ML20095J977

1995 Exercise Manual

ML20095J977
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	12/31/1995
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
References
PROC-951231, NUDOCS 9512280033
Download: ML20095J977 (160)

Text

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L iO VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 i

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VERMONT YANKEE NUCLEAR POWER STATION

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EMERGENCY PREPAREDNESS EXERCISE 1995 TABLE OF CONTENTS Section Title Rev_t

1.0 INTRODUCTION

1.1 Exercise Schedule 0 1.2 Participating Centers / Agencies O l 2.0 EXERCISE OBJECTIVES AND EXTENT OF PLAY 2.1 Vermont Yankee 1 2.2 State of Vermont 7/10/95 2.3 State of New Hampshire 6/14/95 2.4 Commonwealth of Massachusetts 7/13/95 3.0 EXERCISE GUIDELINES AND SCOPE 3.1 Exercise Guidelines and Ground Rules 1 3.2 Procedure Execution List 1 4.0 CONTROLLER INFORMATION

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4.1 4.2 Controller Assignments Controller Exercise Guidance 0 0 I l

l 4.3 Controller Evaluation Criteria 0 4 5.0 EXERCISE SCENARIO ,

l 5.1 Initial Conditions 0 l 5.2 Exercise Sequence of Events O 5.3 Scenario Timeline 0 6.0 EXERCISE MESSAGES 6.1 Command Cards 0 6.2 Message Cards 0 l

l 7.0 STATION EVENT DATA 7.1 Events Summary 0 7.2 Event Mini-scenarios 1 8.0 OPERATIONAL DATA 0 l 1

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f-s .. VERMONT YANKEE NUCLEAR POWER STATION

%.s EMERGENCY PREPAREDNESS EXERCISE a

1995 TABLE OF CONTENTS (continued) i

) Eggilga Title EREA 9.0 RADIOLOGICAL DATA 9.1 Area Radiation Monitors 1 9.2 Process Monitors 0 j 9.3 In-Plant Radiation Levels 1 9.4 Plant chemistry Data 0

'9.5 Radiological Sample Dose Rates O 9.6 Plant Vent Stack Release Data 0 1 9.7 Field Monitoring Maps and Data 1 10.0 METEOROLOGICAL DATA

} 10.1 on-Site Meteorological Data 0 10.2 General Area NWS Forecasts O 1

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 L.1 EIERCISE SCHEDULE NOTE: EXERCISE SCHEDULE TO BE ISSUED UNDER SEPARATE MEMO AND REVIEWED AT THE EXERCISE CONTROLLER BRIEFING SESSIONS.

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' VERMONT YANKEE NUCLEAR POWER STATION j EMERGENCY PREPAREDNESS EXERCISE ,,

1 1995 i

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1x2 PARTICIPATINO CENTERS / AGENCIES j 4

j YERMONT YANKEE NUCLEAR POWER CORPORATION L

i Vermont Yankee Emergency Response Organization 4

Facilities l

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• Vermont Yankee Nuclear Power Station - Vernon, Vermont i

• Control Room (notification and communications functions only)

• Technical Support Center (2nd floor of Administration Building)

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• Operations support Center (1st floor of Administration Building) ,

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• Energy Information Center (Governor Hunt House)

T j vermont Yankee Training Center - Brattleboro, Vermont

• Simulator Room (Control Room functions, 1st floor of Training Center)

Emergency Operations Facility / Recovery Center (1st floor of Training Center) l'

• News Media Center (1st and 2nd floor of Training Center) l 1

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! YANKEE ATOMIC ELECTRIC COMPANY i

i Yankee Nuclear Services Division - Bolton, Massachusetts 1

Facility l

Engineering Support Center l

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Rev. O Page 1.2-2 STATE OF VERMONT Kev Particioatino State Acencies Vermont Emergency Management Vermont State Health Department Facilities State Warning Point, Vermont State Police - Waterbury, Vermont Emergency Operations Center - Waterbury, Vermont

• Incident Field Office - Dummerston, Vermont Department of Health Laboratory - Burlington, Vermont Emergency Operations Facility / Recovery Center - Brattleboro, Vermont

• News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont Key Particioatino Local Aaencies

• Brattleboro, Dummerston, Guilford, Halifax and Vernon Emergency Management Agencies l

Facilities

• Brattleboro Emergency Operations Center (EOC) - Brattleboro Town Hall

• Dummerston EOC - Dummerston Town Office Building l Guilford ECC - Guilford Fire Station l Halif ax EOC - Halif ax Fire Station a

Vernon EOC - Vernon Fire Station Miscellaneous Particioants/ Facilities Schools School Principal Interviews ,

Receotion Center Bellows Falls Union High School Westminster EOC Egnorecate Care Facilities Site Visits to designated facilities American Red Cross Interviews ,

l Scecial Pooulation Center fw s Vernon Green Nursing Home s_s  !

Radio Station j

• WTSA, Brattleboro, VT l l

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STATE OF NEW HAMPSH[Rg i Kev Particioatina State Acencies New Hampshire Office of Emergency Management Department of Public Health Service Facilities

• State Police Communications Center - Concord, New Hampshire

• State Police Troop C - Keene, New Hampshire

• Southwestern NH District Fire Hutual Aid - Keene, New Hampshire

• Emergency Operations Center - Concord, New Hampshire

• Incident Field Office - Keene, New Hampshire Emergency Operations Facility / Recovery Center - Brattleboro, Vermont

- News Hedia Center, Vermont Yankee Training Center - Brattleboro, Vermont Kev Particioatina Local Acencies

• Chesterfield, Hinsdale, Richmond, Swanzey and Winchester Emergency Management Agencies O

bl Facilities

• Chesterfield Emergency Operations Center (EOC) - Chesterfield Fire Dapt.

Hinsdale EOC - Hinsdale Fire Station / Town Hall

• Richmond EOC - Richmond Civil Defense Building

• Swanzey EOC - Swanzey Center Fire Station

• Winchester EOC - Winchester Emergency Service Building Miscellaneous Participants / Facilities Schools School Administration Interviews Reception Center

• Keene State College Reception /Decon Center Radio Station WKNE, Keene, NH s' \

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COMMONWEALTH OF MASSACHUSETTS Kev Particioatino State Acencies and Radio Stations Massachusetta Emergency Management Agency Massachusetts Department of Public Health Facilities Emergency Operations Center - Framingham, Massachusetts Area IV Emergency Operations Center - Belchertown, Massachusetts Emergency Operations Facility / Recovery Center - Brattleboro, Vermont

• News Media Center, Vermont Yankee Training Center - Brattleboro, Vermont Kev Particioatino Local Acencies/Orcanizations

• Bernardston, Colrain, Gill, Greenfield, Leyden, Northfield and Wa rwick Emergency Management Agencies

• Franklin County Dispatch Facilities T

• Bernardston Emergency Operations Center (EOC) - Bernardston Fire Station

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• Colrain EOC - Colrain Fire Station Gill EOC - Gill Fire Station a

Greenfield EOC - Greenfiald Fire Station I Leyden EOC - Leyden Fire Station i Northfield EOC - Town Hall l

• Warwick EOC - Warwick Fire Statien Miscellaneous Participants / Facilities Schools

• School Superintendents

• Offices (Gill-Montague, Mohawk Trail and Pioneer i Valley)

Gill-Montague Regional School District - Gill Elementary School

- Mohawk Trail Regional School District - Colrain Central Elementary School l Pioneer Valley Regional School District - Warwick Elementary School

• Northfield Mount Hermon School (Gill and Northfield Campus)

• Full Circle School (Bernardston, MA) l

• Linden Hill School (Northfield, MA) )

• Otter Pond Preschool (Gill, MA) j School Transportation Providers: Laidlaw Transit, Inc., F.M. Kuzmeskus, l A *

) Sullivan Bus Lines and Chapin & Sadler Bus Company I

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- Greenfield community College Reception Center and Radiological Monitoring and Decontamination Station Concrecate Care Facilities

• Mass care Shelters: Greenfield Armory, Greenfield High School, Federal Street

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Host Facility: University of Massachusetts, Amherst Campus Soecial Pooulation Centers Camp Keewanee, Greenfield, MA Camp Lion Knoll, Greenfield, MA Camp Northfield

• Massachusetts Department of Environmental Management (District 9 Fire Warden)

. Massachusetts Department of Fisheries, Wildlife, and Environmental Law Enforcement, Division of Law Enforcement Radio Station WHYN, Springfield

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Rev.1 Page 2.1 1 EKERCISE OBJECTIVES AND EXTENT OF PLAY VERMONT YANKEE Extent of Plav

' A. Emeroency Classification and Accident Assessment

1. Demonstrate the ability of Control Room A.1 Scenario events initiated on the simulator will provide personnel to recognize emergency the operational and radiological data to allow personnel .

Initiating events and properly classify the to demonstrate this objective in accordance with condition in accordance with Procedure AP 3125, Emergency Plan Classification and pre-established emergency action levels. 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 accordance corrective actions to mitigate accident with established procedures. Early in plant actions conditions, normally performed by the Control Room support personnel may be controlled and performed by Simulator Controllers until after the Alert classification when the Emergency Response Organization is fully activated. Demonstration of in-plant corrective actions are controlled in accordance with the defined exercise mini scenarios (Refer to Section 7.2). Simulation of response activities will be controlled in accordance with the defined mini-scenarios and as specified in the exercise ground rules.

3. Demonstrate that information concerning A.3 Telephone communications and the Simulated Plant plant conditions can be transmitted Process Computer System (SPPCS) data link will be between the Control Room and the TSC in established between the Simulator Control Room and a timely manner. the various Emergency Response Facilities in order to transmit key information and data.

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

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Rev.1 Page 2.12 Extent of Plav

5. Demonstrate the ability of appropriate TSC A5 Scenario events will allow for the discussion between

- staff to participate with the Control Room the SCR, TSC and EOF /RC staff on EAl.s and and the EOFiRC in EALs and classification emergency classification decisions.

discussions.

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6. Demonstrate the ability to assess data A.6 Scenario events will allow for Chemistry and Radiation from appropriate chemistry samples in Protection technicians to simulate taking reactor i support of accident assessment activities coolant, containment air, or plant vent stack samples and plant conditions, to assess plant conditions. Actual sampling and actual manipulation of sampling system components will be simulated. Time frame to provide sampie results will be controlled and compressed. Controllers will provide sample results after sampling activities are discussed

by players.

l 7. Demonstrate the ability to effectively use A.7 ERFIS work stations in the TSC, EOF and ESC will be the Emergency Response Facility connected to the Simulator Control Room through the Information System (ERFIS) in the use of the Simulated Plant Process Computer System assessment and trending of plant (SPPCS) to receive and display scenario-related data.

conditions. (Controllers may also provide additional data to players l- )

as necessary.) This will allow Emergency Response Facility staff personnel the opportunity to demonstrate the use of ERFIS under simulated emergency conditions.

I l B. Notification and Communication i

i i 1. Demonstrate that messages are B.1 Various communications links will be established i transmitted in an accurate and timely between emergency response facilities in order to manner and that decisions, information transmit information and data. Record keeping and and messages are properly logged and documentation will be demonstrated in accordance l documented.' with established procedures.  ;

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

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Rev.1 Page 2.13 i Extent of Plav d

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

classification and significant changes in NRC will be notified by using the FTS 2000 ENS plant status in accordance with telephone. The State authorities will be notified established procedures. tr. rough the Nuclear Alert System (Orange Phone).

3. Demonstrate that appropriate status B.3 Status Boarde (where provided) will be used by boards are utilized to display pertinent re.cponse personnel to display pertinent information.

accident information at various emergency Status Board Caretakers will be assigned by facility response facilities, 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.

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5. Demonstrate that off site monitoring B.5 Off-site Monitoring Teams will be dispatched to the teams (if necessary) can appropriately field and directed to specific sample locations for )

identify their location when reporting monitoring activities (if necessary).

sample results to the EOF.

6. Demonstrate the ability to provide B.6 During the period that the Off Site Monitoring Teams adequate briefings (if necessary) to off site will be in the field, scenario events may require that monitoring teams as conditions and periodic updates be transmitted to the teams in the I

information change. field (if necessary).

7. Demonstrate the ability to adequately B.7 Scenario events will allow the TSC to update plant communicate plant updates to plant personnel on changing plant conditions and plant personnel as plant conditions and status status information. Periodic plant announcements information change.' should be made to brief plant personnel on plant I conditions and emergency status information.

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C. Direction and Control i

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

2. Demonstrate the capability of key C.2 A!! emergency response facilities have designated emergency response facility management coordinators who will direct and coordinate emergency personnel to direct and coordinate their response activities in their particular area of respective emergency response activities responsibility, in an efficient and timely manner.

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

(n I m) D. Emeroency Resoonse Facilities

1. Demonstrate the ability of station D.1 Scenario events will require activation and operation of personnel to activate and staff the D.2 Vermont Yankee emergency response facilities. The emergency response facilities in a timely SCR, Control Room (communication functions only),

manner. TSC, OSC, EOF /RC, News Media Center and Engineering Support Center will be activated in accordance with established procedures. Designated plant and corporate emergency response personnel will j participate in the exercise. l

2. Demonstrate and test the adequacy and f effectiveness of emergency response facilities, operations, and equipment. l t

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Rsv.1 Page 2.15 Extent of Pfav E.-Pfant Auamentation and Staffino

1. Demonstrate the adequacy of plant E.1 Shift personnel will demonstrate the use of the emergency notification methods and emergency callin system to augment plant staff as procedures to augment plant staff and may be required by scenario events, resources.

2. Demonstrate the ability to use outside E.2 The Yankee Nuclear Services Division's Engineering resources to provide technical assistance Support Center (ESC) will be contacted and activated and logistical support. for this exercise. The ESC will provide 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 to staffing and manpower to provide for support extended operations.

future manpower and logistics needs.

F. Radiolooical Exoosure Control

1. Demonstrate the ability to provide F.1 Scenario events will allow OSC On-Site Assistance adequate radiation protection controls for F.2 Teams to be dispatched to investigate problems with on-site emergency response personnel associated plant equipment. Investigation and repair including dosimetry, equipment, and activities in the plant will require implementation of protective clothing, radiation controls which include monitoring and tracking of radiation exposure of OSC On-site

2. Demonstrate the ability to monitor and Assistance Teams. (Refer to Procedure OP 3507, "

track radiation exposure of on site Emergency Radiation Exposure Control.")' in addition, emergency response personnel, the exposure of the Off Site Monitoring Teams will be monitored and tracked in the EOF.

G. In-Plant Corrective and Reoair Actions

1. Demonstrate the ability to dispatch and G1 OSC On site Assistance Teams should be dispatched deploy on-site assistance teams in a timely G.2 to investigate problems associated with plant fashion, consistent with plant conditions equipment. Briefings should be conducted with and assigned function, emergency teams to ensure that job requirements are clear and understood. OSC Team Work Status Forms

2. Demonstrate the ability to provide (VYOPF 3501.06) should be used to keep track of adequate briefings to on-site assistance team assignments and work tasks.

teams on job assignments and tasks.

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Rev.1 Page 2.16 Extent of Plav 4 3. Demonstrate the ability of on site G.3 OSC On site Assistance Teams will be given the assistance teams to perform corrective G.4 opportunity to perform corrective actions associated 4

actions on plant equipment during with plant equipment. Demonstration of in plant 4 emergency conditions, corrective actions are controlled in accordance with I defined exercise mini-scenarios (Refer to Section 7.2).

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4. Demonstrate the ability to provide Equipment mock ups for some repair activities will be

adequate administrative controls and available to perform corrective actions on plant j documentation for necessary repairs of equipment in accordance with the established mini-

plant equipment and systems during an scenario. Simulation of repair activities will be i emergency situation, controlled in accordance with the defined mini-scenarios and as specified in the exercise ground rules.

The exercise mini-scenarios will allow players to i implement the appropriate emergency work controls in accordance with established procedures.

1 i H. Radiolooical Assessment i

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• 1. Demonstrate that adequate dose H.1 The scenario will provide information on plant j' assessment activities can be performed to H.2 conditions and in plant radiological conditions to

determine off site radiological H.3 players that will allow them to evaluate off-site f_, consequences. H.4 potential radiological consequences. The scenario will j H.5 provide off-site radiological data that will allow players l 2. Demonstrate that radiological assessment to evaluate off site radiological conditions (if personnel at the EOF can obtain necessary). Players willimplement appropriate j radiological and meteorological data in a sections of Procedures OP 3513, " Evaluation of Off-timely manner. Site Radiological Conditions" and OP 3511,

• Off-Site ,

! Protective Action Recommendations," as may be l

3. Demonstrate the ability to perform timely required by scenario events, assessment of off site radiological l 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.

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5. Demonstrate the ability to project plume trajectory and potentially affected downwind sectors (if necessary) using computer dose assessment model

- (METPAC).

6. Demonstrate adequate staffing, equipment H.6 Off site monitoring teams will be assigned at the OSC. l

.l readiness check, and deployment (if H.7 Players will implement appropriate sections of i ,

necessary) of off-site monitoring teams. Procedure OP 3510, "Off Site and Site Boundary Monitoring, "as may be required by' scenario events.

7. Demonstrate the use of appropriate equipment and procedures to perform off-site radiological monitoring (if necessary).

I. Protective Action Decision Makino

1. Demonstrate the ability to implement 1.1 On-site protective action measures willinclude 5 appropriate on site protective measures for radiation exposure control and plant evacuation of emergency response personnel, nonessential personnel. After plant evacuation and accountability has been completed, plant personnel and contractors / visitors not directly involved in the exercise may be allowed to return to work at the discretion of the TSC Coordinator.

2. Demonstrate the adequacy of the 1.2 Protective action decision making will be demonstrated protective action decision making process in accordance with Procedure OP 3511, "Off Site to make appropriate recommendations Protective Actions Recommendations". l concerning off site radiological consequences.

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d Rzy.1 Page 2.18 Extent of Plav i g

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J. Public information

1. Demonstrate the ability to develop and J.1 The News Media Center (NMC) will be activated and j periodically disseminate timely and J.2 staffed.Information on the simulated scenario events accurate press releases to the public and J.3 occurring at the plant will be gathered, verified, and the news media.* incorporated into news releases. After approval, information will be disseminated and briefings on the

2. Demonstrate the ability to provide information will be conducted 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 provide for control. rumor control concerning the simulated accident.

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

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% )j K. Parallel and Other Actions

1. Demonstrate the adequacy of methods to K.1 Security activities will be implemented in accordt.nce establish and maintain access control and with established procedures to control access to the personnel accountability within the protected area. Assembly of emergency response protected area. personnel and evacuation of contractors / visitors will be implemented to test personnel accountability process within the protected area (Refer to Procedure OP 3524, "Umergency Actions to Ensure Initial Accountability and Security Response"). However, after the plant evacuation and initial accountability checks have been completed, contractors / 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 areas controllers and players. Critique items will be compiled needing improvement, and documented in accordance with Procedure OP

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! 3505, " Emergency Preparedness Exercises and Drills."

Note: The annual Radiological monitoring drill and semi-annual Health Physics drill will be included as part of this exercise. A separate Health Physics drill will be held to demonstrate the actual sample collection and analysis of in-plant chemistry samples which includes the use of the Post Accident Sampling System (PASS).

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Rev. 1 Page 3.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 1.d EXERCISE GUIDELINES AND GROUND RULES

.The Vermont Yankee Emergency Preparedness Exercise will be conducted on Wednesday, September 13, 1995. 1995 is a " full-participation biennial" exercise.

The exercise will involve full participation from Vermont Yankee, State of Vermont, State of New Hampshire, commonwealth of Massachusetts, and local towns within the plume exposure EPZ. All Vermont Yankee emergency response f acilities will be fully activated, and the scenario will be driven by the simulator, as in past exercises. State and local off-site objectives will be demonstrated for FEMA observation and evaluation.

This section provides the guidance and ground rules for conducting the 1995 Vermont Yankee Emergency Preparedness Exercise. It provides the framework for conducting the exercise, demonstrating emergency response capabilities, and evaluating response activities.

I. Conceets of Ocerations and Control A. Exercise Controller Ocerations An Exercise Coordinator has been appointed by Vermont Yankee management to overree all exercise activities. The Exercise Coordinator is responsible for approving the objectives and developing the scenario time sequence.

The Exercise Coordinator is also responsiblo for the selection and training of the personnel required to conduct and evaluate the exercise.

Vermont Yankee will supply controllers for major locations where an emergency response action will be demonstrated. Prior to the exercise,  !

the controllers will be provided with the appropriate materials necessary for their assigned function. The material will include any maps and  !

f messages to be used and forms for documenting and evaluating observed activities.

In each f acility where an activity takes place, the designated Lead controller will make judgment decisions to keep the action going in accordance with the scenario time line. The Lead controllers will provide advice to other Controllers assigned to their facility to resolve minor i exercise control issues or concerns that may occur. If a major exercise control problem arises, the controller should first contact the Lead )

,O Controller who will then contact the Exercise Coordinator for guidance or resolution of the problem. All major requests for scenario modifications I

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{ l or holding _ periods must be cleared through the Exercise Coordinator., ]

controllers also have the authority to resolve scenario-related problems which may occur during the exercise.

1 Controllers will observe the players as they perform their assigned I emergency response functions. Controllers are responsible for being i knowledgeable in the area of their assigned function and possible activities which may be observed. In the event of corrective or repair :

activities, the Controller shall be cognizant of procedures associated with the action. If an activity is to be simulated (as identified within I the specific mini-scenarios or exercise ground rules), the controller j shall request the players to describe the actions that would be initiated I

to effect the desired outcome of the assigned task within the scenario time sequence of events and constraints allowed. The Controllers will j critique the ef fectiveness of the emergency response actions taken and will also provide a written evaluation of their observations.

The initial conditions will be provided to a Control Room operations crew, )

located in the Simulator. Plant and reactor system parameters for the exercise will be generated by running the accident scenario on the l simulator. Additional message cards and scenario parameters will be q provided by Controllers at the times indicated in the exercise sequence of events or when required by player actions. I As information is provided to the playeAs, they should determine the nature of the emergency and implement appropriate plant procedures )

including emergency plan implementing procedures and emergency operating i procedures. These procedures should include a determination of the l emergency classification in accordance with the Vermont Yankee Emergency )

Plan. Notifications will be made to the appropriate federal and state

) authorities.

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The hypothesized emergency will continue to develop based on data and j information provided to the operators located in the simulator. Wherever possible, operators should complete actions as if they were actually l responding to plant events. Inconsistencies in the scenario may be )

intentional and may be required to test the capabilities of the emergency )

l response f acilities to the maximum extent possible in a limited period of i

time.

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'"' 8. Avoidina Violations of Laws l

Violation of laws.is not justifiable during the exercise. To implement this guideline the following actions must be taken: I

1. Participants must be specifically informed of the need to avoid violating any federal, state and local laws, regulations,  ;

ordinances, statutes and other legal restrictions. The orders of all police, sheriffs or other authorities shall be followed as appropriate.

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

3. Participants will not intentionally take illegal actions when responding to scenario events. Specifically, local traf fic laws (tie, speed limits) will be observed.

C. Avoidino Personnel and Proterty Endancerment

?"ws All participants will be instructed to avoid endangering property (public j

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or private), other personnel responding to the events, members of the l general public, animals and the environment.

D. Actions to Minimize Public Inconvenience It is not the intent, nor is it desirable, to effectively train or test the public response during the conduct of the exercise. Public inconvenience is to be avoided. l l

The conduct of the exercise could arouse public concern that an actual

- emergency is occurring. It is important that conversations that can be

monitored by the public (radio, loudspeakers, etc.) be prefaced and j concluded with the words, "THIS IS A DRILL; THIS IS A DRILL." l l

I II. General Guidance for the conduct of the Exercise l 1

A. Exercise Simulatl2D i

Since the exercise is intended to demonstrate actual capabilities as realistically as possible, participants will be instructed to act as they would in an actual emergency. Wherever possible, emergency response ss . actions will be carried out. Some of the exercise objectives will be

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\/ demonstrated by simulating the associated emergency response actions.

Simulation of response activities will occur when specific actions do not have to be performed, and when actions are outside of the defined mini-scenarios (refer to Section 7.2). When an emergency response is to be simulated, the Controller will provide verbal or written directions on actions tnat are to be simulated.

The following describes those specific actions that do not have to be performed and can be simulated by participants. No action will be allowed which alters or affects the ongoing operation of the plant.

1. Prior to the start of the exercise, specific work station terminals in the TSC, EOF /RC and ESC will be connected to the simulated Plant Process Computer (SPPCS) via the simulator to receive and display scenario-related data. The Main Plant Control Room's work station terminals will remain tied to the plant process computer (ERFIS).

2. A number of individuals from the Vermont Yankee Emergency Response organization will be pre-staged to f acilitate exercise and simulator related logistics. Individuals that will be pre-staged include the y followings

a. The operating crew in the Simulator Control Room, and the crew's exercise Aos and other personnel at the plant to compliment the operating crew at the Simulator.

b. An Chemistry technician assigned as the Chemistry Communicator in the Simulator Control Room if requested by SS/ PED.

c. An individual assigned as an Alternate Communicator in the Simulator Control if requested by SS/ PED.

d. An R&CE person assigned to the Simulator Control Room f or data acquisition if requested by TSC personnel.

e. An RP person assigned to the Simulator Control Room for data acquisition if requested by TSC Coordinator.

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f. R&CE personnel to set up the ERFIS terminals in the SPPCS mode.

,[] 3. Meteorological data will be simulated through the simulator SPPCS

() computer.

Rev. 1 j- A- Page 3.1-5 a

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

5. Discussion of potassium iodide (KI) usage will be done if scenario conditions warrant its use. However, distribution and ingestion of KI will be simulated.

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

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

8. The inner gate and electrically controlled doors will not be lef t in the open position during the exercise.

9. The plant CaiTronics is available between the Simulator control Room and the plant through the use of an interface device. Although not a complete duplication it will allow a person in the plant to talk 4 directly to the simulator over the plant GaiTronics. However, actual plant announcements will be coordinated by the controllers and made from the Vermont Yankee plant Main Control Room.

10. Exercise Controllers will not be issued dosimetry unless plant access is required prior to the exercise. Security will be notified of the Exercise controllers assigned locations.

11. All decontamination actions associated with the scenario events may be simulated after discussion and approval by the Exercise controller.

12. The use of respiratory protection equipment may be simulated by plant personnel after discussion and approval by the Exercise controller.

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! Rev. 1 ps Page 3.1-6 B. Player's Guidelines and Gamesmanshio The following is a list of general guidelines and instructions for the players regarding the exercise.

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1. Participants will include Exercise controllers, Players, and NRC and FEMA Evaluators. Exercise Controllers will provide players with command and message cards to initiate emergency response actions and evaluate player actions. NRC/ FEMA Evaluators will also evaluate and note player actions. Exercise Controllers and NRC/ FEMA Evaluators will be identified by badges.

2. Always identify yourself by name and function to the Exercise controllers. Wear a name tag if one is provided.

3. You may ask the Exercise controller for information such as:

a. Initial conditions of the plant and systems including:

o operating history of the core o initial coolant activity o general weather conditions O 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 skin contamination surveys.

4. You may Boi ask the following from the Exercise Controllers:

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

b. Judgments as to which procedures should be used.

c. Data which will be made available later in the s enario.

d. Assistance in performing actions.

e. Assistance in performing calculations.

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Rev. 1

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

6.- 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 Exercise Controllers. This may seem artificial, but it will assist the controllers 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 Exercise Controller prior to performing the action. Iet f the Exercise Controllers prioritize which actions will be observed l and which ones will not. If an Exercise Controller elects to observe your activity, ensure the Exercise Controller remains with you to observe the task (i.e dor't lose the controller en-route to the area where the action will take place).

Q 9. If you are in doubt aoout completing a response action, ask your Exercise Controller for clarification. The Exercise Controller wU,1 D91 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 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 l 1

" Command Card" from the Exercise Controller. In addition, the Exercise controller may periodically issue messages or instructions designed to initiate response actions. You nua1 q accept these messages immediately. They are essential to the proper completion of the exercise scenario.

11. If an Exercise Controller intervenes in your response actions and recommends you redirect or reconsider your play actions, it is for a good reason. The Exercise Controller's direction may be essential to ensure demonstration of objectives for all participating groups. 4 l

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I Rev. 1 Page 3.1-8

( f 12.= If you disagree with your Exercise Controller, discuss your concerns '

in a professional manner. However, the Exercise Controller's final decisions must be followed. 1 1

13. Respond to questions in a timely manner.

14. Do not accept exercise-related scenario messages / instructions from the NRC. Evaluators. They should work through Vermont Yankee Exercise Controllers if they want to initiate additional emergency conditions. However, you may answer questions directed to you by the NRC Evaluators. If you do not know the answer, offer to get them the answer as soon as possible (without . interfering with exercise activities) or refer them to your lead facility player or Exercise Controller.

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. Exercise Controllers are exempt from simulated radiation levels and

%l other emergency conditions. Do not let this confuse you or cause you to act unwisely. However, no one is exempt from normal plant radiological practices and procedures.

37. Use status boards and log bcoks as much as possible to document and record your actions.

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18. Always begin and and all communications with the words "THIS DRILL," so that exercise-related communications are not confused with an actual emergency.

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

any comments or observations to your lead player or Exercise controller af ter the exercise. Areas for improvement or weaknesses when corrected will improve the overall emergency response capability.

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\m- The following is a list of items that should be followed to improve I gamesmanship during the exercise

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

Keep all messages, status boards, and problem boards accurate, 2.

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current, timed, and dated. I

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

conditions warrant. )

Bound log j

4. Key players should wear badges which identify their role.

books should be used in all emergency response facilities.

should state

5. Ali announcements, including those on the GaiTronics, l "THIS IS A DRILL."

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

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d C. Simulator Control Room fSCR) 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 Controller and communications link with the simulator. All control Room exercise communications should be directed to the SCR.

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2. An interface device has been installed to connect the simulator Control Room in Brattleboro with the plant GalTronics system. l l

Although not a complete duplication it will allow a person in the l l

plant to talk directly to the simulator over the plant GaiTronics. J The Controller in the plant Main Control Room will monitored and manually actuated the interftee, causing a slight delay between CHANNEL 3 will be the designated line to initial communications.

be used for communications between the Simulator Control Room and the Plant.

CHANNEL 1 and CHANNEL 2 will be the designated lines for all other plant exercise related communications and messages.

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Rev. 1 Page 3.1-10

/N k 3. GalTronics announcements done in the Simulator Control Room will be I

coordinated by the Simulator Control Room controller and made from the Vermont Yankee plant Main Control Room. The announcements will be actual made and repeated by the Operating crew in the plant Main Control Room.

2

4. TSC communicators normally assigned to the Control Room and a f Radiation Protection Technician for transmitting radiological and meteorological data will be pre-staged in the simulator.

5. Personnel movement in and out of the SCR will be limited to the Exercise Controllers and designated exercise participants.

6. Communications equipment in the SCR is the same as the plant Control Room. The commercial telephone extensions are different, but the euto-ring down circuits and speaker telephones are operable. The orange Nuclear Alert System (NAS) State telephone and Federal Telecommunications System (FTS 2000) Emergency Notification System (ENS)-NRC telephone will be operable. The orange NAS telephone r extension is 613.

Iv]s D. Personnel Accountability and Participation (Exemoted Particleants)

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, EOT/RC, simulator area, News Media Center, and the Vermont Yankee Corporate Office in Brattleboro.

Although it is expected that all personnel will respond to the declared emergency as delineated in the applicable procedures, it is recognized that a number of persons (e.g., normal plant operations shift, normal security complement, fire watches, etc.) will not participate due to the i nature of their assigned duties and activities. Department Heads will be requested to review their area of responsibility and provide the Exercise Coordinator with a list of names for anyone that should be exempted from participation. The number of exemot 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.

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Plant Security will be provided with the list of exempt personnel for the exercise. All other personn=1, not listed, are expected to participate as

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Page 3.1-11 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.

I E. Off-Site Particication (Federal. State and Local)

I 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 EPZ. This is NRC's and FEMA's biennial look at the state of emergency preparedness of all three states, local towns and Vermont

! Yankee.

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The NRC Emergency Incident Response Team is planning to " play" with us

, .during this exercise. The extent of NRC participation will include

) limited staffing of the NRC Operations Center in Rockville, Maryland and the NRC Site Incident Response Team at Vermont Yankee emergency response facilities. It is expected that our play with the NRC will involve maintaining an open ENS line and an open HPN line; activating Emergency Response Data System (ERDS) with a data link to the Simulator Control Room

j. through the Simulated Plant Process Computer System (SPPCS); and interfacing with the NRC Site Incident Response Team at our emergency f

response facilities.

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The capability to notify federal, state, and local authorities of

! emergency classifications in accordance with established procedures will e

be demonstrated as follows:

! 1. NRC will be notified by using the FTS 2000 ENS telephone.

2. Vermont, New Hampshire, and Massachusetts State Police dispatchers and State Emergency Operations Centers (EOCs) will be notified through the orange NAS telephone.

$ 3. NRC Site Incident Response Team representatives and 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).

If any state official tries to contact the actual plant Control Room REGARDING THE EXERCISE, the Vernon switchboard should transfer the call to the simulator Control Room in Brattleboro. The NAS orange telephone extension in the SCR is 613.

Rev. 1 Page 3.1-12

( \ F. Exercise criticues U

The following is a brief description of the critique sessions that will be held af ter the exercise. The critique sessions are held to determine whether the stated exercise objactives were met, verify the ef fectiveness of the emergency plan and procedures, and identify areas for future improvements. The specific schedule for the critique sessions will be announced at the conclusion of the exercise.

Emeroency Response Facility criticues The critique sessions will be conducted by the Controllers. Exercise participants will be debriefed on the findings for their particular emergency response facility (s). Four critique sessions will be held:

1. SRM and EOF

2. TSC and Simulator Control Room

3. OSC and Security

4. News Media Center Lead controller Debriefina

m iI ) This session will be conducted by the Exercise Coordinator to compile all exercise comments and findings. Participation is limited to Lead Controllers or other Exercise Controllers as needed.

Exercise Criticue This session will be conducted by the Exercise Coordinator to present a summary of major findings identified during the exercise. Participants include Vermont Yankee management, Exercise Controllers, key players, and the NRC.

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

The following steps will be implemented to terminate the exercise:

1. The Exercise Coordinator will obtain information from the Lead controllers regarding the status of player actions and the s,s demonstration of the exercise objectives.

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Rev. 1 Page 3.1-13 O 2. The Lead Controllers are responsible for informing the Exercise Coordinator of their facility status and whether the emergency response actions and objectives have been satisfactorily observed.

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

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4. A coordinated decision to terminate the exercise will be made between the Site Recovery Manager and the TSC Coordinator. The Site Recovery Manager will also receive concurrence from the states to terminate exercise activities.

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5. The Site Recovery Manager will terminate the exercise.

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J The exercise may also be terminated under the following circumstances:

1. In the event of an actual plant emergency condition should occur,

< the following actions will be takens t

h a. 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; i

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

c. Concurrent with the notification in Step b, the control Room will announce the following statement over the plant paging 1

4 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.

d. The Exercise coordinator will be responsible for directing the actions of all other exercise participants.

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2. In the event that actual off-site emergency impacts the response actions of Vermont Yankee participants, the following actions should be taken:

a. The Shift Supervisor will notify the control Room controller who, in turn, will notify the Exercise Coordinator.

b. A coordinated decision will be made in conjunction with the Site Recovery Manager and/or the TSC and EOF Coordinators concerning the completion of the exercise. l

c. The Exercise Coordinator will be responsible for temporarily halting the exercise until such time a decision is made to terminate or continuing the exercise.

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d. If the final decision is to terminate the exercise, the )

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

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If the final decision is to continue the exercise, the e.

Exercise Coordinator is responsible for informing all Controllers of any projected changes to the expected response action (s),

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

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! l VERMONT YANKEE NUCLEAR POWER STATION 4 I

EMERGENCY PREPAREDNESS EXERCISE 1995 I

I i 122 EMERGENCY PLAN IMPLEMENTING PROCEDURE EYECUTION LIST

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Pr.ocedure Number Rev. No. Title  !

AP 3125 14 Emergency Plan Classification and Action Level Scheme l 1

OP 3500 15 Unusual Event I OP 3501 16 Alert OP 3502 28 Site Area Emergency i OP 3503 30 General Emergency 1

OP 3504 29 Emergency Communications i

OP 3507 25 Emergency Radiation Exposure a Control 1 1

OP 3510 21 Off-site and Site Boundary Monitoring g OP 3511 9 Off-site Protective Action Recommendations 4

i OP 3513 18 Evaluation of Off-Site Radiological

Conditions i

OP 3524 11 Emergency Actions to Ensure Initial Accountability and Security Response l OP 3525 6 Radiological Coordination OP 3531 9 Emergency Call-In Method 1

OP 3533 1 Post Accident Sampling of Reactor Coolant 1

i OP 3534 0 Post Accident Sampling of Plant Stack Gaseous Releases i

j OP 3535 0 Post Accident Sampling and Analysis of Primary Containment OP 3536 0 In Plant Air Sample Analysis with Abnormal Condition 1

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O VERMONT YANKEE NUCLEAR POWER STATION EMERGE: ICY PREPAREDNESS EXERCISE 1995 id CONTROLLER ASSIGNMENTS NOTE: ASSIGNMENTS TO BE ISSUED UNDER SEPARATE MEMO AND REVIEWED AT THE EXERCISE CONTROLLER BRIEFING SESSION P

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' Page 4.2-1 r-'S VERMONT YANKEE i EMERGENCY PREPAREDNESS EXERCISE 1995

$ iz2 CONTROLLER EXERCISE GUIDANCE Prior to the exercise, each Controller will be provided a scenario package i

that correspond to their respective assignments. It is the responsibility of the Controller to read the contents of the scenario package and understand their controller assignments.

Each Controller will be requested to attend appropriate briefing sessions prior to the exercise. Any questions regarding the scenario or assignments should be discussed at this time. Each Controller should ensure that they .

are familiar with location (s) required by their assignment.

Controllers should familiarize themselves with their assigned Lead Controller prior to the exercise. The Lead Controller is responsible to direct Controller activities throughout the course of the exercise. At the 1

exercise termination, each controller is responsible to provide their comments, observations and documentation to the Lead Controller. Each Lead Controller is responsible to provide this documentation to the Exercise Coordinator. Each Lead Controller is also responsible to provide a brief summary of their Controller comments to the Exercise Coordinator for

# presentation during the critique.

5 Controllers should identify themselves to players and explain their role in

the exercise. Players should be told that if any actions are going to deviate from standard plant or emergency procedures must be identified to j the Controllers. Controllers should keep a detailed log of their observations throughout the exercise. This log should note the time, 4 location, activity and player responses. Section 4.3 contains log sheets, checklists, and evaluation forms for documentation purposes.

The primary role of the Controller is to document the emergency response

activities of the players. In order to document emergency response activities, each Controller is required to complete the Emergency Exercise / Drill Controller's Evaluation Form (VYOPF 3505.02). When completing this form, each Controller should provide information on overall performance and observations (strength noted of positive actions taken or expected actions done well), comments / recommendations (specific areas that may warrant further evaluation for improvement), and recognized weaknewees or deficiencies (inadequate performance). (Inadequate indicates that the demonstrattd performance could have precluded ef fective implementation of plans or procedures.) For comments / recommendations and recognized

weaknesses or deficiencies (inadequate performance), the Controller should provide a clear written description of the finding or observation.

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, Page 4.2-2 controllers should a21 allow their biases to be documented as recognized weaknesses or deficiencies. observations and comments may be further subdivided according to the following major headings: Facility Activation and organizational Control, communications, Adherence to Plans and Procedures, Equipment Capabilities, Scenario, Training, Facility Layout, off-site Monitoring, Personnel Desimetry/ Exposure control, and General Comments.

Facility Activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the f acility was activated; (3) when initial activities are organized; (4) whether personnel performance follows the organized arrangements specified by plant procedures; and (5) the efficiency of methods of authority transfer. If a transfer of responsibility occurs, then the Controller should determine if affected personcel are aware that the transfer has occurred.

Communication comments should identify: (1) personnel f amiliarity with emergency communications use; (2) whether sufficient communications were available to ensure a timely, ef ficient, and ef fective 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

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g,,/ to traf fic flow); (6) whether there were any recognized dif ficulties in use j

of computer systems; and (7) whether status boards are effectively used.

Controllers should document their comments in this area very carefully, providing sufficient details to track any recognized deficiencies.

Plans and Procedures comments should identify: (1) whether personnel were f amiliar with the details or overall concepts of applicable procedures; (2) whether situations developed which required deviation from the procedure or plan; (3) whether personnel were overwhelmed with procedural requirements distracting them from performing their required emergency response function; and (4) whether the procedures adequately described the actions required to complete an assigned function.

Eauioment cacability comments should identify: (1) whether all necessary materials and equipment were available and functional; (2) whether emergency response personnel checked operability of equipment prior to conducting their assignment; (3) whether backup equipment was ' readily available when malfunctions were reported; (4) whether the available systems provide an adequate service; and (5) whether equipment malfunctions impacted the expected emergency response.

Scenario related comments should address: (1) whether sufficient information was available to ensure appropriate player response; (2) whether the scenario details deviated f rom actual procedural requirements; and (3) whether the scenario detail provided any prompts to the player.

Rev. O Page 4.2-3 Trainino 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 Lavout comments should identify: (1) whether the available work space was adequate; (2) whether traffic flow hindered the response efforts; (3) whether the communications available in the work area were adequate; (4) whether the noise level hindered emergency response efforts; and (5) whether- sufficient references were available to complete the job assignment.

Of f-site Monitorina comments should identify: (1) the adequacy of sampling methods; (2) the adequacy of reporting and documentation; and (3) the ef fectiveness of the team in defining radiological status. Dose projection methods should also be evaluated with this general category. Consideration of dose projection methods should identify: (1) the effectiveness of methods to interpret off-site conditions; and (2) the effectiveness of using the dose projections in positiening off-site teams.

Personnel Dosimetrv/ 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

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(/ measures afforded in plant activities; and (5) the adequacy of decontamination and posting techniques. j l

Controller's evaluation and documentation forms are found in Section 4.3. l All documentation recorded must be provided to the Lead controller after j f

the exercise and prior to the critique, l

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Page 4.3-1 VERMONT YANKEE EMERGENCY PREPAREDNESS EXERCISE 1995 l bl goNTROLLER EVALUATION CRITERIA As discussed in Sections 4.1 and 4.2, each Controller has been assigned specific areas of response to observe and evaluate. This section has been developed to assist the Controllers in recording and documenting their findings and observations. The following attachments are included:

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 Controller should complete the appropriate checklist.

Procedural Form VYOPF 3505.02, " Emergency Exercise / Drill Controller's Evaluation Form," is provided to summarize major findings and observations. This form MUST BE completed by each controller.

All three attachments should be completed and submitted to the Lead Facility Controller. Each Lead Facility Controller will submit the completed attachments to the Exercise Coordinator for documentation of drill or exercise observations and findings.

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l Rsv. O Paga 4.3-3 ATTACHMENT B

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Vermont Yankee l Emeroency Exercise / Drill Evaluation Checklist J l

INSTFUCTIONS The following checklists are provided to assist the controller with their evaluation of the drill / exercise. The Controller should complete the checklist (s) for their assigned l locations (s). To complete the evaluation checklist (s), use the rating scale listed below. ,

The completed checklist should be used as a " road map" to document your observations and  ;

comments on procedural form VYOPF 3505.02. Controllers should provide a clear written description of their findings and observations.

Ratino Symbol Ratino Explanation for Comments Adequate A Adequate indicates that the demonstrated performance was consistent with plans and procedures. Comments may include strong positive strengths or expected actions done well.

4 Inadequate I Inadequate indicates that the demonstrated performance could have precluded effective implementation of plans and procedures. This also may include an aspect of player's response that warrants further evaluation for improvement or corrective action. Comments should provide a clear description of finding and observation noted. This may include recommendations for improvement, if possible.

Not observed or N No comments are required.

3 Not Applicable l

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CHECKLISTS l

i Section Eage ,

i I. Control Room (Simulator and Actual) 4.3-4 II. Technical Support center 4.3-5 III. Operations Support Center 4.3-7 IV. '-argency operations Facility / Recovery Center 4.3-9 l

V. Site and of f-Site Monitoring 4.3-11 VI. Security 4.3-12 VII. News Media Center 4.3-13 h

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Rsv. O Paga 4.3-4 I. CONTPOL POOM r Comments A. Ageident Assessment /Emeroency Classification Ratino

1. Did the Control Room staff demonstrate the Yes/No ability to recognize emergency initiating conditions and classify the events in accordance with AP 31257 5 2. Did the Control Room staff demonstrate the Yes/No

- ability to coordinate the assessment of plant conditions and corrective actions with the Technical Support Center?

l B. Notification and Communication

1. Did the Control Room staff demonstrate the Yes/No ability to notify the plant staff of an emergency through the use of alarms and the

, public address system?

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2. Did the Control Room staff demonstrate the Yes/No

-ability to notify federal and state

authorities of emergency classifications in accordance with established procedures?

l 3. Was information flow within the control Yes/No 3 Room and to other appropriate emergency j response facilities timely, complete, and accurate?

,2 4. Was adequate record keeping of events, Yes/No j .'

%) actions, and communications documented and N ,/ logged by the control Room staff?

! 5. Were adequate emergency communication Yes/No systems available in the Control Room to transmit data and information to

other emergency response facilities?

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6. Did the control Room staff maintain an Yes/No effective open line of communication with the NRC over the ENS as requested?

C. Activation and Resconse

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

and did they follow them?

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

3. Did the Control Room staff interface with Yes/No the NRC site response team in an effective manner?

Controller Name:

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4 Rav. 0 Paga 4.3-5 4

II. TECHNICAL SUPPORT CENTER j A. Accident Assessment /Emercenev classification Patine Comments

, 1. Did the'TSC staff demonstrate the ability Yes/No to support the control Room in 4

identifying the cause of the incident, 1

mitigating the consequences of that 4 incident, and placing the plant in a stable condition?

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j 2. Did the TSC staff demonstrate the ability Yes/No to coordinate the assessment of plant

conditions and corrective actions with the

the Control Room?

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

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

• plant conditions?

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5. Did the TSC staff demonstrate the ability Yes/No

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3 to participate with the Control Room and EOF /RC in emergency classification and EAL discussion?

B. Notification and Communication l h (s,) 1. Was information flow within the TSC and to Yes/No 9

other appropriate emergency response 1 facilities timely, complete, and accurate?

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

3. Were adequate emergency communication Yes/No

, systems available in the TSC to transmit i 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 1

manner?

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

i 6. Did the TSC staff provide technically Yes/No '

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{ qualified individuals to man the open line of communications over the ENS and HPN phone l links with the NRC as requested? i i

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. Controller Name:

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Rsv. O Pego 4.3-6 II. TECHNICAL SUPPORT CENTER (cont'd)

C. Ae-ivation and Reseense Ratino Comments

1. Did the TSC staff demonstrate the ability Yes/No to activate and staff the TSC7

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 1 ability to maintain command and control of TSC emergency response activities?

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

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

8. Did the TSC staff interface with the NRC Yes/No

[h site response team in an effective manner?

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. Controller Name N.

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! III. OPERATIONS SUPPORT CENTER A. Notification and Communication Ratino Comments

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j 1. Was information flow within the OSC and Yes/No I to other appropriate emergency response

, facilities timely, complete, and accurate?

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2. Was adequate record keeping of events, Yes/No 4

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

! 3. Were adequate emergency ecmmunication Yes/No

systems available in the OSC to transmit

data and information to other emergency j response facilities? /

1 i 4. Were status boards utilized and maintained Yes/No to display pertinent accident information at the OSC7 k j

B. Activation and Response

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

<- 2. Did the OSC staff demonstrate the ability Yes/No

, to appropriately implement Emergency Plan Implementing Procedures and did they follow

them7 i

I 3. Were initial and continuous accountability Yes/No

j checks of OSC personnel performed?

4. Did the OSC Coordinator and OSC Yes/No Coordinator's Assistant demonstrate the ability to maintain command and control of

, OSC emergency response activities?

l 5.-Did the OSC keep other emergency response Yes/No j l facilities advised of the status of their activities and information which they had developed? 7 7

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

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

Controller Name:

I

- . _ . . . = _ -. . .- - - .. - .._.. . . . - - - . . -

Rev. O Pago 4.3-8 III. OPERATIONS SUPPORT CE*fTER (cont'd)

Ratina Comments Yes/No

8. Did the OSC staff demonstrate the 4

i ability to monitor and track radiation exposure of on-site emergency response personnel?

Yes/No

9. Did the Osc staff demonstrate the ability to obtain and analyze

' appropriate chemistry samples as directed by the TSC7 Yes/No

10. Did the OSC staff demonstrate the l

ability to initiate, brief, and dispatch 4 on-site assistance teams?

Yes/No

11. Were on-site assistance teams able to trouble-shoot and evaluate problems with plant equipment and systems?

Yes/No

12. Were there adequate administrative j controls and documentation taken to

• perform the necessary repairs of plant equipment and systems during an emergency situation?

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Rsv. O Pags 4.3-9 IV. EMERGENCY OPERATIONS FACILITY / RECOVERY CENTER A. Notlfication and Communication Ratino Comments

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

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

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

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

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

6. Did the EOF staff provide technically Yes/No qualified edividuals to man the open line of comm':  ;; ions over the ENS and HPN phone links att ;he NRC as requested? l l

B. Activation and Reseense

1. Did the EOF /RC staff demonstrate the Yes/No 1 ability to activate and staff the EOF /RC7

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

3. Did the Corporate Security Force Yes/No establish access centrol into the EOF /RC? l

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 emergency 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? j l

1 Controller Name:

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Rtv. O Piga 4.3-10 IV. EMERGENCY OPERATIONS FAC:'_!TY / RECOVERY CENTER (cont'd)

Ratino Commentg f-s

\_- 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?

10. Did the EOF staff interface with the NRC Yes/No site response team in an effective manner?

C. Radiolocical 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

-s accordance with OP 3513?

k ,) 3. Did the EOF staff demonstrate the ability Yes/No to effectively track and define the plume utilizing the computerized dose assessment model (HETPAC)?

D. Protective Action Decision Makino

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 Names

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Pege 4.3-11 V. SITE A?ID OFF-SITE MONITORING A. Activation and Resoonse Mrig Comments Yes/No

1. Did site and off-site monitoring teams demonstrate the ability to transmit information over the radio utilizing proper units and terminology in accordance with Procedure OP-35107 Yes/No

2. Were site and off-site monitoring teams dispatched and deployed in a timely manner?

Yes/No

3. Were team members familiar with the use of equipment, field monitoring procedures, and what was required of them?

Yes/No

4. Were off-site monitoring teams able to determine and communicate their location in the field using appropriate maps and sample points (landmarks)?

Yes/No

5. Were off-site monitoring teams briefed on plant conditions and changes?

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Rav. O j Paga 4.3-12 l l

VI. SECURITY A. Activation and Reseense O. ,

Ratino Comments l

1. Did the Security staff demonstrate Yes/No I the ability to perform accountability <

of personnel within the Protected Area in accordance with Procedure OP 35247 2c 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 l and did they follow them?

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l Rev. O Pago 4.3-13 VII. NEWS MEDIA CENTER

!' A. Activation and Resoonse

( Patina Comments

1. Did the News Media staff demonstrate the Yes/No

. ability to activate and staff the News j 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?

7. Did the News Media staff interface with the Yes/No NRC site response team in an effective manner?

Controller Name:

O

R:v. O Pego 4.3-14 f-~x EMERGENCY EXERCISE / DRILL i ) CONTROLLER'S EVALUATION FORM

%.J Controller's Names Exercise / Drill Da'.es Ex rcise/ Drill

Title:

Controller's Location:

Time Started: Time Ended observed: Player Function 4

Ovstall Performance and Observations: (Include the proper and effective use of procedures, cquipment and personnel)

(~\

\j

• Comments and Recommendations (Specific):

Rscognized Weaknesses and Deficiencies:

ILQT.E Use additional pages as required.

,, Signature Title I 4 i,j VYOPF 3505.02 (Sample)

OP 3505 Rev. 18 Pcge 1 of 1 RT No. 10.E06.151

- - . ._- . . . . - .~ - - _. .. -. - . . - -

R:v. O Page 5.1-1 f VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 121 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 fifteen months with no recent shutdowns. The core is nearing the end of the current operating cycle.

2. The operations crew turnover log provides the following updated plant informations

a. The Circulating Water System is operating in Closed / Hybrid Cycle.

t

b. The semi-annual eight hour surveillance on the 'B' diesel generator was started on the previous shift and is scheduled to be completed at 1000 this morning.

) 3. The initial plant and reactor system parameters associated with the start of the exercise are shown on Table 5.1-1, " Initial Plant and Reactor System Values" and " Vermont Yankee Daily Plant Status Report."

4. The following on-site meteorological conditions exist at 0800:

l Wind Speed, mph (upper / lower) 5.4/4.2 Wind Direction, degrees (upper / lower) 280/269 Delta Temperature, 'F (upper / lower) -0.4/-0.32 Ambient Temperature, T 50.0

)

Precipitation, inches 0.00 1

5. Regional Meteorological Forecast Information:

I

'An upper air trough will pass over the area midday, causing cloudy skies ]

and a wind shift from the west to the northwest. Partly cloudy this morning. Temperatures rising from current 50 's into the 60 's. Westerly winds from 3 to 6 mph becoming northwesterly around midday. l J

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f~s Rev. 0

( Page 5.1-2 Table 5.1-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 161 Inches Reactor Pressure 1008 psig Reactor Coolant Temperature 527 'F Reactor Power - APRM (average) 99.9 %

Core Plate D/P 18 paid Total Core Flow 46 x 10' lbm/hr

-Main Steam Line Flow - Total 6.4 x 10' lbm/hr Main Steam Line Radiation (average) 156 mR/hr Condenser Hotwell Level 60 %

Condenser Vacuum 1.7 in. Hg(Abs)

Condensate Storage Tank Level 49 %

Recirc Drive Flow 29.7 Kgpm/ loop Feedwater Flow 6.4 x 10' lbm/hr Reactor Building D/P -1.44 in H:0 Drywell Pressure 17 psia Drywell Temperature 125 'F

[ \ Torus Water Level 11.05 ft Torus Temperature 74 'F Drywell/ Torus 0 Concentration 0.14 %

High Range Containment Monitors 2.8 R/hr Containment Gas / Particulate 540/25000 cpm Reactor Building Vent Monitors Gas /Part 185/1481 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Jet Air Ejector (ARM) 60 mR/hr SJAE Discharge Rate 3,450 pCi/see stack Gas 1/2 20/20 cpm High Range Noble Gas Monitor 0.1 mR/hr O

j

Rev. O Page 5.1-3

" Tills IS A DRILL FOR DRILL PURPOSES ONLY" b VERMONT YANKEE DAILY PLANT STATUS REPORT DATE: SEPTEMBER 13,1995 VALUE D61E 31ME l PLANT OPERATING STATUS

1. CORE THERM AL POWER (MWt)l(%) 1592l99.9

- 0700

2. GROSS MWo 547 - 0700 l

3. NET MWe 516 - 0700 4 GROSS MWh FOR PREVIOUS DAY 13178 -

5. 46.5/96.9 - 0700 CORE FLOW (Mlb/hr)l(%)

REACTOR COOLANT SYSTEM

6. CONDUCTIVITY (umho/cm)(Panel) 0.092 09/13/95 0600

7. UNIDENTIFIED LEAKAGE @ 0.09 - -

MIDNlGHT PREVIOUS DAY (spm)

8. TOTAL LEAKAGE @ 1.59 -

MIDNIGHT PREVIOUS DAY (spm)

9. SPECIFIC ACTIVITY (uCi/ml) 6.57x to-2 09/12/95 0800 4.50x10-4 09/12/95 0800

10. IODINE - 131 DOSE EQUIVALENT (uCi/ml)

STACK RELEASES

> 11. PARTICULATE (ci/ period) 6.95x10-5 09/11/95 1135

< 100 09/13/95 0050

12. AVERAGE (uci/sec)

13. PEAK (uci/sec) None

[ 1135

14. DISCHARGE AVERAGE GAMMA 0.862 09/11/95 I

j ENERGY (E) (MeV) l

15. DOSE RATE TO CRITICAL ORGANS (mrem /yr) 6.24x10-2 09/11/95 1135

16. IODINE 131 (uCi/sec) 2.11x10-5 09/11/95  !!35 I OFF GAS ANALYSIS

17. SJAE DISC. RELEASE RATE (MEASURED)(uCi/sec) 3450 09/13/95 0050

18. SJAE DISCHARGE SLOPE OF MIXTURE -0.0152 09/13/95 0050 5 19. CONDENSER AIR INLEAKAGE (cfm) 21.5 09/11/95 0226 l I

LIOUID RELEASES & RIVER TEMPERATURE l

20. LIQUID RELEASE (gal) NONE - -

21. LIQUID RELEASE (GROSS: B.)(uCi/ml) NONE - -

22. LIQUID RELEASE (TRITIUM)(uCi/ml) NONE - -

23. LIQUID RELEASE (DISSOLVED NOBLE GAS) (uCi/ml) NONE - -

24. RIVER MON. O HIGHEST TEMP. FOR PREVIOUS DAY (*F) 63.2 - 1950 BURNUP

25. CORE AVG. BURNUP FOR PREVIOUS DAY (MWD /ST) 15569.56 -

26. CORE CYCLE BURNUP FOR PREVIOUS DAY (MWD /ST) 5452.20 - -

" Tills IS A DRILL" NOTE: INITIAL DAILY PLANT STATUS FOR DRILL PURPOSES ONLY a

RIv. O Pago 5.0-1

/ VERMONT YANKEE NtJCLEAR POWER STATION

\ l V EMERGENCY PREPAREDNESS EXERCISE 1995 M EXERCISE SEOtJENCE OF' EVENTS The exercise begins at 0800 with the reactor (simulator) running at 100% power.

The reactor has been in a steady state for the last fif teen months with no recent shutdowns. The core is nearing the end of the current operating cycle. The Circulating Water System is operating in closed / Hybrid Cycle. The previous shif t had begun the semi-annual eight hour surveillance on the 'B' diesel generator, which is scheduled to end at 1000.

Command Cards SCR C 1 (0800): Guidelines provided to Simulatoi Control Room players on the use of GaiTronics and the plant evacuation alarm during the exercise. SCR C 2 (0800):

Instructions provided to Simulator Coatrol Room players that early in-plant actions may be controlled and performed by the Simulator Controllers, Message Cards INITIAL M 1 (start of exercise or facility activation): Exercise scenario initial conditions provided to the Simulator Control Room players and to appropriate Emergency Facility n

Coordinators upon activation. Security (08001: A list of Exercise Controllers and non.

participants provided to Security Shift Supervisor who will not have to be accounted for dunng the exercise.

ht approximately 081_Onthe.2B' diesel generator will trip due to a f ailure of the differential current trip relay. Shif t Supervisor should request maintenance and I&C to investigate the cause of the 'B' diesel generator trip. Because of the loss of the 'B' diesel generator, the Shif t Supervisor will enter a 7 day Limited condition of operation (LCO) with required testing of the 'A' diesel generator in accordance with Technical Specification 4.5.H.1.

At approximately 0910, shortly after surveillance testing of the 'A' diesel generator has begun, the turbine building Auxiliary operator will report a fire in the ' A' diesel generator room (Refer to Mini-scenario 7.2.1) . The 'A' diesel generator will trip and the fire brigade will be called to extinguish the fire.

The cause of the fire will be found to be a loose fuel oil coupling near the air start solenoids. Damage to the coupling and the air start solenoids will render the 'A' diesel inoperable. At this time, the 'A' and the 'B' diesel generators are both inoperable.

,.~

(  ; An? ALERT lshould-be-declared ~(approximately 0940) based on AP 3125,." Fire" (Any in-plant fire which affects or will likely affect safety system equipmenc required for continued operation in the current operating mode). Notifications should be made to appropriate plant personnel and off-site agencies.

R v. O Page 5.2-2 Because both diesel generators are both inoperable, the plant will also be in a O' 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO in accordance with Technical Specification 3.5.H.1. After consultation with the Technical support Center Coordinator and Duty Call of ficer, the Shift Supervisor should de:ide to remain at or near full power since the estimate to repair the 'B' diesel generator will be approximately 2 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(Manual scram of the reactor and level of power reduction will be controlled at this time.) Plant actions will continue to clean up the 'A' diesel generator room and repairs to the 'A' and 'B' diesel generators will be ongoing, with repair efforts on 'B' diesel generator the more likely first priority.

Command Cards SCR C-3 (0910 or when neededh Instructions to prevent manual scram of the reactor and control level of power reduction. SCR C-4 (0955 or when needed Instructions to control the declaration of the Alert. SEC-C 1 (0940 or when neededh Instructions provided to Security Shilt Supervisor to simulate communications with the New England Hydro Power Station.

Message Cards TSC M 1 (0940 or when neededh Guidelines provided to TSC Coordinator on assignment of TSC Communicators to Control Room. SEC M 1 (0940 or when neededh Guidelines provided to Security Shift Supervisor on YNSD pager activation.

Following the ALERT declaration, the Technical support Center (TSC), operations Support Center (osC), Emergency operations Facility / Recovery Center (EOF /RC), and Engineering Support Center (ESC) should be activated and staf fed. The News Media Center has the option to activate at the Alert classification.

At approximately 1040, High Pressure Coolant Injection (HPCI) will isolato on a

. high steam flow signal caused by a failed steam flow detector. Plant should start to investigate the caused of HPCI isolation. Before any repair ef forts or technical specification reviews can be completed, a large break loss of coolant accident will occur (approximately 1050). The reactor will automatically scram with one loop of Low Pressure Coolant Injection (LPCI) will fail to inject (Refer

< to Mini-scenario 7.2.2), and reactor water level will decrease to less than -48 inches. At this time, it is postulated that fuel clad failure begins due to lose of coolant and reactor water level below the top of the reactor fuel.

A SITE AREA EMERGENC1r should be declared (approximately 1110) based on AP 3125,

" Loss of Systems or Equipment" (Loss of systems or equipment such that reactor water level is below -48 inches) QB " Fuel Damage" (Containment radiation monitors reading greater than 1000 R/hr). Notifications should be made to appropriate

' plant personnel and off-site agencies on the escalation to the Site Area O Emergency.

h By 1115, drywell pressure and radiation levels have increased significantly. The shift will follow the appropriate procedures to mitigate the loss of coolant

1 R;v. O Page 5.2-3 q

accident. This should include alternative methods to restore reactor water above l (V )

top of the reactor fuel and control drywell pressure. Off-site dose assessment activities should be initiated to determine potential of f-site dose projections  !

and of f-site monitoring teams may be dispatched to pre-selected monitoring points based on meteorological conditions.

1 Command Cards EOF-C 1 (1125 or when needed): Instructions to control the declaration of the Site Area j Emergency. I Message Cards EOF M 1 (1115 of when reouested): Information to be provided to EOF Rad Assessment staff on the National Weather Service forecast or plant site meteorological conditions.

ESC M 1 (1115 omhen reouested): Information provided to ESC meteorologist on weather forecas, for the Ve.mont Yankee site.

At approximately 1205, the Simulator Operator will insert a casualty that causes the Torus Vent System (TVS) rupture diaphragm to leak. A direct path from the Primary Containment (Torus) to the Plant Vent Stack exists.

, g. By 1210, the Plant Vent Stack (PVS) is indicating a release of radioactivity to

! the environment. Plant Vent Stack radiation monitors will continue to increase as radioactivity inside the Primary Containment is transported through the hardened vent to the Plant Vent Stack. Operators will attempt to isolate the leak by closing the hardened vent isolat lon valve TVS-86 (refer to Mini-scenario 7.2.3). TVS-86 valve will not operate due to a failure of its supply breaker (V16-19-86). Local operation of the valve will not be possible dee to mechanical failure and inhibited by high radiation levels in the area (refer to Mini-scenario 7.2.4).

A GENERAL EMERGENCY should be declared (approximately 1215) based on AP 3125, Fuel Damage" (Loss of 2 of 3 fission product barriers with potential loss of the third). Notifications should be made to appropriate plant personnel and of f-site agencies on the oscalation to the General Emergency. The Site Recovery Manager should formulate and provide protective action recommendations to State authorities based on plant and off-site radiological conditions.

Command Cards EOF-C 2 (1230 or when needed): Instructions to control the declaration of the General Emergency.

, By 1245, teams should be requested to be dispatched from the operations Support Center (OSC) to investigate the problem associated with the TSV-86 isolation valve to isolate the hardened vent system.

. ._ . . . _ . . _ _ ._m . _- . _ _ _ . . _ .. .- _ _ _ -- . . . . . _ . _

R$v. O

' Page 5.2-4 j

Command Cards TSC-C-1 (1245 or when needed): Instructions to control On-site Assistance Team to investigate problem with the TSV-86 supply breaker.

}

1 By 1345, repairs to TVS-86 supply breaker are completed, allowing closure of the hardened vent isolation valve. Upon valve closure, the release to the

- environment is terminated. The Plant Vent Stack high range monitor readings will i start to decrease significantly. Plant conditions are stabilizing.

i.

j At 1400, the exercise may be terminated.

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$ VERMONT YANKEE NUCLEAR POWER STATION V) EMERGENCY PREPAREDNESS EXERCISE s 1995 5.J SCENARIO TIME LINE CLOCK SCENARIO j TIME TIME DESCRIPTION j 0800 0:00 <- Exercise starts with initial conditions established in the Simulator Control Room.

k 0810 0:10 <- During surveillance testing, the 'B' Diesel Generator trips due to failure of the differential current trip relay. Plant enters a 7 day LCO with required testing of the

'A' Diesel Generator per technical specification.

0910 1:10 <-- AO reports fire in the 'A' Diesel Generator Room. 'A' diesel Generator trips. Fire Brigade respond to extinguish fire.

4 0930 1:30 <-- Fire in the 'A' Diesel Generator Room is out. Fire caused damage to the coupling 4 and air start solenoids of the 'A' Diesel Generator. 'A' and 'B' Diesel Generators are inoperable, i 0940 1:40 <-- ALERT [(A;Pd3125/ FIRE)- Any in-plant fire which affects or willlikely affect safety system equipment required for continued operation in the current operating mode.

0945 1:45 <--- Plant actions continue t: clean up the 'A' Diesel Generator Room. Operations initiate actions to repair the 'A' and 'B' Diesel Generators, i

1040 2:40 <-- HPCI isolates on a high steam flow signal caused by a failed steam flow detector.

Plant should start to investigate the caused of HPCI isolation.

1050 2:50 <-- Large break loss of coolant accident occurs. Reactor automatically scrams. One loop of LPCI fails to inject and reactor water level decreases to less than -48 inches. Fuel clad failure begins due to loss of coolant and reactor water level below the top of the reactor fuel.

1110 3:10 <- SEEMEAiEMERGENCY3APj3[25AljoKgSystemp@r[E@i@snt) Loss of systems or equipment such that reactor water level is below -48 inches QH 1

JAP;3125EF6el Dasap) - Containment radiation monitors reading greater than 1000 R/hr.

1115 3:15 <- Drywell pressure and radiation levels have increased significantly. Operators initiate actions to restore reactor water level and control drywell pressure.

1205 4:05 <- Torus Vent System (TVS) rupture disk begins to leak. A direct path from the Torus to the Plant Vent Stack (PVS) exists. Operators attempt to isolate the leak by ,

1 closing hardened vent isolation valve TVS-86. TSV 86 valve does not operate due to a failure of its supply breaker.

4 1210 4:10 <-- PVS ir dicating a release of radioactivity to the environment.

1215 4:15 <- GENERALYEMERGENCY;{AP 31257FUElIDAMAGE)-Loss of 2 of 3 fission product l h

~~

EUders~with"p$tenNallosAbf 15s3ird. I 1345 5:45 <-- Repairs to the TVS-86 supply breaker are complete. Hardened vent isolation valve TVS-86 is closed. The release to the environment is terminated.

1400 6:00 <- EXERCISE MAY BE TERMINATED

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O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 i

l 6.1 COMMAND CARDS l

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Rov. O Pcgo 6.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 SCENARIO COMMAND CARD FROM: Simulator CR Lead Controller COMMAND NO. SCR-C-1 TO: Shift Suoervisor CLOCK TIME: Prior to 0800 LOCATION: Simulator control Room SCENARIO TIME: Prior to 00:00 ]

.............................................................................. i THIS IS A DRILL f 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/ PLANT EVACUATION ALARM.

Please use the GAITRONICS/ PLANT EVACUATION ALARM in the SCR to complete the required PA announcements. An exercise controller will then direct a member of the shif t operations crew at the plant to repeat the announcements from the Main Control Room.

An interface device has been installed to connect the Simulator Control Room in Brattleboro with the plant CAITRONICS system. It will allow a person at the plant to talk directly to the simulator over the plant GAITRONICS. The controller in the plant Main Control Room will monitored and manually actuated the interface, causing a slight delay between initial communications. CHANNEL 3 is the designated the line to be used for communications between the Simulator g Control Room and the Plant. CHANNEL 1 and CHANNEL 2 are the designated lines V

for all other plant exercise related communications and messages.

t 1

THIS IS A DRILL

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Rev. 0 l VERMONT YANKEE NUCLEAR POWER STATION

, EMERGENCY PREPhREDNESS EXERCISE 1995 f-l SCENARIO COMMAND CARD FROM Simulator CR Lead controller COMMAND NO.: SCR-C-2 TO: Shift Suoervisor CLOCK TIME: 0800 or when needed LOCATION: Simulator Control Room SCENARIO TIME: 00:00 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.

Early in-station actions normally performed by Control Room support personnel may be controlled and performed by the simulator controllers until after the operating shif t personnel are augmented by the Emergency Response Organization.

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THIS IS A DRILL D) c v

I R3v. O Pigs 6.1-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 I

SCENARIO COMMAND CARD FROM: Simulator CR Lead controller COMMAND NO. SCR-C-3 TO: Shift Suoervisor CLOCK TIME: 0910 or when needed LOCATION: Simulator control-Room SCENARIO TIME: 01:10 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.

For scenario purposes, DO NOT manually scram the reactor and keep reactor power at or near 80 percent at this time, t

THIS IS A DRILL O

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. . . . _ , . _m . _ _ . . __ _ _ ._ ._ _ . _ .

• Rsv. O Pag 3 6.1-4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE

.p 1995

, - SCENARIO COMMAND CARD FROM Security Lead Controller COMMAND NO.: SEC-C-1 To: Security Shift Suoervisor CLOCK TIME: 0940 or when needed LOCATION: Security Gatehouse 2 SCENARIO TIME: 01:40 ,

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

1 FOR EXERCISE PURPOSES, communications with New England Hydro Powsr Station in Vernon will be simulated.

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,/ 'T ............. 2............................................................... I

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R:v. O Pags 6.1-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995

\w SCENARIO COMMAND CARD FROM: Simulator CR Lead Controller COMMAND NO.: SCR-C-4 To: Shift Suoervisor CLOCK TIME: 0955 LOCATION: Simulator Control Room SCENARIO TIME: 01:55 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.

DECLARE AN ALERT BASED ON AP 3125, " FIRE - Any in-plant fire which affects or

.will likely affect safety system equipment required for continued operation in the current operating mode."

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Rav. O Pago 6.1-6 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 ON SCENARIO COMMAND CARD 1

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FROM: EOF Lead Controller COMMAND NO.: EOF-C-1  ;

TO: Site Recovery Manacer CLOCK TIME: 1125 LOCATION: EOF SCENARIO TIME: 03:25 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.

DECLARE A SITE AREA EMERGENCY BASED ON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT -

Loss of systems or equipment such that reactor water level is below -48 inches QB FUEL DAMAGE - Containment radiation monitore reading greater than 1000 R/hr."

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THIS IS A DRILL

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R:v. O Pago 6.1-7 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE n 1995

%, SCENARIO COMMAND CARD FROM: EOF Lead Controller COMMAND No.: EOF-C-2 TO: Site Recovery Manacer CLOCK TIME: 1230 LOCATION: EOF SCENARIO TIME: 04:30

.......e...................................................**.....*.. ........  ;

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

DECLARE A GENERAL EMERGENCY BASED ON AP 3125, " FUEL DAMAGE - Loss of 2 of 3 fission product barriers with the potential loss of the third".

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<- s 1995 s- SCENARIO COHMAND CARD FROM: TSC Lead Controller COMMAND NO. TSC-C-1 TO: TSC Coordinator CLOCK TIME: 1245 LOCATION: TSC SCENARIO TIME: 04:45 THIS IS A DRILL D0_NOT initiate any actions affecting normal plant operations.

Dispatch an OSC Assistance Team to investigate the problem with the TSV-86 supply breaker.  ;

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4 VERMONT YANKEE NUCLEAR POWER STATION "1

EMERGENCY PREPAREDNESS EXERCISE 1995 i

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6.2 MESSAGE CARDS i

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\ EMERGENCY PREPAREDNESS EXERCISE

[ 1995 L

SCENARIO MESSAGE CARD FROM Facility Lead Controller MESSAGE NO.: INITIAL-M-1 TO: Facility coordinator CLOCK TIME: Start of Exercise or LOCATION: Various ERFs SCENARIO TIME: Facility Activation THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.

For initial conditions, provide Section 5.1 of the exercise manual to players.

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NOTE TO CONTROLLERS Please make sure that the initial conditions are given to the following individuals: Shift Supervisor, Duty Call Officer, Plant Manager, Operations Manager, Assistant Operations Manager, Operations Planning Coordinator, Operations I Superintendent, and VP-Operations.

a THIS IS A DRILL ps t) ..............................................................................

R3v. O Page 6.2-2 VERMONT YANKEE NUCLEAR POWER STATION

[s ,/} - EMERGENCY PREPAREDNESS EXERCISE 1995 SCENARIO MESSAGE CARQ FROM: TSC Lead Controller MESSAGE NO.: TSC-M-1

, TO: TSC Coordinator CLOCK TIME: 09:40 or uoon 2 assianment of Communicators LOCATION: Igg SCENARIO TIME: Oli40 1

1 THIS IS A DRILL 1 DO NOT initiate any actions af fecting normal plant oper.ations.

............................................................+.2......................

? r After simulating assignment of your TSC Communicators to the Control Room, the I

p.;astaged TSC Communicators at the Simulator Control Room can now be used.

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! VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS-EXERCISE

. '~N 1995 i SCENARIO MESSAGE CARD i

j FROM: Security Lead controller MESSAGE NO. SEC-M-1 TO: Security Shift Suoervisor CLOCK TIME: 2912 I

LOCATION: Gatehouse 2 SCENARIO TIME: 01:40 THIS IS A DRILL j DO NOT initiate any actions affecting normal plant operations.

2 i ............................................... ..........*................*........

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NOTE TO CONTROLLER:

l FOR EXERCISE PURPOSES, direct the Security Shift Supervisor when using Procedure OP 3531, " Emergency Call- In Method" to implement the following instructions:

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l. WEEN ACTIVATINO YNSD PERSONNEL PAGER SYSTEM, use pager code as DEFINED IN THE PROCEDURE as the appropriate emergency classification code for YNSD Pager activation during this exercise.

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2. Make sure that all EXERCISE-related notifications are preceded by and end with "THIS IS A DRILL".

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SCENARIO MESSAGE CARD f

FROM Rad Assessment Controller MESSAGE NO.: EOF-M-1 TO: Radiolocical Assistant CLOCK TIME: 1115 or as reauested LOCATION: EOF / Dose Assessment Area SCENARIO TIME: 03:15 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.

NOTE TO CONTROLLER:

When EOF /RC personnel request weather information, provide the General Area NWS Forecasts information and Plant / EOF Weather observations as appropriate contained in Section 10.2 (Page 10.2-1) of the exercise manual.

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Rav. O Page 6.2-5 VERMONT YANKEE NUCLEAR POWER STATION O EMERGENCY PREPAREDNESS EXERCISE 1995 SCENARIO MESSAGE CARD FROM: ESC Lead controller MESSAGE No.: ESC-M-1 l

TO: ESC Meteorplocist CLOCK TIME: 1115 or as reauested j LOCATION: KiG SCENARIO TIME: 03:15 THIS IS A DRILL DO NOT initiate any actions af fecting normal plant operations.  !

NOTE TO CONTROLLER:

When the ESC Meteorologist request information about weather forecast or site specific meteorological information, provide the meteorological information contained in Section 10.2 of the exercise manual as follows:

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1. Provide the general area NWS Forecast information contained in Section 10.2 (page 10.2-1) on ESC activation or when requested.

2. Provide Vermont Yankee Site Forecast information contained in Section 10.2 (page 10.2-2 through 10.2-4) at the appropriate time stated.

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 id EVENTS

SUMMARY

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The following information and supplementary material are provided for those Controllers having in-plant control assignments to further ensure the proper development of the scenario. The information provided in this section assumes that the " players", who are dispatched to perfons repair, rescue, or other

. activities, will take certain actions in response to the scenario. The Controller 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 controller will be required to provide additional information to the players.

s Approximate Mini-scenario Ilms Event Location 7.2.1 0910 Fire in the ' A' Diesel Generator i

'A' Diesel Generator Room 7.2.2 1050 Failure of RHR 27A Reactor Building Elevation 252'

-7.2.3 1205 Trip of Supply Breaker Reactor Building to Hardened Vent Elevation 280' <

Isolation Valve TSV-86 ij 7.2.4 1205 Investigation of Reactor Building Manual Isolation of Elevation 252' l Hardened Vent MOV 7.2.5 N/A Chemistry Samples of Various Locations Plant Systems and around Plant In-plant Radiological Surveys 1

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 W Mini-scenario - Fire in the 'A' Diesel Generator Room

. I. General Descrintion At approximately 0910, an Auxiliary operator ( AO) will report a fire in the

' A' . Diesel Generator Room. - The Control Room will announce the fire and the Fire Brigade will be directed to the scene. Upon arrival at the scene the Fire Brigade will observe flames in the vicinity of the air start solenoids and oil lines on the south. side of the Diesel. The Fire Brigade Leader should request the Control Room to secure the Diesel. The Fire Brigade Leader will extinguish the fire in approximately 15 minutes and report this to the Control Room. Following extinguishment operations, the Fire Brigade Leader will report the apparent cause as a rupture in the oil line.

.II. . Descriotion of Player Responses / Observations / Corrective Actions AO will report to the Control Room that a fire has started in the ' A' Diesel Generator Room. Concurrently, the Control Room will receive a fire panel alarm for the 'A' Diesel Room. The Control Room should announce the fire and the Fire Brigade should be dispatched to the scene.

When the Fire Brigade arrives on the scene, flames and heavy smoke will be visible in the area of the air start solenoids. The Fire brigade should be

/ directed to extinguish the fire concurrent with the direction to trip the Diesel. Hand held extinguishers will be successful in suppressing the fire after about 15 minutes.

After the fire emergency is announced, the Control Room Crew should review AP 3020, Fire Pre-Plans and the Safe Shutdown Capability Analysis as well as AP 3125, Emergency Plan Classification and Action Level Scheme. The control Room should secure the ' A' Diesel at the request of the Fire Brigade Leader.

After the fire is out, approximately 0930, the Fire Brigade Leader will report that the cause was apparently a ruptured oil line and that the air start solenoids have been exposed to direct flame contact. The Fire Brigade Leader will order the establishment of a re-flash watch and request the Control Room to restart room ventilation.

After the notification from the Fire Brigade that the fire is out and that the air start solenoids may be damaged, the Control Room should contact maintenance to effect any necessary repairs to the 'A' Diesel.

CONTROLLER NOTES:

, THE FIRE BRIGADE MAY CHOOSE TO FIGHT THE FIRE WITH WATER. IF THIS METHOD IS SELECTED THE FIRE SHOULD STILL BURN UNTIL 0930.

DAMAGE TO THE AIR START SOLENOIDS SHOULD BE DESCRIBED AS SIGNIFICANT CHARRING OF THE SOLENOIDS THEMSELVES AND SOME MINOR MELTING OF THE l . ASSOCIATED CABLES. DAMAGE TO THE OIL LINES IS LIMITED TO A RUPTURE OF THE '

, FLUIBLE LINE AND SOME ASSOCIATED SCORCHING OF THE PIPING. NO OTHER DAMAGE WILL BE APPARENT.

III. Event closecut

.This event will be terminated when the re-flash watch is established and the maintenance crew is on the scene investigating the extent of the damage to the solenoids and fuel lines.

Rev. 1 Page 7.2.1-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 IV. Messaces All information will be provided verbally by the controller. Responses will be appropriate to the activities of the players. This may include the following expected activities:

AO report of fire to the Control Room.

Fire Brigade response to extinguish the fire.

Fire Brigade damage assessment after the fire is out.

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l Rev. 1 Ipi Page 7.2.2-1 U VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 22222 Kini-scenario - RER 27A Fails to Open I. General Descriotion At approximately 10:50, 2:50 scenario time, a large break loss of coolant accident occurs. One loop of LPCI fails to inject due to spurious trip of thermal overload of the relay that supplies control power to RHR 27A.

II. Descriotion of Player Responses / Observations / Corrective Actions A team.may be sent to investigate the condition of supply breaker to RHR 27A on MCC panel 89A compartment 2B in the reactor building first floor east wall. Upon investigation the team will note that the breaker is in the tripped position indicating that it tripped on thermal overload.

After relaying the condition of the breaker to the TSC, the TSC may direct the operator to reset the breaker. At that time the operator will reset the breaker and inform TSC that the breaker is reset.

CONTROLLER NOTE:

NEEN THE OPERATOR SINULATES THE RESETTINO OF SUPPLY BREAKER To RRR 27A ON MCC PANEL 89A COMPARTMENT, THE COMPLETION OF TASK SHOULD FIRST BE REPORTED BY THE CONTROLLER TO THE SINULATOR CONTROL ROOM CONTROLLER AND

[ THEN REPORTED BY THE OPERATOR. THIS IS TO FACILITATE THE TININO To RESTORE POWER TO THE RHR27A VALVE IN THE SINULATOR CONTROL ROON.

III. Event Closeout This event will be closed out when the team has informed the TSC that the breaker is reset and the team returns to OSC.

IV. Messaces All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players. This may include the following expected activities:

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Initial results of inspection of supply breaker to RHR 27A on MCC panel l 89A compartment 2B.

[ Results of operator resetting the supply breaker. <

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 l 7.2.3 Mini-scenario - Trio of Supolv Breaker To TVS-86 I. General Description At approximately 1205 or 4:05 Hrs into the scenario, the Torus Vent System (TVS) rupture disk begins to leak. At some point after it is determined that a leak exists, operators will attempt to isolate the source by closing the harden vent isolation valve TSV-86. TSV valve does not operate due to a failure of its supply breaker. The only indication the operators have at this point is that when the operator goes to close on the remote operator, the red open indicating light goes out and the green closed indication remains out. The cause of the failure to the breaker is determined to be a short within the breaker causing it to trip on internal over current. The face of the breaker shows signs of damage by black smoke stains. Further investigation determines that the breaker is physically damaged to a point that it needs replacing. Once the leads have been tested and replacement breaker inserted, the valve can be closed and the release terminated.

II. Descriotion of Player Resoonses/ Observations / Corrective Actions The team sent from OSC to investigate the condition of the supply breaker to TSV-86, should proceed to the reactor building through the north door

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T (to avoid unnecessary radiation exposure) up the north stairway to the

( _f first floor. They will proceed to bus 7A compartment 1F, located south end of first floor. The team will be informed by the Controller that the breaker is in the tripped condition and shows evidence of internal damage due to black charring around the breaker.

CONTROLLER NOTE:

A MOCK-UP OF A SIMILAR BREAKER AND BUS CUBICLE WILL BE USED TO ALLOW TEAM MEMBERS TO PHYSICALLY PERFORM BREAKER CHANGE OUT. A REPLACEMENT BREAKER WILL BE OBTAINED FROM MAINTENANCE, (SIMULATINO THAT IT WAS OBTAINED FROM STORES) TRANSPORTED TO THE REACTOR BUILDINO AND INSTALLED INTO THE MOCK-

, UP BUS CUBICLE.

AT SOME POINT THE TEAM MAY BE DIVERTED BY OSC TO PROCEED TO THE LOCAL LOCATION OF THE HARDEN VENT ISOLATION VALVE AND MANUALLY SHUT IT. (IF So FOLLOW MINI-SCENARIO 7.2.4)

III. Event Closecut The repair team will install a replacement breaker, and the breaker will be re-energized. Operations will close TSV-86. The event closeout will need to be coordinated with the Exercise Coordinator to ensure sufficient time has elapsed to produce the resultant radioactive releases and consistent with the established sequence of events (Refer to Controller Notes below).

CONTROLLER NOTES:

1. CLOSURE OF THE TSV-86 VALVE WILL NEED TO BE COORDINATED WITH THE f)

N_- EXERCISE COORDINATOR TO ENSURE SUFFICIENT TIME HAS ELAPSED TO PRODUCE THE RESULTANT RADIOACTIVE RELEASE AND ESTABLISHED OBJECTIVES HAVE BEEN MET. THEREFORE, THE CONTROLLER WILL NEED TO CONTACT THE

, EXERCISE COORDINATOR WHETHER THE TASK NEEDS TO BE DELAYED OR CAN BE COMPLETED.

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Rev. 1 O VERMONT YANKEE NUCLEAR POWER STATION Page 7.2.3-2 EMERGENCY PREPAREDNESS EXERCISE 1995

2. AFTER TASK CONFLETION OF REPLACINO THE BREAKER, THE COMPLETION OF TASK SHOULD FIRST BE REPORTED BY THE CONTROLLER TO THE SIMULATOR CONTROL ROOM CONTROLLER AND THEN REPORTED BY THE OSC TEAM. THIS IS TO FACILITATE THE TIMINO TO ALLOW OPERATORS TO CLOSE TSV-86 AND SHOW THAT TSV-86 VALVE INDICATION IS CLOSED ON THE SIMULATOR CONTROL ROOM BOARD.

IV. Messaces All information will be provided verbally by the Controller. The controller must be prepared to allow repairs to be completed consistent with the established exercise sequence of events. Responses will be appropriate to the activities of the players.

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[N EMERGENCY PREPAREDNESS EXERCISE 1995 7,2,4 Mini-scenario - Investication of Manual ! solation of Harden Vent MOV I. General Descriotion ,

1 At about 10:50, 2:50 scenario time, a large break loss of coolant i accident occurs causing Drywell pressure to escalate significantly resulting in weakening the Torus Vent System rupture disk. Approximately 1:15 minutes later the disk begins to leak creating a direct path from the Torus to the Plant Stack. The operators will attempt to shut the hardened vent isolation MOV, but due to failure to supply breaker the valve will not operate.

II. Descriotion of Player Responses / Observations / Corrective Actions A team may be sent from the OSC to manually shut the hardened vent isolation valve. The 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 from the area and inform the TSC of this situation. If the team is authorized to proceed with the manual closure of the valve, the handwheel does not engage. l CONTROLLER NOTE:

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• A MOCK-UP OF A SIMILAR VALVE THAT IS USED FOR TRAININO WILL BE AVAILABLE (b TO DEMONSTRATE THE MANUALLY CLOSURE OF THE HARDEN VENT ISOLATION VALVE.

THE CONTROLLER SHOULD PROVIDE THE NECESSARY INFORMATION TO IDENTIFY THAT THE TEAM CAN NOT MANUALLY SHUT THE HARDEN VENT ISOLATION VALVE DUE TO MECHANICAL FAILURE OF THE MANUAL OPERATOR. THE VALVE SHOULD NOT BE ALLOWED TO BE MANUALLY CLOSED.

III. Event Closecut This event will be terminated when the team informs the TSC of the general area dose rates and are directed to return to the OSC or the team may attempt to shut the valve manually, but the handwheel does not engage. (Manual isolation of the hardened vent line will not be possible due to mechanical failure of the manual operator.)

IV. Messaces All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players.

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f,A EMERGENCY PREPAREDNESS EXERCISE J-(s,/

1995 1

j 12241 Mini-scenario - Chemistry Samples of Plant Systees and In-clant

! Radioloaical Surveys

. I. General Descriotion l-3- Scenario events postulated for the exercise require that samples of plant systems will.need to be taken and analyzed to assess plant conditions and support accident, assessment activities. Additional in-plant radiological surveys will also be done to monitor and assess plant radiological 1 conditions. This mini-scenario outlines the extent of play and players'

expected actions to be demonstrated.

II. Descriction of Plaver Resoonses/ Observations / Corrective Actions i

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A. Chemistry Samoles of Plant Systems i

d Samples of plant systems may be requested throughout the exercise scenario. It is expected that system samples of reactor coolant,

! primary containment and plant stack effluent will be requested. Plant i systems sampling may be initially directed from the simulator Control

' Room and then transferred to the TSC after activation. Depending on the plant radiological conditions at the time of the sample request,

samples may be taken using established routine sampling procedures or j post accident sampling techniques as specified in post accident

! sampling procedures (OP 3533, OP 3534, OP 3535 and OP 3536). When

samples of plant systems are requested, qualified personnel .from Radiation Protection and Chemistry will be dispatched to obtain and  ;

analyze the requested sample. The assigned sample team or technician 4

should be familiar with the procedural requirements and administrative controls to obtain and analyze the requested sample.

! Once the TSC and OSC is activated and staf fed, all sample requests should be coordinated through the OSC. The assigned sample team j should consult with the OSC Coordinator or alternate for specific l

instructions and obtain a dose commitment limit for the sampling evolution to be conducted. Af ter the team is briefed, the sampling i team should be able to locate the required equipment and then go or simulate going to the sample location. (For purpose of timeliness, these actions may be simulated after discussions and approval of the l

controller.) Once there or simulated there, the sample team or

technician should be instructed to briefly discuss the actions necessary to obtain and analyze the sample.

i CONTROLLER NOTES:

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1. ALL ACTIONS TO OBTAIN AND ANALYIE THE SAMPLE SHOULD BE SIMULATED.

NO MANIPULATION OF EQUIPMENT OR SAMPLING SYSTEM COMPONENTS SHOULD BE DONE. THE APPROPRIATE EQUIPMENT AND TOOLS SHOULD BE AVAILABLE, BUT NOT USED. NO ACTIONS SHOULD BE TAKEN THAT WILL AFFECT THE

SAFETY OF PERSONNEL OR ONGOING OPERATION OF THE PLANT.

i 2. BECAUSE OF THE TIME COMPRESSION OF THE EXERCISE AND THE NEED FOR t PLANT SYSTEM SAMPLE RESULTS TO BE USED TO DEMONSTRATE THE ABILITY f

TO ASSESS THE DATA IN SUPPORT OF ACCIDENT ASSESSMENT ACTIVITIES, J THE TIME FRAME TO OBTAIN AND ANALYSE THE ACTUAL SAMPLE WILL BE

'- SIMULATED AND COMPRESSED. THE ASSUMED SAMPLING PROCESS TIME WILL BE APPROIINATELY 15 MINUTES PER SAMPLE TAKEN UNLESS THE ACTUAL

! SAMPLE TIME IS SHORTER. THEREFORE, AFTER THE ASSUMED SAMPLING

! , PROCESS TIME OF 15 MINUTES AND THE SAMPLE TEAM BRIEFLY DISCUSSES I THE SAMPLING ACTIVITIES TO OBTAIN AND ANALYIE THE SAMPLE, THE

CONTRO11ER SHOULD PROVIDE THE APPROPRIATE INFORMATION ON SAMPLE DOSE RATES AND SAMPLE RESULTS TO THE SAMPLE TEAM. THE SAMPLING TEAM SHOULD THEN REPORT AND LOG SAMPLE RESULTS IN ACCORDANCE WITH THE SAMPLING PROCEDURE REQUIREMENTS.

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Rev. 1 Page 7.2.5-2 VERMONT YANKEE NUCLEAR POWER STATION

/T- EMERGENCY PREPAREDNESS EXERCISE

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5. In-Plant Radioloolcal Surveys Plant radiological surveys (general area dose rates and air samples) will be conducted to establish the necessary radiation protection controls for on-site personnel. Radiation Protection and Chemistry technicians and other qualified personnel will conduct radiological surveys to verify plant habitability and to define the necessary radiation protection controls to support in-plant corrective actions and repair activities. While conducting these radiological surveys, plant personnel should be instructed that they should actual demonstrate these activities to earn information about scenario-related area radiation and airborne activity levels. Controllers should provide the dose rate and airborne levels after surveys or air samples have been properly obtained. (Information on in-plant radiation levels is contained in Section 9.3 of the manual.) Players should be told that they should respond as if the scenario-related radiation and airborne levels are actually present based on the information that they received.

CONTROLLER NOTE:

ALL ACTIONS TO CONDUCT RADIOLOGICAL SURVEYS SHOULD M BE SINULATED I UNLESS DIRECTED BY THE EXERCISE COORDINATOR OR LEAD CONTROLLER. THE APPROPR% ATE EQUIPNENT SHOULD BE USED TO OBTAIN THE INFORMATION.

HOWEVER, NO ACTIONS SHOULD BE TAKEN THAT WILL AFFECT THE SAFETY OF PERSONNEL OR ONOCINO OPERATION OF THE PLANT.

2 L) III. Rygnt closeout This event will be terminated when the sampling teams report sample results of plant system samples requested or when radiological surveys are conducted and completed throughout the exercise scenario. l I

IV. Messaces  !

l All information will be provided verbally by the Controller. Responses will be appropriate to the activities of the players.

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taken in response to the conditions presented within the l scenario. The operational data reflects plant conditions assuming certain basic operator response actions being taken. The operational data was taken from the plant simulator.

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EMERGENCY PREPAREDNESS EXERCISE Page 8 01 1995 8.0 OPERATIONAL DATA SCENARIO TIME 00:00 00.15 00:30 00.45 01:00 INSTR. CLOCK TIME 0800 08.15 08:30 08 45 09-00 ITEM PANEL ID DESCRIPTION UNITS 1 93 FT-23-1061 HPCI FLOW GPM 0 0 0 0 0 2 43 FL10139A RHR A FLOW GPM i 1 1 1 1 4 3 9-3 Fi-101398 RHR 8 FLOW GPM 1 1 1 1 1 4 43 FL14 50A CS A FLOW GPM 0 0 0 0 0 5 9-3 Fb14-508 CS 8 FLOW GPM 0 0 0 0 0 1 6 43 PI-161412A DRYWELL PRESS PSIA 17 17 17 17 17 7 9-3 PI 161412B DRYWELL PRESS PSIA 17 17 17 17 17 8 9-4 FL13-91 RCIC FLOW GPM 0 0 0 0 0 9 9-4 Fl 12141 A RWCU FLOW GPM 65 65 65 65 65 10 94 Fl 12-1418 RWCU FLOW GPM 65 65 65 65 65 11 9-4 2-165A RX COOLANT TEMP DEG F 526 527 527 527 527 12 9-4 2 1658 RX COOLANT TEMP DEG F 526 527 527 527 527 13 9-4 2159A RECIRC A LOOP FLOW KGPM 28.8 29.3 29.3 29 3 29.3 14 44 2 1598 RECIRC B LOOP FLOW KGPM 28 8 29.3 29.3 29 3 29 3 15 95 7-46A APRM/lRM A  % 99 99 99 99 99 16 9-5 7-468 APRM1RM B  % 100 100 100 100 100 17 9-5 7-46C APRMilRM C  % 98 98 99 99 99 18 45 7-46D APRM/lRM D  % 99 99 100 100 100 19 9-5 7 46E APRM'IRM E  % 100 100 100 100 100 20 9-5 7 46F APRM/tRM F  % 100 100 100 100 100 3 84E+05 3.84E+05 3.84E+05

!p 21 22 9-5 95 7-43A 7-438 SRM A SRM B CPS CPS 3 84E+05 4.59E+05 3.82E+05 4 56E+05 4.58E+05 4.58E+05 4 58E+05 1 23 95 7-43C SRM C CPS 5.17E+05 5.14E+05 5.16E+05 5.16E+05 5.16E+05 24 45 7-430 SRMD CPS 4.30E+05 4.27E+05 4 29E+05 4 29E+05 4 29E+05 25 9-5 2-3-95 CORE FLOW MLBeHR 46 46 46 46 46 26 9-5 2-3-95 COREDP PSID 17 18 18 18 18

, 27 45 Fh3 310 CRO FLOW GPM 53.8 55.8 55.7 55.7 55.7 28 9-5 6-96 WIDE RANGE PRESS PSIG 1007 1007 1007 1007 1007 29 95 6-96 NAR RANGE PRESS PSIG 1008 1007 1006 1008 1008 30 9-5 4 97 FEEDWATER FLOW MLB/HR 64 6.3 6.4 8.4 6.4 31 95 6-97 MAIN STEAM FLOW MLB/HR 6.4 6.4 6.4 6.4 6.4 32 9-5 4 98 NAR RANGE LEVEL INCHES 161 159 159 159 159 33 9-5 6-98 WIDE RANGE LEVEL INCHES 476 487 480 480 480 34 9-6 LL107-5 CST LEVEL  % 49 50 50 50 50 35 M Lb102-5A HOTWELL LEVEL N  % 58 57 57 57 57 36 9-6 LL102-58 HOTWELL LEVEL S  % 56 55 55 55 55 37 9-7 PI 101-29 CONDENSER VACUUM IN HG 1.9 2.5 2.5 2.5 2.5 i OPEN OPEN OPEN 38 9-8 D/G A BKR OPEN OPEN 39 9-6 D/G B BKR OPEN OPEN OPEN OPEN OPEN 40 4 23 1619-33A/C TORUS TEMP DEG F 78 78 78 78 78 41 9 25 U4A TORUS LEVEL FEET 11.05 11 05 11.05 11.05 11.05 4 42 9-25 Ll-46B TORUS LEVEL FEET 11.05 11.05 11.05 11.05 11.05 43 9-25 TR 1619-44 TORUS PRESS PSIA 14 6 14 6 14 6 14 6 14.6 44 9-25 TR-1619-44 DRYWELL PRESS PS% 17 17 17 17 17 45 9-25 PR 1156-3 DW/ TORUS OP PSID 1.93 1.96 1.96 1.96 1.96 46 4 25 TR 161445 DRYWELL TEMP DEG F 122 141 141 141 141 47 9 26 Pht 125-3A RX BUILDING DP (N H2O 1.44 1.47 1.47 1.47 1.47 48 9-26 Phi 125-38 RX BUILDING DP IN H2O 1.44 1.47 1.47 -1.47 1.47 40 9-26 Fbt 1251 A SGTS FLOW CFM 8 8 8 8 8 50 4 26 FL11251B SGTS FLOW CFM 0 0 0 0 0 51 CAD DWITORUS O2 CONC.  % 1.16 1,16 1.16 1,16 1.16 O

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VERMONT YANKEE NUCLEAR POWER STATION Rev. O EMERGENCY PREPAREDNESS EXERCISE Page 8 0-2 1995 8 0 OPERATIONAL DATA j SCENARIO TIME 01:15 01:30 01.45 02:00 02:15 INSTR. . CLOCK TIME 09:15 09:30 09.45 10.00 10:15 1 ITEM PANEL 10 DESCMPTION UNITS l 1 93 FT 23106-1 HPCI FLOW GPM 0 0 0 0 0 2 93 F110-139A RHR A FLOW GPM i i 1 1 1 3 9-3 F1101398 RHR B FLOW GPM i 1 1 1 1 4 9-3 F1-14 50A CS A FLOW GPM 0 0 0 0 0 1 5 9-3 . F1-14-508 CS B FLOW GPM 0 0 0 0 0 6 9-3 PI-161412A DRYWELL PRESS PSIA 17 17 17 17 17 7 9-3 PI 1619128 DRYWELL PRESS PSIA 17 17 17 17 17 8 94 F1 13-91 RCIC FLOW GPM 0 0 0 0 0 9 9-4 F1-12-141 A RWCU FLOW GPM 65 65 65 65 65 10 9-4 F1-121418 RWCU FLOW GPM 65 65 65 65 65 11 94 2-165A RX COOLANT TEMP DEG F 527 527 525. 522 522 12 9-4 2 1658 RX COOLANT TEMP DEG F 527 527 525 522 522 13 9-4 2150A RECIRC A LOOP FLOW KGPM 29 3 29 3 25.4 21.5 21.5 14 94 2 1598 RECIRC B LOOP FLOW KGPM 29 3 29 3 25.3 21.5 21.5 1 15 0-5 7-46A APRMvlRM A  % 99 99 91 82 82 i 16 9-5 7 468 APRM/lRM B  % 100 100 91 82 82 l 17 9-5 7 46C APRM/lRM C  % 99 90 90 81 81 9-5 APRM/lRM D  % 100 100 91 82 82 18 7-46 0 ]

19 9-5 7-46E APRMllRM E  % 100 100 92 82 82 '

20 9-5 7 46F APRM/lRM F  % 100 100 91 82 82 21 9-5 7-43A SRM A CPS 3.84E+05 3 64E+05 3.16E+05 2.51 E+05 2.51 E+05 22 9-5 7-438 SRMB CPS 4 582+05 4 58E+05 3 76E+05 2.99E+05 2 99E+05 23 9-5 7-43C SRM C CPS 5.16E +05 5.16E+05 4 24E+05 3.37E+05 3.37E+05 24 9-5 7-43D SRM D CPS 4.29E +05 4.29E+05 3 53E+05 2.80E+05 2.80E+05 l 25 9-5 2 3-95 CORE FLOW MLB/HR 46 46 41 35 35 26 9-5 2-3-95 CORE DP PSID 18 18 15 12 12 27 9-5 F1-3-310 CRD FLOW GPM 55.7 55.7 55.6 55.8 55 8 )

28 9-5 6-96 WIDE RANGE PRESS PSIG 1007 1007 996 965 985 2f, 9-5 6-96 NAR RANGE PRESS PSIG 1006 1006 997 985 985 30 9-5 6 97 FEEDWATER FLOW MLB/HR 64 6.4 5.8 52 52 31 45 6-97 MAIN STEAM FLOW MLB/HR 6.4 6.4 5.8 5.2 5.2 32 9-5 6 96 NAR RANGE LEVEL INCHES 159 159 159 159 159 33 9-5 6-98 WIDE RANGE LEVEL INCHES 480 480 415 354 354

$0 50 de 49 de '

34 9-6 LI-107 5 CST LEVEL  %

35 9-6 U-102-5A HOTWELL LEVEL N  % 57 57 57 57 57 )

36 96 Ll-102-58 HOTWELL LEVEL S  % 55 55 55 55 55  ;

37 97 PI-101-29 CONDENSER VACUUM IN HG 2.5 2.5 2.4 2.2 2.2 i 38 9-8 D/G A BKR OPEN OPEN OPEN OPEN OPEN l 4 39 98 D/GBBKR OPEN OPEN OPEN OPEN OPEN I

40 9-23 16-19 33A/C TORUS TEMP DEG F 78 78 78 78 78 I 41 9-25 U-46A TORUS LEVEL FEET 11.05 11.05 11.05 11.05 11.05 l 1 42 9 25 U-468 TORUS LEVEL FEET 11.05 11.05 11.05 11.06 11.05

} 43 9-25 TR 1019-44 TORUS PRESS PSIA 14 6 14.6 14.6 14.6 14.6 j 44 9-25 TR 16-19 44 DRYWELL PRESS PSIA 17 17 17 17 17 <

45 9 25 PR 1156-3 DW/ TORUS DP PSID 1.96 1.95 1.97 1.97 1.97 46 9 25 TR 1619 45 DRWVELL TEMP DEG F 141 141 141 142 142 47 9 26 Pl-1 125-3A RX BUILDING DP IN H2O 1.47 -1.47 -1.48 1.48 -1.48 48 9-26 PI-1 125-38 RX BUILDING DP IN H2O 1.47 1.47 1.48 1.48 1.48 de 9-26 Fl-11251 A SGTS FLOW CFM 8 8 10 10 10 50 9 26 FI 1 125-18 SGTS FLOW CFM 0 0 0 0 0 "

51 CAD DW/ TORUS O2 CONC.  % 1.16 1.16 1.16 1.16 1.16 ,

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/ VERMONT YANKEE NUCLEAR POWER STATION Rev. 0

(, EMERGENCY PREPAREDNESS EXERCISE Page 8 0-3 1995 8 0 OPERATIONAL DATA SCENARIO TIME 02:30 02:45 03 00 03 15 03-30 INSTR. CLOCK TIME 10.30 to 45 11 00 11:15 11 30 ITEM PANEL 10 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 i 1 1249 6613 6615 3 9-3 F1-10-1398 RHR B FLOW GPM 1 1 11982 11204 11159 4 93 F1-14-50A CS A FLOW GPM 0 0 3609 3438 3413 5 9-3 F1-14-500 CS B FLOW GPM 0 0 3609 3438 3418 6 9-3 PI-1619-12A DRYWELL PRESS PStA 17 17 37 18 18 7 9-3 PI 16-19-128 DRYWELL PRESS PSIA 17 17 37 18 18 8 9-4 F1-13-91 RCIC FLOW GPM 0 0 0 0 0 9 9-4 F I-12-141 A RWCU FLOW GPM 65 65 0 0 0 10 9-4 F1-12-141 B RWCU FLOW GFM 65 65 0 0 0 11 9-4 2165A RX COOLANT TEMP DEG F 522 522 157 140 142 12 9-4 2-1658 RX COOLANT TEMP DEG F 522 522 157 140 142 13 9-4 2159A RECIRC A LOOP FLOW KGPM 21.5 21.5 0 0 0 14 9-4 2-1598 RECIRC B LOOP FLOW KGPM 21.5 21.5 0 0 0 15 95 7 46A APRMilRM A  % 82 82 0 0 0 16 9-5 7-468 APRM/1RM B  % 82 82 0 0 0 17 9-5 7-46C APRMilRM C  % 81 81 0 0 0 18 9-5 7 46D APRM,1RM D  % 82 82 0 0 0 19 95 7-46E APRMilRM E  % 82 82 0 0 0 20 9-5 7-46F APRM,1RM F  % 82 82 0 0 0 21 9-5 7-43A SRM A CPS 2.51 E+05 2.51 E+05 1.24E +04 4 50E+01 4 47E+01 Q 22 23 9-5 9-5 7-438 7-43C SRM B SRM C CPS CPS 2 99E+05 2.99E+05 3 37E+05 3.37E+05 1.46E +04 1.63E+04 4.40E+01 4 40E+01 4 45E+01 4 45E+01 24 9-5 7430 SRM D CPS 2.80E+05 2 80E+05 1.37E+04 4.50E+01 4 46E+01 25 9-5 2-3-95 CORE FLOW MLB/HR 35 35 15 15 15 26 9-5 2-3-95 COREDP PSID 12 12 4 5 4 27 9-5 F1-3-310 CRO FLOW GPM 55 8 55.8 124 5 124.5 124.5 28 9-5 6-96 WIDE RANGE PRESS PSIG 985 985 22 30 33 29 9-5 6-96 NAR RANGE PRESS PSIG 986 985 950 950 950 30 9-5 6-97 FEEDWATER FLOW MLB/HR 5.2 52 0 0 0 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 5.2 5.2 0 0 0 32 9-5 6-98 NM RANGE LEVEL INCHES 159 159 137 187 187 33 9-5 6-98 WIDE RANGE LEVEL INCHES 354 354 200 200 200 34 9-6 Li-107 5 CST LEVEL  % 49 49 48 43 39 35 9-6 L1-102-5A HOTWELL LEVEL N  % 57 57 0 0 0 36 HI LI-102-58 HOTWELL LEVEL S  % 55 55 0 0 0 37 9-7 Pi-101 29 CONDENSER VACUUM IN HG 2.2 2.2 5 12.7 18 38 9-8 U/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 TORUS TEMP DEG F 78 78 120 136 139 41 9-25 Lh46A TORUS LEVEL FEET 11.05 11.05 11.3 11.19 11.48 42 9-25 Ll-468 TORUS LEVEL FEET 11.05 11.05 11.3 11.51 11.48 43 9-25 TR-16-19-44 TORUS PRESS PSIA 14 6 14 6 36 3 18.4 18.7 44 9-25 TR-1619-44 DRYWELL PRESS PSIA 17 17 37 17 18 45 9-25 PR-1156-3 DW/ TORUS DP PSID 1.97 1.97 0 71 -0.38 -0.38 46 9-25 TR 16-19-45 DRYWELL TEMP DEG F 142 142 262 150 149 47 9-26 Pl-1 125-3A RX BUILDING DP IN H2O 1.48 -1,48 -4 42 -10.49 -12.55 48 9-26 PI-1125-3B RX BUILDING DP IN H2O 1.48 -1.48 -4 22 10 49 -12 55 49 9-26 F1 1-125-1 A SGTS FLOW CFM 10 10 1500 1500 956 50 9 26 FI-1 125-1B SGTS FLOW CFM 0 0 1500 1500 956 A, 51 CAD DW/ TORUS O2 CONC.  % 1.16 1.16 1.36 3.27 3.29

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VERMONT YANKEE NUCLEAR POWER STATION Rev. 0

(/ EMERGENCY PREPAREDNESS EXERCISE Pa9e 8.0-4 1995 8.0 OPERATlONAL DATA SCENARIO TIME 03 45 04 00 04 15 04 30 04 45 INSTR. CLOCK TIME 11:45 12.00 12:15 12 ?g 12.45 ITEM PANEL 10 DESCRIPTION UNITS 1 93 FT-23-108-1 HPCI FLOW GPM 0 0 0 0 0 2 9-3 Fb10-139A RHR A FLOW GPM 10207 9629 9650 9594 9545 3 9-3 FL101398 RHR B FLOW GPM 10249 9668 9689 9633 9545 4 9-3 Fl.14-50A CS A FLOW GPM 3148 2961 2957 2923 2876 5 9-3 Fbl4-500 CS B FLOW GPM 3148 2961 2957 2923 2876 6 9-3 Pi-16-19-12A DRYWELL PRESS PSIA 19 20 21 21 21 7 9-3 PI-16-19-128 DRYWELL PRESS PS!A 19 20 21 21 21 8 9-4 FL13-91 RClC FLOW GPM 0 0 0 0 0 9 9-4 Fb12141 A RWCU FLOW GPM 0 0 0 0 0 10 9-4 FL12141 B RWCU FLOW GPM 0 0 0 0 0 11 9-4 2165A RX COOLANT TEMP DEG F 141 146 150 153 157 12 9-4 2-1658 RX COOLANT TEMP DEG F 141 146 150 153 157 13 9-4 2159A RECIRC A LOOP FLOW KGPM 0 0 0 0 0 14 9-4 2-1598 RECIRC B LOOP FLOW KGPM 0 0 0 0 0 15 9-5 7-46A APRMllRM A  % 0 0 0 0 0 16 9-5 7-468 APRM/lRM B  % 0 0 0 0 0 17 9-5 7-46C APRMnRM C  % 0 0 0 0 0 18 9-5 7 46D APRM/lRM D  % 0 0 0 0 0 19 9-5 7-46E APRMilRM E  % 0 0 0 0 0 20 9-5 7-46F APRM/lRM F  % 0 0 0 0 0 9-5 SRMA CPS 4 45E+01 4.4.E +01 4 40E+01 4.37E+01 4 34E+01 t

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') 21 7-43A CPS 4 43E+01 4 40E+01 4.37E+01 4.34E+01 4 29E+01 22 9-5 7-438 SRM B 23 9-5 7-43C SRM C CPS 4.43E+01 4 40E+01 4.37E+01 4 34E+01 4.29E+01 24 95 7 430 SRMD CPS 4 43E+01 4.40E+01 4 38E+01 4 35E+01 4.30E+01 25 9-5 2 4-95 CORE FLOW MLB/HR 9 8 8 0 0 26 9-5 2-3-95 COREDP PSID 4 4 4 3 3 27 9-5 Fi-3-310 CRD FLOW GPM 124.5 124.5 124 5 130.7 130.7 28 9-5 6-96 WIDE RANGE PRESS PSIG 72 97 97 29 29 29 9-5 6-96 NAR RANGE PRESS PSIG 950 950 950 950 950 30 9-5 6-97 FEEDWATER FLOW MLB/HR 2 11 3 3 3 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 0 0 0 0 0 32 9-5 6-98 NAR RANGE LEVEL INCHES 187 187 187 187 187 33 9-5 6-96 WIDE RANGE LEVEL INCHES 200 200 200 200 200 34 9-6 Li-107 5 CST LEVEL  % 36 32 29 26 23 35 9-6 u-102-5A HOTWELL LEVEL N  % 0 1 1 1 1 36 9-6 Ll 102-5B HOTWELL LEVEL S  % 0 1 1 1 1 37 9-7 Pl.101 29 CONDENSER VACUUM IN HG 21 23.8 25.7 27 27 38 9-8 D/G A BKR OPEN OPEN OPEN OPEN OPEN 39 96 D/G B BKR OPEN OPEN OPEN OPEN OPEN 40 9-23 16-19-33A/C TORUS TEMP DEG F 143 148 151 155 157 41 9-25 Lb46A TORUS LEVEL FEET 11.66 12.5 13 6 14.5 15.6 42 9-25 LI-468 TORUS LEVEL FEET 11.66 12.5 13 6 14.5 15.6 43 9-25 TR 16-19-44 TORUS PRESS PS!A 19.2 20.5 19 5 18 17 44 9-25 TR 16-19-44 DRYWELL PRCSS PSIA 19 20 21 21 21 45 9-25 PR 1 156-3 DW/ TORUS OP PSID 0.13 -0.42 0.91 6.35 0.35 46 9 25 TR 1619-45 DRYWELL TEMP DEG F 182 183 183 183 183 47 9-26 PI-1 125-3A RX BUILDING DP IN H2O -12.63 -12.62 -12.4 -12.47 12.47 48 9-26 PL1 125-38 RX BUILDING DP IN H2O 12.63 -12.62 -12.4 -12.47 -12.47 49 9-26 Fh1125-1 A SGlS FLOW CFM 920 925 1026 993 993 50 9-26 FI11251B SGTS FLOW CFM 920 925 1028 993 993 51 CAD DW/ TORUS O2 CONC.  % 3.29 3 31 3.33 3.34 3 34

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Rev. 0 VERMONT YANKEE NUCLEAR POWER STATION Page 8 0-5

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EMERGENCY PREPAREDNESS EXERCISE 1995 8.0 OPERATIONAL DATA SCENARIO TIME 05.00 05.15 05 30 05 45 06.00 INSTR. CLOCK TIME 13.00 13.15 13.30 13:45 14 00 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 9545 9545 9545 9545 9545 3 9-3 Fl-10-1398 RHR B FLOW GPM 9545 9545 9545 9545 9545 4 43 F1-14-50A CS A FLOW GPM 2876 2876 2876 2876 2876 5 9-3 FL14 508 CS B FLOW GPM 2876 2876 2876 2876 2876 6 9-3 Pl-16-19-12A ORYWELL PRESS PSIA 21 21 21 21 21 7 9-3 Pl.16-10-128 DRYWELL PRESS PSIA 21 21 21 21 21 8 9-4 F1-13-91 RCIC FLOW GPM 0 0 0 0 0 9 9-4 FI-12-141 A RWCU FLOW GPM 0 0 0 0 0 10 9-4 F1-121418 RWCU FLOW GPM 0 0 0 0 0 11 9-4 2-165A RX COOLANT TEMP DEG F 159 161 164 166 167 12 44 2 1658 RX COOLANT TEMP DEG F 159 161 164 166 167 13 9-4 2-159A RECIRC A LOOP FLOW KGPM 0 0 0 0 0 14 9-4 2-159B RECIRC B LOOP FLOW KGPM 0 0 0 0 0 15 9-5 7-46A APRM/lRM A  % 0 0 0 0 0 16 45 7-468 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 APRMilRM E  % 0 0 0 0 0 j] 20 9-5 7 46F APRM/lRM F  % 0 0 0 0 0 i / 21 9-5 7 43A SRM A CPS 4.29E+01 4 24E+01 4.19E+01 4.14E+01 4 09E+01 22 45 7-438 SRM B CPS 4 24E+01 4.19E+01 4.14C +01 4.09E+01 4 04E+01 23 9-5 7-43C SRM C CPS 4 24E+01 419E+01 4.14E+01 4.09E+01 4.04E +01 24 9-5 7430 SRM D CPS 4 25E+01 4 20E+01 415E+01 4.10E+01 4 05E+01 25 9-5 2-3-95 CORE FLOW MLB/HR 8 8 8 8 8 26 9-5 2-3-95 COREOP PSID 3 3 3 3 3 27 45 F1-3-310 CRO FLOW GPM 124.5 124.5 124.5 124.5 1245 28 9-5 6-96 WlOE RANGE PRESS PSIG 29 28 28 28 28 29 9-5 6-96 NAR RANGE PRESS PSIG 950 950 950 950 950 30 45 6-97 FEEDWATER FLOW MLB/HR 3 3 3 3 2.9 31 9-5 6-97 MAIN STEAM FLOW MLB/HR 0 0 0 0 0 32 9-5 6-98 NAR RANGE LEVEL INCHES 187 187 187 187 187 33 9-5 6 98 WIDE RANGE LEVEL INCHES 200 200 200 200 200 34 9-6 Li 107-5 CST LEVEL  % 22 21 21 20 20 35 9-6 Li-102-5A HOTWELL LEVEL N  % 1 1 1 1 1 36 9-6 U-102-5B HOTWELL LEVEL S  % 1 1 1 1 1 37 9-7 PI 101-29 CONDENSER VACUUM INHG 27 27 27 27 27 38 9-8 D/G A BKR OPEN OPEN OPEN OPEN OPEN 39 98 D/G B BKR OPEN OPEN OPEN OPEN OPEN 40 9 23 16-19-33A/C TORUS TEMP DEG F 163 165 167 168 169 41 9 25 Lt-46A TORUS LEVEL FEET 15.2 15.1 15.1 15.1 14.9 42 4 25 LI46B TORUS LEVEL FEET 15.2 15.1 15.1 15.1 14.9 43 4 25 TR-1619-44 TORUS PRESS PSIA 16.5 15.9 15.4 15 16 44 9-25 TR 16-19-44 DRYWELL PRESS PSIA 21 21 21 21 21 45 9-25 PR 1156-3 DW/ TORUS OP PSID 6.35 6.35 6.35 6.35 5.05 46 9-25 TR-16-19-45 DRYWELL TEMP DEG F 183 183 183 183 183 47 9-26 Pl 1-125-3A RX BUILDING DP INH 2O 12.47 -12.47 12.4 -12.47 -12.47 48 9-26 PI-1-125-3B RX BUILDING DP IN H2O 12.47 -12.47 -12.4 -12.47 -12.47 49 9 26 Fi-1 125-1 A SGTS FLOW CFM 993 993 993 993 993 p 50 9-26 F1-1125-1B SGTS FLOW CFM 993 993 993 993 993 51 CAD DW/ TORUS O2 CONC.  % 3.44 3 44 3 44 3.44 3.44

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VERMONT YANKEE NUCLEAR POWER STATION Rev.1 EMERGENCY PREPAREDNESS EXERCISE Page 91-1 1995 9.1 AREA RADIATION MONITORS

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R M S Il-1 9-11 RB/252 RX BLDG HI RADS - N R/hr <1 <1 <1 <1 <1 <1 <1 <1 RMS 11-2 9-11 RB/252 RX BLDG HI RADS - S R/hr <1 <1 <1 <1 <1 <1 <1 <1 R M S 11-3 9-11 RBCS 2 TlP RM HI RAD R/hr <1 <1 <1 <1 <1 <1 <1 <1 1 9-11 RB/232 SUPP CHAMB RB EXT PW mR/hr 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 BLDG mR/hr 03 03 0.3 0.3 0.3 03 03 03 4 9-11 RB/252 RX BLD NEUTRON TIP mR/hr 5 5 5 5 5 5 5 5 5

6 9-11 9-11 RB/252 RB/280 PERSONNEL HATCH RX B mR/hr 520 520 520 520 520 520 520 (hb ELEV ENTR 280FT RX mR/hr 8 8 8 8 8 7 7 8 7 9-11 RBC52 CRO REPAIR RX BLDG mR/hr 10 10 10 10 10 10 10 10 8 9-11 RB/303 ELEV ENTR 303FT RX mR/hr 4 4 4 4 3 3 3 4 9 9-11 RB/303 H2O CLEANUP RX BLDG mR/hr 4 4 4 4 4 4 4 4 10 9-11 RS/318 ELEV ENTR 318FT RX mR/hr 7 7 7 6 6 6 6 6 11 9-11 RE/318 H2O CLEANUP RX BLDG mR/hr 4 4 4 4 4 3 3 4 12 9-11 RB/345 ELEV ENTR 348FT ~ 'X mR!hr 4 4 4 4 4 4 4 3 14 9-11 RB/345 WEST REFUEL FL csLDG mR/hr 5 5 5 4 4 4 4 4 15 9-11 RB/345 SPENT FUEL POOL RX mR/hr 15 15 15 15 15 15 15 14 16 9-11 RB/318 NEW FUEL VAULT RX B mR/hr 0.5 0.: - 0.5 0.5 0.5 05 05 04 17 9-11 RWT252 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 1 1 1 1 19 9-11 RW/230 PUMP / TANK AREA RW R mR/hr 1.5 1.5 1.5 1.5 1.5 1.5 1.5 1.5 20 9-11 TB/248 N ACCESS 248FT TURB mR/hr 2 2 2 2 2 2 2 2 21 9-11 TB/248 MAIN STM VALVE TURB mR/hr 200 200 200 200 200 200 200 190 22 9-11 TB/232 COND DEMIN TURB BLD mR/hr 0.3 0.3 0.3 0.3 0.3 0.3 03 0.3 23 9-11 TB/252 DECON/ MACH SHOP TB mR/hr 0.15 0.15 0.15 0.15 0.15 0.15 0.15 0.15 24 9-11 TBr272 TURB STM IN TURB BL mR/hr 8 8 8 8 8 8 8 8 25 9-11 AB/272 VIEW GALLERY CONT RM mR/hr 0.46 0.46 0 46 0.46 0.46 0 46 0 46 0 42 26 9-11 TB/252 REAR GATE TURB WAREH mR/hr 0 09 0 09 0.09 0 09 0 09 0 09 0 09 0 08 13 9-11 TB/228 MOIST SEP AREA TURB mR/hr 110 110 110 110 110 110 110 100 Q________- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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(,~ / U VERMONT YANKEE t LEAR POWER STATION Rev.1 EMERGENCY PREPAREDNESS EXERCISE Page 91-2 1995 91 AREA RADtATION MONITORS

g. 7 - qqy npr ;gr g : SCENARIOTIMEl W02:00 !

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c 02:15 j 02:30! 02:45 03:00 03.15 03.30 03 45

~

l [, CLOCK TIME 10 00 10:15 10:30 10 45 11:00 11:15 11 30 11 45 l

ARM No. PANEL BLDG /ELV DESCRIPTiv.J UNITS

! RMS 11-1 9-11 RB/252 RX BLDG HI RADS - N R/hr <1 <1 <1 <1 <1 <1 <1 <1 R M S 11-2 9-11 RB/252 RX BLDG H1 RADS - S R/hr <1 <1 <1 <1 <1 <1 <1 <1 R M S 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 EXTCW mR/hr 8 8 8 8 (OSH (>lE41') OSH OSH OSH 2 9-11 RB/252 N PERSONNEL RX BLDG mR!hr 3 3 3 3 03 /Q 03 03 03 3 9-11 RB/252 S EQUtP RR RX BLDG mR/hr 0.3 03 03 0.3 {02 02 02 02 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 mR/hr 430 430 430 430 (OSH (>1E OSH OSH OSH 6 9-11 RB/280 ELEV ENTR 280FT RX B mR/hr 8 8 8 8 Y 5 5 5 7 9-11 RB/252 CRD REPA!R RX BLDG mR/hr 10 10 10 10 (h4j 4 4 4 8 9-11 RB/303 ELEV ENTR 303FT RX B mR/hr 3 3 3 3 '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 6 6 6 6 3 3 3 3 11 9-11 RB/318 H2O CLEANUP RX BLDG mR/hr 4 4 4 4 2 2 2 2 12 9-11 RB/345 ELEV ENTR 348FT RX B mR/hr 3 3 3 3 1 1 1 1 14 9-11 RB/345 WEST REFUEL RX BLDG mR/hr 4 4 4 4 1 1 1 1 15 9-11 RB/345 SPENT FUEL POOL RX B mR/hr 14 14 14 14 8 8 8 8 16 9-11 RB/318 NEW FUEL VAULT RX B mR/hr 0.4 04 04 04 0.3 0.3 0.3 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 mR/hr 1 1 1 1 1 1 1 1 19 9-11 RW/230 PUMP / TANK AREA RW B mR/hr 1.5 1.5 1.5 1.5 1.5 1.5 15 15 20 9-11 TB/248 N ACCESS 248FT TURB mR/hr 2 2 2 2 1_ 1 1 1 21 0-11 TB/248 MAIN STM VALVE TURB mR/hr 180 180 180 180 $ Q ,) 4 4 4 22 9-11 TBf232 COND DEMlN TURB BLDG mR/hr 0.3 0.3 03 0.3 0.1 0.1 0.1 01 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 TB/272 TURB STM IN TURB BLD mR/hr 8 8 8 8 7 7 7 7 25 9-11 ABf272 VIEW GALLERY CONT RM mR/hr 0.38 0.38 0 38 0 38 0.11 0 11 0.11 0 11 26 9-11 TB/252 REAR GATE TURB WAREH mR!hr 0 07 0 07 0 07 0 07 0 01 0 01 0 01 0 01 13 9-11 TB/228 MOIST SEP AREA TURB mR/hr 100 100 100 100 1 1 1 1 OSH = Off-scale High i___ _ _ _ _ _ _ . _ . _ _ _ . . . _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ .-

O O VERMONT YANKEE NUCLEAR POWER STATION O

Rev.1 EMERGENCY PREPAREDNESS EXERCISE. Page 91-3 1995

' 9.1 AE*. RADIATION MONITORS a; jd[j.

..f.s, bN:! ,, - , , , /, -

' ' ' CLOCKTIME '

kN .NQ5y[{ 04:30 b { 04:45 L : 05:00J

'12:00- : 12:15' 12 30 12:45 13.00 05:15 : 30 13 15 13.30 05 45 1345 06:00 14:00 j ARM No. PANEL BLDGdELV DESCRIPTION UNITS -

l RMS li-1 9-11 RBG52 RX BLDG HI RADS - N R/hr <1 <1 <1 <1 <1 <1 <1 <1 <1 g

! R M S 18-2 9-11 RBG52 RX BLDG HI RADS - S R/hr <1 /NI 25 25 25 25 25 25 h)T I R M S 11-3 9-11 RB/252 TIP RM HI RAD R/hr <1 M <1 <1 <1 <1 <1 <1 <1 j

1 9-11 RB/232 SUPP CHAMB RB EXTCW mR/hr OSH(1E>4) OSH OSH OSH OSH OSH OSH OSH OSH g

-2 9-11 RB/252 N PERSONNEL RX BLDG mR/hr 0.3 0.3 0.3 0.3 03 0.3 0.3 0.3 3-4 9-11 RB/252 S EQUIP RR RX BLDG mR/hr 0.3 OSH(>1E3) OSH OSH OSH OSH OSH OSH 4(JO_500) 9-11 RBG52 RX BLD NEUTRON TIP mR/hr 5 5 5 5 5 5 5 5 5 5 9-11 Ra/252 PERSONNEL HATCH RX B mR/hr OSH(1E>4) OSH OSH OSH OSH OSH OSH OSH OSH 6 9-11 RB/280 ELEV ENTR 280FT RX B mR/hr 5 5 5 5 5 5 5 5 5 7

8 9-11 9-11 RB/252 RB/303 CRD REPAIR RX BLDG ELEV ENTR 303FT RX B mR/hr mR/hr 4

1 idO)O 1 1 500 1

500 1

500 500 500 hh 1 1 1 1 i 9 9-11 __ RP1303 H2O CLEANUP RX BLDG mR/hr 4 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 3 11 9 11 RB/318 H2O CLEANUP RX BLDG mR/hr 2 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 1 14 9-11 RB/345 WEST REFUEL RX BLDG mR/hr 1 1 1 1 1 1 1 1 1 15 9-11 RB/345 SPENT FUEL POOL RX B mR/hr 8 8 8 8 8 8 8 8 8 16 9-11 RB/318 NEW FUEL VAULT RX B mR/hr 03 0.3 03 0.3 03 0.3 03 03 03 17 9-11 RW/252 PUMP RM RADWASTE BLD mR/hr 1 1 1 1 1 1 1 1 1 18 9-11 RWG52 RADW OPER AREA RW B mR/hr 1 1 1 1 1 1 1 1 1 19 9-11 RW!?30 PUMP / TANK AREA RW B m R/hr 1.6 1.6 1.6 16 1.6 16 1.6 16 1.6 20 9-11 TB/24% N ACCESS 248FT TURB mR/hr 1 1 1 1 1 1 1 1 1 21 9-11 TB/248 MAIN STM VALVE TURB mR/hr 4 4 4 4 4 4 4 4 4 22 9-11 TB/232 COND DEMIN TURB BLDG mR/hr 0.1 0.1 0.1 0.1 0.1 0.1 01 0.1 01' 23 9-11 TBG52 DECONTAM. TURB BLDG mR/hr 0.15 0.15 0.15 0.15 0.15 0.15 0.15 0.15 0.15 24 9-11 TB/272 TURB STM IN TURB BLD mR/hr 7 7 7 7 7 7 7 7 7 25 9-11 AB/272 VIEW GALLERY CONT RM mR/hr 0.1 0.1 0.1 0.1 - 0.1 0.1 0.1 01 0.1 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 0 01 13 9-11 TB/228 MOIST SEP AREA TURB mR/hr 1 1 1 1 1 1 1 1 1

, OSH = Off-scale High l

- . - - .-. - _ . _ . . . . _ _ . .. . _ . . - = - _ _ _ _ _ .-- __-- --- .

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

t I

VERMONT YANKEE NUCLEAR POWER STATK)N Rev.O EMERGENCY PREPAREDNESS EXERCISE Page 9.2-1 1995 9.2 PROCESS MONITORS e, y n ygy ggg g j ,j.p '

M 0055 ^ .p 00:45- ' 01:00 01:15 01:30 '01:45 i ARM' CLOCKTIME 08.00 - - 08:15 - 08:30 08:45 09 00 09:15 09-30 09:45

, NO. PANEL BLDG /ELV DESCRIPTION UNITS 9-2 STC57 STACK GAS MON-GAS 1 cpm 20 20 20 20 20 20 20 20 ,

9-2 STa57 STACK GAS MON-GAS 2 cpm 20 20 20 20 20 20 20 20  ;

9-2 RBa80 CONTAINMENT MON GAS cpm 650 650 650 650 650 650 650 i 9-2 RB/280 CONTAINMENT MON-PART cpm 26000 26000 26000 26000 26000 26000 26000 590 E 24000 9-2 STG57 STACK HI RANGE mRAr 0.1 0.1 0.1 0.1 0.1 0.1 0.1 01 27 9-2 DW/252 DRYWELL CH A RAr 2.8 2.8 2.6 2.8 2.8 2.8 2.8 - 2.5 i 28 9-2 DW/252 DRYWELL CH B RAr 2.8 2.8 2.8 2.8 2.8 2.8 2.ti 2.6 '

9-2 RB/280 RX BLDG VENT GAS cpm 150 150 150 150 150 150 150 150

• 1 9-2 RB/280 RX BLDG VENT- PART cpm 1500 1500 1500 1500 1500 1500 1500 1500 l 31 9-10 RB/280 RX BLDG VENT NORTH mRAr 2 2 2 2 2 2 2 17  !

! 32 9-10 RB/280 RX BLDG VENT SOUTH mRAr 2 2 2 2 2 2 2 17

! 453A 9-10 RB/345 SPENT FUEL POOL A mRAr 3 3 3- 3 3 3 3 3 453B 9 RB/345 SPENT FUEL POOL B mRAr 3 3 3 .3

. 3 3 3 3 I 9-10 RB/256 MAIN STM UNE A mRAr 180 180 180 180 180 180 180 170 9-10 RB/256 MAIN STM UNE B mRAr 180 180 180 180 180 180 180 170 9-10 RB/256 MAIN STM UNE C mRAr 180 180 180 180 180 180 180 170 I 9-10 RB/256 MAIN STM UNE D mRAr 180 180 180 180 180 180 180 170 38 9-10 TB/248 SJAE(AIR EJECTOR) mRAr 60 60 60 60 60 60 60 58 i

i i  !

i 6

l i

i VERMONT YANKEE NUCLEAR POWER STATION Rev. O EMERGENCY PREPAREDNESS EXERCISE Page 9 2-2 1995 9.2 PROCESS MONtTORS SCENARIO TIME 02-00 02:15 02:30 02:45 03.00 03:15 03:30 03.45 ARM' CLOCK TIME 10:00 10:15 10:30 1045 11:00 11:15 11:30 11:45 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 STG57 STACK GAS MON-GAS 2 cpm 20 20 20 20 20 ,_ 20 20 20 9-2 RBa80 CONTAINMENT MON GAS cpm f 540 540 540 540 DSI/Y DSL DSL DSL 9-2 RB/280 CONTAINMENT MON-PART cpm h 21000 21000 21000 21000 S'h DSL DSL DSL 9-2 ST/257 STACK HI RANGE mR/hr 0.1 0.1 0.1 0.1 T1 0.1 01 01 27 9-2 DWG52 DRYWELLCH A R/hr 2.5 2.5 2.5 2.5 (Mk 3500 4200 6300 28 9-2 DWG52 DRYWELL CH B R/hr 2.5 2.5 2.5 2.5 2400j 4 3500 4200 6300 9-2 RB/280 RX BLDG VENT GAS cpm 150 150 150 150 SO 150 150 150 9-2 RB/280 RX BLDG VENT - PART cpm 1500 1500 1500 1500 1500 1500 1500 1500 31 9-10 RB/280 RX BLDG VENT NORTH mR/hr 1.5 1.5 1.5 1.5 (ED'h 0.1 0.1 01 32 9-10 RB/280 RX BLDG VENT SOUTH mR/hr 1.5 1.5 1.5 1.5 d1W 0.1 01 0.1 453A 9-10 RB/345 SPENT FUEL POOL A mR/hr 3 3 3 3 3 3 3 3 4538 9-10 RB/345 SPENT FUEL POOL B mR/hr 3 3 3 3 3 3 3 3 9-10 RB/256 MAIN STM LINE A mR/hr 120 120 120 120 ch ! <1 <1 <1 9-10 RBa56 MAIN STM LINE B mR/hr 120 120 120 120 i <1j j <1 <1 <1 9-10 RB/256 MAIN STM LINE C mR/hr 120 120 120 120  ! <1 Y <1 <1 <1 9-10 RB/256 MAIN STM LINE D mR/hr 120 120 120 120 ) <1, <1 <1 <1 38 9-10 TB/248 SJAE(AIR EJECTOR) mR/hr 56 56 56 56 h1 <1 <1 <1 NOTE: DSL = Down Scale Low

_ . _ .. . . .- ._ .. -- - - ~ .

q r [\

VERMONT YANKEE NUCLEAR POWER STATION Rev.O EMERGENCY PREPAREDNESS EXERCISE Page 92-3 1995 9.2 PROCESS MONITORS 4: 04:00 i +

. SCENARIO TIME . 04:15 04:30 04:45 05.00 05:15 05:30 05:45 06:00 1 ARM ~ J~ ~

' N E I' * " ' CLOCK TIME ' b" ~' 12:00 12 15' 12:30 12:45 ' 13 00 13:15 13:30 13:45 14:00 NO PANEL BLDG /ELV DESCRIPTION UNITS 9-2 ST/257 STACK GAS MON-GAS 1 cpm 20 OSH>1E6 OSH OSH OSH OSH OSH OSH OSH 9-2 ST/257 STACK GAS MON-GAS 2 cpm 20 OSH>1E6 OSH OSH OSH OSH OSH OSH OSH 9-2 RB/280 CONTAINMENT MON GAS cpm DSL DSL DSL DSL DSL DSL DSL DSL DSL 9-2 RB/280 CONTAINMENT MON-PART cpm DSL DSL DSL DSL DSL DSL DSL DSL DSL 9-2 ST/257 STACK HI RANGE mR/hr O1 1200 12000 11000 10000 10000 9200 8400 8 27 9-2 DW/252 DRYWELL CH A R/hr 6100 5800 5300 4800 4300 3800 3500 TiOO 2800 28 9-2 DW/252 DRYWELL CH B R/hr 6100 5800 5300 4800 4300 6'M 9-2 RB/280 RX BLDG VENT GAS 3500 6 3100 4 2800 Q +

cpm 150 150 150 150 _ 150 150 150 150 150 9-2 RB/280 RX BLDG VENT - PART cpm 1500 1500 1500 1500 1500 1500 1500 1500 1500 31 9-10 RB/280 RX BLDG VENT NORTH mR/hr 0.1 0.1 0.1 0.1 01 01 0.1 0.1 0.1 32 9-10 RB/280 RX BLDG VENT SOUTH mR/hr 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 453A 9-10 RB/345 SPENT FUEL POOL A mR/hr 3 3 3 3 3 3 3 3 3 453B 9-10 RB/345 SPENT FUEL POOL B mR/hr 3 3 3 3 3 3 3 3 3 _

9-10 RB/256 MAIN STM UNE A mR/hr <1 <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 <1 9-10 RB/256 MAIN STM LINE C mR/hr <1 <1 <1 <1 <1 <1 <1 <1 <1 9-10 RBf256 MAIN STM UNE D mR/hr <1 <1 <1 <1 <1 <1 <1 <1 <1 38 9-10 TB/248 SJAE(AIR EJECTOR) mR/hr <1 <1 <1 <1 <1 <1 <1 <1 <1 NOTE: OSH = Off Scale H@h DSL = Down Scale Low

m-a& h n. AuAAsA J e.-- 4de.4J---

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 l

l I

l l

9.3 IN-PLANT RADIATION LEVELS l l

1

O 4

i l

i i

1 i

\

TABLE 9.3-1 Rev.1 Reactor Building, Elevation 345' Page 9.3-1 (mR/hr unless otherwise noted)

- Clock' '

< ARM- .ARMV ^ ARM- ARM: , ARM- < Zone :- ' Zone Zone

• Zone-

, *:aTime 1 11 2) 21 4:: ' -;15: 453 A. a E453'B? - Lla '

lic  : lit; ' :IV; 08:00 to 10:50 4 5 15 3 3 5 3 3 3 10:50 to 14:00 4 5 15 3 3 5 3 3 3 Zone Readings are average throughout zone.

General area contamination levels <1K dpm/100 cm2.

O REACTOR BUILDING N= ELEVATION 345'

1. 0' ' '

i CPEN -

=

l II i arca

-C-

. MONITORS l N l r 3 III o gae===

Elevelor Entsance gg, N  :

a_ C

~-

g ee_ _

Refusang Area /

=

{

a /h e e

0 -

a poe. Pw we., ..........................

3 Equemaru Pood . Cawwy  ;

SpentFundPool ............

spong pues poog

" ~~~*********************** l P P Em

\'

a O! !0 i

c' n I .

@ %p i w@

Elev.

di!

C 10 h iAC 10, i4C

?

r

(

TABLE 9.3-2 Rev.1 Reactor Building, Elevation 318' Page 9.3-2 (mR/hr unless otherwise noted) a e

> $%RC30cir ;W99 ARM *AARMMMARMEcZoneT&ZoneM/* Zones "ZoneWaZonep" Zone MrYZoneh

!d@NTinseSTi@t#BM10W2skiMMMM6&%;?fs + ^ Am 24tROMElit?QM9AW$!Mg9BiVEMBAMicm AVlfs 4 0.5 7 4 300 4 80 0.5 0.5

08

00 to 10:50 7 2 0.3 3 2 100 2 60 0.3 0.3 10:50 to 14:00 3 l

Zone Readings are average throughout zone.

General area contamination levels <1K dpm/100 cm2.

Y REACTOR BUILDING N~ ELEVATION 318'

" u a '

, .  : e o a c_5:5' --

s.am a a.a 27 ca cm c;mc a a, i .

(~ m,-.

MONITORS 3 nue. O n 3 -------- ,

1 a b ' " ' " "c Unge

,0 Fiq CUFmeWOomm.

a sw i yy m II I III=! 5 G) a.-%

Elevasor Erwance i I

. . . _ . . - O l hl i m I

i m g nemo, _ ,T(ca '__u a' F=.d.h.

_ t y-

---

i' ,____  ;- 4_ m g= w %.-c=

3 0  ;

+ so

, i <

-_____________x___.f i.

- a g spen l'gj i

i k

Oi a*==

Fueiveum %

• sonom w squiom.n pooi Fu.i sirop i t7 V

i i

i pool e i 3

l 4

?

.n

'u _g._ _ _ _ :o_r o_cu56c_o.-a' : _, ------_'g_P_ _ _ _

can..!,

~%

S 1 -

_- - r VII

- m - A - ,

O LJ TABLE 9.3 3 Rev.1 Reactor Building, Elevation 303' Page 9.3-3 (mR/hr unless otherwise noted)

Zone- Zone- tZone>

• Zone:' , Zone Clock ? ' ARM ~ ARM- . Zone - + ---Zone--

5 Time:. < x

<. 8 - 4 9 .-

.: lt. #it?  : 111 ' :IV > Zone VX  : VI: 'Vii' 4 4 4 3 600 3 60 0.1 0.2 08:00 to 10:50 4 4 3 800 t 3 80 0.1 0.2 10:50 to 11:30 1 4 4 3 1200 1 3 80 0.1 0.2 11:30 to 14:00 1 Zone Readings are average throughout zone.

General area contamination levels <1K dpm/100 cm2.

( ,

v  ;

l REACTOR BUILDING l c N= ELEVATION 303' l a

gooooou u u y

' *5

~~w II a l O =

Iy in l- 7j x

'_ _ _ _ _ _ _"_ _ _ _ Cl. rn g gy _ - - t_ - - - - - - _as

_ _ _ _ _ - _, ps p

' ' ^^ -

RV Samps. SekO eume 2

MONITORS l' g * "o V77) y,,,s @

M J a O l' ] *I f l ~~~~~~~~~~~~~~~~~~~I~~~~~[~

~

5 Og R8CCUHX i g p swam anuanc.

A e

]#7 i /

i  ?

neacw sweeno Dawaiwcaame ,,, ,_

g eew ,,,, / l g W I a.ccw %

l' i

' *P l; u,;,~

i

_ \

\'

O, 3g

=

.,__a__

._____________________l_____p__

0 h- oO I 1 r, U,r OOn c., n y

1

'V TABLE 9.3-4 Rev.1 Reactor Building, Elevation 280' Page 9.3 4 (mR/hr unless otherwise noted)

Cloch .:n ,-wfs.ve R8 Vent Na RB Vent 8%; Zone, cZone Zoned < Zone': eZone, aZone ' " Zoner Zone-

' 2 IV - ^1suV ' - 11VI" - ; Vit J  : Vilt n 7" aTimsm >%.? PARM 6e ! ARM 36a ARM 322. m ti <t ;11.: 21 a Ill; 8 25 9 7 3 1 2 8 08.00 to 10:50 8 2 2 5 150 8 5 2 1 1 5 10.50 to 1400 5 0.1 0.1 Zone Readings are average throughout zone.

General area contamination levels <1K dpm/100 cm2.

i 1

O REACTOR BUILDING N= ELEVATION 280'

" " ~

0000 .'

Mc ca"

.N 0(00 F o,.. __

EN n,= 00 00 ,m.,, o,. l O "f 9IV@ "f 9l m,,

(

MOMTORS --

u i

-u'u~d 'u~u~i III ,,%O " xi m i. v a C

W aw.._ .-

e= av=.

~-.mv,~

3 r-*Y p ." m m [ N,.

______ d' s

~

g

, , s e ~

~~

@ Reactor .q ven,

'h e

, _ II ,! ,

[ g E IrFa~[ ~

4.

,f , Cone /PartMon.

(Soum) 3 g

@ ) ,,,

! N' VI a

i 1

'"'"^"""c" I w pnewn 1 \

i Maal MC '

,c ,

l C N

b '

/ 4t?b "

It.1

~

(

, 'p  % , _ ,. _ _, _ _ _ D- - - - - - '_ _ ._.n_, _"_ _ M,_ . . .l --

s

- i ;yII. l t

e. l, i ..sn6, ,

, ,, pVIII ,, +i ,.,-

TABLE 9 3 5 Rev.1 Reactor Building Elevation 252' Page 9 3 5 (mR/hr unless otherwise noted)

P Clock - ARMr ' NtM:- JARM1 1 ARM.. ~ ARM - 4 RW . iZone - = Zone - ; Zonee eZone- NZone.- iZone Zone l Art Time ' u " 2/ a 3;% -4. a.-#. S e11~% 77 '14 29' N ii > , v II; # lit . > ' o IV 1 WV ' VIC . Vil l 0.3 520 10 100 5 4 0.3 50 0.3 10 25 j 08.00 to 10.50 4 5 OSH (*1E4) 4 100 20 120 100000 20 4 800 j 10.50 to 12.05 0.3 0.2 5 5 12.05 to 12.15 0.3 OSH(>1E3) 5 OSH 200 100 5 20 2000 100000 10000 200 800 l 12:15 to 13 45 0.3 OSH 5 OSH 500 100 5 20 5000 110000 25000 500 800 03 500 OSH 100 100 5 20 500 70000 10000 100 800 13 43 to 14 00 5

++ e ClodL:;. " w NORTH 2: SOUTH " w.TIP %'t RHR A***w Rtm S*" 1 RCL :< HPCl***

t c-> T W . RM8 Il t'. RMS Il-2.c RMS tl-3 n ; QUAD L MQUAD--QUA0 7 QUAD.

08.00 to 10 50 <1 <1 <1 5 5 1 5 10:50 to 11.00 <1 <1 <1 5 80 1 5 11:00 to 1130 <1 <1 <1 5 200 1 5 11:30 to 1145 <1 <1 <1 800 800 1 5 11:45 to 12.05 <1 <1 <1 3000 3000 1 5 f 12.05 to 12.15 <1 10 <1 2000 2000 1 5 l 12.15 to 13 45 <1 25 <1 2000 2000 1 5 l 13:45 to 14 00 <1 10 <1 1800 1800 1 5 NOTES Zone Readings are average throughout Zone. l 1

fm General area contamination levels <1K dom /100 cm2.

" RMS 11 Readings in R/hr (High-Rarge Accident ARMS 1R/hr to 10,000 R/hr) i

( }

• • • Zone Readings are average dose rates throughout the RHR, RCIC and HPCI Quad elevation areas.

REACTOR BUILDING N= ELEVATION 252'

^ - -e ~

1.aa. w mun

!_. III G a ri

_ o. 4, a ii To AHR AQuao -~

y- - - - , --

MONITORS ] L,- - - IV RNR S

, RHR A Valve Valve AMs ,1 1 (NW htocit) l Room Acorn u n ., ,,, ,,,

g l , ,, 58 aa "a*

3

, i =-. s -

o aus n.s tne n- o=,i 3 ,- /) ________p c

O, a.aca j,,_ ,/ cao c",

s E 5

• D m

r=onn.soie.no un so*>ng 4ce.= g._ ,

pacia, % % g-- -

.i sawn oi cn.,g. voun. i ~-- p

-n w acc..  ; cp a n..c. % %,.o 1 - - -

- II ', g:: ~

. ." (n W Mmew DP WecawW Q \ ,4'4 R..ctor Sussng n ctot / t -----

@y 3

Og emonn.uc. son

, i

"" "5'- E g, .gg,hao,,a -

, ' a-I y

gauc=emcony.

- - - L.- p: ,

(o, ...

a-p I

.VII i

O O,, - -- - _ _ _ _ u' ,, F : --  : y 3. ,,.. =

3 s\

T* ar'C l m,aav l m nL0 -0 ,

E I ,i 4 < ' y r.,a Q

@ i a -

3 ,

f

3 (J

TABLE 9.3-8 Rev.1 Turbine Deck, Elevation 272' Page 9.3-6 (mR/hr unless otherwise noted)

• WSWClock3W@tARM199t" Zoned 4WRZoneAMMcZones &TurbineDeckCAM(cpm)2 i MNTunes%W!i ARM 24WM@ in ' GRMW7tpfwMWN m 9% anqNGW9FT Parbculate 08:00 to 10:50 8 100 150 8 250 900 10:50 to 14:00 7 10 20 7 250 900 Zone Readings are average dose rates throughout zone.

General area contamination levels <1K dpm/100 cm2.

'G O

TURBINE DECK ELEVATION 272'

~= 350 ~P,.,?

en I

t@ [E ~ N h ,_g g=

l-C l ____) 3 l

---

il)e 1-c il

@{__- h '

l-l e

'D m

i i

i cus i i e 8 IIIlcuil l_ _ _ _ u __ ____________ l l w

l e ,

! E II ' [5a*J

^

k + + + ++ +

MONITOR

[a_ r- -n =

furtune $leem inlet

l (D ,

y/ '

TABLE 9.3-7 Rev.1 Turbine Building Truck Bay, Make-Up Demineralization Cond. Page 9.3-7 Demineralization Areas, Elevation 252' (mR/hr unless otherwise noted)

%9 'sClockMWMRMa14a23At"^2EARM >;.R$14.36hsZone6MeZona%!# Zone M:': > Zones"

$5WTime/## MUM 7(cpm)W1 J326' -ce'(cpm)s12 IWP:NsMitF*Mr#3alir F+i', lWHis 08:00 to 10:50 150 0.09 150 0.2 0.2 0.1 0.2 10:50 to 14:00 150 0.01 150 0.7 0.3 0.2 0.2 Zone Readings are average dose rates throughout zone.

General area contamination levels <1K dpm/100 cm2.

• i

,O 4 PRETREATMENT ROOM, BOILER ROOM, TURBINE LOADING B AY, MUDS, DIESELS, COND. DEMIN. HATCH ELEVATION 252'

-N s3a

~

f @9 Poroi l-

'1

- -. u. M_l i i

l I'. I u--

l I C

= *t~ _i l l i

m

'n a--a 0 , ] g g 'c==~5l l co h Eacner r------

$ E$9 I, 3 li l 21 r II _l la-"c'ta=

a-- ,

o o O .  : -J' e 2'

d O '

2 l III m -

• On O o I=

lilill  ! ,  !

u g . :-

,......y.._

m, c" 5

u

;

i -

MONITORS D

'+--'~-**] l ll .

SJAE ROOM 7 rm a - -

i l

o L...j

@ a=oa.m rra l l l l 0 ~

• g . "r ..... .m 11

^

\ \ I..............

ggggg

= a o

e o a

gr-.- c O

c-.,.<,_.,.,

O e N -

A f.0 ' Ao o- 1

m U

TABLE 9.3-8 Rev.1 Turbine Building Cond. Bay, Elevation 248' Page 9.3-8 (mR/hr unless otherwise noted)

1. Clockuee#N@ARMhWARMEAZonesD5Zonaa AZone!!aWZoned tdZonemZonen

%MOTisneM6Rus207 @a21140WillMW RNaf6FNVPMW6VIMFiMVilW10!Vllte 08:00 to 10:50 2 200 2 2 4 8 200 2 10:50 to 1400 1 4 1 1 2 3 4 1 Zone Readings are average dose rates throughout zone.

General area contamination levels <1K dpm/100 cm2.

O LJ TURBINE BUILDING c N= ELEVATION 248'

_g dr - - -

W" m W i

(b ,{ _ _ _ _ _ _ VII o ., ~ ,,. o _ _o_-~~ _ _e _o _ _ _yQ _ _ QQQl__ _ _ _ _ _ _ _U (

MONITORS i / --- -

c n- );

MII l @ a+~ a*uo o - ~ ,~. o i g~ j' g i

2!

@ ;re- ee ^ ^ ^ ^ l ' e t-VI'l#El 0 Twtiene Swdeng Mem H! E i

g Lg., ____ m l s l Ld if so I Concenter Condenser 1

' haMom h t

l T IO -

g 7 f"~ l '- III I==%m!, @@ V V V l lll e

00 ._V c lE*~~ in n; O i j i.

1 I

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TABLE 9.3-9 Rev.1 Turbine Building, Demineralization /OG Areas, Elevation 232' Page 9.3 9 (mR/hr unless otherwise noted)

&nPeClocitMISM64e*ARW:* Mis OARW9p;M!EZonenEnGeZoneMcSWZoneCW h MTkne9 ROME 422?sMMB3&E "WMINR*ME MtMME 'ilfl@s 08:00 to 10:50 0.3 60 0.2 0.5 0.2 10:50 to14:00 0.1 D/S 0.2 0.5 0.2 Zone Readings are average dose rates throughout zone.

General area contamination levels <1K dpm/100 cm2.

D/S = Downscale Reading ia a v

1 TURBINE BUILDING l ELEVATION 232' i

, = =c r . .a. -

11111 ggg U f g M, ' y~ gg *Oc O- c

< , . cn I i ,

ao rD.,

MONITORS g 0I g g re- ,

g II 5 g, , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

Q] g

@'L*-

l i

D "

' , , ifl-

%-m u U. = =-

C m

l -

o a s a m

@ -'<=.- - I i@l l r- l m 3  ; ,B:

m r i v 9= 0 1 l l @@@ &

l $ i(

l III a

e w

\

~ l "*" i F ~

l

!,@ rinnini mnmd1 $

l -

l O) t V

TABLE 9.3-10 Rev.1 Turbine Building Cond. Bay, Elevation 222'6" 228'6" Page 9,3-10 (mR/hr unless otherwise noted) c;@cClock #v n s ARM &M! Zone @n&ZoneJWFZonemf#ZoneWMZonas MeZonem 40 gh Oggppt;;jpg, 3gesgggggy lep;tgggygp;3y; appgygg degg;yggsp 08:00 to 10:50 110 3 1 50 150 2 75 10:50 to 14:00 1 3 1 5 15 2 10 Zone Readings are average dose rates throughout zone.

General area contamination levels <1K dpm/100 cm2.

O TURBINE BUILDING

ELEVATIONS 222' AND 228'

-N r l l

! III  !

, MONITOR i i

.a a r.

G ~1.-

._~, - ER_Y ; N non v a

nonl M,

s gg l,g:he

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RES c2 '

j ;__] L_ @ l" * * @

II

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T* 'T" ! IV ! V, h j _ h r- l- $

O Efle6*Il VVVV!99 I i  !

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l . , , , _ _ l c

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i

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l 9_ _ _ _ : _ _ _ _w'_ _:

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V TABLE 9.3-11 Rev.1 Torus Area (Catwalk and Torus Elevation Areas) Page 9.311 (mR/hr unless otherwise noted)

IMtYruCl6cltE4!$125*iMWMMMMM^!MMAdi4AMM9?htMM*UMMW*##EWW pg%%Migf4%#2MMMM!M?sMS&MiMENEWd%%%MBWMMWOMMMS(WME 08:00 to 10:50 8 8 10:50 to 14:00 OSH(>1E4) 50 R/hr Zone readings are average dose rates throughout the Torus Catwalk and Torus elevation areas.

m tj TORUS CATWALK

+

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MONITOR

@ _n.  :

O l C '

Oi swees%

I on chamew Eat Caswee r< w i

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I

O vERuONT vANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE l

1995 9.4 PLANT CHEMISTRY DATA SECTION PAGE 9.4.1 Reactor Coolant Activity Data.... ..... ............ ........ 9.4.1-1 9.4.2 Prirnary Containment Air Activity Data................... 9.4.2-1 9.4.3 Reactor Building Air Activity Data........ ................. 9.4.3-1 O

l l

4 5

1 i

l k

LO -

4 i

Rcv 0 Page 9.4.1 1 VERMONT YANKEE NUCLEAR POWER STATION  !

EMERGENCY PREPAREDNESS EXERCISE I i 1995  !

9.4.1 REACTOR COOLANT ACTIVITY DATA i

' l A. Reactor Coolant Activity Concentrations (uCi/ml) l isotope Prior to 1050 1050 1100 1100-1115 1115-1130 l-131 2.5E-04 2.1 E+02 2.1 E+02 2.1 E+02 j l

1-132 2.8E-04 3.0E+02 2.8E+02 2.6E+02 l

1-133 5.2E-04 4.3E+02 4.2E+02 4.2E+02 l-134 4.1 E-04 4.2E+02 3.4E+02 2.8E+02 l l-135 4.5E-04 3.9E+02 3.8E+02 3.7E+02 Total lodine 1.9E-03 1.8E+03 1.6E+03 1.5E+03 l l-131 D.E. 4.5E-04 3.8E+02 3.7E+02 3.7E+02 Kr-83m 1.2E-03 3.3E+00 5.0E+00 6.4E+00 i Kr-85m 2.5E-02 5.4E+00 5.3E+00 5.1E+00

.! Kr-85 4.8E-03 2.4E-01 2.4E-01 2.4E-01 )

Kr-87 2.9E-03 9.5E+00 8.3E+00 7.2E+00 l

! Kr-88 1.0E-03 1.3E+01 1.2E+01 1.1 E+01 Xe-131m 9.1 E-05 1.4E-01 1.4E-01 1.4E-01 l

Xe-133m 7.3E-04 1.3E+00 1.3E+00 1.4E+00 l

i Xe-133 5.3E-03 4.3E+01 4.4E+01 4.4E+01  :

Xe-135m 5.8E-03 2.4E+01 4.2E+01 5.0E+01 l Xe-135 2.2E-03 1.3E+01 1.9E+01 2.6E+01 )

1 Xe-138 3.8E-03 2.3E+01 1.1E+01 5.4E+00 l

Total Gas 5.3E-02 1.4E+02 1.5E+02 1.6E+02  !

. l l

b l 4

i i l

l

! I

. l i

t

O l i

Reactor coolant sample dose rates are provided in Section 9.5.1

- . . - - . . - _ _ . . . - .. - - - ~.

Rev0 I Page 9.4.1-2

VERMONT YANKEE NUCLEAR POWER STATION

EMERGENCY PREPAREDNESS EXERCISE 1995 1 9.4.1 REACTOR COOLANT ACTIVITY DATA l

A. Reactor Coolant Activity Concentrations (uCl/ml)

I lsotope 1130-1145 1145-1200 1200-1215 1215-1230 ,

j 1-131 2.1 E+02 2.1 E+02 2.1 E+02 2.1 E+02 l l-132 2.4E+02 2.2E+02 2.1 E+02 1.9E+02 1-133 4.2E+02 4.1 E+02 4.1 E+02 4.1 E+02 i 1-134 2.3E+02 1.9E+02 1.5E+02 1.3E+02 l l-135 3.6E+02 3.5E+02 3.4E+02 3.4E+02 1 j Total lodine 1.5E+03 1.4E+03 1.3E+03 1.3E+03 3.6E+02 3.6E+02 3.6E+02 l-131 D.E. 3.7E+02 j Kr-83m 7.5E+00 8.4E+00 9.1 E+00 9.7E+00  ;

Kr-85m 4.9E+00 4.7E+00 4.6E+00 4.4E+00 i Kr-85 2.4E-01 2.4E-.01 2.4E-01 2.4E-01 l Kr-87 6.3E+00 5.5E+00 4.8E+00 4.2E+00 f 8.8E+00 i Kr-88 1.1 E+01 9.9E+00 9.4E+00 i~ Xe-131m 1.4E-01 1.4E-01 1.5E-01 1.5E-01 Xe-133m 1.4E+00 1.4E+00 1.5E+00 1.5E+00 Xe-133 4.5E+01 4.5E+01 4.6E+01 4.6E+01 Xe-135m 5.3E+01 5.4E+01 5.4E+01 5.3E+01

Xe-135 3.2E+01 3.8E+01 4.4E+01 5.0E+01  !

j Xe-138 2.6E+00 1.2E+00 6.0E-01 2.9E-01  ;

Total Gas 1.6E+02 1.7E+02 1.7E+02 1.8E+02 l 3

i 2 l i

l

O

Reactor coolant sample dose rates are provided in Section 9.5.1

- . . _ . . ~ .- - - . - -.-- - - - - . - ..- -. -- - -. -.---- . - ..-.

A Rev 0 l Page 9.4.13

VERMONT YANKEE NUCLEAR POWER STATION

EMERGENCY PREPAREDNESS EXERCISE l

1995 1

9.4.1 REACTOR COOLANT ACTIVITY DATA

]

t 1 A. Reactor Coolant Activity Concentrations (uCi/ml) 1 Isotope 1230-1245 1245-1300 1300-1315 1315-1330

)

3 1-131 2.1 E+02 2.1 E+02 2.1 E+02 2.1 E+02 1-132 1.8E+02 1.6E+02 1.5E+02 1.4E+02 l-133 4.0E+02 4.0E+02 4.0E+02 3.9E+02 l-134 1.0E+02 8.6E+01 7.0E+01 5.8E+01 j

l-135 3.3E+02 3.2E+02 3.1 E+02 3.0E+02 l* Total lodine 1.2E+03 1.2E+03 1.1 E+03 1.1 E+03 l-131 D.E. 3.5E+02 3.5E+02 3.5E+02 3.5E+02 i Kr-83m 1.0E+01 1.0E+01 1.1 E+01 1.1 E+01

} Kr-85m 4.2E+00 4.1E+00 3.9E+00 3.8E+00 4 Kr-85 2.4E-01 2.4E-01 2.4E-01 2.4E-01 l Kr-87 3.7E+00 3.2E+00 2.8E+00 2.4E+00 I l

i Kr-88 8.3E+00 7.8E+00 7.3E+00 6.9E+00 Xe-131m 1.5E-01 1.5E-01 1.5E-01 1.5E-01

. Xe-133m 1.5E+00 1.6E+00 1.6E+00 1.6E+00 Xe-133 4.7E+01 4.7E+01 4.8E+01 4.8E+01 5

Xe-135m 5.2E+01 5.1E+01 5.0E+01 4.8E+01 i Xe-135 5.5E+01 6.0E+01 6.5E+01 7.0E+01 Xe-138 1.4E-01 6.6E-02 3.2E-02 1.5E-02 Total Gas 1.8E+02 1.9E+02 1.9E+02 1.9E+02 i

i i

l l

l O

Reactor coolant sample dose rates are provided in Section 9.5.1

]

Rsv 0 Pags 9.4.1-4 i

i

]P VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE l

1995 I 9.4.1 REACTOR COOLANT ACTIVITY DATA l A. Reactor Coolant Activity Concentrations (uCi/ml)

} lsotope 1330-1345 1345-1400 3 1-131 2.1 E+02 2.1 E+02 j 1-132 1.3E+02 1.2E+02 l-133 3.9E+02 3.9E+02 i 1134 4.7E+01 3.9E+01

l-135 2.9E+02 2.9E+02

! Total lodine 1.1 E+03 1.0E+03 i 1-131 D.E. 3.5E+02 3.4E+02 i

Kr-83m 1.1 E+01 1.1 E+01 l Kr-85m 3.6E+00 3.5E+00 l Kr 85 2.4E-01 2.4E-01 Kr-87 2.1 E+00 1.9E+00 i Kr-88 6.5E+00 6.1E+00 Xe-131m 1.5E-01 1.5E-01

)

] Xe-133m 1.7E+00 1.7E+00 Xe-133 4.9E+01 4.9E+01 f

i Xe-135m 4.7E+01 4.6E+01 Xe-135 7.4E+01 7.8E+01 l

Xe-138 7.3E-03 3.5E-03 l

Total Gas 2.0E+02 2.0E+02 l

i i

4 i

.o Reactor coolant sample dose rates are provided in Section 9.5.1

Rev0 l Page 9.4.21 i

l j VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 ,

l 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Concentrations (uCl/cc)

Isotope Prior to 1050 1050-1100 1100-1115 1115-1130 1-131 5.0E 10 1.6E-01 3.7E-01 5.0E-01 4 l-132 2.0E-10 2.2E-01 4.8E-01 6.0E-01 t 1-133 7.6E-10 3.1E 01 7.3E 01 9.7E-01 1-134 1.2E-10 3.0E-01 5.9E-01 6.5E-01 l l135 4.6E 10 2.9E-01 6.6E-01 8.6E-01 Total lodine 2.0E 09 1.3E+00 2.8E+00 3.6E+00 l l 131 D.E. 7.5E-10 2.8E 01 6.5E-01 8.7E-01 KR-83M 2.4E 07 3.4E+00 7.6E+00 9.9E+00 l KR-85M 5.7E-07 7.3E+00 1.7E+01 2.2E+01 KR-85 3.3E-08 3.5E-01 8.3E-01 1.1 E+00 l

KR 87 0.0E-07 1.3E+01 2.6E+01 3.1 E+01 KR 88 1.3E-06 1.9E+01 4.1 E+01 5.2E+01 l XE 131M 1.9E-08 2.0E-01 4.8E-01 6.4E-01 XE 133M 1.8E 07 1.9E+00 4.4E+00 5.9E+00

{

{ XE-133 5.9E-06 6.3E+01 1.5E+02 2.0E+02 XE 135M 1.9E-07 1.1 E+01 1.8E+01 1.8E+01

XE-135 1.5E-06 1.4E+01 3.4E+01 4.8E+01

XE-138 3.6E-06 3.4E+01 3.9E+01 2.5E+01 Total Gas 1.4E-05 1.7E+02 3.4E+02 4.1 E+02 A

O 4

Primary containment air sample dose rates are provided in Section 9.5.2

Rsv 0 Paga 9.4.2 2 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Concentrations (uCi/cc)

Isotope 1130-1145 1145-1200 1200-1215 1215-1230 1-131 5.7E-01 6.1 E-01 6.4E-01 6.3E-01 1-132 6.4E-01 6.4E-01 6.2E-01 5.7E-01 1133 1.1 E+00 1.2E+00 1.2E+00 1.2E+00

^

1-134 6.1 E-01 5.4E-01 4.6E-01 3.8E-01 l-135 9.7E-01 1.0E+00 1.0E+00 1.0E+00 Total lodine 3.9E+00 4.0E+00 3.9E+00 3.8E+00 1-131 D.E. 9.8E-01 1.1 E+00 1.1 E+00 1.1 E+00 KR-83M 1.1 E+01 1.2E+01 1.2E+01 1.1 E+01 e KR-85M 2.4E+01 2.5E+01 2.5E+01 2.4E+01 1.4E+00 KR-85 1.3E+00 1.4E+00 1.5E+00 KR-87 3.1 E+01 2.9E+01 2.6E+01 2.3E+01 KR-88 5.6E+01 5.7E+01 5.6E+01 5.2E+01 XE-131M 7.3E-01 7.9E-01 8.3E-01 8.2E-01 XE-133M 6.7E+00 7.3E+00 7.6E+00 7.5E+00 1 XE-133 2.3E+02 2.5E+02 2.6E+02 2.6E+02 XE-135M 1.8E+01 1.7E+01 1.6E+01 1.4E+01 XE-135 5.7E+01 6.3E+01 6.8E+01 6.9E+01 XE-133 1.4E+01 7.1 E+00 3.6E+00 1.7E+00 Total Gas 4.5E+02 4.7E+02 4.8E+02 4.6E+02 l

i-t Primary containment air sample dose rates are provided in Section 9.5.2 l

u.-.

Rev0 Page 9.4.2 3 i

l l i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 l 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA ,

1 l

1 A. Primary Containment Air Concentrations (uCi/cc)

]

l isotope 1230-1245 1245-1300 1300-1315 1315-1330 1-131 6.2E 01 6.1 E-01 5.9E-01 5.8E-01 i i 1-132 5.2E-01 4.7E-01 4.2E-01 3.8E-01 l j 1133 1.2E+00 1.1 E+00 1.1 E+00 1.1 E+00 l l134 3.0E-01 2.4E-01 2.0E-01 1.6E-01

] l-135 9.5E-01 9.1 E-01 8.6E-01 8.2E-01 l Total lodine 3.6E+00 3.3E+00 3.2E+00 3.0E+00 i 1-131 D.E. 1.0E+00 1.0E+00 9.8E-01 9.6E-01

! KR-83M 1.1 E+01 1.0E+01 9.5E+00 9.0E+00 l i- KR-85M 2.3E+01 2.1 E+01 2.0E+01 1.9E+01 i j KR-85 1.4E+00 1.4E+00 1.3E+00 1.3E+00

! KR-87 2.0E+01 1.7E+01 1.4E+01 1.2E+01 KR-88 4.8E+01 4.5E+01 4.1 E+01 3.7E+01

i. XE-131M 8.1 E-01 7.9E-01 7.7E-01 7.5E-01 l XE-133M 7.4E+00 7.2E+00 7.0E+00 S.8E+00 XE-133 2.5E+02 2.5E+02 2.4E+02 2.3E+02 l XE-135M 1.3E+01 1.3E+01 1.2E+01 1.2 E+01

[ XE-135 7.0E+01 7.1 E+01 7.1 E+01 7.2E+01 XE-138 8.0E-01 3.8E-01 1.8E-01 8.2E-02 I Total Gas 4.5E+02 4.4E+02 4.2E+02 4.0E+02 1

1 4

O l 2

Primary containment air sample dose rates are provided in Section 9.5.2 4

l 1

Rsv 0  !

Paga 9.4.2-4 O

VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY PREPAREDNESS EXERCISE  !

l 1995 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA j A.' Primary Containment Air Concentrations (uCi/cc) j l

Isotope 1330-1345 1345-1400 j I-131 5.6E-01 5.4E-01 l l-132 3.5E-01 3.1 E-01 l-133 1.0E+00 9.9E-01 1-134 1.2E-01 9.9E-02 l 1-135 7.8E-01 7.3E-01 Total lodine 2.8E+00 2.7E+00 '

l-131 D.E. 9.1 E-01 ,,

8.8E-01 i

l' KR-83M 8.5E+00 8.1 E+00 l KR-85M 1.7E+01 1.6E+01 l KR-85 1.3E+00 1.2E+00 KR 87 1.0E+01 8.7E+00 i KR-88 3.4E+01 3.1 E+01 XE-131M 7.3E-01 7.1 E-01 1 XE-133M 6.6E+00 6.5E+00 l XE-133 2.3E+02 2.2E+02 XE-135M 1.2E+01 1.1 E+01

XE 135 7.2E+01 7.2E+01  !

XE-138 3.8E-02 1.8E-02 I l

i Total Gas 3.9E+02 3.8E+02 l

. \

i I 4

l l

l i

iO Primary containment air sample dose rates are provided in Section 9.5.2 I

l

Rev0 Page 9.4.3 O- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA A. Reactor Building Air Concentrations (uCi/cc)- All Elevations isotope 0800-1400 1-131 l-132 l133 l-134 l-135 Total lodine l-131 D.E.

Kr 83m  ;

Kr-85m i O- Kr-85

• i I

Kr-87 Kr 88 Xe-131m l Xe-133m Xe-133 ,

Xe-135m I i Xe-135 l Xe-138 i Total Noble Gas *  !

i I

l 1

1 i

I

! i lO

(*) Indicates activity concentration below MDL For Reactor Building sample dose rates see Section 9.5.3.

l

l VERMONT YANKEE NUCLEAR POWER STATION

EMERGENCY PREPAREDNESS EXERCISE 1995 e

i 1

l 9.5 RADIOLOGICAL SAMPLE DOSE RATES SECTION PAGE l

9.5.1 Reactor Coolant Sample Dose Rates... .. ..... ..... 9.5.1 -1 I

9.5.2 Primary Containment Sample Dose Rates ..... ... 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 1

i I

I

l d

j a

1

O

?

. - . - -. . .~ .- . - ... . - _ . ... . - . -_ --

Rev0 Page 9.5.1 1 4

(

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 3

9.5.1 Reactor Coolant Sample Dose Rates A. Gas Samples

Unshielded Shielded (1 inch lead)

J (mR/hr per cc)* (mR/hr per cc)*

4 Time Contact 1 ft Contact 1 ft Prior to 1050 1.5E-02 1.1 E-04 ly$les 1.9E 04 1.3E-06 1050-1100 4.0E+01 2.7E-01 k@!A(! 4.8E-01 3.4E-03 1100-1115 4.3E+01 3.0E-01 $9hM 5.3E-01 3.7E-03

1115-1130 4.6E+01 3.1 E-01 f4MDI 5.6E 01 3.9E-03

! 1130-1145 4.8E+01 3.3E-01 ilig#Rd 5.8E 01 4.1 E-03 I 1145-1200 4.9E+01 3.4E-01 di$d 6.0E-01 4.2E-03

1200-1215 5.1E+01 3.5E-01 (We!3 6.2E-01 4.4E-03 l 1215-1230 5.2E+01 3.6E-01 $@M 6.3E-01 4.5E-03 l 1230-1245 5.3E+01 3.6E-01 15 %1 6.5E-01 4.6E-03 1245-1300 5.4E+01 3.7E-01 $$M 6.6E-01 4.6E-03 j 1300-1315 5.5E+01 3.8E-01 $%f$3 6.7E-01 4.8E-03 1315-1330 5.6E+01 3.8E-01 feaM 6.8E-01 4.8E-03 1330-1345 5.7E+01 3.9E-01 MBei 6.9E-01 4.9E-03 4 1345-1400 5.7E+01 3.9E-01 24SD.

1 7.0E-01 5.0E-03 i-l 1

i I

i

O

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

. .. .. . . . - . -. . - . - ~ -.. - . . - .

1 Rev0 Page 9.5.1-2 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE .

1995 9.5.1 Reactor' Coolant Sample Dose Rates B. Liquid (lodine) 1 Unshielded Shielded (1 inch lead)

(mR/hr per cc)* (mR/hr per cc)*

Time Contact 1 ft (fsM Contact 1 ft Prior to 1050 1.5E-03 1.0E-05 REsd 1.9E-05 1.3E-07 1050-1100 1.4E+03 9.5E+00 MM3 1.7E+01 1.2E-01 1100-1115 1.3E+03 8.8E+00 r##f4 1.6E+01 1.1 E-01 1115-1130 1.2E+03 8.3E+00 f#$R1 1.5E+01 1.0E-01 1130-1145 1.1 E+03 7.9E+00 WR4 1.4E+01 9.7E-02 .

1145-1200 1.1 E+03 7.5E+00 MVM 1.3E+01 9.1 E-02 I 1200-1215 1.0E+03 7.2E+00 $4WM 1.3E+01 8.7E-02 1215-1230 1.0E+03 6.9E+00 fifBEi 1.2E+01 8.5E-02 l 1230-1245 9.5E+02 6.6E+00 $$sM 1.2E+01 8.1 E-02

, 1245-1300 9.2E+02 6.4E+00 l$$$s) 1.1 E+01 7.8E 02 1300-1315 8.9E+02 6.2E+00 D?tM 1.1 E+01 7.5E-02 1315-1330 8.6E+02 5.9E+00 B921 1.1 E+01 7.3E 02 1330-1345 8.3E+02 5.8E+00 $N$13 1.0E+01 7.1 E-02 1345-1400 8.2E+02 5.7E+00 kWMd 1.0E+01 6.9E-02 i

i i

O l t

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

i

. -. \

Rsv0 Page 9.5.2 6

O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 l 9.5.2 Primary Containment Sample Dose Rates A. Gas Samples Unshielded Shielded (1 inch lead)

(mR/hr per cc)* (mR/hr per cc)*

}

Time Contact 1 ft Contact 1 ft 4

Prior to 1050 4.1 E-06 2.8E-08 N&# 5.0E-08 3.5E-10 1050-1100 4.8E+01 3.3E-01 f3sM 5.9E-01 4.2E-03 l 1100-1115 9.7E+01 6.8E-01 S$@i 1.2E+00 8.5E-03 1115-1130 1.2E+02 8.3E-01 finM 1.5E+00 1.0E-02 1130-1145 1.3E+02 9.0E-01 Etm 1.6E+00 1.1 E-02 1145-1200 1.4E+02 9.4E-01 k22#11 1.7E+00 1.2E-02 1200-1215 1.4E+02 9.5E-01 MMM 1.7E+00 1.2E-02 1215-1230 1.3E+02 9.3E-01 Rhind 1.7E+00 1.2E-02 1230-1245 1.3E+02 8.9E-01 EbNM 1.6E+00 1.1 E-02 1245-1300 1.3E+02 8.7E-01 E@K4 1.6E+00 1.1 E-02

! 1300-1315 1.2E+02 8.3E-01 n!Eni 1.5E+00 1.0E-02 1315-1330 1.2 E+02 8.0E-01 $$$M 1.4E+00 1.0E-02 l

1330-1345 1.1 E+02 7.8E-01 GiW11 1.4E+00 9.8E-03 1345-1400 1.1 E+02 7.5E-01 $4Mit 1.3E+00 9.4 E-03 a

l d

l l

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

I l

Rsv 0 Page 9,5,3 o VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE l

1995 j

l

9.5.3 Reactor Building Air Sample Dose Rates (lodine Cadridge Only) '

All Elevations 4

Unshielded Shielded (1 inch lead) ,

(mR/hr per cc)* (mR/hr per cc)* l Time Contact 1 ft Contact 1 ft I 0800-1400 As Read As Read @Wh4 As Read As Read 4

1 i

O 1 e

1 i

i.

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

Rav0 Page 9.5.41 i

A VERMONT YANKEE NUCLEAR POWER STATION V EMERGENCY PREPAREDNESS EXERCISE i 1995 i

9.5.4 Plant Vent Stack Sample Dose Rates A. Gas (Grab Sample)

Unshielded Shielded (1 inch lead)

(mR/hr per cc)* (mR/hr per cc)*

j Time Contact i ft Contact i ft PRIOR TO 1210 As Road As Read S$3ft As Read As Read i 1210-1215 7.7E-02 5.4E-04 $$53 9.5E-04 6.8E-06 1215-1230 7.7E-01 5.4E-03 BiBTd 9.5E-03 6.8 E-05 l 1230-1245 7.5E-01 5.3E-03 $iSWd 9.3E 03 6.7E-05 l 1245-1300 7.2 E-01 5.0E-03 $PAEl 8.9E-03 6.4E-05 i 1300-1315 7.1 E-01 4.9E-03 l$$321 8.7E-03 6.2E-05 l 1315-1330 6.7E-01 4.7E-03 R$Wd 8.3E-03 6.0E-05 i 1330-1345 6.4E-01 4.5E-03 iMM1 7.9E-03 5.7E-05

. 1345-1400 6.3E-04 4.4E-06 $$M1 7.8E-06 5.6E-08 1400-1415 As Read As Read 1%$j As Read As Read i

I 4

3

. O

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

l I

Rev0 Page 9.S.4 2 VERMONT YANKEE NUCLEAR POWER STATION

EMERGENCY PREPAREDNESS EXERCISE 1995 9.5.4 Plant Vent Sample Dose Rates i B. Air Sample (lodine Cartridge)

, Unshielded Shielded (1 inch lead)

(mR/hr per cc)* (mR/hr per cc)*

j Time Contact 1 ft Contact 1 ft j PRIOR TO 1210 As Read As Read fMend As Read As Read 1210-1215 1.7E-03 1.2 E-05 @MW 2.1 E-05 1.5E-07 1215-1230' 1.7E-02 1.2E-04 EIB41 2.1 E-04 1.5E-06 1230-1245 1.6E-02 1.1 E-04 RRd 2.0E-04 1.4E-06

, 1245-1300 1.5 E-02 1.1E 04 ERN 1.9E-04 1.3E-06 i 1300-1315 1.4E 02 1.0E-04 R$%M 1.8E-04 1.3E-06

{ 1315-1330 1.4E-02 9.5E-05 BBM 1.7E-04 1.2E-06

! 1330-1345 1.3E-02 9.0E-05 B4M 1.6E-04 1.1 E-06 1345-1400 1.2E-05 8.5E-08 Bifing 1.5E-07 1.1 E-09 s 1400-1415 As Read As Read liMW41 As Read As Read I 4

i i

4 l

i l l

.O l

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

i l

Revo Page 9.5.4-3 i l

'O' VERMONT YANKEE NUCLEAR POWER STATION i

i EMERGENCY PREPAREDNESS EXERCISE l 1995  !

l 9.5.4 Plant vent Stack Sample Dose Rates C. General Area Exposure Rates at Stack (mr/hr) 4 Time At Stack Door inside PRIOR TO 1210 As Read

• 6%%Wi#d As Read

• j 1210-1215 40 EM!iMi 120  ;

1215-1230 400 Gi$6ia 1200 1230-1245 360 REend 1100 i 1245-1300 330 R$$$3 1000 1300-1315 330 isif#sd 1000 1315-1330 300 RE##WX 920 I

1330-1345 280 lMs5El 840

1345-1400 0.3 R E Sd 0.8

1400-1415 As Read

• 14$5H As Read

• I l

i 4

4 i

i O

• Background as read on survey meter.

l I

R2v 0 l

Page 9.61 VERMONT YANKEE NUCLEAR POWER STATION  !

EMERGENCY PREPAREDNESS EXERCISE i 1995 l j

9.6 PLANT VENT STACK DATA  :

l

A. Plant Vent Stack Activity Concentrations (uCi/cc)*

i Isotope PRIOR TO 1210 1210-1215 1215-1230 1230-1245 l-131 3.3E-13 3. . N 3.8E-03 3.7E 03 j I-132 4.8E-13 3.4t::-J.4 3.4E-03 3.1 E-03 l 1-133 7.5E-13 6.8E 04 6.8E-03 6.8E-03 i

J 1-134 6.6E-13 2.2E-04 2.2E-03 1.8E-03 1-135 6.3E-13 5.9E-04 5.9E-03 5.6E-03 Total lodine 2.9E-12 2.2E-03 2.2E-02 2.1 E-02

]

l-131 D.E. 6.1 E-13 6.3E-04 6.3E-03 6.2E-03 1 1

I

. Kr-83m 6.6E-03 6.6E-02 6.2E-02

$[

Kr-85m Kr-85 1.4 E-02 8.2E-04 1.4 E-01 8.2E-03 1.3 E-01 8.2E-03 l Kr-87 1.4E-02 1.4E-01 1.2E-01 l

" l Kr-88 3.1 E-02 3.1 E-01 2.9E-01 Xe-131m 4.8E-04 4.8 E-03 4.7E-03 j Xe-133m 4.4E-03 4.4E-02 4.3E-02 i Xe-133 1.5E-01 1.5E+00 1.5E+00 I Xe-135m 8.2 E-03 8.2E-02 7.5E-02 Xe-135 4.1 E-02 4.1 E-01 4.1 E-01

Xe-138 1.0E-03 1.0E-02 4.7E-03 Total Gas 2.7E-01 2.7E+00 2.6E+00 1

4 I

4 l

I

• To convert concentration (uCi/cc) to release rate (uCl/sec) multiply by 2 the assumed stack flow rate of 4.1E+07 cc/sec.

• • Indicates activity concentration below MDL.

For plant vent stack sample dose rates see Section 9.5.4.

I I

4 Rav 0 Page 9.6 2 f

VERMONT YANKEE NUCLEAR POWER STATION

. EMERGENCY PREPAREDNESS EXERCISE 1995  ;

l 9.6 PLANT VENT STACK DATA j A. Plant Vent Stack Activity Concentrations (uCi/cc)* i l

j isotope 1245-1300 1300 1315 1315-1330 1330-1345 l-131 3.6E-03 3.5E-03 3.4E-03 3.3E 03  ;

4 l i32 2.7E-03 2.5E-03 2.3 E-03 2.1 E-03 I i 1-133 6.7E-03 6.5E-03 6.3E-03 6.0E-03 )

j 1-134 1,4E-03 1.2E-03 8.9E-04 7.5E-04 i 1-135 5.3E-03 5.1 E-03 4.8E-03 4.6E-03 4 Total lodine 2.0E-02 1.9E-02 1.8E-02 1.7E-02 1131 D.E. 5.9E-03 5.8E-03 5.6E-03 5.4E-03 l

\

I Kr-83m 6.0E 02 5.6E-02 5.3E-02 5.0E-02 i Kr-85m 1.2E-01 1.2E-01 1.1 E-01 1.0E-01 f Kr-85 8.2E-03 8.2E-03 7.5E-03 7.5E-03 Kr-87 9.6E-02 8.2E-02 6.8E-02 6.0E-02 1

, Kr 88 2.6E-01 2.4E-01 2.2E-01 2.0E-01 i Xe-131m 4.7E-03 4.5E 03 4.4E-03 4.3E-03 i l

Xe-133m 4.2E-02 4.1 E-02 4.0E-02 3.9E-02

, Xe-133 1.4E+00 1.4E+00 1.4E+00 1.3E+00 4

Xe-135m 7.5E 02 7.5E 02 6.8 E-02 6.8E-02 I

Xe-135 4.2E-01 4.2E-01 4.2E-01 4.2E-01 4 Xe-138 2.2E 03 1.0E-03 4.9E-04 2.3E-04  :

! Total Gas 2.5E+00 2.5E+00 2.4E+00 2.3E+00 I

i 4

l

• To convert concentration (uCl/cc) to release rate (uCl/sec) multiply by the assumed stack flow rate of 4.1E+07 cc/sec.

• • Indicates activity concentration below MDL.

For plant vent stack sample dose rates see Section 9.5.4.

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

Rev0

. Page 9.6-3 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 9.6 PLANT VENT STACK DATA A. Plant Vent Stack Activity Concentrations (uCi/cc)*

lsotope 1345-1400 1400-1415 l-131 3.2E-06 1.7E-12 1-132 1.8E-06 2.4E-12 1-133 5.8E-06 3.8E 12 1-134 5.8E-07 3.3E-12 1-135 4.3E-06 3.2E-12 Totallodine 1.6E-05 1.4E-11 1-131 D.E. 5.2E-06 3.1 E-12 Kr-83m 4.7E-05 O Kr 85m Kr-85 9.6E-05 7.5E-06 Kr-87 5.1 E-05 Kr-88 1.8E-04 Xe-131m 4.2E 06 Xe-133m 3.8E 05 Xe-133 1.3E-03 Xe-135m 6.6E 05 I Xe-135 4.2E 04 Xe 138 1.0E 07 ]

Total Gas 2.2E-03 l

l l

l l

l l

• To convert concentration (uCl/cc) to release rate (uC1/sec) multiply by the assumed stack flow rate of 4.1E+07 cc/sec.

j

" Indicates activity concentration below MDL.

For plant vent stack sample dose rates see Section 9.5.4.

l

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . . . - . . . - _ . .. . . _ - . .l

Rev. 1 Page 9.7-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 M FIELD MONITORING MAPS AND DATA Plume gamma dose rates and radioiodine concentrations have been estimated as a function of time and distance from the plant site using a variable trajectory dose assessment model (METPAC). Geographical representations of the plume are provided in this section for each 15 minute average of the meteorological conditions, starting at clock time 1210 (scenario time 4:10). During the exercise, Controllers will use the information contained in this section to provide field monitoring teams with the appropriate survey results and radiological data for various times and locations.  ;

The designated field monitoring teams will be directed to monitor and track the plume relative to the meteorological conditions postulated for

( the scenario. Figures 9.7-1 through 9.7-11 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, 4 State of Vermont, State of New Hampshire and commonwealth of Massachusetts

field monitoring teams. The tables contained the radiological data to be provided to the field monitoring teams for various times and locations.

! (The tables follow the figure for a given scenario time period.)

l Radiological data on the tables have been provided for each plume segment j 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.

v

Rev. 1

,o Page 9.7-2

'\

Prior to the exercise, training will be provided to controllers on the use of the figures and tables. The controllers should use the following specific instructions:

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, uaist 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 Attempt to provide values that reflect the team's accrued

) utilized.

exposure and range of the pocket dosimeter. f

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, l issue them an "off-scale low" value and "off-scale high" value, respectively.

5. For gamma (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 epm. ]

+

[3 t

\v/

1 1

T Rev. 1 a

D Page 9.7-3

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 and 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.

a 4 6. For air sample measurements taken by field monitoring teams, the following information should be use:

j a. The field monitoring teams will substitute a charcoal cartridge instead of the absorber media crrtridge (silver zeolite) j contained in the field monitoring kits. All air sample data will be given as though the absorber media cartridges (silver zeolite)

were being used in the kits.

1

)

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 and 10-cubic foot (283 liters) for Vermont Yankee; 354 liters for State of Vermont; and  ;

20-cubic foot (566 liters) for State of New Hampshire and 3

Massachusetts field monitoring teams. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally.

i

c. Air sample not count rates for the adsorber media cartridges (silver zeolite) provided in the field data tables have been developed using HETPAC thyroid dose rate projections. The i

formula'used is as follows:

ConcI-131 ( uCi/cc) , neccWonve onFactor ExFx T l

l where E= Instrument Detector Efficiency in epm /dpm (counts per

. disintegration)

F= Flow rate of sample in Ipm or efm T= Sample collection time in minutes CF = Conversion Factor (4.5 E-10 pCi-liter /dpm-cc for flow J

rate in Ipm 93 1.6 E-11 CI-ft 3 /dpm-cc for flow rate in efm

i Rev. 1

/ Page 9.7-4

{ '

l

d. For air sample not count rate for the particulate filter paper,  ;

1 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.

NOTE: THE PLUME PLOT FIGURES ARE GRAPHIC REPRESENTATIVES OF ATMOSPHERIC DISPERSION. LARGER FIGURES WILL BE AVAILABLE TO SITE AND OFF-SITE MONITORING CONTROLLERS FOR THEIR USE ON PROVIDING DATA TO FIELD MONITORING TEAMS.

C

()'

4 1

l PAGE 9.7-5 p -

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TABLE 9.7.1 RIv.1 Ptg3 9.7-52 ON SITE VERMONT YANKEE FIELD DATA p-)

? GAMMA DOSE RATE AIR SAMPLE DATA * (RM 14)"

MONROE RADECO PARTICULATE V CONC. 100 L 10 CF FILTER"*

CLOCK MAP PIC-6 AM 14 l131 SILVER ZEOLITE TIME AREA (mR/hr) (CPM 1 uCi/cc (NET CPM) (NET CPM) (NET CPM) 1210 1215 SLUE 8 29260 0.00E+00 <40 <40 <40 YELLOW <1 AS READ 0.00E+00 <40 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 <40 121S 1230 BLUE 83 OSH 0.00E+00 <40 <40 <40 YELLOW 8 29050 0.00E+00 <40 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 <40 1230-1245 BLUE 76 OSH 0.00E+00 <40 <40 <40 YELLOW 8 26740 0.00E +00 <40 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 <40 l 1245-1300 BLUE 68 OSH 0.00E+00 <40 <40 <40 YELLOW 7 23730 0.00E+00 <40 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 <40 1300 1315 BLUE 63 OSH 0.00E+00 <40 <40 <40 YELLOW 6 21945 0.00E+00 <40 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 <40 1315-1330 BLUE 57 OSH 0.00E+00 <40 <40 <40 YELLOW 6 20090 0.00E+00 <40 <40 <40 GREEN <1 AS READ 0.00E+00 <40 <40 <40

-1345 BLUE 54 OSH 0.00E+00 <40 <40 <40 YELLOW 5 18760 0.00E+00 <40 <40 <40

GREEN <1 1876 0.00E+00 <40 <40 <40

(

J NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

< \ " The RM-14 detector efficiency for 1-131 was assumed to be 0.025 cpm /dpm with the silver Zeolite cartridge.

• " The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample.

l ,  ;

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%. CLOCK TIME: 1210 to 1215

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l TABLE 9.7.2a R:v.1 Page 9.7-63 VERMONT YANKEE FIELD DATA AT CLOCK TIME 12101215 (SCENARIO TIME 0410-0415)

. AIR SAMPLE DATA * (RM 14)" i GAMMA DOSE RATE MONROE RADECO PARTICULATE l FILTER"* I PLUME CONC. 100 L 10 CF SEGMENT OISTANCE MAP PIC-6 RM-14 1131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) l 1.00 SITE BLUE 11 38850 4.03E 11 <40 <40 <40 BOUNDARY YELLOW 1 3885 4.03E 12 <40 <40 <40 GREEN <1 389 4.03E 13 <40 <40 <40 2.00 0.60 BLUE 11 39550 1.04E-10 <40 <40 <40 YELLOW 1 3955 1.04E 11 <40 <40 <40 GREEN <1 396 1.04E 12 <40 <40 <40 1

v l

1 l

I NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler i and 10 cubic feet for the Radeco sampler, if different volumes are collected, the air I sample data provided in the tables should be adjusted proportionally. For example,  !

if a 50 liter sample was collected instead of 100 liters, divide the value given in the )

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V " The RM 14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the ,

sdver zeolite cartridge. )

l

"* The particulate filter sample count rate (cpm) was estimated from the I-131 air j concentration for a 100 liter sample, i l

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TABLE 9.7.3a Rev.1 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1215-1230 (SCENARIO TIME 0415-0430) l 1

j AIR SAMPLE DATA * (RM 14)"

U GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER *"

SEGMENT DISTANCE MAP PIC-6 RM 14 1131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) uCl/cc (NET CPM) (NET CPM) (NET CPM) 1.00 SITE BLUE 110 OSH 4.30E 10 <40 <40 <40 BOUNDARY YELLOW 11 38500 4.30E 11 <40 <40 <40 GREEN 1 3850 4.30E 12 <40 <40 <40 2.00 0.80 BLUE 129 OSH 3.98E 08 223 620 80 YELLOW 13 45150 3.98E 09 <40 32 <40 GREEN 1 4515 3.98E-10 <40 <40 <40 3.00 1.50 BLUE 172 OSH 6.17E-07 3457 9630 1235 YELLOW 17 OSH 6.17E-08 346 963 123 GREEN 2 6020 6.17E49 <40 96 <40 4.00 2.00 BLUE 16 OSH 8.08E-08 452 1260 162 YELLOW 2 5740 8.08E 09 45 126 <40 GREEN <1 574 8.08E 10 <40 <40 <40 O

V 1

i i

NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

(_./ " The RM 14 detector efficiency for 1131 was assumed to be 0.025 cpm /dpm with the silver teolite cartridge.

'" The particulate filter sample count rate (cpm) was estimated from the 1 131 air concentration for a 100 liter sample.

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l TABLE 9.7.4:n Rsv.1 Page 9.7-8a VERMONT YANKEE FIELD DATA AT CLOCK TIME 12301245 (SCENARIO TIME 043v-0445)

,R

(

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) AIR SAMPLE DATA * (RM 14)"

GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER"*

SEGMENT DISTANCE MAP PIC-6 RM 14 l131 SILVER ZEOLITE NO. (MILES) AREA ImR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) 1.03 SITE BLUE 101 OSH 4.47E-10 <40 <40 <40 BOUNDARY YELLOW 10 35350 4.47E 11 <40 <40 <40 GREEN 1 3535 4.47E 12 <40 <40 <40 2.00 0.80 BLUE 119 CSH 4.32E 08 242 674 86 YELLOW 12 41650 4.32E 09 <40 67 <40 GREEN 1 4165 4.32E 10 <40 <40 <40 3.00 1.50 BLUE 149 OSH 5.14E 07 2879 8019 1028 YELLOW 15 OSH 5.14E 08 2e8 802 103 GREEN 1 5215 5.14E-09 <40 80 <40 4.00 2.30 BLUE 140 OSH 6.87E-07 3845 10710 1373 YELLOW 14 49000 6.87E-08 384 1071 137 GREEN 1 4900 6.87E-09 <40 107 <40 5.00 3.10 BLUE 112 OSH 5.94E-07 3328 9270 1188 YELLOW 11 39200 5.94E 08 333 927 119 GREEN 1 3920 5.94E-09 <40 93 <40 6.00 3.60 BLUE 9 29855 3.89E-08 218 608 78 f YELLOW <1 2986 3.89E-09 <40 61 <40

( GREEN <1 299 3.89E-10 <40 <40 <40 )

NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and 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 cilver zeolite cartridge.

"* The particulate fitter sample count rate (com) was estimated from the 1 131 air concentration for a 100 liter sample, l

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TABLE 9.7.52 R:v.1 Pag] 9.7 93 VERMONT YANKEE FIELD DATA AT CLOCK TIME 1245-1300 (SCENARIO TIME 0445-0500) b AIR SAMPLE DATA * (RM 14)"

O GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER"*

SEGMENT DISTANCE MAP PIC-6 RM 14 l131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) uCl/cc (NET CPM) (NET CPM) (NET CPM) 1.00 SITE BLUE 90 OSH 4.88E 10 <40 <40 <40 BOUNDARY YELLOW 9 31570 4.88E-11 <40 <40 <40 GREEN <1 3157 4.88E 12 <40 <40 <40 2.00 0.80 BLUE 107 OSH 5.09E 08 285 794 102 YELLOW 11 37450 5.09E-09 <40 79 <40 GREEN 1 3745 5.09E 10 <40 <40 <40 3.00 1.60 BLUE 132 OSH 4.98E-07 2791 7776 997 YELLOW 13 46200 4.98E-08 279 778 100 GREEN 1 4620 4.98E-09 <40 78 <40 4 00 2.40 BLUE 127 OSH 6.40E-07 3586 9990 1281 YELLOW 13 44450 6.40E-08 359 999 128 GREEN 1 4445 6.40E 09 <40 100 <40 5.00 3.10 BLUE 101 OSH 5.48 E-07 3066 8541 1095 YELLOW 10 35350 5.48E-08 307 854 110 GREEN 1 3535 5.48E-09 <40 85 <40 6.00 3.90 BLUE 75 OSH 3.41 E-07 1909 5319 682 YELLOW 8 26355 3.41 E-08 191 532 68 lO GREEN <1 2630 3.41 E-09 <40 53 <40 lV 7.00 4.70 BLUE 63 OSH 2.98E-07 1670 4653 597 YELLOW 6 22120 2.98E-08 167 465 60 GREEN <1 2212 2.98E-09 <40 <40 <40 8.00 5.20 BLUE 5 18620 2.28E-08 128 356 46 YELLOW <1 1862 2.28E-09 <40 <40 <40 GREEN <1 186 2.28E 10 <40 <40 <40 NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

(

( " The RM 14 detector efficiency for 1131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge.

'" The particulate filter sample count rate (cpm) was estimated from the 1 131 air concentration for a 100 liter sample.

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TABLE 9.7.62 Rev.1 Pagi 9.710a VERMONT YANKEE FIELD OATA AT CLOCK TIME 1300-1315 (SCENARIO TIME 0500-0515) b AIR SAMPLE DATA * (RM 14)"

(V PLUME GAMMA DOSE RATE CONC.

MONROE RADECO 100 L 10 CF PARTICULATE FILTER"'

SEGMENT OlSTANCE MAP PIC-6 RM 14 l131 SILVER ZEOLITE NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) 1.00 SITE BLUE 84 OSH 5.00E-10 <40 <40 <40 BOUNDARY YELLOW 8 29225 5.00E-11 <40 <40 <40 GREEN <1 2923 5.00E 12 <40 <40 <40 2.00 0.80 BLUE 99 OSH 5.39E-08 302 841 108 YELLOW 10 34650 5.39E 09 <40 84 <40 GREEN <1 3465 5.39E 10 <40 <40 <40 3.00 1.60 BLUE 122 OSH 4.77E-07 2672 7443 954 YELLOW 12 42700 4.77E-08 267 744 95 GREEN 1 4270 4.77E-09 <40 74 <40 4.00 2.40 BLUE 112 OSH 5.94E-07 3328 9270 1188 YELLOW 11 39200 5.94E-08 333 927 119 GREEN 1 3920 5.94E-09 <40 93 <40 1

5.00 3.20 BLUE 89 OSH 5.03E 07 2817 7848 1006 YELLOW 9 31010 5.03E-08 282 785 101

<40

]

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9.00 6.30 BLUE 42 OSH 1.82E-07 1018 2835 363 i YELLOW 4 14595 1.82E-08 102 284 <40 (

GREEN <1 1460 1.82E-09 <40 <40 <40 10.00 8.80 BLUE 4 12985 1.50E-08 84 234 <40 YELLOW <1 1299 1.50E 09 <40 <40 <40 GREEN <1 130 1.50E 10 <40 <40 <40 NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and to cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionalty. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

O d " The RM 14 detector efficiency for 1 131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge.

"* The particulate filter sample count rate (cpm) was estimated from the I 131 air concentration for a 100 liter sample.

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i TABLE 9.7.b1 R:v.1 Paga 9.7-1181 VERMONT YANKEE FIELO DATA AT CLOCK TIME 13151330 (6CEieRIO TIME C515-0530) l AIR SAMPLE DATA'(RM 14)"

GAMMA DOSE RATE MONROE RADECO PARTICULATE OPLUMESEGMENT OtSTANCE MAP PIC-6 RM 14 CONC.

1131 100 L 10 CF SILVER ZEOUTE FILTER"*

NO. IMILES) AREA ImR/hr) ICPM) uCi/cc (NET CPM) INET CPM) (NET CPM) 1.00 SITE BLUE 77 OSH 5.11E 10 <40 <40 <40 BOUNDARY YELLOW 8 26810 5.11E 11 <40 <40 <40 GREEN <1 2681 5.11E 12 <40 <40 <40 2.00 0.80 BLUE 91 OSH 5.67E-08 317 884 113 I YELLOW 9 31885 5.67E 09 <40 88 <40 GREEN <t 3189 5.67E 10 <40 <40 <40 3.00 1.60 BLUE 112 OSH 4.59E-07 2568 7155 917 i l

YELLOW 11 39200 4.59E-08 257 716 92

, GREEN 1 3920 4.59E 09 <40 72 <40 l 4.00 2.50 BLUE 103 OSH 5.59E 07 3131 8721 1118 i

YELLOW 10 36050 5.59E 08 313 872 112 GREEN 1 3605 5.59E-09 <40 87 <40 5.00 3.30 BLUE 81 OSH 4.67E-07 2614 7281 933 YELLOW 8 28315 4.67E 08 261 728 93 GREEN <1 2832 4.67E-09 <40 73 <40

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, 7.00 4.90 BLUE 50 OSH 2.58E-07 1447 4032 517 YELLOW 5 17640 2.58E 08 145 403 52 ;

GREEN <1 1764 2.58E-09 <40 <40 <40 8.00 5.60 BLUE 43 OSH 1.92E 07 1076 2997 384 YELLOW 4 15120 1.92E 08 108 300 <40 GREEN <1 1512 1.92E-09 <40 <40 <40 9.00 6.40 BLUE 38 OSH 1.71E 07 960 2673 343 YELLOW 4 13265 1.71 E 08 96 267 <40 GREEN <1 1327 1.71 E-09 <40 <40 <40 10.00 7.20 BLUE 34 OSH 1.37E 07 766 2133 273 YELLOW 3 11760 1.37E-08 77 213 <40 GREEN <1 1176 1.37E49 <40 <40 <40 11.00 7.90 BLUE 30 OSH 1.23 E-07 688 1917 246 l

YELLOW 3 10500 1.23E-08 69 192 <40 GREEN <1 1050 1.23E-09 <40 <40 <40 i

NOTES:

i

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and 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 C silver Zeolite cartridge.

'" The particulate filter sample count rate (cpm) was estimated from the 1 131 air concentration for a 100 liter sample.

TABLE 9.7.7a2 R:v.1 Paga 9.711a2 VERMONT YANKEE FIELO DATA AT CLOCK TIME 13151330 (SCENARIO TIME 0515 0530)

AIR SAMPLE DATA * (RM 14)"

GAMMA DOSE 9 ATE MONROE RADECO PARDCULATE PLUME CONC. 100 L 10 CF FILTER"-

SEGMENT OISTANCE MAP PIC-6 PM 14 1131 SILVER ZEOLITE NO. (MILES) AREA (m Rihr) ICPM) uCl/cc (NET CPM) (NET CPM) (NET CPM) 12.00 8.40 SLUE 3 9625 1.07E-08 60 167 <40 YELLOW <1 963 1.07EG <40 <40 <40 GREEN <1 96 1.07E 10 <40 <40 <40 1

1 0

4 1

4

NOTES

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler, if different volumes are collected, the air sample data provided in the tables riould be adjusted proportionally. For example, if a 50 Itter sample was collected irbtead of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

, " The RM-14 detector efficiency for 1 131 was assumed to be 0.023 epm /dpm with the silver zeolite cartridge.

• " The particulate filter sample count rate (cpm) was estfroated ' rom the 1 131 air concentration for a 100 liter sample,

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1 TABLE 9.7.8s1 Arv.1 Pag 3 9.7-12a1 VERMON7 YANKEE FIELO DATA AT CLOCK TIME 13301345 (SCENARIO TIME 0530-0545)

} AIR SAMPLE DATA'(RM 14)"

MONROE RADECO

/ GAMMA DOSE RATE PARTICULATE PLUME CONC. 100 L 10 CF FILTER"' l

, SEGMENT DISTANCE MAP PIC-6 RM 14 1131 SILVER ZEOLITE ,

NO. (MILES) AREA (mR/hrt (CPM) uCl/cc (NET CPM) (NET CPM) (NET CPM) '

1.00 SITE BLUE 71 OSH 4.68E 10 <40 <40 <40 BOUNDARY YELLOW 7 24990 4.68E 11 <40 <40 <40 GREEN <1 2499 4.68E 12 <40 <40 <40 2.00 0.80 BLUE 85 OSH 5.05E 08 283 788 101 YELLOW 8 29715 5.05E 09 <40 79 <40 GREEN <1 2972 5.05E 10 <40 <40 <40 l 3.00 1.60 BLUE 106 OSH 4.40E 07 2462 6858 879 YELLOW 11 37100 4.40E 08 246 686 88 CREEN 1 3710 4.40E 09 <40 69 <40 4.00 2.50 BLUE 96 OSH 5.38E 07 3014 8397 1077 YELLOW 10 33565 5.38E-08 301 840 # 108 GREEN <1 3357 5.38E-09 <40 84 <40 5.00 3.30 BLUE 75 OSH 4.46E 07 2497 6957 892

YELLOW 8 26390 4.46E-08 250 696 89 j 2

GREEN <1 2639 4.46E 09 <40 70 <40 l 6.00 4.10 BLUE 55 OSH 2.81E 07 1573 4383 562 YELLOW 6 19285 2.81E 08 157 438 56 GREEN <1 1929 2.81 E-09 <40 <40 <40 1,

7.00 4.90 BLUE 46 OSH 2.43E 07 1363 3798 487 YELLOW 5 16240 2.43E-08 136 380 49 GREEN <1 1624 2.43E-09 <40 <40 <40 l 8.00 5.70 BLUE 38 OSH 1.79E 07 1005 2799 359 YELLOW 4 13370 1.79E 08 100 280 <40 GREEN <1 1337 1.79E-09 <40 <40 <40 9.00 6.50 BLUE 34 OSH 1.60E-07 898 2502 321 YELLOW 3 11795 1.60E 08 90 250 <40 GREEN <1 1180 1.60E-09 <40 <40 <40 10.00 7.30 BLUE 31 OSH 1.30E 07 727 2025 260 YELLOW 3 10710 1.30E 08 73 203 <40

. GREEN <1 1071 1.30E 09 <40 <40 <40 d

11.00 8.00 BLUE 27 OSH 1.17E 07 656 1827 234 YELLOW 3 9590 1.17E 08 66 183 <40 GREEN <1 959 1.17E-09 <40 <40 <40

NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

l

( " The RM 14 detector efficiency for I 131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge.

'" The particulate filter sample count rate (cpm) was estimated from the 1 131 air concentration for a 100 liter sample.

TABLE 9.7.8a2 Rw.1 PagD 9.712a2 VERMONT YANKEE FIELO DATA AT CLOCK TIME 13301345 (SCENARIO TIME 0530-0545) f AIR SAMPLE DATA * (RM 14)"

GAMMA DOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER"'

SEGMENT OlSTANCE MAP PIC 6 RM 14 1131 SILVER ZEOLITE NO. IMILES) AREA (mR/hr) (CPM) uCl/cc (NET CPM) (NET CPM) (NET CPM) 12.00 8.80 BLUE 25 OSH 9.92E-08 556 1548 198 YELLOW 3 8355 9.92E-09 56 155 <40 GREEN <1 888 9.92E 10 <40 <40 <40 13.00 9.60 BLUE 23 OSH 8.94E 08 501 1395 179 YELLOW 2 8015 8.94E-09 50 140 <40 GREEN <1 802 8.94E 10 <40 <40 <40 14.00 10.10 BLUE 2 8225 8.02E-09 45 125 <40 YELLOW <1 823 8.02E-10 <40 <40 <40 ,

GREEN <1 82 8.02E 11 <40 <40 <40 O

V NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler, if different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

" The RM 14 detector efficiency for 1 131 was assumed to be 0.025 cpm /dpm with the

% silver zeolite cartridge.

• " The particulate filter sample count rate (cpm) was estimated from the 1 131 air concentration for a 100 liter sample.

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TABLE 9.7.9a1 RIv.1 Pags 9.71331 VERMONT YANKEE FIELO DATA AT CLOCK TIME 13451400 (SCENARIO TIME 0545-0600)

O PLUME GAMMA DOSE RATE AIR SAMPLE DATA * (RM-14)"

CONC.

MONROE RADECO 100 L 10 CF PARTICULATE FILTER *"

SEGMENT DISTANCE MAP PIC-6 RM 14 l131 SILVER ZEOUTE NO. IMILES) AReiA (mR/hr) (CPM) UCi/cc (NET CPM) (NET CPM) (NET CPM) 1.00 1.70 BLUE 106 OSH 4.491 07 2514 7002 898 YELLOW 11 37100 4.491. 08 251 700 90 GREEN 1 3710 4.4EE-09 <40 70 <40 2.00 2.50 8LUE 90 OSH 5.18E 07 2898 8073 1035 YELLOW 9 31500 5.18E-08 290 807 104 GREEN <1 3150 5.18E 09 <40 81 <40 3.00 3.30 BLUE 70 OSH 4.26E-07 2384 6642 852 YELLOW 7 24640 4.26E 08 238 664 85 GREEN <1 2464 4.26E 09 <40 66 <40 4.00 4.10 BLUE 50 OSH 2.65E-07 1486 4140 531 YELLOW 5 17605 2.65E 08 149 414 53 GREEN <1 1761 2.65E-09 <40 <40 <40 5.00 4.90 BLUE 43 OSH 2.29E-07 1283 3573 458 YELLOW 4 14875 2.29E 08 128 357 46 GREEN <1 1488 2.29E 09 <40 <40 <40 6.00 5.80 BLUE 35 OSH 1.69E 07 947 2637 338 i YELLOW 4 12285 1.69E-08 95 264 <40 l GREEN <1 1229 1.69E-09 <40 <40 <40 f O 7 .00 6.60 BLUE YELLOW 30 3

OSH 10640 1.49E-07 1.49E-08 837 84 2331 233 299

<40 1

l i

GREEN <1 1064 1.49E-09 <40 <40 <40 1

8.00 7.40 BLUE 27 OSH 1.21 E-07 675 1881 241 YELLOW 3 9415 1.21 E 08 68 188 <40 GREEN <1 942 1.21 E-09 <40 <40 <40 9.00 8.20 BLUE 24 OSH 1.09E-07 611 1701 218 YELLOW 2 8435 1.09E-08 61 170 <40 i GREEN <1 844 1.09E 09 <40 <40 <40 10.00 8.90 BLUE 23 OSH 9.35E-08 523 1458 187 YELLOW 2 8050 9.35E-09 52 146 <40 GREEN <1 805 9.35E 10 <40 <40 <40 f

11.00 9.70 BLUE 21 OSH 8.48E-08 475 1323 170 YELLOW 2 7315 8.48E-09 47 132 <40 GREEN <1 732 8.48E 10 <40 <40 <40 NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

l O

" The RM 14 detector efficiency for 1 131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge.

• " The particulate filter sample count rate (cpm) was estimated from the I 131 air concentration for a 100 liter sample.

TABLE 9.7.9a2 Rtv.1 Pag? 9.713:2 VERMONT YANKEE FIELO DATA AT CLOCK TIME 13451400 (SCENARIO TIME 0545 0600) p AIR SAMPLE DATA'(RM 14)"

(, GAMMA OOSE RATE MONROE RADECO PARTICULATE PLUME CONC. 100 L 10 CF FILTER"'

SEGMENT OlSTANCE MAP PIC 6 RM 14 1131 SILVER ZEOLITE NO. (MtLES) AREA (mR/hrt (CPM) uCl/cc (NET CPM) (NET CPM) (NET CPM) 12.00 10.50 BLUE 20 OSH 7.50E 08 420 1170 150 YELLOW 2 7035 7.50E-09 42 117 <40 ,

GREEN <40 <40 <40

<1 704 7.50E 10 i

l l

4 I

NOTES: .

I

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players, f

s

" The RM 14 detector efficiency for 1 131 was assumed to be 0.025 cpm /dpm with the silver Zeolite cartridge.

"* The particulate filter sample count rate (cpm) was estimated from the 1 131 air concentration for a 100 liter sample.

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TABLE 9.7.10a Rsv.1 Pags 9.7143 VERMONT YANKEE FIELD DATA AT CLOCK TIME 14001415 (SCENARIO TIME 0600-0615)  !

AIR SAMPLE DATA'(RM 14)"

(QALUME

/ GAMMA DOSE RATE CONC.

MONROE RADECO 100 L 10 CF PARTICULATE FILTER"'

SEGMENT DISTANCE MAP PIC 6 RM 14 l131 SILVER ZEOLITE NO. (MILES) AREA (mR/hrt (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) 1.00 3.40 BLUE 69 OSH 4.11E 07 2300 6408 822 YELLOW 7 23975 4.11 E-08 230 641 82 GREEN <1 2398 4.11 E-09 <40 64 <40 2.00 4.20 BLUE 47 OSH 2.53E 07 1418 3351 507 YELLOW 5 16345 2.53E 08 142 395 51 GREEN <1 1635 2.53E-09 <40 <40 <40 3.00 5.00 BLUE 39 OSH 2.17E 07 1215 3384 434 YELLOW 4 13580 2.17E-08 121 338 43 GREEN <1 1358 2.17E-09 <40 <40 <40 4.00 5.80 BLUE 32 OSH 1.58E-07 885 2466 316 YELLOW 3 11165 1.58E-08 89 247 <40 GREEN <1 1117 1.58E 09 <40 <40 <40 5.00 6.70 BLUE 28 OSH 1.40E-07 782 2178 279 YELLOW 3 9660 1.40E 08 78 218 <40 GREEN <1 966 1.40E-09 <40 <40 <40 6.00 7.50 BLUE 25 OSH 1.13E-07 630 1755 225 YELLOW 2 8575 1.13E-08 63 176 <40 GREEN <1 858 1.13E-09 <40 <40 <40 V 7.00 8.30 BLUE 22 OSH 1.01E 07 565 1575 202 YELLOW 2 7630 1.01 E-08 57 158 <40 GREEN <1 763 1.01E 09 <40 <40 <40 8.00 9.10 BLUE 20 OSH 8.65E 08 485 1350 173 YELLOW 2 7000 8.65E 09 48 135 <40 GREEN <1 700 8.65E 10 <40 <40 <40

9.00 9.90 BLUE 18 OSH 7.90E 08 443 1233 158 YELLOW 2 6405 7.90E 09 44 123 <40

GREEN <1 641 7.90E 10 <40 <40 <40 10.00 10.70 BLUE 18 OSH 7.04E 08 394 1098 141 YELLOW 2 6405 7.04E 09 <40 110 <40 GREEN <1 641 7.04E 10 <40 <40 <40 1

NOTES:

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampler. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead cf 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.

O " The RM 14 detector efficiency for 1131 was assumed to be 0.025 epm /dpm with the silver zeolite cartridge.

'" The particulate filter sample count rate (cpm) was estimated from the I 131 air concentration for a 100 liter semple.

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TABLE 9.7.11a R3v.1 Pagm 9.715s VERMONT YANKEE FIELD OATA AT CLOCK TIME 14151430 (SCENARIO TIME 0615-0630)

AIR SAMPLE DATA'(RM 14)"

) GAMMA DOSE RATE MONROE RADECO PARTICULATE N LUME CONC. 100 L 10 CF FILTER"'

SEGMENT OlSTANCE MAP PIC-6 RM 14 1131 SILVER ZEOLITE NO. IMILES) AREA ImR/hr) (CPM) uCl/cc INET CPM) INET CPM) (NET CPM) 1.00 5.20 BLUE 38 OSH 2.11E 07 1179 3285 421 YELLOW 4 13265 2.11 E-08 118 329 42 GREEN <1 1327 2.11E 09 <40 <40 <40 2.00 6.00 BLUE 30 OSH 1.51 E-07 846 2358 302 YELLOW 3 10395 1.51E 08 85 236 <40 GREEN <1 1040 1.51E 09 <40 <40 <40 3.00 6.80 BLUE 25 OSH 1.32E 07 740 2061 264 YELLOW 3 8890 1.32E-08 74 206 <40 GREEN <1 889 1.32E-09 <40 <40 <40 4.00 7.60 BLUE 22 OSH 1.06E 07 591 1647 211 YELLOW 2 7770 1.06E-08 59 165 <40 GREEN <1 777 1.06E 09 <40 <40 <40 5.00 8.40 BLUE 20 OSH 9.46E 08 530 1476 189 YELLOW 2 6930 9.46E-09 53 148 <40 GREEN <1 693 9.46E 10 <40 <40 <40 6.00 9.20 BLUE 18 OSH 8.08E 08 452 1260 162 YELLOW 2 6370 8.08E 09 45 126 <40 GREEN <1 637 8.08E 10 <40 <40 <40 O' 7.00 10.00 BLUE YELLOW 17 2

OSH 5950 7.33E 08 7.33E 09 410 41 1143 114 147

<40

)

GREEN <1 595 7.33E 10 <40 <40 <40 NOTES:

i

• Air sample data are based on a sample volume of 100 liters for the Monroe sampler and 10 cubic feet for the Radeco sampier. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the i

table by 2 (two) and provide the resulting value to the players.

" The RM 14 detector efficiency for 1 131 was assumed to be 0.025 cpm /dpm with the

{d s

sdver zeolite cartridge.

'" The particulate filter sample count rate (cpm) was estimated from the 1 131 air concentration for a 100 liter sample.

~

Rev. O O Page 101 1 h VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1995 10.1 ON-SITE METEOROLOGICAL DATA CLOCK UPPER UPPER UPPER LOWER LOWER LOWER RAIN LOWER SOLAR TIME SPEED DlR DELTAT SPEED DIR DELTAT INCHES TEMP RAD MPH DEGREES DEGF MPH DEGREES DEGF 1/4 HR DEGF LANGS (Note 1) (Note 2) 08.00 5.40E+00 2.80E+02 -4.00E-01 4.20E+00 2.69E+02 -3.20E-01 0.00E+00 5.00E+01 2.00E-01 08.15 5 30E+00 2.85E+02 -5.00E-01 4 00E+00 2.74E+02 -4.00E-01 0.00E+00 5.10E+01 2.50E-01 08 30 5.20E+00 2.87E+02 -4.00E-01 4.00E+00 2.76E+02 -3.20E-01 0 00E+00 5.30E+01 2.70E-01 08:45 5 20E+00 2.89E+02 -6 00E-01 4.00E+00 2.77E+02 -4 80E-01 0.00E+00 5.50E+01 3.00E-01 09 00 5.30E+00 2.90E+02 -8.00E-01 4.00E+00 2.78E+02 -8.40E-01 0.00E+00 560E+01 3.10E-01 09:15 5.10E+00 2.94 E+02 -9 00E-01 4 30E+00 2.82E+02 -7.20E-01 0 00E+00 5.60E+01 3.50E-01 09.30 5.10E+00 2.92E+02 1.00E+00 4.30E+00 2.80E+02 -8.00E-01 0.00E+00 5.80E+01 4.30E-01 09 45 5.20E+00 2.96E+02 -1.10E+00 4.30E+00 2.84E+02 -8.80E-01 0.00E+00 6.00E+01 4.80E-01 10.00 5.10E+00 3.00E+02 -1.20E+00 4.20E+00 2.88E+02 -9 60E-01 0.00E+00 6.20E+01 5.50E-01 10.15 5.20E+00 3 04E+02 1.20E+00 4.20E+00 2.92E+02 -9 60E-01 0.00E+00 6.30E+01 6.00E-01 10.30 5.30E+00 3.06E+02 1.20E+00 3.40E+00 2.94E+02 -9.60E-01 0.00E+00 6.40E+01 6.80E-01 10:45 5.40E+00 3 08E+02 -1.50E+00 3 00E+00 2.96E+02 1.20E+00 0.00E+00 6.50E+01 7. 50E-01 11:00 5.60E+00 3.10E+02 -1.50E+00 2.60E+00 2.95E+02 -1.20E+00 0.00E+00 6.53E+01 8.00E-01 11:15 5.60E+00 3 09E+02 -1.50E+00 3.00E+00 2.97E+02 -1.20E+00 0.00E+00 6. 54 E+01 7.50E-01 11:30 5.80E+00 3.11 E+02 -1.50E+00 4.00E+00 2.99E+02 1.20E+00 0.00E+00 6.58E+01 7.20E-01 11:45 5.80E+00 3.10E+02 -1.50E+00 5.00E+00 2.95E+02 1.20E+00 0.00E+00 6.60E+01 7.00E-01 12.00 6.00E+00 3.10E+02 -1.80E+00 4.00E+00 2.98E+02 -1.44E+00 0.00E+00 6.63E+01 7.20E-01 12:15 610E+00 3.10E+02 -1.80E+00 3.60E+00 2.91E+02 1.44E+00 0.00E+00 6.65E+01 7.10E-01 12:30 6.20E+00 3.12E+02 -1.80E+00 2.60E+00 3.00E+02 1.44E+00 0.00E+00 6.60E+01 7.00E-01 12:45 640E+00 3.13E+02 -1.80E+00 2.70E+00 2.97E+02 -1.44E+00 0.00E+00 6.70E+01 6 80E-01 13.00 6.50E+00 3.15E+02 -1.90E+00 2.60E+00 3.02E+02 -1.52E+00 0.00E+00 6.80E+01 7.10E-01 13:15 6.60E+00 3.15E+02 -1.90E+00 2.60E+00 2.99E+02 1.52E+00 0.00E+00 6.80E+01 7.20E-01 13:30 6.50E+00 3.15E+02 -1.90E+00 2.40E+00 2.99E+02 -1.52E+00 0.00E+00 6.76E+01 7.30E-01 13 45 6.70E+00 3 20E+02 -1.90E+00 2.70E+00 3 04E+02 -1.52E+00 0.00E+00 6.71E+01 7.10E-01 14.00 6.90E+00 3.20E+02 -1.90E+00 2.90E+00 3 04E+02 1.52E+00 0.00E+00 6.68E+01 7.00E-01 14:15 7.00E+00 3.20E+02 1.80E+00 2.80E+00 3.04E+02 1.44E+00 0.00E+00 6 65E+01 7.00E-01 14:30 7.20E+00 3 25E+02 -1.80E+00 2.70E+00 3.09E+02 1.44E+00 0.00E+00 6 63E+01 6.90E-01 14:45 7.50E+00 3.25E+02 1.70E+00 2.80E+00 3.09E+02 1.36E+00 0.00E+00 6.60E+01 6.80E-01 15.00 7.10E+00 3 27E+02 1.70E+00 2.60E+00 3.11 E+02 1.36E+00 0.00E+00 6.59E+01 6.60E-01 NOTES:

. The height differential for the upper delta temperature on the pnmary tower is 262 ft.

2. The height differential for the lower delta temperature on the primary tower is 165 ft l

Rev. 0 Page 10.2-1

('~

(

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 lb2 QENERAL AREA NWS FORECASTS (See Note) -

Synoosis (08:00)

An upper air trough will pass over the area midday, causing cloudy skies and a wind shift from the west to the northwest.

Valid (08:00-12:00)

Partly cloudy this morning. Temperatures rising from current SO's into the 60's. Westerly winds from 3 to 6 MPH becoming northwesterly around midday.

Valid (12:00-16:001 Mostly cloudy. Temperatures rising to the upper 60's. Northwesterly winds from 4 to 8 MPH.

Valid f16:00-23:001 j Partly cloudy. Low temperatures in the upper 40's. Winds light and

% variable.

PLANT / EOF WEATHER OBSERVATIONS (See Note) - Valid (08:00-17:00) 1 11m3 General Observations 08:00-11:00 Partly cloudy with light to moderate winds. l 11:00-14:00 Mostly cloudy with light to moderate winds.

l 14:00-17:00 Partly cloudy with light winds.

NOTE: GENERAL AREA NWS FORECASTS SHOULD BE PROVIDFD UPON REQUEST.

PLANT / EOF WEATHER OBSERVATIONS WILL BE POSTED AS APPROPRIATE.

(d l

_. . - - - - .- .. _ .~. . . ~ - _ . . - . . _. .-. -- . . - . . _ . . - - - . . . - .

Rev. 0 ->

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 10.2 VERMONT YANKEE SITE FORECAST To be orovided to the ESC Meteorolocist by the ESC Controller at 10:00.

WEATHER FORECAST FOR SITE: VY - VERNON Date of Forecast: 09-13-95 Time of Forecast 10:00 Current Site Meteorology (as of 10:00 ):

Sensor Wind Soeed Wind Direction Delta Tomoerature Steb. Class Precioitation Lower 4.2 MPH 288 DEG FROM 1.0 DEG F D 0.00 IN115 MIN Upper 5.1 MPH 300 DEG FROM 1.2 DEG F D Foreceet Site Meteorology:

Sensor Wind Speed Wind Direction Delta Temperature Stab. Class Precioitation h

1.2 DEG F D I 10:00- Lower 3.5 MPH 295 DEG FROM 12:00 0.00 IN/15 MIN )

Upper 5.5 MPH 305 DEG FROM 1.5 DEG F D 12:00- Lower 3.0 MPH 300 DEG FROM 1.4 DEG F C 14:00 0.00 IN/15 MIN Upper 6.5 MPH 320 DEG FROM 1.8 DEG F D 1 14:00- Lower 3.0 MPH 310 DEG FROM 1.3 DEG F D 16:00 0.00 IN/15 MIN Upper 7.0 MPH 325 DEG FROM 1.7 DEG F D National Weather Service Forecast for site regions i Partly cloudy with temperatures rising from the 50's to the upper 60's.

Light northerly winds becoming northwesterly midday.

Special Weather Statements:

None 1

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j

_. __ __- __ . _ _ _ _ _ _ . _ _ - . . . . _ , . ..._s. - . . _ , _ . . - . . , , _. - .,

Rev. O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1995 10.2 VERMONT YANKEE SITE FORECAST To be orovided to the ESC Meteorolocist by the ESC Controller at 12:00.

WEATHER FORECAST FOR SITE: VY - VERNON Date of Forecast: 09-13-95 Time of Forecast: 12:00 Current Site Meteorology (as of 12:00 ):

12.n,19I M Wind Direction Delta Tomooreture M Precipitation -

1222d fr.!A11 Lower 4.0 MPH 298 DEG FROM 1.4 DEG F C 0.00 IN/15 MIN Upper 6.0 MPH 310 DEG FROM 1.8 DEG F D Foreceet Site Meteorology:

O h larg2I Wind 121td Wind Direction Delta Temperature g fr.!A11 figgjgijggg,rj 12:00- Lower 3.0 MPH 300 DEG FROM 1.4 DEG F C  !

14:00 0.00 IN/15 MIN Upper 6.5 MPH 320 DEG FROM 1.8 DEG F 0 ,

i 14:00- Lower 3.0 MPH 310 DEG FROM 1.3 DEG F D ,

16:00 0.00 IN/15 MIN 1 Upper 7.0 MPH 325 DEG FROM 1.7 DEG F D 4

16:00- Lower 2.0 MPH 315 DEG FROM -0.5 DEG F D ,

18:00 0.00 IN/15 MIN i Upper 5.5 MPH 330 DEG FROM 1.1 DEG F D l 1

1 National Weather Service Forecast for site regions i i Mostly cloudy with temperatures rising into the upper 60's. Light northerly  ;

i winds becoming northwesterly midday.

Special Weather Statements:

i None I

- I

'4 i