ML20115F614

Forwards Vermont Yankee Emergency Response Preparedness Exercise,1992,Exercise Manual. Manual Contains Info Re Performance of Exercise Schedule for 920902

ML20115F614
Person / Time
Site:	Vermont Yankee
Issue date:	07/03/1992
From:	Tremblay L VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BVY-92-73, NUDOCS 9210230152
Download: ML20115F614 (2)

Text

y VERMONT YANKEE .

}

NUCLEAR POWER CORPORATION-

Ferry Road. Brattleboro VT 05301-7002

. - 3[y ) .

((y'g)

ENGINEERING OFFICE '

38o uw smn

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- coaow omo (5093779,671.1 4

i July 3,1992 BVY 92-73 ,

- Umted States Nuclear Regulatory Commission .

ATTN: Document Control Desk Washington, DC 20555

References:

a.- License No. DPR-28 (Docket No. 50-271)-

b. ' Letter, VYNPC to USNRC, BVY 92-69, "1992 Vermont Yankee Emergency Exercise Objectives", dated June 4,~ 1992.=

Subject:

1992 Vermont Yankee Emergency Exercise Scenario

Dear Sir:

Enclosed please find a copy of the 1992 Vermont Yankee Nuclear Power Station Emergency Response Exercise Manual. The exercise scenario package includes allinformation pertinent to ,

performance of the subject exercise, scheduled for Wednesday, September 2,' 1992.

Two copies of the enclosure are being provided directly to Mr. E.C. McCabe of the USNRC Region 1 Staff. Copies of the enclosure are not being provided to the USNRC Resident Inspector at Vermo". Yankee, as we understand it is USNRC's intent to allow the Resident Inspector the -

opportun. y to participate ir, the exercise.

The success of the exercise is highly dependent on the confidentiality of our exercise scenario. Therefore, we are requesting that this letter and enclosure be treated on a "need-to-know" basis and be . withheld from public disclosure in accordance with 10 CFR 2.790,'until the exercise has been completed.

210005

. I EllPIOLD ENCLOSURE FROM PUBLIC DISCLOSURE y 9210230152 920703 . '

isDR ADDCK 05000271: l' F PDR '

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VERMONT YANKEE NUCLEAR POWER CORPORATION Y United States Nuclear Regulatory Commission July 3,1992 Page 2

• Any questions or comments concerning the 1992 Vermont Yankee Annual Emergency

[ Preparedness Exercise should be addressed to Mr. Edward C. Porter. Vermont Yankee Nuclear - '

l. Power Corporation, P.O. Box 169, Ferry Road, Brattleboro, Vermont 05301. Mr. Porter can be

' reached e (802) 257 - 5271, Extension 363, i

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l Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION i D l 0MOV\ ] dN ,

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( Leonard A. Tremblay, Jr.

' Senior Licensing Engineer i

j. Enclosure - Withhold from Public Disclosure cc: USNRC Resident Inspector - VYNPS - (without Enclosure) l

] USNRC Project Manager V YNPS (without Enclosure)

{ Mr. E.C. McCabe, Chief (with 2 Copics of Enclosure)

Emergency Preparedness Section

! United States Nuclear Regulaton Commission i Region I

! 475 Allendale Road

[

King of Prussio, PA 19406-

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i WITHHC LD ENCLOSURE FROM PUBLIC DISCLOSURE a

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VERMONT YANKr,E NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 i

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Section Title Ety.

1.0 INTRODUCTION

, 1.1 Exercise Schedule 0

-1.2 Participating Centers / Agencies 0 1.3 Abbreviat. sns and Definitions 0 1.4 References 0 2.0 EXERCISE OhjECTIVES AND EXTENT OF PLAY 0 3.0 EXERCIPE CUI,DILINES AND SCOPE 3.1 Exercise Guidelines 0 3.2 Player Instructions and Ground Rules 0 3.3 Procedure Execution List 0 4.0 CONTROLLER AND OBSERVER INFOPyATION-4.1 Controller and Observer ' Assignments 0 4,2 ' Controller - and Obserar Exercise Guidance 0 4.3 Controller and Observer Evaluation Criteria- 0 l

5.0 EXERCISE SCFNARIO

, 5.1 T 'tial Conditions -0.

l 5.2 stive Summary 0 5.3 -

. ario Timeline 0 5.4 Ds iled Sequence of Events 0 j 6.0 EXERCISE MESSAGES i

6.1 Command Cards 0.

6.2 Message-Cards 0 7.0 STATION EVENT DAIA 7.1 Events Summary. _

01 7.2- E: at Mini scenarios ~0 i

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Rev. 0 VERHONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 I I4BLE OF CONTENTS

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Sectica Title Rt,y 8.0 QPERATIONAL 3ATA 0 9.0 PADIOLOGICAL DATA 0 i

9.1 Area Radiation Monitors 0

• 9.2 Process Monitors 0 9.3 In. Plant Radiation Levels 0 9.4 Plant Chemistry Data 0 9.5 Radiological Sample Dose Rates 0 9.6  : Plant Vent. Stack Release Data 0 10.0 METEOROLOGICAL DATA 10.1 On Site Meteorological Data 0 10.2 Ceneral Area INS Forecasts 0

-10.3 INS Surface Maps 0-b i

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,, 1992 l 8 1 .

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} 1.1 EXERCISE SCHEDEI, t i A. Controller and Observer Briefinc

. Date: September 1, 1992 Time: 9:30 a.m. '

) Location: Vermont Yankee Corporate Office, Brattleboro, Vermont i

Purpose:

Briefing on Exercise Activities and Assignments

Attendees

Vermont Yankee and Yankee Atom'.R Controllers and Observers 1 B. Controller and Observer Plant Tour i 3

Date: September 1, 1992 Time: As necessary (contact Lead Controller)

Location: Emergency Response Facilitien and Affected In-Station Areas

Purpose:

Tamiliarize Controllers and Observers with Affected Areas Attendees: Vermont Yankee and Yankee Atomic Controllers and Observers C. NRC Entrance and Exercise Briefine Date: September 1, 1992 '

Time: 2:00 p.m.

Location: Vermont Yankee Corporate Of fice, Brattleboro, Vermont

Purpose:

NRC Briefing and Review of Exercise Scenario Attendees: NRC Evaluators

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Date

- September 2, 1992 3 Time: To Be Announced

, Location: Vermont Yankee Emergency Response Centers and Designated r Portions of States' Emergency Response. Centers (as

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necessary) 4

Purpose:

Emergency Response Preparedness Exercise Attendees: Vermont _ Yankee- Emergency Response Organization, NRC Evaluators and Yankee . Atomic = Engineering Support - Center Staff i

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i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 i 1,1 EXERCISE SCHEPULE (continued)

E, Exercise Debriefinr.

Date: Day of Exercise .

To be announced during . or immediately following the Time: '

-exercise '

Location: To be determined ' by the respective Emergency Response l Tacility controller

Purpose:

Debrief Players, Observers and' Controllers '

Attendees: Controllers, observers and Key Participants F. Controller Debriefing i Date: After Exercise Debriefing Time: To be announced Location: To be announced

Purpose:

Exercise Debriefing

, Attendeer: Exercise Coordinator and Controllers i

G. Exercise Criticue

Date

September'3, 1992 ,

Time

12:30 p.m.

Location: - Vermont Yankee Corporate Office, Brattleboro, Vermont

Purpose:

Utility Self-Critique /NRC Preliminary Findinge. ,

Attendees: Vermont Yankee Management, NRC _ Evaluators, Exercise

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• Controllers (Observers as needed) and Vermont Yankee Key Participants 4

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1992 i

1.2 PARTICIPATING. CENTER $/ACENCIES VFPJiONT YA' WEE NUCLEAR POWER CORPOPATION  !

Vermont Yankee Nuclear Power Station:

• Control Room (r.otification and communications functions only)

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

• Operations Support Center (1st floor of Ad:ninistration Building)

• Energy Information Center (Covernor ,t House)

Verniont Yankee Training Center:

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

• Emergency Operations Pacility/ Recovery Center (1st floor of Training Building)

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

YANMEE ATOMIC ELECTRIC COMPAh"I Yankee Atomic Corporate Headquarters (Bolton, Massachusetts):

• Engineering Support Center i

Rev. 0 Page 1.2-2 STATE OF VERMONT (Limited Participation - Practical Training)

Vermont Emergency Management Agency:

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• Emergency Operations Facility / Recovery Center (State representatives located in the State Room)

• Emergency Operations Center (Waterbury, Vermont)

STATE OF NEW HAMPSHIRE (Limited Participation - Practical Training)

New llampshire Offico of Emergency Management:

• Emergency Operations Facility / Recovery Center (State representatives located in the State Room)

• Emergency Operations Center (Concord, New linapshire)

CQHMONVEALTH OF HASSAClIUSETIS(Limited Participation - Practical Training)

Massachusetts Emergency Management Agency:

. Emergency Operations Facility / Recovery Center (State representatives located in the State Room)

• Emergency Operations Center (Framingham, Matsachusetts)

Massachusetts Department of Public llealth (EOF, Brattleboro, Vermont)

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VERMONT YANKEE NUCLEAR POWER STATION

- EMERGENCY RESPONSE PREPAREONESS~ EXERCISE ,

1992 1.3 ABBREVIATIONS AND DEFINITIONS I

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1.3 ABBREV 1AT10NS '.ND DEFINITIONS A. Abbrevietions

. AO -

Auxiliary Operator

. A0G -

Advanced Off-Gas System

. APRM -

Average Power Range Monitor

. ARM -

Area Radiation Monitor

. ATWS -

Anticipated Transient Without Scram

. CR -

Control Room / Control Rod

. CRD -

control Rod Drive-

. CS -

Core Spray

. OW -

Drywell

. EAL -

Emergency Action Level '

. ECCS -

Emergency Core Cooling System

. ENS -

Emergency Notification System

. EOC -

Emergency Operations Center EOF _

Emergency Operations Facility

. EPR -

Electric Pressure Regulator

.- EPZ -

Emergency Planning Zone-

.- ESC -

Ennineering Support Center

. FEMA- -

Federal Emergency Hanagement Agency

. FW -

Feedwater

. HPCI -

High Pressure Coolant Injection

. HPN -

Health Physics Network

. HRNG -

High Range Noble Gas i

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. LPCI - Low Pressure Coolant Injection

. MPR - Mechanical Pressure Regulator

. MSIV -

Main Steam Isolation Valve

. . NAS - Nuclear Alert System

. NG -

Noble Gases

. NRC - Nuclear Regulatory Commission

. OSC - Operations Support Center

. PASS - Post Accident Sampling System Primary Containment Isolation System-

. PCIS -

. PED - Plant Emergency Director-

. PVS

• Plant Vent Stack

. RA - Radiological Assistant

. RCIC - Reactor Core Isolation Cooling

. REMVEC - Rhode Island. Eastern Massachusetts, and Vermont Energy Control.

. RPS -

Reactor Protection System

. RR - Reactor Recirculation System

. RRU -

Reactor Recirculation Unit

. RWCU -

Reactor Water Clean-Up

. Rx -

-Reactor

.. SBGTS - Standby Gas Treatment System

. SJAE -

Steam Jet Air Ejector-

. SRM -

Site Recovery Mantger/ Source Range Monitor

> . TSC -

Technical Support Center

. VY -

Vermont Yankee 3

. VYNPC - Vermont'Y6nkee Nuclear Power Corporation

. VYNPS Vermont Yankee Nuclear Power Station

. YNSD -

Yankee Nuclear Services Division R1Ss128

I key. O t Page 1.3*3 B. Definitions

. Alert -

An emergency classification which

, is defined as an actual or Lotential substantial degradation of the level of safety of the plant.

. Controller -

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

. Critique -

A meeting of key participants in an exercise, usually held shortly af ter its conclusion, to identify weaknesses and deficiencies in emergency response capabilities .

. Emergency Action -

Specific instrument readings, Levels system levels or event observation and/or radiological-levels which initiate event classification, notification procedures, protective actions, and/or the mobilization of the emergency response R15\128

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i Rev. O Page 1.3-4 organization. These are specific threshold readings or observations indicating system failures or

< i abnormalities. l I

. Emergency Assistance -

General term used to refer to the

! Personnel radiation monitoring teams, sample J

i analysis team, and in plant-search and rescue teams.

l . Emergency Operations -

Areas designated by state / local Center representatives as Emergency Plan assembly areas for their respective

staffs, a:

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. Emergency Operations -

An emergency response facility facility / Recovery (Vermont Yankee Training Center, Center Brattleboro, Vermont) which 4

evaluates off site accident consequences and coordinates emergency response and assistance with all off site agencies.

. Emergency Planning -

The areas for which planning is Zones recommended to assure that prompt and effective actions can be taken

- to protect the public in the event of an accident.- The two zones are the 10 mile radius plume inhalation

( exposure pathway zone and thb R15\128 4-,-,, ..= .p._ r,e.., - ..w,- .. -r - . . e-m -

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. Engineering Support - A YNSD emergency support facility Center (Yankee Atomic Electric Corporate Headquarters) established to provide additional engineering  !

support to the affected site in i

plant assessment and recovery l operations. l t i

. Exercise - A demonstration of the adequacy and content of the emergency plan, implementing procedures, methods, and equi, 'n t .

. Full Participation -

An exercise which tests as much of Exercise the licensee, state, and local

, plans as is reasonably achievable without mandatory public participation and inconvenience.

. General Emertency - An emergency classification which is defined as actual or imminent substantial core degradation or-melting with potential for loss of ~

containment integrity.

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. News Media Center -

An emergency response facility (VYNPC Corporate Offices.

Brattleboro, Vermont) dedicated to i

the news media for the purpose of disseminating and coordinating information concerning accident conditions. All activities conducted-within this center will be the responsibility of the Vermont Yankee Nuclear Information Director.

. Observer -

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

weaknesses, and making recommendations for improvement.

. Operations Support -

An emergency response facility-Center (1st floor. Administration Building) established to custer skilled emergency response personnel to perform activities in the plant.

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! Page 1 3 7 Protective Action Those emergency measures taken to

{ effectively mitigate the consequenceb of an accident by

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i minimizing the radiological exposure that would likely occur if such actions were not undertaken.

. Protective Action -

Projected radiological dose i Guides values to the public which warrant

] protective actions following an uncontrolled release of radioactive l material. Protective actions would.

be warranted provided the reduction in the individual dose is not offset by excessive risks to individual safety in implementing such action.

. Scenario -

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

. Site -

That property within the' fenced 4

boundary of Vermont Yankee which is ownedb$theVermontYankeeNuclear Power Corporation.

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. Site Area Emergency -

An emergency classification that indicates an event which involves j l

4 likely or acts. major failures of  ;

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,i plant functions needed for the i protection of the public.  !

. Small Scale Exercise -

An exercise which tests as much of the licensee emergency plan and i procedures with minimal, voluntary l

participation of state and local government agencies. I i

. Technical Support -

An emergency response facility Center (2nd floor, Administration Building) with the capability to assess and mitigate the accident using plant parameters and highly

qualified technical personnel.

Also, assists in accident recovery operations. I

. Unusual Event -

An emergency classification that indicates a potential degradation of plant safety margins which is not likely to affect personnel on site or the public off site or result'in radioactive releases requiring off site monitoring.

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. Yankee Nuclear -

A division of Yankee Atomic l

.1 Services Division Electric Company. An Engineering j

i (YNSD) support organization which provides i .- emergency response' support to Vermont Yankee upon request, j a

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.4 VERMONT Y%'KEE NUCLEAR PO'='ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992

1.4 REFERENCES

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VEPRONT YANKEE NUCLEAR POWER STATIO!J EMERGENCY RESPONSE PREPAREDNESS EXERCfSE 1992

1.4 REFERENCES

1. Vermont Yankee Nuclear Power Station Emergency Plan

2. Vermont Yankee Nuclear Power Station Emergency Plan Implementing Procedures

3. Vermont Yankee Nuclear Power Station Piral' Safety Analysis Report l

4 Verciont Yankee- Nuclear Power Corporation - Communications Department Emergency Response Plan and Procedures.

J

5. Vermont Yankee Nuclear Power Station Emergency Operating Procedures l

6. Vermont Yankee Nuclear Power Station Core Damsge Assessment Methodology

7. Yankee-Atomic Electric Company .

3

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

b. "HETPAC"'(Meteorological Package) Dose Assessment. Computer Model,  ;

Version 4.1 B. Martin, G.F., et al., " Report to the NRC on Guidance for preparing Scenarios for Emergency Preparedness Exercises at Nuclear Generating i Stations," March 1986, USNRC, NUREG/CR-3365 '

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VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE-PREPARE 0 NESS EXERCISE i- .1992'

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- ;I i 2.0 fXERCISE OP,JECTIVES AND EXTENT OF PLAY VERMONT YANRFE  ;

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I Rev. 0 Page 2.0-1 i 2.0 GBJECTIVES AND EXTENT OF PLAY - VERMONT YANKEE

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! Extent of Play

! A. Emergency Classification and Accident Assessment

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

2. Demonstrate the ability of Control Room A.2 The scenario will provide technical information to pctsonnel and-TSC staff to coordinate the players which will allow them to analyze plant assessment of plant conditions and conditions and propose corrective actions.

corrective actions to mitigate accident conditions.*

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3. Demonstrate that information concerning A.3 Telephone communications links will be established  !

] plant conditions can be transmitted by communicators between the Simulator Control between the Control Room and TSC in a Room and the TSC in order to transmit key '

timely manner.- information and data.

4 Demonstrate the ability of the TSC staff A.4 The scenario events will enable the TSC to

.to initiate and coordinate corrective coordinate in-plant corrective actions througf the  !

' actions in an efficient and timely use of OSC personnel.

manner.*

5. Demonstrate the ability of appropriate TSC A5 The scenario includes events which allow for staff.to participate with the Control Room discussion between the Control Room. TSC. and EOF 4

and the EOF /RC in emergency classification staff on classification.  !

and'EAL discussions.

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" Indicates NRC identified item from the 1991 exercise.  ;

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6. Demonstrate the ability to assess data A.6 Scenario events will require Chemistry and from appropriate chemistry samples in Radiation Protection technicians located at the support of accident assessment activities OSC to simulate taking reactor coolant, and plant conditions. containment air, or plant vent stack samples to assess plant-conditions. Sample results will be provided by Observers who accompany the technicians during their sampling activities.

(Refer to Procedure OP-3530. " Post-Accident Sampling.-)

7. Demonstrate the ability to effectively use A.7 Emergrocy Response Facility Information System the ERFIS in the assessment and trending (ERFIS) terminals at the TSC and EOF /RC will be of plant. conditions. linked to the Simulator Control Room to receive and transmit scenario data. This will allow Emergency Response Facility staff personnel the opportunity to demonstrate the effectiveness of ERFIS under simulated emergency conditions.

B. Notification and Communication

1. Demonstrate that messages are transmitted B.1 Various communications links will be in an. accurate and timely manner and that B.3 established between emergency response decisions, information..and messages are B.4 facilities in order to transmit information and properly logged and documented.* data. Record keeping and documentation will be demonstrated in accordance with Procedure OP-3504

" Emergency Communications."

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

Indicates NRC identified item from the 1991 exercise.

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! Extent of Plav i i

2. Demonstrate the. capability'to notify B.2 Vermont Yankee staff. NRC and state authorities *

federal and state authorities of emergency shall be notified in accordance with established

• 4 classifications and significant changes in procedures. NRC will be notified by utilizing the [

l plant status in accordance with FTS 2000 EMS phone. The State authorities will be established procedures.* notified through the Nuclear Alert System (brange t

Phone). l t - P

!. .3. Demonstrate that appropriate status boards i 4

are utilized to display pertinent accident i j information at.the various emergency response facilities.* [

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4. Demonstrate that adequate emergency [

communication systems are in place to facilitate transmittal of data between i I

emergency response facilities and federal -

and state authorities.

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I C. . Direction and Control  !

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1. Demonstrate'the proper transfer of C1 Scenario events requirt the activation of the l -responsibilities from the SS/ PED to the Emergency Response Organization. As each position ,

Duty Call Officer and subsequently to the of authority is activated, respoasibilities l 1 TSC Coordinator and Recovery Manager as associated with that position will be assumed from -

j- appropriate. the SS/ PED up to the Recovery Manager. r i

[ 2. Demonstrate t,he capability of key. C.2 All emergency response facilities have designated  ;

, emergency response facility management coordinators who will direct and coordinate 4 personnel to direct and coordinate their emergency response activities in their particular I

l. respective emergency response activit'.es area of responsibility.

I 'in an efficient ard timely manner.*

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$; Indicates NRC identified item from the 1991 exercise.  ;

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3. Demonstrate appropriate coordination of C.3 The Control Room will initially contact the activities'with federal and state federal and state agencies. providing them vith [

government agencies. appropriate information on plant conditions and emergency status. This function will pass to the i D. Emergency Response Facilities TSC and EOF /RC after the facilities are activated. I

[

!" 1. Demonstrate the ability of station and 0.1 Scenario events will require activation

i. corporate personnel to activace and staff D.2 and operation of Vermont Yankee emergency response 3

the emergency response facilities in a facilities.

timely manner.

The Simulator Control Room. Control Room (communication functions only). TSC. OSC. ,

EOF /RC. News Media Center and Engineering Support {

l 2.. Demonstrate and test the adequacy and Center will be activated in accordance with '

effectiveness of emergency response' estab!ished procedures. Designated plant and  !

facilities. operations..and equipment. corporate emergency response personnel will i participate in the-exercise. j E. Plant Aegmentation and Staffinq i

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1. Demonstrate the adequacy of plant E.1 Shift personnel should demonstrate the use of the emergency notification methods and  !

emergency call-in system to augment plant staff as  :

procedures to augment plant staff and may be required by scenario events. I resources. ,

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

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

future manpower and logistics needs.

F. Radiological Exposure Control

l. Demonstrate the ability to provide F.1 Scenario events will require OSC On-Site adequate radiation protection controls for F.2 Assistance Teams to be dispatched to investigate 2

on-site emergency response personnel problems associated with plant equipment.

dosimetry, equipment and protective Investigation and repair activities in the plant

, clothing. will require implementation of radiation protection controls which include monitoring and

2. Demonstrate the ability to monitor and tracking of radiation exposure of OSC Cn-Site i- track radiation exposure of on-site Assistanct- Teams. (Refer to Procedure OP-3507, i- emergency response personnel.

• Emergency Radiation Exposure Control.") In addition. the exposure of the off-site monitoring teams will be monitored and tracked in the EOF.

G. In-Plant Corrective and Repair Actions

.1. Demonstrate'the ability to dispatch and G.1 OSC on-site assistance teams should be dispatched deploy on-site assistance teams in a G.2 to investigate problems associated with plant timely fashion. consistent with plant G.3 equipment. Briefings should be conducted with

-conditions and assigned function. on-site assistacce teams to ensure that responsibilities are clear and understood.

Briefing sheets (refer to VYOFF 3507.02) should be used to brief and debrief teams on work assignments conducted. All information should be documented in accordance with established procedures. Plant personnel will be given the j opportunity to perform corrective actions associated with damaged plant equipment.

Indicates NRC identified item from the 1991 exercise.

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Extent of Play

2. Demonstrate the ability to provide adequate briefinrs to ERF staff and ['

on-site assistance teams

• as conditions and information change.

3. Demonstrate the ability of on-site t assistance teams to perform e'rrective i actions on plant equipment during j- emergency conditions.

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H. Radioloqical' Assessment

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

I 2. Demonstrate that radiological assessment H.5 Players will implement appropriate sections of personnel.at the E0F can obtain Procedures OP-3513. " Evaluation of Off-Site 1 radiologicci and-meteorological data in a Radiological Conditions" and OP-3511. "Off-Site timely manner. Protective Actions Recommendations.* as may be required by scenario events.

3. Demonst' rate the ability to perform timely assessment of off-site radiological conditions to support the formulation of i

_ protective action recommendations for the j' plume exposure pathway. I i i 1' .

j 4 Demonstrate.the ability to' assess i

potential off-site radiological '

consequences based on plant conditions.

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• Indicates NRC identified item from the 1991 exercise.

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

6. Demonstrate Cdequate staffing, equipment H.6 Off-site monitoring teams will be assigned at readiness cneck. and deployment (if H.7 the OSC. Players will implement appropriate necessary) of off-site monitoring teams. sections of Procedure OP-3510. "Off-Site and Site Boundary Monitoring.* ,

7. Demonstrate the use of appropriate equipment'and procedures to perform off-site radiological monitoring.

I. Protective Action Decision-Making

. 1. Demonstrate the. ability to 2,npl emen t 1.1 On-site protective action measures will inclaie.

appropriate on-site. protective measures radiation exposure control and plant evacuation of for Omergency' response. personnel. nonessential personnel. After plant evacuation and accountability has been completed, all plant personnel and contractors not directly involved'in the exercise may be allowed to return.to work.

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

appropriate recommendationsLconcerning "Off-Site Protective. Actions Recommendations *.

off-site radiological consequences.

a Indicates NRC identified item from the 1991 exercise.

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1. Demonstrite the ability to develop and J.1 The News Media Center will be fully . ivated.

periodically disseminate timely and J.2 Information on the simulated events occurring accurate press releases to the public and J.3 at the plant will be gathered verified, the news media. incorporated into a news elease, and disseminated to key players. After approval, this information

2. Demonstrate the abilit" to provide will be discussed at the News Media Center. i briefings and to interface with the public and news. media.*

3. Demonstrate th2 ability.to communicate and coordinate news releases-between the EOF and the News Media Center.

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

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5. Dem3nstrate the ability to coordinate news J.5 State public information representatives from releases with the state's public Vermont, New Hampshire, and Massachusetts may be information' representatives, if available. present at the News Media Center. Information concerning news releases will be coordinated with the states

• public informoi:on representatives. if .

available.

1 Indicates NRC identified item from the'1991 exercise.

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K. Parallel and Other Actions

1. Test and evaluate the adequacy of methor 5 ity activities will be implemented in to establish and ..laintain access contre' -

dance with established procedures to control  ;

s'd personnel accountability within the s to the protected area. Assembly of protected. area. ,ency response personnel and evacuation of -

..ractor/ visitors will be implemented in order (o test personnel accountability within the protected area. However, after the plant evacuation accountability checks have been completed, contractors and visitors will be exempted from additional personnel accountability checks.

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

Note: The annual Radiological Monitoring drill'and semiannual Health Physics drill will be included as.part of this exercise.

A' separate; Health' Physics drill will be.

held to demonstrate the actual sample-

-collection and analysis of in-plant chemistry samples which includes the use of the Post-Accident. Sampling System i

(PASS).

i Indicates'NRC identified ' item from the 1991 exercise.

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=2 VERMONT YANKEE NUCLEAR POWER STATION 1 EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 N

3.0 EXERCISE GUIDEl.INES AND SCOPE g

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' VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY. RESPONSE PREPAREDNESS EXERCISE 1992 4

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3.1 EXERCISE GUIDELINES

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EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 3.1 EXERCISE GV10ELINES A. Pu.oose This package provides-guidance for conducting the 1992 VYNPS Emergency Response Preparedness Exercise. It provides the framework for demonstrating emergency response capabilities, conducting the exercise and evaluating response activities.

1 B. Concepts of Operations and Control of the Exercise An Exercise Coordinator has been appointed'by Vermont Yankee management to oversee all exercise activities, The Exercise Coordinator is responsible for approving the objectives.and-developing the scenario time scquence. The' Exercise Coordinator.

l 1s also responsible for the selection and training of the-

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personnel reccired to conduct and eval' ate u the exercise.

Vermnnt Yankee will supply Controllers and Observers (Evaluators)

.for major locations where an emergency response action will be l demonstrated. Prior to the exercise..the Evaluators will De j provided with the. appropriate materials necessary for their assigned _ function. The material will include any maps and messages to be used and forms for documenting and evaluating

, observed activities.

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Rev. O t Page 3.1 2 In each facility where an activity takes place'. the Controller will make judgment decisions to keep the action going in accordance with the scenario timeline. The Controllers will also provide guidance to Observers and resolve minor problems which may occur. If a serious problem arises, an Observer should first contact the facility Controller who will then contact the Exercise Coordinator for guidance or resolution of the problem. All major requests for scenario modifications or holding riods must be I cleared through the Exercise Coordinator. Cor llers also have the authority to resolve scenario related problems which may cccur

'b during the exercise.

Observers for the exercise will observe the players as they perform their assigned emergency response functions. Observers are responsible for being knowledgeable in the area of their assigned function. The Observers will critique the effectiveness of the emergency response actions taken during the exercise and will also provide a written evaluation to their Facility Controller.

The exercise initial conditions will be provided to a Control. Room operations crew, located in the Simulator. Plant and reactor system parameters for the exercise will be generated by running the accident scenario on the simulator. Additional exercise message cards and scenario parameters will be provided by Evaluators at the times indicated in the exercise sequence of events, or when requested by the players, s

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( Page 3.1 3 As information is provided to the players, they should determine

the nature of the emergency and implement appropriate emergency plan implementing-procedures and emere ncy operating procedures.

, These procedures should include a determination of the emergency classification in accordance with the Vermont Yankee Emergency Plan. Notifications will be made to the appropriate federal-and

, state authorities.

The hypothesized emergency will continue to develop based on data.

and information provided to-the operators located in the simulator. Wherever possible, operators should complete activities as'if-they were actually responding to-plant events.

, Inconsistencies in the scenario may be intentional and required to test the capabilities of the emergency' response-facilities to the maximum extent possible in a limited period of time, C. General Guidance for the Conduct of the Exercise i.

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1. Simulatina Emeroency Response Actions

, Since the exercise is intended to-demonstrate actual capabilities as realistically es.possible, participants should act as they would during an actual emergency.

Wherever possible. simulation of response activitias should be avoided. Emergency response. actions should be. simulated only when it is not feasible to perform an action or when the action has been previously identified as1being simulated during the exercise (refer to Section 3.2). When an i

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. Page 3.1-4 emergency response is to be simulated, the Evaluator will provide verbal or written directions on which actions are to be simulated.

Radiation Work Permits (RWPs) have not been. issued for the conduct of the exercise. If scenario events direct players to areas that are actually RWP-controlled due to high radiation,' surface contamination, or airborne radioactivity, players will simulate response activities without ictual_ly entering the RWP-controlled area even if they are authorized on the RWP for some other duty.

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

a. All Evaluators and potential participants must be specifically informed of the need to avoid violating any federal, state and local laws, regulations, 4

ordinances, statutes and other legal restrictions.

, The orders of all police, sheriffs or other authorities shall be followed as appropriate.

b. Participants will not_ direct illegal actions to be taken by other participants or members of the general publ i c.

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c. Participants will not inten'.ionally take illegal actions when responding to scenario events.-

Specifically, local traffic laws (i.e., speed limits) will be observed.

3. Avoidino Personnel and Property Endancerment All participants will be instructed to avoid endangering property (public or private), other personnel responding to the events, members of the general public, animals and the environment.

4, Actions to Minimize Public inconvenience It is not the intent, nor is it desirable, to effectively J

train or test the public response during the conduct of the exercise. Public inconvenience is to be avoided.

The conduct of an exercise could arouse public concern that an actual emergency is occurring. It is important that conversations that can be monitored by the public (radio,-

loudspeakers, etc.) .be pref aced and conclude with the words,

• THIS IS A DRILL: THIS IS A DRILL."

D. Emeroency Response implementation =nd Operations

1. Initial and Follow Up Notification Initial' and follow-up notification of.the emergency classification will be made by the plant staff in acco'rdance ,

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l. Page 3.1-6 with existing emergency plan implementing procedures, unless directed otherwise,

2. Control Room Operations A Control Room emergency response crew will be po.it'oned in the Simulator, located.at the Vermont Yankee Training Center in Brattleboro, Vermont. The support staff normally on duty will initially be simulated until after the ALERT 2

classification when it will be performed by the emergency response organization. Plant.and reactor system parameters will be provided to the Control' Room emergency response crew by the simulator control board and-.the' Controllers. Other information, such as radiological data and meteorological data, will be provided to the Control Room' emergency response crew as necessary. Communications links that duplicate the emergency communications capabilities available at the Control Room will be used.to communicate between the Simulator Control Room and other emergency

~

response facilities. -The actualLContrcl Room communication-system for transmission of emergency announcements and information (e.g., Galtronics) will also be utilized.

3. -Technical Support Center (TSC) Operations The TSC emergency response organization will be activated-Curing the exercise. TSC information will originate from the Simulator Control Room. Information'that is normally-accessible by TSC personnel from the plant computer will be provided by Evaluators- utilizing . telephone communications R15\128

Rev, 0 j Page 3.1 7 between the simulator area and plant computer room. In addition, TSC Cnmmunicators, who would normally be assigned to the Control Room to provide TSC requested plant data, will be staged at the Simulator, i

4 Operations Support Center (OSC) Operations The OSC emergency response organization will be activated during the exercise. Operations _ Support Center response activities will be ecmmunicated to the Technical Support.

Center. OSC Observers will accompany OSC teams dispatched during the exercise and will provide _ appropriate operational' and radiological data to the players. No team participating in the exercise should leave-the Staging Area without notifyin'g an Evaluator.

5. Emeroencv ODerations Fec'11tv/ Recovery Center (EOF /RC)

Operations

, The EOF /RC emergency response organization will'be activated during the exercise. Information and data will be transmitted to the EOF /RC from the TSC and Control Room 1 (Simulator). E0F Evaluators will provide other data to

EOF /RC players as necessary.

C. Off-Site Monitorino Teams Off-site monitoring teams will be fully activated and dispatched in accordance with existing procedures, l R15\128

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( Page 3.1 8 Simulated data will be provided to off-site monitoring teams by the Off-Site Monitoring Team EJaluators.

7. News Media Center ODerations i

The News Media Center will be activated and staffed during the exercise. News Media Center staff will-obtain all-the necessary infurmation on current plant status through communications channels with the EOF /RC. Press' releases will be generated and disseminated in accordance with the Vermont Yankee Communications Department Emergency Response f

Plan and Procedures. All press releases are to be clearly.

marked: THIS IS A DRILL.

, 8. Security Operations All exercise related security emergency response activities will be implemented in accordance with existing procecures.

Access contro5 and personnel accountability within the protected area will be demonstrated. At no time will actual-plant security procedures be violated in' support of'the exercise.

E Ex3_rcise Termination The exercise will be terminated by the Exercise Coordinator when all- emergency response actions have been completed in ~accordance with the exercise time sequence and exercise objectives.

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( Page 3.1 9-The following steps will be implemented to terminate the exercise:

1. The Exercise Coordinator will obtain information from the 4

Facility Controllers regarding the status of player actions and the demonstration of the exercise objectives.

2. The Facility Controllers s a responsible.for informing the Exercise Coordinator of their facility status and whcther the emergency response actions and objectives have been satisfactorily observed.

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

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

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

The exercise may elso be terminated.under the following circumstances:

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

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2. An actual off-site emergency impacts the response actions of

, Vermont Yankee exercise participants.

. In the event that item I should occur, the following actions will be taken:

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

2. The Site Recovery Manager v'll immediately inform any State -

representatives at the EOF of the nature of the emergency; i

2

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

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

The emttgency plan exercise has been-terminated.*'

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

4. The Exercise Coordinator will be responsible'for directing the

. actions of all other exercise participants, i In the event that item 2 should occur, the following actions should be

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taken:

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1. The Shif t Supervisor will noti fy. the Control Room Controller who, in turn, will notify the Exercise Coordinator.

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2. A coordinated decision will be made in conjunction with the Site Recovery Manager and/or the TSC and E0F Coordinators concerning-the completion of the exercise. l

3. The Exercise Coordinator will be responsible for temporarily halting the exercise until such time a decision is made.

4. If the final decision is to cancel the exercise, the Exr cise Ceordinator will be responsible for directing the activities C.

all exercise participants, as well as for the notification of the NRC.

5. If the final decision is to continue the exercise, the Exercise Coordinator is responsible for informing all Evaluators of any projected changes to the expected response, action (s).

6. The Exercise Coordinator will direct the orgar.ization as to the i

appropriate action required to restore the exercise sequence.

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VERMONT YANKEE NUCLEAR POWER STATION  ;

' EMERGENCY RESPONSE PREPAPIDNESS EXERCISE i

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VEPJiONT YANKEE NUCLEAR P0k'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1992' s

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3.2 PLAYER INSTRUCTIONS AND CPOUND RULES The Vermont Yankee Emergency Response Preparedness Exercise'will be i conducted on September 2, 1992. .All emergency _ response facilities will be l

fully activated, and.the scenario will ,be ' driven by the simulator; as in

, past exercises. This year's exercise'is a small-scale event with full' I participation from Vermont Yankee and Yankee Atomic. Limited participation is expected from the State of Vermont, New Hampshire, j Commonwealth of Massachusetts cnd-local towns within the plume' exposure-

EPZ. Limited participation for these organizations would pertain to event i

notifications and practical training for the state representatives at the.

EOF. The successful demonstration of emergency response capabilities will I

depend on player response and protocol. The following information contains details and instructiens for the players.regardin5 the exercise.

Department Heads are responsible for ensuring that personnel are made

aware of this information prior.to the scheduled exercise date.

A. General Guidelines

1. Participants will include the Exercise Coordinator, Players, Controllers, Observers,-and NRC Inspectors. Contr'llers o and observers will provide players with ' command and message cards to initiate emergency response actions. Controllers, Observers and 1 j

NRC Evaluators will also evaluate and note player actions.

Controllers, Observers, (herein referred to as " Evaluators") and .

NRC Evaluators will be identtiied.by badges.

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

Wear a name tag if one is provided.

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

1

a. Initial conditions of the plant and systems including:

o operating history'of the core o initial _ coolant activity t'

o general weather conditions o availability of systems according to the scenario

b. Area radiation data at the location of emergency teams.

1 c. Airborne data at the location of emergency teams after_a sample has beer. properly obtained.

d. Counting efficiency of all counting equipment.

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e. Activity from nose swabs or skin contamination surveys.

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4. You may n2r ask the-following from the Evaluators:

a. Information contained in procedures, drawings, or 4

instructions.

b. Judgments as to:which procedures should be used.

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

d. Assistance in performing actions.

e. Assistance in performing calculations.

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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 Evaluator 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 Evaluators. .This may ceem artificial, but it will assist the evaluators in determining the various response actions being initiated and is to your benefit.

8. When you are assigned to complete a response action, be sure to notify an Evaluator prior to performing the action. Let the Evaluators prioritize which actions will be observed and which ones will not. If an Evaluator elects to observe your activity, ensure the Evaluator remains with you to observe the task (i.e don't lose the evaluator enroute to the area where the actic'n will-take place).

9. If you are in doubt about completing a response action, ask your Evaluator for clarification. The Evaluator will not prompt or:

coach you, . Emergency. response actions must not place participants in any potentially ha:ardous situations.

- 10. The scenario has been scrutinized to anticipate as many success-paths the 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 " Command Card" from the Evaluator. In addition, the i

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a Evaluator may periodically issue messages or instructions designed to-initiate response actions. You muit accept these messages immediately. They are essential to the proper

, completion of the exercise scenario.

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

12. If you disagree with your Evaluator, discuss your concerns in'a "

professional manner. However, the Evaluator's final decisions must be followed. -

13. Respond to questions in a timely manner.

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14 D2_n21 accept any messages / instructions from EEG Evaluators..

They are required to work through your Evaluator if they want to initiate additional emergency conditions.

However, you may answer questions-directed to you by'NRC-1

, Evaluators. If you do not hnew the answer, offer to get them the answer as soon-as possible (without interfering with exercise activitiesy or refer them to your. lead-facility player

.or Evaluator. -

15. You must respond as if elevated radiation levels .1re actually present based on the ' scenario' infe rmation you re , eive. This may

require you to'vear protective clothing, respirators, or additional dosimetry, yj-I-

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Rev. O j Page 3.2 16. Evaluators are exempt from simulated radiation-levels and other emergency conditions. Do not let this confuse you or cause-you to act unwisely. However, no one is exempt from normal station n

radiological practices and procedures.

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

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

19, Keep a litt of items which you believo will improve your plans and procedures. A player debriefing vill follow the exercise.

I Provide any Lomments or observations to your lead player or Evaluator after the exercise. Areas for improvement or weaknesses when corrected will improve the overall emergency response capability.

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Rev. 0 j Page 3.2-6 B. Player's Simulation Lisa The following d<sseribes those specific actions which do not have to be performed and can be simulated by participants. All other actions are to be performed in accordance with plant procedures. No action-will be allowed which' alters or affects the ongoing operation of the

, plant.

1. Scenario specif$c data will be programmed into various Simulated l Plant Process Computer (SPPCS) terminals via the simulator. The Control Room's.SPPCS terminal will remain tied to the plant process computer (ERFIS).

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

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

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

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5. Distribution of potassium iodide (KI) will be simulated.

6. Charcoal cartridges will be used in place of silver zeolite cartridges during off-site monitoring activities.-

7. YNSD Site Responders will be prestaged in the area.

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8. Emergency Response Facility evacuation vill not be demonstrated during the exercise.

l 9. Off-site monitoring teams and security boundary monitoring personnel will not wear either protective clothing or respirators.

10. The inner gate and electric;1?y controlled doors will not be left in the open position during the exercise.

l 11. The plant Caitronics is not;available from the simulator;-actual plant announcements will be coordinated by the controllers and made from the Vermont Yankee plant Control Room.

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, 12. Evaluators will not be issued dosimer"; un) . .s plant access is required prior to the exercise. Security will be notified of the Evaluators assigned locations.

I- 13. All decontamination actions associated with the scenario events may be simulated after discussion and-approval by the Evaluator,

, 14. The use of respiratory protection equipment may be simulated by i plant personnel after discussion and approval ;he Evaluator.

15. Radiation Work Permits (RWPs) have D21 been issued for the 1

conduct of the exercise.

4 C. Simulator Control Room Information

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'The following describes how the Simulator Control Room emergency

- 1 response activities will be integrated with the plant Control Room a

functions during the exercise:

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1. Players reporting to the plant Control Room will be directed to an area (SS office) that will have a Control Room Evaluator and-communications link with the cimulator. All Control Room exercise communications should be directed to the Simulator Control Room.

2. All exercise-related Caitronics calls to the Control Room and vice versa will be relayed or answered by the Control Poom Evaluator. CRANNEL 3 should be utilized for all exercise

-messages.

3. Gaitronics p4 ant announcements will be coordinated by the Simulator Evaluator. They will be made by the operating crew in the plant Control Room.

4. TSC Communicators normally assi6 ned to the Control Room and a Radiation Protection Technician for transmitting initial-

, radiological and meteorological data will be prestaged in the simulator.

, 5. Personnel movement in and out of the Simulator Control Room will be limitad to the Evaluators.

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6. Communications equipment in the Simulator Control Room is the same as the plant Control Room. The commercial telephone extensions are different, but the auto-ring down circuits and-speaker. telephones are operable. The orange Nuclear Alert System (NAS) State telephone and Federal Telephone System (PTS)-

2000 Emergency Notification System (ENS)-NRC telephone will be I

operable. The orange NAS telephone extension is 613. The red ENS-NRC telephone will be operable until the TSC takes over this communication function.

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D. Player's Camess,anship The following is- a. list of items thet should be followed to improve gamesmanship during the exercise:

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

2. Keep all messsges, status boards, and problem boards accurate, current, timed, and dated.

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

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

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

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

E. Personnel Accountability and Particination (Exempted Participants)

Procedures require that all participants be identified. Proper identification will not only help eliminate confusion, but is necessary for security end accountability. This requirement applies to all areas within the plant fence, Governor Hunt House, 20F/RC, simulator area, News Media Center, and the Vermont _ Yankee Corporate Office in Brattleboro.

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! Page 3.2-10 Although it is expected that all personnel will respond to the declared emergency as delineated in the applicable procedures, it is

, recognized that a numberlof persons (e.g., normal plant operations shift. . normal security complement, fire watches, etc.) will not

. participate due to the nature of their assigned duties and activities. Department Heads should review their area of responsibility and provide the Exercise Coordinator with a list of names for anyone that should be exempted from participation. Ihg number of exemot nersonnel-should be minimized. As in the past, people evacuated from the plant will be allowed to return to their normal duties upon approval from the TSC Coordinator, Plant Security will be provided with_ the list of exempt personnel for the exercise. All other personnel, not listed, are expected to participate as required by the Emergency Plan. The list of exempt personnel will include the On-Shift Security Crew, Operating Crew, and Duty Chemistry and Radiation Protection Technician and other individuals identified by the Department Heads.

F. Off-Site Participation (Federal. State and Local)

This year, Vermont Yankee. is conducting a small-scale exercise which may involve partial participation of the States of Vermont, New

, Hampshire,- Commonwealth of Massachusetts and the local towns within the Plume Exposure pathway EPZ. -

I The capability to notify federal, state, and local authorities of emergency classifications in accordance with established procedures will be demonstrated as follows:

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

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Rev. O Page 3.2-11

b. Vermont, New Hampshire, and Masscchusetts State Police dispatchers and State Emergency Operacions Centers (EOCs) will be notified through the orange-NAS telephone, i

c. Vermont, New Hampshire, and Massachuse.cs 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 plant Control Room-RECARDING THE EXERCISE, the Vernon switchboard should transfer the call to the Simulator Control F.,a in Brattleboro. The NAS orange telephone extension in-the Simulator Control Room is 613.

C. Exercise Critioues The following is a brief description of the critique sessions that will be held after the exercise. The critique sessions are held to determine'whether the stated exercise objectives were met, verify the effectiveness of the emergency plan and procedures, and identify areas for future-improvements. The specific schedule for the critique sessions will be announced at the_ conclusion of the exercise.

Emercency 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. Operations Support Center and Security i

4. News Media Center i

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contro11.er Debriefine- .

This session vill be conducted by the Exercise coordinator to compile l

all exercise comments and findings. Participation is limited to Exercise Controllers.

Exercise Criticue i

This session vill be conducted by the Exercise coordinatur to present to management a summary of all uajor findings identified during the exercise. Participants include Vermor.: Yankee management, Exercise Controllers, key players, and the NRC.

NRC Exit Immediately following the exercise critique, the NRC will present their preliminary findings. Participants will be the same as tu J a exercise critique session.

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h fi i VERMONT YANKEE IRfCLEAR POWER STATION EHERGENCY RESPONSE PREPAREDNESS EXERCISE 1792 4

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3.3 IEOCEDURE EXECUTION LIST 4

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3.3 f.MERGENCY PIAN IMPLEMENTING PROCEDtPt EXECUTION LYST -

Procedure Nunber Rev. Ng. 11.tle .

AP 3125 - 10 Emergency Plan Classificatior and .

Action Level Scheme OP 3500 11 Unusual Event OP 3501 12 Alert

-OP 3502 24 Site Area Emerges.cy OP 3503 26 General Emergency OP 3504 24 Emergency Communications OP 3507 20 Emergency Radiation Exposure  ;

Control t

OP 3510 18 off-Site and Site Boundary Honitoring OP 3511 6 Off-site Protective Actions Recommend 9 tion OP 3513 14 Evaluation of Off-Site Radiological Conditions OP 3524 9 Emergency Actions to Ensure Accountability and Security Response OP 3525 5 Radiological Coordination OP 3530 14 Post-Accident Sampling OP 3531

- 4 Emergency call-In Method 4

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i VEPJ10NT YANKEE NUC12AR POWER 'TATION r

-s EMERGENCY RESPONSE PREPAREDNES"> EXERCISE 1992 i

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4.0 CONTROLLER AND OBSERVER INFORMATION 1 '

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YEPJiONT YANKIE NUCLEAR POWER STATION.

j i EttERCENCY RESPONSE PREPAREDNESS EXERCISE .

1992 i

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i 4.1 CONTROLLER AND OBSERVER ASSIChMENTS l

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I NOTE: ASSIGNMENTS WILL BE PRO'iIDED AT~ THE EXERCISE BRIEFING SESSION [

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VERHONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSr PREPAREDNESS EXERCISE ,

1992 4 .2 CONTR0llFR AND OBSERVER EXERCISE GUIDANCE 4

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VERMONT YANKEE NUCLEAR POWER STATION

EMERGiNCY RESPONSE PREPAREDNESS EXERCISE 19.21.

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i 4.2 CONTROLLER AND OBSERVER EXERCISE GUIDANCE Prior to the exercise, each Evaluator will be provided a scenario package and the plant emergency plan implementing procedures which )

correspond to their assignment. It is the responsibility of the l Evaluator to read the contents of the package and review the procedures,  !

An Evaluator briefing will be conducted prio.' to the e a rcise. Aay questions regarding the scenario or assignments should be discussed at this time. Each Evaluator should ensure that they are familiar with the

location (s) required by their assignment. Emergency response facility 1 tours are available after the Evaluator briefing. I The Controller is responsible for directing Observer activities throughout the course of the exercise. When the exercise is terminated, the Controllers will meet with the Observers to obtain'their comments, observations, and documentation. Each Controller will be responsible

, for ensuring that the documentation is provided to the Exercist Coordinator at the conclusion of the exercise. Each Controller is also responsible for providing a brief summary of their facility comments during the player debriefing.  ;

Evaluators should identify themselves to the players and explain their

• role in the exercise. Players should be informed that any actions which deviate from standard plant or emergency procedures sho9ld be identified-to the Evaluators. Evaluators should keep a detailed log throughout the exercise. This lop should note the time,-location, and player responses. Section 4.3 contains log sheets, checklists, and evaluation forms for documentation purposes.

The primary role of Evaluators is to evaluate the emergency response activities of the players. In order to document the adequacy of emergency response actions during.tr,e exercise Evaluators are required to complete the Emergency Et,ercise/Dri11' Observers Evaluation form, p When completing this form, Ivaluators should attempt to differentiate T

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Page 4,2~2 their comments into either adequate or potential weaknesses. For i identified weaknesses of personnel, equipment, etc. provide a clear, written explanation of the finding, with recommendations for improvement which detail corrective actions, if possible.

!. Evaluators should not allow their biases to be dor.umented as recognized

weaknesses or deficiencies. Comments and recommendations should be

=

further subdivided under the gereral headings as follows: Facility Activation / Organizational Control, Communications, Adherence to Plans ,

and Procedures, Equipment Capabilities, Scenario, Training, Facility ,

laynut. Off Site Monitoring, Personnel Dosimetry / Exposure Control, and ,

[ General Comments.

i i facility Activation commen u should identify: (1) the time that emergency response personnel were notified: (2) when the facility was i

activated: (3) when initial activities became well organized: (4) whether personnel performance followed the organized arrangements specified by plant procedures and (5) the efficiency of methods of authority transfer. If a transfer of responsibilit.y occurred, then the Evaluator should determine if all affected personnel were aware that the

~

transfer had occurred.

Communication comments =should identify: (1) personnel familiarity with j

emergency communications use; (2) whether sufficient communications were available to ensure a tir ely, ef ficient, and effective flow of information:-(3) whether there were enough communications personnel to-make use of all available equipment (4) th) adequacy of communications logs and the effectiveness of data transfer: (5) whether there were any problems in the design of the existing communications system (i.e.,

location relative to traffic flow): (6) whether there were any recognized difficulties in the use of computer systems: and (7) whether facility boards were effectively used. Evaluators should document their comments in this area very carefully, providing sufficient details-to track any recognized deficiencies.

Plans and Procedural comments should identify: (1) whether personnel were familiar with the details of the overall concepts of applicable procedures: (2) whether situation

• developed which required deviation

• from the procedures or plan: (3) whether personnel were overwhelmed with R15\128

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1 Rev. O j Page 4.2+3 4

l procedural requirements which distracted them from performing their required emergency response function, and (4) whether the procedures

! adequately described the actions required to complete an assigned l function.

4 Equipment capability comments should identify: (1) whether all necessary materials and equipment were available and functional: (2)

~

whether emergency resp 0Se persont.el checked operability of equipment prior to conducting their assignment;-(3) whether backup equipment was ,

4 readily available when m31 functions were reported; (4) whether the-l available systems provided an adequate service: and (5) whether equipinent malfunctions impacted the expected emergency response.

l Scenario re16ted comments should address: (1) whether sufficient data-were available to ensure appropriate player response: (2) whether the j scenario details deviated from actual procedural requirements; and (3) whether the scenario detail provided any prompting to the player. The adequacy of the scenario in keeping the players 6ctive and interested throughout the exercibe should also be addressed by the Evaluators.

1 4

Training comments should identify: (1) whether plant personnel have

been provided sufficient training to handle *ad hoc" procedural deviations; and (2) whether training identified improper procedural requirements.

4 Comments on f acility layout deficiencies / recommendations should identify: (1) whether the available work space was adequite: (2) l whether traf#ic flow hindered the response e' forts:-(3) whether the

noise level hindered-emergency response efforts; and (4) whether

sufficient references were available to complete the job assignment.,

Off site' monitoring team observers should identify: (1) the adequacy of I

sampling methods; (2) the adequacy of contamination control measures; ,

(3) the adequacy _of reporting and documentation measures; and (4) the effectiveness of the team in defining the plume condition _ and sample locations. Dose projection techniques sho91d.be evaluated in l- conjunction with this general category. Observations regarding dose projection technique should identify: (1) the_ effectiveness of the' system in allowing the correct interpretation of.off site conditions.

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p. Page 4.2'4 and (2) the effectiveness of using the projection technique in positioning off site teams.  ;

f j Evaluation of Personnel 00simetry/ Exposure Control activities should ,

j identify: (1) the timeliness and effectiveness of dosimetry distribution: (2) the effectiveness of protective measures, such as

! acministration of potassium iodide: (3) the adequacy of established

! contamination control access points: (4) the adequacy of: exposure i planning measures siforded in plant activities: and (5) the adequacy of l decontamination and posting techniq'les.

i The Evaluators evaluation and documentation forms are four.d in i Section 4.3. All such documentation must be provitted to the Controller .

after the exercise and prior to the plant critique, i

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPARE 0 NESS EXERCISE 1992 i

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4.3 CONTROLLER AtJD OBSERVER EVALUATION CRITERI A i .;

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, Page 4.3*1 VERMONT YANKEE NllCLEAR DOWER STATION EMERGENCY RESPONSE PREPARFONESS EXERCISE 199?

i 4.3 CONTR0llER AND OBSERVER EVALUATION CRITERIA As discussed in Sections 4.1 and 4.2, each Evalcator has been assigned specific areas of response to evaluate. This section has bien developed ,

to assist the Evaluators in recording and documenting their findings and observatinns. The completed material will be an official record of the i exercise observations.

Attachment A consists of form; to be used in maintaining an event.

chronology 109

Attachment B contains evaluation checklists for each emergency response j facility. Each Evaluator should complete the appropriate checklist.

i Attachment C contains an evaluation form which should be used to summarize major findings ano observations. This form HUST BE completed j hy each Evaluator.

All three attachments should be completed and submitted to the facility Controller. Each Controller will then submit the attachments to the Exercise Coordinator for documentation and record keeping.

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Rev. O j Page 4.3 A.1 ATTACHMENT A Vermont Yankee Nuclear Power Stetio,n, Emeroency Response Exercise /Orill Evaluator's Observations Chronolooical too i

Time Observation / Comment ._

i Name: Area ' Evaluated:

. Date:

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i ATTACHMENT A j (Continued) 4 x

4 Tirne Observation / Comment r'

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Rev. O j Page 4.3 B 1 ATTACHMENT ,8 ygrmont Yankee Fmerr,ency Exercise / Drill Evaluation Checklist i

INSTROCT10NS The following evaluation checklists are provided to assist the Evaluator with their evaluation of the drill / exercise. The Evaluator should complete the checklist (s) for their assigned location (s). To complete the evaluation checklist (s), utilize the rating scale listed below. Any comments or suggestions for improvement, should be included on Attachment C, the Emergency Exercise / Drill Evaluation Form or on a separate piece of paper.

Ratino Symbol Comment: and Succested improvements a

Adequate A May be followed by comments and suggestions for improvements, especially if rating is marginal.*

Inadequate  ! Must be followed by comments, together with suggestions for improvement.

Not Observed or N No comments or suggestions are required.

Not Applicable t

i-Comments should also include strong positive strengths that were demonstrated by player actions and response.

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,AL ACHMEN M

! (Continued)

Section M ,

1. Control Room (Simulator and Actual) 4.3*B.3

!!. Technical Support Center 4.3*B.5' ,

!!!. Operations Support Center 4.3 B 7 -

2 IV. Emergency Operations facility / Recovery Center 4.3 8.9 V. Site and Off Site Monitoring 4.3 B.12

VI. Security 4.3 B.13 l Vll. News Media Center 4.3 B.14 I

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1 ATTACHMENT B .

(Continued) i 1. CONTR01 ROOM 4 Ratino o

,Q,o,mmf,n,Lty, A. _Acci..ent Assessment /Emeroency Classification ,

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

2. Did the Control Room staff demonstrate the Yes/No aD111ty to coordinate the assessment of 4 plant conditions.and corrective actions with the Technical Support Center?

ll B. Notification and Communication

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

{ oublic address system?

2. Did the Control Room staff demonstrate the Yes/Nn i ability to notify federal and state authorities of emergency classifications in 3 accordance with established procedures?

3. Was informatior flow within the Control RoomL Yes/No

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

I

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

5. Were adequate emergency communication ies/No systems available in the Control Room to transmit data and-information to other

emergency. response facilities?

C. Activation and Response

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

Plan Implementing Procedures and did they a-follow them?

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Rev. 0 Page 4.3 B.4 ATfACHMENT B (Continued)

1. CONTROL ROOM i

j R.Lt itig Comments  ;

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j 2. Was the person in charge in the Control Room Yes'/No clearly identifiable and was good command and control taken at t.*e Control Room?

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j Rev. O j Page 4.3 B.S ATTACHMENT B (Continued)

II. TECHNICAL SilPPORT CENTFR

{ Ratina Comments q A. Accident Assessment /Emeroency Class 4fication 4

1. Did the TSC staff demonstrate the ability Yes/No to support the Control Room sta/f in

, identifying the-carse of the incident.

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

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

.i 3. Did the T3C staff demonstrate the ability Yes/No to initiate and coordinate corrective actions in an efficient and timely manner?

4 Did the TSC staft deronstrate the ability Yes/No ,

to direct and coordinate the taking of appropriate chemistry samples to analyze -

plant conditions? *

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

B. Notification and Communication

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

2. Was adequate record keeping of events. .

. Yes /lio ections, and communications documented and logged by the TSC staff?

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

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i ATTACRMENT B (Continued) 11, TECHNICAL SUPPORT CENTER

_Ratino Comments 4 Was information concerning plant Yes/No ,

conditions disseminated between the Control Room and TSC performed in a timely ,

, manner?

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

C. Activation and Resonnse

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 l checks of TSC and CR personnel performed?

4. Did the TSC Coordinator establish and Yes/No coordinate access control into the Protected Area and Cont: 01 Room? ,

1- 5. Did the TSC Coordinator demonstrate the _

Yes/No ability to maintain command and control of TSC emergency response activities?

6. Did the TSC keep other emergency response Yes/No i

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?

4 Controller / Observer Name:

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Rev. O I Page 4.3 B.7 ATTACHMENT B i (Continued) 111. SPIRA110NS SUPPORT CfNTER

,Retino Comments A. Notification and Communication ___, Yes/No

1. Was information flow within the OSC and i i to other eppropriate emergency response f acilities timely, complete, and accurate?

Was adequate record keeping of event?

2. Yes/No actions, and communications documented and logged by the OSC staff?

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

4. Were status boards utilized and Yes/No maintained to display pertinent accident information at the OSC? ,

B. Activation and Response

1. Did the OSC staff demonstrate the Yes/No

- ability to accivate and st6ff the OSC?

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

' ~

3. Were initial and-continuous Yes/No accountability 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_05C emergency response activities?

5. Did the OSC keep other emergency Yes/No response faciliti;s edvised of the stetus of their activities and information which they'had developed? -

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• ATTACHMENT B j (Continued) I 111. 0PERATIONS SUPPORT CENTER Ratino Comments j3 i Was the OSC organization and the

6. Yes/No

< initiation of activity efficient and

well organized?

- 7. Did the OSC staff demonstrate the Yet/No [

< ability to providt tdequate radiation ,

protection controls for on site

! emergency response personnel?

8. Did the OSC staff demonstrate tae Yes/No

! ability to monitor and t.ack radiation exposure of on site emergency response-personnel?

9. Did the OSC staff demonstrate the '

Yes/No ,

! ability to obtain and analyze appropriate chemistry samples as directed by the TSC?

10. Did the OSC staff demonstrate the Yes/No ability to initiate, brief.'und dispatch F

on site assistance tkams?

11. Were on-site assistance. teams able to Yes/No i trout?eshnot and evaluate problems with ple.nt equipment and systems?

! 12. Were there adequate administrative Yes/No a

controls and documentation taken to perform the necessary repairs of plant

equipment and systems during on r emergency situation? '

4 Controller /0bserver Name:

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IV. (MERGENCY OPERATIONS FACILITY / RECOVERY CENTER Reting Comments A. Notification and Communication i

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

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

i 3. Was adequate record keeping of events. Yes/No actions, and co'A.urications documented

and logged by the E0F/RC staff?

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

d l S. Were status boards utilizec and Yes/No maintained to display pertinent eccident information at the EOF /RC?

, B. Activation and Response

1. Did the EOF /RC staff Jemonstrate the Yes/No ability to activate and staff the EOF /RC?

2 '. Did the EOF /RC staff demonstrate the Yes/No

. ability to appropriately implement Emergency Plan implementing Procedures and did they follow them?

3. Did the Corporate Securi- .orce Yes/No establish access control into the EOF /RC?

4. .Did-the-EOF Coordindtor demonstrate the Yes/No ability to maintain commend and control of E0F emergency response activities?

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.j Edge 4.3 B.10 ATTACHMENT B (Continued)

IV. EMERGENCY OPERATIONS FAClllTY/ REC 0VERY CENTER

', . Retino Comments

5. Did the EOF /RC keep other emergency Y2s/No ,

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

I d 6. Were the EOF /RC organization and the Yes/No

, initiation of activity efficient and well organized?

3 7. Did the Site Recovery Manager Yes/No 4

demonstrate 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

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recovery phase?

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

C. Radiolooical Assessment i 1. Was information concerning radiological. Yes/No

and meteorological data obtained by appropriate EOF personnel in a timely

manner?

i- 2. Did the EOF staff demonstrate the Yes/No i ability to perform off site dose i assessment in acct <rdance with

, Procedure OP 3513i

3. Did the EOF staft demonstrate the . Yes/No ability to effectively track and define i

the plume utilizing the computerized dose-assessment model (HETPAC)?

-R15\128.

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i ATTACHMENT B ,

(Continued, IV. EMERGENCY OPERATIONS FACILITY /R,EC0VERY CENTER 3

_Ratino Comments i D. Protective Action Decision Makina ____ Yes/No l

1. Did the Radiological Assistant's staff 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 provide the necessary information to the Site Recovery Manager concerning protective action recommendations in accordance with Procedure OP 3511.

3. Did the Site Recovery Manager Yes/No demonstrate the ability to make +

protective action recommendations to off site authorities in accordance with Procedure OP 3511?

Controller /0bserver Name; >

R15\128.

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! ATTACHMENT B i (Continued)

V. $1TE AND OFF SITE MONITORING

, , Rating Comments

A. Activation and Response

1. Did on site and off site monitoring Yes/No teams demonstrate the ability to transmit information over the radio

utilizing proper units and terminology in accordance with Procedure OP 35107 l 2. Were on site and off site monitoring Yes/No i teams dispatched and deployed in a timely manner?

l 3. Were team members familiar with the-use Yes/No 2

of equipment, field monitoring procedurcs, and what was required of 4

them?

, 4. Were off site monitoring team: able to Yes/No l determine and communicate their location

{ in the field using appropriate maps and sample points (landmarks)?

I

5. Were off site monitoring teams briefed- , --Yes/No i on plant conditions and-changes?

4 s

Controller / Observer Name:

5-R15\128

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i ATTACHMENT B (Continued)

VI. SECURITY ,

Ratino Comments A. Activation and Response

1. Old the Security staff demonstrat: the Yes/No j ability to perform accountability of personnel within the Protected Area in j accordance with Procedure OP 3524?

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

3._ Did the Security staff demonstrate the Yes/No ability to appropriately implement

~

Emergency Plan implementing Procedures i

and did they follow them?

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ATTACHMENT B (Continued)

Vll. _ NEWS MEDIA CENTER j ,

Ratino Commenti i A. Activation en, Response f

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

i 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

• j information concerning the emergency.to the public and the news media?

t

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

I representatives? '

$- 6. Did the News Media staff demonstrate the Yes/No

{ ability to provide briefings for and to interface with the public and news media?

i i.

Controller / Observer-Name:

L R15\128  ;

it . - . - . -

Rev. O Page 4.3 C-1 ATTACHMENT C EmeroencY Exercise / Drill Observer's Evaluation Form

, Observer's Name: , Exercise /0 rill Date, Exercise / Drill

Title:

Observers Location:

Time Started: Time Ended' Observed: Pleyer Func"fi on Overall Performance and Obser.ations: (include the proper and effective use of procedures, equipment and personnel):

l Recognized Wea.;nesses and Deficiencies:

Comments and Recommendations (Specific):

NOTE:

Use additi 1a1 pages-as required.

Signature:

Title:

VY9Pf-3505.02 OP-3505, Rev. 15 Psge 1 of 1 R15\128

Rev. O j.; { Page 4.3-C 2 l-ATTACHMENT C (Continued)

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Continued on Additional Pages Yes No Signature:

Title:

Date:

, 1 R15\128 4

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VERMONT' YANKEE NUCLEAR POWER STATION, EMERGENCY RESPONSE PREPAREDNESS EXERCISE-4 1992 4

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. VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992

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5.) INITIAL CONDITIONS i i

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VERMONT YANKEE NUCLEAR F0WER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ,

1992 4

5.1 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).

'1. The reactor is now at approximately 100% power. The reactor has been operating steady state for the past six months with no recent shutdowns.

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

a. The "A" CRD pump has been removed from service and tagged out for repair.

4

b. Off gas system radiation levels have been increasing .over the last month. The 1.ast SJAE discharge release rate-for previous day was 32800 uCi/sec.

c. Reactor Engineering Department recommends limiting power changes to less than 1% CTP/ MIN due to the suspected fuel pin leskage.

3. Maintenance Department indicates that the "A" CRD pump will be returned to service within the next three hours.

4. -All other power generating and safety systems are operable.

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Rev. O i Page 5.1-2 1

! 4. The following on site meteorological conditions exist at 0815:

Wind Speed,-aph (lower / upper) - 3,0/2.8 Wind Direction, degrees (lower / upper) i 125/128 Delta Temperature, 'F (lower / upper) -0.8/ 1.1 Ambient temperature, 'F 57.6 l Precipitation; inches 0.00

5. F.egional Meteorological Forecast Information: ,

A weak hig' pressure ridge centered in the Gulf of Maine will remain stationary over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, A weak frontal houndary extending southwestward from a low centered over Hudson's Bay will drift slowly eastward. - Mostly sunny this morning. Temperatures-rising through the 60's. East to

outheast winds around 5 mph.

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l Table 5.1-1 Initial Plant and Reactor System Values ]

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Reactor Vessel Coolant Level 161 Inchec Reactor Pressure 1008 psig Reactor Coolant Temperature 527 "F Reactor Power .APRM (average) 100 %

! Core Plate D/P 18 psid 4 Total Core Flow 47 x 105 lbm/hr Main Steam Line Flow - Total 6.4 x 105 lbm/hr Main Steam Line Radiation 170 rR/hr Condenser Hotwell Level 61 %

Condenser Vacuum 2.! in..Hg(Abs)

Condensate Storage' Tank Level 50 %

Recire Drive Flow 30.3 Kgpm/ loop Feedwater Flow 6.4 x 105 lbm/hr Reactor Building D/P 1.62 in H 2O Drywell Pressure 17 psia Drywell Temperat:re 138 'F Torus k'ater Level 0.54 ft Torus Temperature 78 'F l

Drywell/ Torus 02 Concentration 1.27 %

High Range Containment Monitors 3.7 R/hr Containment Cas/Pa:ticulate 540/25107 cpm Reactor Building Vent Monitors Gas /Part 185/1481 cpm Reactor Building Vent Exhaust N/S 2 0/2.0 mR/hr Steam Jet Air Ejector (ARM) 61. mR/hr SJAE Discharge Rate 32,800 pCi/see Stack Gas I/II 150/200 cpm High Range Noble Gas Monitor

.1 mR/hr i

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R>v. 0 Page 3.1-4 VERMONT YANKEE DAILY STATUS REPORT -

2 THIS-IS A DRILL ',

1 DATE: SEPT 21992

. PLANT OPER/ TING STATUS '

VALUE DATE TIME -

,. 1. Core ThermalPower ( MWt)i(%) 1593 1 100% 0700

2. Gross MWe (MWe) 538 + 0700 3

3. Met MWe (MWe) 511 -0700 a- 4 Gross MWh for previous day (MWh) 12878 *

~

5. Core Flow (M%hr)l(%) 47 l 97.9 0700

.I

. REACTOR COOLANT SYSTEM 6 CondJetMiy (umho/cm)- .

09 9/1/92 0900

7. Urddent:fied Leakage @ nidnight previous day (DDm) O 41 2

S. Total Leakage @ midnight prevous day (gpm) 1.91 9 Gross Activtry (corn'ml) 202s00 9/1S2 0900 i 10. iodine 131 Dose Equivalent (uCvmi) 4 50E43 8'31/92 0900 s

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. STACK RELEASES -

1 11.- l articulate - (cupenod) 4 08E-03 8/31/92 1430

12. Average - (uCi/sec) 200 9 2'92 l 01 6 _

? 3. Peak (uCit:?) NONE 9/2/92 0115 14 Discharge Average Gamma Energy (Mev) 1.12 9/2S2 0115

I5. Dose Rate to Cntical Organs (mrerrvyear) 1.3 W31/92 1430

\16. lodine-131 (uCusec) 3 30E 05 8/31/92 1430 OFF GAS ANAL.YSIS i

a j 17. SJAE Dis Release Rate Measured / Estimated (ctrcle one) (uCvsec) 32800 9292 0115

! 18. SJAE Discharge Slope of Mixture -0.0686 22S2 0115

, 19.- Condenser Air Leakage (cfm) 13 3 9,292 0115 1

?:

LIQUID RELEASES & RIVER TEMPERATURE

20. Uquid Release (Ga!) NA-

21. Uauld Helease (Gross

Beta. Gamma) (uCuml; NA

22. Licuid Release (Tntium) (UCvmi) NA

~

23 Ocuid Re:sese (Dissolved Noble Gas) (uCVmh NA -

24. River Mon. #3 Highest Temp. for pregs cay (oF) 70 x 1830 4

BURNUP f.'

25 - Core Avg Burnup for previous day (MWD /ST) 16945 75

26. Core Cycle Burnt fgorevious day (MWD /ST) 6325 45 REVIEWER:

7 THIS IS A DRILL 1

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VERM0hT YANKEE NUCLEAR-POWER STATION EMERGENCY RESPONSC PREPAREDNESS ET.ERCISE-i 1992 1

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i-i - 5.2 NARRATIVE

SUMMARY

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Page 5.2 1 VERMONT YANREE NUCLEAR POWER STATION 1

EMERCENCY ?.ESPONSE PREPAREDNESS EXERCISE 1992 3

5.2 NARPATIVE SUMGRY

~

The scenario begins at 0815 with the simulator reactor running at approximately 100% power. The-reactor has been in a steady state for the

. last six months with no recent shutdowns. Night orders have informed the ' -

, operations crew that the "A" CRD pump has been removed from service and tagged out for repair. Maintenance has indicated that the "A"-CRD pump

, will return to ss.rvice within the next three hours. The off-gas system radiation levels have been increasing over the last month indicative of a small fuel pin leak. Reactor Engineering has recommended to limit power enanges to less than .1% per minute due to suspected fuel pin leakage'. All other power generating and safety systems are operable.

4 At 0830, the "B" CRD pump trips. Within several minutes, the control drive accumulator panalarms start to. alarm.- Upon recognition that two hydraulic control units- (HCU's) are inoperable and fall within a 9x9 array, the Shif t Supervisor should declare an UNUSUAL EVENT (approximately 0845). The UNUSUAL EVENT is based upon AP 3125, " Loss of Systems or' 1 Equipmant" (plant shutdown ' required in accordance with - LCO of Tech.

Specs.).

The Shift Supervisor should initiate the appropriate notifications concerning the declaration of the UNUSUAL EVENT and changing piant

< conditions. Plant personnel should be dispatched to investigate the

, problem on "B" CRD pump or expedite the-completion of repairs on "A' CRD

pump. Tech. Spec. 3.3.D requires an orderly shutdown be initiated ar.; the reactor to be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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At 0915, a main steam line high rsdiation signal isolates the Main Steam Isolation Valves (MSIVs). The reactor scrams, but four control rods fail to insert. The operating crew may request support from plant support (TSC or R&CE) about limitations caused by these control rods failing to insert.

1 To insert these rods, operators will have to go to the local HCU and vent

. the above pistons area of each rod (Miniscenario 7.2.1).

The Shift Supervfsor should initiate the appropriate nocifications about the reactor scram and changing plant conditions. The Control Room staff-also will initiate actions to stabilize the plant. This will include using the Safety Relief Valves (SRVs) with the torus as the heat sink to control reactor pressure. During this evolution, the operators will monitor torus temperature and level.

t At 0930, a primary system;1eak occurs. Drywell pressure and radiaticu levels start to increase,

Jy 0945, a high drywell pressure alarm is received that initiates a Primary Centainment Isolation of Groups 2, 3 and 4. Drywell sumps isolate on Group 2 isolation signal.

Coincident with the high drywell pressure signal. some automatic plant systems and equipment does not actuate. The "B" diesel generator does not start due to a clogged starting air filter (Miniscenario 7.2.2). One RHR

, pump (not being used for torus cooling) does not statt due to a circuit breaker problem (Minisconario 7.2.3).

At 1000, highl level alarms for the drywell equipment and drywell floor drain sump are received.

An ALERT should be declared (approximately ~ 1015) . based on AP 3125,

" Coolant 1r.ventory," (drywell pressure greater than or equal to 2.5 psig and both drywell sumps alarming at high level).

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, Following the AlIRT declaration, the Technical Support Center- (TSC),

Operations Support Center (OSC), and Emergency Operations

Facility /Recevery Center (EOF /RC) will be activated and staffed.

,, Notifications should be made to the appropriate personnel including the

- state and federal authorities, i

on -ite assistance _ teams should be requested to ird.stigate the problems ar.sociated with the' "B" diesel generator and the affected RHR pump.

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At 1030, the- torus pressure has reached greater than 4 psig and the

drywell radiation Icvel has reached 450 R/hr. The operators will consider -

spraying the torus to control pressure.

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- Reactor power reduction and _ pressure control will continue. Plant personnel complete activities to allow for contrcl rod insertion. Plant

personnel may be dispatcheo to look for the source of the drywell leakage.

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By 1100, the on-site assistance teams dispatched to the "B" diesel generator and the affected RHR pump will discover the problems associated

-1 with the starting air filter and circuit breaker, respectively.

By 1130, the . repair activities for the "B" diesel generator and the

affected RHR pump have been completed.

By 1145, Simulator Control Room indications show that plant conditions are stabilizing. Plant staff continue actions to stabib es the plant.

At 1200, the exercise viil be terminated.

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4 VERMONT-YANKEE NUCLEAR P0k'ER CIATION-a'

- Y- EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 *

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, VERMONT YANKEE NUCLEAR, POWER STATION +

), EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1992 5.3 SCENARIO TIME LINE CLOCK SCENARIO TIME TIME DESCRIPTION

, 0815 0:00 . < - Initial cond*tions established in the Simulator Control Room.

0830 0:15 < - "B" CRD Pump trips. Control Drive Accumulator _panalarms start to alarm.

0845 0:30 - < - }MUSUALIEVENTIIAR((312$ULOS5[0F[SYSTEMSIOR EQUIPMENT); - Plant thutdown required in accordance with LCO in Tech. Specs.

0900 0:43 -

l -

0915 1:00 . <--- Main Steam Line high' radiation signal isolates MJIV's. Reactor

, .- scrams. Four rods fail to scram (Miniscenario 7.2.1).

0930 1:15 - <--- Primary sys tam . leak occurs . Drywell pressure and radiation levels

- star to F. crease.

945 1:30 - <- - -

High Drywell-Pressure alarm occurs. Drywell sumps isolate.

- "B" diesel generator and RHR pump does not-start on high drywell pressure si 5aal (Miniscenario 7.2.2 and 7.2.3).

1000 1:45 - < -- Drywell equipment and-drywell floor drain sump high level alarms. .

1015 2:00 - <- ALERT;(K;M3125{PC00LANTJNVENTORD .- Drywell pressure it 2.5 psig.

and both drywell: pumps alarmiag at high level.

1030 2:15 - <--- Torus pressure >~4 psig and drywell radiation-levels at 450 R/hr.

Operators may spray torus-for pressure control.

-1045 2:30 . <--- Reactor power reduction and pressure control continues.

>1100 2.45 - <--- Teams discover problems.with "B" diesel generator' starting air.

-1 filter and RRR pump circuit breaker.

1115 3:00 -

1130; 3

13 <- - . "B" diesel Eenerator and tuut' pump repaired.

'1145. 3:30- - < -- Plant conditions are stabilizing. 'Flant staff continue actions to

~

stabilize plant.

1200 3:45 - <--- EXERCISE IS TERMINATED.

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VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE

.i 1992 . .i 1

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5,4 DETAILED SEOUENCE OF EVENTS a

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Rev, O Page 5.4 1-VERMONT YANKEE NUCLEAR POWER STATION-j EMERGENCY PESPONSE PREPAREDNESS EXERCISE '

1992 1.

5,4- DETAILED SEOUENCE OF EVENTS i

Clock Scenario Message Time Time Event /ActiED Information Prior.to EXPECTED CONTROL'R00M (CR) ACTIONS WILL BE 1 0815 00:00 IMPLEMENTED BY-AN EXERCISE OPERATIONS CREW (INCLUDING SUFFICIENT NUMBER OF PRESTACED

! INDIVIDUALS FROM THE VERMONT YANKEE EMERGENCY ORGANIZATION) = LOCATED IN THE

$ -SIMULATORLCOMPLEX IN THE CORPORATE TRAINING CENTER.

OPERATIONAL' CONTROL ROOM DATA WILL BE f PROVIDED BY THE SIMULATOR INSIRUMENTATION-RESPONSES. -IN CASES WHERE SPECAFIC

INFORMATION NOT MONITORED BY THE SIMULATOR IS REQUIRED, IT WILL BE ISSUE 3 BY CONTROLLERS /0BSERVERS ON MESSAGE. CARDS. IN THE EVENT THAT A SIMULATOR MALFUNCTION OCCURS, THE EXERCISE WILL BE CONDUCTED USING INFORMATION DEVELOPED FROM SECTION R,0 AND SECTION 9,0, l

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, The Simulator CR Controller issues-initial SCR/CR-M 1.

i conditions to the simulator CR players. SCR-C-1 j Guidelines for use of.uattronics and the plant evacuation alarm are provided to players, l

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i Clock Scenario .

Message Time Time Event / Action Informat(2D Prior to Initiating messages are also provided_to all ERF M 1 0815 00:00 emergency centers and facility staffs upon TSC H 1 (Cont'd) subsequent activations. - TSC communicators TSC M 2

, prestaged in the SCR, who normally respond i

to the CR, will be available for 4

communication and date tro.4 mission. ERFIS-terminals in the TSC and fuF will be linked to the SCR to-transmit operational and radiological scenario dota. Securi ty will

, be provided a list of Evaluators and i

nonparticipants v1.o will not have to be accounted for during the exercise.

0815 00:00 Simulator is put'into operation, j Reactor is at 100% power. The reactor-has ,

been cperating steady state for the past 6 months with no recent shutdowns.

Night orders have instructed the Operations crew that the "A" CRD pump has been removed from service and tagged out for' repair.

Maintenance has indicated that the "A" CRD

pump will be returned to service within the next 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Off-gas system radiation-a

{ 1evels have been increasing overrthe last month, indicative of a small fuel pin leak.

Reactor Engineering hus recommended to limit power changes to 1% per minute due-to the A-suspected fuel pin leakage.

1 0830 00:15 "B" CRD pu=p trips, Within several minutes, t -

Control Rod Drive accumulator Panalarms start to annunciate.

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Page 5.4 3

' Clock Scencrio Message Time Time Eve nt /Ac ti on _Informatien 0830. 00:15 Operators should recognize that two (Cont'd) hydr;ulte control units (HCUs) are  ;

inoperable and fall within a 9x9 array.  !

,i - Approx. Appiax. The Shif t Supervisor should declare an e 0845 00:30 UNUSUAL EVENT based upon the following EAL:

q AP 3125, "LC.iS OF SYSTEMS OR EQUIPMENT -

Plant shutdown reqaired in accordance with f LCO of Technical Specifications."

R The SS/ PED should initiate Procedure OP 3500, UNUSUAL EVENT and refer to Appendix '

u.e SJ/ PED checklist.

{ 1, l Operators should begin a controlled power reduction in accordance with Tech.

t Spec. 3.3.D l

Plant personnel should be dispatched to investigate the problem with the "B" CRD

, pump, or expedite _ repairs to the "A" pump, t .

4 FOR EXERCISE PURPOSES, EARLY IN STATION SCR-C-2 g ACTIONS MAY BE CONTROLLED AND PERFORMED BY 4

THE SIMULATOR CONTROLLERS.

The SS/ PED should announce the UNUSUAL EVENT i

over the Plant Paging System. This activity

will be performed by players in the l Simulator CR, and simultaneously performed by a Controller directed member of the operating shift crew in the actual Control Room.

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O Rev, 0 Page 5.4-4 Clock Scenario _ _ _Hessage Tiee Time , Event /Ac t i on Information

Approx, 00

30 The SS/ PED should notify Vermont New 0845 Hampshire, and Massachusetts C'. ate Police Agencies using.the Nuclear Alert System j (NAS, orange telephone) and provide the i

appropriate message to each_ agency.

, The SS/ PED should notify the NRC (PTS 2000

, ENS Phone) and maintain communications until relieved by the TSC.

+ ,

'The-Security Shift Supervisor snould implement Procedure OP-3531, "Emergercy 1

Call-?n Method," to notify the appropriate caetgency response personnel.

The Security Shift Supervisor should notify Yankee Nuclear Services Division- (YNSD)

Security and activate the YNSD Persont.el Group Paging System.

The Security Shift Supervisor should also SEC-C-1 notify New England Hydro Power Station of the UNUSUAL EVENT -THIS CALL UILL BE

SIMULATED.

The Primary and Secondary Duty and Call Officers (DCOs) should reportJto the plant af ter notification of the UNUSUAL EVENT Status.

The DCOs should contact the SS/ PED to be advised of the situation. Responsibilitj for TSC and EOF Coordinator assignments 4

would be discussed, as appropriate, i

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Page 5.4 5-Clock Scenario Message lige, Tirre Event / Action Information-Approx. 00:30' The TSC Coordinator should assume the 0845 overall supervision and coordination of the (Cont'd) on site emergency response activities.

This v'11 include escalating the emergency a classification as' conditions warrant.

Activation of the Technical Support Center:

(TSC) is optional at the UNUSUAL EVENT; 4

0900 00:45 IF AN UNUSUAL EVENT HAS NOT BEEN DECIARED BY SCR-C-3 THE SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS TIME.

0915 01:00 Simulator Operator inserts a main steam line high radiation signal, resulting-in a

reactor scram. In addition, the Simulator Operator inserts a malfunction where 4 control' rods do not insert as required by the automatic scram.

l As a result of the changing plant conditions, the SS/ PED should' initiate notitications to the appropriate agencies,-

and to plant personnel.

i The Control Room staff will initiate-activities in an attempt to stabiliae the plant, including insertion of the stuck rods by vsy of venting the piston in the 4- individual HCUs and cycling the SRVs to the torus'to control reactor pressure (refer to Miniscenario 7.2.1).

l j',

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-. ,,- ,-, - , - ..- ,- ,m o y w .-,4._,-. ~ , 9 3.. y7

Rev. O Page 5.4 6 Clock Scenario Message Tine Time __, Event / Action Information 0930 01:15 Simulator Ooerator inserts a primary system leck. Drywell pressure and radiation levels start to increase.

i Radiation Protection Technicians may be dispatched to perform dose rate surveys, air sampling and contamination surveys of the plant 0945 01:30 Drywell pressure has exceeded the high alarm setpoint, a Primary Containment Isolation Signal (PCIS) is initiated for Groups 2, 3 and 4 (the drywell sumps isolate under Group 2 isolation).

The "B" diesel generator did not start on

high drfwell pressure due to clogged starting air filter; (refer to Miniscenario 7.2.2).

One RHR pump (not being used for torus cooling) did not start on high drywell

-pressure due to a blown fuse in the' circuit breaker's charging motor circuit (refer to Miniscenario 7.2.3).

The SS/ PED should inform the TSC Coordinator about the problems with the="B" diesel generator and affected FUUt pump.

1000 01:45 The drywell floor drain and equipment sump levels exceed the high alarm setpoints.

4 Alarms are received in the Simulator Control l Room.

)

1 4

p y m , . . i.., y -e,<

73

Rev. O Page > '

Clock Scenario Message Time Tire Event /Ac t (gg l Informati.2D 1000 01:45 The TSC Coordinator and SS/ PED should review (Cont'd) the plant conditions against Procedure AP 3125 " Emergency Plat, Classification and Action Level Scheme '

i 1015 02:00 The SS/ PED or TSC Coordinator should dec'.are an ALEFT based upon the following EAL:

AP 3125, v001 ANT INVENTORY - Drywell Pressure greater than or equal to 2.5 psig, and both drywell sumps alarming at high leval "

The SS/ PED directs the operations staff to initiate Procedure OP 3501, " ALERT."

An ALERT announcement should be made over the plant page instructing emergency personnel to report to their assigned ,

emergency response facilities, and other personnel, contractors, and visitors report to the Covernor Hunt House Information Center and wait for further instructions.

At this time, the Technical Support Center (TSC), Operations Support Center (OSC), and the Emergency Operations Facility / Recovery Center (EOF /RC) should be activated and staffed.

The SS/ PED should notify the Vermont, New Hampshire, and Massachusetts State Police '

Agencies using the NAS of the escalation to

-the ALERT emergency classificatfon.

' A m p: . .. m

l Rev. 0:

1 Page 5.4 8 Clock Scenario Message.

Time Time Event /Actio.D Information t*

1015 02:00 The NRC should be notified of the escalation

(Cont'd) to the ALERT.

The Security Shift Supervisor should I

-i- initiate the emergency call-in method for

, the ALERT classification.

l The Security Shif t Supervisor should notify Yankee Nuclear Services Division (YNSD)

Security of the escalation to the ALERT status.

) Upon ALERT notification, the YNSD ESC-M-1 i

Engineering Support Center (ESC) is active ed, i

4 The Security Shift Supervisor should notify the New England Hydro Power Station in Vernon of the escalation to the ALERT status. THIS CALL k'ILL BE SIMULATED.

l The TSC Coordinator should notify REMVEC of

the ALERT status and plant conditions.

t- 1020 02:05 The Security Shift Supervisor should ensure

that an accountability of personnel has been i'

initiated in accordance with procedure OP 3524, " Emergency Actions to Ensure Accountability and Security Response."

j g The TSC Coordinator should respond, activate, and scaff the TSC in accordance

with Appendix III of OP.3501, " ALERT."

?

i

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

I Rev 0

, Page 5.4-9 Clock Scenario Message

^

i Tire Time Event / Action Information l

1020 02:05 TSC staff representing the following I 1

(Cont'd) departments should assemble at the TSC ,

1 following the declaration of an ALERTi i

1. Instrument and Control Supervisor i l, 2. Radiation Protection Supervisor or a designated alternate

3. Reactor and. computer Supervisor l 4. . Operations Supervisor

5. Maintenance Supervisor 3 6. Engineering Support Supervisor

7. CE Resident Engineer (as necessary)

8. Plant Services Supervisor

9. Other staff personnel to fulfill the functions of the TSC (i.e., Status Board Caretakers, Communicators, Switchboard Opefators, etc.).

The Emergency Operations Facility (EOF)

Coordinator should activate ahd staff the EOF /RC in accordance with Appendix IV of-OP-3501, " ALERT."

4 4

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o

. . . -_ e4 , se

Rev. O Page 5.4-10

, Clock Scenario Message

. Time Time Event / Action Information i _

1020 02:05 The emergency response staff that reports to EOF-M (Cont'd) the EOF /RC includes the following:

1. Site Recovery Manager and designated corporate staff i

2. EOF Coordinator

3. Purcha-ing Supervisor 4 Public Information Liaison

5. Additional trained plant staff members

, to assume the following tag board ta Ignments:

EOF Coordinator's Assistant

- Radiological Assistant Manpower and Planning Assistant Communications Assistant

- Radiological Coordinator Personnel and Equipment Monitoring Team l 6. Corporate Security Force The Operations Support Center (OSC) d:

Coordinator (assigned by the TSC Coordinator) should activate-and staff the OSC in accordance with Appe lix VII of OP 3501, " ALERT."

4 The Plant staff that reports to the OSC includes the following:

1. Radiation Protection'and Cnemistry Assistants and Technicians

2. Control-Instrument Specialists

3. Maintenance Staff

4. Status Board Caretaker

5. Other personnel as- required.

l

. , i l

W

,_ _, _ w - Py y --- - T

Rev. O Page;5.4 11 Clock Scenario Message ,

Time Time Eyent/Actiga Information 1020 02:05 The Site Recovery Manager (SRM) and staff (Cont'd) should report to the EOF /RC and implement the procedural steps listed in Appendix VIII of OP 3501, " ALERT."

1030 02

15 Torus pressure has exceeded 4 psig and

.drywell radiation level has reached 450 R/hr. Operators may consider spraying the torus to control pressure.

IF AN ALERT HAS NOT BEEN DECLARE'D BY THE SCR-C-4 SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS TIME.

SCR operators will continue to stabilize the plant. This may include activities to allow i

control rod insertion, reactor power reduction and pressure control. Plant personnel may be dispatched to determine the source of_the drywell leakage.

The ESC should be assisting at this time in technical problem solving. In addition, the ESC meteorologist should be providing a-

,. weather forecast for the VY site, t

1045 02:30 The EOF Dose Assessment Personnel should be doing radiological off-site consequence assessments, based upon potential-containment failure, ,

Rey, O Page 5.4 12 Clock Scenario Message j i Tine Time Fvent/ Action Information 5 1100 02:45 On-site assistance teams dispatched to the "B" diesel generator and the affected RHR pump will discover the problems associated with the starting air filter and circuit breaker, respectively. The teams should

. discuss actions to initiate necessary repairs.

The ESC has reviewed the latest NWS forecast ESC M-2 and has updated meteorological information for the site.

l An updated weather forecast is available EOF M-2 .

from the NVS.

1130 03:15 . Repair activities for the "B" diesel

. generator and the-affected RER pump have been completed, The "B" diesel generator and the affected RHR pump are returned back i

to operational status.

4. -

l 1145 3:30 Simulator Control Room indications show that t

plant conditions are stabilizing. Plant staff continue actions to stabilize the plant.

1200 03:45 The exercise is terminated,

i ;- ,

VERMONT YANKEE NUCLEAR POWER STATION

+

EMERGENCY RESPONSE PREPAREDNESS EXERCISE' 1992 4

id l

6.0 EXERCISE MESSAGES -

2 I.

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-l VERMONT YAlmEE NUCLEAR POWER STATION-TMERCENCY RESPONSE PREPAREsNESS EXERCISE k

1992 4

i I

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6.1 COMMND CARDS l

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i

.l Rev. O Page 6.1 1 VERMONT YANKEE NUCLEAR POWER STATION EMERCDiCY RESPONSE PREPAREDNESS EXERCISE I 1992 SCENARIP COW'AND CARD  !

8-FROM: Simulator CR Controller COMMAND h0.2 SCR C 1 4 TO: Shift Sunervieor C14CK TIME: Prior to 0815 l

l 14 CATION: Simulator Control Room SCCUARIO TIME: Prior to 00:00 -

0 l *******************************d******A**********wt***************************

l THIS'IS A DRI1.L l_ DO NOT initiate cny actions affecting normal plant operations.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • S******************************************

i Communications systems that are available in the control Room have been

duplicated in the Simulator Lontrol Room (SCR) EXCEPT for CAITRONICS.and the PIANT EVACUATION ALARM.

l Please use the GAITRONICS/ PLANT EVACUATION ALAPJi in the SCR to complete the

' required FA announcements. An Exercise controller will then drect a memb1r af the shif t operations crev 4: the plant to repeat the announcemenes from the Main

Control Room.

i' A

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• • • • • • • • • • • • • • • • • • /:****************kt*****************************************

THIS IS A DRILL

{

• • • • • • w*****d*****************************************************************

l 4

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Rev. O Page 6.1 2 VERHONT YANKEE NUCLEAR P0k'ER STATJON EMERCENCY RESlUNSE PREPAREDNESS EXERCISE

1992 i

) SCENARIO COMMAh'D CARD f

i FROH: Shift CR Controller COMMAND NO.: SCR C 2 TO: Shift surervisor CISCK TI!!E: 0845 1

! IhCATION: Simulator control Room SCENARIO TIME: 00t30 l

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • r***********************************t,4*****  ;

THIS !S A DRILL DO NOT initiate any actions affecting normal plant operations. l 1

4

• • • • • • • - r********************************************************************

i

Early in station netions will be simulated and information requested at this t';

i- will be provided by controllers. ,

i I

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i-T 4

t' I -

-THIS IS A DRILL l

t J

j Rov. 0 Page 6.1 3 VERMONT YANKEE NUCLEAR Pok'ER STATIOli EMERGENCY RESPONSE PREPAREDNESS EXERCISE ,

4 1992

$fENAR10 COMM'D CARD 1 ,

4 J.

TROM: Security Controller . COMMAND NO.: SEC C 1

TO

1.ceurity supervisor _

CLOCK TIME: 0845 or when needed

[ LOCATION: Security Catehoure_, _ _ ., SCENARIO TIME: 00:30

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +**********************

Tills IS A DRILL

} D0.UOT initiate any actiot.s affecting normal plant operations.

r FOR EXERCISE PURPOSES, communications with New England 11ydro Power Station in j Vernon vill be simulated.

i s

f i

i 4 3 s THIS IS A DRILL

) e

. - . . . . .._ . . r.,_.. , , , - . . ._ . , . . , . . , ~ _ . _ . ,. . . . , . , . . , _ , , . . ~ . _ . .. .-m ,_, . , , .

Rev. O Page 6.1 4 VERMONT YAlMEE NUCLEAR POWER STATION ,

EMERCC!!CY RESPONSE .*REPAREDNESS EXERCISE I 1992 SCENARIO COMMAND CARD FROM: Sitrulator CR Controller COMMAND NO.:- 12.C.3 To: Shife Su srvirer CI4CK TIME: 0900 LOCATION: Simulator Control Room SCENARIO TIME: 00:45 ,

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • t**************************************

Tills IS A DRILL Do NOT initiate any actions affecting nornal. plant operations.

• • • J*********************************v*********,******************************

DECIARE AN UfMSUAL EVENT BASED UPON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT .

Plant shutdown required in accordance with LCO of Technical Specifications".

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• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • r************w**************

THIS IS A DRILL l

Rev. 0

, Pag,e 6.1 5 VEPJ10NT YAlu:EE NUCLEAR PWER STATION j DIERCENCY RESPONSE PREPAREDNEST EXERCISE l* 1992

! SCENARIO COMMAND CARD l

}

. PROM: Simulator CR Controller COMMAND NO.: SCR-C 4

i 70

Shift Sutservisor/PCD C14CV. TIME: 1030 i

Simulator Control Room LOCATION: SCENARIO TIME: 22:15 4

l **********************w***************************************************.t***

! THIS IS A DRILL i

DQ,,HQI initiate any actions affecting normal plant operations.

• • • • • • • • • • • • • • • • • • • • • • • • • • m**********************************************kd***

DECIARE AN ALERT BASED UPON AP 3125, "C001MT INVENTORY - Drywell Pressure greater than or equal to 2.5. psig, and both drywell sumps alarming at high level."

THIS IS A DRILL

[ ************************************************************************'******

I t

i I i, VERHONT YANKEE NUCLEAR POVER STATION ,

EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1992 [

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Rev. O i Page 6.2 1 ,

VERMONT YA!D'EE NUCLEAR PO'n'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE

$. 1992 6 SCENARIO MESSAGE CARD i

i FROM: t'ontroller MESSAGE NO.: SCR/CR M 1

' Shif: Supervisor /DC0 TO: CLOCK TIME: Start of Drill LOCATION: CR/Sim CR SCENARIO TIIC: frior to 00!00

• k****************************************k***********************************

THIS IS A DRILL pal.2I J initiate any actions affecting normal plant operations.

For initial conditions, see attached pages, i

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4 4

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• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • . 1

THIS IS A DRILL 4 ************************w**********************************w******************

i

~ - - - - - -

w

4 j Rev. 0 Page 1 of 4

VERMONT YANKEE NUCLEAR POWER STATION

i EMERGENCY RESPONSE PREPAREDNESS EXERCISE

!i .

ECQiARIO MESSACE CARD [

INITIAL CONDITIONS

1. The reactor is now at approximately 1006 power. The reactor has been i operatinF steady state for the past six months with no recent t I shutdowns.

4

- 2. Night Orders for the operations crew provides the following

information

1 1

i

a. The "A" CRD pump has been removed from service and tagged oat for repair. ,

i b. Off gas system radiation levels have been increasing over the last  ;

4 month. The last SJAE discharge release rate for the previous day was 32,800 pCi/sec.

! c. Reactor Engineering Department recommends limiting power changes to l 1ess than~16 CTP/ minute due to the suspected fuel pin leakage.

3. Maintenance Department indicates the "A" CRD pump will be returned to service within the next 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

l l 4. All other power generat.og and safety systems equipment are operable. 4 l

1 l

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • w***********************************

THIS-IS A drill j *****************************t************************************************

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4 Rev. 0 ,

< q,e 2 of'4

! VERMONT YANKEE NUCLEAR PO'.'ER STATION 4

EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 fCENAR10 MESSACE CARC i i

4. The following on site meteorological conditions exist at 0815:

Wind Speed, mph (lower / upper) 3.0/2.8 l Wind Direction, degrees (lower / upper) 125/128 Delta Temperar are, 'F (lower / upper) 0.8/-1.1 Ambient Temperature, *F 57.6

}

, Precipitation, inches 0.00

5. Regional Heteorological Forecast Information:

A weak high pressure area ridge centered in the Gulf .of Maine will remain nearly stationary over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A weak frontal boundary extending southwestward from a Icv centered over Hudson's Bay I

will delft eastward slowly, c

Mostly sunny this morning. Temperatures rising through the 60's. East to southeast winds around S MPH.

T'

• • • • AV********************************************ggggggggggggggggggggggggggg, .]

THIS IS A DRILL

• • • • • • • • • • • • • • • • • • • • • • • • 1. ,,********************************* m ********** m ***

Rev. 0 e

Page 3 of 4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE

, 1992 i .

SCENARIO MF; SAGE CARD j i i Initial Pinnt and Reactor System Values j 4

j i

- Reactor Vessel Coolant Level 161 Inches  !

Reactor Pressure 1008 psig l

Reactor Coolant Temperature 527 'F Reactor Power APRM (average) 100 t Core Plate D/P 18 psid i Total Core Flow 47 x 10^ lbm/hr Main Steam Line Flow - Total 6.4 x 10' lbm/hr Main Steam Line Radiation 175 mR/hr

! Condenser Hotwell Level 61 %

Condenser Vacuum 2.7 ia, lig(Abs) 4 Condensate Storage Tank Level _ 50 t Recire Drive Flow 30. 5 l'.gpm/ loop l Feedwater Flow 6.4 x ' O' lbm/hr

Reactor Building D/P -1. 62 in ll:0 Dryvell Pressure 17 psia >

Drywell Tempernture 138 'F 4

Torus Water Level 0.54 ft Torus Temperature 78 'F Drywell/ Torus 0, Concentration 1.27 %

~ High Range Containment Monitors 3.7'R/hr Containment Gas / Particulate 540/25107 cpm Reactor Building Vent Monitors Gas /Part 185/1481 cpm

Reactor Building Vent Exhaust N/S 2/2 mR/hr Steam Jet Air Ejector (ARM) 61 mR/hr SJAE Discharge Rate 32,800 pCi/see Stack Gas I/II 150/200 cpm i High Range Noble Gas Monitor v.1 mR/hr 4

+

****4***********************************&*******'k***************************** -

THIS IS A DRILL

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • A****************************t4********kw*

w= i-v -+

3 w , *

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>-. g , r~. f ,e ,--e, e -p, 6 g- ., . - - -

Rev. 0

, P40* 4 of 4 VERMONT YANKEE DAILY STATUS REPORT j

THIS IS A DRILL DATE: SEPT tur PLANT OPERATING STATUS

~

VALUE DATE TIME

1. Co's Thermal Power ( MWt)l(0 1593 1 100% 0700

2. Gross MWe (MWe) 538 0700

3. Not MWe (MWe) 511 +

0700

4. 7 toss MWh for prevcus day (MWh) 12878 e- m a E ore Flow (Mibhr) l (%) 47 t 97.9 l 0700 REACTOR COOLANT SYSTEM 6 Conduettvey (umho/cm) 09 9/1/92 0900

7. Unadentfied Leakage @ rrganight previous day - (gpm) 0 41 m

6. - Total Leakage @ midnig*it pronous day (gpm) 1 91 9 Gross ActMty (cpm /mh 202500 9/1/92 0900

10. todine-13) Dose Ecutvaient (uCvm0 ( 50E-03 &'31/92 0900-(

STACK RELEA?ES-

11. Padscutate (Noemd) 4 OBE43 W31rJ2 1430-

12. Average (uCvsec) 200 E292 0115-

13. Peak (uCVsec) -NONE B'2/92 0115 id Drscharge Average Gamma Energy (Mev) 1.12 -B292 0115 15 Dose Rate to Critest Organs (mrerWyear) 1.3 W31/92 1430 11 6. IC$ne-131 (uCvsec) 3 30E 05 6'31/92 1430

, OFF GAS /M.

17. SJAE Dis Release Rate Measured / Estimated (circle one) (ucksec)l 32800 9292 0115 18 SJAE Discharge Slope of M4ure '

4 0686 h292 - 0115

19. Condenser Air Leakage - (cfm) 13 3 E292 0115 LIQUID RELEASES & RIVER TEMPERATURE i 1

20. Uquid Release (Ga0 NA

21. Uguid f<elease (Gross : Beta. Gamma) (uCVm0 NA

22. MQuid Release (Tritum) (uCumb NA- __.

23. Liould Release (Dissolved Noble Gas) (uCvmb NA-

54. River Mon. 83 Highest Temp. for previous day (oF) 70 , 1830

-BURNUP. -

25. Core Avg Bumupforprevious day (MWD!$T) 16945 75

26. Core Cycle Bumup for prevous cay (MWD /ST) 6325 45 4

REVIEWER:

THIS IS A DRILL i

n - o _________.____.z_._.m_ ____..mJ

2 Rev. O VERMONT YANKEE NUCLEAR POWER STATION

EMERGENCY RESPONSE PREPAREDNESS EXERCISE li42 4

LQENARIO MESSAGE CARD i

• FROM: Psellity Controller MESSAGE NO.: ERF-M 1

( TO: Facility Coordinator CLOCK TIME: Start pf Drill or 14 CATION: Various ERFs SCENARIO TIME: Facility Activation l

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • s*******

THTS IS A DRILL .4 DO NOT initiate any action affecting normal plant operations.

i ****************************************************************************** l 1

For initial conditions, see attached pages. i i

l 6

s J

• • • • • • • • • • • • • • • • • • • • • • • • • • • w************************************************g*

THIS'IS A-DRILL d

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • w.t*******e************************************

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Rev. 0

' Page 1 of 2 VERMONT YANKEE NUCLEAR POWER STATION.

DiERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 SCENARIO MESSAGE CAFJ VERMONT YANKEE  ;

DAILY OPERATIONS REPORT SEPTEMBER 2, 1992 l

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

PLANT STATUS: 100% POWER GEN GROSS 538 MWE OFFCAS 32,800 uCI/sec PLANT OPERATION

SUMMARY

& SIGNIFICANT EVENTGt

• THE PLANT HAS BEEN OPERATING FOR 6 MONTES WITH NO RECENT SHUTDOWNS. CONTINUED FULL POWER OPS.- "A" CRD PUMP IS - - OUT - OF:

SERVICE AND TAGGED OUT FOR REPAIR. OFF-GAS-RAD LEVELS ELEVATED.

SOME MINOR FUEL PIN LEAKAGE.

=========================== .. =================o===

SIGNIFICANT NEW WOR 3

.# DESCRIPTION DEPT PRIORITY NONE

e=ra==================================================

TECH SPEC /LCO-~ EQUIPMENT OUT OF.BERVICE SYSTEM / COMPONENT TECH SPEC DATE/ TIME ALLOWABLE TIME.

-"A" CRD' PUMP

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

STATUS / COMMENTS CN. MAJOR WORK IN PROGRESS l

• MAINTENANCE PERFORMING REPAIRS TO "A" CRD PUMP.

1

" A'? CRD PUMP

!

• TO BE BACE IN SERVICE LATER THIS-MORNING-(1130).

RE INSTRUCTIONS TO . LIMIT POWER - CHANGES . TO '. LESS THAN 14: PER-l MIMITE DUE TO SUSPECTED FUEL PIN LEAL (AGE.

-..r.=========n=========================:----================

PRC'8/ NOTIFICATIONS:

_ NONE

, =================,-=================----============================

h LONG TERM-PROBLEMS. SOLVED I

NONE

---

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

i

(:

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • k*******

i j THIS IS A DRILL t;

• • • • • • • • • +***************************************************************.*****

I I

l t

Rev. O Page 2 of 2 VERMONT YANKEE DA!LY STATUS REPORT THIS IS A DPTI.L DATE: SEPT 21992 PJANT OPERATING STATUS VALUE DATE TIME

1. Core The mal Pcwer ( MWt)1(E 15931100% 0700 2 Gross MWe (MWej 'M O'r00 3 Net MWe (VWei 511 0700

' 4. Gross MWh for previcras day (MWh) 12878 5 Core F6ow (Metr)l(% 474979 __

0700 REACTOR COOLA_f1T.JJSTEM 0.Condued/ (umhsem; 09 9/1/92 0900

7. Unidentfed Leakage @ midnig5t pre.taas cay (ppm) 0 di

8. Totat Leakspe C midneg51 previous day (gom; e 91 9 Gross Aetray (con.*1; 202500 9/1N2 0900 10 lodine 131 D se Eouivalent (uc 4 50E43 6'31/92 OWO STACK PELEASES

11. Pa'ticulge (cupenod 408 43 &*31N2 1430

12. Average (uCusec) 200 9.292 0115 13 Peak (uCusec) NONE k2'92 011b l14 Discharge Aarap Camma Ener;v (Mev) 1.12 9'.192 0115

'15. Dese Rate to Cnical organs (mrenvyear) 1.3 &'31/P2 1430 i 16 lo$ne-131 (uCise 3.M E-05 63142 1430 OFF-GAS ANALYSIS

17. SJAE Dis Reieaw Rate Measured / Estimated (circle one) (uCusec) 32600 9292 0115 18 SJAE Discha*ge slope of M:sture

_ -0 0666 9292 0115 19 Condenser Air Leakspe (cfm; 13 3 9292 0115 LIQUID RELEASES & RIVER TEMPERATURE c 20 Lsquid tie ease '

(Gah NA

21. Uquid Reeste (Gross : Beta. Gamma) (uC6ml) NA 22 Liquid Ra' .ease (Tn:ium) (i C6mh NA 23 Lmund Release (Dissolved Norde Gas) (uCvml> NA 24 Rrver Mon #3 Hghest lemp for previous day (oF) 70 1630 EURNUP

25. Core Avg Bumup for previous day (MWD /ST) 1CG45 75 26 Core Cyck Bumup for previous day (MND/ST) 6325 45 REVIEWER: .

THIS IS A DRILL

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ---J

Rev. O i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 SCENARIO MESSAGE CARD i

FROM: ISSL,, controller MESSAGE NO.: TSC-M 1 TO: ISf._C m dinator . CLOCK TIME: Uoon assirnment of.

Data Pg.gorder LOCATION: TSC _ SCENARIO TIME:

• • • • • • • • • • o*************************************************************+*****

. THIS IS A DR1LL DO NOT initiate any. actions affecting normal plant operations.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • r*****************************

4 To obtain plant computer parameters that are normally available to TSC staff, use the Controller / Observer telephone . in the Planc Computer Room to request the information frotn the Simulator Computer Room.

I l

l

• • • • v*****************w****************************v**************************

THIS IS A DRILL

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • (,*********************************

I

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

1 l

1 l

Acv 0 3 Page 6.2 10 i

/ VERH0h"*' YANKEE NUCLEAR Pok'ER STATION )

EMERCD;CY RESPONSE PREPAREDNESS EXERCISE 1992

$CENARIO MESSACE CARD )

l l

l FROM: TSC Controller MESCACE NO.: ISC-M 7 l l

TO: Ilg, Coordinator CLOCK TIME: ifron_ar*lenment of -

femunicators LOCATION: TSC SCENARIO TIME' THIS IS A DRILL 4 DO NOT initiate any actions affecting normal plant operations. i 1

• • • • • +********,***********************************w**************,*ww**i.-***** >

After assigning your TSC Communicators to the Control Room, the prestaged *;SC

, Communicuors at the Simulator Control Room will be made available.

i

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F A g f' fkgf ff i

THIS IS A DRILL I

• • • • • • • • • k************************************&Attgggggggggggw*gggggggggggggg, G-l'

i. '

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

\

Rev. 0 l, Page 6.2 11 VERMONT YANKEE NUOLEAR P0k'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 SCENARIO MESSACE CARD 3

FROM: ESC Controller MESSAGE NO.: ESC-M-1 TO: ESC Meteorologier CLOCK TIME: 1015 LOCATION: SSC SCENARIO TIME: 0.2.LQ9__.,

t ************************************w*****************************************

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

l ******************************************************************************

,_ Utilize the attached meteorological information to generat.e the weather forecast for the Vermont Yankee site. .

t 1

THIS IS A DRILL i

1

-. -~ . . . . _ . . - , - . - . , . - - . . - , , _ . . , . -. .. ._, ~.~,_ < ..

Rev. 0

{ ~

Page 6.2 12 VERMONT YANKEE NUCLFAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 SCENARIO MESSAGE CARD Date of Forecast: 09-02 92 Time of Forecast: 10:15 i Current Site Meteorology (as of 09 00 ):

Iir._t Seneor Eini Mind D.t.Lt a Stab Preein.

Speed Direction Temperature Class i Lower 2.8 109 DEG 0.9 DEG F D 3 MPH FROM Upper 2.9 129 DEG 1.2 DEG F D 0 IN/15 MPH TROM MIN

, r m- ,

Forecast Site Meteorology:

4 Ilg.g Sensor Hind H.ind Delta Stab. f re c in'.

Speed Direction Temnerature ClILM

, 09:00 Lower 5.0 110 DEG -1.4 DEG F C MPH FROM

11:00 Upper 6.0 120 DEG 1.8 DEG-F D 0 IN/15 I

l MPH FROM MIN 11:00 Lower 6.0 120 DEG -1,6 DEG F B MPH FROM 13:00 Upper 8.0 130 DEG -1.9 DEG F D 0 IN/15 MPH FROM MIN 1

l 13:00 Lower 7.0 160 DEG 1.3 DEG F D MPH FROM 15:00 Upper 10.0 160 DEG 1'.9 DEG F D 0 IN/15 MPH FROM MIN s

-**************************************************+***************************

, THIS IS A DRILL

, ************************************.'1****************************************

i

. - ,a..,,,...-.n-,--.-. . - , . , , , - . . - - - , - , , --n., - . . - . - . , . - n. - -- -

I i

s Rev. 0 1

i Page 6.2 13 VERMONT YANKEE NUCLEAR POWER STATION

! EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992

$ JCENARIO MESSAGE CARD 4i

) National Weather Service Fotecast for site region: i l l 5

Mostly tunny this morning. Temperatures rising through the 60's. East to i -Southeast vinds around 5 MPit. i f

Special Weather Statements:

1 i NONE

)

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• • • • • • • • • • • Ai*****************************************************************

THIS IS A DRILL

't l

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

1 Rev. 0 .

Page 6.2 14 VEPMONT YANKEE !GCLEAR PO'n'ER STATION EMERC.,..Y KESPONSE PREPAREDNESS EXERCISE 1992 l SCENARIO MESSACE CARD i

j l' ROM: EOF /P.A Controller MESSAGE NO.: EOF.M-1 A

TO: Radiolorical Assistant CLOCK T4ME: 1020 or as recue,glgj LOCATION: EOF / Dose Assessment Aren ,,,,, SCENARIO TIME:

! *****************************************************************+************

! THIS IS A DRILL LO NOT initiata any actions affecting normal plant operations,

]- ********2********************************** a*********************.***********

07:00 11:00 - General Area Forecast .

1 9 Mostly sunny this morning. Temperatures- rising through the 60's. East to i southeast vinds around 5 MPH.

4 7

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• • • • ..***************************k********************************&************

THIS IS A' DRILL

• • • • • • • • • • • • • • • • • • • • • • • a i*****************************************++#*********

l 4

.w- , , - , . -w r , - . .- -

, - - , , . . . , - ..~y--,, .r-y , w .- . , , , - - - - , - - - , ., r

Rev. O VERMONT YANKEE NUCLEAR PO'n'ER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1992 SCENARIO MESSAGE CARD FROM: ESC controller MESSAGE NO.: ESC M 2 _

TO: {SC Meteorolorist CthCK TIME: 1100 or my reauested LOCATION: ESC SCENARIO TIME: 02?45 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.

Utilize the attached meteorological informatien tt. generate the weather forecast.

for +,he Vermont Yankee site, i

THIS IS A DRILL

4 Rev. 0

)(

4 VEPJt0NT YANKEE NUCLEAR POWER STATION Page 6.2 16 i

EMERGENCY RESPONSE FREPAREDNESS EXERCISE

, 1992 SCENARIO MESCAGE CAFD Date of Forecast: 09 02-92 Time of Forecast: 11:00 Current Site Meteorology (as of 11 00 ):

lin Sensor Hig EiDA Dalt! 21 Precio.

Speed Direction Ign eraturg Clan Lower 5.9 084 DEG 2.0 DEG F A MPH FROM i Upper 5.4 120 DEG 2.5 DEC F B 0 IN/15 i

MPH. FROM MIN J

Forecast Site Meteorology:

lin Sensor RIM Wind .

Delta Stab. Freelo.

l Speed Direction Irnoerature Class 11:00 Lower 6.0 120 DEG -1,6 ./EG F B MPH FROM

. 13:00 Upper 8.0 130 DEG- -1.9 DEG F D 0 IN/15 MPH FROM MIN 4 -

13:00 Lower 7.0 160 DEG 1.3 DEC F D

- MPH FROM

} Upper 10.0 160 DEG 1,9 DEG F D 0 IN/15 MPH _

FRCM  !!IN j i 15:00 Lower 6.0 180 DEG 0.7 DEG F D MPH FROM 17:00 Upper 9.0 180 DEG 1.3 DEG F D 0 IN/15 MPH FROM MIN

• • • • • • • • • • • • • • • • • • 4*********************************s*************************

g THIS IS A DRILL

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • o*************************#4

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

5 i

Rev. O I l; Page 6.2-17 .

VERMON1 YANKEE UUCLEAR PO'.'ER STATION I 1 EMERGENCY RESPO!SE PREPAREDNESS EXERCISE -

1992 I i

SCENARIO MESSACE-CARD

{

I r

l l National Weather Service Forecast for site region:

1

! Mestly sunny and varm this afternoon. High temperatures in the upper 70's . .

South to southeast vinds 5 10'HPH. l l

Special Weather Statements: j None l Y

4 l

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- Th1S IS A DRILL .

1 1

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

Rev. O i{ Page 6.2 18 VEPEONT YANKEE NUCLEAR POWER STATION

• EMERGENCY RESPONSE PREPAREDNESS EXERCISE -

1992 P

TdfSARIO.MESSACE CABD s

B s FROM: EOF /RA Controller MESSAGE NO.: EOF M-2 4

TO: Radfological Assistant CLOCK TIME: 1100 or as reouested 1

IDCATION: EOF / Dose Assessirent Area SCENARIO TIME: 02:45

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • d********************

THIS IS A DRILL

DO NOT initiate any actions affecting normal plant operations.

11:00 17:00 - General Area Forecast National Weather Service Forecast for site region:

dostly sunny and warrn tnis afternoon. High temperatures'in the upper 70's. ,

South to southeast winds 5 to 10 MPH.

Special Weather Statements:

None 4

4 0

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• • • • • • • • • • • • • • • • '*************************kf-ity************k******************

3 f, THIS IS A DRILL 4

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1 VERMONT YANKEE NUCLEAR PO'n'ER STATION ~

i 5

ENERGENCY RESPONSE PREPAREDNESS EXERCISE

1992 4

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7.0 STATION EVENT DATA 3-4 e

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l' VEPJiONT YANKEE NUCLEAR PO'JER STATION

} i i

EMERGENCY RESPONSE PREPAREDNESS EXERCISE i

! 1992 i i2 4

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, 7.1 EVENTS

SUMMARY

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Page 7.1 1 VERMONT YANKEE NUC1. EAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 *

! i 1 l

,. 7.1 EVENTS

SUMMARY

l r

i 4

The following information and supplementary material are provided for those i

evaluators having in plant control assignmants so as to further ensura the proper 4 development of the scenario. The information provided in this section assumes-that the " players" who are dispatched to. perform repair, rescue, or other

] activities, will take certain actions in response to the scenario. The evaluator i must be cognizant of the actions of those players to which assignmente are given i

and provide information regarding the results of tha players' actions, as j appropriate. The information p 'vided in this section does not preclude the j possibility that the evaluator will be required to provide additional information to the players. >

Approximate j Miniscenario ligt Event Location Initiation i 7.2.1 0715' Control Rod Reactor- OSC

< Venting of Building Controller i

HCU Pistons '

i. 7.2.2 0945 "

B" Diesel "B" Diesel Simulator Generator Generator Room Response 4

Failure 4

4 7.2.3 0945 PJIR Pump; _Svitchgear Simulator 4

Inspection and Room and Response Breaker Reactor Bldg-2 Failure (RHR Pump Corner Rm.)

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-,,,,,.4,,,,ww.y ,,g,p.e,w,+, w,-4,w- , w r -yr-c.q,-yy~m.-,,

~

VERMONT YANKEE 1;UCLEAR POWER CTATION EMERGENCY RESPONSE PREPARELtiESS EXFRCISE 1992 4

.9

.h

, 7 2 , M HlFI SCENARIOS 2

9 s

i l

Rev 0 -

}- Page 7.2.1-1 VEPE NT YANKEL NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISF 1992 7.2,1 Miniscenario - Control R9d Ventine of HCU Pistons I

I. Generai Descriotion At approximately 0915, a main steam line high radiation condition occurs resulting in an isolation signal being sent to the Main Steam Isolation-

] Valves (MSIVs). When the MSIVs trip, a reactor scram signal _ is generated by the Reactor Protection System (RPS). When~ the scram occurs, four control rods fail to insert to the 00 position. -The_SCR Opera; ors will attempt to insert the individual rods from the Reactor Contrs Par.el in the SCR. All operator attempts to insert these rods 4

will fail. The operators should initiate activities to manually . insert i

the rodt using the over piston vent procedure, from. the individual >

Hydraulic Control Unit (HCU), using reactor pressure as the driving uedium.

II, Descriution of Player Responses / Observations / Corrective Actions The Shif t Super /isor should dispatch Auxiliary Operators (A0s) to the 4 vent-over piston crea for each of the affected control rods. The A0s should assemble the necessary tools and equipment for this procedure, obtain a Ftiefing from the SS/ PED and proceed to the first control to- .

be vented. When the A0s arrive at the designated location, they. should establish communications with the SCR and. proceed with the evolution.

III. Event Closcout This event will be closed out when the A0s inform the SCR that they are b

in the process of venting each piston. The Simulator operator will allow each rod-to be inserted to the 00 position,.as the insertion process is carried out. Af ter all the control rods 4 5 3 at . the . 00 position, the miniscenario will be terminated.

IV. Messares

.[ All information will we provided verbally by the appropriate controller, i

a 6

4 4

, ,w . m+ - + 4 ,we3 ,,y , , y --

a Rev. 0-

{ Page 7.2.2 1 VERM0NT YANKEE NUCLEAR POWER STATION FMERGENCY RESPONSE PREPAREDNESS EXERCIFE 1992 7.2.2 d).niscenarlo - "B" Diesel Gen;rator Failurn I. General'L9scrintion When the drywell high pressure sig.a11.. received, SCR operators receive 4

inc'ications that the "B" Diesel C. ..erator failed. to start. Any.

subsequent ettempts to start the diesel will be unsuccessfu?..

i II. Descriotion of PL63.2.r Responses / Observations / Corrective actions l The - SCR may request an A0 or an electrician be dispatched to the "B" Diesel Room to investigate the cause of the failure to start.

i In addition to a; visual inspection, the investigatr'r may be requested to attempt to start the diesel locally. If at any times he performs an j action that would -normally initiate a diesel start, he will be made rare that there seems to be no source of starting air. Upon L

investigation of this symptom, the differential pressure gauge (Pl-3-1B) across the Dollinger air. filter will indicate-120 psid.

Subsequent investigstion will reveal- that the Lfilter is : logged and +;'11 need to be replac d Maintenance vin be , requested to change the air filter es soon-as'possible.

i III. Event Closecut-This event will be terminated when the maintenance team leader informs the evaluator of all actions that would'be taken based'on the conditiona described above. The SCR' operators will then be allowed to start th(

f diesel from the appropriate. control panel,

IV; -Messares i

L All information will be provided verbally by the appropriate controller.

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Rev.-0 j Page 7.2.3-1 ,

VEP.MONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS-EXERCISE 1992 i 7.2.3 Miniscenario - RHR Pump Insueetion and Breaker FailyIg-4 i I. General DescriptioD

When the drywell high pressure signal is received, SCR operators receive indications that the RHR pur; not being used for torus--cooling failed to start. Any -attempts to restart the affected pump will be L

unsuccessful.

'II, peserietion of Player Responses / observations / Corrective Actions f ,

[ The Shift Supervisor should send out .n A0 to investigate the RPR p mp breaker in the switchgear room. He may also send an operator to the RHR corner room to physically inspect the RHR pump and motor, The operator inspecting the RHR pump and motor will find no apparent

problems, and will report his findings to the control room.

The operator inspecting the RHR - pump breaker will find its_ closing I-spring discharged and a blown fuse in the charging motor circuit. .The Shift Super-*isor will request Electrical -Maintenance to check the circuit and replace the fuse.

f i- III. Event Closecut This event will-be terminated when the circuit is check _out normal: and the fuse can be replaced. This will return the pump -to operational status. The SCR operators may decide to start the affected RHR pump without furt'er incident to the breaker closing circuit.

e

, IV. Messaces l All infomation will e t provided verbally by the appropriate controller.

i

-1 i

j R

i. i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE r ,

1992 f

'8 . 0 OPERATIONAL DAT.A.

1 i

NOTE;, The - operational data is, highly dependent on operator actions

.taken in' respon=e to the' conditions presented within the.

scenario. 'the operational data reflects plent con,itions assuming .

certain basic operator: . response -actiens being' tnken, The operational' data was taken fron, the plant simulator.

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' tfERMON9 YANNEE NUCLEAR POWER STATlON Rx 0 ;

EMERGENCY RESPONSE PREPAREDNESS EXERCISE Pa9e 8.0-1 2

19921 g4 - 8 0 OPERATIONAL DATA

• 4 SCENARIO TIME 00.00 00:15 00.30 00 45 01:00 INSTR. CLOCK TIME Co.15 08 30 00 v 09 00 09-15 ITEM PANEL ID DESCRIPTION - UNITS i

1 9-3 FT 23-108-1 HPCI FLOW . GPV 0 0 0 0 0 5 2 43 F) 10-139A RHR A FLOW GPU - 1 1- 1 1 1 4- i 3 43 F1-101398 RHR B FLOW GPM 1 1 1 1 1-

, 4 9-3 FL14 SCA CS A FLOW GPM 0 0 0 0 0 l 5 9-3 Fi-14-50B CS B FLOW G[M 0 0 0 0 0 6 9-3 Pl-1619-12A - DRYWELL PRESS PSIA 17 17 17 17 - 17

. 7 9-3 PL16-19-12B DRYWELL PRESS PSIA 17 17 17 17 17 l 8 9-4 Fb13 91 RCIC FLOW GPM 0 0- 0 0 0 9 9-4 F1-12141 A RWCU FLOW GPM 65 65 65 65 65 l

! 10 ' 9-4 F1-121418 - RWCU FLOW GPM 65 65 65 65 65

! 11 94 2165A RX COOLANT TEMP :  ; D5G F. . 527 527 525 519- 513

12 9-4 2165B RX COOLANT TEMP DEG F -527= 527 525 519 ' 513 -

13 9-4 2159A RECIRC A LOOP FLOW KGPM. 30.5 30.6 27.4 20.3 13 n

14 44 2-1599 - RECl*tC B LOOP FLOW KGPM 30 5 30.5 27.3 20.3 12.9 ,

15 9-5 7-46A . APRMIRM A -%- 100 100 92 73 58 j 16 95 7-46B ' APRM,UtMB  % 100 100 92 74 58

17 9-5 7 46C . APRWIRM C  % 99 99 91 73 57

!. 16 9-5 7-460 APRMilRM D  % 100 100 92 73 58 19 9-5 7-4GE APRMilRM E  % 101 93 f 101 74 58

! , !'O - 9-5 7 46F APRWIRM F  % 100 100 03- 74 58

'. 21 9-5 7-43A SRM A CPS 3.7eE+05 3.81 E+05 3.15E+05 1.93E+05 1.13E+05 22 9-5 7-43B SRM B 4.5'E+05 - 4 56E+05 f _ 2PS 3.77E+05 2.30E+05 1.34E+05

. 23 9-5 7-43C SRM C CPS 5.10E +05 5.14E+05 4.25E +05 2.59E+05 1.52E405 24 95 7-43D ShM D CPS 4 24E+05 4.27E+05 3.53E+05 216E+05 - 1.261?+05

25 9-5 2-3 95 CORE FLOW Ms G/HR 47 47 43 22 26 9-51 2-3-95 COREDP PSiD 18 '18 ' 16 ' 10 ' 7 3

27 9-! FL3 310 CRD FLOW GPM 44.2 44.1 0 0 0 28' 9-5 6-96 WIDE RANGE PRESS PSIG - 100E 1008 = 998- 976 960 F 29 9-5 6-96 NAR RANGE PRESS - PSIG 1008 1008 999 970 . 960 l_ 30 9-5 6-97 FEEDWATER FLOW kLB/HR 6.4 ~ 6.4 46 1 31 9 6-97

-59_ 3.6 MAIN STEAM FLOW ML5/HR - 6.4 6.4 5.9 4.6 3.6

32 9 6-98 NAR RANGE LEVEL - INCHES 161 151 161 161 161 j 33 95 6 WIDE RANGE LEVEL INCHES 497 490 448 310 206 34 ~ 96 Ll-107-5 CST LEVEL  %~ 50 49 ' 49 49 40 35 9-6 LI-102-5A HOTWELL LEVEL N  % 61 61 61 - 62 60 3 9-u LI-102 5B HO1WELL LEVEL S  %- 59 59 59 60 59

37 9-7 _ Pi-101-29 CONDENSER VACUUM . IN HG 2.7 2.7 2.6 2.3 1.9

. 38 R. DIG A BKR OPEN OPEN OPEN. OPEN OPEN 39 98 D/G B BKR OP N OrEN OPEd CPEN- -OPEN

, 40 9 23 16-19-33A/C TORUS TEMP -- DEG F 78 78 78 ~ 78 - 7e

. 41 - 9-25 Lb46A TORUS LEVEL FEET - 0.54 0.54 0.54 0.54 - 0.54 42 9 25 Ll-46B TORUS LEVEL FEET 0.54 0.54 0 54 0.54 0.54 l 43 9-25 TR-16-19-44 TORUS PRESS PSIA 14.6 14.6' 14 6 146 14.6

44 9-25 TR 1619-44 DRYWELL PRESS PSIA 17 17- 17 17 17

~

I 45 9 25 PR 1-156-3 DW/ TORUS OP - PSID 1.96 1.92 1.89 1.86 - 1.9

, 46 9 25 TR-1619-45 DRYWELL TEMP DEG F 138 138 137 137 136

! , 47 9 Pht-125-3A PX BUILDING DP IN H2O -1.62 1.62- . -1.62 1.62 4.62

'48 9 Pl-1-12538 - RX_ BUILDING LP IN H2O 1.62 1.62 1.62 1.62 i.62 49 9-26 . F1-1-125-1 A SGTS FLOW CFM 0- 8 8 8 8

" 50 9-26 Fki 125-1B l SGTS FLOW CFM._ 0 0 0 0 0 51 CAD DW/ TORUS O2 CONC. '  % 1.27 1.27 1.27 1.27 1.26

. .c .- _ . , c ;. , _ a _ ;. _.u _ _ _ _ . . . . - . . . . _ . _ . _ . _ . . . - . _ .._._..-._..-...n_....

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VERMONT YANKEE NUCLEA02 (OWER STA?lON Rev. 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 8 0-2 1992 6 0 OPERATIONAL DATA SCENARIO TIME 01:15 01:30 01:45 02:00 02:15 INSTR. CLOCKTIME 09 30 09:45 10:00 10.15 10:30 ITEM PANEL ID DESCRIPTION UNITS 4

1 9-3 FT 231081 HPCI FLOW GPM 0 0 0 0 0 2 0-3 Fb10139A RHR A FLoiV GPM 5791 2 7367 7366 7365 3 9-3 Fh101398 RHR B FLOW GPM 6063 2 7356 7355 7355 4 43 F1-14-50A CS A FLOW GPM 0 0 0 0 0 5 9-3 Fh14-50B CS B FLOW GPM 0 0 0 0 0 6 43 PI-16-19-12A DRYWELL PRESS PSIA 17 17 18 18 18 7 93 PI-1419-12B DRYWELL PRESS PSIA 17 17 18 18 18

< 8 G-4 F1-13-91 RCIC FLOW GPM 0 0 0 0 0 9 94 Fb12141 A RWCU FLOW GPM 0 0 0 0 0 10 9-4 F1-12-1418 RWCU FLOW GPM 0 0 0 0 0 11 9-4 2165A RX COOLANT TEMP DEG F 527 552 498 453 465 12 9-4 2165B RX COOLANT TEMP DEG F 537 552 498 453 465 13 94 2159A RECIRC A LOOP FLOW KGPM 8.3 8.3 ' 8.2 8.3 8.3 14 44 2-1598 RECIRC B LOOP FLOW KGPM 8.3 83 8.2 8.3 8J 15 9-5 746A APRM,lRM A.  % 0 0 0 0 0 j 16 9-5 7-46B APRMMRM B  % 0 0 0 0 0 17 9-5 7-46C APflM/lRM C  % 0 0 0 3 0 18 9-5 7-460 APRM/lRM D  % 0 0 0 0 0 19 9-5 7 46E APRM/IRM E  % 0 0 0 0 0 20 45 7-4GF APRWIRM F  % 0 0- 0 0 0 21 9-5 74A SRMA CPS 5.82E+01 3.21E+01 3 43E+01 5.00E+02 3.57E*01 22 9-5  ? 43B 0r(M B CPS 6 58E+01 3.21 E+01 3.43E +01 5COE+02 3.57E+01

~

23 9-5 7-43C " SRM C CPS 6.96E+01 3.15E+01 3.36E+01 8.00E+02 3.50E+01 l 24 9-5 7-43D SRM D CPS 6.34E +01 3.23E+01 3 45E+f" 7.00E+02

• 59E+01 25 9-5 2-3-95 CORE FLOW MLB/HR 14 14 44 14 14 26 9-5 , 2-3-95 COREDP PSID 4 4 4 4 4

, 27 9-5 FL3-310 CRD FLOW GPM 0 0 0 0 0 9-5 6-96 WlDE RANGE PRESS PSIG 855 1063 828 432 490

_ 28 29 , 9-5 6-96 NAR RANGE PRESS PSIG 950 1063 950 950 950

30 9-5 6-97 FEEDWATER FLOW MLa'HR 0.1 0 08 0,1 0 31 45 G97 MAIN STEAM FLOW MLB/HR 0 0 .0 0 0 32 9-5 6-98 NAR RANGE LEVEL INCHES 159 157 164 156 160 33 9-5 G98 WIDE RANGE LEVEL INCHES 159 157 164 156 160

34 9-6 Li-107 5 CST LEVEL  % 48 48 47 46 45 35 46- L.Eb5A HOTWELL LEVEL N  % 61- 63 58 59 63 36 9-6 LL102-5B HOTWELL LEVEL S  % 60 60 56 57 59 51 9-7 Pb101-29 CONDENSER VACUUM IN HG 5.1 13.3 18.7 25.3 29.9 f 38 44 D/G A BKR OPEN OPEN OPEN OPEi' OPEN 39 S8 D/G B BKR OPEN OPEN OPEN OPEN OPEN 40 0-23 16-19-33A/C TORUS TEMP DEG F 84 84 88- 95 95 41 9 25 Li-46A TORUS LEVEL FEET 0.57 0.58 0.62 0.69 0.72 42 9-25 Li-46B TORUS LEVEL FEET 0.57 0.58 0 62 0.69 0.72 43 9-25 TR 16-1444 TORUS PRESS PSIA 14.8 15.1 15.6 16.1 16.3 44 9 TR-16-19-44 DRYWELL PRE. PSIA 17 17 18 18 18 45 9-25 PR 1 156-3 DW/ TORUS DD PSID 1.72 - 2.01 2.02 1.93 2.1 46 9-25 TR 16-19-45 DRYWELL TEMP DEG F 136 140 143 145 147 i 47 9-26 Ph11 E A RX BUILDING Da IN H2O -0.68 0 68 -0.68 -0.68 -0.68 l 48 9-25 Pi-1-it , J RX BUILDING DP IN H2O -0.68 -0.60 -0.68 -0.68 O 68-49 9-26 ' FL1-125-1 A SGTS FLOW CFM 1500 1500 1500 1500 1900 50 9 26 Fi-1 125-1 B SGTS FLOW CFM 1500 1500 1500 1EJO 1500 51 CAD DW/ TORUS O2 CONC.  % 1.26 1.21 1.16 1.13 1,1

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";ENCY RESPONSE PREPAREDNESS EXERC'SE Page 9.1-1 1992 3 -

9.1 AREA RADtAT10N MON TORS ,

SCEN ARIO TIME 0.00 0:15 0-30 0:45 - too 1:15 1:30 1:45

' CLOCK TIME 8 15 8.30 8 45 9 00 915 9:30 9'45 1000'  :  !

ARM No. PANELL ' BLDG /f LV' DESCRIPTION UNITS .

7MS 11-1 9-i l ' RB/232 RX BLDG H! RADS - N - 'RMR <1 <1' <1 ~<1 <1 <1 <1 <1

-$1S 15 9-11 ' RB/252 ' RX BLDG HI RADS - S - R/HR <1 <1 <1 <1 <1 <1

<1 <1

'*dS f6 3 9-11 NB/252 - TIP RM Hf RAD R/HR <1 <1 ~ <1 <1 <1 <1 . <1 <1 1 9 11 ' RB/232 SUPP CHAM? R3 EXT CW *!C t 8 8 8 '8 2 ' 9-11 ; RB/252 N PERSONNEL I BLDG' 4 10 100- 30 300 Ii MR/HR 4 4 3 3 190 460 650 .

3 9 11 - ' RB/252 - S EOUtP RR RX Bt.% M"./HR 'O3 03 03 03 03 45 f 20~ 65 4' 9-11 RB/252 RX BLD NEUTRON TIP MR/HR .. 5 5 5 5 5 I

200 475 650 5 9-11 RB/252 PERSONNFL H/.TCH RX B -MRMR 520- 520 500 480 420 O* * #104) OSH OSH i- -6 9 11- RB/200 ELEV ENT R 280FT RX - . MR/HR 8 8 8 7

• - 7 t. 5- 5 I 7 9-11 ' RB/252 CRD REPAIR RX BLDG MRMR 12 12 10 10 8 4 4 4 8- 9-11 RB/303 .- ELEV ENIR 303FT RX - MR/HR 4 -4 4 3 3 1 1 1 4 '9 9-11 ~ RB'303 H2O CLEANUP RX BLDG - MRMR- 4 4 4 4 4 4 4 4 10 9-11 RBf318 ELEV ENTR 318F T RX . MR/HR 7 ;- '7 6: 5 6- 3 3 3 >

11 11 ' 9 8/318 ' H2O CLEANUP RX BLDG MRMR 5 5 5 4 4- 2 2 2

) 12 11 RB/345 - ELEV ENTR 348FT RX -- MR/HR 4 4 4 4 3 1 1 1

,, 14 9-11 RBf345 WEST REFUEL RX BLDG MRMR 5 5 4 4 3

1' 1 1 15 9-11' RB/345 - SPENT FUEL POOL RX MRMR 16 16 15 14 - 13 8 8 8 j 16 9 11 RB/318 NEW FUEL VAULT RX B MRMR 05_ 05' PS 04 0.4 04 0.4 ' 04 17 9 RW/252 PUMP RM RADWASTE BL . IKR/HR 1 1 1 1 1 1 1. 1 16 9 RW/252 - RADW OPEP \REA RW B MRMR 1 1 1 1 1 1 1 1

$ 19 9-11 . RW/230 1 PUMFiTANK AREA RW B MR/HR - 1.5 15 1.5 1.5 ' 1.5 I 1.5 15 1.5 20 ' 9 11 TB/248 N ACCESS 240FTTURB LMRMR '? "2 2 2 2 au-13 15- 1.5 l 21: 9-1 f TE"248 - MAIN STM VALVE 1 URB . MRMR 20u . 200 '200 190 170 4 4 -4

+

22 ' 9-11 TB/232 " COND DEM8N TURB ELD MRMR- 0.26 0 26 0.26 0 25 - 024 0.12 0.12 0.12

{. 23 9-11 .. TB/252 - DECON/ MACH SHOP TB - MR/HR - 0.17 . 0.17 0.17 . 'O.16 0.16 0.15 . 0.15 ' O.' 5 i 24 9-11 TBf272 TURB STM IN TURB BL MRMR' 9' 7 7 7 7 7 7 7 j 25 9-11 ' AB/2M. : - VIEW GALLERY CONT RM MR/HR ' Oh7 - 0.82 0.81 0.77 - 0.7 0.11 0.11 0.11 ' I j 26 9-11 TB/252 ' REAR GATE TURB WAREH - MRMR 0.17 0.17 0 17 0.16 0.14 ~0 01 0.01 0 01

-13 . 9-11 . TS/228 : MOIST SEP AREA TURB - . MR/HR 150 '150 .150 140 125 1 1 1 s . -.

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4 VERMONT YANKEE NUCLEAR POWER STATION Rev.O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 9.1-2 1992 9.1 AREA RADIATION MONITORS ,

i SCENARIO TIME . 2:00 2:15 2:30 2-45 3m 3.15 3:30 3/5 t CLOCK TfME to 15 13-30 -10 45 11X)0 11:15 11 30 11:45 12M

- ARM No: PANEL- BLDG /ELV ' DESCRIPTION UNITS

- RMS 18 9 11 RB/252 PX BLDG HI RADS - N RMR <1 <1 <1 <1 <1 <1 <1 <1

___RMS 81-2 11 R8f2S2 RX BLOG HI RADS . S RMR- <1 <1 <1 <1 - -1 ' <t <t <1 RMS114 9-11 RB/252 TIP RM HI RAD - RMR- ' <1 <1 <1 <1 <1 <1 <1 <1 1 9 11 ~ RBGJ2 SUPP CHAMB RB EXT CW MRMR' 500 500 50C 500 500 500 500 500 i 2 9-11 RB/252 N PERSONNEL RX BLOG MRMR 700 850 850 850 850 260 850 850 i 3 9 11 = R J252 S EOU.P RR RX BLDG - MRMR 7S 80 80 BG ' 80 80 - M 80 4 9-11 7B/252 R7 BLD NEUTRON TtP - MRMR. 760 850 850 85n 850 850- 850 850-S 9 ' 7Br252 ' PERSONNEL HATCH RX B - MR/HR OSH OSH OSH OSH OSH - OSH OSH OSH 6 9-11 , Br280 .. ELEV ENTR 200FT RX B ' PAR /HR S. 5 5- 5 5 5 5- 5 7' 9-11 6 4r252 CRD REPAIR RX E" DG MRMR ~4 4 -4 4' 4 4 4 4 8 . 9-11 - RBr303' ELEV ENT R 303FT RX B MR/HR - 1 1 1 1 -1 1 1. 1-9 9-11 RB/303 H2O Cl EANUP RX BLDG -MRMR 4 4 4 4 4 4 -4 -4 -i 10 9 11 RBM8 - ELEV ENTR 318FT RX B , MRMR 3 -3 3 3 3 3. .3 ;3< .

11 ' 9-11 RB O'* H2O CLEANUP RX BLOG MRMR -2 2- 2 2 2 2 2 .2-12- 9-11 RBGt_ ELEV ENTR 348FT RX B -MRMR 1 1 1- 1 1 1 1 .1 14' 9-11 RB/345 WEST REFUEL RX BLDG VfdHR ,1 - 1- 1- 1 1 1 1 1-15 411 . - 9 8/345 FPENT FUEL POOL RX u - . MR/HR S 8 8 8 8 8 8" 8 16 9-11 RB/318 NEW FUEL VAULT RX 8 - MRMR 0.4 03 03 03 03 0.3 03 0.3 17- 9-11 RW/252 . PUMP RM RADWASTE BLD . MRMR 1 1 1 1 ,1. 1 1 1

'18 9.11' RWr2S2 ' RADW OPE 9 AREA RW B ~ MRMR 1 i 1 1' 1' 1 1 1 9-11 19 RW/230 PUMP / TANK AREA RW 8 MRMR 2 2. 2 2' 2 2 2' 2  !

20

• 9 11- TB/246 ^ N ACCESS 248FTTURB MRMR- 2 2 2- 2 2' 2 1 1-  :

21 9 TBr248 -; kWIN 6TM VALVE 1 URB >MRMR 4 4 4 4- 4 4 4 4 22 ~ 9-11 TBr232 COND DEMIN TURB BLDG ' MRMR 0 12 : 012 0.12 0 12 0.12 0 12 - 0.12 ' O.12 23 ' 9-11 ' TB/252 DECONTAM.1 URB BLDG MRMR 0.15 0.15 0.15 0.15: . 0.15 0.15- 0.15 0.15 24 9-11 'TBrI72 ' TURB STM IN Tl tRB BLD MRMC -7 7

• 7 7 7 7- 7 25 9-11 AB/272 . VIEW G/.LLERY CONT RM MRMR 0.11 - 0.11 0.11 0.11 - 0.11 0.11 0.11. 0.11

' 26 9-11 TB/252 REAR GATE TURB WAREH MRMR- ' b 0* 0 01 0 01 0 01 9 'n 0 01 ' 0 01 0 01 -!

13 9-11 1828' MOtST SEP AJEA TURB W.R/HR - 1 1 1 1 .1 1 1- 1 NOTE- OSH = OffScale High  !

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' VERMONT YANKEE NUCLEAR POWER STATION REV.0 EMERGENCY RESTONSE PREPAREDNESS EXERCISE . PAGE 92-1

-1952

- 9 2 PROCESS MONITORS SGNAR'O TIME 0.00 0:15. 000 0:45 000 1:15 1:30 t45 CLOCKTIME - 8.* 5 ' . 8.30 8.45 900 9:15

• 9:30 9 45 10:00

. APM NO. PANEL BLDG /ELV DESCRIPTION UNITS 4 9 ' ST/257 : STACK GAS MON 4AS 1 CPM 150 150 150 150' 150 - 150 150 150 $

9-2 ST/257 STACK GAS MON GAS 2 . CPM 200 ~ 200 200: 200' 200 -200 200 200 9-2 . RB/200 CONT /1NMENT MON CAS - -CPM 540. 540 530- 495 - 437 OSH(*1E6) . . OSH . OSH

'9-2 RB/280 ' CONTAINMENT MON-PART CPM J 25107 25095 24776- '23 99 20469 OSH (*1E6) OSH- OSH '

' 0-2 :

ST/257 : STACK HI RANGE - MRMR 0.1 0.1 ^ 0.1 ' ' O. . 0.1. 0.1 0.1 0.1 27  : 9-2 : ' DW/252 ' DRYWELL CH A - RMit 3.7 ' 3.7 36 3.4 - '3 200 290 350

- 28 ' a 9-2 . DW/252 DRYWELL CH B RMR 3.7 - 3.7 3.6 3.- 3 200 270 335

, 9-2x RB/280 RX BLDG VENT GAS CPV 185 185 179 16- 149 45 -13088 12444 9-2' RB/200 RX BLDG VENT.PART CPM 1481 1482 1430 1305~ 0189 - 363 ;J4529 99551 31- 91C ' RB/200 ' RX BLDGVENT MRTH MR/HFt - '2 2 2' 2- t 11 123 115'

32. ' 9-10i RB/280 : RX BLDG VENT SOUTH ' MR/HR 2 ~2 2 2' 1 1 120 115

-453A 9-10 ' RB/343 SPENT FUEL Port A ' MRMR- '16 '16 t 5 '. - 13 12 ' 4- 4 4

.-.4538 9*O R8/345 SFI NT FUEL POOL B Mrt/HR 16 16 n5' 13' ' 12 :. 4: ,t 4 9 10 RS/256 MAIN STM LINE A ' MRMR' 173- 173 166- 146 125 1 1 1 9-10 PB/256 " MAIN STM Lt:lE B - .URMR- t06; _167' 160' 1141 121.

1 1 ,

0-10' ' RB/256 ' MAIN STM LINE C ' .MRMR 166 189 161 143 122 1 '1 1-10 RB/256 : MAIN STM LINE D 'MRMR- 175 175- 168 '148 127 1 1- 1 38 9 TB/243 SJAE(AIR EJECTOR) - MRMR' L 61 61 60 57L 51 0 0 0 ,

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VERMONT YANKEE NUCLEAR POWER STATION REVO EMERGENOY RESPONSE PREPAREDNESS EXERCISE PAGc G.2-2 1992 9 2 PROCESS MO 4t' ORS SCENARIO Tikd 220 2 15 2 30 2<; 3M 3:15 3.30 3.45 CLOCK TIME 10:15 10.30 1U45 11t)0 11:15 11:30 11:45 12:00 ARM NO. PANEL BLDG /ELV DESCRIPTtON UNITS 9-2 STM7 STACK GAS MONCAS 1 CPM 150 1P 150 150 150 150 150 '150 9-2 ST/257 STACK GAS MON-GAS 2 CPM 200 200 200 200 200 200 200 200 9-2 kB/200 CONTAINMENT MON GAS CPM OSH (>1ES) OSH OSH OSH OSH OSH OSH OSH 9-2 RB/280 CONTAINMENT ? ION-PART CPM OSH (>1E6) OSH OSH OSH 03H OSH OSH OSH 9-2 7T/257 ST3.CK HI RANGE MRadR 0.1 0.1 0.1 0.1 01 0.1 0.1 0.1 27 9-2 DW/252 DRYWELL CH A R/HR 400 450 440 440 C1 430 430 430 28 9-2 DWCS2 DRYWELL CH B R/HP 400 450 440 440 430 430 430 430 9-2 RB/200 RX bldg VP8T GAS CPM 11840 11265 11265 11265 11265 11255 11265 11205 9-2 RR/200 RX BLDG VENT- PART CPM 94717 90117 90117 90117 90117 '90117 90117 90117 31 9 10 R3/280 RX BLDG VENT NORTH MR!HR 110 100 100 100 100 1(/G 100 100 31 9-10 RS/200 RX BLDG VENT SOUTH MR!HR 110 100 100 100 100 100 100 100 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 RS/256 MAIN STM LINF A MR!HR 1 1 1 1 1 1 1 1 9-10 RB/256 MAIN STM UNE B ' MR' ? 1 1 1 1 1

• 1 1 9-10 RB/256 MAIN STF.l uNE C MR/t Jt 1 1 1 1 1 1 1 1 9-10 RB/250 MAIN S1M LINF D ' MR/HR 1 1 1 1 1 1 1 1 38 9 10 TB/248 SJAE(AIR EJECTOR) MR!HR 0 0 0 0 0 0 0 0 NOTE: OSH = Offscale High L

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, TABLE 9.3-1 Rev. O Page 9.3-la Reaccor Building Refuel Deck, Elevation 345' (mR/hr unless otherwise noted)

Clock Scenario ?cne I Zone II Zone III Zone IV Time Time ARM 12 ARM 14 ARM 15 453 A 453 D _ - - - - - -

5 16 16 15 4 16 16 16 0815 0:00 4 16 16 16 0830 0:15 4 5 16 16' 16 4 0:30 4 4 15 15 15 4 15 13 15 0845 13 0900 0:45 4- 4 14 13 13 4 13 13 12 0915 1:00 3 4 13 12 12 3 12 12 1 1 8 4 4 1 4 4 4 0930 1:15 1:30 1 1 8 4 4 1 4 4 4 0945 4 4 1:45 1 1 8 4 4 1 4 1000 3 1 1 8 3 3 1 3 3 1015 2:00 3

1 8 3 3 1 3 3 1030 2:15 1 3 3 1 1 8 3 3 1 3 1015 2:30 3

1100 2:45 1 1 8 '3 3 1 3 3 1 1 8 3 3 1 3 3 3 1115 3:00 3 3

- 1130 3:15 l' 1 8 3 3 1 3 1145 3:30 1 1 8 3 3 1 3 3 3 1200 3:45- 1 1 8 3 3 1 3 3 3 Notes: Zone readings are average dose rates throughout zone.

General'arca contamination levels ~2K-5K dpm/100 cm2 In all nones.

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REACTOR BUILDING

- -N ELEVAT!ON 345* t MONITORS -

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-(mR/hr unless otherwis; noted)

Clock Scenario Time Time ARM 10 ARM 11 ARM 16 Zone T. Zone II Zone III Zone IV Zone V Zone VI Zone VII

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

0815 0:00 7 5 .5 7 5 300 5 80 .5 .5 0830 0:15 7 5 5 7 5 300 5 80 .5- .5 0845 0:30 6 5 .5 6 L 300 5 80 .5 .5 0900 0 45 1: 6 4 .4 6 4 200 '4 80 .4. .4 0915 1:00 5 4 .4 5 4 200 4 80 .4 .4

- 0930 1:15 3 2 .4 3 2 200 2 80 .4 .4-0945 1:30 3 2 .4 3 2 200 2 80 .4 .4 1000 1:45 3 2 .4 3 2 200 2 80 .4 .4 1015 2:00 3- 2 3 3 2 200 2 80 .3 .3 1030 '2:15 3- 2 3 2 100 2 60 .3 .3 1045 2:30 3 2 . 3 2 100 2 60 .3 .3 1100 2:45 3 2 .3 3 2 100 2 60 .3 .3 1115 3:00 3 2 .3 3 2 100 2 60 .3 .3 1130 3:15 3 2 .3 3 2 100 2 GO .3 .3 1145 3:30 3 2 .3 3 2 100 2 60 .3 .3 1200 -3:<45 :3 2 .3 3 2 100 2 60 .3 .3

--____----------_- -- --_-_------------_---_----------==- - - - - - -- -___ - _ - - _ - - - -..___--____

Noter:' . Zone readings are average dose rates througi;out zone.

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

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

Clock Scenario Zone VI Zone VII Time . Time ARM 8 ARM 9 Zone I Zone II Zone III' Zone IV Zone V =- -------

0:00 4 4 4 3 600 3 60 0.1- 0.2 0815 0.1 0.2 0830 .0:15 4 '4 4 3 600 3 60 0845 0 30 4 -4 4 3 600 3 60 0.1 0 . lc 0900- 0:45 3 4 4 3 600 3 60 0.1 0.2 1:00 3 4 4 3 600- 3 60 0.1 0.2 0915 0930 1:15 1 4 4 3 800 3 60 0.1 0.2 0945 1:30 1 4 4 3 850 3 60 0.1 0.2 -

1000 1:45 1 4 4 3 900 3 60 0.1 0.2 1015 2:00 1 4 4 3 950 3 60 0.1 0.2 1030 2:15 1 4 4 3 100r 3 80 0.1 0.2 2:30 1 4 4 3 1000 3 80 0.1 0.2 1045 1100 2:45 1- 4- 4 3 1100 3 80 0.1 0.2 1115 3:00 l' 4 4 3 1100 3 80 0.1. 0.2 80 3:15 1 4 4' 3 1200 3 0.1 0.2

, 1130 1145 3:30 1 4 4 3 1200 3 80 0.1 0.2

-1200 3:45 1 4 4 3 1200 3 80 0.1 0.2

---

=== -- ==-- == - _ - - -

Notes Zone readings are average dose rates tnroughout zone.

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

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RB Vent RB Vent Zone' -Zone Zone Zone ' Zone South Zone Zone Zone Clock Scenario North II III IV V VI . VII VIII Time Time ARM 6 ARM 31 ARM 32 I

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

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-1200 3:45 5 10^ 100

= - - --=-- - - - - - - - _ -_ _ ______----_

Notes: Zone readings are average dose, rates throughout zone.

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RM- Zone Zone Zone Zone Zone Zone Zone Clock Scenario IV V VI VII

' Time LTime ARM 2 ARM 3 ARM 4 ARMS ARM 7 14-29 I II III

_=- ------------------------

4 5 520 12 100 5 4 .3 50 4 12 24 0815 .0:00 .3 12 0830 0:15 4 .3 5 520 12 100 5 4 .3 50 4 24 0845 0:30 4 .3 5 500 10 100 5 4 .3 50 4 10 20 0900 0:45 3 .3 5 480 10 100 5 3 .3 50 3 10 20 0915 1:00 3 .3 5 420 8 100 5- 3 .3. 40 3 8 16-0930 1:15 190 20 200 (OSH)>1E4 4 100 200 190' 20 2800 190 4 8 0945 1:30 460 45 475 (OSn) 4 100 475 460 45 3800 460 4 8 650 65 650 (OSH) 4 100 650 630 65 -5000 650 4 8 1000 1:45 760 -(OSu) 4 100 .-7 6 0 760 75 6000 760 4 8 1015 2:00 760 75

'1030 2:15 850 80 850 (OSn) 4 100 850 850 80 6500 850 4 8 1045- 2:30 850 80 -850 .(osa) 4 100 850. 850 80 6500 850 4 8 1100 2:45 850 80 850 (Osu) 4 100 850 850 80 6000 850 4 8 1115 3:00 850 80 850 .(Osu) 4 100 850 850 80 6000 850 4 8 1130 3:15 850 80 850 (Osu) 4 100 850 _850 80 c000 850 4 8 1145 3:30 850 ~8 0 850 (Osu) 4 100 850- 850 80 6000 850 4 .8-1200 3:45. 850- 80 850: .(OSH) 4 -100 850 850 80 6000 850- 4 8

---

=

Notes: Zone readings are average dose rates throughout zone.

General area contamin3 tion levels ~1K-2K.dpm/100 cm2 in all zones.

1 i

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Rev. O Page 9.3-Sa.2 TABLE ~9.3 (Continued)

Clock Scenario NORTH SOUTH TIP Time Time RMS II-1** RMS II-2** RMS II-3**

---

_ --------------------------------------------- ==_=----

0815 0:00 <1.0 <1.0 <1.0 0830 0:15 < 1. 0 . <1.0 <1.0 0845 0:30 '<1.0 <1.0 <1.0

~0900 0:45 <1.0 <1.^ <1.0 0915 1:00 <1.0 <1.0 <1.0

-0930 1:15 <i.0 <1.0 <1.0 0945 1:30 <1.0 <1.0 <1.0 1000 1:45 <1.0 <1.0 <1.0 1015 2:00 <1.0 <1.0 <1.0 1030- .2:15 <1.0 <1.0 <1.0 1045 2:30 <1.0 <1.0 <1.0 1100 2:45 <1.0 <1.0 <1.0 1115 3:00 <1.0 <1.0 <1.0 1130 3:15 <1.0 <1.0 <1.0 e '1145 3:30 <1.0 <1.0 <1.0 1200~ 3:45 <1.0 <1.0 <1.0 Notes:

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

Turbine Deck Clock Scenario CAM (cpm)

Time ' Time ARM 24 Zone I Zone II Zone III NG' Particulate-0815 0 00 9 100 150 9 250 coo 0830 0:15 7 75 120 7 250 900 0845 0:30 7 40 60 7 '250 900 0900 0:45 7 20 35 7 250, 900 0915 1:00 7 20 35 7. 250 900 0930 1:15 7 16 30 7 250 900 0945 1:30 7 16 22 7 250 900 1000 1:45 7 16 22 7 250 900 1015 2-00 7 11 22 7 250 900 1030 2:15 7 11 22 7 250 900 1045 2:30 7 11 22 7 250 900  !

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h. ------------------------------------------------------------------- ------------

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n TABLE 9.6-7 Rev. O Turbine Building Truck Bay, Make-Up Domineralization Cond. Page 9.3-7a Domineralization Areas, Elevation 252' (mR/hr unless otherwise noted)

Clock Scenario RM-14-23A RM-14-36 Time Time (cpm) ARM 26 (cpm) Zone I Zone II Zone III Zone IV 0815- 0:00 150 0.17 150 0.2 0.2 0.1 0.2 0830 0:15 150 0.16 150 0.5 0.3 0.2 0.2 0845 0:30 150 0.14 150 0.5 0.3 0.2 0.2 0900 0:45 -150 0.14 150 0.6 0.3 0.2 0.2 0915 -1:00 150 0.13 150 0.6 0.3 0.2 0. 2 '

0930 1:15 150 0.01 150 0.7 0.3 0.2 0.2 "0945 1:30 150 0.01 150 0.7 0.3 0.2 0.2 1000 1:45 '150 0.01 150 0.7 0.3 0.2 0.2 1015 2:00 150 0.01 150 0.7 0.3 0.2 0.2 1030 2:15 150 0.01 150 0.7 0.3 0.2 0.2-1045 2:30 150 0.01 150 0.7 0.3 0.2 0.2 1100 2:45 150. .0.01 150 0.7 0.3 0.2 0.2

• 3115 3:00 150- 0.01 150 0.7 0.3 0.2 0.2

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

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TABLE 9.3-8 Rev. O Turbine Duilding Cond. Day, Elevation 248' Page 9.3-8a

-(mR/hr unless otherwise noted)

Clock Scenario Zone VI Zone VII Zone VIII Time Time ARM 20 ' ARM 21 Zone III Zone IV Zone V

---

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0815 0:00 2 200 2 2 4 8 200 2 0:15 2 200 2 2 4 4 200 2

.0830 0845 0:30 2 200 2 2 3 4 200 2.

0900 0:45 2 190 2 1 3 3 190 2 0915 1:00 2 170 1 1 3 3 170 2 1:15 1 4 1 1 2 3 4 1 0930.

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

Clock Scenario

' Time Time ARM 22 ARM 38 Zone I Zone II Zone III

---__=_-__==----------------------------------------__=_______-

0815 0:00 0.3 60 0.2 0.5 0.2 0830 0:15 0.3 60 0.2 0.5 0.2 0845 0:30 0.2 60 0.2 0.5 0.2

'0900 0:45 0.2 60 0.2 0.5 0.2 0915 1:00 0.2 50 0.2 0.5 0.2 0930 1:15 0.1 D/S 0.2 0.5 0.2 0945 1:30 0.1 D/S 0.2 0.5 0.2 1000 1:45 0.1 D/S 0.2 0.5 0.2 1015 2:00 0.1 D/S 0.2 0.5 0.2 l

l 1030 2:15 0.1 D/S 0.2 0.5 0.2 1045- 2:30 0.1 D/S 0.2 0.5 0.2 1100 2:45 0.1 D/S 0.2 0.5 0.2 1115 3:00 0.1 D/S 0.2 0.5 0.2 1130 3:15 0.1 D/S 0.2 0.5 0.2 1145 3:30 0.1 D/S 0.2 0.5 0.2 1200 3:45 0.1 D/S 0.2 0.5 0.2

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

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

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TABLE 9.3-10 Rev. O Page 9.3-10a Turbine Building Cond. Bay, Elevation 222'6" & 228'6"

.(mR/hr unless otherwise noted)

Clock Scenario Time Time ARM 13 Zone I Zone II Zone III Zone IV Zone V Zone VI

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

0815 0:00 150 3 1 50 150 2 75 0830 0:15 150 3 1 50 150 2 75 0845 0:30 150 1 1 50 150 2 75 0900 0:45 140 1 1 45 14.0 2 70 0915 1:00 125 1 1 40 125 2 60 0930 1:15 1 1 1 1 1 2 1-0945 1:30 1- 1 1 1 1 2 1 1000 1:45 1 1 1 1 1- 2 1 1015 .2:00 1 1 1 1 1 2 1 1030 2:15- 1 1 1 1 'l 2 1 1045 . 2:30 1 1 1 1 1 2 1 1100 2:45 1 1 1 1 1 2 1 t 1115 3:00 1 'l 1 1 l' 2 -- 1

~

1130 ;3:15 1 1 1 1 1 2 1 1145 3:30 1 1 1 1 1 2 1 1200 3:45 1 1 1 1 1 2 1 Notes: . Zone readings are averacje dose rates throughout zone.

General area-centamination levels <1K dpm/100 cm2.

4 4

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, FIGURE 9.3-10 Page 9.310b

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_ n Rev. O Page 9.3-11a TABLE 9.3-11 Torus Catwalk (mR/hr unless otherwise noted)

Clock Scenario Time Time ARM 1 Zone 5 0815' 0:00 8 8 0830' 0:15 8 8 0845 0:30 8 8 0900 0:45 8 8 0935 1:00 10 10 0930 1:15 100 100 0945 1:30 200 200 1000 1:45 300 300 1015 2:00 500 500 1030 2:15 500 500 1045 2:30 500 500 1100 2:45 500 500

.1115 3:00 500 500 1130 3:15 500 500 1145 '3:30 500 500 1200 3:45 500 500 Notes: . Zone readings are' average dose rates throughout zone.

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

- P pe 9.311b ,

FIGURE 9.3;11 ~

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r 4 VERMONT YANKEE NUCLEAR POTTER STATION

~ EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 i

i I'J 4

9.4 PLANT CHEMISTRY DATA j.

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VERMONT YANKEE NUCLEAR POWER STATION  ;

EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 i

i .-

9.4 PIANT CHEMISTRY DA'{6 ,

t SECTION PAGE l

4

~

9. 4.1 Rea.c tor Coolant Activity Data . . . . . . . . . . . . . . . . . . . . . . . . 9.4.1-l' i 9.4'.2 Primary Containment Air Activity Data................. 9.4.2-1 9.4.3 Reactor Building Air Activity Data.................... 9.4.3 1 i

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_ VERMONT YANKEE NUCLEAR-POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE.:

i, -

- . 1992 1

d I

5 4

h I

! 9.4.1. REACTOR C001 ANT ACTIVITY DATA i-4 4

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1 -

I'

f. -

A i4 ii Rev. O

Page 9.4.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 1

9.4.1 REACTOR COOLANT ACTIVITY DATA 1 ________ ____________________

1 A. Reactor Coolant Activity Concentrations (uCi/ml)

~

Time 4

Isotope Prior to 0930 0930-0945 0945-1000 1000-1015 t

I-131 2.5E-03 1.9E+03 1.9E+03 1.9E+03 I-132 2.8E-03 2.6E+03 2.4E+03 2.2E+03 I-133 5.2E-03 3.7E+03 3.7E+03 3.6E+03 4

I-134 4.1E-03 3.6E+03 3.0E+03 2.4E+03 I-135 4.5E-03 3.4E+03 3.3E+03 3.2E+03 Total Iodine 1.9E-02 1.5E+04 1.4E+04' 1.3E+04 i

I-131 Dose 4.5E-03 3.3E+03 3.3E+03 3.2E+03.

Equivalent i

Kr-83m 1.2E-03 1.1E+01 2.7E+01 4.1E+01 Kr-85m 2.5E-02 8.2E+00 8.6E+00 8.3E+00 Kr-85 4.8E-03 2.1E-01 2.1E-01 2.'1E-01 l Kr-87 2.9E-03 1.5E+01 -1,3E+01 1.2E+01 l Kr-88 1.0E-03 1.1E+01 1.0E+01 9.7E+00 l Xe-133m 7.2E-04 1.3E+00 1.6E+00 2.0E+00 i Xe-133 5.3E-03 4.0E+01 4.5E+01 5.0E+01

~Xe-135m 5.BE-03 1.6E+02 3.4E+02 4.2E+02 Xe-135- 2.2E-03 3.7E+01 9.5E+01 1.5E+02-Total Noble 4.9E 2.BE+02 5.4E+02 6.9E+02 Gas 2

i 4

l Note: Reactor coolant sample dose rates are provided in Section 9.5.1. 1 1

i  !

Rev. O Page 9.4.1-2 i

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 i

i A. Reactor Coolant Activity Concentrations (uci/ml) 4 Time 1

Isotope 1015-1030 1030-1045 1045-1100 1100-1115 t I-131 1.9E+03 1.8E+03 1.8E+03 1.8E+03 I-132 2.1E+03 1.9E+03 1.8E+03 1.6E+03 I-133 3.6E+03 3.6E+03 3.5E+03 3.5E+03 1-134 2.0E+03 1.6E+03 1.3E+03 1.1E+03 l I-135 3.1E+03 3.1E+03 3.0E+03 2.9E+03 Total Iodine 1.3E+04- 1.2E+04 .1E+04 1.1E+04 1

l I-131 Dose 3.2E+03 3.2E+03 c.1E+03 3.1E+03 Equivalent I Kr-83m 5.22+01 6.1E+01 6.8E+01 7.4E+01

+

Kr-85m 7.9E+00- 7.6E+00 7.3E+00 .7,0E+00 Kr-85 2.1E-01 2.1E-01 2.1E-01 2.1E-01

Kr-87 1.0E+01 8.9E+00 7.7E+00 6.7E+00 Kr-88 9.2E+00 C.6E+00 8.1E+00- 7.6E+00 Xe-133m 2.3E+00 2.6E+00- 2.9E+00 3.3E+00 Xe-133 5.4E+01 3.8E+03 6.3E+01 6.8E+01

-Xe-135m 4.5E+02 4.6E+02 4.6E+02 4.6EiO2 Xe-135 2.1E+02 2.6E+02 3.1E+02 3.6E+02 Total Noble 8.0E+02 4.6E+03 9.3E+02 9.9E+02 i Gas Note: Reactor coolant sample dose rates are provided in Section 9.5.1.

t

i 4

! Rev. O Page 9.4.1-3.

VERMONT YANKEE NUCLEAR POWER STATION 5

EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 i

9.4.1 REACTOR C001 ANT ACTIVITY DATA e

A. Reactor Coolant Activity Concentrations (uCi/ml)

Timo l Isotope 1115-1130 1130-1145 1145-1200

! I-131 1.8E+03- 1.8E+03 1.8E+03 l I-132 1.5E+03. 1.4E+03 1.3E+03 I-133 3.5E+03 3.4E<03 3.4E+03 l I-134 9.OE+02 7.4E+02 6.0E+02

' 2.8E+03 2.7E+03 2-7E+03 I-135 4

4 Total Iodine 1.1E+04 1.0E+04 9.8E+03 I-131 Dose 3.1E4 03 3.1E+03 3.OE+03 i Equivalent i

Kr-83m 7.8E+01 8.1E+01- 8.3E+01 i,

Kr-85m 6.8E+00 6.5E+00 6.2E+00 Ar-85 2.1E-01 2.1E-01' 2.1E-01 Kr-87 5.9E+00 5.1E+00 4.5E+00 Kr-88 7.1E+00 6.7E+00- 6.3E+00 Xe-133m 3.6E+00 3.9E+00 .4.2E+00 x Xe-133 7.3E+01- 7.7E+01 8.1E+01' Xe-135m 4.5E+02 4.4E+02 4.3E+02 Xo-135 4.1E+02 4.5E+02 5.OE+02

, Total Noble 1.0E+03 1.1E+03 1.1E+03.

.QSu

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

4 1 .

i

. . . , . . ,, . . . _ . . _ . _ . . . . _ _ _. , , _ _ _ _ . , _ . ~ . _ _ _ . . , . , _ _ .

. . .I '

VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1992 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA-w_----

i-Rev. O Dage 9.4.2-1 l'

VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 9.4.2 PRIMARY CONTAINMENT-AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uci/cc)

Time Isotope Prior to 0930 0930-0945 0945-1000 1000-1015 I-131

• 1.3E-02 2.8E-02 4.2E-02 I-132

• 1.8E-02 3.6E-02 5.0E-02.

I-133

• 2.6E-02 5.5E-02 8.1E-02 I-134

• 2.5E-02 4.4E-02 5.4E-02 I-135

• 2.4E-02 -5.0E-02 -7.2E-02 Total Iodine

• 1.1E-01 2.1E-01 3.0E-01 I-131 Dose

• 2.3E-02 4.9E-02 7.2E-02 Equivalent Kr-b3m

• 1.4E-01 2.8E-01 4.0E-01 Kr-85m

• 3.1E-01 6.3E-01 9.1E-01 1 Kr-85

• 1.5E-02 3.1E-02 4.7E-02 Kr-87

• 5.3E-01 9.8E-01 1.3E+00 Kr-88

• 7.6E-01 1.5E+00 2.2E+00 Xe-133m

• 7.8E-02 1-.6E-01 2.5E-01 Xe-133

• 2.6F+00 5.6E+00- 8.4E+00 Xe-135m

• 4.4E-01 6.0E-01 6.2E-01 Xe-135

• 5.9E-01 1.3E+00 1.9E+00

-Total Noble'

• 5.5E+00 1.1E+01 1.6E+01 Gas Note: Primary containment sample dose. rate provided in Section 9.5.2.

• Prior to 1200 containment air activity is below MDA.

. . . . .. ______i'__m.____.

Rev. O Page'9.4.2-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 s

9.4.2 PRIMARY C

________ ONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uci/cc) -

Time Isotope 1015-1030 1030-1045 1045-1100 1100-1115-I-l'11 5.SE-02 6.BE 7.3E 7.7E ~I I-132 6.2E-02 7.1E-02 7.0E-02 6.9E-02' l I-133 1.1E-01 1.3E-01 1.4E-01 1.5E-01 I I-134 5.9E-02 6.0E-02 5.3E-02 4.6E I I-135 9.4E-02 1.1E-01 1.2E-01 1.2E-01 Total Iodino 3.8E-01 4.4E-01 4.5E-01. 4.6E-01 I-131 Doso 9.5E-02 1.2E-01 1.2E-01 1.3E-01 Equivalent Kr-83m 5.0E-01 5.9E-01 5.8E-01 5.7E-01 Kr-85m 1.2E+00 -1.4E+00 -1.4E+00 1.4E+00 Kr-85 6.3E-02 _7.7E-02 8.2E-02; 8.8E-02 Kr-87 1.5E+00 1.6E+00 -1.5E+00, 1.4E+00' Kr-68 2.7E+00 -3.2E+00 3.2E+00- 3.2E+00 Xe-133m 3.3E-01 4.0E-01 4.3E-01 4.5E-011 Xe-133- 1.1E+01 1.4E+01 1.5E+01 1.6E+01 Xe-135m 6.1E-01 5.8E-01 -3.9E 2.9E-01 Xe-135 2.6E+00 3.3E+00 3.5E+00- 3.7E+00 Total Noblo 2.1E+01 2.5E+01 2.6E+01 2.7E+01 Gas Note: Primary containment sample dose:rato provided in Section 9.5.2.

-I

l l

l

.i Rev. 0-Page 9.4.2-3 VERMONT YANKEE NUCLEAR POWER STATION E'MERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY-DATA A. Primary Containment Air Activity ConOen2 rations (uci/cc)

Time Isotope 1115-1130 1130-1145 1145-1200 I-131- 8.2E-02 8.6E-02 9.1E-02 I-132 6.8E-02 6.7E-02 6.5E-02 I-133 1.5E-01 1.6E-01 1.7E-01 1-134 4.0E-02 3.5E-02 3.0E-02 I-135 1.3E-01 1.3E-01 3.2E-02 Total Iodine 4.7E-01 4.EE-01 3.9E-01 I-131 Dose 1.4E-01 1.4E-01 1.4E-01 Equivalent Kr-83m 5.6E-01 5.5E-01 5.5E-01 Kr-85m 1.5E+00 1.5E+00 1.5E+00 Kr-85 9.3E-02 9.8E-02 1.0E-01 Kr-87 1.3E+00. 1.2E+00' 1.1E+00 Kr-88 3.2E+00 3.2E+00 3.1E+00.

Xe-133m 4.8E .5.0E 5.3E-01 Xe-133 1.6E+01 1.7E+01 1.8E+0' Xe-135m 2.4E-01 2.1E-01' 2. 0E* '

Xe-135 3.9E+00 4.1E+00 4.4E+

Total-Noble 2.8E+01- 2.9E+01 3.0E+01-Gas

. Note: Primary containment sample dose rate _provided in Section 9.5.2.

.. _ .. ... . .. .,n.

. . . . . _._._____.__._____.1 ___ . _ _ ___.

t-VERMONT YANKEE NUCLEAR P0k'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE:

s' 1992 9.4.3 . REACTOR BUILDING AIR ACTIVITY DATA 4

's, .

, Rev. O

! Page 9.4.3-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA A. Reactor Building Air Activity Concentrations (uCi/cc)-

A13 elevations - See Notes Below d

Time Isotope 0700-1200 I-131

• I-132

• I-133

• I-134

• I-135

• Total Iodine -*

' 131 Dose iquivalent Kr-83m

• Kr-85m

• Kr-85

• Kr-87

• Kr-88

• Xe-131m"

• Xe-133m

• Xe-133

• Xe-135m

• Xe-135

• Total Noble

• Gas Notes:-

1. (*) Denotes Activity Concentr" tion below MDL.

2. Reactor Building air sample dose rates provided in'Section 9.5.3.-

i e

- ______J

f f

1 1

i VEPJ10NT YANKEE NUCLEAR POWER STATION 1

- EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 l

9,5 RADIOLOGICAL SAMPLE DOSE RATES-t i

h 1

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4 J

d J

f 1

d' m ,

Rev. O i L Page 9.5.1-1

- VERMONY YANKEE NUCLEAR POWER STATIOli EMERGEliCY RESPONSE PREPAREDNESS EXERCISE

. 1992 9.501 Reactor Coolant Sample Dose Rates

!A. Gas Samples Unshielded (mR/hr per cc)* Shielded (1 in. lead in mR/hr per cc)*

Time Contact 1 ft Contact 1 ft P3ior to 0930 1.4E-02 9.8E-05 1.7E-04 1.2E-06 i

~0930-0945 8.1E+01 5.6E-01 9.9E-01 7.0E-03

.0945-1000 1.6E+02 1.1E+00 1.9E+00 1.4E-02 4

1000-1015 2.0E+02 1.4E+00 2.4E+00 1.7E-02 1015-1030 2.3E+02 1.6E+00 2.8E+00 2.0E-02 0-1045 1.3E+03 9.2E+00 1.6E+01 1.2E-01 1045-1100 2.7E+02 1.9E+00 3.3E+00 2.3E-02 1100-1115 2.9E+02 2.0E+00 3.5E+00 2.5E-02 1115-1130 2.9E+02 2.0E+00 3.5E+00 - 2.5E-02

. 1130-114.C , 3.2E+02 2.2E+00 3.9E+00 2.8E-02 3.2E+02 2.2E+00 3.9E+00 2.8E-02 l1145-1200 1

. Notes:

• Value must be multipli4d by the sample volume in cubic centimeters

! for gas samples to obt;ain the samp12 dose rate in mR/hr.

a 5

. - - - , , , , , + , . . - , , 7

Rov. 0 Page 9.5 3-2

't VERMONY YANKEE NUCLEAR POWER-STATION

[ EMPRGENCY Pw1PONSE PREPAREDNESS EXERCISE 1992 9.5.1 Reactor Coolant Sample Dose Rates ,

'B. L'. quid (Iodint) i Unshielded (mR/hr per cc)* Shielded (1 in. lead in mR/hr per cc)*  ;

Time Contact 1 ft Contact 1 ft ,

c Prior to l 4

0930 1.SE-02 1.OE-04 1.9E-04 1.3E-06 ,

0930-0945 1.2E+04 8.1E+01 1.5E+02 9.9E-01

(

0945-1000 1.1E+04 7.6E+01 1.4E+02 9.3E-01 1000-1015 1.0E+04 7.0E+01 1.3E+02 8.6E--01

! *015-1030 a 1.OE+04 7.0E+01 1.3E+02 8.6E-01 30-1045 9.4E+03 6.5E+01 1.2E+02 7.9E-01 1045-1100 8.6E+03 6.0E+01 1.1E+02 7.3E-01 1100-1115 8.6E+03 6.0E+01 1.1E+02 7.3E-01 1115-1130 B.6E+03 6.0E+01 1.1E+02 7.3E-01 1130-1145 5.8E+03 5.4E+01 9.8E+01 6.6E 01 1145-1200 7.6E+03 5.3E+01 -9.6E+01 -6.5E 4 Notes:

• Values must be multiplied by the samp'.e volume in milliliters for liquic. samples to obtain the sample dose rate in mR/hr.

i 1

4 J

l 4

Rev. O Page 9.5.2-1 VF.RMoliY YAliKEE liUCLEAL POWER STATIOli  !

EMERGEllCY RE iPOllSE PREPARED:iESS EXERCISE 1992 9.5.2 Primary Containment Sample Dose Ratob A. Gas Samples Unchielded (mR/hr per cc)* Shiebied (1 in. lend in mR/hr per cc)*

Contact 1 ft Contact 1 ft  ;

Tin'.

Prior to 0930 As Read As Read As Road As Road 0930-0945 1.6E+00 1.1E-02 2.0E-02 1.4E-04 0945-1000 3.2E+00 2.2E-02 3.9E-02 2.8E-04 1000-1015 4.GE+00 3.~4E-02 5.7E-02 4.0E-04 1015-1030 6.0E+00 4.2E-02 7.5E-02 5.3E-04 1030-1045 7.2E+00 5.0E-02 8.9E-02 6.3E-04 1045-1100 7.5E+00 5.2E-02 9.2E-02 6.5E-04 ,

. 00-1115 ' . 8E+ 0 0 5.4E-02 9.6E-02 6.8E-04 1115-1130 8.1E+00 5.GE-02 1.qE-01 7.0Ea04 1130-1145 8.41+00 5.8E-02 1.0E-01 7.3E-04 1145-1200 8.6Et00 6.0E-02 1.1E-01 7.5E-04 1

110tes :

• Values must be multiplied by the t+2ple volume in cubic centimeters for gas samples to obtain the sample done rate in mR/hr.

?

f

-c.e4 yy -ea -- + ..v,y ., . c - v, , vy-- - - - - - e.y--- , - - - - + - -w-- -ew g-..w,---

• y-

Rav. 0 -

Page 9.5.3-1 k VERMOllY YA!!KEE !TUCLEAR POWER STATIOli EMERGE!!CY RESPollSE PREPARED!iESS EXERCISE 1992 9.5.3 Reactor Building Air Sample Dose Rates (Iodine Cartridge Only) ... ....____ .

All elevations - Sco llotes Below Unshielded (mR/hr per cc)

• Shielded (1 in. lead in mR/hr per cc)* ....___ . . ... . _ . ___

Time Contact 1 ft Contact 1 ft 0700-1200 As Road As Road As Road As Road 7

sto values must be multiplied by the sample volume in cubic contimeters to obtain the sample dose rato in mR/hr.

t I

f l

t l

l 4

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

. i i I

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Page 9.5.4-1 3

i

, VERMollY YA! WEE liUCLEAR POWER STATIOli i

EMERGE!1CY RESPO!1SE PREPARED!iESS EXERCISE 1992 i'

j 9.5.4 Plant Vont Stack Sample Dose Rates l A. Gas (Grab Sample)

Unshioided (mR/hr por cc)* Shielded (1 in. load in mR/hr per cc)*

Time Contact 1 ft Contact 1 ft

'l 0700-1200 As Road As Road As Road As Road i

l Ae Values must be multiplied by the sample volume in cubic contimeters j to obtain the sample dose rates in nr/hr.

i j

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Rev. O Page 9.5.4-2 j VERMOliY YAliKEE llUCLEAR POWER STATIOli EMERGEllCY RESPO!!SE PREPARED 11ESS EXERCISE 1992 r

9.5.4 Plant Vent Stack Sample Doso Ratos

p. Air Sattplo (Iodino Cartridge)

Unshioided (mR/hr por cc)* Shielded (1 in. lead in mR/hr por cc)* ,

Time Contact 1 ft Contact 1 ft i 0700-1200 As Road As Road As Road As Read 6

i floto: Values must be multiplied by the cample volume in cubic contimeters to obtain the samplo dose rates in mR/hr. ,

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5 Rev. O i Page 9.5.4-3 1 VERl40!iY YAllKEE INCLEAR POWEA STATIO11  !

EMERGE! ICY RESPollSE PREPARED!iESS EXERCISE 1992 1

9.5.4 Plant Vent Stack Sample Dose Rates

. . . . . .. .._ _ t C. General Area Exposure Rates at Stack (R/hr) 1 Time At Stack Door Inside 0700-1200 As Read

• As Road *

• Background as read on survey meter.

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EMERGENCY RESPONSE PREPAREDNESS EXERCISE >

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, 9.6 PLWT VENT STACK RELEASE DATA A. Plant Vent Stack Activity Release Concentrations (uci/cc)

• Time Isotope 0700-1200 I-131 3.3E-13 I-132 4.8E-13 I-133 7.5E-13 I-134 6.6E-13 I-135 6.3E-13 Total Iodino 2 . '.' I- 12 I-131 Dose 6.1E-13 Equivalent Kr-83m **

Kr-85m **

Kr-85 **

Kr-87 **

Kr-88 **

Xe-133 **

Xe-135m **

Xe-135 **

Total Noble ** '

Gas {

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• Activity concentrations (in uCi/cc) may be converted to activity release rates (uCi/sec) by multiplying by the assumed stack flow rate of 4.9E7 cc/sec.

• • Noble gas release rates are minimal at this time and below MDA of the multi-channel analyzor.

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

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 10 0 METEOROLOGICAL DATA i

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 10.1 ON SITE METEOROLOGICAL DATA

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Revision 0 l( Page 10,1d .

1 VERMONT YANKEE NUCLEAR POWER STATION

] EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1992 li i

10.1 O_N SITE METEOROLOGICAL DATA (07:00 - 08:30)

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, 07.00 07:15 07:30 07:45 08:00 08:15 08:30 j LOWSAV AVG LOWER SPEED MPH 3.2 3.0 2.4 2.8 2.1 3.0 2.1 UPWSAV AVG UPPER SPEED MPH 3.0- 3.1 2.8 2.9 2.3 2.8 2.5 LOWDAV AVG LOWER DIR DEGS 194 193 155 127 137 125 159 i LOWDSD AVG LOWER DlR SIGMA 12 11 25 26 23 25' 39  ;

4 UPWDAV AVG UPPER DIR DEGS 156 165 172 147- 155 128- 144- '

! UPWDSD AVG UPPER DIR SIGMA 14 16- 19 36 28 17- 34 '

LOTTAV AVG LOWER TEMP DEGS (F) 56.6 56.8 57.0 57.2 57.4 57.6 57.7 i

-0.5 0.5 0.5 0.6 0.7 LODTAV AVG LOWER DELTA T DEGS (Fl' -0.8 0,6

UPDTAV AVG UPPER DELTA T DEGS (F)* 0.6 0.8 -0.9 0.9 1.0 1.1 0.9 SOLRAV AVG SOLAR RAD LANGS 0.00 0.01 0.02 0.03 0.04 0.05 0.07 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00- 0.00 0.00 0.00 0.00' O.00

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. T.kna t 08:45 09 00 09:15 M.;3D 09:45 10:00 10:15 '

, LOWSAV AVG LOWER SPEED MPH 2.4 2.8 4.6 . 3.9 3.7 4.9- 5.8 4

UPWSAV AVG UPPER SPEED Mi>H 2.5 ' 2.9 3.9 4.1 - 3.9 5.1 7.3 '

LOWDAV AVG LOWER DIR DEGS 136 109 '113 122 114 111 108 LOWDSD AVG LOWER DlR SIGMA 34 34 17 20- -27 14' 17 i UPWDAV AVG UPPER DlR DEGS 154 129 129 :127 130 123 122 i' UPWDSD AVG UPPER DlR SIGMA 28 20 14 14- 17 12 7 i LOTTAV AVG LOWER TEMP DEGS (F) 57.9' 58.4 58.5 58.8 59.4 59.7 60.3

, LODTAV AVG LOWER DELTA T DEGS (F)* -0,7 0.9 0.8 -- 1.0 1.2 1.2 1.4 *

UPDTAV AVG UPPER DELTA T DEGS (F)* 1.0 1.2 1.2 1.3 1.6 .41.6 1.8

!' SOLRAV AVG SOLAR RAD LANGS~ 0.10 0.11 0.12 0.15 0.18 0.22 'O.41

, RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00- 0.00 0.00 0.00 - 0.00 1 s

l l ' NOTES:

j 1. The height differential (Ah) for the lower delta temperature on the primary tower is 165 feet.

2. The height differential (Ah) for the upper detta temperature on the primary tower is 262 feet, >

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Revision 0 Page 10.12

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VERMONT YANKEE NUCLEAR POWER STATION EMERGEfA7 RESPONSE PREPAREDNESS EXERCISE 1992 i

10.1 ON SITE METEOROLOGICAL DATA (10:30 12:00)

Time 1Q11Q 10:45 11:00 11:15 11:30 11:45 12,00 LOWSAV AVG LOWER SPEED MPH 5.5 5.2 5.9 5.1 5.9 5.3 5.6 UPWSAV AVG UPPER dPEED MPH 7.8 6.8 5.4 5.5 5.9 5.6 7.3 LOWDAV AVG LOWER DlR DEGS 112 090 084 099 093 070 091 LOWDSD AVG LOWER DlR SIGMA 20 19 16 20 18 16 23 UPWDAV AVG UPPER DlR DEGS 116 115 120 113 108 096 121 UPWDSD AVG UPPER DlR SIGMA 8 8 14 8 10 10 10-LOTT AV AVG LOWER TEMP DEGS (F) 61.5 62.6 63.9 65.7 67.2 68.7 71.3 LODTAV AVG LOWER DELTA T DEGS (F)* 1.7 . 1.9 2.0 2.2 1.5 1.3 1.4 UPDTAV AVG UPPER DELTA T DEGS (F)* 2.2 2.4 2.5 2.6 1.3 1.4 1.8 SOLRAV AVG SOLAR RAD LANGS 0.84 0.61 0.59 0.83 1.03 1.05 1.06 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 (12:15 13:45)

Time 121M 12:30 12:45 M;QQ M1H 13:30 13:45 LOWSAV AVG LOWER SPEED MPH 5.3 7.5 8.5 8.0 7.2 7.1 7.1 UPWSAV AVG UPPER SPEED MPH 7.4 10.1 10.8 10.1 9.3 9.4 8.5 LOWDAV AVG LOWER DIR DEGS SS1 163 163 167 161 159 168 LOWDSD AVG LOWER DIR SIGMA 32 15 -20 16 18 in 16 UPWDAV AVG UPPER DIR DEGS 146 163 157 163 160 158 165 UPWDSD AVG UPPER DlR SIGMA 22 8 9 6 11 7 9 LOTTAV AVG LOWER TEMP DEGS (F) 73.6 75.1 75.7 75.9 76.4 76.9 77.4 LODTAV AVG LOWER DELTA T DEGS (F)* 1.5 1.5 1,6 -1.5 1.5 1.5 1.5 UPDTAV AVG UPPER DELTA T DEGS (F)* 2.0 2.1 2.2 2.1 2.0 2.1 2.1 SOLRAV AVG SOLAR RAD LANGS 1.07. 1.07 1.05 1.03 1.00 0.95 0.93 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 T OTfj:

1. The he10 ht differential (Ah) for the lower delta temperature on the primary tower is 165 feet, i 2. The height differential (Ah) for the upper delta temperature on the primary tower is 262 feet, i-I

Revision 0 Page 10.13 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 10.1 ON SITE METEOROLOGICAL DATA (14:00 15:30) lim 2 lifD .14:15 .14:30 .14.:45 15:00 15115 1513D 7.0 8.2 6.5 LOWSAV AVG LOWER SPEED MPH 6.9 8.0 7.9 8.1 UPWSAV AVG UPPER SPEED MPH 9.0 9.7 10.3 9.2 10.8 12.1 9.8 LOWDAV AVG LOWER DIR DEGS 165 162 165 165 162 161 174

LOWDSD AVG LOWER DIR SIGMA 14 12 14 13 14 14 12 UPWDAV AVG UPPER DlR DEGS 161 155 159 158 160 160 165 UPWDSD AVG UPPER DIR SIGMA 8 7 6 7 E 5 7 LOTTAV AVG LOWER TEMP DEGS (F) 77.6 77.6 78.0 78.1 78.2 78.2 78.2 LOD 1 AV AVG LOWER DELTA T DEGS (Fl* 1.4 1.3 1.2 1.2 1.1 1.1 1.0 UPDTAV AVG UPPER DELTA T DEGS (F)' 2.0 1.9 1.8 1.7 1.7 1.7 1,6 SOLRAV AVG SOLAR RAD LANGS 0.88 0.81 0.78 0.72 0.68 0.62 -0.40 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 (15:45 17:15) lim 9 15:45 16 00 16.15 16:30 16:45 .17.00 17:15 LOWSAV AVG LOWER SPEED MPH 6.7 6.2 5.8 6.1 5.3 4.1 3.7 UPWSAV AVG UPPER SPEED MPH 10.3' 9.0 8.2 9.6 8.2 6.4 7.1  :

LOWDAV AVG LOWER DIR DEGS 161 172 179 189 194 193 201 LOWDSD AVG LOWER DlR SIGMA 15 14 12 14 9 9 9 I UPWDAV AVG UPPER DIR DEGS 162 174 180 185 193 193 193 UPWDSD AVG UPPER DlR SIGMA 6 10 9 7 6 8 6 i LOTTAV AVG LOWER TEMP DEGS (F) 78.2 78.0 77.9 77.6- 77.1 76.8 76.0 LODTAV AVG LOWER DELTA T DEGS (Fl* -0.9 -0.8 0.7 -0.6 -0.5 -0.3 0.2 UPDTAV AVG UPPER DELTA T DEGS (F)' 1.5 1.4 1.3 1.1 0.9 0.8 -0.2 4 SOLRAV AVG SOLAR RAD LANGS 0.22 0.36 0.32 0.29 0.22 0.15 0.08 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 t

• NOTE S:

1. The height differential (Ah) for the lower delta ternperature on the primary tower is 165 feet.

2. The height differential (Ah) for the upper delta temperature on the primary tower is 262 feet.

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4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 10.2 GENERAL AREA NATIONAL WEATHER SERVICE (NWS) FORECASTS

Revision 0 Page 10.21

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, VERMONT YANKEE NUCLEAR POWER STATION 1 EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 I

i 10.2 GENERAL ARE A NWS FORECASTS (See Note)-

Synoosts 107:00)

A weak high pressure ridge centered in the Gulf of Maine will tornain nearly stationary over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A weak frontal boundary extending southwestward from a low centered over Hudson's Bay will drif t eastward slowly.

J DJjd (07:0011:001 l Mostly sunny this morning. Temperatures rising through the 60's. East to southeast winds around 5 M PH.

4 yelid (11:0017:09)

Mostly sunny and warm this af ternoon. High temperatures in the upper 70's. South to southeast winds 5 to 10 MPH.

Vaild (17:00 23 00)

Clear and cool this evening. Temperatures dropping into the 50's. South to southwest winds around 5 MPH...becoming light and variable.

i PLANT / EOF WEATHER OBSERVATIONS (See Note) Valid (07:0017:00)

Time QS,,nfral n Observations 07:00 Clear with light winds.

4 08:00 Sunny with light winds.

09:00 Surmy with light winds.

10:00 Sunny with light winds.

11:00 Partly cloudy with light winds.

12:00 Sunny with light to moderate winds.

13:00 Sunny and warm with light to moderate winds.

14:00 Sunny and warm with light to moderate winds.

15:00 Sunny and warm with light to moderate winds.

16:00 Partly cloudy and warm with light to moderate winds.

17:00 Mostly sunny with light winds.

NOTE: GENERAL AREA NWS FORECASTS SHOULD BE PROVIDED UPON REQUEST. PLANT / EOF WE ATHER OBSERVATIONS Will BE POSTED AS APPROPRIATE.

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Revision 0 Page 10.2 2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 10.2 YERMONT YANKEE SITE FORECAST i

To be provided to the ESC Meteorolo.21st by the ESC Controller at 09:00.

WEATHER FORECAGT FOR SITE: VY VERNON Date of Forecast: ._ 0 9 -0 2 9 2,,,

Time of Forecast: 09:00 Current Site Meteorology (as of 09:00 _ ):

Sensor Wind Snged Wind Direction EglEg Sh Precioltation Temoorsture R!an Lower 2.8 MPH 109 DEG FROM -0.9 DEG F D 0.00 IN/15 MIN Upper 2.9 MPH 129 DEG FROM 1.2 DEG F D Forecast Site Meteorology:

Iltng Senso- y/ind Saeed Wind Direction Qgha SA Precieltation Iemocrature C1pjj 09:00- Lower 5.0 MPH 110 DEG FROM 1.4 DEG F C 11:00 0.00 IN/15 MIN Upper 6.0 MPH 120 DEG FROM 1.8 DEG F D 11:00- Lower 6.0 MPH 120 DEG FROM 1,6 DEG F B 13:00 0.00 IN/15 MIN Upper 8.0 MPH 130 DEG FROM 1.9 DEG F D i 13:00- Lower 7.0 MPH 160 DEG FROM 1.3 DEG F D 15:00 -

0.00 IN/15 MIN Upper 10.0 MPH 160 DEG FROM 1.9 DEG F D National Weather Service Forecast for site region:

Mostly sunny this morning. Temperatures rising through the 60's. East to southeast winds around 5 MPH.

Special K ather Statements:

NONE

Revision 0 Page 10.2 3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1992 10.2 VERMONT YANKEE SITE FORECAST Ip._hjtmovided to the ESC Meteoroloaist by the ESC Controller at 11:00.

WEATHER FORECAST FOR SITE: VY - VERNON.

Date of Forecast: _09 02 92 Time of Forecast: 11:00 Current Site Meteorology (as of 11:00 ):

n SfnJs.I Wind Sn. pad Wind Direction Dg!13 h Precloltetton Temoereigtg Gang Lower 5.9 MPH 084 DEG FROM 2.0 DEG F A 0.00 INI15 MIN Upper 5.4 MPH 120 DEG FROM 2.5 DEG F B Forecast Site Meteorology:

Time Sansor Wind Speed Wind Direction l Ef1A M Precioltation Temocraturg Qant 11:00- Lower 6.0 MPH 120 DEG FROM 1.6 DEG F B 13:00 0.00 IN/15 MIN Upper 8.0 MPH 130 DEG FROM 1.9 DEG F D 13:00- Lower 7.0 MPH 160 DEG FROM 1.3 DEG F D 15:00 0.00 IN/15 MIN Upper 10.0 MPH 160 DEG FROM -1.9 DEG F D 15:00- Lower 6.0 MPH 180 DEG FROM -0.7 DEG F D 17:00 0.00 IN/15 MIN Upper 9.0 MPH 180 DEG FROM 1.3 DEG F D National Weather Service Forecast for site region:

.Mostly sunny and warm this af ternoon. High temperatures in the upper 70's. South to southeast winds 5 to 10 MPH.

Special Weather Statements:

NONE j

t Revision 0 j Page 10.24 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE  !

1992 {

10.2 VERMONT YANKEE SITE FORECAST f To be provided to the ESC Meteoroloalst by the ESC Controiler at 13:00.

[

WEATHER FORECAST FOR SITE: VY VERNON t Date of Forecast: 09 02 92 Time of Forecast: 13:00 Current Site Meteorology (as of 13:00 ):

Sensor Wind Sooed . Wind Diraction ~ Qg!13 313b Procloltation

- Iemper11uta Gla11  :

Lower 8.0 MPH 167 DEG FROM 1.5 DEG F - C  :

0.00 IN/16 MIN Upper 10.1 MPH 163 DEG FROM 2.1 DEG F D Forecast Site Meteorology: +

Time Sensof Wind Soeed Wind Direction Dalla 5.11b Precloltation Temoeratura C!all 13:00 Lower 7.0 MPH 160 DEG FROM 1.3 DEG F D 15:00 .

0.00 IN/15 MIN U ; er 10.0 MPH 160 DEG FROM 1.9 DEG F D -

T5:00 Lower 6.0 MPH 180 DEG FROM 0.7 DEG F D 17:00 . =

0.00 IN/15 MIN Upper 9.0 MPH 180 DEG FROM 1,3 DEG F . D 17:00 Lower 3.0 MPH 200 DEG FROM ' 2.5 DEG F F 19:00 .

0.00 IN/15 MIN Upper 7.0 MPH 180 DEG FROM 2.6 DEG F F

-r National Weather Service Forecast for site region: -l Mostly sunny and warm this af ternoon. High temperatures in the upper 70's. South to southeast winds 5 to 10 MPH.

Clear and cool this evening. Temperatures dropping into the 50's South to southwest winds around ,

5 MPH...becoming light and variable.

Special Weather Statoments:

2 >

NONE r

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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESR EXERCISE

• 1092 10.3 NATIONAL WEATHER SERVICE SURFACE MAPS

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