjeld survey information, decision makers will determine the relocation criteria. The corresponding iso-dose rate line will be drawn on appropriate maps. The area of interest will be discusses in regards to the effect on the public, and special population groups. Population estimates, relocation time estimates, and host communi t y requirements, as well as traffic control will be dinennned. ARCA: None 29.(33) RELOCATION, RE-ENTRY, AND RETURN - IMPLEMENTATION. Demonnt i nLe the capability to yes no implement relocation, re-entry, and return. , EXTENT OF PLAY: Relocation efforts will be demonstrated by focusing on those iudividuals not previously evacuated from the restrict ed zone; and for those evacuated populations who are unable to return because of contamination. Actions are dnmonstrated through internal meetings, briefings, disconolons and coordination. ARCA: None 14 1-13-93

L HASSACilOSE'1"I'S OBJECTIVES AND EXTENT-OF-PLAY FOR THE 1993 FULL SCALE EXERCISE VEHMONT YANKEE NUCLEAR POWER STATION State Local of Massachusetts Jurisdiction 30.(34) CONTINUOUS, 24-HOUR BTAFFINO. Demonstrate the capability to maintain staffiny on a continuous 24-hour basis through an actual shift change. EXTENT OF PLAY: Colrain will demonstrate this objective by shift change of key personnel. ARCA: See ARCA from the 1990 Yankee Rowe Exercise 31.(35) OFFCITE BUPPORT FOR THE EVACUATION OF ONSITE PERBoNNEL. Demonstrate the Not an objective capability to provide offsite support for the evacuation of onsito personnel. 32.(36) UNANNOUNCED EXERCIBE OR DRILL. Demonstrate the yes yes capability to carry out emergency response functions in an unannounced exercise or drill. EXTENT OF PLAY: Tbir TH e rt i ve vi:: be d e r :~T..= ~ r e : c t :' r i m the ::. r a::pecur, pan:1way. ARCA: None 33.(36) OFF-HOURS EXERCISE OR DRILL. Demonstrate the yes yes capability to carry out emergency response functions during nn off-hours exercise or drill. EXTENT OF PLAY: This objective will be demonstrated during the plume exposure pathway. ARCA: None 15 1-13-93

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                                                                                         ,4 VERMONT YANKEE                                             .

EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 s s

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3.1 EXERCISE GUIDELINES .

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Rev. O Page 3.1-1 VERMONT YANKEE EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993 3.1 CUIDELINES I A. Puroose d This package provides the guidance for conducting the 1993 Vermont Yankee Emergency Response Preparedness Exercise. It provides the framework for i demonstrating emergency response capabilities, conducting the exercise and-evaluating response activities. B. Concents of Operations and Control of the Exercise 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 exercise time sequence. The

Exercise Coordinator is also responsible for the selection and training of the personnel required to conduct and evaluate the exercise. .l Vermont Yankee will supply Controllers and Observers (Evaluators) for_ major l locations where an emergency response action will be demonstrated. Prior to the exercise, the Evaluators 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 f ar documenting and evaluating observed activities.

                                                                                          . l In each facility where an activity takes place, the Controller will make judgment decisions to keep the action going in accordance with the scenario      3 1

timeline. The Controllers will also provide advice to Observers and resolva i I minor problems which may occur. If a serious problem arises, an Observer. should first contact the Facility Controller who will then contact the i Exercise Coordinator for_ guidance or resolution of the problem. All major

Rev. O Page 3.1 2 requests for scenario modifications or holding periods must be clear;d through the Exercise Coordinator. Controllers also have. the aLthor ity to j resolve scenario-related problems which may occur during the exercise. l Evaluators for the exercise will observe the players as they perform 'their assigned emergency response functions. Evaluators 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 ) Evaluator shall be cognizant of procedures associated with the action. If an activity is to be simulated (as identified on the scenario simulation list), the Evaluator shall request the players to describe, in detail, all actions that would be initiated to effect the desired outcome of the assigned task. The Evaluators will critique the effectiveness of the emergency response actions taken during the exercise 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 exercise message cards and scenario parameters will be provided by : Evaluators 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

k ~ Rev. O~ Page 3.1-3 responding to plant events. Inconsistencies in the scenario may be intentional and may be required to test the capabilities of the emergency. response facilities to the maximum extent possible in a limited period of-time. C. General Guidance for the Conduct of the Exercise

1. Simularinz Emerrency Response Actions Since the exercise is intended to demonstrate actual capabilities,as realistically as possible, participants should act as they would in an actual emergency. Simulation of response activities will occur only when actions are outside of the defined miniscenarios. Section 3.2 also defines specific activities that will be simulated during the exercise.

When an emergency response is to be simulated, the Evaluator will provide i verbal or written directions on which actions are to be simulated.

2. Avoidine Violations of Laws violation of laws is not justifiable during the exercise. To implement this guideline the following actions must.be taken:

a. 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.

b. Participants will not direct illegal actions to be taken by other participants or members of the general public.

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c. Participants will not intentionally take illegal actions when responding to scenario events. Specifically, local traffic laws (i.e. speed limits) will be observed.

3. Avoiding Personnel and Property Endannerment 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.

4. 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 an 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 conclude with the words, "THIS IS A DRILL; THIS IS A DRILL." ; D. Emercency Response Imnlementation and Operations

1. Initial and Follow-up Notifications Initial and follow-up notification of the of the emergency classification will be made by the plant staff in accordance with existing emergency plan implementing procedures, unless directed otherwise.

2. Control Room Operations A Control Room emergency response crew will be positioned in the Simulator Control Room (SCR), located at the Vermont Yankee Training Center in l

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Rev. O Page 3.1-5 Brattleboro, Vermont. Early in station actions normally performed by the Control Room support personnel may be controlled and performed by the simulator controllers until after the ALERT classification. After the ALERT, these activities will be performed by the emergency response organization. Plant and reactor system parameters will be provided to the SCR emergency response crew by the simulator control board and the Controllers. Other information, such as radiological data and meteorological data, will be provided to the SCR emergency response crew as necessary. Communications links that duplicate the emergency communications capabilities available in , the actual Control Room will be used to communicate between the SCR and other emergency response facilities. The actual Control Room communication system for transmission of emergency announcements and information (e.g. Caitronics) will also be utilized.

3. Technical Supporr center (TSC) Operations The TSC emergency response organization will be activated during the exercise. Information for the TSC which would typically come from the Control Room, will originate from the SCR. Emergency Response Facility Information System (ERFIS) terminals at the TSC will be linked to the SCR to receive and transmit scenario data. In addition, TSC Communicators, who normally would be assigned to the Control Room to provide TSC requested plant data, will be staged at the Simulator. TSC Evaluators may also provide additional data to TSC players, as necessary.

4 Operations Suncort Center (OSC) Operations The OSC emergency response organization will be activated during the exercise. OSC response activities will be communicated'to the Technical Support Center. OSC Evaluators will accompany OSC teams dispatched during the exercise and will provide appropriate plant information and data to-the players. No team participating in the exercise should leave the Staging Area without notifying an Evaluator. l l

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5. Emerrency Operations Facilitv/ Recovery Center (EOF /RC) Operations The EOF /RC emergency response organization will be activated during the exercise. Information and data will be transmitted to the EOF /RC from.the TSC, SCR and the Emergency Response Facility Information System (ERFIS).- EOF Evaluators will provide other data to EOF /RC players as necessary, t

6. Off-Site Monitorine Teams Off-Site monitoring teams will.be fully activated and dispatched in accordance with existing procedures. Simulated data will be provided to each team by the Off-Site Monitoring Team Evaluators.

7. News Media Center (NMC) Operations l

l The News Media Center will be activated and staffed during the exercise. News Media Center staff will obtain all the necessary information on current l plant status through communications channels with the EOF /RC. Press releases l will be generated and disseminated in accordance with the Vermont Yankee Communications Department Emergency Response Plan and Procedures. All press. .l l releases are to be clearly marked: THIS IS A DRILL. ; l

8. Escurity Operations All exercise related security emergency response activities will be implemented in accordance with existing procedures. Access control and personnel accountability within the protected area will be demonstrated. At no time will actual plant security be violated in support of the exercise.

E. Exercise Termination The exercise will be terminated by the Exercise Coordinator when all emergency response actions have been completed in accordance with the exercise time sequence and exercise objectives. l

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Rev. O Page 3.1-7 The following steps will be implemented to terminate the exercise:

1. The Exercise Coordinator will obtain information from the Facility Controllers regarding the status of player actions and the demonstration of the exercise objectives.

2. The Facility Controllers are responsible for informing the Exercise Coordinator of their facility status and whether the emergency response actions and objectives have been satisfactorily observed, b

3. Upon receipt of information from the Facility Controllers, the Exercise Coordinator will inform the Site Recovery Manager and TSC Coordinator that all exercise objectives have been completed and the exercise can be-terminated.

4. A coordinated 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.

5. The Site Recovery Manager or TSC Coordinator will terminate the exercise.

The exercise may also be terminated under the following circumstances:

1. An actual plant emergency condition develops coincident with the exercise. ,

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2. An actual off-site emergency impacts the response actions of Vermont Yankee participants, l l

l In the event item 1 should occur, the following actions will be taken:

1. The Shift Supervisor will contact the TSC Coordinator and inform.him of the plant status. The TSC Coordinator will, in turn, contact the Site Recovery Manager and inform him of the plant status;

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2. The Site Recovery Manager will immediately inform any State representatives at the EOF of the nature of the emergency;

3. Concurrent with the notification in Step 2, the Control Room will announce the following statement over the plant paging system:

                           "The emergency plan exercise has been terminated. I repeat. The emergency plan exercise has been terminated."

This message may be immediately followed by the appropriate emergency announcements.

4. The Exercise Coordinator will be responsible for directing the actions of 4

all other exercise participants. , In the event that Item 2 should occur, the following actions should be taken:

1. The Shift Supervisor will notify the control Room Controller who, in.

turn, will notify the Exercise Coordinator.

2. 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

3. The Exercise Coordinator will be responsible for temporarily halting the ,

exercise until such time a decision is made regarding continuing the activities or termination.

4. If the final decision is to cancel the exercise, the Exercise Coordinator .

will be responsible for directing the activities of all exercise participants, as well as for informing the NRC of the exercise termination.

5. If the final decision is to continue the exercise, the Exercise .

Coordinator is responsible for informing all Evaluators of any projected - changes to the expected response action (s).

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6. The Exercise Coordinator will direct.the organization as to.the appropriate action required to restore the exercise sequence.

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m + 4 4 i 1 C VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 -

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Rev. 0 l Page 3.2-1 , VERMONT YANKEE NUCLEAR POWER STATION 1 EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 3.2 PLAYER INSTRUCTIONS AND CROUND RULES The Vermont Yan'kee Emergency Response Preparedness Exercise will be conducted during the week of April 25, 1993. All emergency response ' facilities will be fully activated, and the scenario will be driven by the simulator, as in past exercises. This year's exercise is a full-participation, off-hours and unannounced exercise, which will involve participation of of the Vermont Yankee station and corporate personnel. I The exercise is also off-hours and unannounced for the the State of 1 Vermont, State of New Hampshire, Commonwealth of Massachusetts, and local communities within the plume exposure EPZ who plan to participate in the exercise. In addition to the plume exposure exercise, an ingestion pathway exercise will be conducted on the following days. This activity requires i minimal participation by VY station personnel and will primarily focus on the response capabilities of the respective state organizations. The successful demonstration of emergency response capabilities will depend on player response and protocol. The following information contains details-and instructions for the players regarding the exercise. Department Heads are responsible for ensuring that personnel are made aware of this information prior to the scheduled exercise date.

                                                                                   'I A. General Guidelings

1. Participants will include the Exercise Coordinator, Players, Controllers, Observers, NRC and FEMA Evaluators. Controllers and Observers will provide players with command and message cards to initiate emergency response actions. Controllers, Observers, NRC Evaluators and FEMA Evaluators will also evaluate and note player I actions. Controllers, Observers, (herein referred to as

             " Evaluators") and Federal (NRC and FEMA) Evaluators will be l

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I Rev. O Page 3.2-2 identified by badges. j t

2. Always identify yourself by name and function to the Evaluators.

Wear a name tag if one is provided.

3. You may ask the Evaluator for information such as:

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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. '

d. Counting efficiency of all counting equipment. >

e. Activity from nose swabs or ski n contamination surveys.

4. You may not ask the following from the Evaluators:

a. Information contained in procedures, drawings, or instructions.

b. Judgments as to which procedures should be used.

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c. Data which will be made available later in the scenario.

d. Assistance in performing actions.

e. Assistance in performing' calculations.

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5. Play out all actions, as much as possible, in accordance with your j plan and procedures as if it were an actual emergency. If an action or data is to be simulated, an Evaluator will provide appropriate l direction.

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6. Identify and discuss your actions to NRC Evaluators, if present in ;

your facility and observing your functions. ,

7. Periodically speak out loud, identifying your key actions and decisions to the Evaluators. This may seem artificial, but it will assist the evaluators in determining the various response actions being initiated and is to your benefit.

8. When you are assigned to complete a response action, be sure to notify an Evaluator prior to performing the action. Let the ,

Evaluators prioritize which actions will be observed and wh!ch ones will not. If an Evaluator elects to observe your activity, en.9tc the Evaluator remains with you to observe the task (i.e don't lose the evaluator enroute to the area where the action will take place).

9. If you are in doubt about completing a response action, ask your Evaluator for clarification. The Evaluator will not prompt or coach you. Emergency response actions must not place participants in any potentially hazardous situations.

10. The scenario has been scrutinized to anticipate as many success paths that may be initiated by the response teams. In the event you i or your staff determine there may be alternative responses to scenario conditions, you may not be allowed to initiate your proposed "fix". You will however, be credited with the initiative and requested to continue your response in accordance with a

   " Command Card" from the Evaluator. In addition, the Evaluator may periodically issue messages or instructions designed to initiate response actions. You must accept these messages immediately. They are essential to the proper completion of the exercise scenario.

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11. If an Evaluator intervenes in your response actions and recommends you redirect or reconsider your play actions, it is for'a good reason. The Evaluator's direction may be essential to ensure demonstration of objectives for all participating groups. ,

12. If you disagree with your Evaluator, discuss your concerns in a professional manner. However, the Evaluator's final decisions must 4

be followed.

13. Respond to questions in a timely manner.

14. Do not accept any messages / instructions from the Federal (NRC and FEMA) Evaluators. They should work through Vermont Yankee Evaluators if they want to initiate additional emergency conditions.

However, you may answer questions directed to you by Federal 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 Evaluator. ,

15. 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 .;

dosimetry.

16. Evaluators 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 station radiological practices and procedures.

17. Utilize status boards and log books as much as possible to document and record your actions.

18. Always begin and end all communications with the words "THIS IS A !

1 DRILL," so that exercise related communications are not confused j with an actual emergency. ) i I

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19. Keep a list of items which you believe will improve your plans and procedures. A player debriefing will follow the exercise. Provide ,

any comments or observations to your lead player or Evaluator after the exercise. Areas for improvement or weaknesses when corrected will improve the overall emergency response capability, i B. Plaver's Simulation List The following describes those spec'.fic actions which 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.

1. 5:enario specific data vill be programmed into various Simulated :

Plant Process Computer (SPPCS) terminals via the simulator. The Control Room's SPPCS terminal will remain tied to the plant process computer (ERFIS).

2. A sufficient number of individuals from the Vermont Yankee Emergency Response Organization will be prestaged at the Simulator.

3. Meteorological data vill be simulated through the simulator SPPCS computer.

4 After plant evacuation and accountability have been completed, plant i personnel and contractors / visitors, not directly involved in the exercise, will be allowed to return to work at the discretion of the > TSC Coordinator. i

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 off-site monitoring sampling is required, charcoal cartridges will be used in place of silver zeolite cartridges.

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7. Off-Site monitoring teams and security boundary monitoring personnel will not wear either protective clothing or respirators.

8. The inner Sate and electrically controlled doors will not be.left in-the open position during the exercise. ;

9. The plant Gaitronics is not available from the simulator; actual l plant announcements will be coordinated by the controllers and made.

from the Vermont Yankee plant Control Room.

10. Evaluators will not be issued dosimetry unless plant access is required prior to the exercise. Security will be notified of the j

                                                                                -t Evaluators assigned locations.                                         _

11. All decontamination actions associated with the scenario events may ;

be simulated after discussion and approval by the Evaluator [

12. The use of respiratory protection equipment may be simulated by plant personnel after discussion and approval by_the Evaluator. +

f 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 exercise:

1. Players reporting to the plant Control Room will be directed to an area (SS office) that will have a Control Room Evaluator and ;

communications link with the simulator. All Control Room exercise i communications should be directed to the SCR.

2. All exercise-related Gaitronics calls to the Control Room and vice versa will be relayed or answered by the Contiol Room-Evaluator. ;

CHANNEL 3 should be utilized for all exercise messages. r

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3. Gaitronics plant announcements will be coordinated by the Simulator Evaluator. They will be made by the operating crew in the plant Control Room.

4. TSC Communicators normally assigned to the Control Room and a Radiation Protection Technician for tt.nsmitting initial radiological and meteorological data will be prestaged in the simulator.

5. Personnel movement in and out of the SCR will be limited to the Evaluators.

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 Telecommunications System (FTS 2000) Emer5ency Notification System (ENS)-NRC telephone will be operable. The orange NAS telephone extension is 613.

D. Player's Gamesmanshin The following is a list of items that should be followed to improve gamesmanship during the exercise:

1. Make it known when significant events occur or when you are about to perform a significant activity.

2. Keep all messages, status boards, and problem boards accurcte, current, timed, and dated. l 2

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3. Hold briefings regularly, approximately every 30-45 minutes, or as conditions warrant.

4 Key players should wear badges which identify their role. Bound log books should be used in all emergency response facilities.

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5. All announcements, including those on the Caitronics, should state "THIS IS A DRIII. "

6. Avoid simulation unless it has been specified. Use protective clothing where called for (e.g. , step-off pads, etc.) .

E. Personnel Accountability and Particioation (Exemoted Participants) Procedures require that all participants be identified. Proper identification will not only help eliminate confusion, but is necessary for security and accountability. This requirement applies to all areas within the plant fence, Governor Hunt House, EOF /RC, simulator area, News Media Center, and the Vermont Yankee Corporate Office in l Brattleboro. Although it is expected that all personnel will respond to the declared emergency as delineated in the applicable procedures, it is recognized that a number of persons (e.g. , normal plant operations shift, normal. security complement, fire watches, etc.) will not participate due to the nature of their assigned duties and activities. Department Heads should 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 eersonnel 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. Plant Security will be provided with the list of exempt personnel for the l 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, and Duty Chemistry and Radiation Protection Technician and other individuals identified by the Department Heads.

Rev. O Page 3.2-9 i F. Off-Site Particioation (Federal. State and Local) , This year, Vermont Yankee is conducting a full-participation exercise which will involve substantial participation of the States of Vermont, - New Hampshire, Commonwealth of Massachusetts and the local towns within-the Plume Exposure pathway EPZ. . The capability to notify federal, state, and local authorities of emergency classifications in accordance with established procedures will be demonstrated as follows:

a. NRC will be notified by utilizing the FTS 2000 ENS-NRC telephone,

b. Vermont, New Hampshire, and Massachusetts State Police dispatchers i

and State Emergency Operations Centers (EOCs) will be notified through the orange NAS telephone.

c. 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 ; in the exercise). 5 If any state official tries to contact the actual plant Control Room 't REGARDING THE EXERCISE, the Vernon switchboard should transfer the call , to the Simulator Control Room in Brattleboro. The NAS orange telephone extension in the SCR is 613. G. Exercise Critiaues , l The following is a brief description of the critique sessions that will be held after the exercise. The critiqu;e sessions are held to determine .I whether the stated exercise objectives were met, verify the effectiveness of the emergency plan and procedures, and identify areas for future 1 1 improvements. The specific schedule for the critique sessions will be .; announced at the conclusion of the exercise. l 1 l

Rev 0 Page 3.2-10 Emercency Response Facility Critioues 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 held: A

1. SRM and EOF

2. TSC and Simulator Control Room j

3. OSC and Security

4. News Media Center !

Controller Debriefine This session will be conducted by the Exercise Coordinator _to compile all ; exercise comments and findings. Participation is limited to Exercise Controllers. Exercise Critioue This session will be conducted by the Exercise Coordinator to present to management a summary of all major findings identified during the , exercise. Participants include Vermont Yankee management, Exercise Controllers, key players, and the NRC. NRC Exit Immediately following the exercise critique, the NRC will present their preliminary findings. Farticipants will be the same as in the exercise critique session. t

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                                                           .1 VERMONT YANKEE NUCLEAR POWER STATION                     ,,

EMERGENCY RESPONSE PREPAREDNESS. EXERCISE 1993 3.3 PROCEDURE EXECUTION LIST h

Rev. O Page 3.3-1 3.3 EMERGENCY PIAN IMPLEMENTING PROCEDURE EXECUTION LIST Procedure Number Rev. No. Title AP 3125 11' Emergency Plan-Classification and ! Action Level Scheme OP 3500 12 Unusual Event OP 3501 13 Alert OP 3502 25 Site Area Emergency , OP 3503 27 General Emergency OP 3504 25 Emergency Communications 1 OP 3507 20 Emergency Radiation Exposure Control OP 3510 18 Off-Site and Site-Boundary Monitoring OP 3511 6 Off-site Protective Actions Recommendation OP 3513 14 Evaluation of Off-Site Radiological Conditions OP 3524 10 Emergency Actions'to Ensure l Accountability and Security Response i OP 3525 5 Radiological Coordination OP 3530 14 Post-Accident Sampling OP 3531 4 Emergency Call-In Method l 1

.4 J VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 4.0 CONTROLLER AND OBSERVER INFORMATION 9 J

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t VERMONT YANKEE NUCLEAR POWER STATION. EMERGENCY' RESPONSE PREPAREDNESS EXERCISE-1993-P 4.1 CONTROLLER AND OBSERVER ASSIGNMENTS NOTE: ASSIGNMENTS VILL BE PROVIDED AT THE EXERCISE BRIEFING SESSION I s o t

muis w. A & 2+ j 5 D e -,-a,-, b--2 2.2- n.. L--- + J - p4-, e I f VERMONT YANKEE EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 .

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T 4.2 CONTROLLER AND OBSERVER EXERCISE GUIDANCE (

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VERMONT YANKEE EMERCENCY RESPONSE PREPAREDNESS EXERCISE , 1993 4.2 CONTROLLER AND OBSERVER EXERCISE GUIDANCE Prior to the exercise, each Evaluator will be provided a scenario package , and the plant emergency plan implementing procedures that correspond to, their respective assignments. It is the responsibility of the Evaluator to read the contents of the scenario package and review the procedure (s) associated with their assignment. ! Each Evaluator will be requested to attend a pre-exercise briefing session. , Any questions regarding the scenario or assignments should be discussed at this time. Each Evaluator should ensure that they are familiar with location (s) required by their assignment. Tours will be provided as a portion of the training; however, these tours will be limited in their , duration. It may be advisable to plan an additional tour, if necessary. Observers should familiarize themselves with their assigned Facility Controller prior to the exercise. The Facility Controller is responsible to direct Observer activities throughout the course of the exercise.~ At the exercise termination, each Facility Controller is responsible to meet with their Observers to obtain- their . comments, observations and documentation. Each Facility Controller is responsible to provide this : documentation to the Exercise Coordinator at the conclusion of the critique , session. Each Facility Controller is also responsible to provide a brief summary of their Observer comments to the Exercise Coordinator for presentation during the critique.

Evaluators 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 Evaluators. Evaluators 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. The primary role of the Evaluator is to document the emergency response activities of the players. In order to document emergency response activities, each Evaluator is required to complete the Emergency Exercise / Drill Observers Evaluation Form. When completing this form, each- , Evaluator should attempt to differentiate their comments into either adequate, needs improvement or potential weaknesses. For identified weaknesses of personnel, equipment, etc. provide a clear written description of the finding, with recommendations for improvement detailing corrective actions, if possible. If the evaluation criteria is not applicable to the exercise objectives or the scenario, this should also be noted on the evaluation form.

r Rev. 0- , Page 4.2-2 Evaluators should D21 allow their biases to be documented as recognized weaknesses or deficiencies. Comments and recommendations should be further subdivided according to the following major headings: Facility Activation and Organizational Control, Communications, Adherence to Plans and Procedures, Equipment Capabilities, Scenario, Training, Facility Layout,. Off-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Comments. Facility Activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the facility was activated;_ (3) when initial activities are organized; (4) whether personnel performance follows the organized arrangements specified by plant prucedures; and (5) the efficiency of methods of authority transfer. If a transfer of responsibility occurs , then the Evaluator should determine if affected personnel are aware that the transfer has occurred. 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; (3) whether there were enough communications personnel to make use of all 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 traffic flow); (6) whether there were any recognized difficulties in use of computer systems; and (7) shether status boards are effectively used. Evaluators should document their comments in this area very carefully, providing sufficient details to track any recognized deficiencies. Plans and Procedures comments should identify: (1) whether personnel were , familiar with the details or overall concepts of applicable procedures; (2) whether situations developed which required deviation from the procedure or plan; (3) whether personnel were overwhelmed with procedural requirements distracting them from performing their required emergency response function; and (4) whether the procedures adequately described the actions required to complete an assigned function. Eaulement Capability 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. assignment; (3) Vhether backup equipment was readily available when malfunctions were reported; (4) shether the available systems provide an adequate service; and (5) whether equipment malfunctions impacted the expected emergency response. Scenario related comments should address: (1) whether sufficient information was available to ensure appropriate player response; (2) whether the scenario details deviated from actual procedural requirements; and (3) Whether the scenario detail provided any prompts to the player.

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Page 4.2-3 Traininc comments should identify: (1) whether plant personnel have been provided sufficient training to handle "ad hoc" procedural deviations; and (2) whether training identifies improper procedural requirements. Facility Layout comments should identify: (1) whether the available work space was adequate; (2) whether traffic flow hindered the response efforts; (3) whether the communications available in the work area were adequate; (4) whether the noise level hindered emergency response efforts; and (5) whether sufficient references were available to complete the job assignment. Off-Site Monitorine comments should identify: (1) the adequacy of sampling methods; (2) the adequacy of reporting and documentation; and (3) the effectiveness of the team in defining radiological status. Dose projection . methods should also be evaluated with this general category. Consideration l of dose projection methods should identify: (1) the effectiveness of methods to interpret off-site conditions; and (2) the effectiveness of using the dose projections in positioning off-site teams. Personnel Dosimetry / Exposure Control comments should identify: (1) the .! timeliness and effectiveness of dosimetry distribution; (2) the effectiveness of protective measures; (3) the adequacy of established contamination control access points; (4) the adequacy of exposure planning measures afforded in plant activities; and (5) the adequacy of decontamination and posting techniques. The Evaluators evaluation and documentation forms are found in Section 4.3. All such documentation must be provided to the Controller after the exercise and prior to the critique. > 1 l l l i

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Rev. O Page 4.3-1 l VERMONT YANKEE EMERGENCY PREPAREDNESS EXERCISE 1993 4.3 EXERCISE EVALUATION CRITERIA As discussed in Sections 4.1 and 4.2, each Evaluator has been assigned specific areas of response to observe. This section has been developed to assist the Evaluators in recording and doctunenting their findings and observations. The following attachments are included: , Attachment A provides a form to be used to maintain an event chronology log. Attachment B contains evaluation checklists for each emergency response facility. Each Evaluator should complete the appropriate checklist. Attachment C provides an evaluation form that should be used to summarize major findings and observations. This form MUST BE completed by each Evaluator. All three attachments should be completed and submitted to-the Facility Controller. Each Facility Controller will submit the completed-attachments to the Exercise Coordinator for documentation of exercise observations and findings. b f 5 s s I

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Rev. O Page 4,3-2 ATTACHMENT A Vermont Yankee Nuclear Power Station Emercency Response Exercise / Drill Evaluator's Observations-Chronolocical Loc TIME COMMENT /0BSERVATION 1 i l l l 1 i i i 1 l 1 1 I I Name: Area Evaluated: Date:

l Rev. O Page 4.3-3 ATTACRMENT B Vermont Yankee Emercency Exercise / Drill Evaluation Checklist i INSTRUCTIONS l The following checklists are provided to assist the Evaluator with their evaluation of the drill / exercise. The Evaluator should complete the checklist (s) for their assigned locations (s). To complete the evaluation checklist (s), utilize the rating scale listed below. Any comments or suggestions for improvement, should be included on Attachment C, the Emergency Exercise / Drill Evaluation Form or on a separate piece of paper. Rating Symbol Comments and Succested Improvements Adequate A Comments may include strong positive strengths demonstrated by player actions and responses. Adequate indicates that the demonstrated performance was consistent with plans and procedures. Inadequate I Comments should provide a clear description of finding with recommendations for improvement, if possible. Inadequate indicates that the demonstrated performance could have , precluded effective implementation of plans and procedures. Not Observed or N No comments or suggestions are required. Not Applicable i l I Note: If your evaluation indicates inadequate performance, please provide a description of l the problem area on the Emergency Exercise / Drill Evaluation Form. !

Rev. O Page 4.3-4 ATTACHMENT B (continued) Section Eagg I. Control Room (Simulator and Actual) 4.3-5 II. Technical Support Center 4.3-6 III. Operations Support Center 4.3-8 IV. Emergency Operations Facility / Recovery Center 4.3-10 V. Site and Off-Site Monitoring 4.3-12 VI. Security 4.3-131 VII. News Media Center 4.3-14

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Page 4.3-5 l I. CONTROL ROOM l

A. Accident Assessment /Emercenev Classification Ratinr. Comments

1. Did the Control Room staff demonstrate the Yes/No ability to recognize emergency initiating conditions and classify the events in accordance with AP 3125?

[ . l l 2. Did the Control Room staff demonstrate the Yes/No ( ability to coordinate the assessment of l l plant conditions and corrective actions ! l with the Technical Support Center? j

B. Notification and Communication i I l I

l l 1. Did the Control Room staff demonstrate the Yes/No l l ability to notify the plant staff of an emergency through the use of alarms and the o public address system?

2. Did the Control Room staff demonstrate the .Yes/No ability to notify federal and state authorities of emergency classifications in i accordance with established procedures? j

3. Was information flow within the Control Yes/No Room and to other appropriate emergency I

response facilities timely, complete, and accurate?

'l

4. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the Control Room staff?

5. Vere adequate emergency communication Yes/No systems available in the control Room to transmit data and information to other emergency response facilities?

C. Activation and Resoonse

1. Did the Control Room staff demonstrate the Yes/No 'l ability to appropriately implement l Emergency Plan Implementing Procedures ;

and did they follow them? 1

2. Was the person in charge in the Control Yes/No Room clearly identifiable and was good command and control taken at the Control l Room?

! Controller / Observer Name: l l

Rev. O Page 4.3-6 II. TECHNICAL SUPPORT CENTER .; 1 A. Accident Assessment /Emercency Classification Ratine Comments

i

1. Did the TSC staff demonstrate the ability Yes/No to support the Control Room in identifying the cause of the incident, mitigating the consequences of that incident, and placing the plant in a stable condition?

2. Did the TSC staff demonstrate the ability Yes/No to coordinate the assessment of plant conditions and corrective actions with the the Control Room?

3. Did the TSC staff demonstrate the ability 'Yes/No to initiate and coordinate corrective actions in an efficient and timely manner?

4. Did the TSC staff demonstrate the ability Yes/No to direct and coordinate the taking of appropriate chemistry samples to analyze plant conditions?

5. Did the TSC staff demonstrate the ability Yes/No to participate with the Control Room and EOF /RC in emergency classification and EAL discussion?

B. Notification and Communication ,

1. Was information flow within the TSC and to Yes/No other appropriate emergency response facilities timely, complete, and accurate? ,

2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the TSC staff?

3. Were adequate emergency communication Yes/No systems available in the TSC to transmit data and information to other emergency response facilities?

4 Was information concerning plant Yes/No conditions disseminated between the Control Room and TSC performed in a timely manner?

5. Were status boards utilized and maintained Yes/No to display pertinent accident information at the TSC?

Controller / Observer Name:

Rev. 0-Page 4.3-7 C. Activation and Response Ratine Comments

1. Did the TSC staff demonstrate the ability Yes/No to activate and staff the TSC?

2. Did the TSC staff demonstrate the ability Yes/No to appropriately implement Emergency Plan Implementing Procedures and did they follow them?

3. Were initial and continuous accountability Yes/No checks of TSC and CR personnel performed?

4. Did the TSC Coordinator establish and Yes/No coordinate access control into the Protected Area and Control Room?

5. Did the TSC Coordinator demonstrate the Yes/No ability to maintain command and control of TSC emergency response activities?

6. Did the TSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had developed?

7. Was the TSC organization and initiation of Yes/No activity efficient and vell organized?

1 l Controller / Observer Name:

Rev. O Page 4.3-8 III. OPERATIONS SUPPORT CENTER A. Notification and Communication Rating Comments

1. Was information flow within the OSC and Yes/No to other appropriate emergency response facilities timely, complete, and accurate?

2. Was adequate record keeping of events, Yes/No -

actions, and communications documented and ; logged by the OSC staff?

3. Were adequate emergency communication Yes/No systems available in the OSC to transmit data and information to other emergency response facilities?

4. Were status boards utilized and maintained Yes/No to display pertinent accident information at the OSC7 B. Activation and Response

1. Did the OSC staff demonstrate the ability Yes/No to activate and staff the OSC7 J

2. Did the OSC staff demonstrate the ability Yes/No i to appropriately implement Emergency Plan Implementing Procedures and did they follow .]

them?

3. Were initial and continuous accountability Yes/No checks of OSC personnel performed?

4. Did the OSC Coordinator and OSC Yes/No j Coordinator's Assistant demonstrate the i ability to maintain command and control of -l OSC emergency response activities?

5. Did the OSC keep other emergency response Yes/No 'l facilities advised of the status of their -l activities and information which they had !

developed?

6. Was the OSC organization and initiation of Yes/No activity efficient and well organized?

7. Did the OSC staff demonstrate the Yes/No j ability to provide adequate radiation protection controls for on-site .

emergency response personnel? Controller / Observer Name: , 1 l

-1

Rev.-0 Page 4.3-9 III.-OPERATIONS SUPPORT CENTER 4 Ratinc Comments

8. Did the OSC staff demonstrate the Yes/No ability to monitor and track radiation exposure of on-site emergency response personnel?

9. Did the OSC staff demonstrate the Yes/No ability to obtain and analyze appropriate chemistry samples as ,

directed by the TSC?

10. Did the OSC staff demonstrate the Yes/No- ,

ability to initiate, brief, and dispatch on-site assistance teams? ,

11. Were on-site assistance teams able to Yes/No troubleshoot and evaluate problems with ;

plant equipment and systems?

12. Were there adequate administrative Yes/No controls and documentation taken to perform the necessary repairs of plant equipment and systems during an emergency situation?

5 k

t r i Controller / Observer Name:

l Rev. O i Page 6.3-10 j IV. EMERGENCY OPERATIONS FACILITY / RECOVERY CENTER i j A. Notification and Communication Ratine Comments l

1. Was information flow within the EOF /RC Yes/No and to other appropriate emergency response .!

facilitie, timely, complete, and accurate? j

2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the EOF /RC staff? ,

3. Were adequate emergency communication Yes/No systems available in the EOF /RC to transmit data and information to other emergency response fccilities?

4. Was information concerning plant Yes/No conditions disseminated between the TSC and EOF /RC performed in a timely manner?

5. Were status boards utilized and maintained Yes/No ,'

to display pertinent accident information at the EOF /RC7 B. Activation and Response i

1. Did the EOF /RC staff demonstrate the Yes/No ability to activate and staff the EOF /RC? e i

2. Did the EOF /RC staff demonstrate the Yes/No i ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them?

3. Did the Corporate Security Force Yes/No '

establish access control into the EOF /RC? , f

4. Did the EOF Coordinator demonstrate the Yes/No ability to maintain command and control of ,

EOF emergency response activities?

5. Did the EOF /RC keep other emerge ncy Yes/No ,

response facilities advised of the status of their activities and , information which they had developed? ,

6. Were the EOF /RC organization and the Yes/No initiation of activity efficient and well organized? .

Controller / Observer Name:

Rev. O Page 4.3-11

                                                                        .l IV. EMERGENCY OPERATIONS FACILITY / RECOVERY CENTER Ratine     Comments

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?

8. Did the Site Recovery Manager Yes/No demonstrate the ability to de-escalate from the emergency phase into the recovery phase?

9. Were preliminary recovery plans Yes/No established and discussed between the Site Recovery Manager and appropriate personnel?

C. Radiological Assessment

1. Was information concerning radiological Yes/No and meteorological data obtained by appropriate EOF personnel in a timely manner?

2. Did the EOF staff demonstrate the ability Yes/No to perform off-Site dose assessment in accordance with OP 35137

3. Did the EOF staff demonstrate the ability Yes/No to effectively track and define the plume utilizing the computerized dose assessment model (METPAC)? i D. Protective Action Decision Makinn

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?

2. Did the EOF Coordinator obtain and Yes/No provide the necessary information to the Site Recovery Manager concerning protective action recommendations in accordance with OP 35117

3. Did the Site Recovery Manager Yes/No demonstrate the ability to make protective action recommendations to off-site authorities in accordance with Procedure OP 3511?

Controller / Observer Name:

Rev. O Page 4.3-12 V. SITE AND OFF-SITE MONITORING A. Activation and Response Ratinr. Comments

1. Did site and off-site monitoring Yes/No teams demonstrate the ability to ,

transmit information over the radio utilizing proper units and terminology in accordance with Procedure OP-35107

2. Were site and off-site monitoring Yes/No teams dispatched and deployed in a timely manner?

3. Were team members familiar with the use Yes/No of equipment, field monitoring procedures, and what was required of them?

4. Were off-site monitoring teams able to Yes/No determire and communicate their location in the field using appropriate maps and sample paints (landmarks)?.

5. Were off-site monitoring teams briefed Yes/No on pla.it conditions and changes?

6 L Controller / Observer Name:

Rev. O Page 4.3-13 VI. SECURITY A. Activation and Response Ratine Comments

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

2. Were' access control points established Yes/No and maintained to control access at the site and the Protected Area? ,

3. Did the Security staff demonstrate the Yes/No ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them?

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l Controller / Observer Name:

Rev 0 Page 4.3-14 VII NEW MEDIA CENTER A. Activation and Resoonse Ratinn Comments >

1. Did the News Media staff demonstrate the Yes/No ability to activate and staff the News Media Center? -

2. Was information flow between the News- _ Yes/No Media Center and the EOF /RC timely, complete, and accurate?

3. Were the News Media staff familiar with Yes/No their plans and procedures and do they follow them?

4. Did the News Media staff demonstrate the Yes/No ability to provide accurate and timely information concerning the emergency to the public and the news media? ,

5. Did the News Media staff demonstrate the Yes/No ability to coordinate news releases with the state's public information representatives?

6. Did the News Media staff demonstrate the Yes/No ability to provide briefings for and to interface with public and news media?

Controller / Observer Name:

Rev. O Page 4.3 15 ATTACHMENT C EMERCENCY EXERCISE / DRILL OBSERVERS EVALUATION FORM Observer's Name: Exercise / Drill Date: Exercise / Drill

Title:

Observer's Location: Time Started: Time Ended: Observed: Player Punction Overall Performance and Observations: (Include the proper and effective use of procedures, equipment and personnel) Recognized Weaknesses and Deficiencies: Comments and Recommendations (Specific): NOTE - Use additional pages as required. Signature Title VYOPF 3505.02 OP 3505 Rev. 15 . Page 1 of 1

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS RXERCISE 1993 5.0 EXERCISE SCENARIO l r J l i i l I i

A -- + = h- k 4 4 5 VERMONT YANKEE NUCI. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1 1993 I 5.1 INITIAL CONDITIONS i l B 5 6 h t ,e

Rev. O Page 5.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 5.1 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise) .

1. The reactor is now at approximately 100% power. The reactor has been operating steady state for the past seventeen months with no recent shutdowns. The core is nearing the end of the current operating cycle.

A refueling outage is scheduled to begin in three weeks.

2. Night Orders for the operations crew provides the following information:

a. The Circulating Water System is operating in Open Cycle.

b. All equipment is operable and available.

c. No Limiting Conditions of Operation (LCOs) are in effect.

3. The following on-site meteorological conditions exist at 0245:

Wind Speed, aph (lower / upper) 3.0/3.5 Wind Direction, degrees (lower / upper) 163/170 Delta Temperature, F (lower / upper) -0.5/1.2 Ambient Temperature, F 32.0 Precipitation, inches 0.00

4. Regional Meteorological Forecast Information:

A low pressure system is currently centered over the Pennsylvania area. Mostly cloudy and overcast this morning. Temperatures in the low to mid

   'N         30's. Southerly winds from 3 to 6 mph.

i Rev, O Page 5,1-2 Table 5.1-1 Jnitial Plant and Reactor System Values Reactor Vessel Coolant Level 161 Inches l Reactor Pressure 1008 psig Reactor Coolant Temperature 527 *F Reactor Power - APRM (average) 99.9 % Core Plate D/P 18 psid Total Core Flow 46 x 10' lbm/hr Main Steam Line Flow Total 6.4 x 10' lbm/hr , Main Steam Line Radiation (average) 170 mR/hr Condenser Hotwell Level 60 % Condenser Vacuum 1.7 in. Hg(Abs) Condensate Storage Tank Level 49 % Recire Drive Flow 29.7 Rgpm/ loop Feedwater Flow 6,4 x 10' lbm/hr i Reactor Building D/P -1.62 in H O2 Drywell Pressure 17 psia Drywell Temperature

120 *F Torus Water Level 11.05 ft Torus Temperature 78 *F Drywell/ Torus 0 2Concentration 1,14 % High Range Containment Monitors 1.5 R/hr Containment Cas/ Particulate 540/25000 cpm-Reactor Building Vent Monitors Cas/Part 185/1481 cpm Reactor Building Vent Exhaust N/S 2.0/2.0 mR/hr Steam Jet Air Ejector (ARM) 60.mR/hr SJAE Discharge Rate 22,200 pCi/see Stack Gas I/II 20/20 cpm ! High Range Noble Gas Monitor .1 mR/hr- , 6

                <   .,     e e   w     -   -, . ,~

Rsv. O Pag) 5.1-3 VERMONT YANKEE DAILY PLANT STATUS REPORT THIS IS A DRILL DATE: APR __1993 PLANT OPERATING STATUS VALUE DATE TIME

1. Core Thermal Power ( MWt)l(%) 1592 1 99.9 0700

2. Gross MWe (MWe) 535 0700

3. Het MWe (MWe) 515 0700

4. Gross MWn for previous day (MWh) 12906

5. Core Flow (Mit>hr) l (%) 46 I 95 8 0700 REACTOR COOLANT SYSTEM 6 ConductMty (umho/cm) 0 08 N 193 0900

7. Unident; fed Leakage @ midnight previous day (gam) 1.34

8. Total Leakage @ midneght previous day (gpm) 2.84

9. Gross Actrvity (cpm /ml) 165940 N B3 0900

10. todine-131 Dose Eauivalent (uCuml) 4.50E-03 N /93 0900 STACK RELEASES

11. Particulate (cVperiod) 2.10E-03 4/ /93 1430

12. Average (uCVsec) <100 4/ /93 0115

13. Peak (uCVsec) NONE 4/ /93 0115

14. Discharge Average Gamma Energy (Mev) 1.12 N /93 0115

15. Dose Rate to Crttical Organs (mrem / year) 4.37E-01 & G3 1430 l16. lodine-131 (uCi/sec) 2 34E-04 4/ /93 1430 OFF-GAS ANALYSIS

17. SJAE Dis. Release Rate Measured / Estimated (circle one) (uCVsec) 22200 4/ /93 0115 18 SJAE Discharge Sbpe of Madure -0.0747 4/ /93 0115

19. Condenser Air Leakage (cfm) 12 4 4/ /93 0115 LIQUID RELEASES & RIVER TEMPERATURE

20. Licuid Release (Gal) NA

21. Uguid Release (Gross : Beta. Gamma) (uCVml) NA

22. Ucuid Release (Trttlum) (uCVml) NA

23. UQuid Release (Dissolved Noble Gas) (uCVml) NA 24 Rrver Mon. #3 Highest Temp for previous day (oF) 58 1830 BURNUP 25 Core Avg Burnup for previous day (MWD /ST) 17011.16

26. Core Cycle Bumup for previous day (MWD /ST) 5600.84 REVIEWER:

THIS IS A DRILL

    ~ ,-.                             -     -   -              -.       ...

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993. i r i 5.2 NARRATIVE

SUMMARY

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Rev. O Page 5.2-1 , VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 ; 5.2 NARRATIVE

SUMMARY

The exercise begins at 0245 with the simulator reactor running at approximately 100% power. The reactor has been in a steady state for the last seventeen months with no recent shutdowns. The core is nearing the end of the current operating. cycle. A refueling outage is scheduled to begin in three weeks. Night orders . indicate that all power generating and safety systems are operable. The Circulating Water System is operating in Open Cycle. At 0300, a failure in the Start-Up Transformer lockout relay occurs. This results in a loss of both Start-Up Transformers. Upon recognition of loss of ) both S/U Transformers, the Shift Supervisor should declare an UNUSUAL EVENT (approximately 0315) based on AP 3125, " Loss of Power" (Unplanned Loss of Both' - Start-Up Transformers). The Shift Supervisor should initiate the appropriate notifications concerning the i declaration of the UNUSUAL EVENT and changing plant conditions. Plant personnel should be dispatched to investigate the problem with the lockout switch-and to restore power to the Start-Up Transformers. ] At 0345, an earthquake is sensed on site. This is evident by the Seismic l Annunciator Alarm on the Simulator Control Board. Operations personnel perform inspections of plant equipment in accordance with OP 3127 " Natural Phenomena". j Minor damage around the plant is reported, apparently limited to non-safety related structures and equipment. In the Reactor Building, this includes a steam j leak'from space heater unit SUH-18 on the 345' elevation, also on the 345' I elevation, REAC-lC cooling unit has shif ted position, and the concrete wall, next to the RBCCW pumps on the 303' elevation, is cracked and some of the blocks have fallen to the floor. There is also some water spraying from air cooler RRU 10 on the 280' elevation. In addition, the feeder breaker to DC-3A trips resulting in the loss of Control Room annunciator panels 9-3, 9-4, 9-5, 9-6 and 9-8.

l 1 l Rev. O Page 5.2-2 The Shift Supervisor should direct available personnel to conduct damage I assessment investigations throughout the plant. Upon confirmation of the equipment damage from the earthquake or the loss of CRP annunciators, the Shift Supervisor should declare an ALERT. The ALERT (approximately 0400) is based on-AP 3125, " Loss of Systems or Equipment QE Natural Phenomenon," (Loss of CR Alarm panels or Earthquake exceeds OBE or minor damage to SDI equipment). In either case, notifications should be made to appropriate plant personnel and offsite agencies. Coincident with the notifications, the operations crew will be-verifying plant conditions using available information. Power changes will be minimized until positive indication of reactor status is available. The Simulator Control Room (SCR) staff will continue activities to stabilize . the plant. The Shift Supervisor will request I&C to check the seismic monitor station to determine if an Operating Basis Earthquake (OBE) was exceeded. Following the ALERT declaration, the Technical Support Center (TSC), Operations Support Center (OSC), and Emergency Operations Facility / Recovery Center (EOF /RC) will be activated and staffed. As Emergency Response Support personnel arrive in the OSC, On-Site Assistance teams should be assembled and dispatched to continue investigations in the plant . for earthquake damage, repairs to the S/U transformer lockout relay and restoration of power to the CRP annunciators. At approximately 0415, power is restored to the CRP annunciators by either feeding from DC-1 or reclosing of DC-3A feeder breaker. Power changes can be initiated as soon as reactor status indications have been verified to be in- l service (following repowering of DC-3A). 'I At approximately 0630, excessive turbine vibration occurs and a turbine trip results. Since the S/U Transformers are still unavailable, a Loss of Normal Power occurs, and a Group I isolation is initiated. Additionally, the reactor fails to complete the required scram, resulting in an ATWS condition with reactor power remaining above 2%. The operations crew will attempt to shutdown the reactor by individually driving control rods and by initiating Standby Liquid

Rev. O Page 5.2-3 , Control (SLC). Upon SLC initiation, both Squib explosive valves will fail to actuate, necessitating local actuation of the firing mechanism. Operations personnel should be dispatched by the SS/ PED to manually actuate the Squib valves per OP 3101, Appendix G, to initiate SLC injection. In addition, the CRD Flow control valve fails shut preventing the operators from manually driving control rods. This will have to be evaluated and an A0 dispatched to shif t Flow Control , Valves in accordance with OP 2111. As a result of the ATWS and resultant power / pressure spike, degradation of the fuel cladding occurs causing a maximum of 1% core inventory of Iodine and Noble Gas to be released into the Reactor Coolant System (RCS). Radiation levels inside containment and Torus begin to increase as a result of the increase in reactor coolant activity. A SITE AREA EMERGENCY should be declared (approximately 0645) based on AP 3125,

           " Loss of Systems or Equipment" (failure of RPS to initiate and accomplish a required SCRAM and power generation continues).

At 0700 the Service Water Flow Control Valve (FCV-288) for "B" diesel generator fails shut, resulting in a high temperature trip of the "B" diesel generator. This results in a loss of equipment supplied from Buses 3 and 8. .An On Site Assistance Team should be assigned from the OSC to investigate the failure. 5 i The ATWS condition has resulted in significant heat to be added to the Torus. ? The heat addition causes Torus pressure to increase. Subsequently, by 0715, the Torus to Drywell vacuum breakers open to relieve the buildup of pressure in the Torus. One of the vacuum breakers fails to shut after pressure has equalized l between the Torus and Drywell, resulting in a direct flow path between the two structures. l Repair personnel report that the Start-Up Transformer Lockout relay has been-repaired. Buses 1 and 2 can be re-energized, allowing subsequent powering of associated buses, MCCs and station equipment However, MCC 7 is unable to be re-energized due to a failure in its associated feeder breaker (breaker 27) and 6T7. Repair team personnel should be dispatched from the OSC to investigate this

problem.

1 Rev. O Page 5.2-4 ; Efforts continue to insert control rods and to restore equipment lost as a result of the LNP and loss of the "B" diesel generator. At approximately 0730 and 0815 respectively, Turbine Building ventilation has been restored and all control rods have been inserted. At 0830, a small steam leak occurs into the Primary Containment. Dryvell' pressure begins to increase. At approximately 0845, the hardened vent rupture disk begins to leak when drywell pressure approaches 5 psig. (The hardened vent rupture disk has been weakened due to the induced stress from the earthquake.) Due to the previous failure of ; the Torus to Drywell vacuum breaker and the hardened vent rupture disk leakage, a direct path from the Torus to the Plant Vent Stack exists. Attempts to isolate the hardened vent line using the associated downstream Motor Operated Valve are not successful due to loss of power to the MOV (powered from MCC 7). Local operation of the valve will not be possible due to mechanical failure and inhibited by high radiation levels in the area. ; By 0900, the Plant Vent Stack (PVS) is indicating a release of radioactivity to I the environment. .i A GENERAL EMERGENCY should be declared (approximately 0915) based on AP 3125, Fuel Damage" (Loss of 2 of three fission product barriers with potential loss of , the third). > By 1045, repairs to MCC 7 feeder breaker or 6T7 are completed, power is restored , to MCC 7 to allow closure of the hardened vent isolation valve. Upon valve closure, the source term of the release to the environment is isolated. The PVS ] monitor readings will start to decrease. Offsite activities will continue to-track the release. By 1130, the PVS monitor readings will indicate background levels. l At 1230, the exercise may be terminated. ' l l

4 .g - y A s- ,-- h - ~ 1 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 i 5.3 SCENARIO TIME LINE

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                                                                                                                         - Page 5.3 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 5.3 SCENARIO TIME LINE CLOCK                 SCENARIO TIME                  TIME                                           DESCRIPTION 0245                    0:00 - <..- Initial conditions established in the Simulator. control Room.

0300 0:15 - <--- Loss of both Start Up Transformers due to failure in' the Start-Up Transformer lockout relay. 0315 0:30 - <--- LINUS 11AL*EVENTl(ATPs3125;$T; LOSS 2pgPRJERJ . Unplanned Loss of Both - Start-Up Transformers. 0330 0:45 - 4 0345 1:00 . <-. - Earthquake sensed on-site, resulting in damage to non. safety related equipment. DC-3A feeder breaker trips, causing a loss of Control Room Panel (CRP) annunciators on panels 9-3, -4,. 5, .6 and -8. 0400 1:15 - <--- ALERTX(h!Py]l25))IqSSjoO]S EMSigRiEQUIPMENTipfNATURAI PHENOMENON} - Loss of CR Alarm panels (all control room alarms on CRP 9-3, 4 and 5) .qr Earthquake (exceeds OBE or minor damage to SDI - equipment). , 1415 1:30 - <--- Power to DC-3A is restored, CRP 9-3, .4, 5, -6 and 8 are restored. 0430 1:45 - 0445 2:00 - ' 0500 2:15 - 0515 2:30 . 0530 2:45 . 0545 3:00 . 0600 3:15 - , 0615 3:30 . g ,4ey. , -y-, _ g,--.- _ . _+

Rev. 0 , Page 5.3-2 5.3 SCENARIO TIME LINE (continued) CLOCK SCENARIO TIME TIME DESCRIPTION 0630 3:45 - <.-. Excessive turbine bearing vibration causing a turbine trip. Reactor fails to scram. ATUS conditions exists. Loss of Normal Power (LNP) also occurs. . 0645 4:00 . <.-- $1TE!AREKiEMERGENCYl(APf3125230S$!CESYSTEMSIO[gt!IPMENT); -

                     -        (Failure of RPS to initiate and accomplish a required SCRAM and Power Generation Continues).

0700 4:15 - <-.. Service Water flow control valve to the "B" diesel generator fails

                     -        closed and results in a high temperature trip of the "B" diesel generator.

0715 4:30 - <--- Drywell vacuum breakers open (one fails open) causing a direct

                     .        flow path from the Drywell to the Torus atmosphere.

Repairs to the Start-Up Transformer lockout relay -ve completed. 0730 4:45 . <--- Turbine Building ventilation is restored. 1 l 0745 5:00 <--- Efforts to shutdown the reactor are ongoing, j 0800 5:15 -

'815         5:30       <--- All control rods have been inserted.                                         ;
                                                                                                        -l 0830          5:45 - <--- A small steam leak occurs into the Primary Containment.
                     .        Containment pressure starts to increase.

0845 6:00 - <--- Primary Containment pressure approaches 5 psig due to the steam leak. The hardened vent rupture disk begins to leak. A direct path from the Torus to the Plant Vent Stack (PVS) exists. , 0900 6:15 - <--- PVS indicating a release of radioactivity to the environment. ! 0915 6:30 <--- CENERA18D1ERCENCYjMPf3125p?FUECDAMAGEl . Loss of 2 of 3 fission

                     -        product barriers with potential loss of the third.

0930 6:45 . 0945 7:00 - 1000 7:15 - <--- Activities to repower MCC 7, repair FCV.28B and isolate

                      .       the hardened vent continue.

1015 7:30 . 1030 7:45 -

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Rev. O Page 5.3 3 s.3 SCENARIO TIME LINE (continued) CLOCK SCENARIO TIME TIME DESCRIPTION 1045 8:00 . <-.. Repairs to MCC 7 feeder breaker are complete. Power is restored to the. hardened vent isolation valve and the valve is closed.

                   .        The release to the environment is terminated.

1100 8:15 - <-.. Off-Site monitoring and' dose assessment activities continue. 1115 8:30 . 1130 8:45 - <-.. PVS monitor readings indicate background levels. 4 1145 9:00 - , 1200 9:15 - 1215 9:30 - ,

                   .                                                                              i 1230        9:45 - <--- EXERCISE MAY BE TERMINATED                                                 ;

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4 ,1,4 se4 mD B J - a a m a k I l VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993 4 5.4 DETAILED SEOUENCE OF EVENTS b I W

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Rev. O Page 5'.4 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 5.4 DETAILED SEOUENCE OF EVENTS Clock Scenario Message Time Time Event / Action Information Prior to EXPECTED CONTROL ROOM (CR) ACTIONS WILL BE 0245 00:00 IMPLEMENTED BY AN EXERCISE OPERATIONS CREW (INCLUDING SUFFICIENT NUMBER OF PRESTAGED INDIVIDUALS FROM THE VERMONT YANKEE EMERGENCY ORGANIZATION) LOCATED IN THE SIMULATOR COMPLEX IN THE CORPORATE TRAINING CENTER.

                      ' OPERATIONAL CONTROL ROOM DATA WILL BE                                                                 j PROVIDED BY THE SIMULATOR INSTRUMENTATION                                                              )

RESPONSES. IN CASES WHERE SPECIFIC-

INFORMATION NOT MONITORED BY THE SIMULATOR IS REQUIRED, IT WILL BE ISSUED BY CONTROLLERS /0BSERVERS ON MESSAGE CARDS. IN THE EVENT THAT A SIMUIATOR MALFUNCTION OCCURS, THE EXERCISE WILL'BE CONDUCTED USING INFORMATION DEVELOPED FROM SECTION 8.0 AND SECTION 9.0. The Simulator CR Controller issues initial SCR/CR-M-1 conditions to the simulator CR players. SCR-C-1 Guidelines for use of Gaitronics and the plant evacuation alarm are provided to players

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l Rev. O Page 5.4 2 i Clock Scenario Message l Time Time Event / Action Information 1

Prior to Initiating messages are also provided to all ERF-M-1 0245 00:00 emergency centers and facility staffs upon TSC-M 1 (Cont'd) subsequent activations. TSC communicators TSC-M-2 prestaged in the SCR, who normally respond to the CR, will be available for communication and data transmission. ERFIS terminals in the TSC and EOF will be linked to the SCR to transmit operational and radiological scenario data. Security will . be provided a list of Evaluators and nonparticipants who will not have to be accounted for during the exercise. 0245 00:00 Simulator is put into operation. Reactor is at 100% power. The reactor has j been operating steady state for the past seventeen months with no recent shutdowns. The core is nearing the end of the current operating cycle. A refueling outage is scheduled to begin in three weeks. i 0300 00:15 Failure in the Start-Up Transformer lockout I relay. Loss of both S/U Transformers. (Refer to Miniscenario 7.2.1) l Approx. 00:30 The Shift Supervisor should declare eut 0315 UNUSUAL EVENT based upon the following EAL: AP 3125, " LOSS OF POWER - Unplanned Loss of . both Start-Up Transformers". The SS/ PED should initiate Procedure OP 3500, UNUSUAL EVENT and refer to Appendix I, the SS/ PED checklist. l An A0 should be dispatched to investigate 1 the loss of the S/U Transformers, j 1

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Rev. O Page 5,4 3 Clock Scenario Message Time Time Event / Action Information l l Approx, 00:30 FOR EXERCISE PURPOSES, EARLY IN-STATION SCR-C-2 ) 0315 ACTIONS NORMALLY PERFORKED BY CONTROL ROOM (Cont'd) SUPPORT PERSONNEL MAY BE CONTROLLED AND PERFORMED BY THE SIMULATOR CONTROLLERS UNTIL AFTER THE ON SHIFT OPERATING SHIFT PERS0hTEL ARE AUGMENTED BY THE EMERGENCY RESPONSE ORGANIZATION. The SS/ PED should announce the UNUSUAL EVENT over the Plant Paging System. This activity will be performed by players in _the Simulator Control Room (SCR), and simultaneously performed by a Controller directed member of the shift crew in the actual Control Room (CR). The SS/ PED should notify Vermont,.New Hampshire, and Massachusetts State Police Agencies using the Nuclear Alert System (NAS, orange telephone) and provide the appropriate message to each agency. The SS/ PED should notify the NRC (FTS-2000 ENS Phone) and maintain communications until relieved by the TSC. The Security Shift Supervisor should SEC-M-1 implement Procedure OP-3531', " Emergency Call-In Method," to notify the appropriate emergency response personnel. The Security Shift Supervisor should notify Yankee Nuclear Services Division (YNSD) Security and activate the YNSD Personnel Group Paging System.

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                                                                                                      'l Rev.'0.                 'I Page 5.4 4'             U Clock     Scenario                                                                Message                :

Time Time Event / Action Information i Approx. 00:30 The Security Shift Supervisor also should SEC C-1 j 0315 notify New England Hydro Power Station of (Cont'd) the UNUSUAL EVENT. THIS CALL VILL BE SIMULATED. l The Primary and Secondary Duty and Call officers (DCOs) should contact the SS/ PED to be advised of the situation. The DCOs should report to the plant after notification of the UNUSUAL EVENT Status. Responsibility for Technical Support Center (TSC) and Emer6ency Operations Facility (EOF) Coordinator assignments would be discussed, as appropriate. The TSC Coordinator, when present, should assume the overall supervision and coordination of the On-Site emergency response activities. This will include escalating the emergency classification as - conditions warrant. Activation of the TSC is optional at the , UNUSUAL EVENT. 0330 00:45 IF AN UNUSUAL EVENT HAS NOT BEEN DECLARED BY SCR C-3'

THE SS/ PED, HE WILL BE DIRECTED TO DO SO AT ,

THIS TIME. 0345 01:00 An earthquake is sensed on-site and at SCR-M-2 various locations around the plant. Seismic Annunciator comes in on the simulator control board. Minor damage to non safety related equipment occurs around the plant. (refer to Miniscenario 7.2.2)

. = . . . . . - . . . - _ Rev. 0' , Page 5.4-5' Clock Scenario Message Time _ Time Event / Action Information' 0345 -01:00 DC-3A feeder breaker also trips causing a (Cont'd) loss of Control Room Panel (CRP) annunciators 9-3, 9-4, 9-5, 9 6, and 9-8. (Refer to Miniscenario 7.2.3) The SS/ PED should implement OP 3127,

                             " Natural Phenomena" in response to the earthquake. This will instruct them to check plant instrumentation and'to conduct' visual inspections for an assessment of damage caused by the earthquake.

0355 01:10 This will also include checking the seismic SCR-C-4 monitor work station and contacting Vernon SCR-M-3 and Bellows Falls dams for an assessment of dam status. 1 0400 01:15 The SS/ PED and TSC Coordinator (if present) i should review the plant conditions against Procedure AP 3125, " Emergency Plan Classification and Action Level Scheme." The SS/ PED or TSC Coordinator should declare

                  ,           an ALERT based upon the following EAL:

AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT QR NATURAL PHENOMENON" - Loss of CR alarm panels (all control room alarms on CRP 9-3, 9 4 and 9-5) 2r Earthquake (exceeds OBE or minor damage to SDI equipment). The SS/ PED directs the operations staff to

initiate. Procedure OP 3501, " ALERT."

Rev. O Page 5.4 Clock Scenario Message Ilme Time Event / Action- Information 0400 01:15 An ALERT announcement should be made over (cont'd) the plant page instructing emergency personnel to report to their-assigned- , emergency response facilities, and other personnel, contractors, and visitors report to the Covernor Hunt House Information Center and wait for further instructions. At this time, the TSC, Operations Support Center (OSC), and the Emergency Operations Facility / Recovery Center (EOF /RC)- should be in the process of being activated and staffed. The SS/ PED should notify the Vermont, New Hampshire, and Massachusetts State Police Agencies using the NAS of the escalation to the ALERT emergency classification. The NRC should be' notified of the escalation to the ALERT. j

                                                                                    .q The Security Shift Supervisor should                              I 1

initiate the emergency call-in method for j the ALERT classification. The Security Shift Supervisor should notify Yankee Nuclear Services Division (YNSD) Security of the escalation to the ALERT status. Upon ALERT notification, the YNSD Engineering Support Center (ESC) is activated. I J

_ ~ , Rev. O Page 5.4-7 Clock Scenario Message , Time Time Event /Acti2D Information 0400 01:15 The Security Shift ' Supervisor should notify (cont'd) the New England Hydro Power Station in . Vernon of the escalation to the ALERT status. THIS CALL WILL BE SIMULATED. The TSC Coordinator should notify REMVEC of - the ALERT status and plant conditions. , 0405 01:20 The Security Shift Supervisor should ensure that an accountability of personnel has been initiated in accordance with procedure ; OP 3524, " Emergency Actions to' Ensure Accountability and Security Response." The TSC Coordinator should respond, activate, and staff the TSC in accordance with Appendix III of OP 3501, " ALERT." TSC staff representing the following departments should assemble at the TSC following the declaration of an ALERT:

1. Security Manager

2. Instrument and Control Manager

3. Radiation Protection Manager ,

4. Reactor and Computer Engineering Manager -

5. Operations Manager

6. Maintenance Manager ,

7. Engineering Director

8. Mechanical Engineering & Construction I Supervisor

9. Electrical Engineering & Construction Supervisor

10. Technical Programs Supervisor

11. Communicators

12. Plant Switchboard Operator

n Rev. 0 , Page 5.4-7 l Clock Scenario _ Message i Time Time Event / Action Information { 0400 01:15 The Security Shift Supervisor should notify l (cent'd) the New England Hydro Power Station in , Vernon of the escalation to the ALERT. : status. THIS CALL WILL BE SIMULATED. ; 1 The TSC Coordinator should notify REMVEC of the ALERT status and plant conditions. 0405 01:20 The Security Shift Supervisor should ensure that an accountability of personnel has been i initiated in accordance with procedure OP 3524, " Emergency Actions to Ensure-Accountability and Security Response." The TSC Coordinator should respond, activate, and staff the TSC in accordance with Appendix III of OP 3501, " ALERT." TSC staff representing the following departments should assemble at_the TSC following the declaration of an ALERT: { i

1. Security Manager

2. Instrument and Control Manager

3. Radiation Protection Manager

4. Reactor and Computer Engineering Manager

5. Operations Manager

6. Maintenance Manager ,

7. Engineering Director

8. Mechanical Engineering & Construction Supervisor

9. Electrical Engineering & Construction Supervisor

10. Technical Programs Supervisor

11. Communicators

12. Plant Switchboard Operator l

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Clock Scenario Message Time Time Event / Action Information 0405 01:20 13. Status Board Caretakers , (Cont'd)

14. Other Staff as required to fulfill functions of the TSC The EOF Coordinator should activate and ,

staff the EOF /RC in accordance with Appendix IV of OP-3501, " ALERT." t The emergency response staff that reports to the EOF /RC includes the following:

1. Site Recovery Manager (SRM) and designated corporate staff

                     ".. EOF Coordinator

3. Public Information Liaison

4. Additional trained plant staff members to assume the following tag board assignments:

EOF Coordinator's Assistant s Radiological Assistant ,

                         - Manpower and Planning Assistant
                         - Communications Assistant                                  I Radiological Coordinator.                                ;
                         -  Personnel and Equipment Monitoring Team

5. Corporate Security Force l The OSC Coordinator (assigned by the TSC Coordinator) should activate and staff the .

OSC in accordance with Appendix VII of OP 3501, " ALERT." The Plant staff that reports to the OSC includes the following:

1. Radiation Protection and Chemistry Assistants and Technicians 1

2. Control Instrument Specialists l

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Rev. O Page 5.4-9 Clock -Scenario Message Time Time Event /Actio.D Information 0405' 01:20 3. Maintenance Staff (cont'd)

4. Status Boar / Caretaker

5. Other persoinel as required.

The Site Recovery Manager (SRM) and staff-should report to the EOF /RC and implement the procedural steps listed in Appendix VIII of OP 3501, " ALERT." The SS/ PED may instruct the operators to minimize activities that could influence reactor operations until such time that positive indication of reactor status is available. 0415 01:30 IF AN ALERT HAS NOT BEEN DECLARED BY THE SCR-C-5 SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS . TIME. Repair to the DC-3A Feeder Breaker has been completed or power has_been fed through DC-1. In either case, power is restored to i Control Room Annunciators. SCR operators will continue to stabilize the plant. . Approx 02:00 The ESC should be providing technical and ESC-M-1 04:45 engineering support to Vermont Yankee staff. EOF-M-1 The ESC meteorologist should be providing a , weather forecast for the VY site. Weather forecast information from the NWS is available. 0 5

Rev. O Page 5.4-10 Clock Scenario Message Time Time Event / Action Information , i Approx. 02:00 Activities continue to return the Start-Up 0445 Transformers to service, and to investigate (cont'd) throughout the plant for damage sustained from the earthquake, t 0600 03:15 Local news release information, with details NMC-M-1 of the earthquake, is simulated to have been broadcast over the local radio and television network. 0630 03:45 Excessive turbine vibration occurs such that l a turbine trip occurs. Since the Start-Up Transformers are still unavailable, a Loss of Normal Power (LNP) condition exists and a ,

                                                                                                                       'I Group I isolation occurs. The turbine trip also generates a reactor scram signal. The reactor fails to complete the required scram, resulting in an ATUS condition with a

reactor power remaining above 2%. The CRD Flow Control Valve fails closed preventing the operators from manually driving control rods. An A0 should be dispatched to investigate the failure and to , shift FCVs. (Refer to Miniscenario 7.2.4). When Standby Liquid Control (SLC) is initiated, both Squib explosive valves will . fail to open, requiring local actuation of the valves. (Refer to Miniscenario 7.2.5). F i y _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _

Rev. O. Page 5.4-11 Clock Scenario Message Time Time Event /ActioD Information 0630 03:45 As a result of the ATWS and resultant (cont'd) power / pressure spike, degradation of the fuel cladding occurs causing a maximum of 1% core inventory of Iodine and Noble Gas to be released into the Reactor Coolant System (RCS). Radiation levels inside containment t and the Torus begin to increase as a result of the increased activity in the RCS. 0635 03:50 The SRM, TSC Coordinator and SS/ PED should evaluate plant conditions against Procedure AP 3125, " Emergency Plan Classification and Action Level Scheme." Approx. 04:00 The SRM should declare a SITE AREA EMERGENCY 0645 based on the following EAL: AP 3125 " LOSS - 0F SYSTEMS OR EQUIPMENT" - (Failure of RPS to initiate and accomplish a required scram and power generation continues). If present in the EOF, the SRM should inform the State representatives of Vermont, New Hampshire and Massachusetts assigned to the EOF /RC and contact the State's EOCs via the NAS to inform them of the escalation to the SITE AREA EMERGENCY. The SS/ PED will also be directed to make the appropriate plant announcement concerning the escalation to the SITE AREA EMERGENCY. Upgraded notifications should also be made to YNSD and the NRC i I.

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Rev O Page 5.4-12 , Clock Scenario Message lige_ Time Event / Action Information l 0700 04:15 The Service Water Flow Control Valve to the "B" diesel generator (FCV-28B) fails closed resulting in a high temperature. trip of the "B" diesel generator. (Refer to Miniscenario e 7.2.6) An On-Site Assistance Team should be assembled and dispatched to investigate'the trip of the "B" diesel generator. 0715 04:30 IF A SITE AREA EMERGENCY HAS NOT BEEN EOF-C-1 DECLARED BY THE SRM, HE WILL BE DIRECTED TO DO SO AT THIS TIME , 0715 04: 30 As a result of the ATWS, sufficient heat has i t been introduced into the Torus to cause l Torus pressure to exceed the setpoint for , the Torus to Drywell vacuum breakers. Consequently, the vacuum breakers open relieving the over-pressure into the l Drywell, As pressure equalizes between the , two structures, one of the vacuum breakers fails to reset. Repairs to the Start-Up Transformer lockout relay are completed. Buses 1 and 2 are re-energized. Equipment powered from these sources are returned to service. , MCC 7 cannot be powered due to a failure in , its associated feeder breaker. An On-Site Assistance Team should be dispatched to investigate. (Refer to Miniscenario 7.2.7) Approx. 04:45 Turbine Building Ventilation is restored. 0730

Rev. O' I Page 5.4-13 Clock Scenario Message Time Time Event / Action Information Approx. 04:45 Operators should be continuing attempts to 0730 insert Control Rods and bring the reactor to (cont'd) a shutdown condition.

0815 05:30 All Control Rods have been successfully inserted into the core. 0830 05:45 A small steam leak into the Primary Containment occurs. Primary Containment pressure begins to increase. 0845 06:00 Primary Containment pressure approaches 5 psig. The hardened vent rupture disk begins to leak as a result of the increase in containment pressure and structural deterioration due to the earthquake. -A direct path from the Torus to the Plant Vent Stack (PVS) exists. Attempts to isolate the downstream Motor Operated Valve for the hardened vent are unsuccessful due loss of power to MCC 7. Attempts to manually close the isolation valve are not successful due to mechanical failure and inhibited by elevated aren '; radiation levels. (Refer to Miniscenario 7.2.8) . j 0900 06:15 PVS high range monitor is indicating a release of radioactivity to the environment. The appropriate EOF staff should initiate OP 3513, Evaluation of Off-Site Radiological Conditions to determine potential off-site dose projections.

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Rev. O Page 5.4 14 Clock Scenario Message , Time Time Event / Action Information 0900 06:15 Off-Site Monitoring Teams and a' Site (cont'd) Boundary Team will be dispatched to monitor the plume in the downwind direction in accordance with OP 3510. The SRM, with consultation from the TSC Coordinator and SS/ PED, should recognize the-need to escalate to GENERAL EMERGENCY. Approx. 06:30 The SRM should declare a CENERAL EMERGENCY 0915 based on the following EAL: AP 3125 " FUEL DAMAGE - Loss of 2 of 3 fission product barriers with the potential loss of the third." The SRM should inform the State representatives of Vermont, New Hampshire and Massachusetts assigned to the EOF /RC and contact the State's EOCs via the NAS to inform them of the escalation to the GENERAL EMERGENCY, The SS/ PED will also be directed to make the appropriate plant announcement concerning the escalation to the GENERAL EMERCENCY. i Upgraded notifications should also be made to YNSD and the NRC. I The SRM should also implement Procedure , OP 3511, "Off-Site Protective Action . Recommendations", to formulate and recommend protective actions to State authorities based on plant and off-site radiological conditions.

Rev. O ! Page 5.4-15 ') i Clock Scenario Message q Tine. Time Event / Action Information i 0930 06:45 IF A GENERAL EMERCENCY HAS NOT BEEN DECLARED ~ SRM-C-1 BY THE SRM, HE WILL BE DIRECTED TO DO SO AT l THIS TIME. 10:00 07:15 Activities to repower MCC 7, FCV-28B and closure of the hardened vent isolation' valve 4 continue. 10:45 08:00 Repairs are complete to MCC 7 feeder breaker (breaker 27) or 6T7, power is available to MCC 7. The operators are able to close the hardened vent isolation valve. The source of the release to the environment has been isolated. PVS monitor readings will start to decrease. ' 11:00 08:15 off-Site monitoring and dose' assessment activities continue. Results are used to continually assess Protective Action Recommendations under consideration. In addition, the information is provided to the individual states' representatives for' comparison with their' independent assessments. 11:30 08:45 PVS monitor readings indicate background > levels. 12:30 09:45 Exercise is terminated.

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 6.0 EXERCISE MESSAGES 4 t

l

,v-

E VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 ^.

                                                                         .t 6,1 COMMAND CARDS s

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Rev. O Page 6.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO.: SCR-C-1 TO: Shift Supervisor CIDCK TIME: Prior to 0245 LOCATION: Simulator Control Room SCENARIO TIME: Prior to 00:00 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. Communications systems that are available in the Control Room have been duplicated in the Simulator Control Room (SCR) EXCEPT for GAITRONICS and the PLANT EVACUATION ALAPR. Please use the GAITRONICS/PIANT EVACUATION ALARM in the SCR to complete the required PA announcements. An Exercise controller will then direct a member of the shif t operations crew at the plant to repeat the announcements from the Main Control Room. THIS IS A DRILL

Rev. O Page 6.1-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO COMMAND CARD ) FROM: 3)mulator CR Controller COMMAND NO.: SCR-C-2 TO: lhift Supervisor CLOCK TIME: 0315 LOCAI '.01P Simulator Control Room SCENARIO TIME: 00:30

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THIS IS A DRILL DO NOT initiate any actions affecting normal plant operat. ions. 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. THIS IS A DRILL

Rev. O Page 6.1-3 i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO COMMAND CARD FROM: Security Controller COMMAND NO.: SJC-C-1 TO: Security Shift Supervisor CLOCK TIME: 0315 or when needed LOCATION: Security Gatehouse SCENARIO TIME: 00:30 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. FOR EXERCISE PURPOSES, communications with New England Hydro Power Station in Vernon will be simulated. t THIS IS A DRILL 1

Rev. O Page 6.1-4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO COMMAND CARD t FROM: Simulator CR Controller COMMAND NO.: SCR-C-3 TO: Shift Supervisor CLOCK TIME: 0330 LOCATION: Simulator Control Room SCENARIO TIME: 00:45 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. DECLARE AN UNUSUAL EVENT BASED UPON AP 3125, " LOSS OF POWER - Unplanned Loss of Both Start-Up Transformers".

- - - - i THIS IS A DRILL

Rev, O Page 6.1-5 VERMONT YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO COMMAND CARD 9 FROM: Simulator CR Controller COMMAND NO.: SCR-C-4 TO: Shift Suoervisor CLOCK TIME: 0355 LOCATION: Simulator Control Room SCENARIO TIME: 01:10 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. For exercise purposes, Control Room communications with the Vernon and Bellows Falls Dams will be simulated. THIS IS A DRILL t

Rev. O Page 6.1-6 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993

                        . SCENARIO COMMAND CARD FROM: Simulator CR Controller               COMMAND NO.:    SCR-C-5 TO:    Shift Sunervisor/ PED                CLOCK TIME:     0415 LOCATION:    Simulator Control Room         SCENARIO TIME: 01 30 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.

DECLARE AN ALERT BASED UPON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT E NATURAL PHENOMENON - Loss of CR alarm panels (all control room alarms on CRP 9-3, 9-4 and 9-5) E Earthquake (exceeds OBE or minor damage to SDI Equipment)".

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THIS IS A DRILL ' I l l l l l

Rev. O Page 6.1-7 , VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 , SCENARIO COMMAND CARD FR.0M : EOF Controller COMMAND NO.. EOF-C-1 , TO: Site Recovery Manar.er CLOCK TIME: P715 LOCATION: EOF SCENARIO TIME: 04: 30 > THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. DECLARE A Sl.TE AREA EMERGENCY BASED UPON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT - Failure to SCRAM (Failure of RPS to initiate and accomplish a required SCRAM and power generation continues)". i i t I l 1 I I THIS IS A DRILL

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        ..                m Rev. O Page 6.1-8 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO COMMAND CARD FROM: SRM Controller                         COMMAND NO.:    SRM-C-1 TO:    Site Recovery Manager                 CIDCK TIME:     0930 LOCATION:    EOF                             SCENARIO TIME: 06 45 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.

DECIARE A GENERAL EMERGENCY BASED UPON AP 3125, "WEL DAMAGE - Loss of 2 of 3 ' fission product barriers with the potential loss of the third". 1 THIS IS A DRILL l l i 1

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. . , _ . . - _ _ = . . - m .. _ _ .. _ _ . _ _ . . - VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 6.2 MESSAGE CARDS

Rev. O Page 6.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE r 1993 SCENARIO MESSAGE CARD i FROM: Controller MESSAGE NO.: SCR/CR-M-1 TO: Shift Supervisor /DC0 CLOCK TIME: Start of Exercise LOCATION: CR/ Simulator CR SCENARIO TIME: Prior to 00:00 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. For initial conditions, see attached pages. i THIS IS A DRILL

Rev. O Page 1 of 3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE SCENARTO MESSAGE CARD INITIAL CONDITIONS 3

1. The reactor is now at approximately 100% power. The reactor has been '

operating steady state for the past seventeen months with no recent shutdowns. The core is nearing the end of the current operating cycle. A refueling outage is scheduled to begin in three weeks.

2. Night Orders for the operations crew provides the following information:

I

a. The Circulating Water System is opereting in Open Cycle.

b. All equipment is operable and available. l:

c. No Limiting Conditions of Operation (LCOs) are in effect.

3. The following on-site meteorological conditions exist at 0245:

Wind Speed, mph (lower / upper) 3.0/3.5 Wind Direction, degrees (lower / upper) 163/170 Delta Temperature, 'F (lower / upper) -0.5/1.2 l Ambient Temperature, 'F 32.0 j Precipitation, inches 0.'00

4. Regional Meteorological Forecast Information:

A low pressure system is currently centered over the Pennsylvania area. Mostly cloudy and overcast this morning. Temperatures in the low to mid 30's. Southerly winds from 3 to 6 mph. THIS IS A DRILL

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Rev. 0 j Page 2 of 3 SCENARIO MESSAGE CARD Initial Plant and Reactor System Values i l Reactor Vessel Coolant Level 161 Inches l O Reactor Pressure 1008 psig Reactor Coolant Temperature 527 *F Reactor Power - APRM (average) 99.9 % Core Plate D/P 18 psid Total Core Flow 47 x 10' lbm/hr Main Steam Line Flow - Total 6.4 x 10' lbm/hr Main Steam Line Radiation (average) 170 mR/hr' Condenser Hotwell Level 60 g l Condenser Vacuum 1.7 in. Hg(Abs) l Condensate Storage Tank Level 49 % Recire Drive Flow 29.7 Kgpm/ loop Feedwater Flow 6.4' x 10' lbm/hr Reactor Building D/P -1.62 in H O 2 Drywell Pressure 17 psia i Drywell Temperature 120 "F Torus Water Level 11.05 ft Torus Temperature 78 'F Drywell/ Torus 02 Concentration 1.14 % High Range Containment Monitors 1.5 R/hr Containment Cas/ Particulate 540/25000 -cpm Reactor Building Vent Monitors Cas/Part 185/1481 cpm Reactor Building Vent Exhaust N/S 2.0/2.0 mR/hr Steam Jet Air Ejector (ARM) 60 mR/hr SJAE Discharge Rate 22,200 pCi/see Stack Cas I/II 20/20 epm High Range Noble Cas Monitor 0.1 mR/hr THIS IS A DRILL

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RCV. O Page 3 of 3 VERMONT YANKEE DAILY PLANT STATUS REPORT THIS IS A DRILL DATE: APR _.1993 PLANT OPERATING STATUS VALUE DATE TIME

1. Core Thermal Power ( MWt) l(%) 1592 l 99.9 0700

2. Gross MWe (MWe) 535 0700

3. Net MWe (MWe) 515 0700

4. Gross MWh for previous day (MWh) 12906

5. Core Flow (Mitvhr)l(%) 46 l 95.8 0700 REACTOR COOLANT SYSTEM

6. Conductrvity (umho/cm) 0.08 4/ 19 3 0900

7. Unidentified Leakage @ midnight previous day (gom) 1.34

8. Total Leakage @ midnight previous day (gpm) 2.84 9 Gross Activity (cpm /ml) 165940 4/ /93 0900

10. lodine-131 Dose Equivalent (uCi/m0 4.50E-03 4/ /93 0900 STACK RELEASES

11. Particulate (cupenod)' 2.10E-03 4/ /93 1430

12. Average (uCusec) <100 4/ /93 0115

13. Peak (uCusec) NONE 4/ /93 0115 ,

14. Discharge Average Gamma Energy (Mev) 1.12 4/ /93 0115 l

15. Dose Rate to Critical Organs (mrem / year) 4.37E 01 4/ /93 1430 !

l16. lodine-131 (uCvsec) 2 34E44 4/ /93 1430 l l OFF-GAS ANALYSIS , i

17. SJAE Dis. Release Rate Measured / Estimated (circle one) (uCVsec) 22200 4/ /93 0115 i

18. SJAE Discharge Slope cf Mature 00747 4/ 19 3 0115 I

19. Condenser Air Leakage 12.4 0115 (cfm) 4/ /93 )

LIQUID RELEASES & RIVER TEMPERATURE 20 Liquid Release (Ga!) NA

21. Liquid Release (Gross : Beta. Gamma) (uCumi) NA 22 Liquid Release (Trttium) (uCVml) NA I

23. Liould Release (Dissolved Noble Gas) (uCVml) NA 24 River Mon. #3 Highest Temp. for previous day (oF) 58 1830 BURNUP 25 Core Avg Bumup for previous day (MWD /ST) 17011.16

26. Core Cycle Burnup for previous day (MWD /ST) 5600 84 REVIEWER:

THIS IS A DRILL

Rev. O Page 6.2-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNES3 EXERCISE 1993 b SCENARIO MESSAGE CARD FROM: Facility Controller MESSAGE NO.: ERF-M-1 TO: Facility coordinator CLOCK TIME: Start of Exercise or LOCATION: Various ERFs SCENARIO TIME: Facility Activation

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THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. For initial conditions, see attached pages. 1 i l 1

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i l 1 I Rev. O I Page 1 of 2 , VERMONT YANKEE NUCLEAR POWER STATION ) EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993 i SCENARIO MESSAGE CARD ! VERMONT YANKEE DAILY OPERATIONS REPORT APRIL XX, 1993

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PLANT STATUS: 100% POWER GEN GROSS 535 MWE OFFGAS 22,200 uCI/sec PLANT OPERATION

SUMMARY

& SIGNIFICANT EVENTS:

THE PLANT HAS BEEN OPERATING FOR 17 MONTHS WITH NO RECENT -

SHUTDOWNS. CONTINUED FULL POWER OPS.

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BIGNIFICANT NEW WORs

     #           DESCRIPTION                           DEPT PRIORITY NONE

=====================================================

TECH SPEC /LCO EQUIPMENT OUT OF BERVICE: SYSTEM / COMPONENT TECH SPEC DATE/ TIME ALLOWABLE TIME NONE

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STATUS / COMMENTS ON MAJOR WORK IN PROGRESS: NONE ======== --

                                             - - - - - - - -                            = = = = = = = = = - - -

PRO'8/ NOTIFICATIONS: NONE

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LONG TERM PROBLEMS SOLVED: NONE

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THIS IS A DRILL

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Rov. O Page 2 of 2 VERMONT YANKEE DAILY PLANT STATUS REPORT THIS IS A DRILL DATE: APR _1993 PLANT OPERATING STATUS VALUE DATE TIME

1. Core Thermal Power ( MWt)I(%) 1592 l 99.9 0700

2. Gross MWe (MWe) 535 0700 3 Net MWe (MWe) 515 0700

4. Gross MWh for prevtous day (MWh) 12906

5. Core Flow (Mib/hr) l (%) 46 l 95.8 0700 REACTOR COOLANT SYSTEM

6. Conductivtfy (umho/cm) 0 06 N /93 0900

7. Unidentified Leakage @ midnight previous day (gom) 1.34

8. Total Leakage @ midnight previous day (gpm) 2.84

9. Gross Activity (com/mi) 165940 4/ /93 0900

10. lodine-131 Dose Equivalent (uCvml) 4.50E-03 4/ /93 0900 STACK RELEASES

11. Particulate (evperuxi) 2.10E43 l 4/ 19 3 1430

12. Average (uCusec) <100 1 4/ S3 0115

13. Peak (uCusec) NONE 4/ /93 0115

14. Discharge Average Gamma Energy (Mev) 1.12 4/ /93 0115 5 Dose Rate to Cntical Organs (mrem / year) 4.37E41 4/ /93 1430 116. lodine-131 (uCusec) 2.34E-04 4/ /93 1430 OFF-GAS ANALYSIS

17. SJAE Drs. Release Rate Measured / Estimated (circle one) (uCusec) 22200 4/ /93 0115

18. SJAE D:scharge Slope of Mixture -0.0747 4/ N3 0115 19 Condenser Air Leakage (cfm) 12.4 4/ /93 0115 LIQUID RELEASE S & RIVER TEMPERATURE (Gal) NA

}20. Lktuid Release

21. Uguid Release (Gross : Beta. Gamma) (uCVml) NA

22. Liouid Release (inhum) (uCVml) NA (uCVml) NA (23. Liould Release (Dissolved Noble Gas)

{24. River Mon. #3 Highest Temp. for previous day (oF) 58 1830 SURNUP 25 Core Avg Bumup for previous day (MWD /ST) 17011.16

26. Core Cycle Bumup for previous day (MWD /ST) 5600.84 REVIEWER.

THIS 18 A DRILL -

I l 1 l Rev. 0 .l Page 6.2-8 ; 1 VERMONT YANKEE NUCLEAR POWER STATION ; EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 EQENARIO MESSAGE CARD FROM: TSC Controller MESSAGE NO.: TSC-M-1 TO: TSC Coordinator CLOCK TIME: Upon assienment of Data Recorder LOCATION: TSC SCENARIO TIME: THIS IS A DRILL D0_FOT initiate any actions affecting normal plant operations.

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To obtain plant computer parameters that are normally available to TSC staff, use the Controller / Observer telephone in the Plant Computer Room to_ request the information from the Simulator Computer Room (Brattleboro extention ). c THIS IS A DRILL

I l I Rev. 0 , Page 6.2-9 ) i VERMONT YANKEE NUCLEAR POWER STATION , ) EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO MESSAGE CARD FROM: TSC Controller MESSAGE NO.: TSC-M-2 TO: TSC Coordinator CLOCK TIME: Upon assignment of Communicators LOCATION: TSC SCENARIO TIME: THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. After simulating assignment of your TSC Communicators to the Control Room, the prestaged TSC Communicators at the Simulator Control Room can now be used. 6 I THIS IS A DRILL

Rev. O Page 6.2-10 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO MESSAGE CARD FROM: Security Controller MESSAGE NO.: SEC-M-1 TO: Security Shift Suoervisor CIDCK TIME: 0315 LOCATION: Gatehouse II SCENARIO TIME: 00:30 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. Ensure all EXERCISE related communications over the Security Force radio network and the VY Pager system are preceded by and end with "THIS IS A DRILL". For EXERCISE purposes, use the appropriate emergency classificauion codes for VY Pager activations. THIS IS A DRILL i

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Rev. O Page 6.2-11 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO MESSAGE CARD P FROM: SCR Controller MESSAGE NO.: SCR-M-2 TO: Shift Supervisor CLOCK TIME: 0345 LOCATION: Simulator CR SCENARIO TIME: 01:00 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. Guard House called to report that they sensed the ground moving and that abnormal river motion was observed. A Radiation Protection technician, in the area of the South Warehouse called to report that he was passing by the warehouse when the ground moved and he heard something fall, when he investigated inside the warehouse it appeared that

several items had fallen from the storage shelves. The building itself seems to ,

be intact with no obvious damage. l i i

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THIS IS A DRILL ! I i

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Rev. O Page 6.2 12 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 1QXUARIO MESSAGE CARD . ROM: Controller MESSAGE NO.: SCR-M-3 TO: Shift Suoervisor CLOCK TIME: 0355 LOCATION: Simulator CR SCENARIO TIME: 01 10 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. Dam personnel from the Vernon and Bellows Falls Dams have been contacted and report that they have observed abnormal river motion, but the dams are intact and show no signs of damage or failure. 6 e THIS IS A DRILL

Rev, O Page 6.2-13 VERMONT YANKEE NUCLEFA POWER STATION EMERGENCY RESPONSE PRE?AREDNESS EXERCISE 1993 SCENARIO MESSAGE CARD i FROM: ESC Controller _ MESSAGE NO.: ESC-M-1 TO: ESC Meteorologist CLOCK TIME: 0445 or as reauested LOCATION: ESC SCENARIO TIME: 02:00 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. NOTE TO CONTROLLER: When requested by the ESC Meteorologist for current meteorological information, provide the meteorological information contained in Section 10.2 of the exercise manual for the appropriate time period. 1 I THIS IS A DRILL

Rev. O Page 6.2-14 i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 SCENARIO MESSAGE CARD FROM: EOF /RA Controller MESSAGE NO.- EOF-M-1 TO: Radiolonical Assistant CLOCK TIME: 0445 or as reauested LOCATION: EOF / Dose Assessment Area SCENARIO TIME: 02:00 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. NOTE TO CONTROLLER: When requested by the EOF /RC personnel for current forecast information, provide the General Area NUS Forecasts information contained in Section 10.2 (Page 10.2-1) of the exercise manual for the appropriate time period. ' 7

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Rev. 0 l Page 6.2-15 VERMONT YANKEE NUCLEAR POWER STATION . EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1993 i SCENARIO MESSAGE CARD FROM: News Media Center Observer MESSAGE NO.: NMC-M-1 TO: News Media Center Staff CLOCK TIME: 0600 LOCATION: News Media Center SCENARIO TIME: 03 15 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. (The following information was heard on the local radio stations and local television network.)

       "This morning an earthquake was felt in southern Vermont at around 3:45 a.m.

The New England Seismic Network estimated the magnitude at 4.8 on the open-ended Richter Scale. The epicenter was located near the town of Northfield-Massachusetts (latitude 43 degrees, 43 minutes and longitude 72 degrees, 28 minutes) approximately 11 to 12 miles southeast of Brattleboro, Vermont. No casualties or road and bridge damage have been reported, according to local Brattleboro officials. However, several chimneys have fallen and telephone service was temporarily interrupted in the Greenfield, Massachusetts area. Scientists from the New England Seismic Network also stated that aftershocks may be felt throughout the day. While it may be surprising to most people, an average of five earthquakes are felt somewhere in New England each year. The probabilities of a damaging earthquake occurring somewhere in New England are small be worldwide standards. The chances that a potentially damaging earthquake, of equal or greater value that the one that occurred today will repeat somewhere in New England, are 1 in 300 per year."

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THIS IS A DRIL!.

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                                                                                .1 VERMONT YANKEE NUCLEAR POWER STATION 1

EMERGENCY RESPONSE PREPAREDNESS EXERCISE-1993 i 1

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l l 1 5 1 7.0 STATION EVENT DATA i T

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i l VERMONT YANKEE NUCLEAR POWER. STATION' 3 EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 6 7.1 EVENTS SINMARY

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Rev. O Page 7.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 7.1 EVENTS

SUMMARY

The following information and supplementary material are provided for those evaluators having in-plant control assignments so as 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 evaluator must 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 evaluator will be required to provide additional information j to the players. Approximate Miniscenario Time Event Location Initiation 7.2.1 0300 Failure of the Start-Up OSC S/U Transformer Transformers Controller Lockout relay & Control Room 7.2.2 0345 Earthquake Various Simulator Damage Locations Controller, Inspection in Reactor OSC Building Controller 7.2.3 0345 Loss of Power Cable Vault Simulator to Bus DC-3A Room Response 7,2.4 0630 Shifting CRD Flow Simulator CRD Flow Control Response Control Valve Station - 7.2.5 0630 Local Reactor Simulator Actuation of Building Response SLC Squib El 318' Valves 7.2.6 0700 "B" Diesel "B" Diesel Simulator

Generator Generator Room Response Trip 7.2.7 0900 Loss of Turbine OSC Electrical Building Controller Bus #7 7.2.8 0900 Investigation Reactor OSC of Manual Building Controller Isolation of Hardened Vent -

, MOV

VERMONT YANKEE NUCLEAR POWER STATION EHERCENCY RESPONSE PREPAREDNESS EXERCISE

1993 i 7.2 EVENT MINISCENARIOS l l

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. . , = - - -. . , . Rev. O i Page 7.2.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 7.2.1 Miniscenario - Failure of the Start-Un Transformer's 86ST Relav i I. General Description At approximately 0300, an internal failure in the lockout relay for the Start-Up (S/U) Transformer results in tripping of both S/U Transformers. This results in a number of alarms on CRP 9-8 associated with the S/U Transformers. In addition, the respective circuit breakers will trip to isolate the S/U Transformers from the grid. l II. Description of Player Responses / Observations /Correceive Actions The Shift Supervisor should dispatch the outside AO to the S/U Transformers to investigate the loss of the S/U Transformers. The Control Room crew investigating the S/U Transformer alarms will be informed by the Observer that the lockout switch appears to be open. Further investigation reveals the lockout relay has been damaged and will require replacement. The A0 should report this information to the Simulator Control Room (SCR). The Control Room should request Electrical Maintenance to investigate the failure and return the S/U Transformers to service as soon as practicable. This repair will not be accomplished before 0630 (the S/U' Transformers must not be available to allow for the subsequent Loss of Normal Power). III. Event Closeout This activity will be closed out when the A0 reports his observations i to the Shift Supervisor in the SCR and a repair team has replaced the 86ST relay in the Control Room. i

Rev. O Page 7.2.1-2 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993 IV. Messages All information will be provided verbally by the appropriate controller. Message Approximate Basic Number li,mg, Descriotion 7.2.1-1 0315 Observation of the lockout switch 7.2.1-2 0330 Observation of the lockout 86ST relay 7.2.1-3 0350 Results of internal investigation by-Electricians MESSAGES TO BE DEVELOPED FOLLOWING REVIEW OF BASIC SCENARIO OUTLINE _m, "

Rev. O Page 7.2.2 1 VERMONT. YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 7.2.2 Miniscenario - Earthauake Damare Inspection I. General Description At approximately 0345, an earthquake is sensed on-site. Upon determination that a seismic event has occurred, the SCR should initiate a Seismic Damage Indication (SDI) walkdown in accordance with'OP 3127. In addition, I&C personnel will be asked to implement OP 4396. 'This. will provide the SS/ PED with the OBE status and CAV numbers. II. Description of Player Responses / Observations / Corrective Actions The SCR should initiate the SDI walkdown (after verifying plant-stability) following the guidance established in OP 3127, Attachment A. OSC Observers shall accompany anyone assigned to conduct . an SDI walkdown. When I&C personnel become available, the SS/ PED will request OBE status. The I&C personnel will retrieve the seismic data using OP 4396, Appendix A. The data sheet will be given to the SS/ PED. III. Event Closeout This event will be terminated when all messages have been transmitted to the SCR. Additional information regarding damage to equipment will' be contained in separate miniscenarios, as appropriate to the scenario. IV, Messaces All information will be provided verbally by the assigned Evaluator. Message Approximate Basic _ Time Description Number 7.2.2-1 0345 Steam Leak from SUH-18 (Rx Bldg 345')- 7.2.2-2 0345 Movement of RBAC-lC-(Rx Bldg 345')- 7.2.2-3 0345 Concrete Block wall next to RBCCU - pumps (Rx Bldg 303') 7.2.2-4 0345 Leak from RRU-10 (Rx Bldg 280') i 7.2.2-5 0355 ' Seismic Monitor Data j 1 l 1 1

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Rev O Page 7.2.2 2-VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 MESSAGES TO BE DEVELOPED FOLLOWING REVIEW OF BASIC SCENARIO OUTLINE.

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.. . . . - . _ . . .- . .- . - -. =- Rev. O Page 7.2.3 1 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE ' 1993 7.2.3 Miniscenario - Loss of Power to Bus DC-3A I. Ceneral Description During the earthquake, the feeder breaker for Bus DC-3A experiences excessive movement, resulting in the breaker opening, causing a loss of Control Room Alarms associated with CRP 9-3, 9-4, 9-5, 9-6 and 9-8. The SS/ PED should dispatch an A0 to the Cable Vault to investigate the loss of power. II. Description of Player Responses / Observations / Corrective Actions Upon recognition that a loss of Control Room annunciators has occurred, the SS/ PED should dispatch an A0 or CR0 to the Cable Vault to investigate the loss of power. Upon arrival, he determines that there may be internal damage in the feeder breaker to DC-3A. There is an odor of ozone in the immediate area of the breaker. He notifies the SCR and requests permission to manually transfer the supply to DC-3A from.DC-1, Electrical Maintenance personnel should -be dispatched - to open the. breaker and inspect the internal components When the panel is exposed, there is evidence of a direct short from the trip coil to the breaker housing which resulted in the breaker tripping. The trip coil will need , to be replaced, tested and put back in service before the breaker can be returned to service. III. Event Closecut This activity will be terminated when Maintenance personnel identify the fault and walkthrough the actions required to procure, install, test and return the breaker to service. The feed for DC-3A will be' restored upon manual operation of the transfer switch, i

Rev. O Page 7.2.3-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 V. Messares . All information will be provided verbally by the appropriate controller. Message Approximate Basic Number lig.g Description 7.2.3-1 0345 Loss of alarms on CRP 9-3, 9-5, 9-6 and 9-8 7.2.3 0355 Investigation of DC-3A feeder breaker ! 7.2.3-3 0545 Completion of trip coil replacement MESSACES TO BE DEVELOPED FOLLOWING REVIEW OF BASIC SCENARIO OUTLINE l

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Rev. O Page 7.2.4-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 7.2.4 Miniscenario - Shiftine CRD Flow Control Valve I. General Descrintion As soon as the SCR Operators realize an ATWS condition exists, they will initiate activites to bring the reactor to a shutdown condition. Among the options that may be pursued would be to manually drive the control rods into the core. If this is attempted, the rod (s) selected will fail to move. II. Description of Player Resnonses/ Observations / Corrective Actions After CRD-56 is shut, the SCR Operator will attempt to manually drive control rods, he should observe drive flow and positive indication that the selected rod is moving. When this is not observed, an A0 should be sent to the CRD Flow Control station to investigate the problem. When the A0 indicates to the Observer what he is looking for, the Observer will inform the AO that the CRD Flow Control Valve is shut and there is no air pressure to the valve. This information should be passed on to the SCR Operators. The A0 should be directed to shift FCVs in accordance with OP 2111. THIS ACTIVITY SHALL BE SIMULATED. When the A0 has discussed this procedure with the Observer, completion of the task may be reported to the SCR. t III. Event Closecut This event will be terminated when the A0 successfully demonstrates the , actions necessary to shift the CRD Flow Control Valves and made an appropriate report to the Control Room. IV. Messares. . All information will be provided verbally by the appropriate controller.

4 Rev. O' Page 7.2.4 2 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993. MESSAGES TO BE DEVELOPED FOLLOWING REVIEW OF BASIC SCENARIO OUTLINE

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Rev. O. Page 7.2.5 1 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993 7.2.5 Miniscenario - Local Actuation of SLC Saulb Valves I. General Descriotion At approximately 0630, excessive turbine vibration causes a turbine trip with a resulting reactor scram signal. The reactor will fail to complete the requited scram resulting in an ATWS condition. The SCR operator will elect to inject SLC from the reactor control panel using the keylock control switches. II. Descriotion of Player Resoonses/ Observations / Corrective Actions Upon operation of the keylock switches, the operator will not receive either of the positive indications that SLC has successfully fired. He will not receive the alarm indicating a loss of continuity through the explosive charge, nor will he receive the flow indicating light. At this point the operator should report to the SS/ PED that SLC failed to actuate from the control board. An AO should be dispatched to manually initiate SLC per OP 3101 Appendix G. This requires the AO-to obtain a battery and appropriate electrical leads to attach to the firing mechanism of each valve. THESE ACTIONS WILL BE SIMULATED. When this task has been completed, the A0 should report back to the SS/ PED to verify actuation. , III. Event Closeout i This activity will be closed out when the A0 reports that the SLC , explosive primers have been detonated in accordance with OP 3101, . Appendix G and the SCR has positive indication of SLC injection. IV. Messages All informat ion will be provided verbally by the appropriate controller. Message Approximate Basic Number Time Description 7.2.5-1 0650 Indications of local actuation of SLC

Rev. O Page 7.2'.5-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 MESSAGES TO BE DEVELOPED FOLLOWING REVIEW OF BASIC SCENARIO OUTLINE

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Rev. 0 Page 7.2.6-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 7.2.6 Miniscenario - "B" Diesel Generator Trio I. General Description At approximately 0700, the "B" Diesel Generator Jacket Cooling temperature Hi/ Low alarm actuates, followed shortly after by a trip of the Diesel Generator. The SCR will dispatch an A0 to investigate the alarm and subsequent trip. II. Description of Plaver Responses / Observations / Corrective Actions The A0 dispatched to the "B" Diesel Generator room will find abnormally high lube oil temperatures, and jacket cooling water temperatures are higher than normal. The AO will be informed by the observer that ambient temperatures in the area are noticeably higher than normal, particularly in the area around FCV-104-28B. If the A0 climbs up to the FCV-104-28B valve to determine valve position, the observer will state that the valve indicates " shut". This information should be conveyed to the Control Room, and subsequently to the TSC. The TSC should request the OSC to dispatch I6C and/or maintenance personnel to the "B" Diesel Generator room. When these personnel attempt to manipulate FCV-104-28B, it frees up the shaft binding and the valve opens. III. Event Closeout The event will be terminated when the OSC sends personnel to manipulate the valve and it opens. This allows normal service water flow to be restored to the Diesel Generator Auxiliary Systems. . IV. Messanes , All information will be communicated verbally by the observer. Responses will be appropriate to the activities of the players.

Rev. O Page 7.2 7-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 1 7.2.7 Miniscenario - Loss of Electrical Bus #7 I. General Descriotion Sometime between 0700 and 0800, a spurious trip of the instantaneous overcurrent relay (K50) in breaker 27 occurs. This relay will cause breaker 27 to open, and on interlock the feeder breaker 77 will also open. The cause of the initial fault in the 27 breaker is postulated to be weakened spring fingers of the K50 relay, which failed some time af ter the jolting experienced during the earthquake. By procedure an electrical maintenance team should be dispatched to investigate the problem. If the operating crew attempts to cross-tie using 6T7 breaker to feed bus #7, the green light will go out and neither the red or amber light will illuminate. The 6T7 breaker does not close. The magnitude of the problem will not be realized until approximately 0900 when the lack of power on Bus #7 prevents closure of the hardened vent rupture disk isolation valve to terminate a radioactive release to the atmosphere. Once power is restored to Bus #7, the release may be terminated. II. Description of Player Resoonses/ Observations / Corrective Actions _ The team sent from the OSC to investigate Bus #7 will go to the switchgear room to breaker 27. The team will be informed by the observer that there is an instantaneous overcurrent indicating flag showing on one phase. The maintenance team will follow standard procedure to ensure the bus is de-energized and attempt to locate any grounds using a megger. Results of these activities will reveal that no grounds exist on the bus. When the 6T7 breaker switch is operated ~ from the SCR, fuses FU 30 and FU 6 are blown due to an electrical fault The red, in the DC control circuit. The closing coil is burned up. amber and green indicating lights for breaker 6T7 on CRP 9-8 and at the The team will pursue breaker are not lit due to lack of power. V E

1 I Rev. O Page 7.2.7-2 VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1993 I energizing Bus #7, taking appropriate ground readings as each step in' the e"olution is completed. Ultimately, Bus #7 will be returned to service. j l i III. Event Closecut i 1 Once the maintenance team determines the problem .and completes ' appropriate corrective actions to restore power to Bus #7, the event is terminated. This has to be coordinated with the Exercise Coordinator to ensure sufficient time has elapsed to produce the resultant radioactive release, consistent with the established sequence of events. 1 l IV. Messares i All information will be communicated verbally by the observer. The observer must be prepared to extend the player response to be consistent with the established exercise sequence of events. Responses will be appropriate to the activities of the players. Message Approximate Basic Number Iing Descriotion 7.2.7 1 0730 Observations at breaker 27 7.2.7-2 0735 7.2.7-3 6T7 breaker fuse conditions 0735 6T7 breaker indicating light status 7.2.7-4 0800 Electrical bus meggar readings MESSACES TO BE DEVE14 PED FOLIDWING REVIEW OF BASIC SCENARIO OUTLINE -

Rev. O Page 7.2.8-1 VERMONT YANKEE NUC1. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 7.2.8 Miniscenario - Investination of Manual Isolation of Hardened Vent MOV I. General Descrintion At about 0900, the primary containment pressure will reach approximately 5 psig due to the small steam leak in the drywell. Drywell pressure causes the rupture disk to fail, thereby venting the containment-directly to the stack (failure of the rupture disk is due to weakening , imposed due to the earthquake). The operators may attempt to shut the hardened vent isolation MOV, but power is not available to the MOV due to Bus #7 being de-energized. II. Description of Player Responses / Observations / Corrective Actions A team may be sent from the OSC to manually shut the hardened vent ) isolation valve. This valve is physically located on the south wall of the Reactor Building, elevation 252'. When the team reaches this location, they will encounter high radiation levels in the general area . l (refer to Table 9.3-5 and Figure 9.3-5) and extremely high dose rates .] at the valve (50 to 100 R/hr). The team should immediately back away l from the area and inform the TSC of this situation. l Event Closecut III. This event will be terminated when the team informs the TSC of the general area dose rates and they are directed to return to the OSC. , Manual isolation of the hardened vent line will not.be possible due to mechanical failure of the manual operator and inhibited by elevated dose - , rates in the area. IV. Messages All information will be communicated verbally by the observer. The observer must be prepared to extend the player response to be consistent with the established exercise sequence of events. Responses will be appropriate to the activities of the players. l 1 1 - - - - - -- ---e - - - - - - -- - , - . , . , - - -

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 b f 8.0 OPERATIONAL DATA

FOTE: The operational data is highly dependent on . operator actions- t taken in response' to the conditions presented within the' : scenario. The operational data reflects plant conditions assuming certain basic operator' response actions" being taken. The operational data was taken from the plant simulator. ..; l r h f i

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^ VERMONT YANKEE NUCLEAR POWER STATION Rsv. O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Pags 8.0-1 1993

8 0 OPERAT!ONAL DATA ,

SCENARIO TIME 00.00 00.15 00:30 00 45 01:00 INSTR. CLOCK TIME 02.45 03.00 03.15 03:30 03 45 ITEM PANEL ID DESCRIPTION UNITS 1 9-3 FT-23-108-1 HPCI FLOW GPM O O O O O 2 43 FI-10-139A RHR A FLOW GPM 1 1 1 1 1 3 9-3 F1-10-139B RHR B FLOW GPM i 1 1 1 1 4 9-3 FI-14-50A CS A FLOW GPM 0 0 0 0 0 5 9-3 Fbi 4-50B CS B FLOW GPM 0 0 0 0 0 I 6 9-3 Pl 16-19-12A DRYWELL PRESS PSIA 17 17 17 17 17 7 B-3 PI-16-19-12B DRYWELL PRESS PSLA 17 17 17 17 17 8 9-4 F1-13-91 RCIC FLOW GPM 0 0 0 0 0 9 9-4 Fb12-141 A RWCU FLOW GPM 65 65 65 65 65 10 9-4 F1-12-141B RWCU FLOW GPM 65 65 65 65 65 11 9-4 2-165A RX COOLANT TEMP DEG F 527 527 527 527 527 12 44 2-165B RX COOLANT TEMP DEG F 527 527 527 527 527 13 9-4 2159A RECIRC A LOOP FLOW KGPM 29.7 29.7 29,7 29.7 29.7 14 94 2-1598 RECIRC B LOOP FLOW KGPM 29.7 29.7 29.7 29.7 29 7 15 9-5 7-46A APRM/lRM A % 99 99 99 99 99 16 9-5 7-46B APRWIRM B % 100 100 100 100 100 17 9-5 7-46C APRM/IRM C % 98 98 98 98 98 18 9-5 7-46D APRM/lRM D % 99 99 99 99 99 19 9-5 7-46E APRM/IRM E % 100 100 100 100 100 20 9-5 7-46F APRM/lRM F % 100 100 100 100 100 21 9-5 7-43A SRM A CPS .383E+06 .383E+06 .383E+06 .383E+06 .363E+06 22 9-5 7-438 SRM B CPS .457E+06 457E+06 .457E+06 .457E+06 .457E+06 23 9-5 7-43C SRM C CPS .515E+06 .515E+06 .515E+06 .515E+06 .515E+06 l 24 9-5 7-430 SRMD CPS .429E+06 .429E+06 .429E+06 .429E+06 .429E+06 < 25 9-5 2-3-95 CORE F LOW MLB/HR 46 46 46 46 46 26 9-5 2-3-95 CORE DP PSID 18 18 18 18 18 27 9-5 Fb3-310 CRD FLOW GPM 46.6 46.6 46 6 46 6 46 6 28 9-5 5-96 WIDE RANGE PRESS PSIG 1007 1007 1007 1007 1007 29 9-5 6-96 NAR RANGE PRESS PSIG 1008 1000 1000 1000 1008 30 9-5 6-97 FEEDWATER FLOW MLB/HR 64 64 64 64 64 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 6.4 64 6.4 64 64 32 9-5 6-98 NAR RANGE LEVEL INCHES 161 161 161 161 161 33 9-5 6-98 WIDE RANGE LEVEL INCHES 481 481 481 481 481 34 96 Lb107 5 CST LEVEL % 49 49 49 49 49 35 96 Li-102-5A HOTWELL LEVEL N % 60 60 60 60 60 36 9-6 Ll-102-5B HOTWELL LEVEL S % 58 58 58 58 58 37 9-7 PL10129 CONDENSER VACUUM IN HG 1.7 1.7 1.7 1.7 1.7 38 9-8 D/G A BKR OPEN OPEN OPEN OPEN OPEN 39 9-8 D/G B BKR OPEN OPEN OPEN OPEN OPEN. 40 9-23 16-19-33A/C TORUSTEMP DEG F 78 78 78 78 78 41 9-25 LI-46A TORUS LEVEL FEET 11.05 11.05 11.05 11.05 11.05 42 9-25 LI-46B TORUS LEVEL FEET 11.05 11.05 11.05 11.05 11.05 43 9-25 TR-16-19-44 TORUS PRESS PSIA 14.6 14 6 14 6 14 6 14 6 44 9-25 TR-16-1944 DRYWELL PRESS PSIA 17 17 17 17 17 45 9-25 PR 1<156-3 DW/ TORUS DP PSID 1.94 1.94 1.94 1.94 1.94 46 4 25 TR-16-19-45 DRYWELL TEMP DEG F 120 120 120 120 120 47 9-26 PI-1-125-3A RX BUILDING DP IN H2O -1.62 -1.62 -1.62 -1.62 -1.62 48 9-26 PI-1-125-3B RX BUILDING DP IN H2O -1.62 -1.62 -1.62 -1.62 -1.62 49 9-26 Fbi-125-1 A SGTS FLOW CFM 8 8 8 8 8 50 9-26 FI-1 1251B SGTS FLOW CFM 0 0 0 0 0 51 CAD DW/ TORUS O2 CONC. % 1.14 1.14 1.14 1.14 1.14

e VERMONT YANKEE NUCLEAR POWER STATION Rn0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 8 0-2 1973 8 0 OPERATIONAL DATA SCENARIO TIME 01:15 01:30 01:45 02:00 02:15 INSTR. CLOCK TIME 04.00 04:15 04:30 04.45 05.00 ITEM PANEL 10 DESCRIPTION UNITS 1 9-3 FT-23-108-1 HPCI FLOW GPM 0 0 0 0 0 2 9-3 FL10-139A RHR A FLOW GPM 1 1 1 1 1 3 9-3 F1-10-139B RHR B FLOW GPM 1 1 1 1 1 4 93 FL14-50A CS A FLOW GPM 0 0 0 0 0 5 9-3 FL14-50B CS B FLOW GPM 0 0 0 0 0 6 9-3 PL16-19-12A DRYWELL PRESS PSIA 17 17 17 17 17 7 9-3 Pi 16-19-12B DRYWELL PRESS PSIA 17 17 17 17 17 8 9-4 F1-13-91 RCIC FLOW GPM 0 0 0 0 0 9 N F1-12-141 A RWCU FLOW GPM 65 65 65 65 65 10 N Fl-12-141 B RWCU FLOW GPM 65 o$ 65 65 65 11 N 2-165A RX COOLANT TEMP DEG F 527 527 527 527 527 12 N 2-165B RX COOLANT TEMP DEG F 527 527 527 527 527 . 13 9-4 2-159A RECIRC A LOOP FLOW KGPM 29.7 29.7 29.7 29.7 29.7 14 N 2-159B RECIRC B LOOP FLOW KGPM 29 7 29 7 29.7 29 7 29.7 15 45 7 4GA APRM1RM A % 99 99 99 99 99 16 9-5 7-46B APRM/lRM B % 100 100 100 100 100 17 9-5 7-46C APRM1RM C % 98 98 98 98 98 , 18 9-5 7-46D APRM/IRM D % 99 99 99 99 99 19 9-5 7 46E APRMllRM E % 100 100 100 100 100 20 9-5 7-46F APRM1RM F % 100 100 100 100 100 21 9-5 7-43A SRM A CPS .383E+06 .383E+06 .383E+06 .383E+06 .383E+06 22 0-5 7-43B 3RM B CPS .457E+06 .457E+06 .457E+06 .457E+06 .457E+06 23 9-5 7 43C SRM C CPS - .515E+06 .515E+06 .515E+06 .515E+06 .515E+06 24 9-5 7-43D SRM D CPS .429E+06 .429E+06 .429E+06 .429E+06 .429E+06 I 25 9-5 2-3-95 CORE FLOW MLB/HR 46 46 46 46 46 26 9-5 2-3-95 CORE DP PSID 18 18 18 18 18 27 9-5 Fh"L310 CRD FLOW GPM 46 6 46.6 46.6 46.6 46 6 28 9-5 6-96 W!DE RANGE PRESS PSIG 1007 1007 1007 1007 1007 29 9-5 6 96 NAR RANGE PRESS PSIG 1008 1008 1008 1008 1008 30 9-5 6 97 FEEDWATER FLOW MLB/HR 64 64 6.4 64 64 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 6.4 64 6.4 6.4 64 32 9-5 6-98 NAR RANGE LEVEL INCHES 161 161 161 161 161 33 95 6-98 WIDE RANGE LEVEL INCHES 481 481 481 481 481 34 M Li-107-5 CST LEVEL % 49 49 49 49 49 35 M Li-102 5A HOTWELL LEVEL N % 60 60 60 60 60 36 M LL102-5B HOTWELL LEVEL S % 58 58 58 58 58 37 9-7 PI-101-29 CONDENSER VACUUM IN HG 1.7 1.7 1.7 1.7 1.7 38 9-8 D/G A BKR OPEN OPEN OPEN OPEN OPEN 39 M D/G B BKR OPEN OPEN OPEN OPEN OPEN 40 9-23 16-19-33A/C TORUSTEMP DEG F 78 78 78 78 78 41 9-25 Lb46A TORUS LEVEL FEET 11.05 11.05 11.05 11.05 11.05 42 9-25 Lb469 TORUS LEVEL FEET 11.05 11.05 11.05 11E 11E 43 945 TR-16-19-44 TORUS PRESS PSIA 14 6 14.6 14 6 14.6 14.6 44 9-25 TR-16-19-44 DRYWELL PRESS PSIA 17 17 17 17 17 45 9 25 PR-1-156-3 DW/ TORUS DP PSID 1.94 1.94 1.94 1.94 1.94 46 9-25 TR 161NS DRYWELL TEMP DEG F 120 120 120 120 120 . 47 9-26 PI-1-125-3A RX BUILDING DP IN H2O -1.62 -1.62 -1.62 -1.62 -1.62 ! 48 9-26 PL1-125-3B RX BUILDING DP IN H2O 1.62 -1 62 -1.62 -1.62 1.62 l 49 9-26 FL1 125-1 A SGTS FLOW CFM 8 8 8 8 8 50 9-26 FL1-125-1 B SGTS FLOW CFM 0 0 0 0 0 l 51 CAD DW/ TORUS O2 CONC. % 1.14 1.14 1.14 1.14 1.14 1

i 4KRMONT YANKEE NUCLEAR POWER STATION Rav. O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 8 0-3 1993 8.0 OPERATIONAL DATA SCENARIO TIME 02.30 02:45 03 00 03:15 03 30 INSTR. CLOCK TIME 05:15 05:30 05:45 06 00 06:15 ITEM PANEL ID DESCRIPTION UNITS 1 9-3 FT-23-108-1 HPCI FLOW GPM 0 0 0 0 0 2 9-3 F1-10-139A RHR A FLOW GPM 1 1 1 1 1 3 9-3 FI-10-139B RHR B FLOW GPM i 1 1 1 1 4 9-3 Fi-14-50A CS A FLOW GPM 0 0 0 0 0 5 9-3 FI-14-50B CS B FLOW GPM 0 0 0 0 0 6 9-3 PL16-19-12A DRYWELL PRESS PSIA 17 17 17 17 17 7 43 PL16-19-12B DRYWELL PRESS PSIA 17 17 17 17 17 8 44 F1-13-91 RCIC FLOW GPM 0 0 0 0 0 9 M FL12-141 A RWCU FLOW GPM 65 65 65 65 65 10 94 F1-12-141 B RWCU FLOW GPM 65 65 65 65 65 11 94 2-165A RX COOLANT TEMP DEG F 527 527 527 527 527 12 44 2165B RX COOLANT TEMP DEG F 527 527 527 527 527 13 9-4 2-159A RECIRC A LOOP FLOW KGPM 29.7 29.7 29.7 29.7 29.7 14 44 2-159B RECIRC B LOOP FLOW KGPM 29.7 29.7 29.7 29 7 29 7 15 9-5 7 46A APRMilRM A % 99 99 99 99 99 16 9-5 7-46B APRM'IRM B % 100 100 100 100 100 17 9-5 7-46C APRM/lRM C % 98 98 98 96 9S 18 45 7-46D APRWIRM D % 99 99 99 99 99 19 45 7-46E APRM/lRM E % 100 100 100 100 100 20 45 7-46F APRM/lRM F % 100 100 100 100 100 21 45 7-43A SRM A CPS .383E+06 .383E+06 .383E+06 .383E+06- .383E+06 22 9-5 7-43B SRMB CPS .457E+06 .457E+06 .457E+06 .457E+06 .457E+06 23 9-5 7-43C JRM C CPS .515E+06 .515E+06 .515E+06 .515E+06 .515E+06 24 9-5 7-43D SRM D CPS .429E+06 .429E+06 .429E+06 .429E+06 .429E+06 25 B-5 2-3-95 CORE FLOW MLB/HR 46 46 46 46 46 i 26 9-5 2-3-95 CORE DP PSID 18 18 18 18 18 , 27 9-5 FL3-310 CRD FLOW GPM 46.6 46 6 46.6 46.6 46 6 28 45 6 96 WIDE RANGE PRESS PSIG 1007 1007 1007 1007 1007 29 9-5 6-96 NAR RANGE PRESS PSIG 1008 1008 1008 1008 1008 30 9-5 6-97 FEEDWATER FLOW MLB/HR 6.4 64 6.4 64 64 31 9-5 6 97 MAIN STEAM FLOW MLB/HR 6.4 6.4 6.4 64 64 32 9-5 5 98 NAR RANGE LEVEL INCHES 161 161 161 161 161 33 9-5 6-98 WIDE RANGE LEVEL INCHES 481 481 481 481 481 - 34 9-6 Li-107-5 CST LEVEL % 49 49 49 49 49 ; 35 94 Li-102-5A HOTWELL LEVEL N % 60 60 60 60 60 36 46 LL102-58 HOTWELL LEVEL S % 58 58 58 58 5C 37 9-7 PL101-29 CONDENSER VACUUM IN HG 1.7 1.7 1.7 1.7 1.7 38 98 D/G A BKR OPEN OPEN OPEN OPEN OPEN 39 9-8 DIG B BKR OPEN OPEN OPEN OPEN OPEN 40 9-23 16-19-33A/C TORUS TEMP DEG F 78 79 73 76 78

4i 9-25 LLM[ ~ TOR $$ LEVEL FEET 11.05 11.05 11.05 11.05 11.05 42 9-25 Li46B TORUS LEVEL FEET 11.05 11.05 11.05 11.05 11.05 43 9-25 TR 16-19 44 TORUS PRESS PS A 14 6 14.6 14 6 14 6 146 44 9-25 TR 16-19 44 DRYWELL PRESS PSIA 17 17 17 17 17 45 9-25 PR-1-156-3 DW/ TORUS DP PSID 1.94 1.94 1.94 1.94 1.94 46 4 25 TR 16-19 45 DRYWELL TEMP DEG F 120 120 120 120 120 47 4 26 PL1-125-3A RX BUILDING DP IN H2O -1.62 -1.62 -1.62 -1.62 -1.62 48 9 26 PI-1-125-3B RX BUILDING DP IN H2O -1.62 -1.62 -1 62 -1.62 -1.62 49 9-26 F1-1-125-1 A SGTS FLOW CFM 8 8 8 8 8 50 9-26 FL1-125-1 B SGTS FLOW CFM 0 0 0 0 n 51 CAD DW/ TORUS O2 CONC. % 1.14 1.14 1.14 1.14 1.14

VERMONT YANKEE NUCLEAR POWER STATION Rrv. 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE Paga 6 0 4 1993 6 0 OPERATIONAL DATA SCENARIO TIME 03 45 04.00 04:15 04.30 04.45 INSTR. CLOCK TIME 06.30 06.45 07:00 07:15 07:30 ITEM PANEL ID DESCRIPTION UNITS 1 9-3 FT-23-108-1 HPCI FLOW GPM 0 0 0 0 0 2 9-3 FI-10-139A RHR A FLOW GPM i 5864 5864 5864 5864 3 9-3 Fl-101398 RHR B FLOW GPM i 5576 5576 5576 5576 4 9-3 FL14-50A CS A FLOW GPM 0 0 0 0 0 5 9-3 FL14-50B CS B FLOW GPM 0 0 0 0 0 6 0-3 PI 1&19-12A DRYWELL PRESS PSIA 17 17 16 16 16 7 9-3 Pi-16-19-128 DRYWELL PRESS PSIA 17 17 16 16 16 8 94 F1-1191 RCIC FLOW GPM 0 417 412 414 399 9 9-4 Fl.12-141 A RWCU FLOW GPM 65 0 0 0 0 10 9-4 F1-12-1418 RWCU FLOW GPM 65 0 0 0 0 11 9-4 2-165A RX COOLANT TEMP DEG F $27 461 395 366 394 12 9-4 2-1658 RX COOLANT TEMP DEG F 527 461 395 366 394 13 94 2-159A RECIRC A LOOP FLOW KGPM 29 0 0 0 0 0 14 9-4 2-159B RECIRC B LOOP FLOW KGPM 29.7 0 0 0 0 15 9-5 7-46A APRM/lRM A % 100 2 0 0 0 16 9-5 7-46B APRM/lRM B % 100 2 0 0 0 17 9-5 7-46C APRWIRM C % 99 2 0 0 0 18 9-5 7 46D APRM/lRM D % 100 2 0 0 0 19 9-5 7-46E APRWIRM E % 100 2 0 0 0 20 95 7-46F APRM/lRM F % 100 2 0 0 0 21 9-5 7 43A SRM A CPS .386E*06 .377E+02 .300E+01 .300E+01 .300E+01 22 95 7-438 SRM B CPS .460E+06 .403E+02 .300E+01 .300E+01 .300E +01 23 9-5 7-43C SRM C CPS .519E+06 .370E+02 .300E+01 .300E+01 .300E+01 24 9-5 7-43D SRM D CPS .432E+06 .391 E+02 .300E+01 .300E+01 .300E+01 25 9-5 2-3-95 CORE FLOW MLB/HR 46 16 16 12 12 26 9-5 2-3-95 CORE DP PSID 18 3 3 3 3 27 9-5 F1-3-310 CRD FLOW GPM 47 47 46.4 47 47 28 9-5 6-96 WIDE RANGE PRESS PSIG 1008 784 973 619 444 29 9-5 6-96 NAR RANGE PRESS PSIG 1008 DSL' DSL* DSL' DSL* 30 9-5 6 97 FEEDWATER FLOW MLB/HR 64 0 0 0 0 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 6.4 0 0 0 0 32 9-5 & 98 NAR RANGE LEVEL INCHES 161 -13 -2 40 106 33 9-5 & 98 WlEE RANGE LEVEL INCHES 486 -2 -2 49 136 34 96 Ll-107-5 CST LEVEL % 49 48 47 46 45 35 94 Lk102 5A HOT NELL LEVEL N % 60 63 63 63 59 36 96 Ll-102-5B HOTNELL LEVEL S % 58 63 63 63 58 37 9-7 Pi-101-29 CONDENSER VACUUM INHG 1.7 11.1 17.3 21.5 24 2 38 9-8 DK4 A BKR OPFN CLOSED CLO5ED CLOSED CLOSED 30 9e D/G B BKR OPEN CLOSED OPEN OPEN OPEN 40 9-23 16-19-33A/C TORUS TEMP DEG F 78 122 125 126 124 41 9-25 Li-46A TORUS LEVEL FEET 11.06 1128 11.31 11.32 11.32 42 9-25 Li-46B TORUS LEVEL FEET 11.06 1128 11.31 11.32 11.32 43 9-25 TR-16-11M4 TORUS PRESS PSLA 14.6 16.1 16.2 16.3 16.3 44 9-25 TR 16-19 44 DRYWELL PRESS PSIA 17 17 16 16 16 45 9-25 PR-1-156-3 DW/ TORUS DP PSID 1.98 04 0.3 0 0 46 9 25 TR-16-19-45 DRYWELL TEMP DEG F 120 119 117 117 116 47 9-26 PI-1-125-3A RX BUILDING DP 1N H2O -1.62 -0.68 4).68 -0.68 -0.68 48 9 26 Pl-1 125-3B RX BUILDING DP IN H2O -1.62 0 68 -0.68 -068 -0.68 49 9-26 F1-1-125-1 A SGTS FLOW CFM 0 1500 1500 1500 1500 50 9-26 F1-1-125-1 B SGTS FLOW CFM 0 1500 1500 1500 1500

   $1    CAD                     DW/ TORUS O2 CONC.          %      1.14     1.14      1.14     1.14       1.14
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VERMONT YANKEE NUCLEAR POWER STATION Rw. O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 8.0-5 1993 8 0 OPERATIONAL DATA SCENARIO TIME 05.00 05:15 05.30 05:45 06:00 INSTR. CLOCK TIME 07:45 08.00 08:15 08:30 08.45 ITEM PANEL ID DESCRIPTION UNITS 1 9-3 FT-23-1061 HPCI FLOW GPM 0 0 0 0 0 2 9-3 FL10-139A RHR A FLOW GPM 5864 5864 5864 58G1 5864 3 9-3 F1-10-1398 RHR B FLOW GPM 5576 5576 5576 . 5576 5576 4 9-3 Fbi 4-50A CS A FLOW GPM 0 0 0 0 0 5 93 F1-14-50B CS B FLOW GPM 0 0 0 0 0 9-3 PI-16-19-12A DRYWELL PRESS PSIA 16 16 16 16 19 I 6 7 9-3 Pb16-19-12B DRYWELL PRESS PSIA 16 16 16 16 19 8 9-4 FI-13-91 RCIC FLOW GPM 392 0 0 0 0 9 9-4 Fl-12-141 A RWCU FLOW GPM 0 0 0 0 0 10 0-4 Fi-12-141 B RWCU FLOW GPM 0 0 0 0 0 11 9-4 2-165A RX COOLANT TEMP DEG F 397 420 441 442 410 ; 12 N 2-165B RX COOLANT TEMP DEG F 397 420 441 442 410 13 9-4 % 59A RECIRC A LOOP FLOW KGPM 0 0 0 0 0 14 9-4 .?-1593 RECIRC B LOOP FLOW KGPM 0 0 0 0 0 15 9-5 ?-46a APRWIRM A % 0 0 0 0 0 16 9-5 7 dSB APRM/lRM B % 0 0 0 0 0 17 9-5 7-46C APRM/lRM C % 0 0 0 0 0 18 9-5 7-46D APRM/lRM D % 0 0 0 0 0 19 9-5 7-46E APRWIRM E % 0 0 0 0 0 20 9-5 7-46F APRM/lRM F % 0 0 0 0 0 21 9-5 7-43A SRM A CPS .300E+01 .300E+01 .300E+01 .300E+01 .300E+01 22 9-5 7-43B SRM B CPS .300E+01 .300E+01 .300E+ri .300E+01 .300E+01 23 95 7-43C SRM C CPS .300E+01 .300E+01 .300E+)1 .300E+01 .300E+01 24 9-5 7-43D SRM D CPS .300E+01 .300E+01 .300E+01 .300E+01 .300E+01 25 9-5 2-3-95 CORE FLOW MLB/HR 12 12 11 12 12 26 95 2-3-95 CORE DP PSID 3 3 3 3 3 5 27 9-5 F1-3-310 CRD FLOW GPM 47 47 47 47 112 28 95 6-96 WIDE RANGE PRESS PSIG 403 446 495 500 480 29 9-5 6 96 NAR RANGE PRESS PSIG DSL* DSL' DSL' DSL* DSL* 30 95 6-97 FEEDWATER FLOW MLB/HR 0 0 0 0 0 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 0 0 0 0 0 32 9-5 6-98 NAR RANGE LEVEL INCHES 169 193 21 2 150 118 33 L-5 6-98 WIDE RANGE LEVEL INCHES 202 223 238 185 160 34 96 LI-107-5 CST LEVEL % 44 44 44 44 40 , 35 94 LI-102-5A HOTWELL LEVEL N % 59 58 58 58 82 36 9-6 Li-102 5B HOTWELL LEVEL S % 59 58 58 58 82 37 97 PL10129 CONDENSER VACUUM IN HG 26,1 27.4 28.2 28.8 24 38 98 D/G A BKR _ CLOSED CLOSED CLOSED CLOSED CLOSED 39 9-8 D/G B BKR OPEN OPEN OPEN OPEN OPEN ~ 40 9-23 16-19-33A/C TORUS TEMP DEGV 123 120 120 123 164 41 9-25 Lb46A TORUS LEVEL FEEi 11.32 11.31 11.32 11.35 11.63 l 42 0-25 LL46B TORUS LEVEL FEET 11.32 11.31 11.32 11.35 11,63 l 43 9-25 TR-16-19-44 TORUS PRESS PSIA 16,8 172 17.8 182 18.7 44 9-25 TR 16-19-44 DRYWELL PRESS PSIA 17 17 18 18 19 45 9-25 PR-1-156-3 DW/ TORUS DP PSID 0 0.01 0.01 0 0.08 46 9 25 TR 16-19-45 DRYWELL TEMP DEG F 115 115 115 114 136 47 9-2ft ol-1-125-3A RX BUILDING DP IN H2O -068 -0.68 -0.68 -068 -068 48 9-26 M-1-125-3B RX BUILDING DP IN H2O -068 -0.68 -0.68 -0 68 -0 68 49 9 26 FL1 1251 A SGTS FLOW CFM 1500 1500 1500 i t,N) 1500 1 50 9-26 F1-1-125-1 B SGTS FLOW CFM 1500 1500 1500 1500 2500 51 CAD DW/ TORUS O2 CONC. % 1.14 1.14 1.14 1.14 1.13

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VERMONT VANKEE NUCLEAR POWER STATION Rcv. 0 .l EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 8.0 6 l 1993 I l 8.0 OPERATIONAL DATA SCENARIO TIME 0615 06.30 06.45 07:00 07:15 i INSTR. CLOCK TIME 09:00 09:15 09:30 09.45 10:00 j ITEM PANEL ID DESCRIPTION UNITS j 1 9-3 FT-23-108-1 HPCl FLOW GPM 0 0 0 0 0 2 9-3 FL10-139A RHR A FLOW GPM 5864 5874 5873 5873 5873 3 9-3 FL10-139B RHR B FLOW GPM 5576 5585 5585 5585 5585 4 93 FI-14-50A CS A FLOW GPM 0 0 0 0 0 5 43 Fi-14-50B CS B FLOW GPM 0 0 0 0 0 6 9-3 PI-16-19-12A DRYWELL PRESS PStA 19 18 18 17 17 7 93 PI-16-19-12B DRYWELL PRESS PSIA 19 18 18 17 17 8 N F1-13-91 RCIC FLOW GPM 0 0 0 0 0 9 94 Fl-12-141 A RWCU FLOW GFM 0 0 0 0 0 10 44 F1-12-141 B RWCU FLOW GPM 0 0 0 0 0 11 9-4 2-165A RX COOLANT TEMP r'" ' F 400 419 423 426 426 12 9-4 2-165B RX COOLANT TEMP DEG F 402 419 423 426 426 13 9-4 2-159A RECIRC A LOOP FLOW KGPM ') 0 0 0 0 14 9-4 2-159B RECIRC B LOOP FLOW KGPM 0 0 0 0 0 15 9-5 7-46A APRM1RM A % 0 0 0 0 0 16 45 746B APRM/lRM B % 0 0 0 0 0 17 9-5 7 46C APRM1RM C % 0 0 0 0 0 18 9-5 746D APRMllRM D % 0 0 0 0 0 19 9-5 7-46E APRM/lRM E % 0 0 0 0 0 20 9-5 7-46F APRM/lRV F % 0 0 0 0 0 21 9-5 743A SRM A CPS .300E+01 .300E +01 300E+01 .300E+01 300E+01 22 9-5 7-43B SRM B CPS .300E+01 .300E+01 .300E+01 .300E+01 .300E+01 23 45 7-43C SRM C CPS .300E+01 .300E+01 .300E +01 .300E+01 .300E+01 24 9-5 7-43D SRM D CPS .300E+01 .300E+01 .300E+01 .300E+01 .300E+01 25 9-5 2-3-95 CORE FLOW MLB/HR 12 12 12 12 12 26 45 2-3-95 CORE DP PSID 3 3 3 3 3 27 9-5 F1-3-310 CRD FLOW GPM 112 112 47 47 47 28 9-5 6-96 WIDE RANGE PRESS PSIG , 450 450 353 377 376 29 9-5 6-96 NAR RANGE PRESS PSIG DSL' DSL' DSL' DSL* DSL' 30 9-5 6-97 FEEDWATER FLOW MLB/HR 0 0 0 0 0 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 0 0 0 0 0 32 9-5 6-96 NAR RANGE LEVEL INCHES 137 161 161 155 147 33 9-5 6-98 WIDE RANGE LEVEL INCHES 171 195 198 190 182 34 Bf, Li-107 5 CST LEVEL % 40 41 41 41 41 35 96 Ll-102-5A HOTWELL LEVEL N % 82 42 82 82 82 36 94 Lt-102-58 HOTWELL LEVEL S % 82 82 82 82 82 37 9-7 PI-101-29 CONDENSER VACUUM IN HG 26.1 27.4 28.3 28.9 29.2 38 94 D/G A BKR CLOSED CLOSED CLOSED CLOSED CLOSED 39 9-6 D/G B BKR OPEN OPEN OPEN OPEN OPEN 40 9 23 16-19-33A/C TORUS TEMP DEG F 160 158 157 156 155 41 9-25 Li-46A TORUS LEVEL FEET 11.62 11.63 11.64 11.65 11.67 42 9 25 Ll-46B TORUS LEVEL FEET 11.62 11.63 11.64 11.65 11.67 43 9 25 TR-16-19-44 TORUS PRESS PSIA 18.6 18.3 17.8 17.2 16.7 44 9 25 TR-16-19 44 DRYWELL PRESS PSIA 19 18 18 17 17 45 9-25 PR-1-156-3 DW/ TORUS DP PSID 0.17 0.13 0.09 0.09 0 07 46 9-25 TR-16-19-45 DRYWELL TEMP DEG F 152 161 165 168 170 47 9-26 PL1-125-3A RX BUILDING DP IN H2O -0.68 -0.68 -0.68 -068 -068 48 9-26 PL1-125-38 RX BUILDING DP IN H2O -068 -0.68 -068 -0.68 -0.68 49 9-26 Fi-1-125-1 A SGTS FLOW CFM 1500 1500 1500 1500 1500 50 9-26 FL1-125-1 B SGTS FLOW CFM 1500 1500 1500 1500 1500 51 CAD DWITORUS O2 CONC. % 1.06 0.99 0.94 0.91 0 88

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VERMONT YANKEE NUCLEAR POWER STATION Rav, O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Pege 8.0-7 1993 8 0 OPERATIONAL DATA SCENARIO TIME 07:30 07:45 08 00 08:15 08:30 INSTR. CLOCK TIME 10.15 10.30 10:45 11:00 11:15 ITEM PANEL ID DESCRIPTION UNITS i 1 9-3 FT 23-108-1 HPCI FLOW GPM 0 0 0 0 0 2 43 FL10-139A RHR A FLOW GPM 5873 5874 5873 5873 5873 3 9-3 Fb10-1398 RHR B FLOW GPM 5585 5585 5585 5585 5585 , 4 43 Fbi 4-50A CS A FLOW GPM 0 0 0 0 0 5 9-3 Fl-14-50B CS B FLOW GPM 0 0 0 0 0 6 9-3 P!-16-19-12A DRYWELL PRESS PSIA 16 16 16 16 16 7 9-3 Phi &1912B DRYWELL PRESS PSIA 16 16 16 16 16 8 9-4 Fl-13-91 RCIC FLOW GPM 0 0 0 0 0 9 N F1-12-141 A RWCU FLOW GPM 0 0 0 0 0 10 9 FL12-141 B RWCU FLOW GPM 0 0 0 0 0 11 9-4 2-165A RX COOLANT TEMP DEG F 425 423 400 400 398 12 9 2-165B RX COOLANT TEMP DEG F 425 423 400 400 398 13 N 2-159A RECIRC A LOOP FLOW KGPM 0 0 0 0 0 14 44 2-159B RECIRC B LOOP FLOW KGPM 0 0 0 0 0

15 9-5 7-46A APRM/IRM A % 0 0 0 0 0 16 45 7 46B APRM/lRM B % 0 0 0 0 0 17 9-5 7-46C APRM/lRM C % 0 0 0 0 0 18 9-5 7460 APRM/lRM D % 0 0 0 0 0 19 9-5 7-46E APRM/lRM E % 0 0 0 0 0 9-5 7-46F APRMllRM F % 0 0 0 0 0

 ~20                                                                                                   .300E+01 2'     9-5         7 43A    SRM A                      CPS    .300E+01 .300E+01 .300E+01 .300E+01 22     9-5         7-43B    SRM B                      CPS    .300E+01 .300E+01 .300E+01 .300E+01  .300E+01 '

23 9-5 7-43C SRM C CPS .300E+01 .300E+01 .300E+01 .300E+01 .300E+01 24 9-5 7-43D SRM D CPS .300E+01 .300E+01 .300E+01 .300E+01 .300E+01 ; 25 9-5 2-3-95 CORE FLOW MLB/HR 12 12 12 12 12 26 9-5 2-3-95 CORE DP PSID 3 3 3 3 3

27 45 F1-3-310 CRD FLOW GPM 47.1 47 47.1 47 47 28 9-5 6-96 WIDE RANGE PRESS PSIG 378 386 332 332 332 29 9-5 & 96 NAR RANGE PRESS PSIG DSL* DSL* DSL* DSL* DSL* 30 45 & 97 FEEDWATER FLOW MLB/HR 0 0.2 0 0 0 31 9-5 6 97 MAIN STEAM FLOW MLB/HR 0 0 0 0 0 32 9-5 4 98 NAR RANGE LEVEL INCHES 140 134 151- 147 147 33 9-5 6 98 WIDE RANGE LEVEL INCHES 175 168 189 182 182 34 46 Li-107 5 CST LEVEL % 41 41 42 41 41 35 M Lh102-5A HOTWELL LEVEL N % 82 79 68 66 66 36 &6 Li-102-5B HOTWELL LEVEL S % B2 79 68 66 66 37 9-7 PI-101-29 CONDENSER VACUUM IN HG 29.5 29.5 29.3 29.3 29.2 38 M D/G A BKR CLOSED CLOSED CLOSED CLOSED CLOSED 39 48 D/G B BKR CLOSED CLOSED CLOSED CLOSED CLOSED 40 9-23 1&19-33A/C TORUSTEMP DEG F 154 153 152 151 151 41 9 25 Lb46A TORUS LEVEL FEET 11.68 11.69 11.69 11.7 11.7 42 9-25 Li-468 TORUS LEVEL FEET 11.68 11.69 11.69 11.7 11.7 43 9 25 TR 1419-44 TORUS PRESS PSIA 16.2 15.9 15.6 15 6 15 5 44 9-25 TR 1419-44 DRYWELL PRESS PSIA 16 16 16 16 16 45 9-25 PR-1 1553 DW/ TORUS DP PSID 0.06 0.06 0.05 0.05 0.05 46 9-25 TR-1419 45 DRYWELL TEMP DEG F 172 175 177 177 177 47 9-26 PL1-125-3A RX BUILDING DP IN H2O -0 68 0.68 -0.68 -0.68 -0.68 48 9-26 P!-1-125-3B RX BUILDING DP IN H2O -0.68 -0.68 -068 -0.68 -0.68 49 4 26 Fbt-1251 A SGTS FLOW CFM 1500 1500 1500 1500 1500 50 4 26 F1-1 1251 B SGTS FLOW CFM 1500 1500 1500 1500 1500 51 CAD DW/ TORUS O2 CONC. % 0.86 0.84 0.83 0.83 0 82

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Rev. O VERMONT YANKEE NUCLEAR POWER STATION Page 9.1-1 EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 91 AREA RADIATION MONITORS 00 00 00.15 00:30 00 45 01-00 01:15 01:30 01:45 SCENARIO TIME 03 00 03.15 03.30 03 45 04 00 04-15 04 30 CLOCK TIME 02:45 ARM No PANEL BLDGIELV DESCRIPTION UNITS

                                                                                        <1     <1    <1    <1    <1          <1 RMS 11-1  9-11    RB/252   RX BLDG Hi RADS - N        RMR     <1             <1
                                                                                        <1     <1    <1    <1    <1          <1 RB/252   RX BLDG HI RADS - S         R!HR   <1             <1 RMS 11-2  9-11                                                                                               <1          <1
                                                                                 <1     <t     <1    <1    <1 RMS 11-3  9-11    RB/252   TIP RM Hi R AD              R/HR   <1 8      8     8     8     8           8 9-11     RB/232  SUPP CHAMB RB EXT CW       MR/HR    8              8 1

4 4 4 4 4 4 RB/252 N PERSONNEL RX BLDG MR/HR 4 4 2 9-11 03 03 03 03 03 9-11 RB/252 S EQUIP RR RX BLOG MRMR 03 03 03 3 5 5 5 5 MR/HR 5 5 5 5 4 9-11 RB/252 RX BLD NEUIRON TIP 520 520 MR/HR 520 520 520 520 520 520 5 9-11 RB/252 PERSONNEL HATCH RX B 8 8 8 8 8 8 8 8 6 9-11 RB/280 ELEV ENT R 2 SOFT RX MR/HR 12 12 12 12 12 12 9-11 RB/252 CRD REPAIR RX BLOG MR/HR 12 12 7 4 4 4 4 MR/HR 4 4 4 4 8 9-11 RB/303 ELEV ENTR 303FT RX 4 MR/HR 4 4 4 4 4 4 4 9 9-11 RB/303 H2O CLEANUP RX BLDG 7 MRIHR 7 7 7 7 7 7 7 10 9-11 RB/318 ELEV ENTR 318FT RX 5 5 MRMR 5 5 5 5 5 5 11 9-11 RB/318 H2O CLEANUP RX BLDG 4 4 4 4 4 4 4 4 12 9-11 RB/345 ELEV ENTR 348FT RX MRMR 5 5 5 5 5 5 5 9-11 RB/345 WEST REFUEL RX BLOG MR/HR 5 14 15 15 15 MR/HR 15 15 15 15 15 15 9-11 RB/345 SPENT FUEL POOL RX MRMR 05 05 05 05 05 05 05 05 18 9 11 RB/318 NEW FUEL VAULT RX B 1 1 1 1 1 17 9-11 RW/252 PUMP RM RADWASTE BL MR/HR 1 1 1 1 1 1 1 1 18 9-11 RW/252 RADW OPER AREA RW B MR!HR 1 1 1 1.5 1.5 1.5 1.5 1.5 1.5 RW/230 PUMP / TANK AREA RW B MR/HR 1.5 1.5 19 9-11 2 2 2 MR!HR 2 2 2 2 2 20 9-11 TB/248 N ACCESS 248FT TURB 200 MR/HR 200 200 200 200 200 200 200 21 9-11 TB!248 MAIN STM VALVE TURB 0 26 0 26 MR/HR 0 20 0 26 0 26 0 26 0 26 0 26 22 9-11 TB/232 COND DEMIN TURB BLD 0.17 MR!HR 0 17 0.17 0.17 0 17 0.17 0.17 0.17 23 9-11 TB/252 DECON' MACH SHOP TB 9 9 MR/HR 9 9 9 9 9 9 24 9-11 TB/272 TURB STM IN TURB BL 0 82 0 82 MR/HR 0 82 0 82 0 82 0.82 0.82 0 82 25 9-11 AB/272 VIEW GALLERY CONT RM 0 17 0 17 017 0.17 0.17 0 17 017 0.17 26 9-11 TB/252 REAR GATE TURB WAREH MR/HR 150 150 MRIHR 150 150 150 150 150 150 13 9-11 TB/228 MOIST SEP AREA TURB I l

VERMONT YANKEE NUCLEAR PCWER STATION Rev. 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 91-2 1993 91 AREA RAD!ATION MONITORS SCENARIO TIME 02.00 02:15 02.30 02.45 03.00 03.15 03.30 03 45 CLOCK TIME 04 45 05 00 0515 05-30 05 45 0600 06.15 06 30 ARMNo PANEL BLDG!ELV DESCRIPTION UNITS RMS 11-1 9-11 RB/252 RX BLDG H! RADS - N RMR <1 <1 <1 <1 <1 <1 <1 <1 RMS 11-2 9-11 RB/252 RX BLDG Hf RADS-S R/HR <1 <1 <1 <1 <1 <1 <1 <1 RMS 11-3 9-11 RB/252 TIP RM HI RAD R/HR <1 <1 <1 <1 <1 <1 <1 <1 1 9-11 RB/232 SUPP CHAMB RB EXT CW MRMR 8 8 8 8 8 8 8 8 2 9-11 RB/252 N PERSONNEL RX BLDG MR/HR 4 4 4 4 4 4 4 4 3 9-11 RB/252 S EQUIP RR RX BLOG MR/HR 0.3 03 03 03 03 03 03 03 4 9-11 RB/252 RX BLD NEUTRON TIP MR/HR 5 5 5 5 5 5 5 5 5 9-11 RB/252 PERSONNEL HATCH RX B MRMR 520 520 520 520 520 520 520 520 6 9-11 RB/2SO ELEV ENTR 280FT RX B MR/HR 8 8 8 8 8 8 8 8 7 9-11 RB/252 CRD REPAIR RX BLDG' MR/HR 12 12 12 12 12 12 12 12 8 9-11 RB/303 ELEV ENTR 333FT RX B MR/HR 4 4 4 4 4 4 4 4 9 9-11 RB/303 H2O CLEANUP RX BLDG MR!HR 4 4 4 4 4 4 4 4 10 9-11 RB/318 ELEV ENTR 318FT RX B MR/HR 7 7 7 7 7 7 7 7 11 9-11 RB/318 H2O CLEANUP RX BLDG MRMR 5 _ 5 5 5 5 5 5 5 12 9-11 RB/345 ELEV ENTR 348FT RX B MR/HR 4 4 4 4 4 4 4 4 14 9-11 RB/345 WEST REFUEL RX BLDG MR/HR 5 5 5 5 5 5 5 5 15 9-11 RB/345 SPENT FUEL POOL RX B MR/HR 15 15 15 15 15 15 15 15 18 9-11 RB/318 NEW FUEL VAULT RX B MR/HR 05 05 05 05 05 05 05 05 17 9-11 RW/252 PUMP RM RADWASTE BLD MR/HR 1 1 1 1 1 1 1 1 18 9 11 RWr252 RADW OPER AREA RW B MRMR 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 15 1.5 1.5 1.5 1.5 20 9-11 TB/248 N ACCESS 248FT TURB MR/HR 2 2 2 2 2 2 2 2 21 9-11 TB/248 MAIN STM VALVE TURB MR/HR 200 200 200 200 200 200 200 200 22 9-11 TB/232 COND DEMIN TURD BLOG MR/HR 0 26 0 26 0 26 0 26 0 26 0 26 0 26 0 26 23 9-11 TB/252 DECONTAM. TURB BLDG MR/HR O.17 0 17 0.17 0 17 0.17 0 17 0.17 0.17 24 9-11 TB!272 TURB STM IN TURB BLD MR/HR 9 9 9 9 9 9 9 9 25 9-11 AB,272 VIEW GALLERY CONT RM MR/HR 0 82 0 82 0 82 0 82 0.82 0 82 0.82 0 82 26 9-11 TBf252 REAR GATE TURB WAREH MR/HR 0 17 0 17 0 17 0 17 0 17 017 0 17 0 17 13 9-11 TB/228 MOIST SEP AREA TURB MR/HR 150 150 150 150 150 150 150 150

VERMONT YANKEE NUCLEAR POWER STATION Rev 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 9.1-3 1993 91 AREA RADIATION VONITORS SCENAR10 TIME 04 00 04 15 04 30 04 45 05 00 0515 05 30 C6 45 CLOCK TIME 06 45 07.00 0715 07 30 07.45 08 00 08.15 08 30 ARM No PANEL BLDGrELV DESCRIPTION UNITS RMS 11-1 9-11 RBC52 RX BLDG HI RADS - N RiHR <1 <1 <1 <1 <1 <1 <1 <1 RMS 11-2 9-11 RBCS 2 RX BLDG Hi RADS - S R!HR <1 <1 <1 <1 <1 <1 <1 <1 RMS !!-3 9-11 RBC52 TIP RM Hi RAD RIHR <1 <1 <1 <1 <1 <1 <1 <1 1 9-11 RB732 SUPP CHAMB RB EXT CW MR/HR 250 500 850 1500 5000 8500 OSH OSH 2 9-11 RBC52 N PERSONNEL RX BLDG MR/HR 0.3 03 40 90 120 140 165 175 3 9-11 RBCS 2 S EOUtP RR RX BLOG MR/HR 02 02 4 9 12 14 16 17 4 9-11 RBC52 RX BLD NEUTRON TIP MR/HR 5 5 43 95 120 150 168 189 5 9-11 RB/252 PERSONNEL HATCH RX B MR/HR 4000 5000 8000 OSH OSH OSH OSH OSH 6 9-11 RB/280 ELEV ENTR 280F T RX B MRtHR 5 5 5 5 5 5 5 5 7 9-11 RB/252 CRD REPAIR RX BLDG MR/HR 4 4 4 4 4 4 4 4 8 9-11 RB/303 ELEV ENTR 303FT RX B MR/HR 1 1 1 1 1 1 1 1 9 9-11 RB/303 H2O CLEANUP RX BLOG MR/HR 4 4 4 4 4 4 4 4 10 9-11 RB/318 ELEV ENTR 318FT RX B MR/HR 3 3 3 3 3 3 3 3 11 9-11 RBf318 H2O CLEANUP RX BLDG MR/HR 2 2 2 2 2 2 2 2 12 9 11 RBf345 ELEV ENTR 348FT RX B MRMR 1 1 1 1 1 1 1 1 14 9-11 RBG45 WEST REFUEL RX BLOG MaHR 1 1 1 1 1 1 1 1 15 9-11 RB/345 SPENT FUEL POOL RX B MRiHR 8 8 8 8 8 8 8 8 16 9-11 RB/318 NEW FUEL VAULT RX B MR/HR 05 03 03 03 03 0.3 0.3 03 17 9-11 RW/252 PUMP RM RADWASTE BLD MRMR 1 1 1 1 1 1 1 1 18 9-11 RW/252 RADW OPER AREA RW B MRMR 1 1 1 1 '. i 1 1 19 9-11 RW/230 PUMP / TANK AREA RW B MRiHR 1,5 1.6 1.6 16 1.6 1.6 1.6 1.6

    '20     9-11     TB/248  N ACCESS 248FT TURB        MR/HR    1.5      1.5       1.5     1.5   1.5          1.5      15          1.5 21     9-11     TB1248  MAIN STM VALVE TURB        MR/HR     4        4         4       4      4           4        4           4 22     9-11     TB/232  COND DEMIN TURB BLDG       MRMR    0 12     0 12     0 12     012   0 12         0 12    0 12         012 23     9-11     TB/252  DECONTAM. TURB BLDG        MRiHR   015      015      0.15    0 15   0.15         0 15     0.15        0 15 24     9-11     TB1272  TURB STM IN TURB BLD       MRMR      7        7         7       7      7           7        7           7 25     9 11     AB/272  VIEW GALLERY CONT RM       MRNR    O.11     0.11     0.11     0 11 0.11          0.11     0.11        0.11 26     9-11     TB/252  REAR GATE TURB WAREH MR/HR         0 01     0 01     0 01    0 01   0 01         0 01     0 01        0 01 13    9-11     TB/228  MOIST SEP AREA TURB        MR/HR    1.1      1.1       1.1     1.1    1.1         1.1      1.1         1.1

VERMONT YANKEE NUCLEAR POWER STATION Rev 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 91-4 1993 91 AREA RADIATION MONITORS SCENARIO TIME 06 00 0615 06 30 06 45 07.00 07.15 07.30 07.45 CLOCK TIME 08 45 09 00 09 15 09 30 09 45 1000 1015 10 30 ARM No. PANEL BLOG/ELV DESCRIPTION UNITS RMS 11-1 9-11 RB/252 RX BLDG Hi RADS- N RMR <1 <1 <1 <1 <1 <1 <1 <1 RMS H-2 9-11 RB/252 RX BLDG HI RADS - S RMR <1 1 10 25 25 25 25 25 RMS 11-3 9-11 RB/252 TIP RM HI RAD R1HR c1 <1 <1 <1 <1 <1 <1 <1 1 9-11 RB/232 SUPP CHAMB RB EXT CW MRMR OSH OSH OSH OSH OSH OSH OSH OSH 2 9-11 RB/252 N PERSONNEL RX BLDG MR/HR 175 175 175 175 175 180 185 185 3 9-11 RB/252 S EQUIP RR RX BLDG MRMR 17 200 2000 5000 5000 5000 5000 5000 4 9-11 RB/252 RX BLD NEUTRON TIP MR/HR 180 180 180 180 180 185 190 190 5 9-11 RB/252 PERSONNEL HATCH RX B MRMR OSH OSH OSH OSH OSH OSH OSH OSH 6 9-11 RB/200 ELEV ENTR 280FT RX B MRlHR 5 5 5 5 5 5 5 5 7 9-11 RB/252 CRD REPATR RX BLDG MR/HR 4 4 4 4 4 4 4 4 8 9-11 RB/303 ELEV ENTR 303FT RX B MR/HR 1 1 1 1 1 1 1 1 9 9-11 RB/303 H2O CLEANUP RX BLDG MR/HR 4 4 4 4 4 4 4 4 10 9-11 RB/318 ELEV ENTR 318FT RX B MR/HR 3 3 3 3 3 3 3 3 11 9-11 RB/318 H2O CLEANUP RX BLOG MR/HR 2 2 2 2 2 2 2 2 12 9-11 RB/345 ELEV ENTR 348FT RX B MR/HR 1 1 1 1 1 1 1 1 14 9-11 RB/345 WEST REFUEL RX BLDG MR/HR 1 1 1 1 1 1 1 1 15 9-11 RB/345 SPENT FUEL POOL RX B MRMR 8 8 8 2 6 8 8 8 16 9-11 RB/318 NEW FUEL VAULT RX B MRMR 03 0.3 0.3 03 0.3 03 0.3 0.3 17 9-11 RW/252 PUMP RM RADWASTE BLD MR/HR 1 1 1 1 1 1 1 1 18 9-11 RW/252 RADW OPER AREA RW B MRMR 1 1 1 1 1 1 1 1 19 9-11 RW/230 PUMP / TANK AREA RW B MR/HR 1.6 1.6 1.6 16 1.6 1.6 1.6 1.6 20 9-11 TBr248 N ACCESS 248FT TURB MRMR 1.5 15 1.5 1S 15 1.5 1.5 15 21 9-11 TB/248 MAIN STM VALVE TURB MRMR 4 4 4 4 4 4 4 4 22 9-11 TB/232 COND DEMIN TURB BLDG MRMR 012 0 12 012 0 12 0 12 0.12 012 0.12 23 9-11 TB/252 DECONTAM. TURB BLDG MR/HR 0.15 0.15 0.15 0.15 0 15 0,15 0.15 0.15 24 9-11 TBr272 TURB STM IN TURB BLD MRMR 7 7 7 7 7 7 7 7 25 9-11 AB/272 VIEW GALLERY CONT RM MR/HR 0 11 0 11 0.11 0 11 0.11 0.11 0.11 0.11 26 9-11 TB/252 REAR GATE TURB WAREH MR/HR 0 01 0 01 0 01 0 01 0 01 0 01 0.01 0 01 13 9-11 TB/228 MOIST SEP AREA TURB MR/HR 1.1 1.1 1.1 1.1 1.1 1.1 1.1 1.1

VERMONT YANKEE NUCLEAR POWER STATION Rev. O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 91-5 1993 9.1 AREA RADIATION MONITORS SCENARIO TIME 08 00 0815 08 30 08 45 09 00 09.15 09 30 09 45 CLOCK TIME 10 45 11 00 11 15 11:30 11 45 12:00 12:15 12 30 ARM No PANEL BLDG /ELV DESCR!PTION UNITS RMS 11-1 9-11 RB/252 RX BLOG Hi RADS - N R/HR <1 <1 <1 <1 <1 <1 <1 <1 RMS !!-2 9-1 RBr252 RX BLDG Hf RADS-S RMR 10 1 <1 <1 <1 <1 <1 ' <1 RMS 11-3 9-1 ) RB/252 TIP RM HI RAD R/HR <1 <1 <1 <1 <1 <1 <1 <1 1 9-11 RB/232 SUPP CHAMB RB EXT CW MRMR OSH OSH OSH OSH OSH OSH OSH OSH 2 9-11 RB/252 N PERSONNEL RX BLDG MR/HR 185 185 185 185 185 185 185 185 3 9-11 RB1252 S EQUfP RR RX BLDG MR/HR 2000 200 200 200 200 200 200 200 4 9-11 RB/252 RX BLD NEUTRON TIP MR/HR 190 190- 190 190 190 190 190 190-5 9-11 RB/252 PERSONNEL HATCH RX B MR/HR OSH OSH OSH OSH OSH OSH OSH OSH 6 9-11 RB/280 ELEV ENTR 200FT RX B MRMR 5 5 5 5 5 5 5 5 7 9-11 RB/252 CRD REPAIR RX BLDG MR/HR 4 4 4 4 4 4 4 4 8 9-11 . RB/303 ELEV ENTR 303FT RX B MR/HR 1 1 1 1 1 1 1 1 9 9-11 RB/303 H2O CLEANUP RX BLOG MRMR 4 4 4 4 4 4 4 4 10 9-11 RB/318 ELEV ENTR 318FT RX B MR/HR 3 3 3 3 3 3 3 3 11 9-11 RB!318 H2O CLEANUP RX BLDG MRMR 2 2 2 2 2 2 2 2 12 9-11 RB/345 ELEV ENTR 348FT RX B MR/HR 1 1 1 1 1 1 1 1 14 9-11 RB/345 WEST REFUEL RX BLDG MRMR 1 1 1 1 1 1 1 1 15 9-11 RB/345 SPENT FUEL POOL RX B MRMR 8 8 8 8 8 8 8 8 18 9-11 RB/318 NEW FUEL VAULT RX B MRMR 0.3 03 03 03 03 0.3 03 03 17 9-11 RW/252 PUMP RM RADWASTE BLD MR/HR 1 1 1 1 1 1 1 1 18 9-11 RW/252 RADW OPER AREA RW B MRMR 1 1 1 1 1 1 1 1 19 9-11 RW/230 PUMP / TANK AREA RW B MR/HR 1.6 1.6 1.6 1.6 1.6 1.6 1.6 1.6 20 9-11 TB/248 N ACCESS 248FT TURB MRMR 1.5 1.5 1.5 15 1.5 15 1.5 15 21 9-11 TB/248 MAIN STM VALVE TURB MR/HR 4 4 4 4 4 4 4 4 22 9-11 TB!232 COND DEM!N TURB BLOG MR/HR 0 12 0 12 0 12 0 12 0.12 0 12 012 0 12 23 9-11 TB/252 DECONTAM. TURB BLDG MR/HR 0.15 0.15 0.15 0 15 0.15 015 0.15 0.15 24 9-11 TB/272 TURB STM IN TURB BLD MR/HR 7 7 7 7 7 7 7 7 25 9-11 AB/272 VIEW GALLERY CONT RM MR/HR 0 11 0 11 0.11 0.11 0.11 0.11 0 11 0.11 26 9-11 TB/252 REAR GATE TURB WAREH MRMR 0 01 0 01 0 01 0 01 0 01 0 01 0 01 0 01 13 9-11 TB/228 MOIST SEP AREA TURB MR/HR 1.1 1.1 1.1 1.1 1.1 1.1 1.1 1.1

S i VERMONT YANKEE NUCLEAR. POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 -l 9.2 PROCESS MONITORS ! p 4

VERMONT YANKEE NUCLEAR POWER STATION Rev.O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 92-1 1993 92 PROCESS MONtTORS SCENARIO TIME 00.00 0015 00'30 00 45 01:00 01:15 01:30 01:45 , CLOCK TIME 02 45 03 00 03 15 03 30 03 45 04 00 04-15 04 30 ARM NO. PANEL BLOG/ELV DESCRIPTION UNITS 9-2 ST/257 STACK GAS MON-GAS 1 CPM 20 20 20 20 20 20 20 20 9-2 ST/257 STACK GAS MON-GAS 2 CPM 20 20 20 20 20 20 20 20 9-2 RB/200 CONTAINMENT MON GAS CPM 535 535 535 535 535 535 535 535 9-2 RB/280 CONTAINMENT MON-PART CPM 24981 24981 24981 24981 24981 24961 24961 24981 9-2 ST/257 STACK HI RANGE MR/HR 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 27 9-2 DW/252 DRYWELL CH A R!HR 36 36 36 36 36 36 36 36 28 9-2 DW/252 DRYWELL CH B R/HR 36 3.6 3.6 3,6 3.6 3.6 36 36 9-2 RB/200 RX BLOG VENT GAS CPM 185 185 185 185 185 185 185 185 9-2 RB/200 RX BLDG VENT PART CPM 1478 1478 1478 1478 1478 1478 1478 1478 31 9-10 RB/200 RX BLDG VENT NORTH MRMR 1.7 1.7 1.7 1.7 1.7 1.7 1.7 1.7 32 9-10 RB/280 RX BLDG VENT SOUTH MR/HR 1.7 1.7 1.7 1.7 1.7 1.7 1.7 1.7 453A 9-10 RB/345 SPENT FUEL POOL A MR/HR 16 16 16 16 16 16 16 16 4538 9-10 RB/345 SPENT FUEL POOL B MRIHR 16 16 16 16 16 16 16 16 9-10 RB/256 MAIN STM LINE A MR!HR 172 172 172 172 172 172 172 172 9-10 RB/256 MAIN STM LINE B MR!HR 166 106 166 166 166 166 166 166 9-10 RBf256 MAIN STM LINE C MR/HR 168 168 168 168 168 168 168 168 9-10 RB/256 MAIN STM LINE D MR/HR 175 175 175 175 175 175 175 175

 -     38   9-10    TB/248 SJAE(AIR EJECTOR)             MRMR      61        61     61       61    61       61           61       61
                 . NOTE:    OSH = Offscale High -

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VERMONT YANKEE NUCLEAR POWER STATION Rev O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 9 2-2 1993 9 2 PROCESS MON! TORS SCENARIO TIME 02 00 02.15 02.30 02:45 0100 03:15 03:30 03 45 CLOCK TIME 04 45 05 00 05 15 05 30 05-45 06 00 06:15 0630 ARM NO. PANEL BLDG /ELV DESCRIPTION UNITS 9-2 ST/257 STACK GAS MON-GAS 1 CPM 20 20 20 20 20 20 20 20 9-2 ST/257 STACK GAS MON-GAS 2 CPM 20 20 20 20 20 20 20 20 9-2 RB/280 CONTAINMENT MON GAS CPM 535 535 535 535 535 535 535 535 9-2 RBr280 CONTAINMENT MON-PART CPM 24981 24981 24981 24981 24981 24981 24981 24959 9-2 ST/257 STACKHIRANGE MR/HR 0.1 0.1 0.1 0.1 0.1 0.1 0.1 01 27 9-2 DW/252 DRYWELL CH A R/HR 36 36 36 36 36 36 36 36 28 9-2 DW/252 DRYWELL CH B R/HR 36 3.6 36 36 3.6 36 3.6 3.6 9-2 RB/280 RX BLOG VENT GAS CPM 185 185 185 185 185 185 185 185 9-2 RB/280 RX BLDG VENT - PART CPM 1478 1478 1478 1478 1478 1478 1478 1480 31 9-10 RB/280 RX BLOG VENT NORTH MR/HR 1.7 1.7 1.7 1.7 1.7 1.7 1.7 17 RB/200 RX BLOG VENT SOUTH MR/HR 1.7 1.7 1.7 1.7 1.7 1.7 1.7 1,7 32 9-10 453A 9-10 RB/345 SPENT FUEL POOL A MR/HR 16 16 16 16 16 16 16 16 453B 9-10 RB!345 SPENT FUEL POOL B MR/HR 16 16 16 16 16 16 16 16 9-10 RBf256 MAIN STM LINE A MR/HR 172 172 172 172 172 172 172 172 9-10 RB/256 MAIN STM LINE B MR/HR 166 166 166 166 166 166 166 166 9-10 RB/256 MAIN STM LINE C MR!HR 168 168 168 168 168 168 168 168 9-10 RB/256 MAIN STM LINE D MR/HR 175 175 175 175 175 175 175 175 38 9-10 TB/248 SJAE(AIR EJECTOR) MR/HR 61 61 61 61 61 61 61 61 NOTE: OSH = Offscale High

VERMONT YANKEE NUCLEAR POWER STATION Rev 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 9.2-3 1993 9 2 PROCESS MONITORS SCENARIO TIME 04 00 04 15 04.30 04 45 05-00 05:15 05:30 05 45 CLOCK TIME 06 45 07-00 07:15 07:30 07:45 0800 08:15 08 30 ARM NO PANEL BLDGELV DESCRIPTION UNITS 9-2 ST/257 STACK GAS MON-GAS 1 CPM 20 20 20 20 20 20 20 20 9-2 STC57 STACK GAS MO4 GAS 2 CPM 20 20 20 20 20 20 20 20 9-2 RS/200 CONT AINMENT MON GAS CPM OSH OSH OSH OSH OSH OSH OSH OSH 92 RB/200 CONTAINMENT MON-PART CPM OSH OSH OSH OSH OSH OSH OSH OSH MR/HR 01 0.1 0.1 0.1 0.1 0.1 0.1 0,1 9-2 ST/257 STACK HI RANGE 27 9-2 DW/252 DRYWELL CH A R/HR 28 36 56 92 115 140 100 170 28 9-2 DW/252 DRYWELL CH B R!HR 28 36 56 92 115 140 160 170 9-2 R5/280 RX BLDG VENT GAS CPM 25 25 29 34 37 40 42 43 9-2 RD/200 RX BLDG VENT - PART CPM 197 198 230 275 290 317 333 342 31 9 10 RB/200 RX BLDG VENT NORTH MR/HR 04 04 0.4 05 05 05 05 05 32 9-10 RB/200 RX BLDG VENT SOUTH MR/HR 0.4 OM 0.4 05 0.5 0.5 0.5 05 453A 9-10 RB/345 SPENT FUEL POOL A MR/HR 3.5 35 35 35 35 35 35 35 4538 9-10 RB/345 SPENT FUEL POOL B MR/HR 3.5 3.5 35 3.5 3.5 3.5 3.5 3.5 9-10 RBC56 MAIN STM LINE A MR/HR 1 1 1 1 1 1 1 1 9-10 RB/256 MAIN STM UNE B MR/HR 1 1 1 1 1 1 1 1 9.10 RB/256 MAIN STM UNE C MR/HR 1- 1 1 1 1 1 1 1 9-10 RB/256 MAIN STM UNE D MR/HR 1 1 1 1 1 1 1 1 38 9 10 TBr248 SJAE(AIR EJECTOR) MR/HR 0 0 0 0 0 0 0 0 NOTE: ORH = Offscale High q y -

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VERMONT YANKEE NUCLEAR POWER STATION Rev 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 9 2-4 1993 9 2 PROCESS MONITORS SCENARIO T!ME 0G00 06 15 06 30 06 45 07.00 07:15 07:30 07-45 . CLOCK TIME 08 45 09 00 09.15 09-30 09-45 10-00 10r15 10 30 ARM NO_ PANEL BLOGELV DESCRIPTION UNITS 9-2 ST/257 ST ACK GAS MON-GAS 1 CPM 20 100000 OSH OSH OSH OSH OSH OSH 9-2 ST/257 STACK GAS MONGS 2 CPM 20 100000 OSH OSH OSH OSH OSH OSH 9-2 RB/200 CONTAINMENT MON GAS CPM OSH OSH OSH OSH OSH OSH OSH OSH 9-2 RB/280 CONTAINMENT MON-PART CPM OSH OSH OSH OSH OSH OSH OSH OSH 9-2 ST/257 STACK Hi RANGE MR/HR 0.1 5 470 450 450 450 440 440 9-2 DW/252 DRYWELL CH A R/HR 170 170 170 170 170 170 170 170 27 28 9-2 DW/252 DRYWELL CH B R/HR 170 170 170 170 170 170 170 170 9-2 RB/280 RX BLDG VENT GAS CPM 44 44 44 44 44 44 44 44 9-2 - RB/280 RX BLDG VENT - PART CPM 350 350 350 350 350 350 350 350 31 9-10 RB/200 RX BLDG VENT NORTH MR/HR 05 100 1000 OSH OSH OSH OSH OSH 32 9-10 RS/280 RX BLOG VENT SOUTH MR/HR 05 100 1000 OSH OSH OSH OSH OSH 453A G-10 RB/345 SPENT FUEL POOL A MR/HR 35 35 35 35 35 35 3.5 35 4538 9-10 RB/345 SPENT FUEL POOL B MR/HR 3.5 35 35 3.5 3.5 3.5 3.5 3.5 9-10 RB/256 MAIN STM LINE A MRMR 1 1 1 1 1 1 1 1 9-10 RB/256 MAIN STM LINE B MR/HR 1 1 1 1 1 1 1 1 9-10 RB/256 MAIN STM LINE C MRMR 1 1 1 1 1 1 1 1 9-10 RB/256 MAIN STM LINE D MR!HR 1 1 1 1 1 1 1 1 38 9-10 TB/248 SJAE(AIR EJECTOR) MR/HR 0 0 0 0 0 0 0 0 NOTE: OSH = Offscale High m - 2 _ _ _ _ _ _ _ _ . - _ _ _ _ - _ . . ___-m. _ _ . _ _ _______. _ _ _ .

VERMONT YANKEE NUCLEAR POWER STATION Res O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 9.2-5 1993 9.2 PROCESS MONITORS SCENARIO TIME 0800 08.15 08 30 08-45 09 00 0915 09.30 09 45 CLOCK TIME 10 45 11-00 11:15 11:30 11:45 12:00 12:15 12:30 ARM NO PANEL BLOG/ELV DESCRIPTION UN!TS 9-2 ST/257 STACK GAS MON-GAS 1 CPM OSH 100000 30000 20 20 20 20 20 9-2 ST/257 STACK GAS MONGS 2 CPM OSH 100000 30000 20 20 20 20 20 9-2 RB/200 CONTAINMENT MON GAS CPM OSH OSH OSH OSH OSH OSH OSH OSH 9-2 RB/280 CONTAINMENT MON PART CPM OSH OSH OSH OSH OSH OSH OSH OSH , 9-2 ST/257 STACK HI RANGE MR/HR 420 4 1 0.1 0.1 0.1 01 0.1 27 9-2 DW/252 DRYWELL CH A R!HR 170 170 170 170 170 170 170 170 28 9-2 DW/252 DRW/ ELL CH B R/HR 170 170 170 170 170 170 170 170 9-2 RB/280 RX BLDG VENT GAS CPM 44 44 44 44 44 44 44 44 9-2 RS/200 RX BLDG VENT - PART CPM 350 350 350 350 350 350 350 350 31 9-10 RB/280 RX BLDG VENT NORTH MR/HR 1000 100 10 10 10 10 to 10 32 9-10 RB/200 RX BLDG VENT SOUTH MR/HR 1000 100 10 10 10 to 10 10 453A 9-10 RB/345 SPENT FUEL POOL A MR/HR 34 34 34 34 34 34 34 34 4538 9-10 RB/345 SPENT FUEL POOL B MR/HR 34 3_4 34 34 34 3.4 3.4 34 9-10 RB/256 MAIN STM LINE A MRMR 1 1 1 1 1 1 1 1 9-10 RB/256 MAIN STM UNE B MR/HR 1 1 1 1 1 1 1 1 9-10 RB/256 MAIN STM LINE C MR/HR 1 1 1 1 1 1 1 1 '. 9-10 RB/256 MAIN STM LINE D MR/HR 1 1 1 1 1 1 1 1 38 9 10 TB/248 SJAE(AIR EJECTOR) MRMR 0 0 0 0 0 0 0 0 r l - I ____._m.__ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _____ _ ___..__ _ _ . _ __ - ._ . . _ , .. . , - , . . - -

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TABLE 9.3-1 Rev. O Page 9.3-la Reactor Building Refuel Deck, Elevation 345' (mR/hr unless otherwise noted) Clock Scenario Time Time ARM 12 ARM 14 ARM 15 453 A 453 B Zone I Zone II Zone III Zone IV 0245 0:00 4 5 15 16 16 5 16 16 16 0630 3:45 4 5 15 16 16 5 16 16 16 4:00 1 1 8 4 4 1 4 4 4 0645 0700 4:15 1 1 8 4 4 1 4 4 4 4:30 1 1 8 4 4 1 4 4 4 0715 4 0730 4:45 1 1 8 4 4 1 4 4 5:00 1 1 8 4 4 1 4 4 4 0745 5:15 1 1 8 4 4 1 4 4 4 0800 5:30 1 1 8 4 4 1 4 4 4 0815 5:45 1 1 8 4 4 1 4 4 4 0830 6:00 1 1 8 4 4 1 4 4 4 0845 4 0900 6:15 1 1 8 4 4 1 4 4 6:30 1 1 8 4 4 1 4 4 4 0915 6:45 1 1 8 4 4 1 4 4 4 0930 7:00 1 1 8 4 4 1 4 4 4 0945 7:15 1 1 8 4 4 1 4 4 4 1000 1 8 4 4 1 4 4 4 1015 7:30 1 4 4 1030 7:45 1 1 8 4 4 1 4 8:00 1 1 8 4 4 1 4 4 4 1045 8:15 1 1 8 4 4 1 4 4 4 1100 4 1 8 4 4 1 4 4 1115 8:30 1 4 4 1130 8:45 1 1 8 4 4 1 4 1 1 8 4 4 1 4 4 4 1145 9:00 1 1 8 4 4 1 4 4 4 1200 9:15 1 8 4 4 1 4 4 4 1215 9:30 1 4 4 4 1230 9:45 1 1 8 4 4 1 Notes: Zone readings are average dose rates throughout zone. General area contamination levels 2K-5K dpm/100 cm2 in all zones.

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TABLE 9.3-2 Rev. O ' Reactor Building, Elevation 318' Page 9.3-2a (mR/hr unless otherwise noted) Clock Scenario Time Time ARM 10 ARM 11 ARM 16 Zone I Zone II Zone III Zone IV Zone V Zone VI Zone VII 0245 0:00 7 5 .5 7 5 300 5 80 .5 .5 0630 3:45 7 5 .5 7 5 300 5 80 .5 .5 0645 4:00 3 2 .5 3 2 200 2 60 .5 .5 0700 4:15 3 2 .3 3 2 100 2 60 .3 .3 0715 4:30 3 2 .3 3 2 100 2 60 .3 .3 0730 4:45 3 2 .3 3 2 100 2 60 .3 .3 0745 5:00 3 2 .3 3 2 100 2 60 .3 .3 0800 5:15 3 2 .3 3 2 100 2 60 .3 .3 0815 5:30 3 2 .3 3 2 100 2 60 .3 .3 , 0830 5:45 3 2 .3 3 2 100 2 60 .3 .3

0845 6:00 3 2 .3 3 2 100 2 60 .3 .3 0900 6:15 3 2 .3 3 2 100 2 60 .3 .3-0915 6:30 3 2 .3 3 2 100 2 60 .3 .3 0930 6:45 3 2 .3 3 2 100 2 60 .3 .3 0945 7:00 3 2 .3- 3 2 100 2 60 .3 .3 1000 7:15 3 2 .3 3 2 100 2 60 .3 .3 1015 7:30 3 2 .3 3 2 100 2 60 .3 .3 1030 7:45 3 2 .3 3 2 100 2 60 .3 .3 1045 8:00 3 2 .3 3 2 100 2 60 .3 .3 1100 8:15 3 2 .3 3 2 100 2 60 .3 .3 1115 8:30 3 2 .3 3 2 100 2 60 .3 .3 1130 8:45 3 2 .3 3 2 100 2 60 .3 .3 1145 9:00 3 2 .3 3 2 100 2 60' .3 .3 1200 9:15 3 2 .3 3 2 100 2 60 .3 .3 1215 9:30 3 2 .3 3 2 100 2 60 .3 .3 1230 9:45 3 2 .3 3 2 100 2 60 .3 .3 Notes: Zone readings are average dose rates throughout zone.

General area contamination levels 1K-5K dpm/100 cm2 in all zones.

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TABLE 9.3-3 Rev. O Reactor Building, Elevation 303' Page 9.3-3a (mR/hr unless otherwise noted) Clock Scenario Time Time ARM 8 ARM 9 Zone I Zone II Zone III Zone IV Zone V Zone VI Zone VII 0245 0:00 4 4 4 3 600 3 60 0.1 0.2 0630 3:45 4 4 4 3 600 3 60 0.1 0.2 0645 4:00 1 4 4 3 800 3 80 0.1 0.2 . 0700 4:15 1 4 4 3 850 3 80 0.1 0.2 0715 4:30 1 4 4 3 900 3 80 0.1 0.2 0730 4:45 1 4 4 3 950 3 80 0.1 0.2 0745 5:00 1 4 4 3 1000 3 80 0.1 0.2 0800 5:15 1 4 4 3 1100 3 80 0.1 0.2 0815 5:30 1 4 4 3 1200 3 80 0.1 0.2 0830 5:45 1 4 4 3 1200 3 30 0.1 0.2 0845 6:00 1 4 4 3 1200 3 80 0.1 0.2 0900 6:15 1 4 4 3 1200 3 80 0.1 0.2 0915 6:30 1 4 4 3 1200 3 80 0.1 0.2 0930 6:45 1 4 4 3 1200 3 80 0.1 0.2 0945 7:00 1 4 4 3 1200 3 80 0.1 0.2 1000 7:15 1 4 4 3 1200 3 80 0.1 0.2 1015 7:30 1 4 4 3 1200 3 80 0.1 0.2 ; 1030 7:45 1 4 4 3 1200 3 80 0.1 0.2 1045 8:00 1 4 4 3 1200 3 80 0.1 0.2 1100 8:15 1 4 4 3 1200 3 80 0.1 0.2 1115 8:30 1 4 4 3 1200 3 80 0.1 0.2 1130 8:45 1 4 4 3 1200 3 80 0.1 0.2 1145 9:00 1 4 4 3 1200 3 80 0.1 0.2 1200 9:15 1 4 4 3 1200 3 80 0.1 0.2 1215 9:30 1 4 4 3 1200 3 80 0.1 0.2 1230 9:45 1 4 4 3 1200 3- 80 0.1 0.2 Notes: Zone readings are average dose rates throughout zone. General area contamination levels 1K-5K dpm/100 cm2 in all zones. I _ . _ . _ _ . _ _ . _ . . _ _ . _ . _ _ . _ _ _ _ _ _ _ . _ _ _ _ . _ r. .i . _ . _ ,w . v ,

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TABLE 9.3-4 Rev. O Reactor Building, Elevation 280' (mR/hr unless otherwise noted) RL Vent RB Vent Clock Scenario North South Zone Zone Zone Zone Zone Zone Zone Zone Time Time ARM 6 ARM 31 ARM 32 I II III IV V VI VII VIII 0245 9:00 8 2 2 8 29 9 7 3 1 2 8 0630 3:45 8 2 2 8 20 9 7 3 1 2 8 0645 4:00 5 2 2 8 20 8 7 2 1 2 8 0700 4:15 5 2 2 7 20 8 7 2 1 2 7 0715 4:30 5 1 1 7 20 8 1 2 1 1 7 0730 4:45 5 1 1 5 20 8 5 2 1 1 5 0745 5:00 5 1 1 5 20 8 5 2 1 1 5 0800 5:15 5 1 1 5 20 8 5 2 1 1 5 0815 5:30 5 1 1 5 20 8 5 2 1 1 5 0830 5:45 5 1 1 5 20 8 5 2 1 1 5 0845 6:00 5 1 1 5 15 8 5 2 1 1 5 0900 6:15 5 100 100 5 15 8 5 2 1 50 5 0915 6:30 5 1000 1000 5 15 e 5 2 1 500 5 0930 6:45 5 (OSH)>1E4(OSH)>1E4 5 15 8 3 2 1 5000 5 0945 7:00 5- (OSH) (OSH) 5 15 8 5 2 1 5000 5 1000 7:15 5 (OSU) (OSH) 5 15 8 5 2 1 5000 5 1015 7:30 5 (OSH) (OSH) 5 15 8 5 2 1 5000 5 1030 7:45 5 (OSH) (OSH) 5- 15 8 5 2 1 5000 5 1045 8:00 5 1000 1000 5 15 8 5 2 1 500 5 1100 8:15 5 100 100 5 15 8 5 2 1 50 5 1115 8:30 5 10 10 5 15 8 5 2 1 5 5 1130 8:45 5 10 10 5 15 8 5 2 1 5 5 1145 9: 00 5 10 10 5 15 8 5 2 1 5 5 1200 9:15 5 10 10 5 15 8 5 2 1 5 5 1215 9:30 5 10 10 5 15 8 5 2 1 5 5 10 5 15 8 5 2 1 5 ; 1230 9:45 5 10 Notes: Zone readings are average dose rates throughout zone. General area contamination levels 1K-2K dpm/100 cm2 in all zones.

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TABLE 9.3-5 Rev. O Reactor Building, Elevation 252' Page 9.3-Sa.1 (mR/hr unless otherwise noted) Clock Scenario RM- Zone Zone Zone Zone Zone Zone Zone Time Time ARM 2 ARM 3 ARM 4 ARMS ARM 7 14-29 I II III IV V VI VII 0245 0:00 4 .3 5 520 12 100 5 4 .3 50 .3 12 24 0630 3:45 4 .3 5 520 12 100 5 4 .3 50 .3 12 24 5 4000 4 100 5 .3 .2 40 .2 4 8 0645 4:00 .3 .2 0700 4:15 .3 .2 5 5000 4 100 5 .3 .2 50 .2 4 8 0715 4:30 40 4 45 8000 4 100 43 40 4 780 4 4 8 0730 4:45 90 9 95 (OSH)>1E4 4 100 95 90 9 1300 9 4 8 0745 5:00 120 12 120 (OSH) 4 100 120 120 12 1600 12 4 8 0300 5:15 140 14 150 (OSH) 4 100 150 140 14 2000 14 4 8 0815 5:30 165 16 168 (OSH) 4 100 168 165 16 2300 16 4 8 0830 5:45 175 17 180 (OSH) 4 100 180 175 17 2400 17 4 8 0845 6:00 175 17 180 (OSH) 4 100 180 175 17 2400 17 4 8 0900 6:15 175 200 180 (OSH) 4 100 180 175 200 2400 1000 4 8 0915 6:30 175 2000 180 (OSH) 4 100 180 175 2000 2400 10000 4 8 175 5000 180 (OSH) 4 100 180 175 5000 2400 25000 4 8 0930 6:45 175 5000 180 (OSH) 4 100 180 175 5000 2400 25000 4 8 0945 7:00 8 1000 7:15 180 5000 185 (OSH) 4 100 185 180 5000 2400 25000 4 1015 7:30 185 5000 190 (OSH) 4 100 190 185 5000 2400 25000 4 8 185 5000 190 4 100 190 -185 5000 2400 25000 4 8 1030 7:45 (OSH) 185 2000 190 4 100 190 185 2000 2400 10000 4 8 1045 8:00 (OSH) 185 200 190 4 100 190' 185 200 2400 1000 4 8 1100 8:15 (OSH)- 185 200 190 4 100 190 185 200 2400 500 4 8 1115 8:30 (OSH) 185 200 190 4 100 190- 185 200 2400 500 4 8 1130 8:45 (OSH) 185 200 190 (OSH) 4 100 190 185 200 2400 500 4 8 1145 9:00 1200 9:15 185 200 190 (OSH) 4 100 190 185 200 2400 500 4 8 1215 9:30 185 200 190- (OSH) 4 100 190 185 200 2400 500 4 8 1230 9:45 185 200 190 (OSH) 4 100 190 185 200 2400 500 4 8 Notes: Zone readings are average dose rates throughout zone. General area contamination levels 1K-2K dpm/100 cm2 in all zones.

Rev. O Page 9.3-Sa.2 TABLE 9.3-5 (Continued) (mR/hr unless otherwise noted) Clock Scenario NORTH ** SOUTH ** TIP ** RHR A RHR B RCIC HPCI Time Time RMS II-1 RMS II-2 RMS II-3 QUAD QUAD QUAD QUAD 0245 0:00 <1.0 <1.0 <1.0 5 5 50 50 0630 3:45 <1.0 <1.0 <1.0 5 5 50 50 0645 4:00 <1.0 <1.0 <1.0 5 5 50 50 0700 4:15 <1.0 <1.0 <1.0 5 5 50 50 0715 4:30 <1.0 <1.0 <1.0 40 40 500 500 0730 4:45 <1.0 <1.0 <1.0 100 100 1000 1000 0745 5:00 <1.0 <1.0 <1.0 120 120 2400 2400 0800 5:15 <1.0 <1.0 <1.0 150 150 3000 3000 0815 5:30 <1.0 <1.0 <1.0 168 168 3500 3500 0830 5:45 <1.0 <l.0 <1.0 180 180 3600 3600 0845 6:00 <1.0 <l.0 <1.0 180 180 3600 3600 i 0900 6:15 <1.0 1.0 <1.0 180 180 3600 3600 0915 6:30 <1.0 10.0 <1.0 .180 180 3600 3600 0930 6:45 <1.0 25.0 <1.0 180 180 3600 3600 0945 7:00 <1.0 25.0 <1.0 180 180 3600 3600 1000 7:15 <1.0 25.0 <1.0 185 185 3800 3800 1015 7:30 <l.0 25.0 <1.0 190 190 3800 3800 1030 7:45 <1.0 25.0 <l.0 190 190 3800 3800

                                                                    <1.0          10.0        <1.0      190         190       3800         3800 1045    8:00 3800 1100    8:15                 <1.0          1.0        <1.0      190         190        3800 8:30                 <1.0        <1.0         <1.0      190         190        3800        3800 1115                                                                                               3800 1130    8:45                 <1.0         <1.0        <1.0      190         190        3800 1145   9:00                 <1.0         <1.0        <1.0      190         190        3800        3800 1200   9:15                  <1.0        <1.0        <1.0      190         190        3800        3800
                                                                     <1.0         <1.0        <1.0      190         190        3800        3800 1215   9:30 1230   9:45                  <l.0        <1.0        <1.0      190         190        3800-       3800 Notes:
                                         **   RMS II readings in R/hr (high-range accident ARMS - 1 R/hr to 10,000 R/hr)

N REACidR BUILDING ELEVATION 252' MONITORS s, _.'ct m =oo~ctrrn' '

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TABLE 9.3-6 Rev. O Page 9.3-6a Turbine Deck, Elevation 272' (mR/hr unless otherwise noted) Turbine Deck Clock Scenario CAM (cpm) Time Time ARM 24 Zone I Zone II Zone III NG Particulate 0245 0:00 9 100 150 9 250 900 0630 3:45 9 75 120 9 250 900 0645 4:00 7 40 60 7 250 900 0700 4:15 7 20 35 7 250 900 0715 4:30 7 20 35 7 250 900 0730 4:45 7 16 30 7 250 900 0745 5:00 7 16 22 7 250 900 0800 5:15 7 16 22 7 250 900 0815 5:30 7 11 22 7 250 900 0830 5:45 7 11 22 7 250 900 0845 6:00 7 11 22 7 250 900 0900 6:15 7 10 20 7 250 900 0915 6:30 7 10 20 7 250 900 0930 6:45 7 10 20 7 250 900 0945 7:00 7 10 20 7 250 900 1000 7:15 7 10 20 7 250 900 1015 7:30 7 10 20 7 250 900 1030 7:45 7 10 20 7 250 900 1045 8:00 7 10 20 7 250 900 1100 8:15 7 10 20 7 250 900 1115 8:30 7 10 20 7 250 900 1130 8:45 7 10 20 7 250 900 1145 9:00 7 10 20 7 250 900 1200 9:15 7 10 20 7 250 900 1215 9:30 7 10 20 7 250 900 1230 9:45 7 10 20 7 250 900 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2. _:_. h

TUf1BINE DECK - ELEVATION 272* . MONITOR h TURBWE BUR.DNG TURBNE STEAM NLEI N-w OPEN xxxxro:XX HATQt

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TABLE 9.3-7 Rev. O Page 9.3-7a Turbine Building Truck Bay, Make-Up Demineralization Cond. Demineralization Areas, Elevation 252' (mR/hr unless otherwise noted) Clock Scenario RM-14-23A RM-14-36 Time Time (cpm) ARM 26 (cpm) Zone I Zone II Zone III Zone IV 0245 0:00 150 0.17 150 0.2 0.2 0.1 0.2 0630 3:45 150 0.17 150 0.5 0.3 0.2 0.2 0645 4:00 150 0.01 150 0.5 0.3 0.2 0.2 0700 4:15 150 0.01 150 0.6 0.3 0.2 0.2 0715 4:30 150 0.01 150 0.6 0.3 0.2 0.2 0730 4:45 150 0.01 150 0.7 0.3 0.2 0.2 0745 5:00 150 0.01 150 0.7 0.3 0.2 0.2 0800 5:15 150 0.01 150 0.7 0.3 0.2 0.2 0815 5:30 150 0.01 150 0.7 0.3 0.2 0.2 0830 5:45 150 0.01 150 0.7 0.3 0.2 0.2 0845 6:00 150 0.01 150 0.7 0.3 0.2 0.2 0900 6:15 150 0.01 150 0.7 0.3 0.2 0.2 0915 6:30 150 0.01 150 0.7 0.3 0.2 0.2 0930 6:45 150 0.01 150 0.7 0.3 0.2 0.2 0945 7:00 150 0.01 150 0.7 0.3 0.2 0.2 1000 7:15 150 0.01 150 0.7 0.3 0.2 0.2 1015 7:30 150 0.01 150 0.7 0.3 0.2 0.2 1030 7:45 150 0.01 150 0.7 0.3 0.2 0.2 1045 8:00 150 0.01 150 0.7 0.3 0.2 0.2 1100 8:15 150 0.01 150 0.7 0.3 0.2 0.2 1115 8:30 150 0.01 150 0.7 0.3 0.2 0.2 1130 8:45 150 0.01 150 0.7 0.3 0.2 0.2 1145 9:00 150 -0.01 150 0.7 0.3 0.2 0.2 1200 9:15 150 0.01 .150 0.7 0.3 0.2 0.2 1215 9:30 150 0.01 150 0.7 0.3 0.2 0.2 1230 9:45 150 0.01 150 0.7 0.3 0.2 0.2 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2.

Eb .ATION 252' N- e PRETREATMENT ROOM, BOILER R60ldi, TURBINE LOdDING BAY, MUDS, DIESELS, COND. DEMIN. HATCH : -i r j Y --- f

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TABLE 9.3-8 4 Rev. O Turbine Building Cond. Bay, Elevation 248' Page 9.3-8a (mR/hr unless otherwise noted) Clock Scenario Time Time ARM 20 ARM 21 Zone III Zone IV Zone V Zone VI Zone VII Zone VII 0245 0:00 2 200 2 2 4 8 200 2 0630 3:45 2 200 2 2 4 4 200 2 i 0645 4:00 1 4 2 2 3 4 4 2 0700 4:15 1 4 2 1 3 3 4 2 0715 4:30 1 4 1 1 3 3 4 2 0730 4:45 1 4 1 1 2 3 4 1 0745 5:00 1 4 1 1 2 3 4 1 0800 5:15 1 4 1 1 2 2 4 1 0815 5:30 1 4 1 1 2 2 4 1 0830 5:45 1 4 1 1 1 1 4 1 0845 6:00 1 4 1 1 1 1 4 1 0900 6:15 1 4 1 1 1 1. 4 1 0915 6:30 1 4 1 1 1 1 4 1 0930 6:45 1 4 1 1 1 1 4 1 0945 7:00 1 4 1 1 1 1- 4 1 1000 7:15 1 4 1 1 1 1 4 1 1015 7:30 1 4 1 1 1- 1 4 1 1030 7:45 1 4 1 1 1 1 4 1 1045 8:00 1 4 1 1 1 1 4 1 1100 8:15 1 4 1 1 1 1 4 1 1115 8:30 1 4 1 1 1 1 4 1 1130 8:45 1 4 1 1 1 1. 4 1 1145 9:00 1 4 1 1 1 1 4 1 1200 9:15 1 4 1 1 1 1 4 1 1215 9:30 1 4 1 1 1 1 4 1 1230 9:45 1 4 1 1 1 1 4 1 Notes: Zone readiangs are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2.

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TABLE 9.3-9 Rev. O Page 9.3-9a Turbine Building, Demineralization /OG Areas, Elevation 232' (mR/hr unless otherwise noted) Clock Scenario Time Time ARM 22 ARM 38 Zone I Zone II Zone III 0245 0:00 0.3 60 0.2 0.5 0.2 0630 3:45 0.3 60 0.2' O.5 0.2 0645 4:00 0.1 D/S 0.2 0.5 0.2 0700 4:15 0.1 p/S 0.2 0.5 0.2 0715 4:30 0.1 D/S . 0. 2 0.5 0.2 0730 4:45 0.1 D/S 0.2 0.5 0.2 0745 5:00 0.1 D/S 0.2 0.5 0.2 0800. 5:15 0.1 'D/S 0.2 0.5 0.2 0815 5:30 0.1 D/S 0.2 0.5 0.2 0830 5:45 0.1 D/S 0.2 0.5 0.2 0845 6:00 0.1 D/S 0.2 0.5 0.2 0900 6:15 0.1 D/S- 0.2 0.5 0.2 0915 6:30 0.1 D/S' O.2 0.5 0.2 0930 6:45 0.1 D/S 0.2 0.5 0.2 0945 7:00 0.1 D/S 0.2 0.5 0.2 1000 7:15 0.1 D/S 0.2 0.5 0.2 1015 7:30 0.1 D/S 0.2 0.5 0.2 1030 7:45 0.1 D/S 0.2 0.5 0.2 1045 8:00 0.1 D/S 0.2 0.5 0.2 1100 8:15 0.1 D/S 0.2 0.5 0.2 1115 8:33 0.1 Ih/S 0.2 0.5 0.2 1130 8:45 0.1 D/S 0.2 0.5 0.2 1145 9:00 0.1 D/S 0.2 0.5 0.2 1200 9:15 0.1 D/S 0.2 0.5 0.2 1215 9:30 0.1 D/S 0.2 0.5 0.2 1230 9:45 0.1 D/S 0.2 0.5 0.2 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2. D/S = Downscale reading.

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, TABLE 9.3-10 Rev. O Page 9.3-10a Turbine Building Cond. Bay, Elevation 222'6" & 228'6" (mR/hr unless otherwise noted) Clock Scenario Time Time ARM 13 Zone I Zone II Zone III Zorie IV Zone V Zone VI 0245 0:00 150 3 1 50 150 2 75 0630 3:45 150 3 1 35 110 2 55 0645 4:00 1 1 1 5 15 2 7 0700 4:15 1 1 1 5 15 2 7 0715 4:30 1 1 1 5 15 2 7 0730 4:45 1 1 1 5 15 2 7 0745 5:00 1 1 1 5 15 2 7 0800 5:15 1 1 1 5 15 2 7 0815 5:30 1 1 1 5 15 2 7 0830- 5:45 1 1 1 5 15 2 7 0845 6:00 1 1 1 5 15 2 7 0900 6:15 1 1 1 5 15 2 7 0915 6:30 1 1 1 5 15 2 7 0930 6:45 1 1 1 5 15 2 7 0945 7:00 1 1 1 5 15 2 7 1000 7:15 1 1 1 5 15 2 7 1015 7:30 1 1 1 5 15 2 7 1030 7:45 1 1 1 5 15 2 7 1045 8:00 1 1 1 5 15 2 7 1100 8:15 1 1 1 5 15 2 7 1115 8:30 1 1 1 5 15 2 7 15 1130 8:45 1 1 1 5 2 7 1145 9:00 1 1 1 5 15 2 7 1200 9:15 1 1 1 5 15 2 7 1215 9:30 1~ 1 1 5 15 2 7 1230 9:45 1 1 1 5 15 2 7 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2. 4 __~ _..a-__-____-__.---__-.____-_-.x---_.__--.w.-_-_._-__a_ _ - 1 - _

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Rev. O Page 9.3-11a TABLE 9.3-11 Torus Cat' walk (mR/hr unless otherwise noted) Clock Scenario Time Time ARM 1 Zone 5 0245 0:00 8 8 0630 3:45 8 8 0645 4:00 250 250 0700 4:15 500 500 0715 4:30 850 850 0730 4:45 1500 1500 0745 5:00 5000 5000 0800 5:15 8500 8500 0815 .5:30 OSH>10000 12000 0830 5:45 OSH 14000 0845 6:00 OSH 16000 0900 6:15 OSH 17000 0915 6:30 OSH 17000 0930 6:45 OSH 17000 0945 7:00 OSH 17000 1000 7:15 OSH 17000 1015 7:30 OSH 17000 1030 7:45 OSH 17000 1045 8:00 OSH 17000 , 1100 8:15 OSH 17000 1115 8:30. OSH 17000 1130 8:45 OSH 17000 1145 9:00 OSH 17000 1200 9:15 OSH 17000 1215 9:30 OSH 17000 1230. 9:45 OSH 17000 Notes: Zone readings are average dose rates throughout zone.

m - Page 9}11b FIGURE 9.3-11 i V H

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U e 4 0 - en 3 C V 1 MONITORS - R G/ EACTOR BUILDNQ SUPPRESSON OLAMBER EXT. CATWALK l 1 l 1 l 1

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 P a l 9.4 PLANT CHEMISTRY DATA SECTION PAGE . 9.4.1 Reactor Coolant Activity Data. . . . . . . . . . . . . . . . . . . . . . . . 9.4.1-1 9.4.2 Primary Containment Air Activity Data................. 9.4.2-l'- 9.4.3 Reactor Building Air Activity Data.................... 9.~4. 3 - 1 4 i i 2 4 a .' t y , y s,.-- ..y, ,---i. nn.- , - , ,, , 9i. . . -

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Q-sa b=_ - - s- & 6 -+4y ak 4 J J4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1 1993 I l 9.4.1 REACTOR COOLANT ACTIVITY DATA

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                               -,mm,~       -m, we--  ,   ,a o  -a e -. v,      ,- +        --    -e,-        -a, , --  - -   - -- =- - - - - ---*i --- ---A--

Rev.O Page 9.4.1 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESC EXERCISE 1993 9.4.1 REACTOR COOLANT ACTIVITY DATA s A. Reactor Coolant Activity Concentrations (uCi/ml) Isotope Prior 10 0630 0630-0645 0645-0700 0700-0715 1131 2.5E-03 2.3E-02 2.0E-01 1.8E+00 1132 2.8E-03 2.5E-02 2.3E-01 2.0E+00 1-133 5.2E-03 4.7E-02 4.2E-01 3.8E+00 I-134 4.1 E-03 3.7E-02 3.3E-01 3.0E+00 1-135 4.5E-03 4.1 E-02 3.6E-01 3.3E+00 Total lodine 1.9E-02 1.7E-01 1.5E+00 1.4E+ 01 1-131 Dose Equiv. 4.5E-03 4.0E-02 3.6E-01 3.2E+00 Kr 83m 1.2E-03 5.4E-03 2.4E 02 1.1 E-01 Kr-85m 2.5E-02 1.1E-01 5.1E-01 2.3E+00 Kr-85 4.8E-03 2.2E-02 9.7E-02 4.4E-01 Kr 87 2.9E-03 1.3E-02 5.9E-02 2.6E-01 Kr-88 1.0E-03 4.5E-03 2.0E-02 9.1E-02 Xe-133m 7.3E-04 3.3E-03 1.5E-02 -6.6E-02 Xe-133 5.3E-03 2.4E-02 1.1E-01 4.8E-01 Xe-135m 5.BE-03 2.6E-02 1.2E-01 5.3E-01 Xe-135 2.2E-03 9.9E-03 4.5E-02 2.0E Total Noble Gas 4.9E-02 2.2E-01 9.9E-01 4.5E+00

Note: Reactor coolant sample dose rates are provided in Section 9.5.1.

Rev.0 Page 9.4.12

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1993 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCi/mi) Isotope 0715-0730 0730-0745 0745-0800 0800-0815 l131 2.1 E+01 2.1E+ 02 2.1 E+02 2.1 E+02 1-132 3.0E+01 3.0E+02 2.7E+02 2.5E+02 1133 4.2E+01 4.2E+02 4.2E+02 4.1E+02 1134 4.1 E+01 4.1 E+02 3.4E+02 2.7E+02 1135 3.9E+01 3.9E+02 3.8E+02 3.6E+02 Total lodine 1.7E+02 1.7E+03 1.6E+03 1.5E+03 l-131 Dose Equiv. 3.7E+ 01 3.7E+02 3.7E+02 3.6E+ 02 Kr-83m 2.3E+00 2.3E+01 2.3E+01 2.3E+01 Kr 85m 5.0E+00 5.0E+01 4.BE+01 4.6E+01 Kr-85 2.4E-01 2.4E+00 2.4E+00 . 2.4E+00 Kr-87 8.6E+00 8.6E+01 7.5E+01 6.5E+01 Kr-88 1.3E+01 1.3E+02 1.2E+02 1.1E+02 Xe-133m 1.3E+ 00 1.3E+01 - 1.3E+01 1.2E+01 Xe-133 4.3E+ 01 4.3E+02 4.2E+02 4.2E+02 Xe-135m 8.1 E+00 8.1E+01 7.0E+ 01 6.3E+01 Xe-135 9.7E+00 9.7E+01 1.0E+02 1.1E+02 Total Noble Gas 9.1 E+ 01 9.1 E+02 8.7E+02 8.5E+02 Note: Reactor coolant sample dose rates are provided in Section 9.5.1.

Rev.O Page 9.4.1-3 VERMONT YANKEE NUCLEAR POVER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCl/mi) Isotope 0815-0830 0830-0845 0845-0900 0900-0915 l-131 2.1E+02 2.1E+02 2.0E+02 2.0E+02 1-132 2.3E+ 02 2.1E+02 2.1 E+02 2.0E+02 l-133 4.0E+02 4.0E+02 3.9E+02 3.9E+02 1-134 2.2E+02 1.8E+02 1.6E+02 1.5E+02 1-135 3.5E+02 3.4E+02 3.3E+02 3.3E+02 Total lodine 1.4E+03 1.3E+03 1.3E+03 1.3E+03 1-131 Dose Equiv. 3.6E+02 3.6E+02 3.4E+02 3.4E+02 Kr-83m 2.2E+ 01 2.1 E+01 2.1 E+01 2.1 E+01 Kr-85m 4.4E+01 4.2E+01 4.1 E+01 4.0E+01 Kr 85 2.3E+00 2.3E+00 2.3E+00 2.3E+00 Kr-87 5.6E+01 4.8E+01 4.5E+01 4.2E+ 01 Kr-88 1.0E+02 9.6E+01 9.2E+01 8.9E+01 Xe-133m 1.2E+01 1.2E+01 1.2E+01 1.2E+01 Xe-133 4.2E+02 4.1E+02 4.1E+02 4.1E+02 Xe-135m 5.9E+01 5.6E+01 5.4 E+ 01 5.3E+01 Xe-135 1.1E+02 1.1E+02 1.2E+02 1.2E+02 - Total Noble Gas 8.3E+02 - 8.0E+02 8.0E+02 7.9E+02 Note: Reactor coolant sample dose rates are provided in Section 9.51.

i Rev.0 Page 9.4.1-4 I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCi/ml) isotope 0915-0930 0930-0945 0945-1000 1000-1015 l-131 2.0E+02 2.0E+ 02 2.0E+02 2.0E+ 02 1-132 1.8E+02 1.7E+02 1.5E+02 1.4E+02 1-133 3.9E+02 3.8E+02 3.7E+02 3.7E+02 1-134 1.2E+02 9.8E+01 8.0E+01 6.5E+01 1-135 3.2E+02 3.1E+02 3.0E+02 2.9E+02 Total lodine 1.2E+03 1.2E+03 1.1 E+03 1.1 E+03 1-131 Dose Equiv. 3.4E+02 3.4E+02 3.3E+02 3.3E+02 Kr-83m 2.0E+01 1.9E+01 1.9E+01 1.8E+01 Kr-85m 3.BE+01 3.6E+01 3.5E+01 3.3E+01 Kr-85 2.3E+00 2.3E+00 2.3E+00 2.3E+00 Kr-87 3.6E+01 3.2E+01 2.7E+01 2.4E+01 Kr-88 8.4E+ 01 7.8E+01 7.3E+01 6.BE+01 Xe-133m 1.2E+01 1.2E+01 1.2E+01 1.2E+01 Xe-133 4.1 E+ 02 4.1 E+02 4.0E+02 4.0E+02 Xe-135m 5.1 E+01 5.0E+01 4.8E+01 4.6E+01 Xe-135 1.2E+02 1.2E+02 1.3E+02 1.3E+02 Total Noble Gas 7.7E+ 02 7.6E+02 7.5E+02 7.3E+02 Note: Reactor coolant sample dose rates are provided in Section 9.5.1.

Rev.O Page 9.4.15 I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCi/ml) Isotope 1015-1030 1030-1045 1045-1100 POST 1100 1-131 2.0E+02 2.0E+02 1.9E+02 1.9E+02 l132 1.3E+02 1.2E+02 1.1 E+02 1.0E+02 1133 3.6E+02 3.6E+02 3.5E+02 3.5E+02 1-134 5.3E+01 4.4E+01 3.6E+01 2.9E+01 1135 2.8E+02 2.7E+ 02 2.6E+02 2.5E+02 Total lodine 1.0E+03 9.9E+02 9.5E+02 9.2E+02 1-131 Dose Equiv. 3.3E+02 3.3E+02 3.1 E+02 3.1 E+02 Kr-83m 1.7E+01 1.6E+ 01 1.6E+01 1.5E+01 Kr-85m 3.2E+01 3.0E+01 2.9E+01 2.8E+01 Kr-85 2.2E+00 2.2E+00 2.2E+00 2.2E+00 Kr-87 2.1 E+01 1.8E+01 1.6E+ 01 1.3E+01 Kr-88 6.4 E+01 6.0E+01 5.6E+01 5.2E+01 Xe 133m 1.2E+01 1.2E+01 1.2E+01 1.2E+01 Xe-133 4.0E+02 4.0E+02 4.0E+02 3.9E+02 Xe-135m 4.5E+ 01 4.3E+01 4.2E+01 4.1 E+01 Xe-135 1.3E+02 1.3E+02 1.4E+02 1.4E+02 Total Noble Gas 7.2E+02 - 7.1 E+ 02 7.1 E+02 6.9E+02 Note: Reactor coolant sample dose rates are provided in Section 9.5.1.

J+ A. w 44...- # w M - 4 m aw ge _ 5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 t 9.4.2 PRIMARY CONTAINMENT AIR' ACTIVITY DATA 9 a I t M n

b 4 4 s.. _. _ _ ._. -_ . ._ . . . _ ..

Rev.O Page 9.4.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uCi/cc) Isotope Prior to 0630 0630-0645 0645-0700 0700-0715 l-131 6.1 E-07 5.5E-06 4.9E-05 1-132 8.4E-07 7.6E-06 6.8E-05 l-133 1.2E-06 1.1 E-05 1.0E-04 l-134 1.1E-06 1.0E-05 9.2E-05 l135

1.1 E-06 1.0E-05 9.2E-05 Total lodine 4.9E-06 4.5E-05 4.0E-04 l-131 Dose Equiv.
1.1 E-06 9.8E-06 8.8E-05 Kr-83m 6.5E 06 5.8E-05 5.3E-04 Kr-85m 1.4E-05 1.3E-04 1.2E-03 Kr-85 6.8E-07 6.1E-06 5.5E-05 Kr-87 2.5E-05 2.2E-04 2.0E 03 Kr-88 3.6E 05 3.2E-04 2.9E-03 Xe 133m 3.6E-06 3.2E-05 2.9E-04 Xe-133 1.2E-04 1.1E-03 1.0E-02 Xe-135m 2.1 E-05 1.9E-04 1.7E-03 Xe-135 2.7E-05 2.4E-04 2.2E-03 Total Noble Gas 2.6E 04 2.3E-03 2.1 E-02 Note: Primary containment sample dose rate provided in Section 9.5.2.
Prior to 0630 containment air activity is below MDA.

'l

Rev.0 Page 9.4.2-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 ,. 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uCi/cc) isotope 0715-0730 0730-0745 0745-0800 0800-0815 l-131 5.9E-04 5.9E-03 1.1E-02 1.6E-02 l-132 8.2E-04 8.2E-03 1.4E-02 1.9E-02 1-133 1.2E-03 1.2E-02 2.1 E-02 3.1 E-02 1134 1.1E-03 1.1 E-02 1.7E-02 2.1E-02 1-135 1.1 E-03 1.1 E-02 1.9E-02 2.8E-02 Total lodine 4.BE-03 4.8E-02 8.2E-02 1.2E-01 1-131 Dose Equiv. 1.1 E-03 1.1 E-02 1.9E-02 2.8E-02 Kr-83m 6.3E-03 6.3E-02 1.1 E-01 1.5E-01 Kr-85m 1.4E-02 1.4E-01 .2.4E-01 3.5E-01 Kr-85 6.6E-04 6.6E-03 1.2E-02 1.8E-02 Kr-87 2.4E-02 2.4E 01 3.8E-01 4.9E-01 Kr-88 3.5E-02 3.5E-01 6.0E-01 8.4E-01 Xe-133m 3.5E-03 3.5E-02 6.3E-02 9.5E-02 Xe-133 1.2E-01 1.2E+00 2.2E+00 3.2E+00 Xe-135m 2.0E-02 2.0E-01 2.3E-01 2.4E-01 Xe-135 2.6E-02 2.6E-01 4.9E-01 7.5E-01 Total Noble Gas 2.5E-01 2.5E+00 4.3E+00 6.1E+00 Note: Primary containment sample dose rate provided in Section 9.5.2.

                                                       . m          _

Rev.0 Page 9.4.2 3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uCi/cc) Isotope 0815-0830 0830-0845 0845-0900 0900-0915 1-131 2.1E-02 2.6E-02 3.0E-02 3.2E-02 1-132 2.4E-02 2.7E-02 2.9E-02 2.8E-02 1-133 4.1E-02 5.0E-02 5.7E-02 6.0E-02 1134 2.3E-02 2.3E-02 2.2E 02 1.9E-02 1-135 3.6E-02 4.3E-02 4.8E-02 5.0E-02 Total lodine 1.5E-01 1.7E-01 1.9E-01 1.9E-01 1-131 Dose Equiv. 3.6E-02 4.4E-02 5.1 E-02 5.4E-02 Kr-83m 1.9E-01 2.2E-01 2.4E 01 2.4 E-01 Kr-85m 4.5E-01 5.3E-01 5.8E-01 5.9E-01 Kr-85 2.4 E-02 2.9E-02 3.4E-02 3.6E-02 Kr-87 5.7E-01 6.1E-01 6.1 E-01 5.7E-01 Kr-88 1.1 E+00 1.2E+00 1.3E+00 1.3E+00 Xe 133m 1.3E-01 1.5E-01 1.8E-01 1.9E-01 Xe-133 4.3E+00 5.2E+00 6.0E+00 6.4E+00 Xe-135m 2.4E-01 2.2E-01 1.9E-01 1.7E-01 Xe-135 1.0E+00 1.3E+00 1.5E+00 1.6E+00 Total Noble Gas 8.0E+00 9.5E+00 1.1 E+01 1.1 E+ 01 Note: Primary containment sample dose rate provided in Section 9.5.2. -\

Rev.0 . Page 9.4.2-4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uCil_. Isotope 0915-0930 0930-0945 0945-1000 1000-1015 l-131 3.3E-02 3.5E-02 3.7E-02 3.8E-02 1-132 2.8E-02 2.7E-02 2.6E-02 2.5E-02 1-133 6.3E-02 6.6E-02 6.BE-02 7.0E-02 1-134 1.6E-02 1.4E-0.; 1.2E-02 1.0E-02 1-135 5.1E-02 5.2E-02 5.3E-02 5.4E-02 Total lodine 1.9E-01 1.9E-01 2.0E-01 2.0E-01 1-131 Dose Equiv. 5.CE-02 5.8E-02 6.1E-02 6.3E-02 d Kr-83m 2.4E-01 2.4E-01 2.4E-01 2.3E-01 Kr-85m 6.0E-01 6.1E-01 6.1 E-01 6.1E-01 Kr-85 3.8E-02 1.0E-02 4.2E-02 4.3E-02 Kr-87 5.2E-01 4.CF-01 4.4E-01 4.0E-01 Kr-88 1.3E+00 1.3E+00 1.3E+00 1.2E+00 Xe-133m 2.0E-01 2.1E-01 2.1E-01 2.2E-01 Xe '.33 6.7E+00 7.0E+00 7.3E+00 7.6E+00 Xe-135m 1.5E-01 1.4E-01 1.4E-01 1.3E-01 Xe-135 1.7E+00 1.8E+00 1.9E+00 2.0E+00 Total Noble Gas 1.1E+ 01 1.2E+01 1.2E+01 1.2E+01 I Note: Primary containment sample dose rate provided in Section 9.5.2. i i I

Rev.O Page 9.4.2 5. VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 ; 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uCl/cc) Isotope 1015-1030 1030-1045 1045-1100 POST-1100 1-1; 1 3.9E-02 4.0E-02 4.1E-02 4.1 E-02 1-11_ 2.4E-02 2.3E-02 2.2E-02 2.2E-02 1-133 .2E-02 7.3E-02 7.5E-02 7.5E-02 1-134 8.7E-03 7.4E-03 6.2E-03 6.2E-03 1-135 5.4E-02 5.4E-02 5.4E-02 5.4E-02 Total looine 2.0E-01 2.0E-01 2.0E-01 2.0E-01 l-131 Dose Equiv. 6.4 E-02 6.5E-02 6.7E-02 6.7E-02_ Kr-83m 2.3E-01 2.3E-01 2.2E-01 2.2E-01 Kr-85m 6.1 E-01 6.0E-01 6.0E-01 6.0E-01 Kr-85 4.5E-02 4.6E-02 4.7E-02 4.7E-02 Kr-87 3.6E-01 3.2E-01 2.9E-01 2.9E-01 Kr-88 1.2E+00 1.2E+00 1.1E+00 1.1 E+00 Xe-133m 2.3E-01 2.4 E-01 2.4E-01 2.4E-01 Xe-133 7.9E+00 8.1 E+00 8.3E+00 8.3E+00 Xe 135m 1.3E-01 1.3E-01 1,2E-01 1.2E-01 Xe-135 2.1 E+00 2.1E+00 2.2E+00 2.2E+00 Total Noble Gas 1.3E+01 1.3E+01 1.3E+ 01 1.3E+01 Note: Primary containment sample dose rate provided in Section 9.5.2.

1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 6

                                                                           -i 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA                        i s

4 6 I e t 1

                                         .                                 -I
                                                                            .l

t Rev.O Page 9.4.3-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA A. Reactor Building Air Activity Concentrations (uCi/cc) All elevations - See Notes Below isotope 0245 to END l-131 l-132 l-133 l-134 l-135 Totat lodine l-131 Dose Equiv. Kr-83m , Kr-85m Kr-85 Kr-87 Kr-88 ' Xe-131m Xe-133m Xe-133 ' Xe-135m Xe-135 Total Noble Gas Notes:

Denotes Activity Concentration below MDL.

Reactor Building air sample dose rates provided in Section 9.5.3.

VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS' EXERCISE 1993 9.5 RADIOLOGICAL SAMPLE DOSE RATES SECTION pfg,g 9.5.1 Reactor Coolant Sample Dose Rates......... ......... 9.5.1-1 9.5.2 Primary Containment Sample Dose' Rates..... 4 ........ 9.5.2-1 9.5.3 Reactor Building Air Sample Dose Rates...............-9.5 3-1. 9.5.4 Plant Vent Stack Sample Dose Rates................... 9.5.4-1 4

k VERMONT YANKEE NUCLEAR POWER' STATION j EMERGENCY RESPONSE PREPAREDNESS EXERCISE

1993 9.5.1 REACTOR COOLANT SAMPLE DOSE RATES '

                                                 .i T

i ( i t

j l Rev.0: 1 Pa0e 9.5.1-1 j VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 f 9.5.1 Reactor Coolant Sample Dose Rates . A. Gas Samples j j Shielded U Unshielded (mR/hr per cc)* (1 in. lead in mR/hr per cc)* j Time Contact i ft Contact 1 ft c Prior to , 0630 " 1.4E-02 9.8E-05 1.7E-04 1.2E-06 0630-0645 6.4E-02 4.4E-04 7.8E-04 5.5E-06 0645-0700 2.9E-01 2.0E-03 3.5E-03 2.5E-05 0700-0715 1.3E+00 9.0E-03 1.6E-02 ~ 1.1 E-04 0715-0730 2.6E+01 1.8E-01 3.2E-01 2.3E-03 l 0730-0745 2.6E+02 1.8E+00 ' 3.2E+00 . 2.3E-02 ; 0745-0800 2.5E+02 1.7E+00 3.1E+00 2.2E-02 0800-0815 2.5E+02 - 1.7E+00 3.0E+00 2.1E-02 0815-0830 - 2.4E+02 1.7E+ 00 2.9E+00 2.1 E-02 0830-0845 - 2.3E+02 1.6E+00 2.8E+00 2.0E-02 0845-0900 2.3E+02 1.6E+00 2.8E+00 2.0E-02 0900-0915 2.3E+02 1.6E+00 2.8E+00 2.0E-02 0915-0930 2.2E+02 1.5E+00 2.7E+00 1.9E 02 0930-0945 2.2E+02 .1.5E+ 00 2.7E+00 1.9E-02 0945 1000 2.2E+02 1.5E+00 2.7E+00 1.9E-02 1000-1015 2.1 E+02 1.5E+ 00 2.6E+00 - 1.8E-02 1015-1030 2.1 E+02 1.4E+00 2.6E+00 -. 1.8E , 1030-1045 2.1E+02 1.4E+00 - 2.5E+00 1.8E-02 1045-1100 2.1E+02 1.4E+00 2.5E+00 1.8E-02 POST 1100 2.0E+02 1.4E+ 00 2.4E+00 1.7E-02 Note:

Value must be multiplied by the sample volume in cubic i:entimeters for gas samples to obtain the sample dose rate in mR/hr.

Rev.O Page 9.5.12 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.5.1 Reactor Coolant Sample Dose Rates U. Liquid (lodine) Unshielded Shielded (mR/hr per cc)* (1 in. lead in mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 0630" 1.5E-02 1.0E-04 1.9E-04 1.3E-06 0630-0645 1.3E-01 9.2E-04 1.7E-03 1.1 E-05 1 0645-0700 1.2E+00 8.1 E-03 1.5E-02 9.9E-05 0700-0715 1.1 E+01 7.6E-02 1.4E-01 9.3E-04 0715-0730 1.3E+02 9.2E-01 1.7E+00 1.1 E-02 . 0730-0745 1.3E+03 9.2E+00 1.7E+01 1.1 E-01 0745-0800 1.2E+03 8.7E+00 1.6E+01 1.1 E-01 0800-0815 1.2E+03 8.1 E+00 1.5E+01 9.9E-02 0815-0830 1.1 E+03 7.6E+00 1.4E+01 9.3E-02 0830-0845 1.0E+03 7.0E+00 1.3E+01 8.6E-02 0845-0900 1.0E+03 7.0E+00 1.3E+01 8.6E-02 0900-0915 1.0E+03 7.0E+00 1.3E+01 8.6E-02 0915-0930 9.4E+02 6.5E+00 1.2E+01 7.9E-02 0930-0945 9.4E+02 6.5E+00 1.2E+01 7.9E 0945-1000 8.6E+02 6.0E+00 1.1 E+01 7.3E-02 1000-1015 8.6E+02 6.0E+00 1.1E+01 7.3E-02 1015-1030 7.8E+02 5.4E+00 9.8E+00 6.6E-02 1030-1045 7.7E+02 5.4E+00 9.7E+ 00 6.5E-02 1045-1100 7.4E+02 5.1E+00 9.3E+00 6.3E-02 POST 1100 7.2E+ 02 5.0E+00 9.0E+00 6.1E-02 Note: ' Values must be multiplied by the sample volume in milliliters for liquid samples to obtain the sample dose rate in mR/hr.

a

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4 4 m . . A 4

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993- [ L 1 9.5.2 PRIMARY CONTAINMENT SAMPLE DOSE RATES , p 7 h i I w - -

l Rev.O Page 9.5.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.5.2 Primary Containment Sample Dose Rates A. Gas Samples Unshielded Shielded (mR/hr per cc)* (1 in, lead in mR/hr per cc)* Time Contact 1 ft Contact i ft Prior to 0630 " As Read As Read As Read As Read 0630-0645 7.5E-05 5.2E-07 9.2E-07 6.5E-09 0645-0700 6.6E-04 4.6E-06 8.2E-06 5.8E-08 0700-0715 6.0E-03 4.2E-05 7.5E-05 5.3E-07 0715-0730 7.2E-02 5.0E-04 8.9E-04 6.3E-06 0730-0745 7.2E-01 5.0E-03 8.9E-03 6.3E-05 0745 0800 1.2E+00 8.6E-03 1.5E-02 1.1 E-04 0800-0815 1.8E+00 1.2E-02 2.2E-02 1.5E-04 0815-0830 2.3E+00 1.6E-02 2.8E-02 2.0E-04 0830-0845 2.7E+00 1.9E-02 3.4E-02 2.4E-04 0845-0900 3.2E+00 2.2E-02 3.9E-02 2.8E-04 0900-0915 3.2E+ 00 2.2E-02 3.9E 02 2.8E-04 0915-0930 3.2E+00 2.2E-02 3.9E-02 2.8E-04 0930-0945 3.5E+00 2.4E-02 4.3E-02 3.0E-04 0945-1000 3.5E+00 2.4E-02 4.3E-02 3.0E-04 1000-1015 3.5E+00 2.4E-02 4.3E-02 3.0E-04 1015-1030 3.7E+00 2.6E-02 4.6E-02 3.3E-04 1030-1045 3.7E+00 2.6E-02 4.6E 02 3.3E 04 1045-1100 3.7E+ 00 2.6E-02 4.6E-02 3.3E-04 POST 1100 3.7E+ 00 2.6E-02 4.6E-02 3.3E-04 Note:

Values must be multiplied by the sample volume in cubic centimeters for gas samples to obtain the sample dose rate in mR/hr.

                                                 -l
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)

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE , 1993 l

                     .                           't i

9.5.3 REACTOR BUILDING AIR SAMPLE DOSE RATES

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Rev.O Page 9.5.3-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.5.3 Reactor Building Air Sample Dose Rates (lodine Cartridge Only) All elevations - See Notes Below Unshielded Shielded (mR/hr per cc)* (1 in, lead in mR/hr per cc)* Time Contact 1 ft Contact 1 ft 0245-END As Read As Read As Read As Read 4 Note:

Values must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rate in mR/hr.

1 l I l

t VERMONT YANKEE NUCLEAR POWER STATION ; EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 i 4 9.5.4 PLANT VENT STACK SAMPLE DOSE RATES

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Rev.0 Page 9.5.4-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.5.4 Plant Vent Stack Sample Dose Rates A. Gas (Grab Sample) Unshielded Shielded (mR/hr per cc)* (1 in. lead in mR/hr per cc)* Contact i ft Contact 1 ft Time Prior to 0845 " As Read As Read As Read As Read 0845-0900 3.1 E-04 2.2E-06 3.9E-06 2.8E-08 0900-0915 3.1E-02 2.2E-04 3.9E-04 2.BE-06 0915-0930 3.1E-02 2.2E-04 3.9E-04 2.8E-06 0930-0945 3.4E-02 2.4E-04 4.2E-04 3.0E-06 0945-1000 3.4E-02 2.4E-04 4.2E-04 3.0E-06 1000-1015 3.4E-02 2iE-04 4.2E-04 3.0E-06 1015-1030 3.4E-02 2.4E-04 4.2E-04 3.0E-06 1030-1045 3.7E-02 2.6E-04 4.6E-04 3.3E-06 1045-1100 3.7E-04 2.6E-06 4.6E-06 3.3E-08 POST 1100 As Read As Read As Read As Read Notes:

Value must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rates in mR/hr.

                        " Plant vent stack sample dose rates remain constant from 0245-0845 given the same sample volume.

Rev.0 Page 9.5.4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.5.4 Plant Vent Stack Sample Dose Rates B. Air Sample (lodine Cartridge) Unshleided Shielded (mR/hr per cc)* (1 in. lead in mR/hr per cc)* Time Contact i ft Contact i ft Prior to 0845 " As Read As Read As Read As Read 0845-0900 1.4 E-05 9.7E-08 1.7E-07 1.2E-09 0900-0915 1.4E-03 9.7E-06 1.7E-05 1.2E-07 0915-0930 1.5E-03 1.0E-05 1.8E-05 1.3E-07 0930-0945 1.5E-03 1.0E-05 1.8E-05 1.3E-07 0945-1000 1.5E-03 1.0E-05 1.8E-05 1.3E-07 1000-1015 1.5 E-03 1.0E-05 1.8E-05 1.3E-07 1015-1030 1.5E-03 1.0E 1.8E-05 1.3E-07 1030 1045 1.5E-03 1.0E-05 1.8E-05 1.3E-07 1045-1100 1.5E-05 1.0E 07 1.8E-07 1.3E-09 POST 1100 As Read As Read As Read As Read Notes:

Value must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rates in mR/hr.

                          " Plant vent stack sample dose rates remain constant from 0245-0845 given the same sample volume.

Rev.O Page 9.5.4 , VERMONT YANKEE NUCLEAR POVER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.5.4 Plant Vent Stack Sample Dose Rates r C. General Area Exposure Rates at Stack (mr/hr) Time At Stack Door inside Prior to 0845 As Read

As Read
0845-0900 1 10 0900-0915 10 100 0915-0930 10 100 0930L0945 10 100 0945-1000 10 100 1000-1015 10 100 1015-1030 10 100 1030-1045 10 10C 1045-1100 1 10 POST 1100 As Read
As Read" l
Background as read on survey meter.

1 1 1 i l l l 1 VERMONT YANKEE NUCLEAR POWER STATION l i EMERGENCY RESPONSE PREPAREDNESS EXERCISE. ! 1993 9.6 PLANT VENT' STACK RELEASE DATA I i f

j 8 m

Rev.0 Page 9.6-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.6 PLANT VENT STACK RELEASE DATA A. Plant Vent Stack Activity Release Concentrations (uCi/cc)

Isotope Prior to 0845 0845-0900 0900-0915 1-131 3.3E-13 3.1 E-06 3.1 E-04 l-132 4.BE 13 2.8E-06 2.8E-04 l-133 7.5E-13 5.9E-06 5.9E-04 l-134 6.6E-13 1.8E-06 1.8E-04 l-135 6.3E-13 4.9E-06 4.9E-04 Total lodine 2.9E-12 1.8E-05 1.8E 03 1-131 Dose Equiv. 6.1E 13 5.2E-06 5.2E-04 Kr-83m 2.4E-05 2.4E-03 Kr 85m 5.8E-05 5.8E-03 Kr-85 3.5E-06 3.5E-04 L Kr-87 5.6E-05 5.6E-03 Kr-88

                                     "              1.3E-04          1.3E-02 Xe-131m
                                     "              2.0E-06          2.0E-04 Xe-133m
                                     "              1.8E-05          1.8E-03 Xe-133 6.2E-04          6.2E-02 Xe-135m 1.6E-05          1.6E-03 Xe-135 1.5E-04          1.5E-02 Total Noble Gas 1.1 E-03         1.1E-01 Activity concentrations (in uCi/cc) may be converted to activity release rates (uCl/sec) by multiplying by the assumed stack flow rate of 4.9E7 cc/sec.
                      "      Noble gas release rates are minimal at this time and below MDA of the multi-channel analyzer.

Note: Plant vent stack sample dose rates are provided in Section 9.5.4.

i Rev.0 Page 9.6-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.6 PLANT VENT STACK RELEASE DATA A. Plant Vent Stack Activity Release Concentrations (uCl/cc)

Isotope 0915-0930 0930-0945 0945-1000 1000-1015 1-131 3.3E 04 3.4 E-04 3.6E-04 3.7E-04 l-132 2.7E-04 2.6E-04 2.5E 04 2.5E-04 l-133 6.2E-04 6.4E-04 6.6E-04 6.8E-04 l-134 1.6E-04 1.4E-04 1.2E-04 1.0E-04 l135 5.0E-04 5.1E-04 5.2E-04 5.2E-04 Total lodine 1.9E-03 1.9E-03 1.9E-03 1.9E-03 1-131 Dose Equiv. 5.5E-04 5.7E-04 5.9E-04 6.1 E-04 Kr-83m 2.4E-03 2.3E-03 2.3E-03 2.3E-03 Kr-85m 5.9E-03 5.9E-03 6.0E-03 6.0E-03 Kr-85 3.7E-04 3.9E-04 4.0E-04 4.2E-04 Kr-87 5.1E-03 4.7E-03 4.3E-03 3.9E-03 Kr-88 1.3E-02 1.2E-02 1.2E-02 1.2E-02 Xe-131m 2.1E-04 2.2E-04 2.3E-04 2.4E-04 '

Xe-133m 1.9E-03 2.0E-03 2.1 E-03 2.2E-03 Xe-133 6.6E-02 6.9E-02 7.2E-02 7.4E-02 Xe-135m 1.5E-03 1.4E 03 1.4E-03 1.3E-03 Xe-135 1.6E-02 1.7E-02 1.8E-02 1.9E-02 Total Noble Gas 1.1 E-01 1.2E-01 1.2E-01 1.2E 01 Activity concentrations (in uCl/cc) may be converted to activity release rates (uCi/sec) by multiplying by the assumed stack flow rate of 4.9E7 cc/sec. Note: Plant vent stack sample dose rates provided in Section 9.5.4. l l

t Rev.O Page 9.6 3 VERMONT YANKEE NUCl. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 9.6 PLANT VENT STACK RELEASE DATA A. Plant Vent Stack Activity Release Concentrations (uCl/cc)

Isotope 1015-1030 1030-1045 1045-1100" l-131 3.8E-04 3.9E-04 3.9E-06 l-132 2.4 E-04 2.3E-04 2.3E-06 l-133 7.0E-04 7.1 E-04 7.1E-06 l-134 8.5E-05 7.2E-05 7.2E-07 l-135 5.3E-04 5.3E-04 5.3E-06 Total lodine 1.9E-03 1.9E-03 1.9E-05 l-131 Dose Equiv. 6.2E-04 6.4 E-04 6.4E-06 Kr-83m 2.2E-03 2.2E-03 2.2E 05 Kr-85m 5.9E-03 5.9E-03 5.9E-05 Kr-85 4.3E-04 4.5E 04 4.5E-06 Kr-87 3.5E-03 3.1E-03 3.1E-05 Kr-88 1.2E-02 1.1 E-02 1.1E-04 Xe-131m 2.5E-04 2.5E 2.5E-06 Xe-133m 2.2E-03 2.3E-03 2.3E-05 Xe-133 7.7E-02 7.9E 02 7.9E-04 Xe-135m 1.3E-03 1.2E-03 1.2E-05 Xe-135 2.0E-02 2.1E-02 2.1E-04 Total Noble Gas 1.2E-01 1.3E-01 1.3E-03 Activity concentrations (in uCi/cc) may be converted to activity release rates (uCi/sec) by multiplying by the assumed stack flow rate of 4.9E7 cc/sec.

Post 1100 values as read. i Note: Plant vent stack sample dose rates provided in Section 9.5.4. i I l u l

l 2

k VERMONT YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE' P 1993 .;

                                                 -s i

i 9.7 FIELD MONITORING MAPS AND DATA i

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                                                                                   .c Rev. O Page 9.7-1 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993                                            ;

9.7 FIELD MONITORING MAPS AND DATA Plume whole body dose rates and radioiodine concentrations have been estimated as a function of time and distance from the plant site using a variable traj ec tory dose assessment model (METPAC). Geographical-representations of the plume are provided in this section for each 15 minute average of the meteorological conditions, starting at clock time-0850 (scenario time 6:05). During the exercise, field team observers will . l 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 9.7-1 through 9.7-14 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 and State of New Hamphsire 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 1 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. I

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1

Rev. O Page 9.7-2 Prior to the exercise,- training will be provided to field monitoring observers on the use of the figures and tables. The field monitoring observers should use the following specific instructions:

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 spent in an affected area. Use the values provided for the PIC-6 or the closed window, waist level reading for the gamma dose rate. Do not issue pocket dosimeter results to team' members, unless they actually simulate checking their dosimeter reading. The-pocket dosimeters have specific ranges and intervals in mR or R values. Ask them the ranges associated with the pocket dosimeter utilized. Attempt to provide values that reflect-the team's accrued exposure and range of the pocket dosimeter.

4. Ask the field monitoring teams what equipment they have available for their use. Ask them the scales associated with the equipment; log the 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, respectively.

Rev. O Page 9.7-3

5. For gamma (whole body dose rates) survey readings taken by field monitoring teams, the following information should be use:

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 approximately 1.0 mR/hr. Therefore, 14 mR/hr will, cause the RM-14/HP-210 to read "off-scale high. " The upper range of.the RM-14/HP-210 is 50,000 cpm.

b. Whenever a team takes a " ground level" survey, the results should be the same as the " waist level" survey.

c. Certain field monitoring teams may take open window Fnd closed 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 use:

a. The field monitoring teams will substitute a charcoal cartridge instead of the adsorber media cartridge (silver zeolite)

contained in the field monitoring kits. All air sample data will be given as though the adsorber media cartridges (silver zeolite) were being used in the kits.

b. Air sample volume assumptions have been used in the calculation of the net count rates for the air sample results. The sample volume was assumed to be 100 liters for Vermont Yankee, 177 liters for State of Vermont and 20-cubic foot (566 liters) for State of New Hamphsire field monitoring teams. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. l

Rev. O Page 9.7-4

c. Air samp'le net count rates for the absorber media cartridges (silver zeolite) provided in the field data tables have been developed using METPAC thyroid dose rate proj ections . The formula use'd is as follows:

ConcI-131 (uCi/cc) = "*#'E"xd . 5E-10uci-1/dpm-cc ExFxT where: E- Instrument Detector Efficiency in cpm /dpm (counts per disintegration) F- Flow rate of sample in Ipm (liters per minute) T- Sample collection time in minutes

d. For air sample net count rate for the particulate filter paper, it is assumed that a G M survey meter is used to obtain the sample count. rates. Filter count rates (cpm) were estimated from the I-131 air concentration for the respective ' standard ' air '

sample volume taken.

                                                                                            .l NOTE: THE PLUME PIDT FIGURES ARE GRAPHIC REPRESENTATIVES OF ATMOSPHERIC                    d
                                                                                            'l DISPERSION. IARGER FIGURES WILL BE AVAILABLE TO OBSERVERS FOR THEIR                 1 USE ON PROVIDING DATA TO FIELD MONITORING TEAMS, i
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E i TABLE 9.7.1 Rev. 0 ON-SITE VERMONT YANKEE FIELD DATA AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM-14** SAM-II RM-14*** CONC. PARTICULATE CLOCK MAP PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER TIME AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) b8bb5b9b0 B[.bb~ "~k[ ~h5b 'bbbk+bb EEb 'Eh'REkb ~~~kdb YELlDW <1 AS READ 0.00E+00 <40 AS READ <40 GREEN <1 AS READ 0.00E+00 <40 AS READ <40 0900-0915 BLUE 6 21000 0.00E+00 <40 AS READ <40 YELIDW <1 2100 0.00E+00 <40 AS READ <40 GREEN <1 210 0.00E+00 <40 AS READ <40-0915-0930 BLUE 6.5 22750 0.00E+00 <40 AS READ <40 YELLOW <1 2275 0.00E+00 <40 AS READ <40 GREEN <1 228 0.CnE+00 <40 AS READ <40 0930 0945 BLUE 6.5 22750 0.00E+00 <40 AS READ <40 YELLOW <1 2275 0.00E+00 <40 AS READ <40 GREEN <1 228 0.00E+00 <40 AS READ <40 0945-1000 BLUE 7 24500 0.00E+00 <40 AS READ <40 YELLOW <1 2450 0.00E+00 <40 AS READ <40 GREEN <1 245 0.00E+00 <40 AS READ <40 1000-1015 BLUE 7 24500 0.00E+00 <40 AS READ <40 YELLOW <1 2450 0.00E+00 <40 AS READ <40 GREEN <1 245 0.00E+00 <40 AS READ <40 1015 1030 BLUE 8 28000 0.00E+00 <40 AS READ <40 YELLOW <1 2800 0.00E+00 <40 AS READ <40 GREEN <1 280 0.00E+00 <40 AS READ <40 1030-1045 BLUE 7 24500 0.00E+00 <40 AS READ <40 YELLOW <1 2450 0.00E+00 <40 AS READ <40 CREEN <1 245 0.00E+00 <40 AS READ <40 1045-1100 BLUE <1 245 0.00E+00 <40 AS READ <40 YELLOW <1 AS READ 0.00E+00 <40 AS READ <40 GREEN <1 AS READ 0.00E+00 <40 AS READ <40 1100-END BLUE <1 AS READ 0.00E+00 <40 AS READ <40 YELLOW <1 AS READ 0.00E+00 <40 AS READ <40 GREEN <1 AS READ 0.00E+00 <40 AS READ <40 NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be ad usted proportionally. For example., if a 50 liter sam of 100 liters, divide the valurs given in the table by 2 (two)ple was collected insteaand provide the resulting value to the players.

     ** The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the silver  zeolite                              I-131 cone. (uCi/cc) X 5.6E+09 will calculate the net   samplecar   *: ridge.

count Therefore, rate in epm on t he silver zeolite cartridge.

   *** The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample.

                                                                     .REV. O PAGE 9.7-5B/C        ,

3 1

                                                                                  'i i

PAGES INTENTIONALLY LEFT BLANK [ NOTE: STATE OF VERMONT AND STATE OF NEW HAMPSHIRE FIELD DATA IS NOT t REQUIRED FOR ONSITE (PPOTECTED AREA) PLANT SURVEYS. t e t 1 f l 6 k

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t Rev. O TABLE 9.7.2a Pr.ge 9.7-6A . VERMONT YANKEE FIELD DATA AT CLOCK TIME 0850 0900 (SCENARIO TIME 6:05 6 13) AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM-14** SAM-II RM.14***

PLUME CONC. PARTICULATE SECMENT DISTANCE MAP PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER NO. (MILES) AREA (mR/hr) (CPM) uCi/cc '(NET CPM) (NET CPM) (NET CPM) >

   ...g. ... g . ...g.. ...g....                     ..g...                   . 3.g . . .g. . . . . . . .g               ...g....       '

BOUNDARY YELIDW <1 21 4.26E.18 <40 AS READ <40 , GREEN <1 AS READ 4.26E-19 <40 AS READ. <40 2.00 0.80 BLUE <1 350 2.54E.10 <40 AS READ <40 YELLOW <1 35 2.54E 11 <40 AS READ <40 GREEN <1 AS READ 2.54E-12 <40 AS READ <40 i p i l i I NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adfusted proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas collected provide instead of the resulting 100to value liters, the players.

         ** The RM.14 detector efficiency for I.131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge. Therefore, he                I.131 conc.

silver (uC1/cc) zeolite X 5.6E+09 will calculate cartridge. the net sample count rate in epm on t

       *** The particulate filter sample count rate (cpm) was estimated from the I.131 air                                                i concentration for a 100 liter sample.                                                                                   j l

1 l l I __ _ , , - - ..-m , _ _, __

Rev. 0 TABLE 9.7.2b Page 9.7-6B t STATE OF VERMONT FIELD DATA AT CLOCK TIME 0850-0900 (SCENARIO TIME 6:05 - 6:15) CAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND CROUND LEVEL READINGS LUDLUM 2220 G-M METER PLUME CLOSED OPEN CONC. ACX-2** PARTICULATE *** SECMENT DISTANCE MAP WINDOW WINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM) i$b0 ~~55Tk' " kE.bb' b$b5' . b$55 'E$55b55) E5'kbEb ~~E5b BOUNDARY YELLOW AS READ AS READ 4.26E-18 AS READ <50 CREEN AS READ AS READ 4.26E-19 AS READ <50 , 2.00 0.83 BLUE 0.10 0.20 2.53E-10 AS READ <50 YELLOW AS READ AS READ 2.53E-ll AS READ' <50 GREEN AS READ AS READ 2.53E-12 AS READ <50 l s i 41 1 i l l NOTES: '

Air sample data are based on a sample volume of 177 liters. If different volumes

, are collected, the air sample data provided in the tchles should be adj_usted proportionally. For example, if a 89 liter sample vas collected instead of 177 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

        ** The Ludlum 2220 detector efficiency for I-131 was a:sumed to be 0.080 epn/dpm with the ACX-2 cartridge. Therefore, I-131 conc. (uci/ce) X 3.2E+10 vill calculate the the net sample count rate in epm on the ACX-2 cartridge.
       *** For analysis of the particulate filter it is assumed that a C-M survey meter is used to obtain the sample count rates. The filter count rate was estimated from the I-131 air concentration for a 177 liter sample volume.

1 i l l

         .. ~ _ .                    - , _ . .                           _                        ,           .           ,   ,

Rev, O TABLE 9.7.2c Page 9.7-6C STATE OF NEW HAMPSHIRE FIELD DATA AT CLOCK TIME 0850 0900 (SCENARIO TIME 6:05 - 6:15) , GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)* WAIST AND CROUND LEVEL READINCS E-140/HP-210 G-M METER ; PLUME CLOSED OPEN CONC. AGX-2** FARTICULATE*** SECMENT DISTANCE MAP WINDOW WINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (cR/hr) (mR/hr)

uCi/cc (NET CPM) (NET CPM) 5$b0 ~~55Tb'~~5[.Uk" b$b5~ b$5k'~ 4$55E55Y " kk~kE b ~~kSb"~~~~ BOUNDARY YELLOW AS READ AS READ 4.26E-18 AS READ <50 GREEN AS READ AS READ 4.26E-19 AS READ <50 2.00 0,80 BLUE 0.10 0.20 2.53E-10 AS READ <50 YELLOW AS READ AS READ 2.53E-11 AS READ <50 GREEN AS READ AS READ 2.53E-12 AS READ <50 1 1 I i l I J

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 adfusted proportionally. For example, if a 10 cu ft sam divide the value given in the table by 2 (two)ple andwas collected provide instead value the resulting of 20 cu to ft,,

the players.

            ** The E-140/HP-210 detector efficiency for I-131 was assumed to be 0.0024 epm /dpm with the AGX-2 cartridge. Therefore, I-131 conc. uCi/cc) X 3.1E+09 vill calculate the the net sample count rate in cpm.on the ACX- 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 Eilter count rate was estimated from the I-131 air concentration for a 20 cu foot sample volume.

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Rev. O TABLE 9.7.3a Page 9.7-7A VERMONT YANKEE FIELD DATA AT CIDCK TIME 0900-0915 (SCENARIO TIME 6:15 - 6:30) AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM 14** SAM II RM-14*** PLUME CONC. PARTICUIATE PIC-6 RM 14 I-131 SILVER .'.EOLITE FILTER-SEGMENT DISTANCE MAP (NET CPM) NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) '. NET CPM) ) ~~~5$b0 5ETk' 5[.bb~ "'ki""

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                                                                         'E$56b255 4.26E-16 E5b"~'kh'kEkb
                                                                                          <40       AS READ
                                                                                                                   ~"k5b~~~
                                                                                                                      <40 BOUNDARY YELLOW                                                                                         <40 CREEN                  <1              2           4.26E-17     <40       AS READ 2.00      1.20     BLUE                    14       49000             2.04E-07       1141        3422          204 YELLOW                    1        4900             2.04E-08        114         342          <40 CREEN                  <1          490             2.04E-09     <40       AS READ           <40 3.00      2.10     BLUE                   <1          315             1.42E-09     <40       AS READ           <40 YELLOW                   <1            32           1.42E-10     <40       AS READ           <40 GREEN                   <1             3           1.42E-11     <40       AS READ           <40 t

NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables shetid be adiusted proportionally. For example, if a 50 liter sam t divide the value given in the table by 2 (two)ple andwas collected provide insteaavalue the tosulting of 100 to liters,'

the players.

          ** The RM-14 M       actor efficiency for I-131 was assumed to be 0.025 cpm /dpm with the silver zeol        4     cartridge. Therefore, I-131 conc. (uCi/cc) X 5.6E+09 will calculate the net sam e.           count rate in epm on the silver zeolite cartridge.
         *** The particulate filter sample count rate (cpm) was estimated from the I-131 air-concentration f               6   a 100 liter sample, i

1

Rev. O TABLE 9.7.3b Page 9.7-7B STATE OF VERMONT FIELD DATA AT CLOCK TIME 0900-0915 (SCENARIO TIME 6:15 - 6:30) GAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINCS LUDLUM 2220 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) uCi/cc (NET CPM) (NET CPM) 5$b0 ~~5kTb~^ELbb "b$b5 b$55' 5555b$555kkED '"E5b~~~~ BOUNDARY YELLOW AS READ AS READ 4.26E-16 AS READ <50 GREEN AS READ AS READ 4.26E-17 AS READ <50 - 2.00 1.20 BLUE 14.00 28.00 2.04E-07 6519 367 > YELLOW l.40 2.80 2.04E-08 652 <50 GREEN 0.14 0.28 2.04E-09 65 <50 3.00 2.10 0.09 0.18 1.42E 09 AS READ <50 AS READ AS READ 1.42E 10 AS READ <50 AS READ AS READ 1.42E-ll AS READ <50 NOTES:

Air sample data are based on a sample volume of 177 liters. If different volumes are collected, the air sample data provided in the tables should be adfusted proportionally. For example, if a 89 liter sample was collected instead of 177 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

            ** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 epm /dpm with the AGX-2 cartridge. Therefore, I-131 cone. (uCi/ce) X 3.2E+10 will calculate the the net sample count rate in epm on the ACX-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 concentration for a 177 liter sample volume.

                                           .       .    -   - . . _                         -              1       _ -

Rev. O TABLE 9.7.3c Page 9.7-7C STATE OF NEW HAMPSHIRE FIELD. DATA AT CLOCK TIME 0900-0915 (SCENARIO TIME 6:15 - 6:30) GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)* UAIST 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 CARTkIDGE FILTER NO. (MILES) AREA (mR/hr). (mR/hr) uCi/cc (NET CPM) (NET CPM)

  '"5$b0 ~~55Tbbi.bb'             5$bb~    55$bb~~~      ~4$55b255 "EU'dbEb                'k55~~~~~

BOUNDARY YELLOW 0.60 1.20 4.26E-16 AS READ <50 GREEN 0.06 0.12 4.26E-17 AS READ <50 2.00 1.20 BLUE 14.00 28.00 2.04E-07 640 1161 YELLOW 1.40 2.80 2.04E-08 64 116 GREEN 0.14 0.28 2.04E-09 AS READ <50 3.00 2.10 BLUE 0.09 0.18 1.42E-09 AS READ <50 YELLOW AS READ 0.00 1.42E-10 AS READ <50 GREEN AS READ 0.00 1.42E-ll AS READ <50 9 I , 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 sam divide the value given in the table by 2 (two)ple andwas collected provide instead the resu'- of 20 cu ting value to ft, the players. . -

        ** The E 140/HP 210 detector efficiency for I 131 was assumed to be 0.0024 cpm /dpm with i            the AGX-2 cartridge. Therefore, 1-131 conc. (uCi/cc) X 3.1E+09 will calculate the-the net sample count rate in cpm on 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 races. The filter count rate was estimated from the

!. I-131 air concentration for a 20 cu foot sample volume. 1

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4 Rev. O TABLE 9.7.4a Page 9.7 8A VERMONT YANKEE FIELD DATA AT CLOCK TIME 0915 0930 (SCENARIO TIME 6:30 6:45) , AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM.14** SAM-II RM-14***

   -PLUME                                                                CONC.                                      PARTICUIATE SECMENT DISTANCE MAP                        PIC.6    RM.14             I.131          SILVER ZEOLITE                                    FILTER NO.        (MILES)        AREA         (mR/hr)    (CPM) uCi/cc (NET...

CPM) ... . (NET CPM) (NET CPM) BOUNDARY YELIDW <1 2450 1.67E-16 <40 AS RFAD <40 CREEN <1 245 1.67E-17 <40 AS READ <40 2.00 1.00 BLUE 10 35000 1.60E.08 90 270 <40 YELLOW l 3500 1.60E.09 <40 AS READ <40 GREEN <1 350 1.60E.10 <40 AS READ <40 3.00 2.10 BLUE 8 28000 1.36E.07 760 2281 136 YELLOW <1 2800 1.36E.08 76 228 <40 2 CREEN <1 280 1.36E-09 <40 AS READ <40 4.00 2.90 BLUE <1 210 9.26E.10 <40 AS READ <40 YELLOW <1 AS READ 9.26E.ll <40 AS READ <40 GREEN <1 AS READ 9.26E.12 <40 AS READ <40 P J I NOTES: .

Air sample data are baled on a sample volume of 100 liters. If different volumes are collected, the air Tample data provided in the tables should be adfusted proportionally. For exauple, if a 50 liter sam divide the value given in the table by 2 (two)ple and was collected provide insteadvalue the resulting of 100 . toliters,.

the players.

           ** The RM-14 detector afficiency for I.131 was assumed to be 0.025 cpm /dpm with the                                                    ,

silver zeolite cartridge. Therefore, I.131 cone. the net sample count rate in epm on the silver zeo(uci/ce) X 5.6E+09 will calculate lite cartridge. ,

        *** The particulate filter sample count rate (cpm) was estimated from the I.131 air concentration for a 100 liter sample

Rev. O TABLE 9.7.4b Page 9.7-8B STATE OF VERMONT FIELD DATA AT CLOCK TIME 0915-0930 (SCENARIO TIME 6:30 - 6:45) CAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G M METER PLUME CLOSED OPEN CONC. ACX-2** PARTICUIATE*** SECMENT DISTANCE MAP VINDOW WINDOW I-131 CARTRIDGE FILTER i

    ..     . b        ..       -     .b       [.           5.     --       $ . . f.               <50 1.00     SITE      BLUE               7.00    14.00            1.67E-15    AS READ                                  1 BOUNDARY YELLOW                0.70     1.40            1.67E-16   .AS READ          <50                      i CREEN              0.07     0.14            1.67E-17     AS READ         <50 2.00      1.00     BLUE              10.00    20.00            1.60E-08         514         <50 YELLOW              l.00     2.00            1.60E-09          51         <50

, GREEN 0.10 0.20 1.60E-10 AS READ <50 3.00 2.10 BLUE 8.00 16.00 1.36E-07 4346 244 YELLOW 0.80 1.60 1.36E-08 435 <50 GREEN 0.08 0.16 1.36E 09 AS READ <50 i 1 4.00 2.90 BLUE 0.06 0.12 9.26E-10 AS READ <50 i YELLOW AS READ AS READ 9.26E-11 AS READ <50 i GREEN AS READ AS READ 9.26E-12 AS READ <50 l l

                                                                                                                           .l F

1 NOTES:

Air sample data are based on a sample volume of 177 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 89 liter sam ,

divide the value given in the table by 2 (two)ple andwas collected provide insteadvalue the resulting of 177 toliters, the players.

            ** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 epm /dpm with                          '

the ACX-2 cartridge. Therefore, I-131 cone. (uCi/cc) X 3.2E+10 will calculate the the net sample count rate in epm on 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 Illter count rate was estimated Yrom the I-131 air concentration for a 177 liter sample volume.

Rev. 0 TABLE 9.7.4c Page 9.7-8C. STATE OF NEW HAMPSHIRE FIELD DATA AT CLOCK TIME 0915-0930 (SCENARIO TIME 6:30 - 6:45) GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)* WAIST AND GROUND LEVEL READINGS E-140/HP-210 G M METER r CLOSED OPEN CONC. AGX 2** PARTICULATE *** PLUME SEGMENT DISTANCE MAP UINDOW WINDOW I-131 CARTRIDGE FILTER AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM) ~~ NO. (MILES)

    '"5$b0 ~~biTk' EE.bE' '"~i$bb'                      55$bb'

1.40

                                                                    '5$6i5555~~Eh'kEEb 1.67E 16         AS READ
                                                                                                       ~~E5h
                                                                                                         <50 BOUNDARY YELLOW           0.70                                                           <50 GREEN       0.07                0.14   1.67E-17         AS READ 10.00            20.00       1.60E             50             91 2.00           1.00   BLUE
                                                                                                         <50 YELLOW       1.00                2.00    1.60E-09        AS READ GREEN       0.10                0.20    1.60E-10        AS READ            <50               ,

8.00 16.00 1.36E-07 426 774 3.00 2.10 BLUE 1.36E-08 AS READ -77 YLLLOW 0,80 1.60 <50 GREEN 0.08 0.16 1.36E-09 AS READ-0.06 0.12 9.26E-10 AS READ <50 4 00 2.90 BLUE 9.26E-11 AS READ <50 YELLOW AS READ AS READ <50 GREEN AS READ AS READ 9.26E-12 AS READ' . i l l l i 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 adfusted proportionally. For example, if a 10 cu ft sample was collected instead of 20 cu ft, divide the value given in the table by 2 (two) and provide the resulting value to l the players. l

            ** The E-140/HP-210 detector efficiency for I-131 was assumed to be 0.0024 cpm /dpm with the AGX-2 cartridge. Therefore, I-131 cone. (uCi/ce) X 3.1E+09 will calculate the the net sample count rate in cpm on the AGX-2 cartridge.
           *** For analysis of the particulate filter it is assumed that a G-M survev meter is used
                                                                  ~

to obtain the sample count rates. The Iilter count rate was estimated Irom the I-131 air concentration for a 20 cu foot sample volume. i

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                                                                          *** '[N%                                                                                                       SCALE s

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CLOCK TIME: 0930 to 0945 s waM. t'%. _ m. . s.. , s u i

Rev. O TABLE 9.7.Sa Page 9.7-9A VERMONT YANKEE FIELD DATA IT CLOCK TIME 0930-0945 (SCENARIO TIME 6:45 7:00) AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM-14** SAM-II RM-14*** PLUME CONC. PARTICU1 ATE SECMENT DISTANCE MAP PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) BOUNDARY YELLOW <1 2450 1.79E-17 <40 AS READ <40 GREEN <1 245 1.79E-18 <40 AS READ <40 2.00 0.90 BLUE 10 35000 6.17E-09 <40 104 <40 YELLOW 1 3500 6.17E-10 <40 AS READ <40 CREEN <1 350 6.17E-ll <40 AS READ <40 3.00 1.90 BLUE 12 42000 1.91E.07 1072 3215 191 ! YELLOW l 4200 1.91E-08 107 321 <40 GREEN <1 420 1.91E-09 <40 AS READ <40 4.00 2.90 BLUE 6 21000 9.26E-08 519 1556 93 YELLOW <1 2100 9.26E-09 52 156 <40 GREEN <1 210 9.26E-10 <40 AS READ <40 5.00 3.70 BLUE <1 175 7.41E-10 <40 AS READ <40 YELLOW <1 AS READ 7.41E-11 <40 AS READ <40 CREEN <1 AS READ 7.41E-12 <40 AS READ <40 l l l l I 1 J l l l

                                                                                                                          .l NOTES:

Air sample data are based on a sample volume of 100 liters.. If different volumes ;

are collected, the air sample data provided in the tables should be adfusted ; proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas collected instead of 100to liters, l provide the resulting value the players.

         ** The RM-14 detector efficiency for I-131 was assumed to be 0.025 epm /dpm with the                               l silver zeolite cartridge. Therefore, I-131 conc. (uCi/ce) X 5.6E+09 will calculate the net sample count rate in epm on the silver zeolite cartridge.
       *** The particulate filter sample count rate (cpm) was estimated from the I 131 air concentration for a 100 liter sample.

l 4

. ~ . .-. Rev. O TABLE 9.7.5b Page 9.7-9B STATE OF VERMONT FIELD DATA AT CLOCK TIME 0930 0945 (SCENARIO TIME 6:45 - 7:00) CAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G M METER PLUME CLOSED OPEN CONC. AGX-2** PARTICULATE *** SEGMENT DISTANCE MAP WINDOW VINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM)

      ~'5$b0         biTk'~~ELbb~             'i$bb     .[4$bb            5$i9b$56 ~~Eh~ki1b           ~~k5b~~~~

BOUNDARY YELLOW 0.70 1.40 1.79E-17 AS READ <50 GREEN 0.07 0.14 1.79E-18 AS READ <50 2.00 0.90 BLUE 10.00 20.00 6.17E-09 198 <50 YELLOW l.00 2.00 6.17E-10 AS READ <50 GREEN 0.10 0.20 6.17E-11 AS READ <50 3.00 1.90 BLUE 12.00 24.00 1.91E-07 6123 344 YELLOW l.20 2.40 1.91E-08 612 <50 GREEN 0.12 0.24 1.91E-09 61 <50 4.00 2.90 BLUE 6 00 12.00 9.26E-08 2963 167

                              -YELLOW           0.60        1.20          9.26E-09           296               <50                      1 GREEN           0.06        0.12          9.26E-10       AS READ               <50 5.00            3.70   BLUE            0.05        0.10          7.41E-10       AS READ-              <50                      l YELLOW      AS READ AS READ                7.41E ll       AS READ               <50~

CREEN AS READ AS READ 7.41E-12 AS READ <50 i l l l l l NOTES:

Air sample data are based on a sample volume of 177 liters. If different volumes are collected, the air sample data provided in the tables should be adiusted proportionally. For example, if a 89 liter sam divide the value given in the table by 2 (two)ple andwas collected provide instead value the resulting of 177toliters, the players.

              ** The Ludlum 2220 detector efficiency for I 131 was assumed to be 0.080 cpm /dpm with the AGX 2 cartridge. Therefore, I-131 cone. (uCi/cc) X 3.2E+10 will calculate the the net sample count rate in epm on the AGX-2 cartridge.
             *** For analysis of the particulate filter it is assumed that a G-M survey meter is used                                   i to obtain the sample count rates. The filter count rate was estimated from the                                        !

I 131 air concentration for a 177 liter sample volume.

Rev. O TABLE 9.7.5c Page 9.7-9C STATE OF NEW HAMPSHIRE FIELD DATA AT CLOCK TIME 0930 0945 (SCENARIO TIME 6:45 - 7:00) I GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU FT)* WAIST AND GROUND LEVEL READINGS E-140AP-210 G-M METER l PLUME CLOSED OPEN CONC. AGX-2**' PARTICULATE *** I SEGMENT DISTANCE MAP WINDOW WINDOW I-131 CARTRIDGE FILTER 1 NO. (MILIS) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM)

                                                                                                                                               'i 1.00         SITE           BLUE              7.00       14.00        1.79E-16            AS READ                 <50 BOUNDARY YELLOW                       0.70         1.40        1.79E-17           AS READ                 <50 GREEN             0.07         0.14        1.79E-18           AS READ                 <50 4

2.00 0.90 BLUE 10.00 20.00 . 6.17E-09 AS READ <50 YELLOW l.00 2.00 6.17E-10 AS READ <50' GREEN 0.10 0.20 6.17E-ll AS READ <50 3.00 1.90 BLUE 12.00 24.00 1.91E.07 601 1091 YELLOW l.20 2.40 1.91E 08 60 109 GREEN 0.12 0.24 1.91E-09 AS READ <50 4.00 2.90 BLUE 6.00 12.00 9.26E-08 291 528 YELLOW 0.60 1.20 9.26E-09 AS READ 53 GREEN 0.06 0.12 9.26E-10 AS READ <50 5.00 3.70 BLUE 0.05 0.10 7.41E-10 AS READ <50 YELLOW AS READ AS READ 7.41E-ll AS READ <50 GREEN AS READ AS READ 7.41E-12 AS READ <50

     - NOTES:

Air sample data are based on a sample volume of 20 cu f t, If different volumes are collected, the air sample data provided in the tables should be adfusted proportionally. For example, if a 10 cu ft sam ,

divide the value given in the table by 2 (two)ple andwas providecollected instead value the resulting of 20 cu to ft, the players.

               ** The E-140/HP-210 detector efficiency for I-131 was assumed to be 0.0024 cpm /dpm with the AGX-2 cartridge. Therefore, I-131 conc. (uCi/cc) X 3.lE+09 vill calculate the the net sample count rate in epm on the ACX-2 cartridge.
             *** For analysis of the particulate filter it is assumed that a G-M survey meter is used to obtaih the sample count rates. The Illter count rate was estimated from the I-131 air concentration for a 20 cu foot sample volume.

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                                                                                                                                                                                                                                            >       4          ,u
                                                                                                                                                                                                                                                                                            \f SCALE
                                         ,                                                                 CLOCK TIME: 0945 to 1000                                                                                                                                                                                 ;

2. = -. m- m., x s- g -

       ,                          . _ ,             ~ , . . , _ . .                               .,      __        _          -            _                                 _        _                                 . _.                  _

Rev. O TABLE 9.7.6a Page 9.7 10A VERMONT YANREE FIELD DATA AT CLOCR TIME 0945-1000 (SCENARIO TIME 7:00 7:15) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM.14** SAM-II RM-14*** PLUME CONC. PARTICULATE' PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER SEGMENT DISTANCE MAP NO. (MILES) AREA (mR/hr) (CPM) uCi/cc- (NET CPM) (NET CPM) (NET CPM) ...g9 ...g.. ...g.. ......... ..... ..

                                                              . g g . . . .;. . . . . . . .g             ....6"'

BOUNDARY YELLOW <1 2450 1.79E-17 <40 AS READ <40 GREEN <1 245 1.79E-18 <40 AS READ <40 2.00 0.80 BLUE 10 35000 6.17E-09 <40 104 <40 YELLOW 1 .3500 6.17E-10 <40 AS READ <40. GREEN <1 350 6.17E-ll <40 AS READ <40 3.00 1.60 BLUE 14 49000 1.91E.07 1072 3215 191 YELLOW l.5 4900 1.91E.08 107 321 <40 GREEN <1 490 1.91E-09 <40 AS READ <40 4.00 2.60 BLUE 8 28000 9.26E-08 519 1556 93 YELLOW <1 2800 9.26E-09 52 . 156 <40 GREEN <1 280 9.26E.10 <40 AS READ <40 5.00 3.60 BLUE 5 17500 7.41E-10 <40 AS READ <40 YELLOW <1 1750 7.41E-11 <40 AS READ <40 GREEN <1 175 7.41E-12 <40 AS READ <40 6.00 4.40 BLUE <1 140 5.74E 10 <40 AS READ <40 YELLOW <1 AS READ 5.74E-11 <40 AS READ <40 GREEN <1 AS READ 5.74E-12 <40 AS READ <40 NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided-in the tables should be adjusted proportionally.

divide the valueForgiven example, in theif table a 50 liter by 2sam (two)ple andwas collected provide instead value the resulting of 100toliters,. the players.

      ** The-RM-14 detector efficiency for I 131 was assumed to be 0.025 epm /dpm with the silver                                         I.131 conc. (uci/cc) X 5.6E+09 will calculate the netzeolite sample cartridge.

count rateTherefore, in epm on the silver zeolite cartridge.

     *** The particulate filter sample count rate (cpm) was estimated from the I.131 air concentration for a 100 liter sample.

l 1 l

       .         _     .           . . -                      -.       _             . -      . - - -     .               _ - = .          ..  .

Rev. 0 TABLE 9.7.6b Page 9.7-10B STATE OF VERMONT FIELD DATA AT CLOCK TIKE 0945-1000 (SCENARIO TIME 7:00 - 7:15)

CAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND CROUND LEVEL READINGS LUDLUM 2220 G M METER PLUME CLOSED OPEN CONC. AGX-2** PARTICU1 ATE *** SEGMENT DISTANCE MAP WINDOW WINDOW I-131 CARTRIDGE FILTER No. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM)

      "~i$b0 ~~55Tk' ~~Ei.bb" '~~i$bb~                              ib$bb~~~          'i$i9kIi6 ~~E5~kkEb                          ~l55~~

BOUNDARY YELLOW 0.70 1.40 1.79E-17 AS READ <50 GREEN 0.07 0.14 1.79E AS READ <50 2.00 0.80 BLUE 10.00 20.00 6.17E-09 198 <50

YrLLOW l.00 2.00 6.17E-10 AS READ <50 GREEN 0.10 0.20 6.17E-ll AS READ <50 3.00 1.60 BLUE 14.00 28.00 1.91E 07 6123 344 YELLOW l.40 2.80 1.91E-08 612 <50 GREEN 0.14 0.28 1.91E-09 61 <$0 4.00 2.60 BLUE 8.00 16.00 9.26E-08 2963 167 YELLOW 0.80 1.60 9.26E-09 296 <50 GREEN 0.08 0.16 9.26E-10 AS READ <50 4 5.00 3.60 BLUE 5.00 10.00 7.41E-10 AS READ <50 YELLOW 0.50 1.00 7.41E-ll AS READ <50 GREEN 0.05 0.10 7.41E-12 AS READ <50 6.00 4.40 BLUE 0.04 0.08 5.74E-10 AS READ <50 YELLOW AS READ AS READ 5,74E-ll AS READ <30 GREEN AS READ AS READ 5.74E-12 AS READ <50 r

I 4 1 NOTES:

Air sample data are based on a sample volume of 177 liters. If different volumes are collected, the air sample data provided in the tables should be adfusted proportionally. For example, if a 89 liter sam divlde the value given in the table by 2 (two)ple and wasprovide collected instead value the resulting of 177toliters, the players.

,              ** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 cpm /dpm with I

the AGX 2 cartridge. Therefore, I-131 cone. (uci/cc) X 3.2E+10 will calculate the - the net s. ample count rate in cpm on 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 Yrom the I-131 air concentration for a 177 liter sample volume.

_. . . . _ - - . . . .- -. = - ~ _ _ . . _ - - . . .

                                                                                                                    . - -. -                        -.        . ~ .
                                                      ~

1 Rev. O TABLE 9.7.6c Page 9.7-100 STATE OF NEW HAMPSHIRE FIELD DATA AT CLOCK TIME 0945-1000 (SCENARIO TIME 7:00 - 7:15) GAMMA SURVEY DATA AIR SAMPLE DATA (20 CU Fr)* WAIST AND GROUND LEVEL READINGS E-140/HP-210 G-M METER PLUME CLOSED OPEN CONC. AGX-2** PARTICULATE *** SEGMENT DISTANCE MAP WINDOW VINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM)

                                               ~~"
                 ~~~5b0 ~ ~555b' ~ ~B5.bb                7bb~       54$bb ~                           5$b2b55     E5'RbEb                  ~~E5b'~~~

BOUNDARY YELLOW 0.70 1,40 8,02E-19 AS READ <50 , GREEN 0.07 0.14 8.02E-20 AS READ <50 l 2.00 0.80 BLUE 10.00 20.00 9.88E 10 AS READ <50 ) YELLOW 1.00 2.00 9.88E-11 AS READ <50 GREEN 0.10 0.20 9.88E-12 AS READ <50 j I 3.00 1.60 BLUE 14.00 28.00 2.47E-07 775 1407 YELLOW 1.40 2.80 2.47E-08 78 141 l GREEN 0.14 0.28 2.47E-09 AS READ <50 4.00 2.60 BLUE 8.00 16.00 1.36E-07 426 774 YELLOW 0.80 1.60 1.36E-08 AS READ 77 GREEN -0.08 0.16 1.36E 09 AS READ <50 5.00 3.60 BLUE 5.00 10.00 7.41E-08 233 422 ; YELLOW 0.50 1.00 7.41E 09 AS READ <50 GREEN 0.05 0.10 7.41E-10 AS READ <50 6.00 4.40 BLUE 0.04 0.08 5.74E-10 AS READ <50 YELLOW AS READ AS READ 5.74E-ll AS READ <50 GREEN AS READ AS READ 5.74E-12 AS READ <30 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 sam divide the value given in the table by 2 (two)ple andwas collected provide instead of the resulting 20 cu value to ft, the players.

                        ** The E-140/HP-210 detector efficiency for I-131 was assumed to be 0.0024 cpm /dpm with the.AGX-2 cartridge. Therefore, I-131 cone. (uCi/cc) X 3.lE+09 will calculate the the net sample count rate in cpm on the ACX-2 cartridge.
                      *** For analysis of the particulate filter it is assumed that a G-M survey meter is used                                                      l to obtain the sample count races. The Illter count rate was estimated from the                                                          i I 131 air concentration for a 20 cu foot sample volume.

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.                                                                                                               Rev. O TABLE 9.7.7a                                                   Page 9.7-llA VERMONT YANKEE FIELD DATA AT CLOCK TIME 1000-1015 (SCENARIO TIME 7:15 - 7:30)

AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM-14** SAM-II RM-14*** PLUME CONC. PARTICULATE SEGMENT DISTANCE MAP PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET... CPM) ... . (NET CPM) (NET CPM) BOUNDARY YELLOW <1 2450 8.02E.19 <40 AS READ <40 GREEN <1 245 8.02E-20 <40 AS READ <40 2.00 0.80 BLUE 10 35000 1.11E-09 <40 AS READ <40 YELLOW 1 3500 1.11E-10 <40 AS READ <40 GREEN <1 350 1.11E-11 <40 AS READ <40 3.00 1.50 BLUE 17 OSH 2.72E-07 1521 4563 272 YELLOW 2 5950 2.72E-08 152 456 <40 GREEN <1 595 2.72E-09 <40 AS READ <40 4.00 2.40 BLUE 10 35000 1.85E-07 1037 3111 185 YELLOW 1 3500 1.85E-08 104 311 <40 GREEN <1 350 1.85E-09 <40 AS READ <40 5.00 3.40 BLUE 6 21000 1.05E-07 588 1763 105 YELLOW <1 2100 1.05E-08 59 176 <40 GREEN <1 210 1.05E-09 <40 AS READ <40 6.00 4.30 BLUE 4 14000 5.56E-08 311 933 56 YELLOW <1 1400 5.56E-09 <40 93 <40 GREEN <1 140 5.56E.10 <40 AS READ <40 , 1 7.00 5.10 BLUE <1 105 4.63E 10 <40 AS READ <40 i YELLOW <1 AS READ 4.63E 11 <40 AS READ <40 l-GREEN <1 AS READ 4.63E-12 <40 AS READ <40 NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas provide collected instead value the resulting of 100toliters, the players.

       ** The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge. Therefore, I-131 cone. (uCi/ce) X 5.6E+09 will calculate the net sample count rate in epm on the silver zeolite cartridge.
      *** The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample.

OSH Off-Scale High (Count rate higher than upper scale of the instrumentation)

                                                                          ..        -- - . - - - .          -..        -- -            - ~.

Rev. O TABLE 9. 7. 7b Page 9.7-11B STATE OF VERMONT FIELD DATA AT CLOCK TIME 1000-1015 (SCENARIO TIME 7:15 - 7:30) GAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G-M METER PLUME CLOSED OPEN CONC. AGX-2** PARTICU1 ATE *** SECMENT DISTANCE MAP WINDOW WINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM)

                                             ~~
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BOUNDARY YELLOW 0.70 1.40 8.02E-19 AS READ <50 GREEN 0.07 0.14 8.02E-20 AS READ <50 2.00 0.80 BLUE 10.00 20.00 1.11E-09 AS READ <50 YELLOW 1.00 2.00 1.11E-10 AS READ <50 GREEN 0.10 0.20 1.11E-ll AS READ <50 3.00 1.50 BLUE 17,00 34.00 2.72E-07 8691 489 YELLOW 1.70 3.40 2.72E-08 869 <50 GREEN 0.17 '0.34 2.72E-09 87 <50 4.00 2.40 BLUE 10.00 20.00 1.85E-07 5926 333 YELLOW 1.00 2.00 1.85E 08 593 <50 GREEN 0.10 0.20 1.85E-09 59 <50 5.00 3.40 BLUE 6.00 12.00 1.05E-07 3358 189 YELLOW 0.60 1.20 1.05E-08 336 <50 GREEN 0.06 0.12 1.05E-09 AS READ <50 6.00 4.30 BLUE 4.00 8.00 5.56E-08 1778 100 ' YELLOW 0.40 0.80 5.56E-09 178 <50 GREEN 0.04 0.08 5.56E-10 AS READ <50 ! 7.00 5.10 BLUE 0.03 0.06 4.63E-10 AS READ <50 YELLOW AS READ AS READ 4.63E 11 AS READ <50 GREEN AS READ AS READ 4.63E-12 AS READ <50 l l l I I l l l l l NOTES:

Air sample data are based on a sample' volume of 177 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 89 liter sam divide the value given in the table by 2 (two)ple andwas provide collected instead value the resulting of 177toliters,

 ,                the players.
              ** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 cpm /dpm with-the ACX 2 cartridge. Therefore, I-131 cone. (uci/ce) X 3.2E+10 vill calculate'the

i the net sample count rate in cpm on 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 concentration for a 177 liter sample volume.

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l Rev. O TABLE 9.7.8a Fage 9.7-12A VERMONT YANKEE FIELD DATA AT CLOCK TIME 1015-1030 (SCENARIO TIME 7:30 - 7:45) AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM-14** SAM-II RM-14*** PLUME CONC. PARTICULATE l SEGMENT DISTANCE MAP PIC 6 RM-14 I-131 SILVER ZEOLITE FILTER NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET .CPM) (NET CPM) BOUNDARY YELLOW <1 2450 6.17E-21 <40 AS READ <40 CREEN <1 245 6.17E-22 <40 AS READ <40 2.00 0.60 BLUE 9 31500 2.47E-11 <40 AS READ. <40 YELIDW <1 3150 2.47E-12 <40 AS READ <40 GREEN <1 315 2.47E-13 <40 AS READ <40 3.00 1.40 BLUE 20 OSH 3.09E-07 1728 5185 309 YELLOW 2 7000 3.09E-08 173 519 <40 GREEN <1 700 3.09E-09 <40 52 <40 4.00 2.10 BLUE 12 42000 2.47E-07 1383 4148 247 YELLOW l 4200 2.47E-08 138 415 <40 CREEN <1 420 2.47E-09 <40 AS READ <40 5.00 3.00 BLUE 8 28000 1.42E-07 795 2385 142 YELLOW <1 2800 1.42E-08 80 239 <40 GREEN <1 280 1.42E-09 <40 aS READ <40 6.00 4.00 BLUE 5 17500 8.02E-08 449 1348 80 YELLOW <1 1750 8.02E-09 45 135 <40 GREEN <1 175 8.02E-10 <40 AS READ <40 7.00 5.00 BLUE 3 10500 4.88E-08 273 819 49-YELLOW <1 1050 4.88E-09 <40 82 <40 GREEN <1 105 4.88E-10 <40 AS READ <40 8.00 5.70 BLUE <1 105 3.95E.10 <40 AS READ <40 YELLOW <1 AS READ 3.95E-ll <40 AS READ <40 GREEN <1 AS READ 3.95E-12 <40 AS READ <40 NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes -

are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas collected provide instead of the resulting 100toliters, value the players.

       ** The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge. Therefore, I-131 conc. (uci/ce) X 5.6E+09 will calculate                         i the net sample count rate in cpm on the silver zeolite cartridge.
     *** The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample.                                                                       ;

OSH Off scale High (Count rate higher than upper scale of the instrumentation) l l l

Rev. O TABLE 9.7.8b Page 9.7-12B STATE OF VEPJiONT FIELD DATA AT CLOCK TIME 1015 1030 (SCENARIO TIME 7:30 - 7:45) GAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINGS LUDLUM 2220 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) uCi/cc (NET CPM) (NET CPM)

                                                                                                                                                           ~~
    ~~~[$b0 "EkTb' "b[.bb"                                             ~h$bb~     id$bb~ "                ~5$5hb52b " b~kb1b               ~~k5b BOUNDARY YELLOW                                      0.70       1.40                    6.17E-21         AS READ          <50 GREEN                     0.07       0.14                    6.17E-22         AS READ          <50 2.00                      0.60         BLUE                      9.00      18.00                    2.47E-ll         AS READ-         <50 YELLOW                     0.90       1.80                    2.47E-12         AS READ          <50 GREEN                     0.09       0.18                    2.47E-13         AS READ          <50 3.00                       1.40        BLUE                     20.00      40.00                    3.09E-07           9877             556 YELLOW                     2.00       4.00                    3.09E-08              988          . 56' GREEN                     0.20       0.40                    3.09E-09               99         <50 4.00                       2.10        BLUE                     12.00      24.00                    2.47E-07           7901             444 YELLOW                     1.20       2,40                    2.47E-08              790         <50                         :

GREEN 0.12 0.24 2.47E-09 79 <50 5.00 3.00 BLUE 8.00 16.00 1.42E-07 4543 256 YELLOW 0.80 1.60 1.42E-08 454 <50 GREEN 0.08 0.16 1.42E-09 AS READ <50 6.00 4 00 BLUE 5.00 10.00 8.02E-08 2568 144 YELLOW 0.50 1.00 8.02E-09 257 <50 GREEN 0.05 0.10 8.02E-10 AS READ <50 7.00 5.00 BLUE 3.00 6.00 4.88E 08 1560 88 YELLOW 0.30 0.60 4.88E-09 156 <50 GREEN 0.03 0.06 4.88E-10 AS READ <50 8.00 5.70 BLUE 0.03 0.06 3.95E 10 AS READ <50 YELLOW AS READ AS READ 3.95E-ll AS READ <50 ' GREEN AS READ AS READ 3.95E-12 AS READ '< 50 i

                                                                                                                                                                       ;I i

NOTES:

Air sample data are based on a sample volume of 177 liters. If different volumes are collected, the air sample data provided in the tables should be adiusted proportionally. For example, if a 89 liter sam t divide the value given in the table by 2 (two)ple andwas collected instead of 177.toliters, provide the resulting value the players.

          ** The Ludlum 2220 detector efficiency for I 131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge. Therefore, I-131 conc. (uci/cc) X 3.2E+10 will calculate the                                                                     :

the net sample count rate in epm on 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 Illter count rate was estimated Irom the I-131 air concentration for a 177 liter sample volume, i S

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FIGURE 9.7-9 b. .- .- 2 _.. ( . I E SCALE [

    .                   . %h                           A.             s          CLOCK TIME:1030
                                                                                  .n...,                               s               ,- ., to 1045 .

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f Rev. O TABLE 9.7.9a Page 9.7-13A > VERMONT YANKEZ FIELD DATA AT CLOCK TIME 1030-1045 (SCENARIO TIME 7:45 - 8:00) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM-14** SAM-II RM-14*** PLUME CONC. PARTICULATE SEGMENT DISTANCE MAP PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) BOUNDARY YELLOW <1 2450 6.17E-21 <40 AS READ <40 GREEN <1 245 6.17E-22 <40 AS READ <40 , 2.00 0,60 BLUE 9 31500 2.47E-11 <40 AS READ <40 YELLOW <1 3150 2.47E-12 <40 AS READ <40 ' GREEN <1 315 2.47E-13 <40 AS READ <40 3.00 1.20 BLUE 22 OSH 2.84E-07 1590 4770 .280 YELLOW 2 7700 2.84E-08 159 477 <40 GREEN <1 770 2.84E-09 <40 AS READ <40 . 4.00 2.00 BLUE 14 49000 2.47E-07 1383 4148 250 YELLOW 1 4900 2.47E-08 138. 415 <40 CREEN <1 490 2.47E-09 <40 AS READ <40 5.00 2.80 BLUE 10 35000 1.79E-07 1000 3007 180 YELLOW 1 3500 1.79E-08 100 301 <40 GREEN <1 350 1.79E-09 <40 AS READ <40 ; 6.00 3.60 BLUE 6 21000 1.11E-07 620 1867 110 YELLOW <1 2100 1.11E-08 60 187 <40 GREEN <1 210 1.11E-09 <40 AS READ <40 7.00 4.60 BLUE 4 14000 6.17E-08 350 1037 60 YELLOW <1 1400 6.17E-09 <40 104 <40 GREEN <1 140 6.17E-10 <40 AS READ <40 8.00 5.60 BLUE 3 10500 4.14E-08 230 695 40 YELLOW <1 1050 4.14E-09 <40 69 <40 GREEN <1 105 4.14E-10 <40 AS READ <40 , 9.00 6.30 BLUE <1 70 3.40E-10 <40 AS READ <40 YELLOW <1 AS READ 3.40E-11 <40 AS READ <40. ~ GREEN <1 AS READ 3.40E-12 <40 AS READ <40 NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adiusted proportionally.

divide the valueFor example, given if a 50 in the table byliter sam and 2 (two)ple was collected provide insteaB of the resulting 100 to value lit < t,*, the players. ,

          ** The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the silver                                                I-131 conc. (uCi/ce) X 5.6E+09 will calculate the netzeolite sample cartridge.

count rateTherefore, in epm on the silver zeolite cartridge.

         *** The particulate filter sample count rate (epm) was estimated from the I-131 air concentration for a 100 liter sample.

OSH Off-Scale High (Count rate higher than upper scale of the instrumentation)

Rev. O TABLE 9.7.9b Page 9.7-13B STATE OF VERMONT FIELD DATA AT CLOCK TIME 1030-1045 (SCENARIO TIME 7:45 - 8:00) I GAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G-M METER > PLUME CLOSED OPEN CONC. AGX-2** PARTICULATE *** SECMENT DISTANCE HAP VINDOW VINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) .(mR/hr) uCi/cc (NET CPM) (NET CPM)

            ~i$b0 hiTk ~ bLbb                ~)$bb       14$bb          6$5)k2b~~h~kkkb 2                      ~~kSb~~~~~

BOUNDARY YELLOW 0.70 1.40 6.17E-21 AS READ <50 , GREEN 0.07 0.14 6.17E-22 AS READ <50 -l 2.00 0.60 BLUE 9.00 18.00 2.47E-11 AS READ <50 YELLOW 0.90 1.80 2.47E-12 AS READ <50 ; GREEN 0.09 0.18 2.47E-13 AS READ <50 3.00 1.20 BLUE 22.00 44.00 2.84E-07 9086 311 ! YELLOW 2.20 4.40 2.84E-08 909 51 .' GREEN 0.22 0.44 2.84E-09 91 <50 2.00 14.00 28.00 2.47E-07 7901 444 4.00 BLUE

                                                                                                              <50 YELLOW             l.40        2.80         2.47E-08         790 GREEN             0.14        0 28         2.47E-09            79              <50 I

5.00 2.80 BLUE 10.00 20.00 1.79E-07 5728 322 YELLOW l.00 2.. 1.79E-08 573 <50 GREEN 0.10 0.20 1.79E-09 57 <50 , 6.00 3.60 BLUE 6.00 12.00 1.11E-07 3556 200 . YELLOW 0.60 1.20 1 llE-08 356 <50 i GREEN 0.06 0.12 1.11E-09 AS READ <50 ; 7.00 4.60 BLUE 4.00 8.00 6.17E-08 1975 111 YELLOW 0.40 0.80 6.17E-09 198 <50 GREEN 0.04 0.08 6.17E-10 AS READ <50 l

                                                                                                                                  .i 5.60                      3.00        6.00          4.14E-08       1323                   74 8.00              BLUE 4.14E-09         132               <50 YELLOW             0.30        0.60 GREEN             0.03        0.06          4.14E-10    AS READ               .< 50 9.00      6.30    BLUE              0.02         0.04         3.40E-10    AS REAP                <50 YF.LLOW        AS READ AS READ               3.40E-ll     AS READ                <50 GREEN         AS READ AS READ               3.40E-12     AS READ               <50                  ;

1 1 NOTES:

Air sample data are based on a cample volume of 177 liters. If different volumes arecollected,theairsampledatahrovidedinthetablesshouldbeadjusted proportionally. For example, if a B liter sam I

divide the value given in the table by 2 (two)ple andwas collected provide insteadvalue the resulting of 177toliters, the players.

                ** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 epm /dpm with the AGX-2 cartridge. Therefore, I-131 conc. (uci/ce) X 3.2E+10 vill calculate the

.r the net sample count rate in cpm on the AGX-2 cartridge.

               *** For analysis of the particulate filter          it is assumed that a G-M survey meter is used to obtain the tcmple count rates. The lilter count rate was estimated from the I-131 air     3 -c  tration for a 177 liter sample volume.

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} ' f . ) 1.N IC H E S T hI s . - -,s / - / ;- /s , a %r, s M,,, " "//re b < 9, j. #'" L * ~ [ ' . FIGURE 9.7-10 i i i4 , , , ~- SCALE 1 I s * & ,I +- h. A, .. CLOCK . -ee. n.. , - TIME: x 1045 u g to 1100 -- s _m ______m________..-=______a__ _ _ _ _ _ _ _ _ _ - _ - _ _ _ . _ _ - . _ . - _ . _______.____-__m __-__ -'.__ " % W 9 et- ur .+- -W 'w tv>w .T ed i Rev. 0 TABLE 9.7.10a Page 9.7 14A VERMONT YANKEE FIELD DATA AT CLOCK TIME 1045-1100 (SCENARIO TIME 8:00 8:15) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM-14** SAM-II Re l'***- 4 PLUME CONC. PARTIOLIATE , SEGMENT DISTANCE MAP PIC-6 RM-14 I-131 SILVER ZEOLITE FI LTER NO. (MILES) AREA (mR/hr) (CFM) uCi/cc (NET C?M) (NET CPM) (NEf. CPM) BOUNDARY YELLOW <1 25 6.17E-23 <40 #S READ <:40 GREEN <1 2 6.17E-24 <40 11 READ <40 2.00 0.60 BLUE <1 315 2.4)E-13 <40 AS READ <40 YELLOW <1 32 2.47E-14 <40 AS READ <40 GREEN <1 3 2.47E-15 <40 AS READ <40- ! 1 3.00 1.20 BLUE 22 OSH 3.21E-07 1800 5'93 320 YELLOW 2 7700 3.21E.08 160 539 <40 GREEN <1 770 3.21E-09 <40 54 <40 4.00 1.90 BLUE 15 OSH 2.65E.07 1500 4459 265 YELLOW 2 5250 2.65E.08 150 446 <40 GREEN <1 525 2.65E-09 <40 A3 READ <40 , 5.00 2.60 BLUE 10 35000 2.04E.07 1140 3422 200 YELLOW 1 3500 2.04E.08 114 342 <40 GREEN <1 350 2.04E-09 <40 A3 READ <40 ! 6.00 3.40 BLUE 8 28000 1.42E.07 800 2385 140 YELLOW <1 2800 1.42E.08 80 239 <40 ': GREEN <1 280 1.42E-09 <40 AS READ <40 7.00 4.20 BLUE 5 17500 9.26E.08 520 1556 90 . YSLLOW <1 1750 9.26E.09 50 156 <40 GREEN <1 175 9.26E.10 <40 AS READ <40 8.00 5.20 BLUE 4 14000 5.62E-08 315 944 55 YELLOW <1 1400 5.62E-09 <40 94 <40 GREEN <1 140 5.62E 10 <40 AS READ <40 9.00 6.20 BLUE 3 8750 3. 5 2 E- O'8 200 591 <40. ^ YELLOW <1 875 3.52E 09 <b 59 <40 GREEN <1 88 3.52E.10 <@ AS READ <40. ; 10.00 6.90 BLUE G 70 2.96E-10 <40 AS READ <40 YELLOW d AS READ 2.96E-11 <40 AS READ <40 i GREEN <1 AS READ 2.96E-12 <40 AS READ <40 i NOTES:

Air samplo data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be ad.iusted proportionally. For example, if a 50 liter sam divide the.value given in the table by 2 (two)ple andwas providecollected instead value the resulting of 100toliters, the players.

** The RM.14 detector efficiency for I.131 was assumed te be 0.025 cpm /dpm with the silver zeolite cartridge. Therefore, I-131 conc. the net sample count rate in epm on the silver zeo(uci/cc) X 5. tie +09 will calculate lite cartridge. *** The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample. OSH Off-Scale High (Count rate higher than upper scale of the instrumentation)> l v . i Rev. 0 l TABLE 9.7.10b Page 9.7-14B STATE C' . ' RMONT FIELD DAT4 AT CLOCK TIME 1045-1100 (SCENARIO TIME 8:00 - 8:15) CAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINGS LUDLUM 2220 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) ~~~ ~ uCi/cc (NET CPM) (NET CPM) ~~~[$b0 ~ ~55Tb' ~ ~bLbk' ~ ~ ~ ~b$b7 ~b$54 6$575$55~~15~kEkb ~~k5b~~~~~ BOUNDARY YELIDW AS READ 0.00 6.17E-23 AS READ <50 GREEN AS READ 0.00 6.17E-24 AS READ <50 2.00 0.60 BLUE 0.09 0.18 2.47E-13 AS READ <50 YELLOW AS READ 0.00 2.47E-14 AS READ <50 GREEN AS READ 0.00 2.47E-15 AS READ <50 3.00 1.20 BLUE 22.00 44.00 3.21E-07 10272 578 YELLOW 2.20 4.40 3.21E-08 1027 58 GREEN 0.22 0.44 3.21E-09 103 <50 4.00 1.90 BLUE 1$.00 30.00 2.65E-07 8494 478 YELLOW l.50 3.00 2.65E 08 849 <50 GREEN 0.15 0.30 2.65E-09 85 <50 5.00 2.60 BLUE 10.00 20.00 2.04E-07 6519 367 YELLOW l.00 2.00 2.043-08 652 <50 GREEN 0.10 0.20 2.04E-09 65 <50 6.00 3,40 BLUE 8.00 16.00 1.42E-07 4543 256 , YELLOW 0.80 1.60 1.42E-08 454 <50 GREEN 0.08 0.16 1.42E-09 AS READ <50 7.00 4.20 BLUE 5.00 10.00 9.26E-08 2963 167 YELLOW 0.50 1.00 9.26E-09 296 <50 GREEN 0.05 0.10 9.26E-10 AS READ <50 8.00 5.20 BLUE 4.00 8.00 5.62E-08 1798 101 YELLOW 0.40 0.80 5.62E-09 180 <50 GREEN 0.04 0.08 5.62E-10 AS READ <50 9.00 6.20 BLUE 2.50 5.00 3.52E-08 1126 63 , YELLOW 0.25 0.50 3.52E-09 113 <50 GREEN 0.03 0.05 3.52E-10 AS READ <50 10.00 6.90 BLUE 0.02 0.04 2.96E-10 AS READ <50 YELLOW AS READ AS READ 2.96E-ll AS READ <50 GREEN AS READ AS READ 2.96E-12 AS READ <50 , NOTES: !

Air sample data are based on a sample volume of 177 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 89 liter sam divide the value given in the table by 2 (two)ple andwas collected provide instead of the resulting 177toliters, value the players.

** The Ludlum 2220 detector efficies.cv for 1-131 was assumed to be 0.080 cpm /dpm with > the AGX-2 cartridge. Therefore, I-131 conc. (uCi/cc) X 3.2E+10 will calculate the the net sample count rate in cpm on 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 couat rates. The Eilter count rate was estimated from the I-131 air concentration for a 177 liter sample volume. - .l,[i TG q;= 4 ,)%)a&$ \- e ~' = 5; ,^ 7 s _ L 1 ' T' S . / s g \ ' . - ? t E - qi - D g ,. j \.. H - . +. . pk# n.' . / / t4,<;.2c.5"$ *e. ? 3,WV -w./'CN. = . _E g 1 , i l aS 3 - L .%? js ;y i;gTx.4yd(a c ,A s ,f [ C E'.E )ha.MgtN'p',, 4 .w r ,S gcb~ ' A hf pi.2 T , xs.:1>N$ . 3 . le S ' a ds . $.n ' E nW \ yh .. . { il , ,ts !i J . ,,,/Cd,%~9' l~ s J ' w 1 5 1 1 1 )1 .% 1 y, a' s- .~ . ~ ,@s ./ nh* $g , - 7 o g, . t s-LLhb- - 9

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y gJlt [~ 5 9 * !ia u s a '2 m 0h,, 5l. 4,#' ,pI Gc p ^# ,J ' 1 ,g s s[i I r e v f. m _. a-n 4 %n.$ e d g,% M s_ Mya le &;gs a w a. ;G w r 9 'a i, , r ** fy %. [ .. , '5 ) y m1 Ii t 4 , ,g s r - ex ; M-pC-m _ a - m t- %. m y yd y m. 3v

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t - _ r _ F %f9P a m x _ # A l a - u f i L [ l a y , ,v M;x / n a ,4 { 3eh<*** n H /V \ t ;; l,! Rev. O TABLE 9.7.11a Page 9.7-15A VERMONT YANKEE FIELD DATA AT CLOCK TIME 1100-1115 (SCENARIO TIME 8:15 - 8:30) AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM-14** SAM-11 RM-14*** PLUME CONC. PARTICULATE SECMENT DISTANCE MAP PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER No. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) ...g. ....g. .. g .. ...g.... ..g.... .. . . .g. . . g .g ...g.... YELLOW <1 35 4.01E-13 <40 AS READ <40 GREEN <1 AS READ 4.01E-14 <40 AS READ <40 > 2.00 1.30 BLUE <1 700 3.21E-09 <40 54 <40 YELLOW <1 70 3.21E.10 <40 AS READ <40 GREEN <1 AS READ 3.21E-11 <40 AS READ <40 3,00 1.90 BLUE 16 OSH 2.96E.07 1660 .4978 300 YELLOW 2 5600 2.96E-08 166 498 <40 GREEN <1 560 2.96E-09 <40 AS READ <40 4.00 2.60 BLUE 10 35000 2.16E-07 1210 3630 215 i YELLOW 1 3500 2.16E-08 120 363 <40 GREEN <1 350 2.16E-09 <40 AS READ <40 5.00 3.30 BLUE 9 31500 1.60E-07 900 2696 160 YELLOW <1 3150 1.60E-08 90 270 <40 GREEN <1 315 1.60E-09 <40 AS READ <40 6.00 4.10 BLUE 6 21000 1.11E-07 620 1867 110 YELLOW <1 2100 1.11E-08 60 187 <40 , GREEN <1 210 1.11E-09 <40 AS READ <40 7.00 5.00 BLUE 4 14000 7.41E-08 415 1244 75 YELIDW <1 1400 7.41E-09 45 124 <40 GREEN <1 140 7.41E-10 <40 AS READ <40-8.00 6.00 BLUE 3 10500 4.69E 08 260 788 50 YELLOW <1 1050 4.69E 09 <40 79 <40 GREEN <1 105 4.69E-10 <40_ AS READ <40 , 9.00 6.90 BLUE 2 7000 3.09E-08 170 519 <40 YELLOW <1 700 3.09E-09 <40 52 <40 GREEN <1 70 3.09E-10 <40 AS-READ <40 10.00 7.60 BLUE <1 70 2 59E-10 <40 AS READ <40 YELLOW <1 AS READ 2.59E-11 <40 AS READ <40 GREEN <1 AS READ 2.59E-12 <40 AS READ <40 l l NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas collected provide instead value the resulting of 100toliters, the players.

** The RM-14 detector efficiency for 1 131 was assumed to be 0.025 cpm /dpm with the silver 1 131 conc. (uCi/cc) X 5.6E+09 will calculate - the netzeolite sample cartridge. count rate Therefore, in epm on t he silver zeolite cartridge. *** The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample. OSH Off-Scale High (Count rate higher than upper scale of the instrumentation) l Rev. O TABLE 9.7.11b Page 9.7-15B STATE OF VERMONT FIELD DATA AT CLOCK TIME 1100-1115 (SCENARIO TIME 8:15 - 8:30) GAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* LUDLUM 2220 G-M METER WAIST AND GROUND LEVEL READINGS PARTICULATE *** CLOSED OPEN CONC. AGX-2** PLUME I-131 CARTRIDGE FILTER SEGMENT DISTANCE MAP VINDOW WINDOW AREA (mR/hr) (mR/hr) uC1/cc (NET CPM) (NET CPM) NO. (MILES) ~ ~~ ~~~i$b0 ~~ ~b$ 7b ~ ~bLbb~ ~ ~ ~'b$5b~~b$2b~~~ ~E$ bib $5h~'SRkb <5b~~~ 0.01 0.02 4.01E-13 AS READ <50 ' YELLOW <50 GREEN AS READ AS READ 4.01E 14 AS READ , 0.20 0.40 3.21E-09 103 <50 2.00 1.30 BLUE 3.21E-10 AS READ <50 YELLOW 0.02 0.04 <50 GREEN AS READ AS READ 3.21E-ll AS READ 16.00 32.00 2.96E-07 9481 533 3.00 1.90 BLUE 2.96E-08 948 53 YELLOW 1 60 3.20 95 <30 GREEN 0.16 0.32 2.96E-09 10.00 20.00 2.16E 07 6914 389 , 4.00 2.60 BLUE 2.16E-08 691 <50 YELLOW 1.00 2.00 <30 GREEN 0.10 0.20 2.16E-09 69 9.00 18.00 1.60E-07 5136 289 5.00 3.30 BLUE 1.60E-08 514 <50 YELLOW 0.90 1.80 GREEN 0.09 0.18 1.60E-09 51 <50

6.00 12.00 1.11E-07 3556 200 6.00 4.10 BLUE 1.11E-08 356 <50 YELLOW 0.60 1.20 <50 GREEN 0.06 0.12 1.11E-09 AS READ 4.00 8.00 7.41E-08 2370 133 7.00 5.00 BLUE <50 YELLDW 0.40 0,80 7.41E-09 237 GREEN 0.04 0.08 7.41E-10 AS READ <50 3.00 6.00 4.69E-08 1501 84 8.00 6.00 BLUE 150 <50 YELLOW 0.30 0.60 4.69E-09 GREEN 0.03 0.06 4.69E-10 AS READ <50 2.00 4.00 3.09E-08 988 56 9.00 6.90 BLUE 3.09E-09 99 <50 YELLOW 0.20 0.40 <50 GREEN 0.02 0.04 3.09E-10 AS READ 0.02 .0.04 2.59E 10 -AS READ <50 10.00 7.60 BLUE 2.59E-11 AS READ <50 YELLOW AS READ AS READ <50 GREEN AS READ AS READ 2.59E-12 AS READ l

l NOTES:

Air sample data are based on a sample volume of 177 liters. If different volumes {

are collected, the air sample data provided in the tables should be adjusted , proportionally. For example, if a 89 liter sample was collected instead of 177 liters, i d,1vlde the value given in the table by 2 (two) and provide the resulting value to tne players. ** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 epm /dpm with the AGX-2 cartridge. Therefore, I-131 cone. (uCi/ce) X 3.2E+10 will calculate the the net sample count rate in cpm on the AGX-2 cartridge. , 1 *** For analysis of the particulate filter it is assumed that a G-M survey meter is used l to obtain the sample count rates. The filter count rate was estimated from the f I-131 air concentration for a 177 liter sample volume. I i H' - , { ' ), 'l ,- % f,j ,>oy c p6 n# 5 , .k g f i ,. s g x i n NT \ w; / S k , g 4* _ E a ,i g* . H a> *f4 p j. . , / - . - C - ^= . Q. / ! ] yfyI u9 ) , 'i .' N. :. ". i'.gb re RN'x: . A e '. 1 n + P *

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i 4 2 o a gp- 7 m r O o r, sm % *& 5, %b b e lW" - Y "* )D n.pi F i l x o s _ f.t m / % ""'*'r- e m H a () ' S' _ y/ ,\ T + ._ Rev. O TABLE 9.7.12a Page 9.7-16A VERMONT YANKEE FIELD DATA AT CLOCK TIME 1115 1130 (SCENARIO TIME 8:30 - 8:45) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM-14** SAM-II RM-14*** PLUME CONC. . PARTICULATE SEGMENT DISTANCE MAP PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) YELLOW <1 70 3.64E-10 <40 AS READ <40 GREEN <1 AS READ 3.64E-11 <40 AS READ <40 2.00 2.10 BLUE <1 525 2.84E-09 <40 AS READ <40 YELLOW <1 53 2.84E-10 <40 AS READ <40 GREEN <1 AS READ 2.84E-ll <40 AS READ <40 3.00 2.70 BLUE 12 42000 2.28E-07 1270 3837 230 YELLOW l 4200 2.28E-08 130 384 <40 GREEN <1 420 2.28E-09 <40 AS READ <40 4.00 3.30 BLUE 9 31500 1.67E-07 930 2800 170 YELLOW <1 3150 1.67E-08 90 280 <40 GREEN <1 315 1.67E-09 <40 AS READ <40 5.00 4,10 BLUE 7 24500 1.23E-07 690 2074 125 YELLOW <1 2450 1.23E-08 70 207 <40 GREEN <1 245 1.23E-09 <40 AS READ <40 6.00 4.80 BLUE 5 17500 9.26E 08 520 1556 90 YELLOW <1 1750 9.26E.09 52 156 <40 GREEN <1 175 9.26E-10 <40 AS READ <40 7.00 5.70 BLUE 4 14000 6.05E-08 340 1016 60 YELLOW <1 1400 6.05E-09 <40 102 <40 GREEN <1 140 6.05E-10 <40 AS READ <40 8.00 6.70 BLUE 3 10500 3.95E-08 220 664 <40 YELLOW <1 1050 3.95E-09 <40 66 <40 GREEN <1 105 3.95E 10 <40 AS READ <40 9.00 7.60 BLUE 2 7000 2.59E-08 145 436 <40 YELLOW <1 700 2.59E-09 <40 AS READ <40 GREEN <1 70 2.59E-10 <40 AS READ <40 10.00 8.30 BLUE <1 70 2.28E-10 <40 AS READ <40 YELLOW <1 AS READ 2.28E-ll <40 AS READ <40 GREEN <1 AS READ 2.28E-12 <40 AS READ <40 NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas collected provide instead value the resulting of 100toliters, the players.

** The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the silver 1-131 cone. (uci/ce) X 5.6E+09 will calculate the netzeolite sample cartridge. count rate Therefore, in cpm on t he silver zeolite cartridge. 1 *** The pasticulate filter sample count rate (cpm) was estimated from the I-131 air I concentration for a 100 liter sample. l l a I 1 _ l l , Rev. O TABLE 9.7.12b Page 9.7-16B STATE OF VERMONT FIELD DATA 'AT CLOCK TIME 1115-1130 (SCENARIO TIME 8:30 - 8:45) GAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G-M METER PLUME CLOSED OPEN CONC. AGX-2** PARTICULATE *** SEGMENT DISTANCE MAP UINDOW UINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr). (mR/hr) uCi/cc (NET CPM) ' (NET CPM) ~~~5b0 ~i[5b ~~bLbb' ~~~~b[2b' 'b'Eb' ~5$65b$b9 [57 ~~k5b YELLOW 0.02 0.04 3.64E-10 AS READ <50 GREEN AS READ AS READ 3.64E-ll AS READ <50 2.00 2.10 BLUE 0.15 0.30 2.84E-09 91 <50 YELLOW 0.02 0.03 2.84E-10 AS READ <30 GREEN AS READ AS READ 2.84E-ll AS READ <50 . 3.00 2.70 BLUE 12.00 24.00 2.28E-07 7309 411 YELLOW 1.20 2.40 2.28E-08 731 <50 GREEN 0.12 0.24 2.28E-09 73 <50 4.00 3.30 BLUE 9.00 18.00 1.67E-07 5333 300 YELLOW 0.90 1.80 1.67E 08 533 <50 GREEN 0.09 0.18 1.67E-09 53 <50 5.00 4.10 BLUE 7.00 14.00 1.23E-07 3951 222 YELLOW 0.70 1.40 1.23E-08 395 <50 4 GREEN 0.07 0.14 1.23E-09 AS READ <50 6.00 4.80 BLUE 5.00 10.00 9.26E-08 2963 167 YELLOW 0.50 1.00 9.26E-09 296 <50 GREEN 0.05 0.10 9.26E-10 AS READ <50 7.00 5.70 BLUE 4.00 8.00 6.05E-08 1936 109 YELLDW 0.40 0.80 6.05E 09 194 <50 GREEN 0.04 0.08 6.05E-10 AS READ <50 8.00 6.70 BLUE 3.00 6.00 3.95E 08 1264 71 YELLOW 0.30 0.60 3.95E-09 126 <50 GREEN 0.03 0.06 3.95E-10 AS READ <50 9.00 7.60 BLUE 2.00 4.00 2.59E-08 830 <50 YELLOW 0.20 0.40 2.59E-09 83 <50 - GREEN 0.02 0.04 2.59E 10 AS READ <50 10.00 8.30 BLUE 0.02 0.04 2.28E-10 AS READ <50 YELLOW AS READ AS READ 2.28E-11 AS READ <50 GREEN AS READ AS READ 2.28E-12 AS READ <50 NOTES:

Air sale data are based on a sample volume of 177 liters. If different volumes are collected, the air sample data provided in the tables should be adfusted proportionally.

the value Forgiven example, in theiftable a 89 liter by 2sam (two)ple divide andwas collected provide instead of ene resulting 177to value liters, the players. ** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge. Therefore, I-131 cone. (uci/ce) X 3.2E+10 will calculate the the net sample count rate in epm on the ACX-2 cartridge. it is assumed that a G-M survey meter is used *** For to analysis obtain theof the particulate sample count filterrates. The Illter count rate was estimated from the I-131 air concentration for a 177 liter sample volume. l l J w .. .,,,,,,,,,,,, %; m - ,_., ,w , ,, _ ,_. ) -- ,4,. ~ - - - - - - ~- \- - ,i r g, g %... g /, 7 c . i / p-men W--{ , gg 'l f 7 , *'*% g - ^ ,e / .' - .,' ' '-* , s ;_/ , 3 ,- _ ) ;e . # "54 - 11 m - 'N cbEST p D \\y. V N ryM::,A 7h,a. ,,4, . %.e'; -e, e Qa: x- - [D a4 i s., , 3g %. a a.a y j,> ^ s i 2g .. .g:' ,, us 3t - / / - w - .mo , . . , , _,p \ ~. 2i:: "u'~G,".?k P % g\ \ : j / W 4 0 Yi1 f: g.\ M .y/ g t ( %ru,oro ' iii j - /,4 k. -y**(,"*~" e:5G c- e ./ t a ,, _, ,, 3 -r 3,1 gq;u 3jn . 3, pz J ,})A' ,.l 2 - ,\% % Y <,~I'T " X .i iWQ?y g # s T .' A c r . . . . - s, .s u., . t y - - s,s - . s a. .u..c..,y. y<a4.m. s -- p ;i ,,47, . , ,. 3 . w.o. m 1 8 a. /[ 3 sl _ q3. '2'# -Ak, ,, J ,, _[ TV % , , 'gd( t 2 D' ' ~ " O **** %Q re i ; cf4 s . ' '. m8 9! N ' C J o,,;i gf = - % , ,u. ! s ., 3 J )g CA Rt. )- . Cc'* f '"f% Lg - ,. 'q w; _O m , g g- - - - an - *' N GrussiRivsej ( l j > N I ? H 8 # l.N C H E,S T ,, u_alifax / g j ( i . f s @ p- %rm %< \ "( E . %, ##'#^ ,, y . gj^ ' \Y - t ,, [ FIGURE 9.7-13 , , , , , , , , , , ,

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E CLOCK TIME: 1130 to 1145 s N. A h ' .FMV M_ .h _._ 4

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eb P e Rev, O TABLE 9.7.13a Page 9.7-17A VERMONT YANKEE FIELD DATA AT CLOCK TIME 1130 1145 (SCENARIO TIME 8:45 - 9:00) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM 14** SAh-II RM-14*** CONC. PARTICULATE PLUME FILTER SECMENT DISTANCE MAP PIC-6 RM-14 I-131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) <1 53 2.84E-10 <40 AS READ <40 YELLOW <40 GREEN <1 AS READ 2.84E-11 <40 AS READ 2.90 <1 350 2.16E 09 <40 AS READ <40 2.00 BLUE <40 <40 YELLOW <1 35 2.16E-10 AS READ GREEN <1 AS READ 2.16E-11 <40 AS READ <40 3.50 31500 1.79E-07 1000 3007 179 3.00 BLUE 9 100 301 <40 YELLOW <1 3150 1.79E-08 GREEN <1 315 1.79E 09 <40 AS READ <40 ' 4.00 4.10 BLUE 7 24500 1.30E-07 726 2178 130-YELLOW <1 2450 1.30E-08 73 218 <40 GREEN <1 245 1.30E-09 <40 AS READ <40 5.00 4.90 BLUE 5 17500 9.88E-08 553 1659 100 YELLOW <1 1750 9.88E-09 55 166 <40 GREEN <1 175 9.88E-10 <40 AS READ <40 14000 7.41E-08 415 1244 74 6.00 5.60 BLUE 4 124 <40 YELLOW <1 1400 7.41E 09 41 GREEN <1 140 7.41E-10 <40 AS READ <40 6.50 10500 5.06E-08 283 850 51 7.00 BLUE 3 <40 85 <40 YELLOW <1 1050 5.06E-09 GREEN <1 105 5.06E-10 <40 AS READ <40 7000 3.33E-08 187 560 <40 8.00 7.50 BLUE 2 <40 <40 YELLOW <1 700 3.33E-09 56 GREEN <1 70 3.33E-10 <40 AS READ <40 9.00 8.40 BLUE 2 5250 2.22E-08 124 373 <40 l YELLOW <1 525 2.22E-09 <40 AS READ <40 GREEN <1 53 2.22E-10 <40 AS READ <40 '1 9.10 <1 35 1.98E-10 <40 AS READ <40 10.00 BLUE <40- <40 YELLOW <1 AS READ 1.98E-11 AS READ GREEN <1 AS READ 1.98E-12 <40 AS READ <40 l NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adiusted proportionally.

divide the valueFor givenexample, if a 50byliter in the table sam andwas 2 (two)ple collected provide insteaa value the resulting of 100toliters, the players. ** The PE-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge. Therefore, he I-131 cone. silver (uCi/cc) zeolite X 5.6E+09 will calculate cartridge. the net sample count rate in epm on t *** The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample. . l 3 l Rev. 0 -i TABLE 9.7.13b Page 9.7-17B STATE OF VERMONT FIELD DATA AT CLOCK TIME 1130-1145 (SCENARIO TIME 8:45 - 9:00) GAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G-M METER PLUME CLOSED OPEN CONC. AGX-2** PARTICULATE *** SECMENT DISTANCE MAP WINDOW WINDOW I-131 CARTRIDGE FILTER ' NO. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM) ~~~5$b0 ~5 $5b ~b[.Ub b$55 ~b$3b~~~ ~5$55b~bh~~ 55~ ~~E5b~~~~~ YELLOW 0.02 0.03 2.84E-10 AS READ <50 GREEN AS READ AS READ 2.84E-ll AS READ <50 2.00 2.90 BLUE 0.10 0.20 2.16E-09 69 <50 YELLOW 0.01 0.02 2.16E-10 AS READ <50 GREEN AS READ AS READ 2.16E-ll AS READ <50 3.00 3.50 BLUE 9.00 18.00 1.79E-07 5728 322 l YELLOW 0.90 1.80 1.79E-08 573 <50 GREEN 0.09 0.18 1.79E-09 57 <50 1 4.00 4.10 BLUE 7.00 14.00 1.30E-07 4148 233 1 YELLOW 0.70 1.40 1.30E-08 415 <50 i GREEN 0.07 0.14 1.30E-09 AS READ <50 l 5.00 4.90 BLUE 5.00 10.00 9.88E-08 3160 178 4 YELLOW 0.50 1.00 9.88E-09 316 <50 GREEN 0.05 0.10 9.88E-10 AS READ <50 6.00 5.60 BLUE 4.00 8.00 7.41E 08 2370 133 YELLOW 0.40 0.80 7.41E-09 237 <50 , 0.08 7.41E-10 <50 ' GREEN 0.04 AS READ 7-.00 6.50 BLUE 3,00 6.00 5.06E-08 1620 91 YELLOW 0.30 0.60 5.06E-09 162 <50 GREEN 0.03 0.06 5.06E-10 AS READ <50 j 8.00 7.50 BLUE 2.00 4.00 3.33E-08 1067- 60-YELLOW 0.20 0.40 3.33E-09 107 <50 GREEN 0.02 0.04 3.33E.10 AS READ <50 9.00 8.40 BLUE 1.50 3.00 2.22E-08 711 <50 ) YELLOW 0.15 0.30 2.22E-09 71 <50 ! GREEN 0.02 0.03 2.22E-10 AS READ <50 10.00 9.10 BLUE 0.01 0.02 1.98E 10 AS READ <50 YELLOW AS READ AS READ 1.98E-11 AS READ <50 GREEN AS READ AS READ 1.98E.12 AS READ <50 i NOTES:

Air sample data are based on a sample volume of 177 liters. If different volumes ,

are collected, the air sample data provided in the tables should be adfusted l proportionally. For example, if a 89 liter sam ! divlde the value given in the table by 2 (two)ple andwas collected provide instead of the resulting 177toliters, value l the players. ** The Ludium 2220 detector efficiency for I-131 was assumed to be 0.080 cpm /dpm with I 131 cone. X 3.2E+10 will calculate the the the ACX-2 net cartridge. Therefore, sample count rate in cpm on the AGX.{uci/cc{dge. cartr *** 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 1-131 air concentration for a 177 liter sample volume. i - + - \,y $ - . :. f f [ T>O ,*$e ~. ._ ,s - \\ ' _, 1 = 3 3 7 [' NT ' t \ ~ ; ~*'* / i S , e ~Qd ' .{ E ~ _ i \ . U ^ y H . r h j/ , . "

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% r yle f g%m. ;t S . x ~5_U ~ ,d d il v s T a f i a W* / g, ~ , r e l H a g, G / ^ 4y / ^ x/ t-Kw + l : ,l! l Rev. O TC LE ?.7.14a Page 9.7-18A VERMONT YAhTEE FIELD DATA AI OLOCK TIME 1145-1200 (SCENARIO TIME 9:00 - 9:15) AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM-14** SAM-II RM-14*** PLUME CONC.. PARTICULATE SEGMENT DISTANCE MAP PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER i NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) l YELLOW <1 35 2.16E-10 <40 AS READ' <40 ! GREEN <1 AS READ 2.16E-11 <40 AS READ <40 2.00 3.60 BLUE <1 315 1.73E-09 <40 AS READ <40 l YELLOW <1 32 1.73E-10 <40 AS READ <40 i GREEN <1 AS READ 1.73E-11 <40 AS READ <40 ! 1.42E-07 795 2385 142 ! 3.00 4.30 BLUE 7 24500 YELLOW <1 2450 1.42E-08 80 239 <40 l GREEN <1 245 1.42E-09 <40 AS READ <40 4.00 4.90 BLUE 6 21000 1.05E-07 588 1763 105 1 YELLOW <1 2100 1.05E-08 59 176 <40 GREEN <1 210 1.05E-09 <40 AS READ <40 5.00 5.60 BLUE 5 17500 8.02E 08 449 1348 80 YELLOW <1 1750 8.02E.09 45 135 <40 GREEN <1 175 8.02E-10 <40 AS READ <40 6.00 6.40 BLUE 4 14000 6.11E-08 342 1027 61 YELLOW <1 1400 6.llE-09 <40 103 <40 GREEN <1 140 6.11E.10 <40 AS READ <40 7.00 7 20 BLUE 3 10500 4.32E-08 .242 726 43 YELLOW <1 1050 4.32E.09 <40 73 <40 GREEN <1 105 4.32E-10 <40 AS READ <40 8.00 8.20 BLUE 2 7000 2.90E-06 162 487 <40 YELLOW <1 700 2.90E-09 <40 AS READ <40 GREEN <1 70 2.90E-10 <40 AS READ <40 9.00 9.20 BLUE 2 5250 1.98E 08 111 332 <40 YELLOW <1 525 1.98E-09 <40 AS READ <40 GREEN <1 53 1.98E 10 <40 AS READ <40 10.00 9.80 BLUE <1 35 1.73E.10 '< 40 AS READ <40 t YELLOW <1 AS READ 1.73E 11 <40 AS READ <40 GREEN <1 AS READ 1.73E-12 <40 AS READ <40 NOTES:

Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas providecollected instead value the resulting of 100toliters, the players.

** The RM-14 detector efficiency for I 131 was assumed to be 0.025 cpm /dpm with the silver eolite cartridge. Therefore, I-131 conc. (uci/cc) X 5.6E+09 will calculate the net sample count rate in epm on the silver zeolite cartridge. *** The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample. 1 i l l Rev. O i TABLE 9.7.14b Page 9.7-18B ) STATE OF VERMONT FIELD DATA AT CLOCK TIME 1145-1200 (SCENARIO TIME 9:00 9:15) GAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERS)* WAIST AND GROUND LEVEL READINGS LUDLUM 2220 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) uCi/cc (NET CPM) (NET CPM) ~~~ ~ ' 5$b0 3$bb ~~b[.bk' ~ b$5b' 'b$5b ~ ~5$5655b9 69 ~~k5b YELLOW 0.01 0.02 2.16E-10 AS READ <50 GREEN AS READ AS READ 2.16E-11 AS READ <50 0.18 2.00 3.60 BLUE 0.09 1.73E-09 55 <50 YELLOW AS READ AS READ 1.73E-10 AS READ <50 GREEN AS READ AS READ 1.73E-11 AS READ <50 3.00 4.30 BLUE 7.00 14.00 1.42E-07 4543 256 YELLOW 0.70 1.40 1.42E-08 454 <50 GREEN 0.07 0.14 1.42E-09 AS READ <50 4.00 4.90 BLUE 6.00 12.00 1.05E-07 3358 189 YELLOW 0.60 1.20 1.05E 08 336 <50 GREEN 0.06 0.12 1.05E-09 AS READ <50 5.00 5.60 BLUE 5.00 10.00 8.02E-08 2568 144 YELLOW 0.50 1.00 8.02E-09 257 <50 GREEN 0.05 0.10 8.02E-10 AS READ <50 6.00 6.40 BLUE 4.00 8.00 6.11E-08 1956 110 YELLOW 0.40 0.80 6.11E-09 196 <50 GREEN 0.04 0.08 6.11E-10 AS READ <50 7.00 7.20 BLUE 3.00 6.00 4.32E-08 1383 78 YELLOW 0.30 0.60 4.32E-09 138 <50 GREEN 0.03 0.06 4.32E-10 AS READ <50 8.00 8.20 BLUE 2.00 4.00 2.90E-08 928 52 YELLOW 0.20 0.40 2.90E 09 93 <50 GREEN 0.02 0.04 2.90E-10 AS READ <50 9.00 9.20 BLUE 1.50 3.00 1.98E-08 632' <50 YELLOW 0.15 0.30 1.98E-09 63 <50 GREEN 0.02 0.03 1.98E-10 AS READ <50 10.00 9.80 BLUE 0.01 0.02 1.73E-10 AS READ <50 YELLOW AS READ AS READ 1.73E-ll AS READ <50 GREEN AS READ AS READ 1.73E-12 AS READ <50 NOTES:

Air sample data are based on a sample volume of 177 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 89 liter sam divide the value given in the table by 2 (two)ple andwas collected provide instead of the resulting value177toliters, the players.

** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge. Therefore, I-131 cone. (uci/cc) X 3.2E+10 will calculate the - the net sample count rate in cpm on the AGX-2 cartridge. *** For analysis of the particulate filter it is assumed that a C-M survey meter is used to obtain the sample count rates. The filter count rate was estimated from the ; I-131 air concentration for a 177 liter sample volume. ; i i l g_ y _& .- n -4a- + -.44 a LA--.,, ..JL a u A aJ & & I 1 J I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 5 10.0 METEOROLOGICAL DATA I s k .. 4 -- t- .w , s n a . - - - .. . ~ . . .. , 4 4 1 e ) VERMONT YANKEE NUCLEAR POWER STATION , EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 [

a. ,

a 10.1 ON-SITE METEOROLOGICAL DATA I t i ' 'l l l 's l 1 -J l t -w-, , , , , , - 1 Rev.O Page 10.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 10.1 ON-SITE METEOROLOGICAL DATA CLOCK UPPER UPPER UPPER LOWER LOWER LOWER RAIN LOWER SOLAR TIME SPEED DIR DELTAT SPEED DlR DELTAT INCHES TEMP RAD MPH DEGREES DEGF MPH DEGREES DEGF 1/4 HR DEGF LANGS (Note 1) (Note 2) 02:45 3.50E+00 1.70E+02 1.20E+00 3.00E+00 1.63E+02 -5.00E-01 0.00E+00 3.20E+01 0.00E+00 03:00 3.80E+00 1.75E+02 1.50E+00 3.20E+00 1.68E+02 -5.00E-01 0.00E+00 3.20E+01 0.00E+00 03:15 4.00E+00 1.80E+02 1.80E+00 3.40E+00 1.73E+02 -5.00E-01 0.00E+00 3.20E+01 0.00E+00 03:30 3.90E+00 1.85E+02 1.00E+00 3.30E+00 1.78E+02 -5.00E-01 0.00E+00 3.20E+01 0.00E+00 03:45 4.00E+00 1.70E+02 1.20E+00 3.40E+00 1.63E+02 -8.00E-01 0.00E+00 3.20E+ 01 0.00E+00 04:00 4.50E+00 1.75E+02 1.00E+00 3.80E+00 1.68E+02 -8.00E-01 0.00E+00 3.20E+01 0.00E+00 04:15 4.00E+00 1.65E+02 1.20E+00 3.40E+00 1.58E+02 -8.00E-01 0.00E+00 3.20E+01 0.00E+00 04:30 3.80E+00 1.60E+02 1.20E+00 3.20E+00 1.54E+02 -8.00E-01 0.00E+00 3.20E+01 0.00E+00 04:45 3.90E+00 1.68E+ 02 1.00E+00 3.30E+00 1.61 E+02 -9.00E-01 0.00E+00 3.20E+01 0.00E+00 05:00 4.00E+ 00 1.70E+02 1.00E+00 3.40E+00 1.63E+02 -9.00E-01 0.00E+00 3.20E+01 0.00E+00 05:15 4.20E+00 1.75E+02 1.50E+00 3.60E+00 1.68E+02 -9.00E-01 0.00E+00 3.30E+01 1.00E-01 05:30 4.50E+00 1.75E+02 1.00E+00 3.80E+00 1.68E+02 -9.00E-01 0.00E+00 3.30E+01 1.00E-01 05:45 4.80E+00 1.70E+02 1.00E+00 4.00E+00 1.63E+02 -9.00E-01 0.00E+00 3.40E+01 1.00E 01-06:00 4.80E+00 1.70E+02 1.00E+00 4.00E+00 1.63E+02 -9.00E-01 0.00E+00 3.40E+01 1.50E-01 06:15 4.50E+00 1.72E+ 02 5.00E-01 3.80E+00 1.65E+ 02 -9.00E-01 0.00E+00 3.40E+01 1.50E-01 06:30 4.50E+00 1.75E+02 -5.00E-01 3.80E+00 1.68E+02 -9.00E-01 0.00E+00 3.40E+01 2.00E-01 06:45 4.80E+00 1.75E+02 5.00E-01 4.00E+00 1.68E+02 -9.00E-01 0.00E+00 3.40E+01 2.00E-01 07:00 4.90E+00 1.75E+02 -8.00E-01 4.20E+00 1.68E+02 -1.40E+00 0.00E+00 3.40E+01 2.00E-01 07:15 4.80E+00 1.78E+02 -1.00E+0'O 4.00E+00 1.71E+02 -1.40E+00 0.0'0E+00 3.50E+01 2.00E-01 07:30 4.80E+00 1.78E+02 1.00E+00 4.00E+00 1.71E+02 -1.40E+ 00 0.00E+00 3.50E+01 2.00E-01 07:45 4.80E+00 1.80E+02 1.00E+0'O 4.00E+00 1.73E+02 -1.40E+00 0.00E+00 3.50E+01 2.00E-01 08.00 4.80E+00 1.80E+02 -1.20E+00 4.00E+00 1.73E+02 -1.40E+00 0.00E+00 3.70E+01 2.00E-01 08:15 5.00E+00 1.80E+02 1.20E+00 4.30E+00 1.73E+02 -1.40E+00 0.00E+00 3.70E+01 2.00E-01 l l NOTES:

1. The height differential for the upper detta temperature on the primary tower is 262 ft. j I

2. The height differential for the lower detta temperature on the primary tower is 16511. I l

l l l Rev.O Page 10.1-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 10.1 ON-SITE METEOROLOGICAL DATA CLOCK UPPER UPPER UPPER LOWER LOWER LOWER RAIN LOWER SOL.AR ' TIME SPEED DIR DELTAT SPEED DIR DELTAT INCHES TEMP RAD. MPH DEGREES DEGF MPH DEGREES DEGF 1/4 HR DEGF LANGS (Note 1) (Note 2) 08:30 5.00E+00 1.80E+02 -1.20E+00 4.30E+00 1.73E+02 -1.50E+00 0.00E+00 3.80E+01 2.00E-01 08:45 5.00E+00 1.80E+02 -1.20E+00 4.30E+00 1.73E+02 -1.50E+00 0.00E+00 3.90E+01 3.00E-01 09:00 5.00E+00 1.80E+02 -1.20E+00 4.20E+00 1.73E+02 -1.50E+00 0.00E+00 4.00E+01 3.00E-01 09:15 5.00E+00 1.80E+02 -1.20E+00 4.20E+00 1.73E+02 -1.50E+00 0.00E+00 4.00E+01 3.00E-01 09:30 4.00E+00 1.35E+ 02 -1.20E+00 3.40E+00 1.30E+02 -1.50E+ 00 0.00E+00 4.00E+01 3.00E-01 09:45 3.50E+00 1.35E+02 -1.50E+00 3.00E+00 1.30E+02 -1.50E+00 0.00E+00 4.00E+01 . 3.00E-01 10:00 3.00E+ 00 1.35E+02 -1.50E+00 2.60E+00 1.2BE+02 -1.50E+00 0.00Ev00 4.00E+01 3.00E-01 10:15 3.00E+00 1.35E+02 -1.50E+00 2.60E+00 1.30E+02 -1.50E+00 0.00E+00 4.00E+01 3.00E 10:30 2.50E+00 1.35E+02 -1.50E+00 2.10E+00 1.30E+02 -1.50E+00 0.00E+C0 4.00E+01 3.00E-01 10:45 2.50E+00 1.35E+02 -1.50E+00 2.10E+00 1.28E+02 -1.50E+00 0.00E+00 4.00E+01 3.00E-01

11:00 2.50E+00 1.35E+02 1.80E+00 2.10E+00 1.30E+02 1.50E+00 0.00E+00 4.00E+01 3.00E-01 11:15 2.80E+00 1.35E+02 -1.80E+00 2.40E+00 1.27E+02 -1.40E+00 0.00E+00 4.00E+01 3.00E-01 11:30 3.00E+00 1.35E+02 -1.80E+00 2.60E+00 1.30E+02 -1.40E+00 0.00E+00 4.00E+01 - 3.00E-01 11:45 3.20E+00 1.35E+02 -1.80E+00 2.70E+00 1.28E+02 -1.40E+00 0.00E+00 4.00E+01 ' 3.00E-01 q 12:00 3.00E+00 1.35E+02 -1.90E+00 2.60E+00 1.30E+02 -1.40E+00 0.00E+00 4.00E+01 3.00E-01 1 12:15 3.00E+00 1.35E+02 1.90E+00 2.60E+00 1.28E+02 -1.40E+00 0.00E+00 4.00E+01 3.00E-01 ' l 12:30 2.80E+00 1.35E+02 -1.90E+00 2.40E+00 1.30E+02 1.50E+00 0.00E+00 4.00E+01 3.00E-01 j 12:45 3.20E+00 1.35E+ 02 1.90E+00 2.70E+00 1.28E+02 -1.50E+00 0.00E+00 4.00E+01 3.00E-01 l 13:00 3.50E+00 1.35E+02 -1.90E+00 2.90E+00 1.30E+02 -1.50E+00 0.00E+00 4.00E+01. 3.00E-01 )

l 4 NOTES:

1. The height differential for the upper delta temperature on the primary tower is 262 ft.

2. T1e height differential for the lower delta temperature on the primary tower is 165 ft.

-1 l l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE' PREPAREDNESS EXERCISE - , ~ 1993 10.2 GENERAL AREA NATIONAL WEATHER SERVICE (NWS) FORECASTS l l . l l l i l l 9 % , - _- - - - _ a__ m___a . - . - - - . . .~- -.- _. . - .- .. . - 3 Rev. O Page 10.2-1. VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 10.2 CENERAL AREA NWS FORECASTS (See Note) - Synoosis (03:00,1 A low pressure system is currently centered over Pennsylvania. Valid (03:00-05:00) , Southerly winds from 3 to 6 MPH. Temperatures in the low to mid 30's. Valid (05:00-11:00) F Overcast this morning. Temperatures rising to the low 40's. Southerly winds ' becoming southeasterly late in the morning; wind speeds around 5 MPH will' diminish to 2 - 3 MPH. Valid (11:00 17:00) Continued overcast with rain, possibly heavy at times, likely in the_early: afternoon. High temperatures in the low 40's. Light southeasterly _ winds. Valid (17:00-23:00) Rain continuing tonight, possibly heavy at times. Temperatures dropping into the 30's. Light southeasterly winds. l PLANT / EOF WEATHER OBSERVATIONS (See Note) - Valid (03:00-15:00) General Observations Time 03:00 Overcast with light to moderate winds. 04:00 overcast with light to moderate winds. 05:00 overcast with light to moderata winds. 06:00 overcast with light to moderate winds. 07:00 Overcast with light to moderate winds. 08:00 overcast with light to moderate winds. 09:00 Overcast with light to moderate winds. 10:00 overcast with light winds. 11:00 Overcast with light winds. 12:00 Overcast with light winds. 13:00 Rain with light winds. 14:00 Rain with light winds. 15:00 Rain with light vinds. NOTE: CENERAL AREA NWS FORECASTS SHOULD BE PROVIDED UPON REOUEST. PLANT / EOF H WEATHER OBSERVATIONS VILL BE POSTED AS APPROPRIATE. I Rev. O Page 10.2 2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1993 l 10.2 VERMONT YANKEE SITE FORECAST To be provided to the ESC Meteorolocist by the ESC Controller at 04:00. j WEATHER FORECAST FOR SITE: VY - VERNON Date of Forecast: 04-___-93 Time of Forecast: 04:00 Current Site Meteorology (as of 04:00 ): Sensor Wind Speed Wind Direction Detta Stab. Preeloitation Temperature Class Lower 3.4 MPH 180 DEG FROM 1.0 DEG F D 0.00 IN/15 MIN Upper 4.0 MPH 180 DEG FROM 1.5 DEG F D l Forecast Site Meteorology: Time sensor Wind speed - Wind Direction Delta stab. Precipitation Temperature Class 04:00- Lower 3.0 MPH 180 DEG FROM 1.0 DEG F D 06:00 0.00 IN/15 MIN Upper 3.5 MPH 180 DEG FROM 1.5 DEG F D 06:00- Lower 3.5 MPH 180 DEG FROM 1.0 DEG F D 08:00 0.00 IN/15 MIN - Upper 4.0 MPH 180 DEG FROM 1.5 DEG F D , 08:00- Lower 4.0 MPH 160 DEG FROM 1.0 DEG F D 10:00 0.00 IN/15 MIN Upper 5.0 MPH 160 DEG FROM 1.5 DEG F D National Weather Service Forecast for site region: Overcast with temperatures rising into the mid to upper 30's. Light southerly winds becoming southeasterly aid morning. Special Weather Statements: NONE 1 t ?h <#.t+@ v, IMAGE EVALUATION %o .#, 4 1,,j[ gk/* TEST TARGET (MT-3) / /g+$t #, 4 \/[Off ' /// 4 '+ 4 4 %% $,/(t Y<>9 ) 9 (. -, t F l.0 EM M li *mW== l,l f,M !!lhN _1._8 i 1.25 1.4 1.6 = . =

150mm >
6" >

e> % +4 A+ + 4>&;,,3,%/,4 g _ - ,77 _ .(4 "y > _ . %: ;w =. w - . -. jQhuSl$$qa __ . _ ,,,; h $#$ th'e 0 & Q qik2e 4, t in v IMAGE EVALUATION \'[ \/,O,j//' %kf# TEST TARGET (MT-3) / j[4 ,f@gs #4 Y \\\\\/// *\ jff +4 + p,77, % i l,() f Ell lil?d = fd MLulllllM ~ I.I b m ll]l2R 1.8 l.25 ll 1.4 1.6 ll 5 . 4 150mm > 4 6" > 4%+a/s* l*#[&,3sr &////:r ~~'~~~ %@p ' "1 ;g'f4 e __< m g j>v*d ) IMAGE EVALUATION l to dif4 ;t4* restTAaGer(ur-s> //// ' , xxxx9 1.0 EN E lc*m* L=E = 2 ?3 llll=?S l.1 L 4 1.25 1.4 1.6 r._ _ w 4 150mm > l 4-- 6" > I se % + /A

45. y ,y,,,, 7 -

g////h de e, i ,. . . . , . .idhf.;, h v. 7-Ap $> ' & / ,p.< ~Wc . 'Op 0 s g, -v, c.1 -: IMAGE EVALUATION 0 \g N fj// ("' ~ 9h)@ TEST TARGET (MT-3) / f, ((4, 4;g p lf,,// k'4l,A?{g 'V v %%<e l.0 " "" ? ; p1%u == 3y j,l Y ':' lll}.L9 7 == ~ ll 1.8 ums 1.25 ! l.4 il Ime il =I.6= 4 150mm > 4- - 6" > 'O .y 6$% 77;*1% 4 %} cc jyj ffb% <,j;j'~ ,ps cok &f/4 y o}w ; e&m q ep //,, ; e - -j '2m _ mm . ~ d . m i Rev. O Page 10.2-3 ! j I VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1993 10.2 VERMONT YANKEE SITE FORECAST To be provided to the ESC Meteorologist by the ESC Controller at 06:00. WEATHER FORECAST FOR SITE: VY - VERNON Date of Forecast: 04 - ____ - 9 3 Time of Forecast: 06:00 Current Site Meteorology (as of 06:00 ): Sensor Wind Speed Wind Direction Detta Temperature Stab. Class Precipitation Lower 3.4 MPH 180 DEG FROM 1.0 DEG F D 0.00 IN/15 MIN Upper 4.0 MPH 180 DEG FROM -1.5 DEG F D Forecast Site Meteorology: Time Sensor Wind Speed Wind Directiot. Dette Temperature Stab. Class Precipitation 06:00- Lower 3.5 MPH 180 DEG FROM -1.0 DEG F D 08:00 0.00 IN/15 MIN Upper 4.0 MPH 180 DEG FROM -1.5 DEG F D 08:00- Lower 3.5 MPH 180 DEG FROM -1.0 DEG F D 10:00 0.00 IN/15 MIN Upper 40 MPH 180 DEG FROM 1.5 DEO F D 10:00- Lower 1.5 MPH ' 180 DEG FROM 1.0 DEG F D 12:00 0.00 IN/15 MIN Upper 2.5 MPH 180 DEG FROM 1.5 DEG F D National Weather Service Forecast for site region: Overcast with temperatures rising into the mid to upper 30's. Light southerly winds becoming southeasterly mid morning. Special Weather Statements: NONE Rev. O Page 10.2-4 VERMDNT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSr REPAREDNESS EXERCISE 1)93 10.2 VERMONT YANKEE SITE FORECAST To be provided to the ESC Meteorolorist by the ESC Controller at 08:00. WEATHER FORECAST FOR SITE: VY - VERNON Date of Forecast: 04- -93 Time of Forecast: 08:00 Current Site Meteorology (as of 08:00 ): Sensor Wind Wind Direction Detta Temperature Stab. Precipitation ; Speed Class Lower 3.4 MPH 180 DEG FROM -1.0 DEG F D ' 0.00 IN/15 MIN Upper 4.0 MPH 180 DEG FROM 1.5 DEG F D Forecast Site Meteorology: Th Sensor Wind Wind Direction Delta Temperature Stab. Precipitation Speed Clase 08:00- Lower 3.5 MPH 160 DEG FROM -1.0 DEG F D 10:00 0.00 IN/15 MIN Upper 4.0 MPH 160 DEG FROM -1.5 DEO F D. 10:00- Lower 2.0 MPH 135 DEG FROM 1.0 DEG F D 12:00 . 0.00 IN/15-MIN Upper 2.5 MPH 135 DEG FROM -1.5 DEG F D 12:00- Lower 2.0 MPH 135 DEG FROM -1.0 DEG F D l Upper 2.5 MPH 135 DEO FROM -1.5 DEG F D National Weather Service Forecast for site region: i Overcast with temperatures rising into the mid to upper 30's. Light southerly winds becoming southeasterly mid morning. Special Weather Statements: NONE j ) l Rev. 0 -. Page 10.2-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1993 l 10.2 VERMONT YANKEE SITE FORECAST ' To be provided to the ESC Meteorolonist by the ESC Controller at 10:00. WEATHER FORECAST FOR SITE: VY - VERNON Date of Forecast: 04 __-93 Time of Forecast: 10:00

Current Site Meteorology (as of 10:00 ):

Sensor Wind Speed Wind Direction Detta Stab. Preeloitation Temperature Class Lower 2.6 MPH 135 DEG FROM -1.0 DEG F D 0.00 IN/15 MIN Upper 3.0 MPH 135 DEG FROM -1.5 DEG F D Forecast Site Meteorology: , Time Sensor Wind Speed Wind Direction Deka Stab. Preelpitation . Tempereture Class 10:00- Lower 2.0 MPH 1.'5 DEG FROM 1.0 DEG F D . I 12:00 0.00 IN/15 MIN Upper 2.5 MPH 135 DEO FROM -1.5 DEG F D , 12:00- Lower 2.0 MPH 135 DEG FROM -1.0 DEG F D 14:00 - 0.00 IN/15 MIN l Upper 2.5 MPH 135 DEG FROM -1.5 DEG F D 14:00- Lower 2.0 MPH 135 DEG FROM 1.0 DEG F D 16:00 0.00 IN/15 MIN Upper 2.5 MPH 135 DEG FROM 1.5 DEG F D National Weather Service Forecast for site region: Overcast with temperatures rising into the low 40's. Light southeasterly winds. Rain, possibly heavy at times, starting in the late afternoon and continuing tonight. Special Weather Statet ents: NONE ; P _A 4 4 _ 4 4.4 u 4 -. 34 2 s'. A e-u -_4 _ i- b-- =AA 4 W - #- e N -A& is /d r. ----? 9 9 A VERMONT YANKEE NUCLEAR POWER STATION ; EMERGENCY RESPONSE PREPAREDNESS EXERCISE -> t 1993 ; 9 f t 4 1 10.3 NATIONAL k'EATHER SERVICE SURFACE MAPS - 3 4 .t r! 3 3 1 f i ] t i b i 1 l l k 4 1 i .1 i

I

-l l 3 Rev 0 Page 10.3-1 10.3 NATIONAL VEATHER. SERVICE SURFACE MAP (07:00 EST) Today's Maps , L Surfaz feather Map at 7M AM EST , kt Arallable Not Artilable *i =

1

-~ s ., , . _ .ax ._t_ . L 9 t A. -. i 1 ') i i l l t 4 C i Rev 0 Page 10.3 2 10.3 NATIONAL WEATHER SERVICE SURFACE MAP (19:00 EST) l Today's Maps L I l l 's U Surface feather Map at 7dX) AM BT 6 Not Available Fol Available .- ._ .1,, m, ..aa ,_ ~, i i A. . ~~ _ _ _ _ _ _ _ _ _ _ _ _ _ .}}

ML20046C876

Contents

Text

1.0 INTRODUCTION

Purpose:

Purpose:

Purpose:

Purpose:

Purpose:

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Purpose:

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Purpose:

1.4 REFERENCES

1.4 REFERENCES

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SUMMARY

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SUMMARY

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ML20046C876

Text

1.0 INTRODUCTION

Purpose:

Purpose:

Purpose:

Purpose:

Purpose:

Purpose:

Purpose:

Purpose:

Purpose:

Purpose:

1.4 REFERENCES

1.4 REFERENCES

Title:

SUMMARY

SUMMARY

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SUMMARY

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= = = _.- - ----==================_=====

=====- -=___: - ===== --=== - = = - - - - =

= = = = = = = = - -======_

SUMMARY

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