ML20154M577

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Emergency Response & Evaluation 1988 Exercise
ML20154M577
Person / Time
Site: Maine Yankee
Issue date: 08/08/1988
From:
Maine Yankee
To:
References
NUDOCS 8809290033
Download: ML20154M577 (240)


Text

I MAINE YANKEE ATOMIC POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1988 l

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1475e/2.161 I g\ l' GGO9290033 G30503 PDR ADOCK 0"000309 PDC F

Rev. 1 8/08/88 MAINE YANKEE ATOMIC POWER STATIF.

EMERGENCY PREPAREDNESS EXERCISE 1988 TABLE OF CONTENTS Pagg

1.0 INTRODUCTION

1.1 Exercise Schedule........................................... 1.1-1 1.2 Participating Centers / Agencies.............................. 1.2-1 k 1.3 Definitions................................................. 1.3-1 1.4 References.................. ............................... 1.4-1 2.0 EXERCISE OBJECTIVES 2.1 Shine Yankee Atomic Power Station Exercise Objectives...... 2.1-1 0 EXERCISE GUIDELINES AND SCOPE 3.1 Guidelines.................................................. 3.1-1 G 3.2 3.3 Extent of P1ay..............................................

Simulation List.............................................

3.2-1 3.3-1 3.4-1 3.4 Player Instructions.........................................

3.5 Procedure Execution List.................................... 3.5-1 3.6 Exercise Termination Criteria............................... 3.6-1 4.0 CONTROLLER /0BSERVER INFORMATION 4.1 Assignments................................................. 4.1-1 4.2 Exercise Guidance / Evaluation Sheets......................... 4.2-1 5.0 EXERCISE SCENARIO 5.1 Initial Conditions..........................................

5.1-1 5.2 Scenario 0utline............................................ 5.2-1 5.3 Narrative Summary........................................... 5.3-1 f.4 Scenario Time Line.......................................... 5.5-1 5.5 Detailed Sequence of Events................................. 5.6-1 6.0 EXERCISE MESSAGES 6.1 Command Cards...............................................

6.1-1 6.2 Messages Cards.............................................. 6.2-1 7.0 STATION EVENT DATA Events Surmary..............................................

7.1-1 7.1 Event Miniscenarios........................................

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TABLE OF CONTENTS (Continued)

Page 8.0 OPERATIONAL DATA AND PL0TS........................................ 8.0-1 9.0 RADIOLOGICAL DATA 9.1 Area Radiation Monitors..................................... 9.1-1 9.2 Process Radiation Monitors.................................. 9.2-1 9.3 In-Plant Radiation Leve1s................................... 9.3-1 9.4 Plant Chemistry Data........................................ 9.4-1 9.5 Sample Dose Rates........................................... 9.6-1 9.6 Off-Site Monitoring Team Observer Instructions / Data......... 9.7-1 10.0 METEOROLOGICAL DATA 10.1 On-Site Meteorological Data................................ 10.1-1 10.2 General Area National Weather Forecasts.................... 10.2-1 10.3 Na t io na l We a t he r S e r vi c e Ma p s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10.3-1 t

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'sm- / Page 1.1-1 MAINE YANKEE EMERGENCY RESPONSE EXERCISE 1988 1.1 EXERCISE SCHEDULE Date: September 19, 1988 Times 10:00 a.m.

Location: Maine Yankee Informstion Center

Purpose:

Centrol',er/ Observer Briefing Attendees: Phine Yankee and Yankee Atomic Controllers / Observers

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\v Late September 19, 1988 l

Time: As necessary Location: Emergency Response Centers and In-Station Areas Purpose Familiarize Controllers / Observers with Affected Areas I Attendees Controllers / Observers

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- 8/08/88 Page 1.1-2 (s) v Date: September 19, 1988 Times 1:00 p.m.

Location: Maine Yankee Purposes Meeting to Review Exercise Player Instructions Attendees: Players Date: September 19, 1988 Time 2:00 p.m.

~4 cation: Maine Yankee Information Center O

Purpose:

Brief NRC Evaluators Attendecs: Exercise Coordinator, Lead Controllers, and NRC Evaluators

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i Date: September 20, 1988 Time: 8:30 - 1:00 p.m.

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Location: Maine Yankee Emergency Response Centers ,

Purpose:

Emergency Response Exercise Attendees: Maine Yankee Emergency Response Organization, ,

Controllers / Observers, NRC Evaluators. State Division of Health Engineering, Maine Emergency Management A6ency, and

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w Yankee Atomic Engineering Suppcrt Center l i  !

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(,) Page 1.1-3 Date: September 20, 1988 Time: Following Exercise Termination Locations Maine Yankee Emergency Response Centers l

Purpose:

Energency Response Center Exercise Debriefings Attendeest Controllers / Observers / Players (NRC Evaluators welcome)

Date: September 20, 1988 Time: 3:00 p.m.

C) tocation, Maine van,ee inio,mation Cente,

Purpose:

Exereise Debeiefing

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Attendees: Controllers / Observers, Key Participants Date: September 21, 198S Time 10:00 a.m.

L Location: Maine Yankee Information Center

Purpose:

Utility Self-Critique Attendees: Maine Yankee Management NRC Evaluators, and Exercise Controllers (Observers need not attend) 1476e/2.162

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s Date: September 21, 1988

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l Time: Following Utility Self-Critique Location: Maine Yankee Information Center  :

Purpose NRC Exit Meeting i

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Attendees: Maine Yankee Management and NRC Evaluators l t

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'Q Page 1.2-1 MAINE YAhTEE E'tERGENCY PREPAREDNESS EXERCISE 1988 i 1.2 PARTICIPATING CENTERS / AGENCIES l

A. MAINE YAhTEE ATOMIC POWER COMPANY Maine Yankee Atomic Power Station Emergency Operations Facility j Technical Support Center Operations Support Center Simulator (Control Room functions)

Control Room (NRC notification functions only) hecovery Manager's Office B. STATE OF MAINE Maine Emergency Management Ar,ency Division of Health Enginew.ing Maine State Police Other State Agencies, as appropriate O 1477e/26.293

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( ,) Page 1.3-1 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 1.3 DEFINITIONS A. Abbreviations APD - Air Particulate Detector AO - Auxiliary Operator CIS - Containment Isolation Signal CMP - Central Maine Power Company CR - Control Room CR0 - Control Room Operator EAL - Emergency Action Level 7~

ks _/ EC - Emergency Coordinator EOC - Emergency Operations Center i EOF - Emergency Operations Facility ENS - Emergency Notification System ESC - Engineering Support Center FEMA - Federal Emergency Management Agency HPSI - High Pressure Safety Injection KI -

Potassium Iodide LPSI - Low Pressure Safety Injection NG -

Noble Gas MEMA Maine Emergency Management Agency MSL - Main Steam Line MSP - Maine State Police MY -

Maine Yankee MYNSD Maine Yankee Nuclear Support Division OSC - Operations Support Center g OSDE - On-Site Data Evaluator s_- ) PAB - Primary Auxilliary Building PAC -

Protective Actio.. Guide i

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s ,) Page 1.3-2 POD - Pocket Dosimeter PORV - Power Operated Re!.ief Valve PSS - Plant Shift Superintendent PZR - Pressurizer PVS - Primary Vent Stack Q - Release Rate RCP - Reactor Coolant Pump RCS - Reactor Coolant System REA - Radiological Evaluation Assistant RDE - Radiological Data Evaluator RERS - Residual Heat kemoval System RSC - Radiological Sample Coordinator RWST - Refueling Water Storage Tank NSE - Nuclear Safety Engineer SIAS - Safety Injection Actuation Signal

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\s/ SG - Steam Generator SV - Safety Valve TSC - Technical Suppe t Center VCT - Volume Control Tank YNSD - Yankee Nuclear Services Division B. Terminology o Alert - An emergency classification which is defined as an actual or potential substantial degradation of the level of safety of the plant.

o Central Maine - Principle owner of Maine Yankte Power Company Atomic Power Station.

(CMP)

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( Page 1.3-3 o 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 (acting as an umpire), supervising and otherwise assisting as needed.

o Critique - A meeting of key r rticipants in an >

exercise usually beld shortly after its conclusion, to identify weaknesses, deficiencies, and improvements in emergency response capabilities. It may or may not i involve dialogue between players and exercise officials, o Emergency Action - Specific threshold conditions that Levels (EAL) may be used to designate a particular class or level of emergency.

o Emergency Operations - Plant emergency center established Facility below grade in the Staff Building for ,

the purpose of coordinating off-site response.

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

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o General Emergency - Actur.1 or imuninent substantial core  !

degradation or melting with potential

~for loss of containment integrity. [

i Corporate re,sponse group from Maine

o Maine Yankee Nuclear -

Support Division Yankee who provides technical j

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(MYNSD) support to plant and management. 6

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o Observer - A member of an exercise control [

] group. He or she may also serve in a f dual capacity as both a Controller and ,

Observer. Each Observer may be  !

' assigned to one or more activities or l 1 functions for the purpose of ,

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  • evaluating, recording and reporting [

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the strengths and weaknesses, and making recorrrnendations for improvement.

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o Operations Support - The piant center established i Center (OSC) below grade in the Staff Building to I j

p; ovide Operations' support and relief I l

in the event of an accident. ,

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o Public Affairs - Maine Yankee Public Affairs organiza- j

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j Department tion which works out of CMP head- f e

quarters in Augusta. ,

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1 o Scenario - The hypothetical situation, from start f to finish, in an exercise which is the i

4 theme or basis upon which the action ,

l or play of the exercise unfolds. [

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Rev. 1 8/08/88 g Page 1.3-5 o Site Area Emergency - An emergency classification which is defined as actual or likely major failures of plant functions needed for the protection of the public.

o Staff Building - Building outside the security perimeter that houses the EOF, TSC and OSC. Access to the plant is via an underground passage, o Technical Support -

The plant center established Center (TSC) below grade in the Staff Building to provide the Plant Shift Superintendent with adequate evaluation of plant

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b o Unusual Event - An Unusual Event 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.

o Yankee Nuclear - Yankee Atomic Electric Company Services Division Engineering support organization (YNSD) activated by Maine Yankee in order to support activities.

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MAINE YAhTEE EMERGENCY PREPAREDNESS EXERCISE 1988  ;

1.4 REFERENCES

o Maine Yankee Atomic Power Station Emergency Plan.

o Maine Yankee Atomic Power Station Implementing Procedures to the Energency Plan, o Maine Yankee Atomic Power Station. Final Safety Analysis Report.

o State of Maine Radiological Incident Plan, o Yankee Nuclear Services Division Emergency Response Plan (TA', No.12),

o Martin, G. F. et al., "Report ts the NRC on Guidance for Preparing Scenarios for Emergency Preparedness Exere'ses ut Nuclear Generating Stations ." March 1986. L'SNRC, hTREGICS.-335F.

1 o Daily Weather Maps, National keather Service, Climate Analysis Center Washington, DC 2',233.

j o Maine Yankee Statio'. Core Damage Assessment Methodology.

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9/15/88 Page 2.1-1 MAINE YANKEE ATOMIC POWER COMPANY 2.1 1988 EMERGENCY PREPAREDNESS EXERCISE OBJECTIVES A. Control Room

1. Accident Assessment / Emergency Classification ,
a. Demonstrate the ability of the Control Room operators to promptly recognize that emergency action levels have been reached or exceeded and declare the appropriate Emergency Classification.
b. Demonstrate the ability of the Plant Shift Superintendent to initiate coordination and provide control over emergency response activities conducted from the Control Room throughcut the exercise.
2. Notification
a. Demonstrate the ability to notify Maine Yankee emergency response personnel.
b. Demonstrate the ability to notify Federal and O* ate authorities of

() emergency classification in a timely manner.

  • c. Demonstrate the ability to incorporate appropriate protective action recommendations as part of initial notification process, if necessary.
3. Communications
c. Demonstrate the ability to coordinate information with the TSC regarding the status of emergency conditions and in-plant emergency response activities.
  • b. Demonstrate adequate record keeping of events, actions and communications.

B. Technical Support Center

1. Accident Assessment / Emergency Classification
a. Demonstrate the ability of the TSC staff to initiate and coordinate accident assessment,
b. Demonstrate TSC proficiency in assisting the Emergency Coordinator in emergency classification or escalation.
c. Demonstrate the ability to analyze current plant conditions, and s_ identify projected trends and potential consequences.
  • Indicates NKC/ utility identified improvement items from the 1957 exercise.

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2. Direction and Control
a. Demonstrate the activation of the TSC.
b. Demonstrate the primory functional responsibilities and/or problem-solving capabilities of the TSC staff.
3. Comunications
  • a. Demonstrate the adequacy, operability, and effective use of emergency comunications equipment and procedures, including the status board.
b. Demonsteate TSC ability to gather, assess, and disseminate information to other Emergency Response Facilities regarding the status of emergency conditions and emergency response activities.
c. Demonstrate the ability of the TSC staff to direct and coordinate in-plant actions through the OSC.
  • d. Demonstrate adequate record keeping of events, actions, and comunica tions .

C. Emergency Opeq.tions Taellity

1. Direction and Control
  • a. Demonstrate the timely activation of the EOF.
b. Demonstrate the ability of the Emergency Coordinator to maintain comand control over all errergency response activities conducted from the EOF throughout the exercise.
2. Comunication
a. Demonstrate the adequacy, operability, and effective use of emergency comunications equipment and procedures.
b. Demonstrate adequate comunications and transfer of data between the Maine Yankee Emergency Response Facilities, off-site monitoring teams, and the EOT.
c. Demonstrate the ability to conraunicate station status, radiological conditions, and emergency response actions to off-site authorities.
  • d. Deronstrate adequate record keeping of events, actions, and comunications.
  • Indicates htC/ utility identified improvement items from the 1987 exercise.

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3. Radiological Assessment
a. Demonstrate the ability of the EOF staff to deploy off-site monitoring teams in a timely manner.
b. Demonstrate the ability of the of f-site monitoring team personnel to perform dose rate surveys.
c. Demonstrate the ability to perform off-site dose calculations and assess radiological consequences.

l l d. Demonstrate the ability to formulate and implement or-site protective action measures, if necessary.

j e. Demonstrate appropriate health physics practices during the

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l 4 Protective Actions

a. Demonstrate the ability to evaluate monitoring data, of f-site radiological dose projections, and plant conditions to arrive at appropriate protective action recommendations.

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  • b. Demonstrate the ability to make protective action recommendations to off-site authorities.

D. Operations Support Center

1. Direction and Control i
a. Demonstrate the activation of the OSC.
b. Demonstrate the ability of the OSC Coordinator to exercise command control over all emergency response activities conducted f rom the OSC throughout the exercise. Demonstrate command interf ace with the TSC.

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  • c. Demonstrate the ability of the OSC to adequately staf f and conduct functional responsibilities as requested by the TSC.
d. Demonstrate the ability to provide adequate briefings to in-plant teams.
2. Corr ~ ' t ca t irms
  • a. Demonstrate the adequacy, operability. and ef fective use of I conrunications equipment for communications between the OSC and j OSC personnel within the plant.

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  • Indicates NRC/ utility identified improvement items from the 1957 exercise.

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b. Demonstrate the ability to gather, assess, and transfer information regarding the status of plant operational or radiological conditions and the status of OSC activities te OSC staff and other Emergency Response Facilities.
  • c. Demonstrate adequate record keeping of events, actions, and coernunications.
3. Radiological Assessment
a. Demonstrate the ability to direct and coordinate the deployment of on-site repair teams, and maintain / document appropriate radiological controls.

E. Security

1. Demonstrate the ability of the station security organization to effectively implement special security measures, as necessary.

Demonstrate timely accountability of exercise personnel within the I protected area.

3. Demonstrate appropriate access control measures are effectively implemented for the staff building.

F. Recovery

1. Demonstrate, through table top discussions, the establishment of the recovery organization and the formulation of a recovery plan.

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  • Indicates NRC/ utility identified improvement items from the 1987 exercise.

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MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 1

3.1 CUIDELINES ,

I A. Purpore and Scope, l

l This document provides guidance for conducting the 1988 Maine Yankee Emergency Preparedness Exercise. It provides methods for demonstrating emergency response e sability, conducting the exercise !

I and evaluating the results. Section 3.3 summarises the actions to l be simulated by players during the exercise. ,

B. Concepts of Operations and Centrol of the Exercise (

O Maine Ya'.kee will supply official Controllers / Observers for each i

l h w. ten where an emergency response activity is being l comonstratM. Prior to the exercise, the Controllers / Observers will

' i l be y-ovis'td with appropriate maps. materials and evaluation fores.  !

Centerallers/ Observers will distribute infortn.ation to players on l message cards. Controllers will provide advice to Observers and j resolve problems. For scenario purposes Controllers muy be required l to issue command cards to direct the play of some events. The f Exercise Coordinator will be in overall charge of conducting the .

exercise. Major requests for scenario modifications or holding  !

periods must be cleared through the Exercise Coordinator. j f

The exercise initial conditions will be provided to a Control Room [

operations crew located in the simulator by the Control Room / i Simulator Controller also in the simulator. The remaining exercise O message cards will be provided by Controllers / Observers at other l t

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Rev. 0 8/8/38 Page 3.1-2 emergency response facilities at the times indicated by the scenario outline and sequence of events. Other message cards may be issued to players at times required by player actions during the exercise.

Scenario data generated by the simulator is expected to be similar to the data provided in this package. The Control Room / Simulator Controller / Observer will be able to account for any data discrepancies encountered during the scenario. If the simulator should crash during the exercise, the simulator controller will provide all Control Room data appropriate to the scenario verbally to the operators.

As the initiating events are provided to the plant staff, they will determine the nature of the emergency and the implementation of appropriate caergency plan implementing procedures and emergency operating procedures. These procedures are expected to in:1ude a determination of the emergency classification in accordance with the energency plan. Notifications will te 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.

Operators will complete responses as if they were actually responding to the station events. Inconsistencies in the scenario may be intentional and required to provide a basis which tests capabilities of emergency centers to the maximum extent feasible in a limited time. Controllers have the authority to resolve or explain problems that may occur with the scenario during the exercise.

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l Rev. O N 8/8/88 s ,) Page 3.1-3 C. General Guidance for the conduet of the Exercise

1. Sinulating Emergency Actions Some of the exercise objectives will be demonstrated by simulating the associated emergency response actions. Wherever  ;

possible, actions should be carried out. When an emergency l f

response is to be simulated the Controller will provide the players with written directions in the form of a command card l on which actions are to be simulated. [

2. Avoiding _ Violations of Laws Intentional violation of laws is not justifiable during any exercise. To implement this guideline the following actions l must be taken i

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a. All Controllers / Observers and potential exercise i participants must be specifically informed of the need to [

l avoid intentional violation of all federal, state and local laws, regulations, ordinances, statutes and other [

1egal restrictions. The orders of all police, sheriffs or l other authorities should be followed as would normally be  :

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b. Exercise participants will not direct illegal actions l being taken by other exercise participants or members of f the general public, i i
c. Exercise participants will not intentionally take illegal ,

actions when being called out to participate in an  !

f exerelse. Specifically, local traffic laws such as speed O

l laws will be observed, f l

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3. Avoidinz Perronnel and Property Endanzerment Participants and Evaluators will be instructed to avoid ,

endangering property (public or private), other personnel  ;

responding to the exercise, members of the general public, animals and the environment. I l

4 Actions to Minimize Publie Inconvenience t

It is not the intent, nor is it desirable or feasible, to l effectively train or test the public response during the conduct of radiological emergency exercises. Publie ,

inconvenience is to be minimized. l The actions of federal, state and local agencies and nuclear ,

power plant operators receive continuous public notice and scrutinyt therefore the conduct of an exercise could arouse public conearn that an actual energency is occurring. It is ,

important that conversations that can be monitored by the  !

public (radio, loudrpeakers etc.) be prefaced and conclude j with the words, "This_is a drill; This__is a drill." [

l D. Frergency Response implementation and Operations j

1. Initial Notification {

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Initial notification of the emergency classification will be l made by station staff and the states in accordance with l existing emergency plan implementing procedures. Initial (

notification made to 1, cal comunities by the state shall be

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2. Emergency Operations Facility (EOF) Operations ,

The EOF emergency response organization will be activated during this exercise. Data will be distributed and transmitted by Controllers / Observers in the EOF, TSC, Simulator (Control Room), Security and OSC. Meteorological data will be provided to EOF players.

3. Control Room Operations A Control Room emergency response crew will be located in the Simulator during this exercise. Operational data will be provided to operators by the simulator control board and from the Control Room Controller, when necessary, in the form of message or command cards. Meteorological data will be provided to Control Room players.

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5. Technical Support Center (TSC) Operations The TSC emergency response organisation will be activated I during this exercise. TSC infor1mation and direction will come from the Control Room Operators, located in the Simulator.

Data which is norns11y accessible from the Safety Parameter i Display System (SPDS) will be provided to the TSC directly from l the simulator. I

6. Operations Support Center (OSC) Operations l r

The OSC emergency response organisation will be activated during this exercise. Operations Support Center responses, direction and infornation will be comunicated with the Technical Support Center. OSC Controllers / Observers will accompany all OSC teares dispatched during the exercise and will have appropriate operational and radiological data for the players, wuwasA__sm

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7. Off-site Monitoring Teams Off-site monitoring teams will be fully activated and may be dispatched in accordance with existing procedures. Simulated data will be provided to off-site monitoring teams by Exercise Controllers.
8. Media Center Operations The Media Center will not be fully activated and staffed during the exercise. Pre.s releases to the general public and news media vill be simulated. Media Center staff will obtain all necessary information on current status of the exercise through normal communications channels with the EOT. Simulated press releases will be compiled.

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9. Security Operations All security emergency responses appropriate to the exercise scenario will be implemented in accordance with existing procedures. Evacuation and accountability will be -

demons t ra ted . Evacuation of exercise nonratticipants shall be simulated.

E. Exercise Termination 1

' The exercise will be terminated by the Exercise Coordinator when all 1

! emergency response actions have been completed in accordance with 1

the exercise time sequence.

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\/ 'J ns Rev. 3 9/15/88 Page 3.2-1 MAINE YIA'KEE f EMERCSNCY PREPAREDNESS EXERCISE 1988 3.2 OBJECTIVES AND EXTENT OF PIAY Extent of Play A. Control Room

1. Accident Assessment / Emergency Classifiestion 1. The scenario events initiated on the simulator provide operational and
a. Demonstrate the ability of the Control radiological data which allows Centrol Room Room Operators to promptly recognize personnel to detect and classify an that emergency action Icvels have been emergency. Also, the plant Shift reached or exceeded and declare the Superintendent will assume the role of appropriate Emergency Classification. Interim Emrrgency Coordinator until relievet
b. Demonstrate the ability of thn plant Shift Sap (cintendent to initiate coordination and provide command and control over emergency response activities conducted from the Control Room throughout the exercise.
2. Notification 2. Maine Yankee staff, federal, and state authorities shall be notified via pegers,
a. Demonstrate the ability to nutify Maina telephone, alarms, and public address Yankee emergency response persor.nel. systems in accordance with the steps outlined in Procedure 2.50.17 "Emergency
b. Demonstrate the ability to notify Notificacion." A1. communications should Federal and State authorities of the be prefaced with the words "This is a emergency classification in a timcly Drill."

manner.

  • Indicates URC/ utility-identified improvement items from 1987 exercise.

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  • c. Demonstrate the abilary to incocprrate appropriate protective action recommendations as part of icitial notification process, d necessary.
3. Communications 3. Communications shall be demonstrated between the Control Room and TSC via
a. Demonstrate the ability to coordinate telephone and the SPDS. Recordkeeping will information with the ISC regarding the be demonstrated in accordance with existing status of emergency conditiona and procedures. A smooth Control Room log will in-plant emergency responte activ?tjes. he developed from a rough log kept during the exercise.
  • b. Demonstrate adequate recordkeeping of events, actions, and communications.

B. Technical Support Center

1. Accident Assessment /Emergengy Classification
1. The TSC staff will use scenario data provided by the Control Room staff and via
a. Demonstrate the ability of the TSC SPDS to assist in accident assessment and staff to initiate and coordinate determination of corrective acticns and a cident assessment. emergency classification.
b. Demonstrate TSC proficiency in assisting the Emergency Coordinator in emergency classification or escalation.
c. Demonstrate the ability to analyze current plant conditions, and i:ientify projected trends and potential consequences.
  • Indicates NRC/ utility-identified improvement items from 1987 exercise.

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2. Direction and Control 2. Scenario events and exercise play events allow full activation and operation of the
a. Demonstrate the activation of the TSC. TSC.
b. Demonstrate the primary functional responsibilities and/or problem-solving capabilities of the TSC staff.
3. Communications 3. Normal emergency communications links will be established in order to transmit
  • a. Demonstrate the adequacy, operal:ility, information and data. Exercise and effective use of emergency controllers / observers will evaluate the communicatione equipment and accuracy and timeliness of messages.

procedures, including the statas f >oa rd .

The scenario provides events and plant

b. Demonstrate TSC sbility 'o gather, conditions which will enable the TSC to assess, and disseminate is. formation to direct and coordinate in-plant corrective other Emergency Respensc Facilities actions through the OSC.

regarding the statas of emergeocy condicious and emergency response Record keeping will be demonstrated in activities. accordance with exiatie- procedures.

c. Demonstrate the ability of the TSC staff to direct and coordinate in-plant surveys through the OSC.
d. Demonstrate adequate record keeping of events, actions, and communications.
  • Indicates NRC/ utility-identified improvement items from 1987 exercise.

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C. Emergency Operations Facility

1. Direction and Control 1. The EOF will be fully activated during this exercise. All connunications and
  • a. Demonstrate the timely 3ctivation of coordination activities normally conducted the EOF. in the EOF will be addressed. Also, representatives of the state have been
b. Demonstrate the ability of the invited to participate; however, this is a Emergency Coordinator to maintain suull-scale exercise.

command control over all emergency response activities conducted from the EOF throughout the exercise.

2. Communication 2. Connunications and transfer of data between facilities and off-site monitoring teams
a. Demonstrate the adequacy, operability, will be evaluated for timeliness, and effective use of emergency completeness, and accuracy.

connunications equipment and precedures.

Record keeping will be demonstrated in

b. Demonstrate adequate communications and accordance with existing procedures.

transfer of data between the Mais.e Yankee Emergency Response Facilities, Off-Site Monitoring Teams, and the EOF.

c. Demonstrate the ability to conrmianicate station status, radiological conditions, and emergency respo::se actions to off-site authorities.
  • d. Demonstrate adequate record keeping of events, actions, and communications.
  • Indicates NRC/ utility-identified improvement items from 1987 exercise.

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3. Radiological Assessment 3. Off-site monitoring teams will be directed and deployed f rom the EOF, as necessary. ,
a. Demonstrate the abi.11ty of the EOF Off-site monitoring results may be used to staff to deploy off-site monitaring reassess off-site dose projections and the teams in a timely manner. postulated release rate.
b. Demonstrate the ability of the off-site On-site protective actions may be monitoring teams personnel to perform considered along with ALARA health physics dose rate surveys. practices for in-plant sampling activities. Coordination of radiological
c. Demonstrate the ability to perform data will be evaluated by off-site dose calculations and assess controller / observer located in the EOF.

radiological consequences.

d. Demonstrate the ability to formulate An on-site emergency response team should and implement on-site protective action be prepared to demonstrate the appropriate measures, if necessary. use of protective clothing and respirators, as necessary.
e. Demonstrate appropriate health physics practices during the exercise.
4. Protective Actions 4 Protective action recommendations may be formulated based on plant conditions and
a. Demonstrate the ability to evaluate potential release consequences, outlined by monitoring data, of f-site radiological scenario events.

dose projections and plant. conditions to arrive at appropriate protective action recommendations.

b. Demonstrate the ability to make protective action recommendations to off-site authorities.
  • Indicates NRC/ utility-identified improvement items from 1987 exercise.

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j D. Operations Support Center 1

4 l 1. Direction and Control 1. The OSC will be fully activated and staffed

) as required by the exercise events and

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a. Demonstrate the activation of the OSC. in-plant corrective actions will be conducted.

! b. Demonstrate the ability of the OSC Coordinator to exercise command ce,ntrol

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j over all ener?:eney aesponse activities a conducted from the OSC throughcut ihe j exercise. Demonstrate command i interface with TSC.

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  • c. Demonstrate the ability of the OSC to adequately staff and conduct functional responsibilitic.t as requested by the TSC.

) d. Demonstrate the ability to provide j adequate briefia;s to in-plart tears.

1 j 2. Communications 2. All OSC communicailras shall be completed 1 in accordance with existing procedures.

] *a. Demonstrate the adequacy, operability, 4

and effective use of communications Record keeping will be deoonstrated in equipment for commm.ic.itions between accordance with existing procedures.

the OSC and OSC personnel within the plant.

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  • Ind8 cates NRC/ utility-identified improvement items from 1987 exercise.

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b. Demonstrate the ability to gather, assess, and transfer information regarding the status of plant operational or radiolot t eel corditions and the status of OSC activities to OSC staff and other hergency hesponst.

Facilities.

c. Demonstrate adequate record keeping of events, actions, and communicatlans.
3. Radiological Assessment 3. Scenario events will require OSC teams to be dispatched tc investigate plant
a. Demonstrate the ability to direct and systems. Investigation and repair coordinate the deployment of On-Site activities in the plant may require Repair Teams, and maintain / document implementation of radiological survey and appropriate radiological controls. controls including cumulative exposure tracking.

E. Security

1. Demonstrate the ability of the station 1. Security activities will be implemented in security organizatien to effe: Lively accordance with scenario requirements.

Implement special security measures, as Evacuation of selected station staff will necessary. be implemented in order to test accountability. Contractor personnel,

2. Demonstrate timely accountability of however, will be exempt from evacuation exercise personnel within the protected activities, area.
  • Indicates NRC/ utility-identified imprb'.ement items from 1987 exercise.

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3. Demonstrate appropriate access c.3ntrol measures are effectively implemented for the staff building. .

F. Recovery

1. Demonstrate, through table-top discusrions, 1. The recovery discussions will follow the the establishment of the recovery planned time jump and restoration of the organization and the formulation af a plant to a stable condition.

recovery plan.

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  • Indicates NRC/ utility-identif ied improvement. items from l'187 exercise.

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MAINE YAhTEE EMERGENCY PREPAREDNESS EXERCISE 1988 3.3 SIMULATION LIST l

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(> Page 3.3-1 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 3.3 SIMULATION LIST ,

i The following plant actions will be simulated: ,

1. Simulator Operations Crew notifying the NRC on the red phone (NRC will be notified from the Control Room of the start and finish of the exercise).
2. Any issuance of potassium iodide (KI);
3. Personnel and area decontamination; O 4. Collection and analysis of all environmental samples and TLDs;
5. Containment entry; 4 6. Playing of c.11 the prerecorded emergency ocasage tapes on the public informatien telephone;
7. Post-accioent sampling;
8. Plant evacuation of nonparticipants;
9. RWPs for exercise activities; ,
10. Yankee Environmental lab response; and
11. Activation of the PEAS. , h M U. @\ lhhW CL $l ,/
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MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 3.4 PLAYER INSTRUCTIONS The Maine Yankee annual exercise of the Emergency Plan is scheduled for September 20, 1988. The successful demonstration of emergency response capabilities will depend on player response and protocol. General guidelines for the exercise are as follows:

1. Exercise participants include Players, Controllers Observers, NRC Evaluators, and an Exercise Coordinator. Controllers and Observers will provide players with cue and command cards to instigate emergency responses. They will be identified by colored hats and will also evaluate Player actions.
2. Always identify yourself by name and function to the Controllers, Observers, and Evaluators.
3. Play out all actions, as much as possible, in accordsnee with your Euergency Plan and Procedures as 1f it were an actuti emergency. If an action or data is to be sitt.ulated, en Exercise Controller or Observer will provide Players with appropriate directian.

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4. Always identify and discuss your actions '4o the Controllers and l Observers. It is to your advantage to exercise as me.ny appropriate f response actions as possible. l i
3. Periodically speak out loud, identifying your key actions and  !

decisions to the Controllers / Observers. This may seem artificial, l but it will assist the evaluators and is to your benefit.

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6. When you are 1 , signed to complete a response action, be sure to be accompanied by an Exercise Controller or Observer at all times.
7. If you are in doubt about completing a response action, ask your Controller or Observer for clarification. The Controller / Observer will not prompt or coach you. Emergency response actions must not place exercise participants in any potentially hazardous situations.
8. The Controller / Observer will periodically issue messages or instructions designed to initiate response actions. You must accept these messages immediately. They are essential to the successful completion of the exercise.
9. If the Controller intervenes in your response actions and recommends you redirect or reconsider your play actions, it is for a good

( reason. His direction may be essential to the overall success of the exercise for all participating groups.

10. If you disagree with your Controller or Observer, discuss your problem vith him. However, Controllers / Observers final decisions must be follnwed.
11. Respoed to questions in a ti.mtly manner.
12. Dr., not accept any messages /in;>tructions f rom Nhc Evaluators. They are required to work through your Controller / Observer if they want to '.nstigate additicnal emergency conditions.
13. You must play as if radiation levels are actually present in accordance with the information you receive. This may require you to wear additional dosimeters, observe emergency radiation protection practices, and to be aware of and minimize your radiation exposures.

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14. Controllers / Observers / 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 safety and radiological practices and procedures.
15. Utilize status boards and log books as much as possible to document and record your actions.
16. Always begin and end all communications with the words "THIS IS A DRILL " during the exercise so that these comunications are not confused to indicate an actual emergency.
17. Only use procedures from procedures books in the emergency center cabinets. DO NOT USE MARKED UP, OUTDATED COPIES, OR PERSONAL NOTES.
18. Keep a list of items which you believe will improve your plans and procedures. Provide your input to your facility coordinator or Controller / Observer imediately af ter the exeecise.
19. Control Room operators in the simulator should prepare a smooth log at the end of the exercise.
00. All logs, form, messages, and completed procedures should be given tc, y:,ur center controller af ter the center debriefing.
21. The Simulater Contro$ Room PSS should coordinate with the Control Room PSS on initiation of evacuation alarm and NRC notifications on the ENS line (red phone).

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(,)s Page 3.5-1 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 3.5 PROCEDURE EXECUTION LIST Operating Procedures (OP)

OP 1-4 Operations at Power OP 1-6 Reactor Shutdown OP 1-22-6 Backfeeding Buses 3-6 from the 345 kV Yard f

Abnormal Operating Procedures (AOP)

AOP 2-11 Loss of Instrument Bus AOP 2-32 Loss of Secondary Component Cooling l ACP 2-46 Loss of Off-Site Power l

1 Emergency Operating Procedures (EOP)

F-0 Emergency Shutdovu From Power or Safety Injection

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I Rev. 1 8/8/88 l ('] Page 3.5-2 l  %.J ES-1.1 SI Termination FR-H.1 Loss of Secondary Heat Sink Emergency Plan Implementing Procedures (EPIP)

EPIP 2.50.0 Declaration and Categorization of Emergency Condition EPIP 2.50.1 Notification of Unusual Event EPIP 2.50.2 Alert EPIP 2.50.3 Site Area Emergency (h.)

EPIP 2.50.7 Emergency On-Site Radiation Monitoring Procedure i l

l EPIP 2.50.9 Security Fnrce Radiation Emergency Plan l

EPIP 2.50.10 Evaluation of Radiological Data EPIP 2.50.11 Plant Entry atid R4:covery Plan ElIP 2.50.12 Emergency Off-Site Radiation Monitoring Procedure EPIP 2.50.13 Emergency Operations Facility l

EPIP 2.50.14 Emergency Radiation Exposure Control EPIP 2.50.15 Release of Public Information During Emergencies EPIP 2.50.16 Protective Action k2 commendations 1944e/2.174

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Rev. 0 5/26/88 Page 3.6-1 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 3.6 EXERCISE TERMINATION CRITERIA The exercise may be terminated under the following circumstances

a. 't all emergency response actions have been completed in accordance with the exercise time sequence; or
b. If en actual plant ercergency condition develops coincident with the exercise.

In the event that Item b should occur, the following actions will be takent

1. The Plant Shift Superintendent (PSS) will contact the Simulator PSS and inform him of plant status;
2. The Simulator PLS will immediately contact the Energency Coordinator and/or the Plant Manager who, in turn, will immediat.ely inform any j Federal or State representatives s'; the EOF of the nature of the f emergency; ,

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3. Concurrent with the notification in Step 2, the Plant Shift Superintendent will annotmce over the plant Paging System the l following statements i

The emergency plan, exercise has been j terminated. I repeat. The emergency plan '

exercise has been terminated.

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l i emergency class announcement (if appropriate);  ;

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4. The Emergency Preparedness Coordinator'would be responsible for  !

i directing the actions of the Controllers / Observers; and '

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implemented in accordance with the nature of the emergency. [

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MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 4.1 ASSIGNMENTS Center Controller Observer Lead Controller J. Temple Simulator Control Room M. Schwartz Emergency Operations Facility S. Evans J. Hawxhurst, YNSD Technical Support Center D. Whittier W. Metevia, MYP Operational Support Center J. McArdle YNSD R. Sibley B. Lord J. McCann, MYP K. Traegde, YNSD D. McDavitt, YNSD Off-Site Monitoring Teams J. Arms, YNSD E. Saloraon, YNSD C. Albright, D'S D Recovery W. Riethle, YNSD Security J. Gilman, YNSD State EOC and Media Center G. Stowers R. Zikaras, YNSD O 1969e/2.185

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] Page 4.2-1 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 4.2 EXERCISE GUIDANCE / EVALUATION SHEETS Prior to the exercise, each Observer / Controller will be provided the contents of this package and a set of Emergency Plan Implementing Procedures (EPIPs) which correspond to their respective assignments. It is the responsibility of the Observer / Controller to read the contents of this package and review the procedure (s) associated with the assignment.

Prior to the exercise, each Observer / Controller will be requested to attend an Observers / Controllers Briefing Session. During this meeting, each Observer / Controller should identify any questions regarding the package content and/or their assignment. It is the responsibility of each Observer / Controller to ensure thne they are familiar with the various plant locations where their assignment vill take piece. Tours will be provided as a portion of the trainingt however, thae tourt; wil.

be limited in their duration. It may be .dvisable to plan an aMitional tour.

Observers should familiarize themselves rith their assigt,ed Center Controller prior es the exercise. The Coatroller will b resoonsiWe Nr directing observer activities thrwahout the course of the exerciso. At exercisa termination, each Center C,ntroller is responsible for meeting with their Observers and directing their critique and documentation of their exercise cosaments. Each Controller will be responsible for ensuring that this documentation is provided to the Emergency Preparedness Coordinator at the conclusion of the critique session. Each Controller is also responsible for providing a brief sumnary of their Observer connents during the formal critique.

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Rev. 1 8/8/88 (Jg) Page 4.2-2 Observers / Controllers should identify themselves to players and explain their role in the exercise. Observers / Controllers should inform players that if their actions are going to deviate from standard plant or emergency procedures they should tell the Observer why. Observers /

Controllers should keep a detailed time log throughout the exercise, listing all transferred data and player responses. This log and related coments should provide the time, place, and names of involved personnel.

The primary role of exercise Observers / Controllers is to evaluate the emergency responses of the players. In order to document the adequacy of emergency response actions during the exercise. Observers / Controllers are required to complete the Emergency Exercise / Drill Observers Evaluation Form. When completing this form, Observers / Controllers should differentiate their comments into either adequate, needs improvement, potential weakness, or deficiency. For recognized deficiencies of personnel, equipment, etc. provide recomendations for improvement dr.talling corrective /nitigative actier,s. If the evaluation criteria is not applicatie en t.he exercise objectives or the scenario, this should be noted on the eveluatien form also.

Observers / Controllers should ny allow their biases to be docum(nted as cecognized inadequacies. Com.ents and recommendations should be further subdivided according to the folicwing major headirgs: Facility i Activation / Organizational Control. Comunications, Adherence te Plans and Procedures, Equipment Capabilities, Scenario Training, Facility Layout, Off-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Coment s .

Tacility Activation coments should identifyt (1) the time that emergency response personnel were notified (2) when the facility was activated: (3) when initial activities become well organized: (4) whether O 1474e/26.300

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, 8/8/88 Page 4.2-3 personnel performance follows the organized arrangements specified by plant procedures; and (5) the efficiency of methods of authority transfer. If a transfer of responsibility occurs, then the Evaluator should determine if all affected personnel are aware that the transfer has occurred.

Comunication coments should identify: (1) personnel familiarity with emergency comunications use; (2) whether suf f'cient comunications were available to ensure a timely, efficient, and effective flow of information (3) dether there were enough comunications personnel to make use of all available equipment; (4) the adequacy of comunications logs and describe the effectiveness of data transfert (5) whether there were any problems in the design of the existing comunications system (i.e. location relative to traffic flow); (6) whether there were any recognized difficulties in use of computer systems; and whether center status boards are effectively used. Evaluators should document their coments in this area very carefully, providing suf ficient details to  !

track any recognized deficiencies.

Plans and Procedures coments should identify: (1) whether personnel were familiar with the details or overall concepts of applicable

,l procedursst (2) whether situations developed which required deviation t

I from the procedure or plan; (3) whether personnel were overwhelmed with procedural requirements distractieg them from performing their required emergency response function; and (4) whether the procedures adequately >

described the actions required to complete an assigned function. I i

5 Equipment Capability coments should identify: (1) whether all necessary I materials and equipment were available and functionall (2) whether

! emergency response personnel checked operability of equipment prior to conducting their assignment (3) whether backup equipment was readily 1 j

available when malfunctions were reported; (4) whether the available l O systems provide an adequate service; and (5) whether equipment l

Q malfunctions impacted the expected emergency response.

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Scenario _ reisted comments should address: (1) whothet sufficient j inform 6!an was available to ensure appropriate player re:;ponse; (2) ,

{ whether the scenario details deviated f rom actual procedural requirements; and (3) whether the scenario detail provided any prompt to the player. An additional question should be answered by Observers / Controllers concerning the adequacy of the scensrio in keeping the players active and interested throughout the exercise.

Trainina ce ments should identify (1) whether plant personnel have been

provided s'itiicient training to handle "ad hoc" procedural deviations; j and (2) whether training identifies in roper procedural requirements.

4 Coments on Facility 1.ayout 4ficiencies/reconsnendations should identifyt (1) whether the available work space provided was adequate; a

i (2) whether traf fic flow hindered the response ef forts; (3) whether the

! cournunications available in the work area were adecuate; (4) whether the t

' noine level hindered emergency response efforts; and (5) whether 4

sufficient references were availeble to complete the job assignment.

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Off-Site Monitorin; Team should .dentify: (1) the adequacy of sampling methodst (2) the edequacy of reporting and documentation mes4ures; and (3) the effectiveness of the team in defining radiological status. Dose l projection techniques should be evaluated in conjunction with this l

general category. Consideration of dose projection technique deficiency /reconnendations should identifyt (1) the effectiveness of the system in allowing the correct 2nterpretation of off-site conditions; and (2) the effectiveness of using the projection technique in positioning of f-site tea:ns.

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( ) Page 4.2-5 Evaluation of Personnel Dosimetry / Exposure Control _ activities should identify: (1) the timeliness and ef fectiveness of dosimetry distributiont (2) the effectiveness of protective measures; (3) the adequacy of established contamination control access pointst (4) the adequacy of exposure planning measures af forded in plant activities; and (5) the adequacy of decontamination and posting techniques.

The Contro".ler/ Observers will be provided an Evaluation List and Evaluation Form f ound in this section. All such documentation must be provided to the Center Controller prior to the conclusion of the critique.

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MAINE YANKEE l Exercise Evaluation List A. C0hTROL ROOM

1. Accident Assessment / Emergency Classification
a. Did Control Room staff demonstrate the ability to yes/no/NA prceptly recognize that emergency action levels were reached or exceeded and declare the appropriate Emergency Classifications?
b. Did the Plant Shift Superintendent demonstrate the yes/no/NA ability to initiate coordination and provide control over emergency response activities conducted from the p)

( Control Room throughout the exercise?

2. Notification
a. Did Control Room staff demonstrate the ability to yes/no/NA notify Maine Yankee emergency response personnel?
b. Did Control Room staff demonstrate the ability to yes/no/NA l notify Federal and State authorities of emergency
1assification within 15 minutes of the classification? l
  • c. Did Control Room staff demonstrate the ability to yes/no/NA incorporate appropriate protective action recoornendations as part of initial notification process, if necessary? l O N/A - Not applicable.
  • Indicates NRC/ Utility identified improvement iteals from 19S7 exercise.

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3. Comunica tions I P
a. Did Control Room staff demonstrate the ability to yes/no/NA coordinate information with the TSC regarding the status of the emergency conditions and in-plant emergency response activities?
  • b. Did Control Room staff demonstrate the adequate yes/no/NA record keeping of events, actions, and comunications?

B. TECHNICAL SUPPORT CENTER

1. Accident Assessment / Emergency Classification
a. Did the TSC staff demonstrate the ability to initiate M no/NA O- and coordinate accident assessment?
b. tid TSC staff demonstrate proficiency in assisting the /no/NA Emergency Coordinator in emergency classification or escalation?
c. Did TSC staff demonstrate the ability to analyst hno/NA current plant conditions, and identify projected trends and potential consequences?
2. Direction and Control
a. Did the TSC staff demonstrate the ability to activate /no/NA the TSC in a timely manner?

N/A - Not applicable.

  • Indicates NRC/ Utility identified ireprovement items f rom 1987 exercise.

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b. Did the TSC staff demonstrate the primary yes no/NA functional responsibilities and/or problem-solving capabilities?
3. Communi:ation
  • a. Did the TSC staff demonstrate the adequacy, operability, yes/no/NA and ef fective use of emergency communications equipment d ?7 ,

and procedures, including the status board?

b. Did the TSC staff demonstrate the ability to gather, yes/no/NA assess, and disseminate information to other Emerger'y Response Facilities, regarding the status of emergency conditions and emergency response activities?
c. Did the TSC staff demonstrate the ability to direct yes/no/NA

{m}

and cworditiate in-plant actions through the OSC7

  • d. Did the TSC staff demonstrate adequate record keeping yes/no/NA of events, actions, and communications?

C. EMERGENCY OPERATIONS FACILITY

1. Direction and Control
  • a. Did the EOF staff demonstrate the appropriate activation yes/no/NA of the EOF 7 N/A - Not applicable.
  • Indicates NRC/ Utility identified improvement items from the 1987 exercise.

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b. Did the Emergency Coordinator demonstrate the ability yes/no/NA to maintain command and control over all emergency response activities conducted from the EOF throughout the exercise?
2. Communications
a. Did the EOF staff demonstrate the adequacy, operability, yes/no/NA and effective use of emergency communications equipment and procedures?
b. Did the EOF staf f demonstrate adequate communications yes/no/NA and transfer of data between the thint Yankee Emergency Response Facilities, the off-site monitoring teams, and the EOF?
c. Did the EOF staff demonstriste the ability to yes/no/NA communicate 2tation status, radiologieri conditions, and emergency response actions to off-site authori' est i
  • d. Did the EOF staf f demonstrate adequate record keeping of events, actions, and communications?
3. Radiological Assessment
a. Did the EOF staff demonstrate the ability to deploy, yes/no/NA in a timely manner, the of f-site monitoring teams? I i
b. Did the of f-site monf.toring team personnel demon,trate yes/no/NA the ability to perform dose rate surveys? '

s, s N/A - Not applicable.

  • Indicates NRC/ Utility identified improvement items from the 1987 exercise.

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c. Did the EOF staff demonstrate the ability to perform yes/no/NA off-site dose calculations and assess radiciogical consequences?
d. Did the EOF staff demonstrate the ability to formulate yes/no/NA and implement on-site protective action measures, if necessary?
e. Did the EOF staff demonstrate appropriate health physics yes/no/NA <

practices during the exercise?

A. Protective Actions

a. Did the EOF staff demenstrate the ability to evaluate yes/no/NA T monitoring data, off-sito radiological dose

, projections, and plant conditions to arrive at appropriate protective action recommendations?

  • b. Did the EOF staf f demonstrate the at 111ty to yes/no/NA make protective action recommendations to off-site authoritiest i

D. OPERATIONS SUPPORT CENTER l L

1. Direction and Control
a. Did the OSC staff demonstrate activation of the yes/no/NA i OSC in a timely rannert l i

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N/A - Not applicable.

  • Indicates ':RC/ Utility identified improvement items f rom the 19S7 exercise.

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b. Did the OSC Coordinator demonstrate the ability to yes/no/NA exercise comand and control over all ercergency response activities conducted from the OSC throughout the exercise? Did the OSC Coordinator demonstrate command interface with the TSC't
  • c. Did the OSC demonstrate the ability to adequately yes/no/NA staff and conduct functional responsibilities as requested by the TSC?
d. Did the OSC Coordinator demonstrate the ability to yes/no/NA provide adequate briefings M r in-plant teams?
2. Comunications b

v *a. Did the OSC staff demonstrate the acequacy, operability, yes/no/NA and effective use of communications equipment for comunications between the OSC and OSC personnel within the plant?

b. Did the OSC Coordinator demonstrate the ability to yes/no/N/.

gather, assess, and transfer information regarding the status of plant operational or radiological conditions and ti.e status of OSC activities to OSC staff and other Emergency Response Facilitiest

  • c. Did OSC staff demonstrate adequate record keeping of yes/no/NA events, actions, and comunications?

N/A - Not applicable.

  • Indicates NRC/ Utility identified improvement itercs f rom the 1937 exercise.

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3. Radiological Assessment
a. Did the OSC staff demonstrate the ability to direct yes/no/NA and coordinate the deployment of on-site repair teams and maintain / document appropriate radiological controls?

E. SECURITY i

1. Did the station security personnel demonstrate the ability yes/no/NA to effectively implement special security measures, as necessary?
2. Did the s tation security personnel demonstrate the timely yes/no/NA s accountability of exercise personnel within the protected area?
3. Did the station security personnel demonstrate appropriate yes/no/i?A  :

access control measures for the staff buildings?  !

i F. RECOVERY

1. Did the exercise players, through table-top discussions, yes/no/NA demonstrate the establishment of an initial recovery organization and formulate a recovery plant i i

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i N/A - Not applicable.

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Proc. No. 2.50.23

<-~x Rev. No. 3 Page 10 of 14 Pv)

ATTACHMENT B EMERGENCY EXERCISE / DRILL OBSERVERS EVALUATION FORM Observer: _

Name Exercise / Drill Date Exercise / Drill Title _

Time Scarted:

Location of Observer:

Infonnation Provided to Pa. eicipants:

Participar.ts Observed:

Time Information Provided:

b

\~- (Proper use of equipment, correct procedures, effectiveness of Observations:

individual and group action, etc.)

Comments and Recommendations (Specific): __

Use additional pages as required.

Signature Date O 1474e/26.300

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( ) MAIllE YANKEE

'N / EMERGENCY PREPAREDNESS EXERCISE 1988 EMERGENCY RESPONSE EXERCISE / DRILL OBSERVER'S EVALUATION FORM DJ

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b CONTINUED ON ADDITIONAL PAGES YES NO NAME SIGNATURE DATE PAGE OF

MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 EMERGENCY RESPONSE EXERCISE / DRILL OBSERVER'S EVALUATION FORM

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('" ) MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 EliERGENCY RESPONSE EXERCISE / DRILL OBSERVER'S EVALUATION FORM em (x

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CONTINUED ON ADDITIONAL PAGES YES _NO l

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kJ EMERGENCY PREPAREDNESS EXERCIjI 1988 EMERGENCY RESPONSE EXERCISE / DRILL EVALUATOR'S OBSERVATIONS CHRONOLOGICAL LOG TIME OBSERVATION / COMMENT O

AREA NAME EVALUATED DATE PAGE OF

7, MAINE YANKEE (x- j EMERGEllCY PREPAREDNESS EXERCISE 1988 EMERGENCY RESPONSE EXERCISE /_ DRILL EV,ALUATOR'S OBSERVATIONS CHRONOLOGICAL LOG TIME OBSERVATION /COMMEllT O

AREA NAME EVALUATED

- DATE PAGE OF

MAINE YANKEE (v EldERGENCY PREPAREDNESS EXERCISE us.s EMERGENCY RESPONSE EXERCISE / DRILL EVALUATOR'S OBSERVATIONS CHRONOLOGICAL LOG TlHE OBSERVATION / COMMENT s

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AREA NAME EVALUATED DATE PAGE OF

9 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 5.0 EXERCISE SCENARIO O

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/L]N MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 5.1 INITIA!, CONDITIONS (This information will be provided to the Control Room players at the start of the exercise.)

1. The reactor is at approximately 100% rated power. The reactor has been operating near steady state for the past six months, with a 9S%

capacity factor.

2. The P-25B steam-driven auxiliary feedwater pump is out-of-service for extended repairs.

O 3. The reactor coolant activity is 4.49E-02 dose equivalent I-131.

4 All other power generating equipment is operating and all safety system equipment is operable.

5. The following on-site meteorological conditions exist at 0830:

Wind speed, mph (upper / lower) 10.3/4.4 Wind direction, degrees (upper / lower) 193/173 Delta temperature. F (difference) 0.3 Ambient temperature. F 61.0 Precipitation, inches /per 15 minutes 0.0

6. Synoptic (regional) meteorological conditions:

Rain ending this morning, with fog in low lying areas clearing by midday.

K 1963e/4.410

Rev. 1 8/12/88 Page 5.1-2 V

Winds southwesterly 3-5 mph, temperatures mid 70s by afternoon.

Winds will shift to westerly as a cool frent makes it way through the forecast area this evening.

As the warm front moves further north, warm southerly flow will continue through this afternoon. The cold front expected this evening will bring an occasional shower and cooler temperatures tomorrow.

7. Initial plant and reactor system values are attached (Table 5.1-1).

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v TABLE 5.1-1 initial Plant and Reactor System Values RCS Pressure 2,226 psia Containment Pressure 16.09 psia Containment Radiation <1.0 R/hr Hottest CET 604.3 of No. 1 S/G Level 319 inchew (65%)

No. 1 S/G Pressure 854 psia No. 2 S/G Level 320 inches (65%)

No. 2 S/G Pressure 853 psia No. 3 S/G Level 320 inches (65%)

No. 3 S/G Pressure 853 psia Tave 5760F Reactor Power Level 2630 MWt Charging /HPSI Flow 65 spm Pressurizer Level 58%

Core Subcooling 600F Core F.xit T/C 5980F

~ 1963e/4.410

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MAINE YANKEE j .THIS IS A DRILL rea100$$/N"Mo^Eri'yys,,- THIS IS A DRILL 1

[lg 'EE.ATIA0 SYA7US f

Today's Alert Today's Alert values Units Values Values Unite Values teactor Power Level o7597 - >2630 r.i RCs 7 TVS 6 ) 552 'F 78/ ) 190 Re CECM tion ANO Gl < 1l) Ster Gross Elect. Gen. , _

I3 8960 Nat Elect. Gen. NN (2) Eve Ave Ccre turnup ' K.0 / M* .'

C:ndenser Back Fressure d 88 > 3 'Hg RCs Ave test F. ate .JV > C.8 tra Condenser Rotemeter /. 6~ > 4(3) sefn CaleMar fear Net

/8 6 > 19.5 psid Cumulative Gen.

Reacter Cere D/P (as cf 0001) NdO[ ' K.*I CHEF.ISTEY l

RCS stCCNDARY Alert Alert Vtlues Ur.i t s Talues Unitt Gross Ga= a /SO > 2 ve/n1 Condensate Czyten db >5 F;;

C'***"" " - ' '"

(94 E- 3 >t. uc/n1 stes :

O-131 2 131/133 _ d. d O ') 0.1 cenereters ?

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1 Dose Q-I-131 4&98 c2. > 1.0 uti/n1 rF 1 7.5 91 7./$ M L '71 < 7.3 Lithius C.39 ** ppa cend  ! /. 9 1 /. A i /. 9 1 > 5 unt:

loren Concentratica /#

  • p;n Cl- l< 2 01//O 14v2O I > 20  ;;)

leren 1 6. 616 716. 31 < $ > lc ;;-

DiscHAtc!!

Liquids: crets tete - Car.*. Tritium A//M tals. ,ut/n1 ut ut/n1 c gals. ,ve/n1 ut ue/n1 c Cases:

A act uc/cc ut ve/cc c FLANT OPEPlT!cNS st'v. vary Avp $IcvIrf eLv7 EvtnTs:

ktw 5"FD foMA S ?T 8 /S Our OP SfMdd ' MA/M7MANCE (1)J.ve. Ccre turnst as cf 00C; vice OECO. Prepared ty: I9

' 2)5ased en especte? statics. service usage 20-23.w , sr.c;;c ti M 3t.m less ina- t c:-

electrical generatien nunter

  • Liniting value dees net a;;1y.

(3)Ccedenser Retcreter value f rcm C000 reading en Secenetry A.C. Let "Dependent en Ecret. It r.tiet t ir. c er t :ttt rM . A:cer:: tit r t e. p :.

L! = (0.3i - .0:150,1 0 ;! ::-

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1965e/3.225

Rev. 4 09/15/88 O Page 5.2-1 MAINE YANKEE ATOMIC POWER STATION '

EMERGENCY PREPAREDNESS EXERCISE 198S 5.2 Scenario outline Scenario Clock i l

Time Time Events 00:00 8:30 LOSS OF ALL RESERVE POWER CAUSED BY A LIGHT P!WiE CRASH kHILE ON APPROACH TO THE WISCASSET AIRPORT.

' CONFIRMED BY SECURITY GUARDS kl0 SEE SMOKE FROM GUARD TOWERS AND THROUGH VERITICATION WITH WISCASSET POLICE DEPARTMENT.

00:15 8:50 Unusual Event should be declared due to loss of i both 115 kV lines.

00:30 9:00 TURBINE TRIPS ON LOSS OF CONTROL OIL PRESSURE ON i

P-2C, REACTOR TRIPS, BOTH DIESELS START.  ;

1 00:31 9:01 DC-1B TRIPS DUE TO A FAULT IN ITS OUTPUT BREAKER (P-25A TRIPS IF RUNNING). (LIGHTS IN ERTs MAY BE LOST FOR 10 TO 15 M!htTES DUE TO LOSS OF POWER ON  :

BUS No. 3.)

( i 00:32 9102 P-25C THE ONE REMAINING EMERGENCY PEEDWATER PUMP, l FAILS.

00:45 9:15 Alert should be declared, due to complete loss of  !

feedwater. (Note: Loss of feed may also be considered a Site Area Emergencyl operators may  :

i declare this.)

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Rev. 4 09/15/88 l Page 5.2-2 v

Scenario Clock Time Time Events 00:45 9:15 Operations may try to backfeed Bus 6 from Bus 8 by (Cont 'd ) using Breaker 7T8. to provide power to P-25A.

However, if attempted, the breaker will reopen due to a ground on the bus.

OSC team may be dispatched to lift leads on P-25C to transfer them to P-25A.

l 01:00 9:30 Level in all three steam generators will be less than 150" wide range.

l The exact time of reaching this condition will depend on actual operator actions.

Atmospheric steam dump valve (s) may be opened to lower RCS temperature.

01:15 9:45 Operators should declare Site Area Emergency after steam generators fall below 150" wide range low steam generator levels (if not declared already at 00:45 above).

OSC tears should be investigating DG-18 and restoring P-25C. OSC team will find that the DC-15 output breaker has melted into the breaker cubicle.

TSC should look at extended consequences of loss of off-site power. coupled with less of feed (i.e..

loss of subcooling possible).

Rev. 4 09/15/88 Page 5.2-3 (o%] \

l Scenario Clock Time Time Events 01:15 9:45 OSC and TSC should also be working with CMP  !

(Cont'd) engineers to backfeed the plant from the 345 kV  !

yard.

01:20 9:50 Operators may use HPSI and the PORVs to remove heat from the RCS.

l 01:30 10:00 Shortly aftet opening the PORVs, containment i radiation levels will begin to increase due to a i blown rupture disc on pressuriser relief tank. [

EOF may be working on "what if" dose projections, ,

and may have teams in the field performing off-site O i Q monitoring.

i 02:00 10:30 OSC TEAM REFORTS IT WILL TAKE APPROXIMATELY 1 Sl:Ir!  :

i TO REPA!R P-25C AND RETURN IT TO SERVICE.

Steam Generator levels now 40" .

J RCS temperature Tave = 552 .

]

RCS pressure 1210 psig .

Margin to saturation 0-20 degrees . I i

., i 03:30 12:00 Scenario hold. ,

l i TIME JUMP OF SIX HOURS - WE .iOW HAVE BACKTEED FROM 345 kV YARD. [

i 09:35 12:20 Teedvater flow restored by starting P-25A.  !

i i 10:00 12:30 RCS FRESStlRE AND TEMPERATVRE START TO STABILIZE.

STEAM GENERATORS RISE ABOVE 150" WE.

1 1965e/3.225 f

Rev. 4 09/is/88 Page 5.2-4 Scenario Clock Time Time Events 10:00 12:30 Recovery Manager and Center Coordinators should discuss shifting into recovery phase is plant is now stable with power from 345 kV yari, feedwater flow established, etc.

RECOVERY DISCUSSIONS BEGIN. TOCUSING ON RESTORATION OF EQUIPMENT. 1.ONG-TERM C001.DOWN. ETC.

10:30 13:00 RECOVERY ENDS - EXERCISE TERMtNATED.

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5.3 Narrative Summary 1

The scenario begins at 0830 with the simulator reactor running at approximately 100% power. The reactor has been operating in a steady state for the past six months, with a 98% capacity factor. The P-25B, '!

steam-driven auxiliary feedwater pump is out-of-service for extended repairs. The reactor coolant activity is: 4.49E-02 dose equivalent I-131. All other power generating equipment is operating, and all safety system equipment is operable.

At 0830, a light plane crashes while on approach to the Wiscasset

() airport. Both 115 kV lines are lost as a result. The security officers in the guard towers are able to see moke ..vrth northwest of the plant from the crash. A loss of all reserve power exists due to the unavailability of both 115 kV linec. An UNUSUAL EVENT should be declared based on a loss of both 115 kV lines for 10 minutes.

At 0900, the turbine trips on loss of control oil pressure on P-2C.

The loss of the turbine causes the reactor to scram.

Without off-site ac power available both diesels start, and Diesel Generator B (DG-1B) trips due to an electrical fault on the output breaker. The P-25A feedwater pump will also trip if running due to a loss of ac power.

1966e/26.340

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A minute later, P-25C emergency feedwater pump also trips. An ALERT should be declared (approximately 0915) based on a loss of all emergency feedwater capability. Following the Alert, the TSC, OcC, and EOF will be activated and staffed. Notifications should be made to the State of Maine, NRC, and Yankee Nuclear Services Division.

Also note that at this time a SITE AREA EMERGENCY may be declared based on a loss of functions needed for emergency pier.t coaldown condition.

The complete loss of feedwater may be used for this event.

The Shift Supervisor should complete appropriate notifications. The Control Room staff will attempt to stabilize the plant. The Shift Supervisor may also requect that plant personnel be dispatched to backfeed Bus 6 from Bus 8 by using Breaker 7T8 to provide power to P-25A. However, if attempted, the breaker will reopen due to the

/N, ground on the bus, b

It is anticipated that plant personnel will be dispatched to investigate DG-1B and try to restore P-25C. At the time, DG-1A is operable and powering all necessary A-train ECCS pumps.

By 0930, the level in all three steam generators should be less than 150 inches wide range; the exact levt.1 will depend on operator actions. The operators may also open the atmospheric steam dump valve (s) to lower RCS temperature.

A SITE AREA EMERGENCY should be declared after all steam generator levels are below 150 inches wide range with a loss of all feedwater capability (approximately 0945).

The OSC teams dispatched should be working on DG-1B and P-25C. The OSC team will find that the DG-1B output breaker has melted into the

~'s breaker cubicle.

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The TSC should assess potential consequences from an extended loss of off-site power, coupled with-loss of feed (i.e., loss of subcooling).

By 1000, the operator may use charging pumps and the PORVs to remove heat from the RCS. The containment radiation levels will increase due to a blown rupture disc on the pressurizer relief tank.

At 1130, slightly elevated radiation levels may be detected by field teams performing on-site monitoring.- The dose rates at the site boundary are negligible, and dose projections should result in minimal off-site doses.

At 1200, a twenty-minute hold period will be followed by a scenario time jump with the backfeed from the 345 kV yard assumed complete (approximately six hours). Feedwater flow is restored by starting P-25A.

By 1230, RCS pressure and temperature start to stabilize. Steam l

generators rise above 150 inches wide range. The Recovery Manager and the center coordinators should discuss the shift into the recovery phase since the plant is stablizing and off-site power from the 345 kV yard is restored.

, At 1300, the exercise will be terminated.

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SCENARIO 0:0 0:30 0:45 1:00 1:15 2:00 3:30 4:00 4:30 TIME 0.1. 2.3.4. 5. 6. 7. 8. 9. 10. 11.

Scenario Clock Time Time

0. Ord 0830 Exercise begins,
1. 4:0 0830 Plane crash while on approach to the Wiscasset Airport
2. 3:20 0850 **UE**. loss of both 115 kV lines
3. 0:30 0900 Reactor trips due to turbine trip on loss of control oil pressure
4. 0:32 0902 Remaining emergency feedwater pump fails
5. 0:45 0915 ** ALERT ** complete loss of feedwater
6. 1:00 0930 Level in all three steam generators should be less than 150"
7. 1:15 0945 **SAE**, low steam generator levels and loss of feedwater
8. 2:00 1030 OSC repair teams working to restore feedwater
9. 3:30 1200
10. 10:00 1230 Recovery discussions
11. 10:30 1300 Exercise terminated

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EMERGENCY PREPAREDNESS EXERCISE 1C'8 '

5.5 DETAILED SEQUENCE OF EVENTS Scenario Clock Time Time Event / Action Message Command EXPECTED CONTROL ROOM ACTIONS ,

WILL BE IMPLEMENTED BY AN EXERCISE OPERATIONS CREW LOCATED IN THE SIMULATOR COMPLEX AREA 0F THE STAFF BUILDING.

OPERATIONAL CONTROL ROOM DATA WILL BE OBTAINED FROM THE SIMULATOR INSTRUMENTATION. IN CASES WHERE SPECIFIC INFORMATION NOT MONITORED BY THE SIMULATOR IS REQUIRED, IT WILL BE ISSUED BY CONTROLLERS ON MESSAGE CARDS. IN THE EVENT THAT A SIMULATOR MALFLHCTION OCCURS, THE EXERCISE WILL BE CONDUCTED USING CONTINGENCY MESSAGE CARD INFORMATION.

-00:15 8:15 THE SIMULATOR CONTROL ROOM SCR-M-1 SCR-C-1 CONTROLLER ISSUES INITIAL CONDITION INFORMATION TO THE EXERCISE OPERATIONS CREW IN THE SIMULATOR CONTROL ROOM.

1960e/18.382

Rev. 3 9/15/88 Page 5.5-2

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( 'j

%.j' Scenario Clock Time Time Event / Action Message Command

-00:15 8:15 GUIDELINES FOR USE OF THE (cont'd) FEMCO AND THE PLANT EVACUATION ALARM WILL BE PROVIDED TO THE PLAYERS.

  • INITIAL CONDITIONS MESSAGES ARE TSC-M-1 ALSO PROVIDED TO ALL EMERGENCY OSC-M-1 RESPONSE FACILITY STAFFS UPON EOF-M-1 SUBSEQUENT ACTIVATIONS. SEC-M-1 ESC-M-1 0FERATIONAL AND RADIOLOGICAL DATA WILL BE AVAILABLE IN THE TSC AND EOF OVER THE SPDS LINKS TO THE

(~ ' SIMULATOR.

METEOROLOGICAL DATA WILL BE PROVIDED ON CUE CARDS EVERY 15 MINUTES.

SECURITY WILL BE PROVIDED A LIST OF CONTROLLERS /0BSERVERS WHO WILL NOT NEED TO BE ACCOUNTED FOR DURING THE EXERCISE.

00:00 8:30 LOSS OF ALL RESERVE POWER AS INDICATED BY ZERO VOLTAGE ON THE 115 kV SECTIONS 69 AND 207 kV METERS.

  • Upon facility activation.

(

1960e/18.382

Rev. 3 9/15/88 Page 5.5-3

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Scenario Clock Time Time Event / Action Message Command 00:05 8:35 Security notes that smoke is SEC-M-2 visible in the direction of the Wiscasset Airport (as observed from the guard tower), and they confirmed reports that the Wiscasset Police are responding to a reported plane crash north of the airport.

00:20 8:50 UNUSUAL EVENT should be declared due to loss of both 115 kV lines for ten minutes per Procedure 2.50.0, "Declaration p and Categorization of Emergency Conditions."

THE SECURITY GUARD WILL BE DIRECTED SEC-C-1 TO NOTIFY THE P.S.S. THAT SMOKE IS VISIBLE IN THE DIRECTION OF THE WISCASSET AIRPORT.

Operators should review E0Ps to  ;

determine appropriate mitigative actions.

PSS should direct Control Room staff to initiate Procedure 2.50.1, "Notification of Unusual Event."

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Rev. 3 9/15/88 Page 5.5-4

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Scenario Clock Time Time Event / Action Message Command 00:20 8:50 THE PSS SHOULD CONTACT THE ACTUAL sca-C-1A (cont'd) CONTROL ROOM, INF0kM THEM THAI THE EXERCISE HAS STARTED, REQUEST TEAT THEY INITIATE PLANT ANNOUNCEMENTS PER PROCEDURE, AND THAT THEY NOTIFY THE NRC VIA THE ENS (RED) TELEPHONE TO INFORM THEM THAT THE EXERCISE HAS STARTED AND AN UNUSUAL EVENT HAS BEEN DECLARED.

PSS should direct plant personnel to continue what they are doing.

PSS should notify the Maine State Police.

The Shift Engineer (SE) should report to the Simulator Control Room and review the incident classification with the PSS.

1960e/18.382

Rev. 3 9/13/88

(~ 'g Page 5.5-5 kJ Scenario Clock Time Time Event / Action Message Command 00:20 8:50 PSS should notify the Duty Call (cont'd) Officer per Procedure 2.50.17.

(The Duty Call Officer may elect to report to the Simulator Control Room and assume the role of Emergency Coordinator.)

PSS or designee should notify the Central Maine Power (CMP)

Dispatcher.

The Public Affairs Director (PAD) will prepare any necessary press releases concerning the

(} nature of the UNUSUAL EVENT l

declaration. Before issuing any press releases, the PAD will coordinate with ti- Maine Division of Health Engineering and the Governor's Press Secretary, if possible.

PLAYING OF ALL THE PRERECORDED PI-C-1 EMERGENCY MESSAG' TAPES ON THE PUBLIC INFORMATION TELEPHONE WILL BE SDfULATED THROUGHOUT THE EXERCISE.

O V 1960e/18.382 l

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Rev. 3 ,

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V Page 5.5-6 l Scenario Clock Time Time Event / Action Message Command 00:20 8:50 Nuclear Safety Engineer (NSE) l (cont'd) should notify Maine Yankee Nuclear Services Division.

PSS should assign a Control Room staff member to maintain a detailed log of events.

00:30 9:00 IF AN UNUSUAL EVENT HAS NOT BEEN SCR-C-2 DECLARED BY THE PSS, HE WILL BE DIRECTED TO DO SO AT THIS TIME.

TURBINE TRIPS DUE TO A LOSS OF CONTROL OIL PRESSURE IN FEED PUMP P-20. REACTOR TRIPS DUE TO TURBINE TRIP. BOTH EMERGENCY DIESEL GENERATORS START.

00:31 9:01 EMERGENCY DIESEL GENERATOR 1B TRIPS DUE TO AN ELECTRICAL FAULT.

(The lights in the TSC, OSC, and EOF may be turned off due to loss of power on Bus No. 3.)

00:32 9:02 EMERGENCY FEEDWATER PUMP P-25C FAILS AND DISASSEMBLING THE PUMP FOR REPA!RS WILL TAKE ONE FULL SHIFT TO COMPLETE.

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Rev. 3 9/15/88

,m Page 5.5-7

( j Scenario Clock Time Time Event / Action Message Command 00:32 9:02 Control Room operators may (cont'd) dispatch auxiliary operators to perform in-station tasks associated with reactor shutdown procedures and the loss of DG-1B and P-25C.

INITIAL IN-PLANT AUXILIARY SCR-C-3 OPERATORS' RESPONSES FROM THE SIMULATOR CONTROL ROOM SHOULD BE DIRECTED TO THE OSC (LUNCH ROOM) TO OBTAIN A CONTROLLER /0BSERVER BEFORE ENTERING THE PLANT.

/N 00:45 9:15 ALERT should be declared due to V a complete loss of steam generator feed capability.

Note: A Site Area Emergency may be declared based on the loss of functions needed for emergency plant cooldown condition (i.e., complete loss of Feedwater System).

PSS should initiate Procedure 2.50.2, "ALERT."

The PSS should instruct personnel to sound the evacuation alarm and make the Alert announcement.

1960e/18.382

[

Rev. 3 9/15/88

(~~) Page 5.5-8 L)

Scenario Clock Time Time Event / Action Message Command 00:45 9:15 NOTE: THE EVACUATION ALARM AND SCR-C-4 (cont'd) FEMCO ANNOUNCEMENT SHOULD BE COORDINATED WITH THE ACTUAL CONTROL ROOM STAFF.

The TSC, OSC, and EOF should be EOF-C-1 activated per Procedures 2.50.13, 2.50.18, and 2.50.19.

ALL OPERATIONAL AND RADIOLOGICAL DATA NOR31 ALLY AVAILABLE IN THE TSC AND EOF VIA THE SPDS WILL BE AVAILABLE.

O ~'

METEOR 00 LOGICAL DATA WILL BE PROVIDED ON CUE CARDS EVERY 15 MINUTES.

The NRC should be notified of the escalation to the Alert classification.

The NSE should activate the Yankee Nuclear Services Division (YNSD) Pager System.

The Control Room should provide a brief but accurate account of actions taken, and anticipated actions to the TSC and EOF when they are activated.

(

i  !

1960e/18.382 ,

Rev. 3 9/15/88

-- Page 5.5-9 N -)

Scenario Clock Time Time Event / Action Message Command 00:45 9:15 When both the TSC and EOF are (cont'd) activated, they should confer with the Control Room to coordinate manpower needs and of f-site connunicar, ions.

All off-site notifications will be directed by the Tiargency Coordinator (with the exception of the Ebine State Police) from the EOF when activated.

PSS should activate pager

(T notification.

b PSS should review Procedure 2.50.16 and evaluate potential radiological consequences.

The NSE should make appropriate notifications.

) 1960e/18.382

Rev. 3 9/15/88 t'^N Page 5.5-10 t }

%.J Scenario Clock Time Time Event / Action Message Command 00:45 9:15 The Duty call Officer / Emergency (cont'd) Coordinator should make the appropriate notifications..

The Central thine Power (CMP)

Dispatcher should make appropriate notifications.

00:45 9:15 Operators may attempt to backfeed SCR-M-2 (Approx.) Bus 6 from Bus 8 through Bus Tie Breaker 7T8. This breaker will not shut due to the presence of a ground condition existing on Bus 6.

[

'# STEAM GENERATOR LLVELS ARE CONTINUING TO DECREASE AT A RATE OF APPROXIMATELY 3.5 INCH / MINUTE.

01:00 9:30 IF AN ALERT HAS NOT BEEN DECLARED SCR-C-5 BY THE PSS. HE WILL BE DIRECTED TO DO SO AT THIS TIME.

01:00 9:30 LEVELS IN ALL THREE STEAM (Approx.) GENERATORS ARE BELOW 150 INCHES WIDE-RANGE (WR).

Operators may attempt to initiate feedwater flow by any of a number of methods (i.e., tie in the fire protection diesel).

O 1960e/18.382

r Rev. 3 9/15/88 C ') Page 5.5-11 Q)

Scenario Clock Time Time Event / Action Message Command 01:00 9:30 OSC should be organizing and OSC-M-2 (cont'd) dispatching an investigative repair team to determine the cause of the loss of DG-1B (Mini Scenario 7.2.2).

TSC and OSC should be OSC-M-3 investigating the possibility of expediting the repair of Auxiliary Feed Pump P-25B (Mini Scenario 7.2.5).

TSC and OSC should be organizing OSC-M-4 and dispatching an investigative v) repair team to determine the cause OSC-M-5 OSC-M-6 of the loss of Auxiliary Feed Pump P-25C (Mini Scenario 7.2.3).

TSC should be coordinating efforts OSC-M-7 to determine the cause of the loss OSC-M-8 of control oil pressure in Feed OSC-M-9 Pump P-2C (Mini Scenarlo 7.2.1).

TSC should be investigating the procedure to backfeed power from the 345 kV yard and coordinate efforts with the OSC and CMP (Mini Scenario 7.2.4).

p 1960e/18.382

Rev. 3 9/15/88 r 's Page 5.5-12

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%)

Scenario Clock Time Time Event / Action Message Command  ;

01:00 9:30 TSC should be developing a list (cont'd) of equipment available and unavailable due to the loss of various electrical buses.

Operators may open the Atmospheric ,

Steam Dump Valves MSM-161 and MSM-162 in order to lower RCS temperature.

NOTE: THE EXACT TIME OF STEAM GENERATOR LEVEL DECREASING BELOW 150 INCHES AND OPERATION OF ATMOSPHERIC STEAM DUMP VALVE 3 IS DEPENDENT UPON ACTUAL OPERATOR ACTIONS.

01:15 9:45 PSS should declare a SITE AREA EMERGENCY due to the loss of all feedwater capability and steam generator water levels below 150 inches (wide range).

The PSS should follow Procedure 2.50.3 "SITE AREA EMERGENCY" and make appropriate l

i notifications and announcements.

The PSS should coordinate the activation of the sirens (simulated).

(}

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Scenario Clock Time Time Event / Action Message Command 01:15 9:45 OSC team investigating the loss OSC-M-10 (cont'd) of DG-1B should report that the output breaker has melted into the breaker cubicle.

01:20 9:50 Based on the Reactor Coolant System parameters and steam generator water inventory, the operators may elect to use HPSI pumps and PORVs to remove heat from the RCS.

01:30 10:00 IF A SITE AREA EMERGENCY HAS SCR-C-6 NOT BEEN DECLARED BY THE PSS, HE N WILL BE DIRECTED TO DO SO AT THIS TIME.

The ESC should be providing ESC-M-2 technical and engineering support to the Maine Yankee staff. The ESC meteorologist should provide a specialized weather forecast for the Maine Yankee site.

Q 1960e/18.382

Rev. 3

^

9/15/88 Page 5.5-14

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Scenario Clock Time Time Event / Action Measage Commarid 01:30 10:00 WHEN THE PORVs ARE OPENED FOR AN (cont'd) EXTENDED PERIOD OF TIME, THE RUPTURE DISC IN THE PRESSURIZER QUENCH TANK WILL RUPTURE, THEREBY INCREASING RADIATION LEVELS INSIDE CONTAINMENT.

The EOF should demonstrate "what if" EOF-C-2 dose projections and monitor off-site field survey results.

OSC repair team reports that it OSC-C-1 will take approximately one full

() shift to return P-25C to service.

If not already done, the TSC TSC-C-1 Coordinator will be directed to dispatch on-site assistance team to backfeed power from the 345 kV yard.

01:45 10:15 If not already done, the TSC TSC-C-2 Coordinator will be directed to dispatch on-site assistance team to investigate the problem with the DC-1B output breaker. L i

l 1960e/18.382

Rev. 3 9/15/88 Page 5.5-15

(~

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Scenario Clock Time Time Event / Action Message Command 02:00 10:30 The appropriate EOF staff should EOF-M-2 continue to evaluate potential off-site consequences. An updated weatner forecast is available.

02:15 10:45 If not already done, the TSC TSC-C-3 Coordinator will be directed to dispatch an on-site assistance team to investigate the problem with the control oil pressure in Feed Pump P-2C and repair of Auxiliary Feed Pump P-25B.

O 03:15 11:45 Repairs associated with backfeed OSC-M-11 from the 345 kV yard will be ,

completed in approximately six hours.

03:30 12:00 SCENARIO HOLD FOR 20 MINUTES, SCR-C-7 FOLLOWED BY A TIME JUMP OF TSC-C-4 SIX H0l'RS. LUNCH WILL BE OSC-C-2 PROVIDhD, AND PLAYERS SHOULD EOF-C-3 IDENTIFY OUTSTANDING ACTIONS ESC-C-1 AND RE-ESTABLISH PRIORITIES. SEC-C-2 PI-C-2

'd 1960e/18.382 C

Rev. 3

. 9/15/88

(~~') Page 5.5-16 N--l Scenario Clock Time Time Event / Action Message Command 09:30 12:20 BACKFEED FROM 345 kV YARD COMPLETE.

P-25A HAS POWER AND IS AVAILABLE TO SUPPLY FEEDWATER TO ALL STEAM GENERATORS.

09:35 12:25 FEEDWATER FLOW FROM P-25A IS SCR-M-3 RESTORED. STEAM CENERATOR LEVELS START TO SLOWLY INCREASE.

09:40 12:30 STEAM GENERATOR LEVELS INCREASE TO GREATER THAN 150 INCHES WIDE RANGE.

Recovery Manager and Center f}

Coordinator should discuss actions necessary to commence recovery phase since the plant is now stable with power supplied from the 345 kV yard and feedwater flow re-established.

Recovery discussion should focus on restoration of equipment, long-term cooldown, etc.

10:10 13:00 RECOVERY ENDS - EXERCISE EOF-C-4 TERMINATED.

1960e/18.382

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4 MAIllE YANKEE j EMERGENCY PREPAREDNESS EXERCISE ,

! I 1988 i i

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6.0 EVENT MESSAGES l r l

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MAINE YANKEE ,

i EMERGENCY PREPAREDNESS EXERCISE i r

! 1988 i

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Rev. 2 r] 9/14/88 d MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE age 6.1-1 1988 SCENARIO MESSAGE FORM SCR-C-1 FROM MESSAGE NUMBER CLOCK TIME 0815 TO

-00:15 LOCATION SCENARIO TIME PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

ACTIVATION OF THE PEAS SHALL BE SIMULATED.

EACH ACTIVATION OF THE EVACUATION ALARM AND FEMCO ANNOUNCEMENTS SHOULD BE COORDINATED WITH THE ACTUAL CONTROL ROOM.

O

                                                  • THIS IS A DRILL *******************

O

Rev. 2 MAINE YANKEE 9/14/88 Page 6.1-1A EMERGENCY PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE FORM FROM SIMULATOR CR CONTROLLER MESSAGE NUMBER SCR-C-1A P.S.S. CLOCK TIME U.E. DECLARATION TO A OR CR SCENARIO TIME LOCATION PARTIC7 PANT MESSAGE

  • * * * * * * * * *
  • e * * * * * * * * * * * *
  • 112 f S I S A D R I L L * * * * * * * * * * * * * * * * * *
  • CONTACT THE ACTUAL CONTROL ROOM AND REQUEST ITIAL ACTIVATION OF THE PLANT EVACUATION ALARM AND NOTIFICATION 7 THE NRC VIA THE ENS (RED) TELEPHONE THAT THE EXERCISE HAS STAi.*ED AND THAT AN UNUSUAL EVENT HAS BEEN DECLARED.

A LSO , REQUEST THE ACTUAL CONTROL ROOM TO MAKE THE APPROPRIATE EXERCISE ANNOUNCEMENT PER PROCEDURE REGARDING THE UNUSUAL EVENT O CLASSIFICATION.

EACH ACTIVATION OF THE EVACUATION ALARM AND FEMCO ANNOUNCEMENTS SHOULD BE COORDINATED WITH THE ACTUAL CONTROL ROOM.

                                                  • THIS IS A DRILL *******************

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Rev. 2 MAINE YANKEE 9/14/88 Page 6.1-2 EMERGENCY PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE FORM PI-C-1 FROM MESSAGE NUMBER PUBLIC AFFAIRS DIRECTOR C14CX TIME 0850 TO SCENARIO TIVE 00120 LOCATION PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

PIAYING OF THE PRE-RECORDED EMERGENCY MESSAGE TAPES ON THE PUBLIC INFORMATION TELEPHONE WILL BE SIMULATED THROUGHOUT THE EXERCISE.

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Rev. 2 MAINE YANKEE 9/14/88 Page 6.1 3 EMERGENCY PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE FORM i

R R CONTRO W R MESSAGE NUMBER SCR-C4 FROM

[

CLOCK TIME 09:00 TO SI OR CR SCENARIO TIME LOCATION i

PARTICIPANT MESSAGE e

                                                  • THIS IS A DRILL *******************  ;

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$ DECLARE AN UNUSUAL EVENT PEL i-)- OSOURE l 2.50.0, LOSS OF OFFSITS POWER.

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I Rev. 2 i MAINE YANKEE 9/14/88

) EMERGENCY PREPAREDNESS EXERCISE Page 6.1-4 1988 ,

SCENARIO MESSAGE FORM ,

FROM OF CONTROLLER MESSAGE NUMBER EOF-C-1 CLOCK TIME UPON ACTIVATION EMERGENCY COORD.  !

TO EOF SCENARIO TIME UPON ACTIVATION LOCATION PARTICIPANT MESSAGE

                              • u"********THIS IS A DRILL ******************* .

ACTIVATION OF THE PEAS SHALL BE SIMULATED. j i

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                                                  • THIS IS A DRILL **=****************

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Rev. 2 C MAINE YANKEE 9/14/88 EMERGENCY PREPAREDNESS EXERCISE Page 6.1-5 1988 SCENARIO MESSAGE FORM SECURITY CONTROLLER MESSAGE NUMB' R SEC-C-1 FROM TO RITY GUARD CLOCK TIME 0840 GUARD HOUSE SCENARIO TIME 00:10 LOCATION PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

IF NOT ALREADY DONE SO, INFORM THE P.3.S. (IN THE SIKULATOR CONTROL ROOM) THAT YOU OBSERVE SMOKE IN THE DIRECTION OF THE WISCASSET AIRPORT AND THAT THE WISCASSET POLICE DEPARTMENT ARE RESPONDING TO AN AIRPLANE CRASH NORTH OF THE AIRPORT.

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                                                  • THIS IS A DRILL *******************

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I Rev. 2 l MAINE YANKEE 9/14/88 EMERGENCY PREPAREDNESS EXERCISE Page 6.1-6 1988 SCENARIO MESSAGE FORM ,

l FROM SIMULATOR CR CONTROLLER MESSAGE NUMBER SCR-C-3 TO P.S.S. CLOCK TIME 0902 a LOCATION SIMULATOR CR SCENARIO TIME 00:32 PARTICIPANT MESSAGE  ;

                                                  • THIS IS A DRILL ******************* l l  !

1 AUXILIARY OPERATOR RESPONSES FROM THE SIMULATOR CONTROL ROOM l SHALL BE OBSERVED BY AN OSC OBSERVER. DIRECT THE AO TO OBTAIN AN  :

OBSERVER FROM THE OSC PRIOR TO PERFORMING ANY EXERCISE RELATED ,

ACTIVITIES. t i

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                                                  • THIS IS A DRILL ******************* i i

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MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE Page 6.1-7 9/14/88 4

1988 SCENARIO MESSAGE FORM i SIMULATOR CR CONTROLLER MESSAGE NUMBER SCR-C-4 FROM ,

P.S.S. CLOCK TIME 091$

i TO LOCATION SIMULATOR CR SCENARIO TIME 00:45 PARTICIPANT MESSAGE 1

                                                  • THIS IS A DRILL *******************

CALL THE ACTUAL CONTROL ROOM, REQUEST THAT THEY SOUND THE PLANT EVACUATION AIARM FOR 10 SECONDS. ONCE THE EVACUATION ALARM HAS BEEN SOUNDED REQUEST THAT THEY MAKE THE APPROPRIATE FEMCO ANNOUNCEMENTS PER PROCEDURE.

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_,_,,n,_ -,.-,.,nnn,-a . , ~w- - , . . - , - ,

Rev. 2 MAINE YANKEE 9/14/88

. Page 6.1-8 EMERGENCY PREPAREDNESS EXERCISE 1988 l SCENARIO MESSAGE FORM i

FROM I OR CR CONTROLLER MESSAGE NUMBER SCR-C-5 l i

CLOCK TIME 0930  ;

TO _ _

LOCATION SIWWOR CR SCENARIO TIME ____

01:00 I I

PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************  ;

DECLAltE AN ALERT IN ACCORDANCE WITH PROCEC'URE 2.50.0, COMPLETE LOSS OF STEAM GENERATOR FEED CAPABILITY O

                                                  • THIS IS A DRILL *******************

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Rev. 2 O

t 9/14/88 V MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE Page 6.1-9 1988 SCENARIO MESSAGE FORM SIMULATOR CR CONTROLLER SCR-C-6 MESSAGE NUMBER CLOCK TIME 1000 TO OR CR SCENARIO TIME 01230 LOCATION I

i PARTICIPANT MESSAGE j

                                                  • THIS IS A DRILL *******************

RECOMMEND A SITE AREA EMERGENCY DECLARATION PER PROCEDURE 2.50.0, ALL STEAM GENERATOR LEVELS BELOW 150" WIDE RANGE I

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l Rev. 2 MAINE YANKEE 9/14/88

" EMERGENCY PREPAREDNESS EXERCISE Page 6.1-10 1988 SCENARIO MESSAGE FORM OSC REPAIR TEAM OBSERVER MESSAGE NUMBER OSC-C-1 FROM OSC REPAIR TEAM LEADER CLOCK TIME 1000 TO i LOCATION AUX. FEED PUMP P-25C SCENARIO TIME 01:30 PARTICIPANT MESSAGE i

                                                  • THIS IS A DRILL *******************

4 NECESSARY REPAIRS WILL TAKE APPROXIMATELY 1 FULL SHIFT TO COMPLETE.

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' ^ Rev. 2 MAINE YANKEE 9/14/88 .;

EMERGENCY PREPAREDNESS EXERCISE Page 6.1-11 1988 SCENARIO MESSAGE FORM TSC OBSERVER- MESSAGE NUMBER TSC-C-1 TSC COORDINATOR CLOCK TIME 1000

TO i

TSC SCENARIO TIME 01:30 LOCATION

' PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

1 1

DISPATCH A REPAIR TEAM TO START BACKFEED PROCEDURES FROM THE

, 345kV SWITCHYARD.

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Rev. 2 x 9/14/88

('~' ) MAINE YANKEE EMERGENCY PREPAREDNESS EXTRCISE Page 6.1-12 1988 SCENARI7 MESSAGE FORM SC CONTROLLER MESSAGE NUMBER TSC-C-2 FROM NATOR CLOCK TIME 1015 TO LOCATION SCENARIO TIME 01:45 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

DISPATCH A REPAIR TEAM TO INVESTIGATE THE PROBLEM WITH DG-1B O

N)

                                                  • THIS IS A DRILL *******************

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Rev. 2 MAINE YANKEE 9/14/88 EMERGENCY PREPAREDNESS EXERCISE Page 6.'l-13 1908 SCENARIO MESSAGE FORM EOF CONTROLLER MESSAGE NUMBER EOF-C-2 FROM RGENCY C@RD. CLOCK TIME 1000 TO LOCATIO!, OF SCENARIO TIME 01 30 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

DISPATCH AT LEAST ONE FIELD MONITORING TEAM.

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                              • ii*********TNIS IS A DRILL *******************

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Rev. 2 MAINE YANKEE 9/14/88

. EMERGENCY PREPAREDNESS EXERCISE Page 6.1-14 1988 SCENARIO MESSAGE FORM ,

1 N OMR MESSAGE NUMBER TSC-C-3 FROM NA OR CLOCK TIME 1045 TO I4 CATION SCENARIO TIME 02 15 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

DISPATCH TEAMS FROM THE OSC TO INVESTIGATE THE PROBLEMS WITH FEED PUMP P-2C AND AUXILIARY FEED PUMP P-25B i

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Rev. 2 MAINE YANKEE 9/14/88

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's_ EMERGENCY PREPAREDNESS EXERCISE Page 6.1-15 1988  ;

SCENARIO MESSAGE FORM SI LA OR CR CONTROLLER MESSAGE NUMBER SCR-C-7 FROM P.S.S. CLOCK TIME 1200  ;

TO LOCATION LATOR CR SCENARIO TIME 09:30 PARTICIPANT MESSAGE  !

4

                                                  • THIS IS A DxILL*******************

THE SIMULATOR IS BEING PUT ON HOLD.

{ RECALL ANY PERSONNEL DISPATCHED FROM YOUR FACILITY AT THIS TIME. j i LUNCH IS BEING PROVIDED FOR EXERCISE PARTICIPANTS.

THE EXERCISE WILL CONTINUE FOLLOWING A 15-20 MINUTE LUNCH BREAK AT WHICH i I

() TIME THE FOLLOWING CONDITIONS WILL EXIST:

f A TIME JUMP OF 6 HOURS HAS OCCURRED.

l REACTOR IS THUTDOWN Tave= 532 F i RCS PRESSURE = 998 PSIA 1

STEAM GENERATOR LEVELS (AVERAGE)= 37" I

CONTAINMENT RADIATION LEVELS = 17.5 R/HR ,

CONTAINMENT PRESSURE = 16.36 PSIA f 9 i BACKFEED OF OFFSITE POWER FROM THE 345 kV SWITCHYARD IS ,

COMPLETE.

l J l j *************************THIS IS A DRILL *******************

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MAINE YANKEE 9/14/88 [

EMERGENCY PREPAREDNESS EXERCISE Page 6.'.-16  ;

1988 SCENARIO MESSAGE FORM ,

I TSC CONTROLLER MESSAGE NUMBER TSC-C-4 FROM t TSC COORDINATOR CLOCK TIME 1200 .

TO  !

LOCATION TSC SCENARIO TIME 09:30 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL ******************* l THE SIMULATOR IS BEING PUT ON HOLD. l 1

i RECALL ANY PERSOl;NEL DISPATCHED FROM YOUR FACILITY AT THIS TIME. <

LUNCH IS BEING PROVIDED FOR EXERCISE PARTICIPANTS. f

THE EXERCISE WILL CONTINUE FOLLOWING A 15-20 MINUTE LUNCH BREAK AT WHICH I

()

TIME THE FOLLOWING CONDITIONS WILL EXISTt 1 A TIME JUMP OF 6 HOURS HAS OCCURRED.  !

REACTOR IS SHUTDOWN l 6 i Tave= 532 P  ;

RCS PRESSURE = 998 PSIA ,

STEAM GENERATOR LEVELS (AVERAGE)= 37" 6

CONTAINMENT RADI ATION LEVELS = 17.5 R/HR l l

CONTAINMENT PRESSURE = 16.36 PSIA

, BACKFEED OF OFFSITE POWER FROM THE 345 kV SWITCHYARD IS i COMPLETE.

E 1 l j *************************THIS IS A DRILL ******************* i f

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Rev. 2 9/14/88 O MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE Page 6.1-17 1988 SCENARIO MESSAGE FORM l NTROLLER MESSAGE NUMBER OSC-C-2 [

FROM OSC COORDINATOR CLOCK TIME 1200 TO LOCATION SCENARIO TIME 09:30 l r

PARTICIPANT MESSAGE I

                                                  • THIS IS A DRILL ******************* l THE SIMULATOR IS BEING PUT ON HOLD.  !

t RECALL ANY PERSONNEL DISPATCHED FROM YOUR FACILITY AT THIS TIME.

LUNCH IS BEING PROVIDED FOR EXERCISE PARTICIPANTS.

a THE EXERCISE WILL CONTINUE FOLI4 WING A 15-20 MINUTE LUNCH BREAK AT WHICH i f TIME THE FOLLOWING CONDITIONS WILL EXIST:

l A TIME JUMP OF 6 HOURS HAS OCCURRED.

REACTOR IS SHUTDOWN Tave= 532 F l RCS PRESSURE = 998 PSIA  !

i STEAM GENERATOR LEVELS (AVERAGE)= 37" t l

CONTAINMENT RADIATION LEVELS = 17.5 R/HR j CONTAINMENT PRESSURE = 16.36 PSIA 1  !

I

' I BACKFEED OF OFFSITE POWER FROM THE 345 kV SWITCHYARD IS COMPLETE.

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                                                  • THIS IS A DRILL ******************* l 1
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Rev. 2 9/14/88 O MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE Page 6.1-18 1988 SCENARIO MESSAGE FORM EOF CONTROLLER MESSAGE NUMBER EOF-C-3 FROM EMERGENCY COORDINATOR CLOCK TIME 1200 TO LOCATION EOF SCENARIO TIME 09:30 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

THE SIMULATOR IS BEING PUT ON HOLD.

RECALL ANY PERSONNEL DISPATCHED FROM YOUR FACILITY AT THIS TIME.

LUNCH IS BEING PROVIDED FOR EXERCISE PARTICIPANTS.

THE EXERCISE WILL CONTINUE FOLLOWING A 15-20 MINUTE LUNCH BREAK AT WHICH TIME THE FOLLOWING CONNTIONS WILL EXIST:

A TIME JUMP OF 6 HOURS HAS OCCURRED.

REACTOR IS SHUTDOWN Tave= 532 F RCS PRESSURE = 998 PSIA STEAM GENERATOR LEVELS (AVERAGE)= 37" CONTAINMENT RADIATION LEVELS = 17.5 R/HR CONTAINMENT PRESSURE = 16.36 PSIA BACKFEED OF OFFSITE POWER FROM THE 345 kV SWITCHYARD IS COMPLETE.

  • * * * * * * * * * * * * * * * * * * * * * * *
  • TH I S I S A DR I LL * * * * * * * * * * * * * * * * * *
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MAINE YANKEE 9/14/88  !

_ EMERGENCY PREPAREDNESS EXERCISE Page 6.I-19 i 1988 SCENARIO MESSAGE FORM ESC CONTROLLER MESSAGE NUMBER ESC-C-1 FROM ESC COORDINATOR CLOCK TIME 1200 TO LOCATION ESC SCENARIO TIME 09:30 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

THE SIMULATOR IS BEING PUT ON HOLD.

RECALL ANY PERSONNEL DISPATCHED FROM YOUR FACILITY AT THIS TIME.

LUNCH IS BEING PROVIDED FOR EXERCISE PARTICIPANTS.

THE EXERCISE WILL CONTINUE FOLLOWING A 15-20 MINUTE LUNCH BREAK AT WHICH

() TIME THE FOLLOWING CONDITIONS WILL EXIST:

A TIME JUMP OF 6 HOURS HAS OCCURRED.

REACTOR IS SHUTDOWN Tave= 532 F RCS PRESSURE = 998 PSIA STEAM GENERATOR LEVELS (AVERAGE)= 37" CONTAINMENT RADIATION LEVELS = 17.5 R/HR CONTAINMENT PRESSURE = 16.36 PSIA BACKFEED OF OFFSITE POWER FROM THE 345 kV SWITCHYARD IS COMPLETE.

                                                  • THIS IS A DRILL *******************

O

Rev. 2 s' MAINE YANKEE 9/14/88 Page 6.1-20 EMERGENCY PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE FORM SECURITY OBSERVER MESSAGE MUMBER SEC-C-2 FROM CLOCK TIME 1200 TO LOCATION SCENARIO TIME 09130 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

THE SIMULATOR IS BEING PUT ON HOLD.

RECALL ANY PERSONNEL DISPATCHED FROM YOUR FACILITY AT THIS TIME.

LUNCH IS BEING PROVIDED FOR EXERCISE PARTICIPANTS.

THE EXERCISE WILL CONTINUE FOLI4 WING A 15-20 MINUTE LUNCH BREAK AT WHICH TIME THE FOLLOWING CONDITIONS WILL EXIST:

A TIME JUMP OF 6 HOURS HAS OCCURRED.

REACTOR IS SHUTDOWN BACKFEED OF OFFSITE POWER FROM THE 345 kV SWITCHYARD IS COMPLETE.

                                                  • THIS IS A DRILL *******************

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i Rev. 2 9/14/88 l () MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 Page 6.1-21 SCENARIO MESSAGE FORM PI-C-2 FROM MESSAGE NUMBER PUBLIC AFFAIRS D? RECTOR 1200 TO CLOCK TIME 09:30 LOCATION SCENARIO TIME PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

THE SIMULATOR IS BEING PUT ON HOLD.

RECALL ANY PERSONNEL DISPATCHED FROM YOUR FACILITY AT THIS TIME. l l

LUNCH IS BEING PROVIDED FOR EXERCISE PARTICIPANTS.  !

THE EXERCISE WILL CONTINUE FOLLOWING A 15-20 MINUTE LUNCH BREAK AT WHICH l TIME THE FOLIJ3 WING CONDITIONS WILL EXISTt A TIME JUMP OF 6 HOURS HAS OCCURRED.

REACTOR IS SHUTDOWN Tave= 532 F RCS PRESSURE = 998 PSIA STEAM GENERATOR LEVELS (AVERAGE)= 37" CONTAINMENT RADIATION LEVELS = 17.5 R/HR CONTAINMENT PRESSURE = 16.36 PSIA BACKFEED OF OFFSITE POWER FROM THE 345 kV SWITCHYARD IS COMPLETE.

                                                  • THIS IS A DRILL *******************

O

l Rev. 2

/" 9/14/88 b] MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 Page 6.1-22 SCENARIO MESSAGE FORM FROM ECT/TSC CONTROLLER MESSAGE NUMBER EOF-C-4 EMERGENCY COORD./SRM CLOCK TIME 1310 TO LOCATION ECT/TSC SCENARIO TIME 10t10 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

TERMINATE RECOVERY DISCUSSIONS-EXERCISE HAS BEEN COMPLETED.

COORDINATE WITH THE ACU!AL CONTROL ROOM TO INFORM THE NRC VIA THE ENS (RED) TELEPHONE THAT THE EXERCISE HAS BEEN COMPLETED.

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                                                  • THIS IS A DRILL *******************

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MAI!iE YAllKEE l

d EMERGE! ICY PREPAR'CD!iESS EXERCISE l

1988 i

6.2 SCE11ARIO MESSAGE CARDS [

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Rev. 2 MAIllE YA!1XEE 9/14/88

() EMERGEllCY PREPARED!lESS EXERCISE Page 6.2-1 1988 SCEllARIO MESSAGE FORM SIMULATOR CR CONTROLLER SCR-M-1 FRM MESSAGE NUMBER CLOCK TIME 0815 TO Oh CR SCEllARIO TIME -00:15 14CATIOtt PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

INITIAL CO!!DITIONS ARE AS OUTLINED IN THE FOLLOWING PAGES O

                                                  • THIS IS A DRILL *******************

O

Rev. 2 9/14/08 q) Page 6.2-2 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1985 INITIAL CONDITIONS (This information will be provided tu the players at the start of the J exercise.)

1. The reacter is at approximately 100% rated power. The reactor has been operating near steady state for the past six months, with a 98%

capacity factor.

2. The P-25B steam-driven auxiliary f eedvater purep is out-of-service for extended repairs.

v

3. The reactor coolant activity is 4.49E-02 dose equivalent I-131.

l 4. All other power generating equirr:ent is operating and all safety system equipment is operable.

5. The following on-site meteorological conditions exist at 0830:

1 Wind speed, eph (upper / lower) 10.3/4.4 Wind direction, degrees (upper / lower) 193/173 Delta teroperature. F (difference) 0.3 Ambient temperature, F 61.0 Precipitation, inches /per 15 minutes 0.0

6. Synoptic (regional) ceteorological conditions:

t Rain ending this morning, with fog in low lying areas clearing by midday.

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Page 6.2-3 ,

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Winds southwesterly 3-5 mph, terrperatures raid 70s by af ternoon. l Winds will shift to westerly as a cool front rr.akes it way through the forecast area this evening.

As the warra f ront moves further north, varm southerly flow will continue through this afternoon. The cold front expected this evening will bring an occasional shower and cooler temperatures tomorrow.

4 I 7. Initial plant and reactor system values are attached 9

e

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

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

Rev. 2 9/14/88 9 Page 6.2-4 Initial Plant and Reactor System Values _

, l RCS Pressure 2,226 psia Containment Pressure 16.09 psia Containment Radiation (1.0 R/hr Hottest CET 604.3 0F No.1 S/G Level 319 inches No. 1 S/G Pressure 854 psia ,

No. 2 S/G Level 320 inches l No. 2 S/G Pressure 853 psia No. 3 S/G Level 320 inches No. 3 S/G Pressure 853 psia 5760F Tave 2630 MWt l Reactor Power Level Charging /RPSI Flow 65 gpm 5S%

Pressuriser Level Core Subcooling 600F Core E. tit T/C 5980r O

MaineYankee name sticum, ec%: u,:i ...,

Rev. 2 9/1/./ 80 7 Page 6.2-5 l Po tox os . wis:>45tt wamt east 6. ach stu2D [

t F.Y.0 23 72. Fev. 26

' PA!NI YANKEE f THIS IS A DRILL rtuco $!' $ $fi$$^[S'c"yff,,e THIS IS A DRILL l F13).i 0FEFATING STATUS l

fogsy's Alert Today's Alert  !

Values Values Units Values Vtlues Units l R0tetor Power Level c)S97 > 2430 K.i RCS T M 7 > 552 *T i 78/ ) 190 CEDF. No tion Afd C5 < 14 3 Stept Grcss Elect. Gen. P.w e Wet Elect. Gen. 26M (2) P.we Ave Cere turnup III 8960 ' K.'D /r.TV  ;

C::densar Estt Fressure d 88 > 3 "HL RCS Ave test Rate .N > 0. 8 Lpm f C:: denser Roteneter _/f > 4(3) stfm Calendar fear Het f Reactor Core D/P /8 M > 19.5 psid Ce.ulative Gen.

N3OM ' K.*E (as of 0001)

I CHEP.ItifY RCS SECONDART I Alert 11ert i Values Units Values Units f Gross Gem s /. [8 > 2 ut/n1 Cendensate oxygen d6 >$ prb 131 Y9I' 8' 3 > I-2 ut/n1 l

s te s:: i , I l I-131/133 de dd ) 0.1 Generatere 1., 1 2 3 I i Dose Q.I-131 M98 c2- > 1. 0 uti/n1 rF 1 7.69I 7"S 81 T d9l <. 7.3 f' Lithium C.39 n pra cere I /. 9 i /. A I /. 9 I > 5 ue.c Boren Cententration /// ' ;ps Cl- l < 2 0 t /.20 14 2O 0 _ l > 20 TTt Feren I d. 0 i S. E I 0. 3 l < 5 > 10 Trn J f

i p_:5CH AF 0f 5 Liquids: Cress Fete -Cama Tritiun

_ A//N gals. .,u t / n1 ut ut/n1 C gals, ut/ml ut ut/n1 c i l

Casest 2[N stf uc/tt ut ut/tt t

[

t PlJLVT OPTTJ7 IONS StTvRY AND FIGNIFICAWT ITEN!!:  ;

kttr fBFO fo& ?" 2 6~ 0 /S OV 7~ Of $/~/V/[S " M4aMx/Ax/CE _ i

[

l

)1) Ave.Ccreturnu;tscfC001viceC600. Fre;tre? By: N/7 f

,(2)5ased en es;ected statien service usage :( . 'e.

- s .t c ul d t e ;!- 3 Cr./e le s s it an g r e s s  ;

electrical generstien nunter l

' Liniting value dess net a;;1y.

(33C entenser Retereter value frem COO; restit: en te:cr.dary A.C. Let. '

Defendent en Eerce tc reintett tenstart th. u:e::ttl+ rents

  • L! e (0.15  ;*:t- . * !! rr-  !

,s Rev. 2 l I MAIllE YANKEE 9/14/88 EMERGE! ICY PREPAREDNESS EXERCISE Paga 6.2-6 1988 SCEllARIO MESSAGE FORM FROM MESSAGE NUMBER TSC-M-1

^ CLOCK TIME UPON ACTIVATIO!1 TO 14 CATION _

SCENARIO TIME PARTICIPA!!T MESSAGE

                                                  • THIS IS A DRILL *******************

INITIAL CONDITIONS ARE AS OUTLINED IN THE FOLLOWING PAGE C-

                                                  • THIS IS A DRILL *******************

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MaineYankee

.mne nicu eme. .e $ a .,, .

xe 2 9/14/c*

l' Page 6.2-7 l eo aos aos . ms:A:sti umt 04sts . n:7i sattm O MAINE YANKEE MY-0 23-72. Rev. 24 '

THIS IS A DRILL Pruce$!E/E"Id5^5Ec"'IES,,- THIS IS A DRILL  !

PR.N; Ortr>;ING s;A70s -

t Tedsy's Alert Today's Alert t values values Units Values values Units  !

Roacter Power Level JS97 - >2630 K4 F.C$ 7 f MS. I > 552 *T f Gross Elect. Gen. 98/ > tso xwe CrexN!! tion Afo _ cs < 163 sten i N3t Elett. Gen. 26N (2) Mwe Ave Core Burnup III 8950

  • K.'D/MTU h Condenser Bact Pressure d.88 > 3 "Hg RCS Ave Leak Rate . 2Y 70.8 sp C ndenser Rotemeter __ /. f ) 4(3) sein Calendar fear Net Eostter Core e/F /8 M > 19. 5 psid Cunulative Gen.

N3N ' K4 (as of 0001) i CHEMISU1 ICS SECONDART j Alert

' Alert Values Ur.it: T alue s Ur.i t s

)

Gross Gama /MO > 2 ut/n1 .a.densate Czygen db >$ ;Tb  ;

Condensate pH 9.60 7 S.2 L 131 & E-3 > t.: u /21  ;

! $tesa l  ; I l l I-131/133 . de d O ') 0.1 Generaters 1 I 2 3 l Des e Q4-131 M978 cA > 1. 0 uti/r1 tM I7.d917.'S8ITdNI<.7.3 (

Lithium C. 39 " pp Cend i/.91 /. A I /. 9 l */ 5 unhe I Baron Contentration ///

  • ppa Cl- 1( 201//O IMO l > 20  ;;t f

l Beren 1 4. 6 1 d. 710 3_l < $ > 10 rp '

1 L

DISCHAFCES I

j tiquidst Crest h t e - C am a Tritium i

, _ AbN tals. __,ut/mi ut ut/nl t f tals, ut/n1 ut ut/n1 C Gasest 4/d/ scf ut/tc ut ut/tt c 1

FLANT OPTFJLTIONS $DXAFY AWS $1CNIFICART EVENTS: f i kt LY NFt) AnMA S 25 0 /S bu r Ot= ,$f/V/DE " YA/MA/AAll'S l .

- i i F

~*

(

[

! 1) Ave. Cere Eurr.u; as cf 0001 vice 0600. Prepared By: .si 8 7 f j (23E ased cm es;t etet staticn service usate 26-2ty.'e. shculd te' 25 3th/c less tr.an ticss f electricts teneratic. tu-ter l

' Linitint value cces r.ct t;;1y. [

IIICcedenser Ectc eter value frer. C000 reading en Secenitry A.O. Les. [

"Of te!. dent et leren :: .tittait censtEn ;M. Acceptstle itett if i L! = I0,31 - .00'.10s: . 0 . '. ! : - . f t

s l

T Rev. 2 5n) MAINE YANKEE 9/14/88 EMERGENCY PREPAREDNESS EXERCISE Page 6.2-8 1988 SCENARIO MESSAGE FORM

~

FROM OSC CONTRO M R MESSAGE NUMBER CSC-M-1 n

OSC COORDINATOR CLOCK TIME UPON ACT!V^ TION TO L', CATION O.cc SCENARIO TIME WHEN ACTIVATED PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

INITIAL CONDITIONS ARE AS OUTLINED IN THE FOLLOWING PAGE r

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MaineYankee amasse cuasicen roa vame smcc m, a.2 9/14/88 i Page 6.2-9 PO Box 408 WISOASSET. M AINE 04576. (2c?! 882-E3:1 MY-O-23-72. Rev. 26

( ) XAIIC YANKEE THIS IS A DRILL grg,103 s's/M"'6MS.TtMy,3,y _ THIS IS A DRILL PLANT OFEPJ. TING STATUS Today's Alert Today's Alert values Values values Units Values Ur.i t s c2597 > 2630 L'I RCS T f YS. E > 552 *T Esactor Power Level 98/ > 890 Mwe CEDM o tion Afd G5 < 163 Steps I. Grcss Elect.. Gen. '

Not Elect. Gen. N (2) Mwe Ave Core Burnup 8250 ' L*D/MTV C;;ndenser Bact Pressure C2. 88 _ > 3 H g RCS Ave Leak Rats . c2Y 70.8 spn i Condenser Rotometer /- [ > 4(3) scfm Calendar Year Net Racetor Core D/P /8.M > 19 . 5 psid Cumulative Gen.

3Oh ' L'E (as of 0001)

CHEMISTRY RCS SECONDARY l

Alert Alert Values Units Ytlues Unitt d

Gross Gt r:a /. [h > 2 uc/n1 Condensate Oxygen ) 5 ppt Cendenstte pH @ 60 7 9.2 46-3 > E-2 ue/ml (m}-131

('/ S t e ar. I 1 l l I-131/133 O,80 7 0.1 Generaters l 1 1 2 1 3 l Dase Q-I-131 N98 -52. > 1.0 uti/mi pH l 7.dkI 7 3 81'8 $ i l< 7.3 Lithium C,39 r* ppm Cend I/91 /. A 1 /. 9 \ > 5 unhc Boron Concentration /M

  • ppn Cl- I<20lMCIdMO l > 20 ppb Beren i 4. 6 i 6 716. 3 i < 5 > 10 pp=

DISCHARGES Liquids: Gross B(te - Ga.ma Tritium

,_,. 4//A gals. __ ,ut/n1 ut uc/n1 c tals. ue/n1 ue uc/mi c l Geses:

uc/cc ue/cc c 4/

scf ue l

l PLANT OPEP).TIONS SUXMARY AND SIGNIFICANT EVENTS:

klLY ff?Ed fuMA S 25 0 /S OV 7~ Ot= $ f A'V/d d " / W A / W l~fA / A AI $ $

)

^ -

/1) Ave. Core Burnup es of 0001 vice 0600. Prepared By: _ IMN _

('-4 2) Based en expected station service usage 26-2Eh'e, should be'25-30X/e less tnan trc :

electrical generaticr. n e.ber

  • Lin!;ing vs.lue does not apply.

(3) Condenser Roto.teter value f ren 0000 reading on Secondtry A.C. Let,.

Depender.t en Fc:en te naintain constant pH. Acceptcble rengt ir Li - (C.35 - .0050s) 0.".5 trm.

4 Rev. 2 MAINE YANKEE 9/14/88 b EMERGENCY PREPAREDNESS EXERCISE Page 6.2-10 1988 SCENARIO MESSAGE FORM N OER MESSAGE NUMBER EOF-M-1 FROM_

OORD. CLOCK TIME UPON ACTIVATION TO EOF SCENARIO TIME LOCATION PARTICIPANT MESSAGE DRILL *******************

~

                                                  • THIS INITIAL CONDITIONS ARE AS OUTLINED IN THE FOLLOWING PAGE
O
                                                  • THIS IS A DRILL *******************

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Mainelankee attitets e ttcwenv , w ut. t s:.cc ,,,2 Rev. ,.

gfy4jgg Page 6.2-11 ro 8o7 4c6. wis Assti uwt c4576. (20n stic321

)

XY-0-23-72. Eev. 26 XAINE YANKEE THIS IS A DRil,'_ ptR13 Es:cMeM,.Tri_El T g, THIS IS A DRILL PLANT OFEFJ. TING STATUS Today's Alert Today's Alert Values values Units Values Values Unit R; actor Power Level '259 c 7 > 2630 &*I RCS T N 5. E > 552 *F Gr:ss Elect. Gen. 98/ > ESO Mwe CEDX tion _ _

AMO G5< 163 Step Net Elect. Gen. N (2) Mwe Ave Core Burnup 89S0 ' &*D/XTU Ctndenser Back Pressure d.88 > 3 li g RCS Ave Leat Rate . cN > 0. 6 gp C:ndenser Rotometer /. 6~ > 4(3) sefm Ce.lendar Year Net R: actor Core D/P /8.26 > 19.5 psid Cunulative Gen.

MbOM' 6'E (as of 0001)

CHEXISTRY RCS SECONDARY Alert Alert Values Units Values Un!* r d ppt Gross Ga=ca / SO > 2 ue/c1 Condensate Oxygen ) 5 Ccndensate pH @ 80 7 S.2 rN (v' J-131 96E-3 > E-2 uc/n1 l l S t e s. l l-I-131/133 d,8 d ') 0.1 Generaters i 1 f 2 f 3 l Dose Q-I-131 /M98 -d2. > 1. 0 uti/c1 pH I 7.59I 7.'$ 8i T dkl < 7.3 Lithium 0,.39 == ppm Cene  ! /. 9 i /. A i /. 9 1 > 5 u:5c Boron Concentration /M t ppm C1- l< 2 0 i t.20 14 M O l > 20 pri Beren i S 6 I S.N 10. 31 < 5 > 10 pp DISCHAFGES Liquids: Gross Beta - Gam.a Tritium A//A gals. ,uc/ml ut ue/n1 e gals. uc/ml ut uc/ml e Cases:

Alh scf uc/cc uc uc/cc c PLA?TT OPEPATIONS

SUMMARY

AND SIGNIFICANT EVENTS:

kuX b"Ed St>MA ? 2 5 0 /S O V 7'~ 0t= $f/V/[S ' /WA/Al ffA/AA/$5

(% :_  :

W Ave. Core Burnup as of 0001 vice 0600. Prepared By: M7 (2) Based on expected station service usage 26-2EXwc. should tc 25-3CM.'e 1 e : s *. r. i t trc!:

electrical generation number

  • Liniting value does not apply.

W ondenser C Rotometer value frem 0000 res. ding rn Secondtry A.C. LOL "Dependent on Beren to maintain constant ph. Acceptttle ranic Li . (0.35 .00150 ) . c.15 :: ,

Rev. 2 MAINE YANKEE 9/14/88 EMERGENCY PREPAREDNESS EXERCISE Page 6.2-12 1988 SCENARIO MESSAGE FORM ESC CONTROLLER MESSAGE NUMBER ESC-M-1 FROM OORDINATOR CLOCK TIME UPON ACTIVATION TO ESC SCENARIO TIME LOCATION PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

INITIAL CONDITIONS ARE AS OUTLINED IN THE FOLLOWING PAGES O

                                                  • THIS IS A DRILL *******************

O

MaineYan' lice Rev. 2 9/14/88 mete sticu. car rea uwe sv.c im --

Page 6.2-13 PO Box 406. wiS0AS$ti M AINE 04576. (2071822 C321

( MY-0-23-72. Fev. 26

( MAINE YANKEE THIS IS A DRILL ptp.103 #;[d.c"i%sMEc7%f?g,,c THIS IS A DRILL l

F1).N! OPEFJ. TING STATUS Today's Alert Today's Alert Values values tv. 2 t s Values Values U r. i t t R: actor Power Level c2597 >2630 K./T RCS T fN. 6 > 552 *F l 98/ > E90 Ewe CEDM os tion MO G5( 103 Steyr Grass Elect. Ge3. .

' 8750

  • KC/MTU Het Elect. Gen. 28k (2) Mwe Avs Core Burnup C:ndenser Bact Pressure d 88 > 3 H g RCS Ave Leat Rate .M > 0. 8 t: l C:ndenser Rotometer /. f > 4(3) scfm Calendar Year Net R actor Core D/P /8 M > 19.5 psid Cumulative Gen.

(as of 0001) N[OM ' Y*E CHEMISTEY RCS SECONDARY Alert Alert Values Unitt Valuer U r. i t t Gross Gr=.a /. 50 > 2 ue/ml Condensate Oxygen db > 5 r;t Cendensate pH @ CO 7 5.2 (O>131 94E-3 > E-2 ue/ml

~

Ste u: } l l l I-131/133 O,dd ) 0.1 Generaters i 1 1 2 l 3 l g//98 c2. uci/ml pH l7.d9f7,38i7d7l<7.2 D2so Q-I-131 > 1.0 Lithiun o.39 => ppm Cone } /. 9 i /. A 1 / 9 1>$ u=h:

Boron Concentration /N

  • ppm Cl- l< 2 0 1 2 ,70 id M O l > 20  ;;

Beren i S.b 1 d N l 0 31 < ; 71C pp:

DISCHARGES Liquids: Grors Eeta - G r.~.e Tritium A//A gals. ,uc/ml ue __ uc/ml c gals. ,_

ue/ml ut ue/ml c Gasos:

scf ut/cc ue ue/cc c PLANT OPERATIONS SITMMARY AND SIGNIFICANT EVENTS:

kar fi=EO Poa 7 25'B is our of Sfsyici -6/4/s/rux/su/c2

1) Ave. Core Burnup t.s of 0001 vice 0600. Freptredby:j (2) Based on expected station service usete 20- Eh.ec. should 1( 2 5- E M .'c lets r.u. trcr-electrical generatien number
  • Limiting ve.lue does not apply.

(3) Condenser Roto:-eter value f rca 0000 ree.cing cn Secer.ctry A.C. ut.

"Dependent en Beren to meintein censter.t TH.  ;; crittle rtn;e '

Li = (0. 3 5 - . 0 0 '. 5 0 r ) 0.1? O r r. .

Rev. 2

/G 9/14/88 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE Page 6.2-14 1988 SCENARIO MESSAGE FORM TY ^ * "'"r# MESSAGE NUMBER SEC-M-2 FROM SECURITY OFFICER CLOCK TIME 0835 TO ,

GUARD HOUSE SCENARIO TIME 00.05 l PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

SMOKE IS VISIBLE IN THE DIRECTION OF THE WISCASSET AIRPORT.

THE WISCASSET POLICE ARE RESPONDING TO AN AIRPLANE CRASH NORTH OF THE AIRPORT.  !

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                                                  • THIS IS A DRILL ************t****

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MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE Page 6.2-15 1988 SCENARIO MESSAGE FORM FROM SIMULATOR CR CONTROLLER _

MESSAGE NUMBER SCR-M-2 TO P.S.S. CLOCK TIME 0915 LOCATION SIMULATOR CR SCENARIO TIME 00:45 PARTICIPANT MESSAGE

, *************************THIS IS A DRILL *******************

(NOTE THIS MESSAGE IS TO BE ISSUED IF OPERATORS ATTEMPT TO BACKf'EED :1!(!G 6 FROM BUS 8 THROUGH BUS-TIE BREAKER 7T8)

BREAP..:R 7T8 WILL NOT STAY SHUT. THE BREAKER TRIPS OPEN ON OVERCURRENT IMMEDIATELY AFTER CLOSING SEQUENCE IS COMPLETED.

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                                                  • THIS IS A DRILL *******************

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) MAINE YANKEE 9/14/88 EMERGENCY PREPAREDNESS EXERCISE Page 6.2-16 1988 SCENARIO MESSAGE FORM FROM OSC REPAIR TM OBSERVER MESSAGE NUMBER OSC-M-2 TO OSC REPAIR TEAM LEADER CLOCK TIME 0930 DG-1B SCENARIO TIME 01:00 LOCATION PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

THE FOLLOWING CONDITIONS ARE' OBSERVED UPON INSPECTION OF THE DG-1B OUTPUT BREAKER:

-BREAKER CUBICLE IS WARM TO THE TOUCH

-INTERNAL INSPECTION REVEALS THAT THE BREAKER HAS APPARENTLY MAJOR DAMAGE TO THE CONTACTOR AND ASSOCIATED WIRING, A MORE DETAILED INSPECTION WILL BE PERFORMED UPON ARRIVAL OF s SUPPORT PERSONNEL

() BREAKER HAS SOMEHOW PARTIALLY WELDED ITSELF TO THE CUBICLE HOUSING. THE BREAKER CON 7; CTS ARE BADLY PITTED, BURNED AND HAVE THE APPEARANCE OF BEING PAk!IALLY MOLTEN AT ONE TIME.

INSULATION ON THE WIRES IS CHARRED AND BRITTLE.

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                                                  • THIS IS A DiiTLL*******************

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' EMERGENCY PREPAREDNESS EXERCISE. Page 6.2-17 1988 SCENARIO MESSAGE FORM OSC CONTROLLER MESSAGE NUMBER OSC-M-3 FROM OSC COORDINATOR CLOCK TIME 0930 TO OSC SCENARIO TIME 01:00 LOCATION PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

(THIS MESSAGE CARD IS TO BE ISSUED IF THE TSC REQUESTS THE OSC TO EXPEDITE REPAIRS TO AUXILIARY FEED PUMP P-25B)

MAINTENANCE REPORTS THAT EXPEDITING THE REPAIR TO AUXILIARY FEED PUMP P-25B WOULD STILL REQUIRE APPROXIMATELY 10 HOURS TO REASSEMBLE THE EQUIPMENT WITHOUT PERFORMING ANY CORRECTIVE ACTIONS. THE TURBINE ROTOR HAS BEEN DETERMINED TO BE GROSSLY O UNBALANCED AND IS IN THE PROCSSS OF BEING BALANCED BY CONTRACTORS FROM THE MANUFACTURER.

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Rev. 2

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's-) MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE Page 6.2-18 1988 SCENARIO MESSAGE FORM OSC REPAIR TEAM OBS MESSAGE NUMBER OSC-M-4 FROM OSC REPAIR TEAM LEADER CLOCK TIME 0930 TO LOCATION AUX FEED PUMP P-25C SCENARIO TIME 01:00 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

OSC REPAIR TEAM MEMBERS INVESTIGATING THE LOSS OF AUXILIARY FEED PUMP P-25C FIND THE FOLLOWING:

-ELECTRICAL SYSTEMS ARE UNDAMAGED (BREAKER AND MOTOR CONTROLLER)

-MOTOR SHAFT AND COUPLING ARE FINE, BUT THE PUMP SHAFT APPEARS TO BE SLIGHTLY WORN IN THE AREA OF THE PUMP CASING.

() *- , .a. ******************************************************

W4c '10 OBSERVER: IF THE REPAIR TEAM STATES THAT THEY WOULD PERFORM A TRIAL RUN OF THE PUMP, INFORM THEM THAT THEY WOULD HEAR METAL-TO-METAL CONTACT IN THE AREA OF THE PUMP SHAFT AND CASING.

ALSO, THE MOTOR CONTROLLER OVERLOAD DEVICE TRIPS PRIOR TO THE PUMP COMING UP TO RATED SPEED) * * *

                                                  • THIS IS A DRILL *******************

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-k MAINE YANKEE 9/14/88 Page 6.2-19 EMERGENCY PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE FORM A

MESSAGE NUMBER OSC-M-5 FROM TO OSC MAG TEM MADM CLOCK TIME 0930 14 CAT 10N

-25C SCENARIO TIME 01:00 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

(IF THE REPAIR TEAM DECIDES THAT THEY WILL ATTEMPT TO INSTALL A JUMPER BETWEEN P-25C AND P-25A)

WHILE ATTEMPTING TO DISCONNECT THE POWER LEADS FROM P-25C, ONE OF THE TERMINAL LUGS STRIPS.

IT WILL TAKE APPROXIMATELY 4 HOURS TO COMPLETE THE INSTALLATION OF O JUMPERS BETWEEN THE TWO MOTORS.

                                                  • THIS IS A DRILL *******************

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~N 9/14/88 (k MAINE YANKEE ms ! Page 6.2-20 EMERGENCY PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE FORM OSC REPAIR TEnM OBSERVER MESSAGE NUMBER OSC-M-6 FROM OSC REPAIR TEAM LDR CLOCK TIME OBSERVERS DISCRETION TO LOCATION AUX. FEED PUMP P-25C SCENARIO TIME __

PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

I AFTER DISASSEMBLING THE PUMP, THE FOLLOWING CONDITION IS NOTICED:

I

-THE BALANCE DRUM SPLIT RING IS DAMAGED

-THE SHIMS ARE CRACKED AND MISALIGNED

- -AXIAL CLEARANCES ARE OUT OF MANUFACTURER'S ALLOWABLE

! TOLERANCE l

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(' age 6.2-21 EMERGENCY PREPAREDUESS EXERCISE 1988 SCENARIO MESSAGE FORM

^ MESSAGE NUMBER

~

FROM OSC REPAIR TEAM LEADER 0930 TO CLOCK TIME FEED P M P-2C 01:00 LOCA'I TON SCENARIO TIME PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

INVESTIGATION OF THE LOSS OF FEED PUMP P-2C REVEALS THE FOLLOWING:

-D.C. LUBE OIL PUMP IS RUNNING

-NO APPARENT PHYSICAL DAMAGE IS PRESENT ON EITHER LUBE OIL PUMP P-120A OR P-120B (NO FURTHER INVESTIGATION CAN BE DONE UNTIL POWER IS RESTORED) l l

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                                                  • THIS IS A DRILL *******************

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MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 9/14/88 Page 6.2-22 1988 i SCENARIO MESSAGE FORM OSC REPAIR TEAM OBSERVER MESSAGE NUMBER OSC-M-8 FROM TO OSC REPAIR TEAM LEADER CLOCK TIME OBSERVERS DISCRETION LOCATION LUBE OIL PUMP P-120 A/B SCENARIO TIME PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

TEST RUN OF P-120A REVEALS THAT THE RELIEF VALVE HAS STUCK OPEN, PASSING OIL DIRECTLY TO THE LUBE OIL SUMP.

P-120B IS OPERATING NORMALLY.

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(./ EMERGENCY PREPAREDNESS EXERCISE Page 6.2-23 1988 SCENARIO MESSAGE FORM FROM OSC REPAIR TEAM OBSERVER MESSAGE NUMBER OSC-M-9 A TEAM LEADER OBSERVERS DISCRETION TO CLOCK TIME LOCATION LUBE OIL PUMP P-120A SCENARIO TIME PARTICIPANT MESSAGE

          • ?*******************THIS IS A DRILL *******************

DISASSEMBLY OF RELIEF VALVE REVEALS A MISALIGNED SHAFT. THE  !

MISALIGNMENT AND SUBSEQUENT VALVE OPERATION HAS SCORED THE SHAFT SUCH THAT A PROPER SEAL CANNOT BE MADE AROUND THE SHAFT. THE SHAFT WILL EITHER BE REPLACED OR MACHINED.

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(_, MAINE YANKEE 9/14/88 Page 6.2-24 EMERGENCY PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE FORM A

MESSAGE NUMBER OSC-M-10 FROM

^ ^ A CLOCK TIME 0945 TO

~

SCENARIO TIME 01:15 LOCATION PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

! INTERNAL INSPECTION OF THE BREAKER CUBICLE REVEALS THAT THE BREAKER HAS SOMEHOW PARTIALLY WELDED ITSELF TO THE CUBICLE HOUSING. THE BREAKER CONTACTS ARE BADLY PITTED, BURNED AND HAVE THE APPEARANCE OF BEING PARTIALLY MOLTEN AT ONE TIME.

INSULATION ON THE WIRES IS CHARRED AND BRITTLE.

                      • .**************THIS IS A DRILL *******************

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  1. s 9/14/88 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE Page 6.2-25 1988 SCENARIO MESSAGE FORM ESC CONTROLLER MESSAGE NUMBER ESC-M-2 FROM ESC METEOROMGIST CLOCK TIME 1000 TO _

ESC SCENARIO TIME 01:30 LOCATION _

PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

FROM THE ATTACHED NWS SURFACE MAPS, PROVIDE AN UPDATED WEATHER FORECAST FOR THE MAINE YANKEE SITE.

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                                                  • THIS IS A DRILL *******************

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EMERGENCY PREPAREDNESS EXERCISE Page 6.2-27 1988 SCENARIO MESSAGE FORM a

OF CONTROLLER EOF-M-2 FROM MESSAGE NUMBER RAD EVAL ASST. 1030, AS REQUESTED TO CLOCK TIME _

LOCATION EOF SCENARIO TIME 02:00 PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

UPDATED WEATHER FORECAST IS AS FOLLOWS ON THE ATTACHED PAGE 4

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      • THIS IS A DRILL ***

i GENERAL AREA NATIONAL WEATHER SERVICE FORECASTS 10:00 - 14:00 GENERAL AREA FORECAST CLOUDY WITH WINDS SOUTH-SOUTHWESTERLY AT 3-5 MPH, SHIFTING TO j WESTERLY BY EARLY EVENING, AS A COOL FRONT PASSES THROUGH THE FORECAST AREA. CHANCE OF AN OCCASIONAL SHOWER TONIGHT, LOW NEAR 50 F. HIGH TOMORROW 62 F.

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' EMERGENCY PREPAREDNESS LXERCISE Page 6.2-29 1988 SCENARIO MESSAGE FORM OSC CONTROLLER MESSAGE NUMBER OSC-M-11 [

FROM A OR CLOCK TIME 1145 TO OSC SCENARIO TIME 03:15 LOCATION I PARTICIPANT MESSAGE ,

                                                  • THIS IS A DRILL *******************

REPAIR TEAM DISPATCHED TO COORDINATE AND COMPLETE THE BACKFEED OF POWER FROM THE 345 kV SWITCHYARD REPORT THAT IT WILL TAKE APPROXIMATELY 6 HOURS TO COMPLETE THE BACKFEED. i.

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' MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE Page 6.2-30 9/14/88 1988 SCENARIO MESSAGE FORM FROM SIMULATOR CR CONTROLLER MESSAGE NUMBER SCR-M-3 TO P.S.S. CLOCK TIME 1235 (APPROX)

LOCATIO!; SIMULATOR CR SCENARIO TIME 09:35 (APPROX) i ,

PARTICIPANT MESSAGE

                                                  • THIS IS A DRILL *******************

1 FEEDWATER FLOW IS AVAILABLE FROM AUXILIARY FEEDWATER PUMP P-25A.

STEAM GENERATOR LEVELS ARE SLOWLY INCREASING.

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i MAINE YANKEE EMERGEliCY PREPAREDNESS EXERCISE ,

I 1988  :

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SUMMARY

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( j 9/14/88 N/ Page 7.1-1 MAINE YANKEE ATOMIC POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1988 7.1 EVENTS

SUMMARY

The following information and supplementary material are provided for those observers having in-plant control assignments so as to further ensure the proper development of the scenario.

The information provided in this section assumes that the "players", who are dispatched to perform repair or other activities will take certain actions in response to the scenario.

The controller / observer must be cognizant of the actions of those players to which assignment is given and provide information regarding the results of the players' actions as appropriate.

The information provided in this section does not preclude the possibility that the observer will be required to provide additional information to the players.

    • OBSERVERS SHALL ENSURE THAT PLAYERS DO NOT MANIPULATE ANY **

EQUIPMENT WHICH WILL AFFECT ACTUAL PLANT OPERATIONS.

Approximate Mini-scenario Time Event Location 7.2.1 0900 Loss of Steam Driven Turbine Bldg.

Main Feed Pump, P-2C 7.2.2 0901 Emergency Diesel Turbine Bldg.

Generator (DG-1B)

Failure 7.2.3 0902 Emergency Feed Pump Turbine Bldg.

Failure, P-25C 7.2.4 0930 Backfeed of Power Discussions From the 345 kV in TSC and Switchyard OSC 7.2.5 0930 Expediting Repair Discussions of Steam Driven in TSC and Auxiliary Feed OSC Pump P-25B 7.2.6 0931 Loss of Power In TSC, OSC and TSC, OSC and EOF EOF

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t EMERGEllCY PREPAREDNESS EXERCISE

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8/8/88 Page 7.2.1-1 MAINE YANKEE ATOMIC POWER STATI'.s EMERGENCY PREPAREDNESS EXERC. M l 1988 l

l 7.2.1 Loss of Steam Driven Main Feed Pumo. P-2C l

l I. General Descriotion The relief valve on the operating lube oil pump (P-120A) lifts and sticks open causing a decrease in control oil pressure to the steam dri.:.n main feed pump (P-2C). Auxiliary lube oil pump (P-120B) s srts but pressure does not recover quick enough to prevent tripping of P-2C and subsequently the Main Turbine. The .

Main Turbine trip results in a reactor scram and loss of AC power.

II. DescriDtion of Player ResDonse/ Observations / Corrective Actions

() The Ao should check to ensure that the D.C. emergency lube oil pump has started. Due to the loss of power, both Main Lube oil pumps will be inoperable.

Upon restoration of AC power, maintenance should test both pumps to determine operability and output pressure control. The relief valve on the discharge of P-120A will be found to be stuck open, thereby passing lube oil to the sump. The output of P-120B will be found to be normal.

III. Event Closcout Upon verification of the cperation of the DC lubo oil pump, further action must avait restoration of AC power supplies to the main and auxiliary feed pumps.

Subsequent repair or replacement of the damaged stom of the relief valve will allow the return to service of the Main Lubo oil Pump.

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' - ' Page 7.2.2-1 MAINE YANKEE ATOMIC POWER ST.itION >

EMERGENCY PREPARE 0 NESS EXERCISE 1988 7.2.2 Emeraency Diesel Generator (DG-1B) Failure L

I. General Descriotion Diesel Generator 1B output breaker trips open as soon as load is applied. This results in a loss of the 4160 volt Bus 6.

The loss of Bus 6 disables The followir.g major pieces of equipment:

Emergency Feed Pump P-25A Charging Pump P-14B Secondary Component Cooling Pumps P-10A and 10B 2

Any attempt to reshut the Diesel Generator's output breaker will not be successful.

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( II. pescription of Player Resoonse/ Observations / Corrective Actions The Control Room should dispatch an AO and subsequently (when available apprx 0900) an OSC team to determine the problem.

The AO. upon initial investigation, will discover that there is extreme heat in the area of the breaker housing and that an internal inspection of the breaner reveals that the contacta appear to be badly pitted, burned and had apparently been

] partially molten at sone point. He also notices that the breaker frame has somehow welded itself into the switchgear cubicle.

l An OSC repair team should estimate a repair time and report this to the Control Room. (Estimated time to repair will be

! approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). Repair should include clearing Bus 6 switchgear and removing the Diesel Generator output breaker.

It is not known if any damage has been done to the Diesel Generator, y

but damage is possible and load testing should be accomplished before it is returned to service.

The following actions may be discussed in order to repair / replace the DG-1B output breaker:

A. The repair team may replace the damaged breaker with any i number of breakers (of equal rating) presently installed for j other non-essential pieces of equipment.

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Page 7.2.2-2 B. The team may also attempt to obtain an equally rated breaker from spare parts inventory.

(NOTE: THE ABOVE ACTIONS SHOULD BE INVESTIGATED CONCURRENTLY TO DETERMINE WHICH ACTION WOULD RESTORE DG-1B TO SERVICE AS SOON AS POSSIBLE)

C. The repair team may algo be directed to work towards clearing Bus 6 of its faulted condition so that the bus can be re-energized from other sources. This would preclude investigation of diesel generator operability and would constitute determining what initially caused the breaker to overload.

The repair team should outline the procedure to be used in extracting the damaged breaker from the switchgear cubicle and troubleshooting of the faulted bus. The repair team should also be able to describe the actions required to determine the extent of any damage to the diesel generator.

III. Event Closecut When the integrity of Bus 6 is established, the bus can be re-energized f rom available sources of power (other than DG-1B) .

Operability of the diesel generator need not be demonstrated in the short term if the 345kV system is going to bo used for re-energizing the bus.

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' f-~x) Rev.1 t 8/8/88 Page 7.2.3-1 MAINE YANKEE ATOMIC POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1988 7.2.3 Emercency Feed Pumo P-25C Failure I. General Descrintion An overcurrent alarm for Emergency Feed Pump P-25C is received in the control Room. The pump motor ammeter indicates off-scale high, and within a few seconds of receiving the alarm, the pump's supply breaker trips open. Attempts to reset the breaker and restart the pump are unsuccessful.

II. Descrintion of Player Resconse/ Observations / Corrective Actions The Control Room may dispatch an AO to the Emergency Fced Water (EFW) Pump Room to investigate tripping of the pump's breaker. The AO performs a visual inspection of the breaker s

internals and determines that nothing is apparently wrong with the equipment. He should then proceed to inspect the pump and motor. Inspection of the purp shaft will reveal that the shaft is bind. g against the pump casing. If the Control Room elects to attempt a restart of the pump, obvious metal-to-metal contact j will be heard as the pump gains speed. The pump however, will not attain rated speed before the breaker trips on overload.

Disassembly of the pump will be necessary to correct the problem. The balance drum split ring and shims will be found to be damaged and must be replaced. Axial clearances will need to be re-established per manufacturer's specifications. Disassembly and repair will take at least one full shift. Reassembly and testing will take at least one additional shift. All corrective actions should be in accordance with procedures contained in the

' manufacturer's Installation, Operation and Maintenance (IOM)

Manual.

4 The repair team should be aware that a complete spare EFU pump may be available in spare parts inventory.

III. Eygnt Closecut

After the problem is identified, the balance drum split

! rings replaced, the shims re-installed and the thrust bearing

, inspected, the pump may be reassembled, tested and returned to service, i

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Rev.1 O 8/8/88 Page 7.2.4-1 MAINE YANKEE ATOMIC POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1988 7.2.4 Backfeed of Power from the 345 kV Switchvard I. General Descriotion Due to the loss of both 115 kV lines attempts to restore off-site power may be initiated. This procedure would involve supplying power from the 345 kV switchyard. Coordination between MYAPC and CMP personnel will be required to accomplish this activity.

II. Qggpriotion of Player ResDonse/ Observations / Corrective Actions The P.S.S. should direct one of the operators to contact the CMP dispatcher to find out hcw long the 115 kV lines will be unavailable. If this takes place the Simulator controller shall O inform the operator that it will take approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the 115 kV lines to service.

Based on this estimate, operations personnel and OSC team membero should initiate the actions specified in Section 10.5.3 of AOP 2-90-8, Plant, Cooldown From the Alternate Shutdown Panel Personnel should identify the tools, reference drawings and means of notifying and coordinating actions with CMP crews. The physical location of the relays to be jumpered should be identified.

III. Event Closeogt This event will be terminated at the direction of the controller at approximately 1200, following appropriate discussions relevant to actually performing the backfeed from the 345 kV yard.

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Rev.1 8/8/88 Page 7.2.5-1 MAINE YANKEE ATOMIC POWER STATION  ;

i EMERGENCY PREPAREDNESS EXERCISE t l'

1988  !

L 7.2.5 Exceditina Reedir of Steam Driven Auxiliary Feed Pumo P-25B I. General Descriotion i

The Steam Driven Auxiliary Feed Pump P-25B has been out of service for extended maintenance. While being serviced it was

! discovered that seversi rows of turbine blades have been making contact v'.th the tuvoine shroud. This has caused sufficient  ;

I wearing c; the blading as to cause an imbalance condition beyond manufacturer's allowable tolerance. .i II. Descriotion of Player Resoonse/ Observations / Corrective Actions The OSC may be requested to expedite the repairs to the Out-of-Service Steam Driven Auxiliary Feed Pump, P-25B. This ,

component is unavailable due to being mid-way through it's i overhaul and will not be able to be assembled in sufficient time l to be of any use in recovering from the loss of Steam Generator l Feed casualty being experienced. OSC Repair personnel may i attempt to determine the state of repair of the pump assembly but t will not be allowed to reassemble the pump due it having an j unbalanced turbine rotor which renders it unusable. No  !

corrective actions can be initiated which will rectify the j problem.

III. Event Closecut j This event will be terminated following operator investigation  ;

4 into the present state of repair of P-25B. i i

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P Rev.1 fT

\l 8/8/88 i Page 7.2.6-1 e

MAINE YANKEE ATOMIC POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1988 7.2.6 Loss of Power in the TSC. OSC and EOF I. General Descriotion 1

i The loss of the 115 kV lines coupled with the turbine trip and loss of DG-1B may cause a temporary loss of power in the Maine Yankee Staff r Building. This building contains the Technical Support Center,

Operations Support Conter and the Emergency Operations Facility, j The power could remain off until the operations crew establishes an energized bus te provide the necessary power to the facilities.

II. Description of Player Response / Observations / Corrective Actions  ;

! The first person reporting to any of the facilities should notice i 1

a O that the lights are not on. This person should notify the control roon of the situation and request that they expedite restoring power so that facility activation can be accomplished.

I III. Event Closecut l This event will be terminated following operator actions to restore power to the appropriate bus. Depending on the method i the controller organization decides upon to simulate the actual j loss of power in the facilities, (i.e. shutting off the power at

the local wall switch or opening the appropriate circuit breaker [

] at the distribution panel) power will be restored upon notification that the operations crew has re-energized the appropriate bus. (This notification would be made by the i Simulator Control Room Controller to the Exercise Lead Controller who would then notify the respective facility controllers)

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i MAINE YANKEE j i EMERGENCY PREPAREDNESS EXERCISE 1988 a

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8.0 OPERATIONAL DATA AllD GRAPHS 1

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O O O Rev. 2 9/14/88 8.0 OPERATIONAL DATA Page 8.0-1 CLOCK TIME 8:30 8:45 9:00 9:15 SCENARIO TIME 0:00 0:15 0:30 0:45 -

  1. 1 S/G LEVEL WR (in) 319.49 319.49 231.91 186.92
  1. 2 S/G LEVEL WR (in) 320.54 320.54 240.22 193.29
  1. 3 S/G LEVEL WR (in) 320.15 320.15 239.82 192.96
  1. 1 S/G PRESSURE (PSIA) 853.53 853.53 963.55 996.75-
  1. 2 S/G PRESSURE (PSIA) 853.43 853.43 971.01 996.35
  1. 3 S/G PRESSURE (PSIA) 853.43' 853.43 970.54 996.33 RCS PRESSURE (PSIA) 2226.49 2226.49 2270.09 2043.64 CNTMT PRESSURE (PSIA) 16.09 16.09 16.09 16.08 CNTMT RAD LEVEL (R/HR) <1.0 <1.0 <1.0 <1.0 HOTTEST CET (DEG F) 604.33 604.33 587.70 572.19 TOTA.'.FEEDWATER FLOW 3153.93 3153.93 117.00 0.00 Tave (DEG F) 576.00 576.00 576.00 580.00

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Rev.2 9/14/88 Page 8.0-2 8.0 OPERATIONAL DATA CLOCK TIME 9:30 9:45 10:00 10:15 SCENARIO TIME 1:00 1:15 1:30 1:45

  1. 1 S/G LEVEL WR (in) 135.88 75.77 51.02 44.54
  1. 2 S/G LEVEL PR (in) 136.29 74.55 50.11 43.98
  1. 3 S/G LEVEL WR (in) 136.44 74.68 50.20 44.03
  1. 1 S/G PRESSURE (PSIA) 990.59 627.40 392.47 406.69 3
  1. 2 S/G PRESSURE (PSIA) 990.59 627.39 392.46 406.70
  1. 3 S/G PRESSURE (PSIA) 990.59 627.39 392.46 406.70 RCS PRESSURE (PSIA) 2083.46 2050.53 1359.28 1267.59 CNTMT PRESSURE (PSIA) 16.07 16.07 16.19 16.27 CNTMT RAD LEVEL (R/HR) <1.0 <1.0 2.50 13.00 HOTTEST CET (DEG F) 581.96 583.56 590.05 569.65 TOTAL FEEDWATER FLOW 0.00 0.00 0.00 0.00 Tave (DEG F) 580.00 582.00 590.00 570.00

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Rev. 2 9/14/88 Page 8.0-3 8.0 OPERATIONAL DATA CLOCK TIME 10:30 10:45 11:00 11:15 SCENARIO TIME 2:00 2:15 2:30 2:45

  1. 1 S/G LEVEL WR (in) 40.53 39.80 39.50 39.00
  1. 2 S/G LEVEL WR (in) 40.18 39.80 39.60 39.00
  1. 3 S/G LEVEL WR (in) 40.14 39.80 39.50 39.00
  1. 1 S/G PRESSURE (PSIA) 357.42 325.00 300.00 290.00
  1. 2 S/G PRESSURE (PSIA) 357.42 325.00 300.00 290.00
  1. 3 S/G PRESSURE (PSIA) 357.42 325.00 300.00 290.00 RCS PRESSURE (PSIA) 1137.32 1110.00 1080,00 1040.00 CNTMT PRESSURE (PSIA) 16.31 16.32 15.33.- 16.33 CNTMT RAD LEVEL (R/HR) 15.00 15.00 15.50 16.00 HOTTEST CET (DEG F) 551.73 548.00 544.00 540.00 TOTAL FEEDWATER FLOW 0.00 0.00 0.00 0.00 Tave (DEG F) 551.00 549.00 544.00 540.00

n Rev. 2 9/14/88 Page 8.0-4 8.0 OPERATIONAL DATA CLOCK TIME 11:30 11:45 12:00 12:15*

SCENARIO TIME 3:00 3:15 3:30 9:45*

  1. 1 S/G LEVEL WR (in) 38.20 37.80 37.29 39.57
  1. 2 S/G LEVEL WR (in) 38.20 37.80 36.96 40.71
  1. 3 S/G LEVEL WR (in) 38.20 37.80 36.99 38.69
  1. 1 S/G PRESSURE (PSIA) 282.00 279.00 276.84 165.48
  1. 2 S/G PRESSURE (PSIA) 282.00 279.00 276.84 165.51
  1. 3 S/G PRESSURE (PSIA) 282.00 279.00 276.34 165.50 RCS PRESSURE (PSIA) 1010.00 1009.00 997.97 1203.25 CNTMT PRESSURE (PSIA) 16.34 16.35 16.36 18.20 CNTMT RAD LEVEL (R/HR) 16.50 17.00 17.50 25.00 IlOTTEST CET (DEG F) 538.00 535.00 532.37 502.10 TOTAL FEEDWATER FLOW 0.00 0.00 0.00 61.59 Tave (DEG F) 538.00 535.00 532.00 502.00
  • NOTE: SCENARIO TIME JUMP OF 6 IIOURS IIAS OCCURRED.

PIANT COOLDOWN IS IN EFFECT, BACKFEED FROM 345 kV SWITCIIYARD IS COMPLETE.

-q O O O Rev. 2 9/14/88 Page 8.0-5 8.0 OPERATIONAL DATA CIDCK TIME 12:30* 12:45* 13:00*

SCENARIO TIME 10:00* 10:15* 10:30*

  1. 1 S/G LEVEL WR (in) 110.65 204.79 255.22
  1. 2 S/G LEVEL WR (in) 107.70 194.52 247.04
  1. 3 S/G LEVEL WR (in) 160.70 196.48 247.60
  1. 1 S/G PRESSURE (PSIA) 124.06 176.87 136.08
  1. 2 S/G PRESSURE (PSIA) 124.03 176.85 136.08
  1. 3 S/G PRESSURE (PSIA) 124.02 176.86 136.08 RCS PRESSURE (PSIA) 935.83 947.67 672.81 CNTMT PRESSURE (PSIA) 18.64 18.81 19.10 CNDIT RAD LEVEL (R/HR) 25.00 26.00 30.00 HOTTEST CET (DEG F) 469.09 397.51 364.29 TOTAL FEEDWATER FIDW 83.43 81.67 82.98 Tave (DEG F) 469.00 397.00 364.00
  • NOTE: A SCENARIO TIME JUMP OF 5 HOURS HAS OCCURRED.

PLANT COOLDOWN IS IN EFFECT, BACKFEED FROM 345kV SWITCHYARD IS COMPLETE.

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9.0 RADIOLOGICAL DATA O

1967e/3.226

O MAINE YANKEE MERGENCY PREPAREDNESS EXIRCISE 1988

9. AREA RADIATION McNyrogg O

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V U Rev.2 9/14/88 Page 9.1-1 9.1 AREA RADIATION MONITORS CIDCK TIME 8:30 8:45 9:00 9:15 SCENARIO TIME 0:00 0:15 0:30 0:45 RADIATION MONITOR UNITS MANIPUIATOR CRANE R/HR O.03 0.03 0.03 0.004 RI-6104 CONTAINMENT llIGH RANCE 1 R/11R <1.0 <1.0 <1.0 <1.0 1 CONTAINMENT HIGli RANGE 2 R/IIR <1.0 <1.0 <1.0 <1.0 i

CONTAINMENT IDW RANGE R/IIR 0.01 0.01 0.01 0.002 RI-6105 DECON AREA R/IIR O.01 O.01 O.01 0.01 a RI-6106 F17EL POOL AREA R/liR O.0005 0.0005 0.0005 0.0002 RI-6107 SAMPLE ROOM R/IIR O.004 0.004 0.004 0.001 RI-6108 PRIMARY AUXILIARY BLDG R/HR 0.0006 0.0006 0.0006 0.0004 i RI-6109 i

SPRAY t JMP AREA R/ilR 0.0015 0.0015 0.0015 0.001 RI-6110 1

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~ %j' Rev.2 9/14/88 Page 9.1-2 9.1 AREA RADIATION MONITORS CIDCK TIME 9:30 9:45 10:00 10:15 SCENARIO TIME 1:00 1:15 1:30 1:45 RADIATION MONITOR UNITS MANIPULATOR CRANE R/HR 0.004 0.004 2. ) OSH RI-6104 CONTAINMENT HIGH RANGE 1 R/HR <1.0 <1.0 2.5 13 CONTAINMENT HIGH RANGE 2 R/HR <1.0 <1.0 2.5 13 CONTAINMENT LOW RANGE R/HR 0.002 0.002 2.5 OSH RI-6105 DECON AFS.A R/HR 0.01 0.01 0.01 0.01 RI -6106 FUEL POOL AREA R/HR O.0002 0.0002 0.0007 0.0002 RI-6107 SAMPLL ROOM R/IIR 0.001 0.001 0.'J01 0.001 RI-61C9 PRIMARY .UXILIARY BLDG R/HR 0.0004 0.0004 0.0004 0.0004 RI-6109 SPRAY PUMP AREA R/IIR O.001 0.001 0.002 0.003 RI-6110 f

3 v s .s Rev.2 9/14/88 Page 9.1-3 9.1 AREA RADIATION MONITORS CLOCK TIME 10:30 10:45 11:00 11:35 SCENARIO TIME 2:00 2:15 2:30 2:45 RADIATION MONITOR UNITS HANIPULATOR CRANE R/HR OSII OSH OSH OSH RI-6104 CONTAINMENT HIGH RANGE 1 R/HR 15 15 15.5 16 CONTAINMENT HIGri RANGE 2 R/HR 15 15 15.5 16 CONTAINMENT LOW RANGE R/HR OSli OSH OSH OSH

. RI-6105 DECON AREA R/HR 0.01 0.01 0.01 0.01 RI-6106 FUEL POCL AREA R/HR 0.0002 0.0002 0.0002 0.0002 RI-6107 SAMPLE ROOM R/HR 0.002 0.002 0.002 0.002 RI-6108 PRIMARY AUXILIARY BLDG R/HR 0.0004 0.0004 0.0004 0.0004 RI-6109 SPRAY PUMP AREA R/HR 0.003 0.003 0.003 0.003 R1-6110

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Rev.2 9/14/88 Page 9.1-4 _

CIDCK TII** 11:30 11:45 12:00 12:15*

SCENARIO TIME 3:00 3:15 3:30 9:45*

RADIATION MONITOR UNITS MANIPULATOR CRANE R/HR OSH OSh OSH OSH ,

RI-6104 CONTAINMEN" HIGH RANGE 1 R/HR 16.5 17 17.5 25 CONTAINMENT HIGH RANGE 2 R/HR 16.5 17 17.5 25 CONTAINMENT IDW RANGE R/HR OSII OSH OSH OSH RI-6105 DECON AREA R/IIR 0.01 0.01 0.01 0.01 RI-6106 FUEL POOL AREA R/IIR O.0002 0.0002 0.0002 0.0002 RI-6107 SAMPLE ROOM R/IIR 0.002 0.002 0.002 0.002 RI-6108 PRIMARY AUXILIARY BLDG R/IIR 0.0004 0.0004 0.0004 0.0004 RI-6109 SPRAY PUMP AREA R/IIR O.003 0.003 0.003 0.004 RI-6110

  • NOTE: A SCENARIO TIME JUMP OF 6 HOURS HAS OCCURRED.

PLANT COOLDOWN IS IN EFFECT, BACKFEED FROM THE i 345 kV SWITCI; YARD IS COMPLETE.

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- ____g O O O Rev.2 9/14/88 Page 9.1-5 9.1 AREA RADIATION MONITORS l CIDCK TIME 12:30* 12:45* 13:00*

SCENARIO TIME 10:00* 10:15* 10:30*-

RADIATION MONITOR UNITS MANIPULATOR CRANE R/HR OSH OSH OSH RI-6104 CONTAINMENT HIGH RANGE 1 R/HR 25 26 30 CONTAINMENT HIGH RANGE 2 R/hR 25 26 30 CONTAINMENT IDW RANGE R/HR OSH OSH OSH RI-6105 DECON AREA R/HR O.01 0.01 0.01 RI-6106 FUEL POOL AREA R/HR 0.0002 0.0002 0.0002 RI-6107 SAMPLE ROOM R/HR O.002 0.002 0.002 RI-6108 PRIMARY AUXILIARY BLDG R/HR 0.0004 0.0004 0.0004 RI-6109 SPRAY PUMP AREA R/HR O.004 0.004 0.005 RI-6110

  • NOTE: A SCENARIO TIME JUMP OF 6 HOURS HAS OCCURRED.

PLANT COOLDOWN IS IN EFFECT, BACKFEED FROM THE 345 kV SWITCHYARD IS COMPLETE.

2

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MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE ,

i l I

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9.2 PROCESS RADIATION MONITORS l

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O O O Rev.2 9/14/88 Page 9.2-1 9.2 PROCESS RADIATION MONITORS CIDCK TIME 8:30 8:45 9:00 9:15 i SCENARIO TIME 0:00 0:15 0:30 0:45 RADIATION MONITOR UNITS PRIMARY VENT STACK CPM 400 400 400 400 RI-3902X PRIMARY VENT GAS CPM 110 110 110 50 RI-3902Y CONDENSOR AIR EJECTOR CPM 85 85 85 65 RI-1801 PRIMARY COMP. COOLING CPM 100 100 1C: 100 RI-3401 SECONDARY COMP. COOLING CPM 80 80 80 80 RI-1"J01 CPM 300 300 300 50 NO.1 S/G BLOWDOWN RI-2601 CPM 300 300 300 50 NO.2 5/G BLOWDOWN PI-2602 CPM 300 300 300 50 l NO.3 S/G BLOWDOWN l

RI-2603 SERVICE BLDG. EXHAUST CPM 40 40 40 40 l

RI-6101 SERVICE WATER CPM 40 40 40 30 RI-1601

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Rev. 2 9/14/88 Page 9.2-2 9.2 PROCESS RADIATION MONITORS CLOCK TIME 8:30 8:45 9:00 9:15 SCENARIO TIME 0:00 0:15 0:30 0:45 RADIATION MONITOR UNITS LIQUID WASTE DISPOSAL CPM 200 200 200 200 RI-3801 LETDOWN (LOW RANGE) CPM NIS NIS NIS NIS RI-3101 LETDOWN (HIGH RANGE) CPM 1000 1000 1000 100 RI-3102 WASTE GAS VENT CPM 70 70 70 250 RI-3901 BORON WASTE CPM 50000 50000 50000 50000 RI-3701 CONTAINMENT PARTICULATE CPM 900 900 2000 20000 RI-6102X CONTAINMENT GAS CPM 100 100 5000 OSH RI-6102Y

.. .. . . < , _ _ _ - - _. -.. __ .. . . _. _ ~_ .

t O O O Rev.2

. 9/14/88 Page 9.2-3 i 9.2 PROCESS RADIATION MONITORS 3 CLOCK TIME 9:30 9:45 10:00 10:15 SCENARIO TIME 1:00 1:15 1:30 1:45 RADIATION MONITOR UNI!3 PRIMARY VENT STACK CPM 400 400 400 400 RI-3902X l PRIMARY VENT GAS CPM 50 50 50 50

) RI-3902Y l 65 65 65

)

CONDENSOR AIR EJECTOR CPM 65 j RJ-1801 i

PRIMARY COMP. COOLING CPM 100 100 100 100

! RI-3401 SECONDARY COMP. COOLING CPM 80 80 80 80 RI-1701 l

i NO.1 S/G BLOWDOWN CPM 50 50 50 50

, RI-2601 l

j NO.2 S/G BLOWDOWN CPM SO 50 50 50 t RI-2602 NO.3 S/G BLOWDOWN CPM SG 50 50 50 RI-2603 j SERVICE BLDG. EXHAUST CPM 40 40 40 40

! RI-6101 1

SERVICE WATER CPM 30 30 30 30 l RI-1601 a

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Rev.2 9/14/88 Page 9.2-4

  • 9.2 PROCESS RADIATION MONITORS CIDCK TIME 9:30 9:45 10:00 10:15 SCENARIO TIME 1:00 1:15 1:30 1:45 RADIATION MONITOR UNITS LIQUID WASTE DISPOSAL CPM 200 200 200 200 RI-3801

~

LETDOWN (IDW RANGE) CPM NIS NIS NIS NIS RI-3101 LETDOWN (HIGH RANGE) CPM 100 100 100 100 RI-3102 WASTE GAS VENT CPM 250 250 250 250 RI-3901 BORON WASTE CPM 50000 50000 50000 50000 RI-3701 CONTAINMENT PARTICULATE CPM OSH OSH OSH OSH RI-6102X CONTAINMENT GAS CPM OSH OSH OSH OSH RI-6102Y

O O O Re'. 2 9'14/88

~/ age 9.2-5 9.2 PROCESS RADIATION MONITORS CLOCK TIME 10:30 10:45 11:00 11:15 SCENARIO TIME 2:00 2:15 2:30 2:45 RADIATION MONITOR UNITS PRIMARY VENT STACK CPM 400 400 400 400 RI-3902X PRIMARY VENT GAS CPM 50 50 50 50 RI-3902Y CONDENSOR AIR EJECTOR CPM 65 65 65 65 RI-1801 PRIMARf COMP. COOLING CPM 100 100 100 100 RI-3401 SECONDARY COMP. COOLING CPM 80 80 80 80 RI-1701 NO.1 S/G BLOWDOWN CPM SO 50 50 50 RI-2601 NO.2 S/G BLOWDOWN CPM SO 50 50 50 RI-2602 NO.3 S/G BLOWDOWN CPM SO 50 50 50 l RI-2603 I

40 40 40 SERVICE BLDG. EXHAUST CPM 40 RI-6101 SERVICE WATER CPM 30 30 30 30 RI-1601

3%

f Rev.2-9/14/88 Page 9.2-6 9.2 PROCESS RADIATION MONITORS CIDCK TIME 10:30 10:45 11:00 11:15 SCENARIO TIME 2:00 2:15 2:30 2:45 RADIATION MONITOR UNITS LIQUID WASTE DISPOSAL CPM 200 200 200 200 RI-3801 LETDOWN (IDW RANGE) CPM NIS NIS NIS NIS RI-3101 LETDOWN (HIGH RANGE) CPM 100 100 100. 100 l RI-3102 WASTE GAS VENT CPM 250 250 250 250 RI-3901 BORON WASTE CPM 50000 50000 50000 50000 RI-3701 CONTAINMENT PARTICULATE CPM OSH OSH- OSH OSH RI-6102X CONTAINMENT GAS CPM OSH OSH OSH OSH RI-6102Y

O O O Rev.2 9/14/88 Page 9.2-7' 9.2 PROCESS RADIATION MONITORS CLOCK TIME 11:30 11:45 12:00 12:15*

SCENARIO TIME 3:00 3:15 3:30 9:45*

RADIATION MONITOR UNITS PRIMARY VENT STACK CPM 400 400 400 400 RI-3902X PRIMARY VENT GAS CPM SO 50 50 50 RI-3902Y CONDENSOR AIR EJECTOR CPM 65 65 65 65 RI-1801 PRIMARY COMP. COOLING CPM 100 100 100 100 RI-3401 SECONDARY COMP. COOLING CPM 80 80 80 80 RI-1701 NO.1 S/G BLOWDOWN CPM 50 50 50 SG RI-2601 NO.2 S/G BLOWDOWN CPM 50 50 50 50 RI-2602 NO.3 S/G BLOWDOWN CPM SO 50 50 50 RI-2603 SERVICE BLDG. EXHAUST CPM 40 40 40 40 RI-6101 SERVICE WATER CPM 30 30 30 30 RI-1601

  • NOTE: A SCENARIO TIME JUMP OF 6 HOURS IIAS OCCURRED.

PLANT COOLDOWN IS IN EFFECT, BACKFEED FROM TIIE 345 kV SWITCHYARD IS COMPLETE.

O O - 5f

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Rev.2 9/)4/88 Pag. 9.2 9.2 PROCESS RADIATION MONITOR 3 CIDCK TIME 11:30 11:45 12:00 12:15*

SCENARIO TIME 3:00 3:15 3:30 9:45*

RADIATION MONITOR UNITS LIQUID WASTE DISPOSAL CPM 200 200 200 200 RI-3801 LETDOWN (LOW RANGE) CPM NIS NIS NIS NIS RI-3101 LETDOWN (HIGH RANGE) CPM 100 100 100 100 RI-3102 WASTE GAS VENT CPM 250 250 250 250 RI-3901 BORON WASTE CPM 50000 50000 50000 50000 RI-3701 CONTAINMENT PARTICULATE CPM OSH OSH OSH OSH RI-6102X CONTAINMENT GAS CPM OSH OSH OSH OSH RI-6102Y

  • NOTE: A SCENARIO TIME JUMP OF 6 HOURS HAS OCCURRED.

PLANT COOLDOWN IS IN EFFECT, BACFFEED FROM THE 345 kV SWITCHYARD IS COMPLETE.

% -] \v' ~ _ .

Rev.2 9/14/88 1

Page 9.2-9 9.? PROCESS RADIATION MONITORS CIDCK TIME 12:30* 12:45* 13:00*

SCENARIO TIME 10:00* 10:15* 10:30*

RADIATION MONITOR UNITS PRIMARY VENT S"'ACK CPM 400 400 400 RI-3992X PRIMARY VENT GAS CPM 50 50 50 RI-3902Y CONDENSOR AIR EJECTOR CPM 65 65 65 RI-1801 PRIMARf COMP. COOLING CPM 100 100 100 RI -3401 SECONDARY COMP. COOLING CPM 80 80 80 RI-1701 NO.1 S/G BIDWDOWN CPM 50 50 50 RI-2601 NO.2 S/G BLOWDOWN CPM 50 50 50 RI-2602 NO.3 S/G BIOWDOWN CPM 50 50 50 RI-2603 SERVICE BLDG. EXIIAUST CPM 40 40 40 RI-6101 SERVICE WATER CPM 30 30 30 RI-1601

  • NCTE: A SCENARIO TIME JUMP OF 6 HOURS IIAS OCCURRED.

PLANT COOLDOWN IS IN EFFECT, BACKFEED FROM TIIE 345 kV SWITC11 YARD IS COMPLLTE.

[% -

\~_ ,

Rev.2 9/14/88 Page 9.2-10 ,

9.2 PROCESS RADIATION MONITORS CLOCK TIME 12:30* 12:45* 13:00*

SCENARIO TIME 10:00* 10:15* 10:30*

RADIATION MONITOR UNITS LIQUID WASTE DISPOSAL CPM 200 200 200 RI-3801 LETDOWN (IDW RANGS) CPM NIS NIS NIS RI-3101 LETDOWN (HIGH RANGE) CPM 100 100 100 RI-3102 WASTE GAS VENT CPM 250 250 250 RI-3901 BORON WASTE CPM 50000 50000 50000 RI-3701 CONTAINMENT PARTICULATE CPM OSH OSH OSH RI-6102X CONTAINMENT GAS CPM OSH OSH OSH RI-6102Y

  • NOTE: A SCENARIO TIME JUMP OF 6 HOURS HAS OCCURRED.

PLANT COOLDOWN IS IN EFFECT, BACKFEED FROM THE 345 kV SWITCHYARD IS COMPLETE.

l 1

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L MAINE YANKEE EMERGENCY 1REPAREDNESS EXERCISE 1988 4

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1

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MAINE YANKEE DIERGENCY PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT SYSTEM ACTIVITY O

O 1973e/26.343

Rev. 1

,- 8/8/88

( ) Page 9.4.1-1

%,)

MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT SYSTEM ACTIVITY (pCi/ml)

Time Isotope 0830 - 0845 0845 - 0900 0900 - 0915 Kr-83m 1.6E-3 1.5E-3 2.9E-3 Kr-85 2.1E-3 2.0E-3 3.8E-3 Kr-85m 1.5E-2 1.4E-2 2.7E-2 Kr-87 2.7E-2 2.6E-2 4.9E-2 Kr-88 2.5E-2 2.4E-2 4.5E-2 Xe-131m 7.7E-3 7.3E-3 1.4E-2 Xe-133 1.5E-1 1.4E-1 2.7E-1 Xe-133m 6.2E-3 5.9E-3 1.1E-2 Xe-135 1.6E-1 1.5E-1 2.9E-1 Xe-135m 1.2E-3 1.1E-3 2.2E-3 O Total Noble Gas: 4.0E-1 3.8E-1 7.2E-1 I-131 4.6E-3 4.4E-3 9.6E-3 I-132 4.0E-2 3.8E-2 8.4E-2 1-133 6.3E-2 6.0E-2 1.3E-1 I-134 8.6E-3 8.2E-3 1.8E-2 I-135 9.5E-2 9.0E-2 2.0E-1 Total Iodine: 2.1E-1 2.0E-1 4.4E-1 I-131 Dose Equivalent: 6.5E-2 6.2E-2 1.4E-1 l NOTE: Reactor coolant sample dose rates are provided in Section 9.5.2.

\- 1973e/26.343

Rev. 1 8/8/88

/ '~ ~N

)

Page 9.4.1-2

%_)

MAINE YANKEE ,

EMERGENCY PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT SYSTEM ACTIVITY (pCi/ml) (Continued)

Time Isotope 0915 - 0930 0930 - 0945 0945 - 1000 Kr-83m 1.6E-3 3.9E-4 5.2E-4 Kr-85 2.1E-3 5.1E-4 6.8E-4 Kr-85m 1.5E-2 3.7E-3 4.9E-3 Kr-87 2.7E-2 6.6E-3 8.8E-3 Kr-88 2.5E-2 6.1E-3 8.1E-3 Xe-131m 7.7E-3 1.9E-3 2.5E-3 Xe-133 1.5E-1 3.7E-2 4.9E-2 Xe-133m 6.2E-3 1.5E-3 2.0E-3 Xe-135 1.6E-1 3.9E-2 5.2E-2 Xe-135m 1.2E-3 2.9E-4 3.9E-4 m

k,) Total Noble Gas: 4.0E-1 9.8E-2 1.3E-1 I-131 7.4E-3 9.2E-3 8.8E-3 1-132 6.5E-2 8.0E-2 7.6E-2 I-133 1.0E-1 1.3E-1 1.2E-1 I-134 1.4E-2 1.7E-2 1.6E-2 I-135 1.5E-1 1.9E-1 1.8E-1 Total Iodine 3.4E-1 4.2E-1 4.0E-1 I-131 Dose Equivalent: 1.1E-1 1.3E-1 1.2E-1 NOTEt Reactor coolant sample dose rates are provided in Section 9.5.2.

\s 1973c/26.343

Rev. 1 8/8/88 Page 9.4.1-3

('

Q_.')'\

, MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT SYSTEM ACTIVITY ( C1/ml) (Continued)

Time Isotope 1000 - 1015 1015 - 1030 1030 - 1045 l Kr-83m 1.*E-2 1.2E-2 9.2E-3 Kr-83 1.4E-2 1.6E-2 1.2E-2 Kr-85m 1 OE-1 1.2E-1 8.6E-2 Kr-87 1.8E-1 2.1E-1 1.6E-1 Kr-88 1.7E-1 1.9E-1 1.4E-1 Xe-131m 5.2E-2 6.0E-2 4.4E-2 Xe-133 1.0E-0 1.2E-0 8.6E-1 Xe-133m 4.2E-2 4.8E-2 3.6E-2 Xe-135 1.1E-0 1.2E-0 9.2E-1 Xe-135m 8.1E-3 9.3E-3 6.9E-3 O)

I q_, Total Noble Gas 2.7E-0 3.1E-0 2.3E-0 1-131 1.8E-2 2.1E-2 1.6E-2 I-132 1.6E-1 1.8E-1 1.4E-1 I-133 2.5E-1 2.9E-1 2.2E-1 I-134 3.4E-2 3.9E-2 2.9E-2 I-135 3.8E-1, 4.3E-1 3.3E-1 Total Iodine: 8.3E-1 9.5E-1 '.2E-1 1-131 Dose Equivalent: 2.6E-1 3.0E-1 2.2E-1 NOTE: Reactor coolant sample dose rates are provided in Section 9.5.2.

A 1973e/26.343 I

Rev. 1 8/3/88 .

I,_si Page 9.4.1-4 V

MAINE YANKIF.

ESEhGENCY PREPAREDNESS EXERCISE 1988 9.4.1 RESCTOR COOLANT SYSTEM ACTIVITY (pCi/ml) (Continued)

Time Isotope 1045 - 1100 1100 - 1115 1115 - 1130 Kr-83m 5.6E-3 3.1E-3 2.2E-3 Kr-85 7.4E-3 4.1E-3 2.9E-3 Kr-85m 5.3E-2 2.9E-2 2.1E-2 Kr-87 9.5E-2 5.3E-2 3.7E-2 Kr-88 S.8E-1 4.9E ,1 3.4E-2 Xe-131m 2.7E-2 1.5E.2 1.1E-2 Xe-133 5.3E-1 2.9E-1 2.1E-1 Xe-133m 2.2E-2 1.2E-2 8.5E-3 Xe-135 5.6E-1 3.1E-1 2.2E-1 Xe-135m 4.2E-3 2.3E-3 1.7E-3 (q

s_,) Total Noble Cas 1.4E-0 7.8E-1 5.5E-1 '

I-131 1.4E-2 1.1E-2 9.0E-3 1-132 1.2E-1 9.5E-2 7.8E-2 1-133 2.0E-1 1.5E-1 1.2E-1 I-13a 2.7E-2 2.0E-2 1.7E-2 I-135 2.9E-1 2.3E-1 1.9E-1 Total Iodine 6.5E-1 5.0E-1 4.1E-1 I-131 Dose Equivalens: 2.0E-1 1.6E-1 1.3E-1 NOTE: Reactor coolant sample dose rates are provided in Section 9.5.2.

1973e/26.343 1

Rev. 1 8/8/88 Page 9.4.1-5

' \~,J

(~ N)

MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT SYSTEM ACTIVITY (pCi/ml) (Continued)

Time Isotopa 1130 - 1145 1145 - 1200 1200 - 1215 Kr-8?m 3.1E-3 3.3E-3 1.6E-3 Kr-85 4.1E-3 4.4E-3 2.1E-3 Kr-85m 2.9E-2 3.1E-2 1.5E-2 Kr-87 5.3E-2 5.6E-2 2.7E-2 Kr-88 4.9E-2 5.2E-2 2.5E-2 Xe-131m 1.5E-2 1.6E-2 7.7E-3 Xe-133 2.9E-1 3.1E-1 1.5E-1 Xe-133m 1.2E-2 1.3E-2 6.2E-3 Xe-135 3.1E-1 3.3E-1 1.6E-1 Xe-135m 2.3E-3 2 5E-3 1.2E-3

Total Noble Cast 7.8E-1 8.3E-1 4.0E-1 1-131 5.5E-3 5.9E-3 6.1E-3 I-132 4.8E-2 5.1E-2 5.3E-2 I-133 7.5E-2 8.1E-2 8.4E-2 I-134 1.0E-2 1.1E-2 1.1E-2 7-135 1.iE-1 1.2E-1 1.3E-1 f

total Iodine: 2.5E-1 2.7E-1 2.8E-1 t I-13t Dose Equivalent: 7.8E-1 8.4E-2 8.7E-2 NOTE: Reactor coolant sample dose rates are provided in Section 9.5.2. t l

i i 1

1973e/26.343 I

Rev. 1 8/8/60 Fage 9.4.1-6

[]

' _J I

MAINE YANKEE 4 EMERGENCY PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT SYSTEM ACTIVITY (pCi/ml] (Cont 1nued) 1 Time ,

Isotope 1215 - 1230 Kr-83m 1.7E-3

-85 2.2E-3 L -3'm 1.6E-2 Kr / 2.8E-2 J8 2.6E-2 Xe-131m 8.1E-3 Xe-133 1.6E-1 Xe-133m 6.5E-3 Xe-135 1.7E-1 Xe-135m 1.3E-3 C\

(s_,) Total Noble Cast 4.2E-1 I-131 4.4E-3 I-132 3.8E-2 I-133 6.0E-2 I-134 8.2E-3 I-135 9.0E-2 Total Iodine 2.0E-1 1-131 Dose Equivalent: 6.2E-2 NOTE: Reactor coolant sample dose rates are provided in Section ?#.5.2.

's_ - 1973e/26.343

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Time Isotope 0830 - 0945 0945 - 1000 1000 - 1015 Kr-83m 1.3E-7 5.3E-7 2.5E-4 Kr-85 1.4E-8 5.7E-8 2.7E-5 Kr-85m 2.3E-7 9.7E-7 4.6E-4 Kr-87 1.4E-7 5.7E-7 2.7E-4 Kr-88 4.6E-7 1.9E-6 9.1E-4 Xe-131m 1.4E-8 5.9E-8 2.8T, 5 Xe-133 2.7E-6 1.1E-5 5.3E-3 Xe-133m 8.2E-8 3. 4 r.-7 1.6E-4 Xe-135 9.7E-7 4.0E-6 1.9E-3 Xe-135m 2.9E-7 1.2E-6 527E-4 Total Noble Gas: 5.0E-6 L.0E-5 9.9E-3 I-131 2.2E-10 8.7E-10 4.3E-7 I-132 1.9E-9 7.7E-9 3.9E-6 I-133 3.0E-9 1.2E-8 6.0E-6 I-134 4.1E-10 1.6E-9 8.2E-7 I-135 4.6E-9 1.8E-S 9,2E-6 Total Iodine: 1.0E-8 4.0E-8 2.0E-5 1-131 Dose Equivalent: 3.1E-9 1.3E-8 6.3E-6 NOTES: 1. The highest containment air concentrations correspond to a release of approximately 0.02% of the noble gas inventory.

2. Containment sample dose rates are provided in Section 9.5.

1970e/12.553

Rev. 1

,_. 8/C/88 Page 9.4.2-2

[J]

w MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 9.4.2 CONTAINMENT AIR ACTIVITY CONCENTRATIONS (uCi/ce) (Continued)

Time Isotope 1015 - 1030 1030 - 1045 1045 - 1100 Kr-83m 1.5E-3 2.2E-3 3.0E-3 Kr-85 1.6E-4 2.4E-4 3.2E-4 Kr-85m 2.7E-3 4.1E-3 5.5E-3 Kr-87 1.6E-3 2.4E-3 3.2E-3 Kr-88 5.4E-3 8.1E-3 1.1E-2 Xe-131m 1.7E-4 2.5E-4 3.3E-4 Xe-133 3.1E-2 4.7E-2 6.3E-2 Xe-13 2.n 9.6E-4 1.4E-3 1.9E-3 Xe-135 1.1E-2 1.7E-2 2.3E-2 3.4E-3 5.1E-3 6.8E-3

(s Xe-135m

\J Total Noble Gast 5.8E-2 8.8E-2 1.2E-1 I-131 2.6E-6 3.9E-6 5.2E-6 I-132 2.3E-5 3.5E-5 4.6E-5 I-133 3.6E-5 5.4E-5 7.2E-5 I-134 4.9E-6 7.4E-6 9.8E-6  ;

I-135 5.5E-5, 8.2E-5 1.1E-4 Total Iodine: 1.2E-4 1.8E-4 2.4E-4 i I-131 Dose Equivalent: 3.8E-5 5.o4-3 7.5E-5 NOTESt 1. The highest containment air concentrations correspond to a release of approximately 0.02% of the noble gas inventory.

2. Containment sample dose rates are provided in Section 9.5.

k- 1970e/12.553 e.. _

Rev. 1 8/8/88

(x Page 9.4.2-3 NI MAINE YANXEE EMERGENCY PREPAREDNESS EXEh0ISE 1988 9.4.2 CONTAINMENT AIR !.CTIVITY CONCENTRATIONS (uCi/ce) (Continued)

Time Isotope 1100 - 1115 1115 - 1130 1130 - 1145 Kr-83m 7.2E-3 1.6E-2 2.5E-2 Kr-85 7.8E-4 1.8E-3 2.7E-3 Kr-85m 1.3E-2 3.0E-2 4.6E-2 Kr-87 7.8E-3 1.5E-2 2.7E-2 Kr-88 2.6E-2 5.9E-2 9.1E-2 Xe-131m 8.0E-4 1.8E-3 2.8E ,1 Xe-133 1.5E-1 3.4E-1 5.3E-1 Xe-133m 4.6E-3 1.0E-2 1.6E-2 Xe-135 5.5E-2 1.2E-1 1.9E-1

~ Xe-135m 1.6E-2 3.7E-2 5.7E-2 7

Total Noble Gas: 2.8E-1 6.4E-1 9.9E-1 I-131 1.2E-5 2.8E-5 5.3E-5 I-132 1.1E-4 2.5E-4 3.9E-4 I-133 1.7E-4 3.9E-4 6.0E-4 I-134 2.3E-5 5.3E-5 8.2E-5 I-135 2.6E-4 6.0E-4 9.2E-3 Total Iodine: 5.6E-4 1.3E-3 2.0E-3 I-131 Dose Equivalent: 1.8E-4 4.1E-4 6.3E-4 NOTES: 1. The highest containment air concentrations correspond to a release of approximately 0.02% of the noble gas inventory.

2. Containment sacple dose rates are provided in Section 9.5.

1970e/12.553

l Rev. 1 i 8/8/88

[N Page 9.4.2-4

\ms MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1988 9.4.2 CONTAINMENT AIR ACTIVITY CONCENTRATIONS (uC1/ce) (Continued)

Time Isotope 1145 - 1200 1200 - 1215 1215 - 1230 Kr-83m 3.5E-2 4.0E-2 3.8E-2 Kr-85 3.7E-3 4.3E-3 4.1E-3 Kr-85m 6.4E-2 7.3E-2 6.9E-2 Kr-87' 3.7E-2 4.3E-2 4.1E-2 Kr-88 1.3E-1 1.4E-1 1.4E-1 Xe-131m 3.9E-3 4.4E-3 4.2E-3 Xe-133 7.3E-1 8.4E-1 8.0E-1 Xe-133m 2.2E-2 2.5E-2 2.4E-2 Xe-135 2.6E-1 3.0E-1 2.9E-1 Xe-135m 7.9E-2 9.0E-2 8.6E-2

(~S)

Total Noble Cas: 1.4E0 1.6E0 1.5E0 I-131 6.1E-5 6.9E-5 6.5E-5 I-132 5.4E-4 6.2E-4 5.8E-4 I-133 8.4E-4 9.6E-4 9.0E-4 I-134 1.1E-4 1.3E-4 1.2E-4 I-135 1.3E-3 1.5E-3 1.4E-3 Total Iodine: 2.8E-3 3 7E-3 3.0E-3 4

1-131 Dose Equivalentt 8.8E-4 1.0E-3 9.4E-4 NOTES: 1. The highest containment air concentrations correspond to a release  ;

of approximately 0.02% of the noble gas inventory.

2. Containment sample dose rates are provided in Section 9.5.

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Rev. 1 8/8/88 w Page 9.5.1-1 MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE 1983 9.5.1 C E TAINMENT AIR SAMPLE DOSE RATES l'a shielded Shielded (mR/hr per cc)* (1 in lead in mR/hr per cc)*

Time Contact 1 Ft. Contact 1 Ft.

0830-0945 1.4E-6 1.0E-8 1.8E-8 1.3L-10 0945-1000 5.8E-6 4.0E-8 7.2E-8 5.0E-10 1000-1015 2.9E-3 2.0E-5 3.6E-5 2.5E-7 1015-1030 1.7E-2 1.2E-4 2.1E-4 1.5E-6 1030-1045 2.5E-2 1.SE-4 3.2E-4 2.2E-6 1045-1100 3.5E-2 2.4E-4 4.3E-4 3.0E-6 1100-1115 8.1E-2 5.6E-4 1.0E-3 7.0E-6

() 1115-1130 1130-1145 1.8E-1 2.9E-1 1.3E-3 2.0E-3 2.3E-3 3.6E-3 1.6E-5 2.5E-5 1145 1200 4.0E-1 2.8E-3 5.0E-3 3.5E-5 1200-1215 4.6E-1 3.2E-3 5.SE-3 4.0F-5 1215-1230 4.3E-1 3.UE-3 5.4E-3 3.SE-5

  • t.'alues must be multiplied by the sample volute in cubic centimeters to obtain the sample dose rate in mR/hr.

1971e/4.412

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Rev. 1 l 8/8/88 l Page 9.5.2-1 9 1

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EMERGENCY PREPAREDNESS EXERCISE

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4 O 1974e/26.344

Rev. 1 8/8/88 I' ') Page 9.5.2-2 r

' 'Am)

MAINE YANKEE EMERGENCY PREPAREDNESS EXERCISE ,

1988 9.5.1 REACTOR COOLANT SYSTEM SAMPLE DOSE RATES A. Cas Samples

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(mR/hr per cc)* (1" Lead in mR/hr per ec)*

Time Contact. One Foot Contact One Foot 0830 - 1000 - AS READ - - AS READ -

1000 - 1015 7.8E-1 5.4E-3 9.7E-3 6.8E-5 i 101; - 1030 8.9E-1 6.2E-3 1.1E-2 7.8E-5 1030 1045 6.6E-1 4.6E-3 8.3E-3 5.8E-5 1045 - 1100 4.0E-1 2.8E-3 5.0E-3  ;.5E-5 1100 - 1115 2.2E-1 1.6E-3 2.8E-3 2.0E-5 l 1115 - 1230 - AS READ - - AS READ -

B. Liquid Samples (todine)*

l 0830 - 1000 - AS READ - - AS READ -  !

1000 - 1015 6.0E-1 4.2E-3 7.5E-3 5.2E-5 i

, 1015 - 1030 6.SE-1 4.8E-3 8.6E-3 5.9E-5  ;

1030 - 1045 5.2E-1 3.6E-3 6.5E-3 4.5E-5 [

1045 - 1100 4.7E-1 3.3E-3 5.9E-3 4.1E-5 1100 - 1115 3.6E-1 2.5E-3 4.5E-3 3.1E-5 {

1115 - 1230 - AS READ - - AS READ -  ;

  • NOTES (1) Gas samples indicate noble gases only and liquid samples indicate only iodine.

(2) Values must be multiplied by the sample volume in cubic i centimeters to obtain the sample dose rates in mR/hr. '

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9.6 0FT-SITE MONITORING TEAM OBSERVER INSTRUCTIONS / DATA i

l NOTE: Off-Site Monitoring Team measurements should be "as read" in

all cases. Plume projections are provided for comparative i

< purposes.

i i

i 9 1962e/4.409

Rev. 2 8/12/88 O Page 9.6-1 NI NOTE: THE PLUME PLOT FIGURES ARE GRAPHIC REPRESENTATION OF ATMOSPHERIC DISPERSION. THE THREE-DIMENSIONAL PLUMES VARY IN TIME AhT SPACE. A SIMI!AR VERSION OF THE FIGURES OVERLAYED ON A LARGER FIELD SURVEY MAP WILL BE USED TO ASSIST CONTROLLERS IN INTERPRETING DATA.

RADIATION MEASUREMENT VALUES PRESENTED IN THE MAP KEY ARE BASED ON CONTAINMENI DESIGN LEAKAGE CALCULATIONS A'iD MAY BE BELOW THE INSTRUMENTATION SENSITIVITY USED BY THE FIELD TEAMS. TRAINING WILL BE PROVIDED ON INSTRUMENT RANCES, ACCURACIES (MDA), AhT ROL?iTING OF VALUES.

O ,

1962e/4.409

l Rev. 2 8/12/88 Page 9.6-2 MAINE YANKEE ATOMIC POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 9

9.6 MONITORING TEAM OBSERVER INSTRUCTIONS / DATA Off-site plume centerline whole body dose rates have been estimated as a function of time and distance from the site using a variable trajectory dose assessment model. Geographical representations of the plume are l provided in this package for each 15 minute average of meteorological conditions, starting at 11:30. During the exercise, off-site monitoring team observers will use the information contained in this package to provide field monitoring teams with radiological data for various times and locations.

During the exercise, the Survey Team Coordinator (s) will direct off-site l

monitoring teams to monitor locations relative to the meteorological conditions postulated for the exercise scenario. Use Figures 9.6-1 through 9.6-5 to provide survey results to the off-site monitoring teams.

i Figures 9.6-1 through 9.6-5 depict the plume conditions at various times l throughout the exercise. These figures represent a plume width which is equivalent to a 3-sigma value of the centerline conditions. Since the figures show a plume width relative to the centerline, gama dose rates can be estimated using the color coded maps and off-centerline value provided. Radiological data for other locations within the plume can be calculated as a function of the centerline and outer edge values at a given segment / distance. Radiological data has been provided for each l particular segment at centerline. Dose and count rates for locations

! b6 ween two segments can be estimated as a function of the values at those segments.

1962e/4.409

Rev. 2 8/12/88 j Page 9.6-3 l

ci MAINE YANKEE ATOMIC POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 9.6 0FF-SITE MONITORING TEAM OP. SERVER INSTRUCTIONS / DATA Prior to the exercise, training will be provided to the off-site monitoring team controller / observers on the use of this package. The following are specific actions which off-site monitoring team controller //bservers should take during the exerciset

1. As off-site monitoring teams are designated, check that Procedure Number 2.50.12 is followed by team members. This will include the initial equipment check.
2. While enroute to the assigned monitorics location, or while traversing the plume, use the attached figures and tables to issue appropriate radiological data.
3. Attempt to estimate the team's accrued exposure as a function of their continual job assignment. Do not issue pocket dosimeter results to team members, unless they actually simula m checking their dosimeter reading. The pocket dosimeters issued at the EOF have a range of 0-500 mR which are subdivided into 20 mR intervals.

Attempt to provide realistic values! 0-5 R dosimeters may be provided. Always check to ask them the range.

4. Ask the off-site monitoring teams what equipment they have available for their use. Ask them the scales associated with the equipment; log these answers to ensure that you do not provide them with data that exceeds the range of their equipment. If, at any point during the exercise, a situation occurs where the upper range of their equipment is exceeded, eben issue them an "off-scale high" value.

1962e/4.409

Rev. 2

,, 8/12/88 Page 9.6-4 (v}

5. If the off-site monitoring team stops to take an air sample:
a. Report the appropriate whole body dose icvels at that location.
b. If an E-520/HP-210 is left on to track the plume while driving the meter count rate can be estimated using the following relationships:

(1) 5,000 epm on the E-520/HP-210 is equivalent to approximately 1.0 mR/hr.

(2) 24,000 epm is the upper range of the E-520/HP-210. Upon reaching 24.000 epm, the HP-210 probe should be interchanged with the HP-270 probe, to read out in mR/hr.

(3) 200 mR/hr is the upper range of the E-520/HP-270.

6. Whenever a team takes a "ground level" survey, the results should be the s ee as the waist-high survey.
7. Certain field monitoring teams may take open window aM closed window readings with their dose rate survey meters. If a team is located in the plume (see maps), assume the open window reading is three times the gamma (closed window) line dose rate reading given on the map.
8. The E-140 may be substituted for an E-520 when performing contamination surveys or locating the plume (using an HP-210 or HP-177 probe) or when performing low level dose rate surveys (using an HP-270 probe).

. NOTE : THE PLUME PLOT FIGURES ARE GRAPHIC REPRESENTATIONS OF AIMOSPHERIC DISPERSION. THE THREE-DIMENSIONAL PLUMES VARY IN TIME AND SPACE. A SIMILAR VERSION OF THE FIGURES OVERLAYED ON A LARGER FIELD SURVEY MAP WILL BE USED TO ASSIST C057 ROLLERS IN IhTERPRETING DATA.

196:e/4.409

> l Rev. 2 8/12/88 Page 9.6-5 G

RADIATION MEASUREMENT VALUES PRESENTED IN THE MAP KEY ARE BASED ON CONTAIhMENT DESIGN LEAKAGE CALCULATIONS AND MAi BE BELOW THE  ;

INSTRUMENT SENSITIVITY USED FY THE FIELD TEAMS. TRAINING WILL BE i PROVIDED ON INSTRUMENT RANGES ACCURACIES (MDA), AND Rot,WDING OF ,

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10.1 ON-SITE METEOR 01.0CICA1. DATA i

NOTE: Actual hourly meteorolog).al data used from Set.tember 30 1916.

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m /m U U Rev. 2 9/15/88 Page 10.1-1 10.1 On-site Meteorological Data SPDS Meteorological Data 1 2 3 4 5 6 7 8 9 10 11 12 13 ITime) 0700 0715 0730 0745 0800 0815 0R30 0845 0900 0915 0930 0945 1000 Upper Wind Direction (0) 197 192 198 193 193 196 193 197 202 207 211 210 215 Upper Wind Speed (sph) 7.H C.2 S.6 8.9 10.3 10.8 10.3 11.7 13.3 13.6 13.8 14.1 15.1

  • r Wind Direction (0) 158 156 152 159 173 179 173 200 203 209 221 225 225 c.wcr Wind Speed (mph) 3.1 3.3 3.5 3.7 4.4 5.2 4.4 6.7 9.5 8.7 7.9 7.1 4.2 Air Temperature (33ft/0F) 59.8 60.0 60.2 60.3 61.0 61.4 61.0 62.1 63.5 63.6 63.7 63.8 64.1 Air Temperature (196 33ft/0F) 0.4 0.4 0.4 0.4 C.3 0.3 0.3 0.3 -0.1 -0.; -0.1 -0.1 -0.4 Precipitation (inches) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1

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SPDS Meteorological Pata (Continued) 1 2 3 4 5 6 7 o 9 ID 11 12 13 (Time} 1015 1030 1045 1100 1115 1130 1145 1200 1215* 1230* 1245* 1300* 1315*

Upper Wind Direction (0) 214 218 215 212 211 214 216 217 219 207 211 208 215 Upper *.'ind breed (mph) 14.3 13.5 12.7 9.7 9.7 9.7 9.7 9.7 10.0 10.2 10.5 11.5 11.7 Lower Wind Direction (0) 22C 227 23. 231 219 230 212 115 211 210 196 199 l'19 Lower Wind Speed (mph) 4.2 4.2 4.2 4.2 4.3 4.3 4.4 4.6 4.9 5.3 5.6 6.9 6.6 Air Temperature (33f t/0F) 64.1 64.2 ^G.2 64.4 64.7 65.0 65.3 66.5 66.8 67.2 67.5 68.8 69.4 Air Temperature (196-33ft/ F) -0.4 -0.4 -0.4 -0.9 -0.9 -0.9 -0.9 -1.4 -1.4 -1.4 -1.4 -1.1 -1.1 l Precipitation (inches) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0

  • NOTE: A SCENARIO TIME .'dMP OF 6 HOURS HAS OCCURRED.

1946e/18.377

O MAINE YAFKEE EMERGENCY RESPONSE EXERCISE 1988 l '0.2

. CENERAL AREA NATIONAL WEATHER SERVICE FORECASTS i

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f' Page 10.2-1 q 10.2 General Area National Werther Service Forecasts THIS IS A DRILL L 4

6:00 - 10:00 General Area Forecast ,

Rain ending this morning, with fog in low lying areas clearing by midday.

Winds southwesterly 3-5 mph, temperatures reaching mid 70's by ,

afternoon. Winds will shift to westerly as a cool front makes its way through the forecast area this evening.

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Rev. 1 7/LO/88

['v-) Page 10.2-2 10.2 General Area National Weather Service Forecasts THIS IS A DRILL l

D 10:00 - 14:00 General Area Forecast Cloudy with winds south-southwesterly at 3-5 mph, shifting to westerly by early evening, as a cool front passes through the forecast area.

Chance of an occasional shower tonight, low near 50 F. High tomorrow 62 F.

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