ML20215E364
ML20215E364 | |
Person / Time | |
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Site: | Maine Yankee |
Issue date: | 06/30/1987 |
From: | Maine Yankee |
To: | |
References | |
PROC-870630, NUDOCS 8706190346 | |
Download: ML20215E364 (253) | |
Text
{{#Wiki_filter:_ SCHEDULE DAY OF EXERCISE 2:30 P.M. CONTROLLERS /0BSERVERS BRIEFING DAY AFTER EXERCISE 7:30 A.M. CONTROLLERS /0BSERVERS (PRELIMINARY FINDINGS) 8:00 A.M. PLAYERS DEBRIEF 10:00 A.M. MANAGEMENT MEETING 11:00 A.M. NRC MEETING ND0'*$00$k Os08SSo9 P PDR l 7 i8815L-GDW i
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THE 1987 MAINE YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE EXERCISE AND EVA'LUATION PLAN JUNE 1987 l O 1475e i
h Rev. 0 3/11/87L O' V 1987 MAINE YANKEE EMERGENCY RESPONSE EXERCISE AND EVALUATION PLAN TABLE OF CONTENTS Page
1.0 INTRODUCTION
...................................................... 1.0-1 1.1 Exercise Schedule........................................... 1.1-1 1.2 : Participating Centers / Agencies.............................. -1.2-1 1.3 Definitions................................................. 1.3-1 1.4 References.................................................. 1.4-1 2.0 EXERCISE OBJECTIVES............................................... 2. 0-1 ' 2.1 Maine Yankee Nuclear Power Station Exercise Objectives...... 2.1-1 2.2 State of Maine Exercise Objectives / Extent of Play........... 2.2-1 3.0 EXERCISE GUIDELINES AND SC0PE..................................... .3.0-1 3.1 Guidelines.................................................. 3.1-1 3.2 Extent of P1ay.............................................. 3.2-1
.r-(- Simulation List............................................. 3.3-1
(_ j 3.3 3.4 Player Instructions......................................... 3.4-1 3.5 Procedure Execution List.................................... 3.5-1 3.6 ' Exercise Termination Criteria............................... 3.6-1 4.0 CONTROLLER /0BSERVER INFORMATION................................... 4.0-1 4.1 Assignments................................................. 4.1-1 4.2 Exercise Guidance / Evaluation Sheets......................... 4.2-1 5.0 EXERCISE SCENARIO................................................. 5.0-1 5.1 Initial Conditions.......................................... 5.1-1 5.2 Scenario 0utline............................................ 5.2-1 5.3- Narrative Summary........................................... 5.3-1 5.4 Radiological Development.................................... 5.4-1 5.5- Scenario Time Line.......................................... 5.5-1 5.6 Detailed Sequence of Events................................. 5.6-1 6.0 SCENARIO DATA / EVENTS (MESSAGE CARDS / COMMAND CARDS)................ 6.0-1 6.1 Event Messages.............................................. 6.1-1 l t
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. . .Rev. 0- \# 3/11/87 TABLE OF CONTENTS (Continued)
Page 7.0 STATION EVENT DATA................................................- 7.0-1 7.1 Events Summary.............................................. 7.1-1 i 7.2 Event Miniscenarios........................................ 7.2-1 8.0 0PERATIONAL DATA.................................................. 8.0-1 i 1 9.0 RADIOLOGICAL DATA................................................. 9.0-1 I 9.1 Area Radiation Monitors..................................... 9 .1-l ' 9.2 Process Radiation Monitors.................................. 9.2 4 9.3 Primary Coolant Activity Concentrations..................... 9.3-1 , 9.4 Containment Air Activity Concentrations..................... 9.4-1 9.5 Primary Coolant Sample Dose Rates........................... 9.5 9.6 Containment Air Sample Dose Rates........................... 9.6-1 9.7 Off-Site Monitoring Team Observer Instructions / Data......... 9.7-1 9.8 On-Si te Moni to ring Da ta . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.8-1 9.9 In-Plant Survey Maps........................................ 9.9-1 10.0 METEOROLOGICAL DATA............................................... .10.0-1 i l 0
l O i MAIllE YANKEE l GRADED EXERCISE JUNE 1987 O
1.0 INTRODUCTION
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4 MAINE. YANKEE GRADED EXERCISE ! 1 JUNE 1987 O 1.1 EXERCISE SCHEDULE l l I l ) ( I 1.
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( . Page 1.1-1 MAINE YANKEE GRADED EXERCISE JUNE 1987 1.1 EXERCISE SCHEDULE Date: Tuesday, June 9, 1987 Time: 1300 Location: Maine Yankee Information Center
Purpose:
Controller / Observer Briefing-f- s Attendees: Maine Yankee and Yankee ~ Atomic Controllers / Observers, NRC I ,,,) Evaluators Date: Tuesday, June 9, 1987 Time: 1500 Location: Emergency Response Centers and In-Station Areas
Purpose:
Familiarize Controllers /0bservers with Affected Areas Attendees: Controllers / Observers, NRC Evaluators O v 1476e
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i 3/11/87 Page 1.1-2 Date: Wednesday, June 10, 1987 Time: 1700 to approximately 2230 Location: Maine Yankee Emergency Response Centers
Purpose:
Graded Exercise Attendees: Maine Yankee Emergency Response Organization, Controllers /0bservers, NRC Evaluators, State Division of Health Engineering, State Bureau of Civil Emergency Preparedness, and Yankee Atomic Engineering Support Center j l
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Date: Wednesday, June 10, 1987 ) i Time: 2245 Location: Maine Yankee Emergency Response Centers 1 f
Purpose:
Emergency Response Center Exercise Debriefings l l l Attendees: Controllers /0bservers/ Players (NRC Evaluators welcome) . I ! O 1476e
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's Date: Thursday, June 11, 1987 Time: 0800 Location: Maine Yankee Information Center j
Purpose:
Exercise Debriefing
-Attendees: Controllers /0bservers, Key Participants Date: Thursday, June 11, 1987 l )
Time: 1000 Location: Maine Yankee Information Center , O'
Purpose:
Utility Self-Critique /NRC Preliminary Findings
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l Attendees: Maine Yankee Management, NRC Evaluators, and Exercise Controllers (Observers need not attend) l 1 (% 1476e N_s t
i l O 1 i I MAINE YANKEE l GRADED EXERCISE JUNE 1987 l 0 1.2 PARTICIPATING CENTERS / AGENCIES i O 1477e
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- p. s Page 1.2-1 MAINE YANKEE GRADED EXERCISE JUNE 1987 1.2 PARTICIPATING CENTERS / AGENCIES MAINE YANKEE ATOMIC POWER COMPANY IMaine Yankee Nuclear Power Station Emergency Operations Facility Technical Support Center Operations Support Center Simulator'(Control Room functions) i Control Room (notification functions only) '
STATE OF MAINE' Division of Health Engineering Bureau of Civil Emergency Preparedness Maine State Police YANKEE ATOMIC ELECTRIC COMPANY Engineering Support Center NUCLEAR REGULATORY COMMISSION NRC Site ~ Responders to TSC and EOF LOCAL COMMUNI~I_ES Wiscasset Georgetown Dresden Edgecomb Westport Bowdoinham Newcastle Woolwich Alna South Bristol Bath Bristol Boothbay- Arrowsic Damariscotta Boothbay Harbor West Bath Phippsburg Southport Brunswick r^ (' -1477e 1 l
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MAINE YANKEE !
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GRADED EXERCISE i 1 JUNE 1987 l 1 0 1.3 DEFINITIONS f l i
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. JUNE 1987 1.3 DEFINITIONS
- A. Abbreviations
- 1. APD - Air Particulate Detector
- 2. A0 - Auxiliary Operator
- 3. CIS - Containment Isolation' Signal
- 4. CMP - Central Maine Power Company
- 5. CR -
Control Room -
- 6. CR0 - Control Room Operator
- 7. EAL - Emergency Action Level
- 8. EC - Emergency Coordinator
- 9. E00 - Emergency Operations Center j
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- 10. EOF - Emergency Operations Facility j
- 11. ENS - Emergency Notification System a 12.- ESC -
Engineering Support Center i 13. FEMA - Federal Emergency Management Agency 1478e
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- 14. HPSI - High Pressure Safety Injection
- 15. KI - Potassium Iodide
- 16. LPSI - Low Pressure Safety Injection
- 17. NG -
Noble Gas
- 18. MBCEP - Maine Bureau of Civil Emergency Preparedness
- 19. MSL - Main Steam Line
- 20. MSP - Maine State Police
, 21. MY - Maine Yankee
- 22. MYNSD - Maine Yankee Nuclear Support Division I
- 23. OSC - Operations Support Center
- 24. OSDE - On-Site Data Evaluator
- 25. PAB - Primary Auxilliary Building I
- 26. PAG - Protective Action Guide l l
- 27. POD - Pocket Dosimeter l 1
- 28. PORV - Power Operated Relief Valve
- 29. PSS - Plant Shift Superintendent
- 30. PZR - Pressurizer 1478e
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- 31. PVS -
Primary Vent Stack
- 32. Q -
Release Rate
- 33. RCP - Reactor Coolant Punip
- 34. RCS- - Reactor Coolant System
- 35. REA - Radiological. Evaluation Assistant l
- 36. - RDE - Radiological Data Evaluator l
-37. RHRS - Residual-Heat Removal System- , , 38. RSC - Radiological Sample Coordinator
- 39. RWST Refueling Water Storage Tank u
.40. NSE - Nuclear Safety Engineer 1
- 41. SIAS . Safety Injection Actuation Signal 1
- 42. SG -
Steam Generator
- 43. SV - Safety Valve
- 44. TSC -
Technical Support Center
- 45. u -
Average Wind Speed
. 46. VCT -
Volume Control Tank
- 44. YNSD - Yankee Nuclear Services Division 1478e ;
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-Rev. 0 3/11/87-Page.1.3-4 B. Terminology
- 1. Alert- - An emergency classification which is-i.. defined as an actual or potential- .
substantial, degradation of the level of safety of the plant. 1
- 2. Central Maine -. Principle owner of Maine Yankee.
Power Company Nuclear Power Station.
'(CMP)
- 3. Controller: - A member o'f an exercise control group. Each Controller may be .
assigned to one or more activities or p functions for the purpose of keeping -l the action going according to a ! scenario, resolving differences (acting as an umpire), supervising and otherwise assisting as needed.
- 4. Critique - A meeting of key participants in an exercise usually held shortly after its conclusion, at which exercise officials constructively criticize the operation and the performanca of individuals or groups. It may or may not involve dialogue between players and exercise officials.
- 5. Emergency Action -
Specific' threshold conditions that Levels (EAL) may be used to designate a particular class or level of emergency. 1478e
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- 6. Emergency Operations - Plant emergency center established i Facility below grade in the Staff Building for !
the purpose of coordinating off-site response. i
- 7. Emergency Planning - The areas for.which planning is Zones recommended to assure that prompt and effective actions can be taken to protect the public in the event of an accident. The two zones are the j 10-mile radius plume exposure pathway l zone and the 50-mile radius ingestion exposure pathway zone. I l
- 8. General Emergency -
Actual or imminent substantial core ! degradation or melting with potential for loss of containment dategrity.
- 9. Maine Yankee Nuclear - Corporate response group from Maine Support Division Yankee who provides te'hnical c
i (MYNSD) support to plant and management.
- 10. Observer - A member of an exercise control group. He or she may also serve in a dual capacity as both a Controller and Observer. Each Observer may be assigned to one or more activities or functions for the purpose of evaluating, recording and reporting the strengths and weaknesses, and making recommendations for improvement.
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'11. Operations Support - ~The plant center established l j . J Center (OSC) below grade in the Staff Building to ;
provide Operations' support and relief in the event of an' accident.
- 12. Public Affairs - Maine Yankee Public Affairs organiza-Department tion,which works out.of CMP head-L quAEter.sinAugusta.
- 13. Scenario - The' hypothetical situation, from start' to finish, in an exercise which is the theme or basis upon which the action or play of the exercise unfolds.
. 14. ' Site' Area Emergency - An emergency classification which is
[ defined'as actual or likely major failu'res of plant functions.needed for the protection of.the public.
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- 15. Staff Suilding ~ - Building outside the security perimeter that houses the EOF, TSC and OSC. Access to the plant:is via an 1
underground passage. !
- 16. Technical Support - The plant center established .
1 Center (TSC) below' grade in the Staff Building to provide the Plant Shift Superintendent with adequate evaluation of plant conditions. 4
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- 17. 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.
- 18. 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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O MAINE YANKEE GRADED EXERCISE JUNE 1987
1.4 REFERENCES
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1.4 REFERENCES
Maine Yankee Atomic Power Station Entergency. Plan. Maine Yankee Atomic Power Station Implementing Procedures to the Emergency Plan. State of Maine Radiological Incident Plan.
. Yankee ~ Nuclear Services Division Emergency _ Response Plan (TAG No. 12). 'J O 1482e . ]
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O MAINE YANKEE GRADED EXERCISE JUNE 1987 2.0 EXERCISE OBJECTIVES
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1 I l i l I v 5 MAINE YANKEE ) GRADED MERCISE JUNE 1987 O 2.1 MAINE YANKEE NUCLEAR POWER STATION EXERCISE OBJECTIVES O
I i MAINE YANKEE ATOMIC POWER COMPANY 2.1 1987 EMERGENCY PREPAREDNESS EXERCISE OBJECTIVES I A. Control Room
- 1. Accident Assessment /Emeraency Classification
- a. Demonstrate the ability of the Control Room operators to promptly recognize the emergency action levels (EAL's) have been reached or-exceeded, and declare the appropriate Emergency Classification.
- 2. Notification
- a. Demonstrate the ability to notify Maine Yankee emergency repsonse personnel.according to Procedure 2.50.17.
- b. Demonstrate the ability-to notify Federal and State authorities of the emergency classification according to Procedure 2.50.17.
- 3. Communications
- a. Demonstrate the ability to coordinate information with the TSC
-(~ regarding the status of emergency conditions and in-plant
< emergency response activities. Demonstrate adequate recordkeeping of events, actions and b. communications. B. Technical Sucoort Center
- 1. Accident Assessment /Emeraency Classification
- a. Demonstrate the ability of the TSC staff to support the Control .
Room staff in ' identifying the cause of an incident, mitigating the consequences of.that incident, and placing the unit in a safe and stable condition.
- b. Demonstrate TSC proficiency in assisting the Emergency Coordinator in emergency classification or escalation,
- c. Demonstrate the ability to analyze current plant conditions, and identify projected trends and potential consequences.
- 2. Direction and Control
- a. Demonstrate the activiation of the TSC in accordance with Procedure 2.50.19.
- b. Demonstrate the primary responsibilities and/or problem-solving l capabilities of the TSC staff.
- c. Demonstrate the ability of the TSC to initiate and coordinate '
, activities according to Procedure 2.50.19.
I
.n l h 3. Communications ,
I
- a. Demonstrate the adequacy, operability, and effective use'of l emergency communications equipment and procedures, including the ; l l
status board. l
- b. Demonstrate 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 repair actions through the OSC.
C. Emeraencv Ooerations Facility
- 1. Direction and Control
- a. Demonstrate the staffing of the EOF in accordance with EPIPs. .
- b. Demonstrate the ability of the Emergency Coordinator to maintain command control over all emerge,'cy response activities conducted from the EOF throughout the exerc'se.
N 2. Communication
- a. Demonstrate the adequacy, operability, and effective use of emergency communications equipment and procedures.
- b. Demonstrate adequate communics.tions and transfer of data between the Maine Yankee Emergency Response Facilities, and between the EOF and the off-site monitoring teams.
- c. Demonstrate the ability to communicate station status, radiological conditions, and emergency response actions to off-site authorities.
- 3. Radiolooical Assessment
- a. Demonstrate the ability of the EOF staff to direct and coordinate the deployment of off-site monitoring teams according to EPIPs.
- b. Demonstrate the ability of the off-site monitoring team personnel to perform dose rate surveys and collection of radiological samples according to EPIPs as directed by the Radiological Sample Coordinator. ,
- c. Demonstrate the ability to perform off-site whole body and thyroid dose assessment based upon estimation of source term for iodines ,
and noble gasses, in accordance with EPIPs using Dose Assessment V[3 Procedures. 8497L-JMT
a 1 1
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'C d. Demonstrate the ability to formulate and implement on-site i protective action measures.
- e. Demonstrate appropriate health physics practices during the exercise to ensure on-site personnel and off-site monitoring team-exposures are minimized.
- 4. Protective Actions
- a. Demonstrate the ability to evaluate monitoring data, off-site radiological dose projections, and actual or potential degradation of plant and core conditions to arrive at appropriate protective action recommendations.
b Demonstrate the ability to make protective action recommendations to off-site authorities. D. Qperations Sucoort Center
- 1. Djrection and Control
- a. Demonstrate the activation of the OSC in accordance with Procedure
.t 2.50.18.
- b. Demonstrate the ability of the OSC Coordinator to exercise command control over all emergency response activities conducted from the ;
OSC throughout the exercise. Demonstrate command interface with TSC.
- c. Demonstrate the ability of the OSC to adequately staff and conduct functional responsibilities as requested by the TSC.
- d. Demonstrate the ability to provide adequate information briefings for in-plant teams for the mitigation of emergency conditions.
- 2. Communications
- a. Demonstrate the adequacy, operability, and effective use of communications equipment for communications between the OSC and OSC personnel within the plant.
- 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 to OSC staff and other Emergency Response Facilities.
p 3. Radioloaical Assessment
- a. Demonstrate the ability to direct and coordinate the deployment of on-site repair teams, and maintain / document appropriate radiological controls.
8497L-JMT
f. ( (,}, :. 1
- b. Demonstrate the ability to track cumulative exposure of corrective ,
action team members. I E. Security
- 1. Demonstrate the ability of the station security organization to effectively implement Procedure 2.50.9.
- 2. Demonstrate accountability within the protected area.
- 3. Demonstrate appropriate access control measures for the staff building.
F. Recovery Plannina.
- 1. Demonstrate though table top discussions, the establishment of the recovery organization and the formulation of a recovery plan necessary to return the plant to service from the simulated accident.
f, (h G. I l l Y l (k.
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Indicates NRC/ Utility identified improvement items from the 1986 exercise. l 8497L-JMT .) I
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O l j MAINE YANKEE GRADED EXERCISE JUNE 1987 3.0 EXERCISE GUIDELINES AND SCOPE O l l l O 1483e
'l MAINE YANKEE GRADED EXERCISE JUNE 1987 l 3.1 GUIDELINES Q t O 1483e 1 l l
l Rev. 0 l 3/11/87- ) Page 3.1-1 MAINE YANKEE j GRADED EXERCISE ) JUNE 1987 3.1 . GUIDELINES A. Purpose and Scope i This document provides guidance for conducting the June 1987 Maine Yankee Graded Exercise. It provides methods for' demonstrating '- emergency response capability, conducting the exercise and evaluating the results. Section 3.3 summarizes the actions to be simulated by players during the exercise. B. Concepts of Operations and Control of'the Exercise i Maine Yankee will supply official Controllers /0bservers for each location where an emergency response is being demonstrated. Prior to'the exercise, the Controllers /0bservers will be provided with appropriate maps, materials and evaluation forms. 4 Controllers / Observers will distribute information to players on message cards. Controllers will provide advice to Observers and resolve problems. For scenario purposes Controllers may be required I to issue command cards to direct the play of some events. The Exercise Coordinator will be in overall charge of conducting the exercise. Major requests for scenario modifications or holding l periods must be cleared through the Exercise Coordinator. ; The exercise initial conditions will be provided to a Control Room operations crew located in the simulator by the Control Room / Simulator Controller also in the simulator. The remaining exercise message cards will be provided by Controllers / Observers at other 1483e i
Rev. 0 3/11/87 ry 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 operators 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 emergency plan implementing procedures. These procedures are expected to include a determination of the emergency Si classification in accordance with NUREG-0654, FEMA-REP-1, Rev. 01. (O Notifications will be made to the appropriate federal and state authorities. The hypothesized emergency will continue to develop based on data and information provided to the operators located in the simulator. 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 i a limited time. Controllers have the authority to resolve or explain problems that may occur with the scenario during the exercise. l l 1 r S,
) 1483e l
l l 4
Rev. 0 3/11/87 [ 'h Page 3.1-3
&J C. General Guidance for the Conduct of the Exercise i
l 1.. Simulating 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 response is to be simulated the Controller will provide the 1 players'with written directions in the form of a command card i on which actions are to be simulated. i
- 2. Avoiding Violations of Laws l'
Intentional violation of laws is not justifiable during any l exercise. To implement this guideline the following actions () must be taken:
- a. All Controllers /0bservers and potential exercise participants must be specifically informed of the need to avoid intentional violation of all federal, state and ;
local laws, regulations, ordinances, statutes and other legal restrictions. The orders of all police, sheriffs or other authorities should be followed as would normally be the case.
- b. Exercise participants will not direct illegal actions being taken by other exercise participants or members of the general public.
- c. Exercise participants will not intentionally take illegal actions when being called out to participate in an exercise. Specifically, local traffic laws such as speed
,,~s laws will be observed. -( )
1483e
i Rev. 0 3/11/87 i Page 3.1-4
- 3. Avoiding Personnel and Property Endangerment Participants and Evaluators will be instructed to avoid !
endangering property (public or private), other personnel responding to the exercise, members of the general public, L animals and the environment. L i
- 4. Actions to Minimize Public Inconvenience I s
It is not the intent, nor.is it desirable or feasible, to effectively train or test the public response during the conduct of radiological emergency exercises. Public inconvenience is to be minimized. ) i 1 i
- 'The actions of federal, state and local agencies and nuclear ]
power plant operators receive continuous public notice and scrutiny; therefore, the conduct of an exercise could arouse public concern that an actual emergency is occurring. It is important that conversations that can be monitored by the public (radio, loudspeakers, etc.) be prefaced and conclude with the words, "this is a drill; this is a drill." ( .. D. Emergency Response Implementation and Operations
- 1. Initial Notification Initial notification of the emergency classification will be made by station staff and the states in accordance with existing emergency plan implementing procedures. Initial 9 notification made.to local communities by the state shall be .
completed for this exercise. t 1483e
Rev. O rx 3/11/87 Page 3.1-5 {}
- 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 i 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 vill be provided j () _ to Control Room players.
- 5. Technical Support Center (TSC) Operations .
i j The TSC emergency response organization will be activated during this exercise. TSC information and direction will come from the Control Room Operators, located in the Simulator. Data which is normally accessible from the Safety Parameter Disp 19y System (SPDS) will be provided to the TSC directly from the simulator.
- 6. Operations Support Center (OSC) Operations The OSC emergency response organization will be activated during this exercise. Operations Support Center responses, direction and information will be communicated with the Technical Support Center. OSC Controllers / Observers will h accompany all OSC teams dispatched during the exercise and will have appropriate operational and radiological data for the players.
I l
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._. Page 3.1-6 p .)
- 7. Off-Site Monitoring Teams Off-site monitoring teams will be fully activated and 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 be fully activated and staffed during the exercise although these activities are not part of the formal exercise objectives. Press releases to the general public and news media will be simulated. Media Center staff will obtain all necessary information on current status of the exercise through normal communications channels with the EOF. Simulated rmi press releases will be compiled and implemented in accordance b with the Yankee Media Center Emergency Procedures.
- 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 demonstrated. Evacuation of exercise nonparticipants shall not be demonstrated, however.
l E ,. Exorcise Termination l The exercise will be terminated by the Exercise Coordinator when all i emergency response actions have been completed in accordance with 1 the exercise time sequence. I l (Oj 1483e l
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l; f.- O I i MAINE YANKEE
)
GRADED EXERCISE JUNE 1987 3.3 SIMULATION LIST
\ \
l O h O 1479e 1
/ -Rev. O ~3/11/87 .Page_3.3-1 MAINE: YANKEE-GRADED EXERCISE- l SEPTEMBER 1986 . 3. 3 SIMULATION LIST 4
The-following plant actions will be simulated:
- 1. . Simulator Operations Crew notifying the NRC on the red phone (NRC will be notified from the.Cc,ntrol Room of the start and finish'of.the exercise).
- 2. Any issuance of potassium iodide (KI); 4 I
- 3. Personnel and area decontamination; O 4. . Collection and analysis of-all environmental samples and TLDs;
- 5. Activation of the' EOF /TSC Emergency Ventilation Systems N
- 6. Containment entry;
.7. Playing of all the prerecorded emergency. message tapes on the public information telephone; 1
- 8. Post-accident sampling;
;9. Plant evacuation of nonparticipants;
- 10. RWPs for' exercise activities;
- 11. Yankee ~ Environmental lab response; and O 13,. Activation of the PEAS will be simulated.
1479e
i l i l I' O 1 MAINE YANKEE GRADED EXERCISE JUNE 1987 3.4 PLAYER INSTRUCTIONS O 4 l 1 i 4 O 1485e
I Rev. 0 3/11/87 Page 3.4-1 73 'd MAINE YANKEE GRADED EXERCISE JUNE 1987 l l i 3.4 PLAYER INSTRUCTIONS The Maine Yankee graded exercise of the Emergency Plan will be held on June 10, 1987. The successful demonstration of emergency response capabilities will depend on player observation using the following guidelines:
- 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
,r] emergency responses. They will be identified by colored hats and O will also be evaluating 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 accordance with your Emergency Plan and Procedures as if it were a real emergency. If an action or data is to be simulated, an Exercise Controller or Observer will provide Players with appropriate direction.
- 4. Always identify and discuss your actions to the Controllers and Observers. State your data out loud as you are recording it. For your own benefit, it is recommended that you play out your actions as much as possible, as if it were a real emergency. It is to your advantage to exercise as many appropriate response actions as l
possible. j g Q 1485e
Rev. 0 3/11/87 /~N Page 3.4-2
) 1
- 5. Periodically speak out loud, identifying your key actions and decisions to the Controllers / Observers. This may seem artificial, 1
but it will assist the evaluators and is to your benefit. i l
- 6. When you are assigned 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 J
will not prompt or coach you. Emergency response actions must not j 4 place exercise participants in any potentially hazardous situations. j
- 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 your successful
!n) V performance.
- 9. If the Controller intervenes in your response actions and recommends 1 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.
I l
- 10. If you disagree with your Controller or Observer, discuss your problem with him. However, Controllers /0bservers final decisions i must be followed.
- 11. Respond to questions in a timely manner.
- 12. Do not accept any messages / instructions from NRC Evaluators. They are required to work through your Controller / Observer if they want to instigate additional emergency conditions. I i
(% 1485e i
l Rev. 0 3/11/87 Page 3.4-3 (~~)') L
'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.
- 14. Controllers /0bservers/ Evaluators are exempt from simulated radiation levels and other emergency conditions. Do not let this confuse you or cause you to act unwisely. However, no one is exempt from normal station radiological practices and procedures.
- 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 theso communications are not Q ,1 confused with an actual emergency.
- 17. Only use procedures from procedures books in the ERF cabinet. DO NOT USE MARKED UP, OUTDATED COPIES, OR PERSONAL NOTES.
I' j ~ 1485e
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i O l
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l l l MAINE YANKEE GRADED EXERCISE JUNE 1987
\
3.5 P_ROCEDURE EXECUTION LIST O 1 4 l l l I h i
'l O 1480e
[~ 1 Rev. 0. 3/11/87 Page 3.5-1 i
. MAINE YANKEE GRADED. EXERCISE JUNE 1987 1
3.5 PROCEDURE EXECUTION LIST
' Operating Procedures (OP)
OP 1 Operations,at Power OP 1-4-2 Coastdown Operation Using TC Control OP'l-6 Reactor Shutdown p$ OP 1-7 Plant Cooldown
'.' gQ Abnormal Operating Procedures (AOP)
AOP 2-10 Loss of-Pressure Control /RCS Leak A0P 2-25 High Radiation Levels i Emergency Operating Procedures (EOP) j l E-0 Emergency Shutdown from Power or Safety Injection E-1 Loss of Primary or Secondary Coolant j . 1480e i 1 1
Rev.-0 3/11/87 1/ ' Page 3.5-2 ? LJ' Emergency Plan' Implementing Procedures (EPIP) g EPIP 2.50.0 Declaration and Categorization of Emergency. Condition EPIP 2.50.1 ' Notification of Unusual-Event: ! EPIP 2.50.2 Alert
- EPIP 2.50.7 Emergency On-Site Radiation Monitoring Procedure EPIP 2.50.9 Security Force Radiation Emergency Plan EPIP.2.50.10 Evaluation of Radiological Data
'EPIP 2.50.11 Plant Entry and Recovery Plan )
EPIP 2.50.12 Emergency Off-Site Radiation Monitoring Procedure EPIP 2.50;14 Emergency Radiation Exposure Control EPIP 2.50.15 Release of Public Information During Emergencies EPIP 2.50.16 Protective Action Recommendations EPIP.2.50.17 Emergency Notification EPIP 2.50.18 Operations support Center EPIP 2.50.4 General 'rergency (
'\ / 1480e 1
I , l s Rev. 0-- 3/11/87
-, '7 Page 3.5-3 Emergency Implementing Procedures'(EIP) - Continued EPIP 2.50.19- Technical Support Center EPIP 2.50.20- -Prophylatic' Administration of KI for Thyroid Blocking Health Pnysics Procedures 9.1.7 Area and Equipment Decontamination, j Chemistry Procedures -7.1.16 Post-Accident Sampling Panel Operation for Training and Exercises.
1
, 1 1480e ;
O MAINE YANKEE GRADED EXERCISE JUNE 1987
.I )
C 3.6 EXERCISE TERMINATION CRITERIA I
!l O 1,ee, 1 i
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6 i' =. Rev. 0 4/9/87~
'Page 3.6-1 ;Vfy-4 . MAINE YANKEE GRADED EXERCISE JUNE 1987 3.6 EXERCISE TERMINATION CRITERIA ,
The exercise may be. terminated under-the following circumstances:
- a. . .If a11' emergency response actions have been-completed in accordance with the exercise time sequence;.or )
b.s If an' actual plant emergency. condition develops coincident with the exercise. JI~'i In the event that Item b should occur, the following actions _will be u taken:
- 1. The Plant Shift Superintendent (PSS) will contact the Simulator PSS and inform him of plant status;
- 2. The Simulator PSS will immediately contact the Emergency Coordinator and/or the Plant Manager who, in turn, will immediately. inform any Federal or State' representatives at the EOF of the nature of the emergency; 3.. Concurrent with the notification in Step 2, the Plant Shift Superintendent will announce over the plant Paging System the following statement:
The emergency plan exercise has been terminated. I repeat.. The emergency plan
, exercise has been terminated.
i., Rev. O' O 4/9/87 Page 3.6-2 This message would be'immediately followed by the' appropriate, emergency-class' announcement;
- 4. ' The Emergency Preparedness Coordinator would be responsible for.
directing the actions of the Controllers /0bservers; and
'5. The emergency plan / procedures applicable to the event would be implemented in accordance with the nature of the emergency.
1 0 l i 1 l j O 1506e
l O f i MAINE YANKEE GRADED EXERCISE JUNE 1987 1
\
4.0 CONTROLLER /0BSERVER INFORMATION O 1 r
'l 1481- -O l 4
i
O 1 MAINE YANKEE \ GRADED EXERCISE q JUNE 1987 l
\
4.1 ASSIGNMENTS O s, 4 l i O 1481e
Rsv. 2 6/4/87 Page 4.1-1
#i MAINE YANKEE \}
GRADED EXERCISE JUNE 1987 4.1 ASSIGNMENTS Exercise Coordinator Jeff Temple Recovery Center Controller Bill Riethle Emergency Operations Facility Controller Steve Evans Dose Assessment Controller Tom Fuller EOF Observer Ed Wojnas Control Room Controller (Simulator) Bill Ball CR (Simulator) Observer Mike Swartz Technical Support Center Controller Doug Whittier [} TSC Observer Pete Anderson
\J Operational Support Center controller Ed Salomon OSC Observer Bruce Lord OSC Observer Ray Sibley OSC Observer ' Dan McDavitt OSC Observer Mike Thornhill Off-Site Monitoring Team Observer John McArdle Off-Site Monitoring Team Observer Dennis Hickey Off-Site Monitoring Team Observer Jim Hawxhurst :
j News Media Center Controller Ruth Zikaras News Media Center Observer Bill McGee Engineering Support Center Controller Ken Traegde '/)
\~.J Security Controller Dorsey Holsinger ;
l State Emergency Operations Center George Stowers
O b MAINE YANKEE GRADED EXERCISE June 1987 \ 4.2 Exercise Guidance / Evaluation Sheets e 0 1474e
Rev. 0 3/11/87 h("N Page 4.2-1 MAINE YANKEE GRADED EXERCISE JUNE 1987 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 plant emergency implementing procedures which correspond to their assigned audit function. It is the responsibility of the Observer / Controller to read the contents of this package, review the procedure associated with the assignment, and then, develop a checklist of important concepts associated with the designated procedure which can be used as a reference during the exercise. In developing this checklist, an attempt should be made to categorize the concepts under general headings such as Communications, (' i Training / Procedural actions, Organizational Control, etc. This checklist N should supplement the ones which are provided in this package. Prior to the exercise, each Observer / Controller will be requested to attend an Observers / Controllers Briefing Session. During this meeting, each Observers / Controller should identify any questions he/she has with the package content and/or their assignment. It is the responsibility of each Observer / Controller to ensure that he/she is familiar with the various plant locations where their assignment will require their presence. Tours will be provided as a portion of the training; however, these tours will be limited in their duration. It may be advisable to plan an additional tour. Observers should familiarize themselves with their assigned Center Controller prior to the exercise. The Controller will be responsible for directing observer activities throughout the course of the exercise. At exercise termination, each Center Controller is responsible for meeting Q with their Observers and directing their critique and documentation of d their exercise comments. Each Controller will be responsible for ensuring that this documentation is provided to the Emergency j 1474e l L
l l l { Rev. O i l 3/11/87 Page 4.2-2 Preparedness Coordinator at the conclusion of the critique session. Each > Controller is also responsible for providing a brief summary of their Observer comments during the formal critique. . / . Observers / Controllers should identify themselves to players and explain \ 3 their role in the exercise and wrat they are critiquing. Observers / Controllers sM uld 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 I log throughout the exercise, listing all transferred data and player responses. This log and related comments should provide the time, place, and names of involved personnel. The primary role of exercise Observers / Controllers is to review and note 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 or inadequate performance. For inadequate performance of personnel, equipment, etc. provide recommendations for improvement detailing corrective / mitigative actions. If the evaluation criteria is not applicable to the exercise objectives or the scenario, this should be noted on the evaluation form also.
Observers / Controllers should ng allow their biases to be documented as l recognized inadequacies. Comments and recommendations should be further subdivided according to the following major headings: Facility Activation / Organizational Control, Communications, Adherence to Plans and , , Procedures, Equipment Capabilities, Scenario, Training, Facility Layout, l Off-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Comments. 1474e
Rev. 0 (N 3/11/87 () Page 4.2-3 Facility Activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the facility was activated; (3) when initial activities become well organized; (4) whether personnel performance follows the organized arrangements specified by plant procedures; and (5) the efficiency of methods of authority transfer. If a transfer of responsibility occurs, then the Observer should determine if all affected personnel are aware that the transfer has occurred. Communication comments should identify: (1) personnel familiarity with emergency communications use; (2) whether sufficient communications were available to ensure a timely, efficient, and effective flow of information; (3) whether there were enough communications personnel to make use of all available equipment; (4) the adequacy of communications g logs and describe the effectiveness of data transfert (5) whether there 1 ( ,' were any problems in the design of the existing communications system (i.e., location relative to traffic flow); (6) whether there were any recognized difficulties in use of computer systems; and whether center status boards are effectively used. Observers should document their comments in this area very carefully, providing sufficient details to track any recognized deficiencies. Plans and Procedures comments should identify: (1) whether personnel were familiar with the details or overall concepts of applicable procedures; (2) whether situations developed which required deviation from the procedure or plan; (3) whether personnel were overwhelmed with procedural requirements distracting them from performing their required emergency response function; and (4) whether the procedures adequately described the actions required to complete an assigned function. Equipment capability comments should identify: (1) whether all necessary materials and equipment were available and functional; (2) whether V emergency response personnel checked operability of equipment prior to ' conducting their assignment; (3) whether backup equipment was readily i 1:s % i
l Rev. O.
.A 3/11/87 l _ }] Page 4.2-4 l available when malfunctions were reported; (4) whether the available systems provide an adequate service; and (5) whether equipment-malfunctions impacted the expected emergency response.
1
' Scenario related comments should address: (1) whether sufficient information was available to ensure appropriate player response; (2) l whether the scenario details deviated from actual procedural 4 requirements; and (3)'whether the scenario detail provided any prompt to l the player. An additional question should be answered by ,
Observers / Controllers concerning the adequacy of the scenario in keeping. l the players active and interested throughout the exercise. Training comments should identify: (1) whether plant personnel have been provided sufficient training to handle."ad hoc" procedural deviations;
.:4 and (2) whether training identifies improper procedural requirements. l i .\j i Comments on facility layout deficiencies / recommendations should identify: (1) whether the available work space provided was adequate; (2) whether traffic flow hindered the response efforts; (3) whether the communications available in the work area were adequate; (4) whether the noise level hindered emergency response efforts; and (5) whether sufficient references were available to complete the job assignment.
Off-site monitoring team should identify: (1) the adequacy of sampling methods; (2) the adequacy of reporting and documentation. measures;-and (3) the effectiveness of the team in defining radiological status. Dose j projection techniques should be evaluated in conjunction with this
. general category. Consideration of dose projection technique deficiency / recommendations should identify: (1) the effectiveness of the system in allowing the correct interpretation of off-site conditions; and (2) the effectiveness of using the projection technique in positioning - . off-site teams.
( -
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1474e
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V ' !
-Evaluation of Personnel Dosimetry /ExposureL-Control' activities should-identify: (1) the timeliners and effectiveness of' dosimetry distribution;'(2)'the effectiveness of protective measures; (3) the . adequacy.'of established contamination control access points;-(4) the..
adequacy of: exposure planning measures afforded in plant activities; and (5) the adequacy of decontamination and posting techniques.- .
"~
The' Controller / Observers will be provided an Evaluation List and
. Evaluation Form found in this section.- All such documentation must be- ; - provided to the Center Controller prior to the conclusion of the critique ~ .
- I f
O O -1474e* i i
Rev. 0 3/11/87 .j] Page 4.2-6 ..V MAINE YANKEE Exercise Evaluation List A.- . CONTROL ROOM
)
- 1. Accident Assessment / Emergency Classification
- a. Did Control Room operators demonstrate the ability to yes/no/NA-promptly recognize that emergency action levels were reached or exceeded and declare the appropriate Emergency
. Classifications in accordance'with Procedure 2.50.0? l l
- 2. Notification
- a. Did Control Room operators demonstrate the ability to yes/no/NA ;
notify Maine Yankee emergency response personnel according-to Procedure 2.50.17? l i
- b. Did Control Room operators demonstrate the ability to yes/no/NA notify Federal and State authorities of emergency -j classification according to Procedure 2.50.17?~
- c. Did Control Room operators demonstrate the ability to yes/no/NA notify station personnel of an emergency through the use of alarms and the public address system according to Procedures 2.50.1 and 2.50.2?
- 3. Communications
- a. Did Control Room staff demonstrate the ability to yes/no/NA disseminate information to the TSC regarding the status of the emergency conditions and in-plant
, emergency response activities in accordance with Emergency Procedure 2.50.27 1474e
1 ll Rev. 0 3/11/87 Page 4.2-7; I (q , l' b. Did Control Room operators demonstrate'the-adequate yes/no/NA. I record keeping of events, actions, and communication according to emergency procedures? j l B.. TECHNICAL SUPPORT CENTER
.1. Accident Assessment / Emergency Classification i
- a. Did the TSC staff demonstrate the ability to support yes/no/NA ;
l the Control Room staff _in identifying the cause of I the incident, mitigating the consequences:of that j l incident,'and placing the unit in a safe and stable condition?
- b. Did TSC staff demonstrate proficiency in' assisting the yes/no/NA
' Emergency Coordinator in emergency classification or O- ' escalation according to Procedure 2.50.197 I
- c. Did TSC staff demonstrate the ability to analyze yes/no/NA current plant conditions, and identify projected trends and potential consequences according to procedures?
- 2. Direction and Control
- a. Did the TSC staff demonstrate the ability to direct and yes/no/NA coordinate radiological planning, monitoring, and sampling with the OSC and to communicate in-plant radiological conditions with the EOF?
h (! b. Did the TSC staff demonstrate the ability to hold yes/no/NA emergency briefings, including the station status and transfer of responsibilities, and maintain emergency
- /"% status boards?
LU 1474e
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. Page 4.2-8
- 3. Communication
- a. Did the TSC staff demonstrate the adequacy, operability, yes/no/NA and effective use of emergency communications equipment.
and procedures?
- b. Did the TSC staff demonstrate the ability to gather, yes/no/NA' assess, and disseminate information between Maine Yankee Emergency Response Facilities,-the EOF, and off-site monitoring teams?
- c. Did the TSC staff demonstrate the ability to direct 'yes/no/NA i and coordinate in-plant surveys through the OSC in accordance with Procedure 2.50.197 :!
. /~ ' ,
C. EMERGENCY OPERATION'S FACILITY
' 1
- 1. Direction and Control
- a. Did the EOF staff demonstrate the appropriate activation yes/no/NA of the EOF 7 l l
- 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? ] i
- 2. Communications
- a. Did the EOF staff demonstrate the adequacy, operability, yes/no/NA and effective use of emergency communications equipment according to Procedures 2.50.1, 2.50.2, 2.50.15, and O 2.50.17?
1474e
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- b. Did the EOF staff demonstrate adequate communications yes/no/NA and transfer of data between the Maine Yankee Emergency
, Response Facilities and between the EOF and the off-site J monitoring teams according to Procedures 2.50.7, 2.50.12, 2.50.18, 2.50.19, and 2.50.217 s
- c. Did the EOF staff demonstrate the ability to yes/no/NA communicate station status, radiological conditions, and emergency response actions to off-site authorities according to Procedures 2.50.15, and 2.50.167
- 3. Radiological Assessment
]
- a. Did the EOF staff demonstrate the ability to direct and yes/no/NA coordinate the deployment of off-site monitoring teams I according to Procedures 2.50.12 and 2.50.2?
J
- b. Did the EOF staff demonstrate the ability of the yes/no/NA off-site monitoring team personnel to perform dose rate surveys and collection of radiological samples according to Procedure 2.50.12 as directed by the Off-Site Monitoring Coordinator?
- c. .~ Lid the EOF staff demonstrate the ability to perform yes/no/NA off-site dose assessment in accordance with Procedure 2.50.107 i t
- d. Did the EOF staff demonstrate the ability to formulate yes/no/NA and implement on-site protective action measures according to Procedures 2.50.20, 2.50.14, 2.50.11, 2.50.10, and 2.50.7?
O N, 1474e l 1
J , m;_ n i 8, .'.I 5 Rev. O' L c :3/11/87 J. Page 4.2-10.- , 'N ' N,
- e. LDid the. EOF' staff demonstrate appropriate' health physics yes/no/NA
[Q practices,-such as contamination control, during the. w: cise to ensure personnel exposures,are As Low As
' Reasonably Achievable (ALARA) according to Procedures 2.50.14 and 2.50.77.'..
- 4. 'Profective Actions}
- a. Did the EOF staff; demonstrate the. ability to evaluate: yes/no/NA
. monitoring data, off-sir.e~1 radiological dose 1, . , ' . y. .Lt ; , i-7 projections, and plant conditions to arrive at m 7 V / appropriate' protective' action recommendations in' accordance with Proaee es 2.50.10 and L:59.367 g . 'b~. Eid the EOF stali.e- w trate the abili!:p to , 'yes/no/NA-I make protective'acn .a recommendations'to off-site y, "h '
authorities according to. Procedure 2.50.16i
~ .T"
- w. s
- ) w g
- Y-5.,.'Q}ftSrpffing.
'.l' .._[j . s, 4 ?- iy S - .y. . ?
yes/no/NA q :0 it.a g Did,',the EOF staff demonstrate through-discussions
~and. staff planning,1:the method to perform a shift change in eMh Emergency Center? 'D. OPERATIONS SUPPORT CENTER .- x -1. Direct and Control ! ,s
- a. . Did the OSC staff demonstrate the activation of the yes/no/NA 350 in accordance with Procedure 2.50.18?
'h \
1474e
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.; ) Page 4.2-11
- b. Did the OSC Coordinator demonstrate the ability to yes/no/NA command and control overall emergency response activities conducted from the OSC throughout the '
exercise as designated in Procedure 2.50.18? Did f l the OSC staff demonstrate command interface with the TSC Coordinator?
- c. Did the OSC staff demonstrate the ability and adequate yes/no/NA staffing to conduct functional responsibilities as requested by the TSC?
- d. Did the OSC Coordinator demonstrate the ability to yes/no/NA provide adequate information briefings for.in-plant teams for the mitigation of emergency conditions in
,-3, accordance with Procedure 2.50.18?
./ \ V Communications I 2.
- a. Did the OSC staff demonstrate the adequacy, operability, yes/no/NA and effective use of communications equipment and procedures for communications between the OSC and OSC personnel within the plant according to Procedures 2.50.18, 2.50.11, and 2.50.7?
- b. Did the OSC Coordinator demonstrate the ability to yes/no/NA gather, assess, and transfer information regarding the status of plant operational or radiological conditions and the status of OSC activities to OSC staff and other emergency response facilities in accordance with Procedure 2.50.18?
g-(j 1474e j l l i I a
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- 3. Radio' logical Assessment
- a. Did the OSC staff demonstrate the ability lto direct 'yes/no/NA 1 l
and coordinate the' deployment of and maintain -{ appropriate radiological controls for on-site-repair teams according to Procedures 2.50.18, 2.50.7, 2.50.11, and 2.50.147
- b. Did the OSC staff demonstrate appropriate coordination yes/no/NA' -j with OSC Coordinator regarding appropriate radiological )
controls? ;
, E. 'PUBLIC INFORMATION-l !
l ; l 1. 'Did the Public Information staff-demonstrate the ability to~ yes/no/NA,
- i. conduct coordinated news briefings and issue coordinated-V news releases?
~!
- 2. Did the Public Information staff demonstrate.the ability to yes/no/NA staff the. appropriate media. release locations?
- 3. Did the Public Information Staff demonstrate the ability to 'yes/no/NA coordinate with off-site authorities on rumor control?
l
- 4. Did the Public Information staff demonstrate the timely yes/no/NA l'- exchange of information among participating designated i V
spokespersons? F. RECOVERY PIANNING
- 1. Did the emergency recovery organization, through table yes/no/NA top discussions, demonstrate the establishment of a
( recovery plan necessary to identify and repair the source of the leak? n19.
1 I Rev. O 3/11/87 3
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G. SECURITY ] l
- 1. Did security demonstrate the ability to effectively yes/no/NA implement Procedure 2.50.9?
i
- 2. Did security demonstrate accountability within the yes/no/nA protected area? ,
- 3. Were appropriate access control measures demonstrated yes/no/NA for the Staff Building?
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,_, Rev. 0 / ') 3/11/87
- s. / Page 4.2-14 MAINE YANKEE !
Emergency Exercise / Drill Observers Evaluation Form Observer: Name Exercise / Drill Date Exercise / Drill
Title:
Time Started: Location of Observer: Observed: Player Function (N Overall Performance: 1
.\_ /
Recognized Inadequacies: (General categories specified in the Introduction of this section.) Recommendations for Improvement (Specific): Use additional pages as required.
/%
L-) Signature Date 1474e ) 1 I
9 j MAINE YANKEE i GRADED EXERCISE: l JUNE 1987 l l 1 5.0 EXERCISE SCENARIO f O iis i
l I MAINE YANKEE GRADED EXERCISE JUNE 1987 1 5.1 INITIAL CONDITIONS O l' l i 1 1470e l
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V MAINE YANKEE GRADED EXERCISE JUNE 1987 5.1 INITIAL CONDITIONS A crew of Control Room operators located in the simulator will be provided the following information at the start of the exercise:
- 1. The reactor has been operating at full power for the last fourteen months and is nearing the end of core life.
- 2. The reactor is operating at:
2610 MWt 888 MWe 576 Tave (*F) l 2235 Pressurizer Pressure (psig) l 58 Pressurizer Level (%)
- 3. The latest reactor coolant analysis completed and verified by j
I ("'j Chemistry indicates 0.9 uCi/g dose equivalent I-131 (at Technical Specification limit) and 8.0 uCi/g noble gas. im _/
- 4. HPSI Pump P-14-A is out of commission for motor repairs and is I awaiting spare parts. When operators attempted to valve in the spare HPSI Pump, P-14-S, at 1635 hours today, a flange gasket failure occurred, rendering the pump inoperable. The necessary paperwork to l perform the replacement are being prepared including the stores requisition for the new gasket. (Refer to Miniscenario 7.2.1(a).)
The immediate area around the charging pumps is experiencing elevated l dose rates of 300 (mR/hr) and contamination surveys in the area are l indicated as 100,000 (dpm/m2 ). The area has been roped off and f marked in accordance with HP Procedure 9.1.6, " Establishing and Posting Controlled Areas." Decontamination efforts have been initiated. (Refer to Miniscenario 7.2.1(b).)
- 5. Containment personnel hatch inner door failed an 0-ring test at 1545. A maintenance crew is replacing the 0-rings.
- 6. Yesterday, at 1805, while performing routine maintenance on valve CS-M-1, damage to the valve stem was found which most likely occurred during last closure as a result of improper torque switch setting.
The valve was declared inoperable and the remedial action of Technical Specification 3.6 is invoked. A pew stem is expected
,f 3 on-site by 2000 today.
NJ 1470e
7-I O 4 MAINE YANKEE GRADED EXERCISE JUNE 1987 i 5.2 SCENARIO OUTLINE
. O- O O 1471e I
Rev. 1 7.s 5/18/87 l Page 5.2-1 G Y' MAINE YANKEE GRADED EXERCISE JUNE 1987 i 5.2 SCENARIO OUTLINE Clock Scenario Time Time 1715 0000 OPERATORS RECEIVE INITIAL CONDITIONS WITH SIMULATOR INDICATING PLANT STATUS AT NORMAL FULL POWER. I 1725 0010 AN RCS LEAK OF 5 GPM OCCURS. 1730 0015 RCS leakage in containment should be evident to operators as indicated by: ,,- ~ . f o RADIATION MONITORING SYSTEM INCREASE o VOLUME CONTROL TANK (VCT) LEVEL DECREASE l o LOOP 2 CONTAINMENT SM0KE DETECTOR (HEAT SENSOR) ALARM o CONTAINMENT SUMP LEVEL INCREASE o CONTAINMENT AIR PARTICULATE DETECTOR (APD) INCREASE 1733 0018 Operators should notify the maintenance crew working on the personnel hatch of increased radiation levels and possible leakage recommending an immediate evacuation of containment. , l.
'" 1471e
Rev. 1
-5/18/87 ~1 Page 5.2-2' 1 ' Clock- ' Scenario Time Time 1735. 0020f 'THE RCS LEAK RATE INCREASES TO APPROXIMATELY 30 GPM.
FOR EXERCISE PURPOSES, ANY ATTEMPT TO ESCALATE THE
. EMERGENCY CLASS TO ALERT WILL BE CONTROLLED VERBALLY BY THE FACILITY CONTROLLERS UNTIL 1820.
l 1736 0021 Operators should commence a rapid controlled power reduction to shutdown the reactor in accordance with A0P 2-10 and in compliance with' Technical Specifications
]
3.0.A and 3.14. ! 1745 0030 An UNUSUAL EVENT may be. declared by the Plant Shift Superintendent (PSS). Operators may elect to trip plant. 1753 0038 ' CONTAINMENT HIGH RANGE RMS ALARMS. 1803 0048 THE MAINTENANCE CREW WORKING ON THE CONTAINMENT HATCH REPORTS THAT IN THEIR HASTE TO EXIT THE PERSONNEL HATCH THEY BELIEVE THE OUTER DOOR SEAL MAY HAVE BEEN DAMAGED. REPAIRS TO THE INNER DOOR SEALS HAD NOT BEEN COMPLETED. (Refer to Miniscenario 7.2.2.) 1815 0060 VACUUM IN THE CONDENSER IS LOST DUE TO LOSS OF THE TURBINE GLAND SEAL STEAM LINE. LOSS-OF-VACUUM CAUSES A TURBINE TRIP, A REACTOR TRIP, AND ISOLATION OF CONDENSER STEAM DUMP.
.]
S/G SAFETY VALVES LIFT j i l Operators should open the decay heat release valve to p' ' effect cooldown. ( 1471e l l i J
Rev.:1
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- Page 5.2-3 h 3Q ;
Clock _ Scenario Time- Time 1820 0065 THE RCS LEAK RATE INCREASES TO 200 GPM (WHICH IS.THE '] MAXIMUM CAPACITY OF THE CHARGING PUMP).
'I Operators should-recognize major leakage is' occurring, probably greater than 100 gpm,'by' charging. flow. increase and drop in Pzr level and declare'an ALERT LEVEL FMERGENCY.
1833 0078 CONTAINMENT'HIGH PRESSURE ALARM IS RECEIVED (APPR0XIMATELY 3 PSIG). Operators should swap charging pump. suction to RWST due
,. to. low VCT level or initiate HPSI.
t.j AN ALERT IS DECLARED DUE TO RCS LEAK RATE EXCEEDING 100 GPM. . 1835 0080 AT APPR0XIMATELY THIS TIME, CHARGING PUMP SUCTION WILL AUTO SWITCH TO RWST ON LOW VCT LEVEL. l 1835-1900 All utility, state, and hTC emergency response facilities should be activated.
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Rev. l' 5/18/87' Page 5.2-4 -[] Q Clock Scenario.- Time- Time'- 1925 0130. IF CONTAINMENT SPRAY HAS BEEN PREVIOUSLY INITIATED, AN UNKNOWN COMPLETE FLOW BLOCKAGE WILL OCCUR AT THIS TIME. WHILE IF THE DECISION TO INITIATE CONTAINMENT SPRAY IS MADE BETWEEN NOW AND 2100, VALVE CS-M-2 WILL FAIL TO OPEN. . A MAINTENANCE TEAM SHOULD BE SENT TO INVESTIGATE. (Refer to Miniscenario'7.2.3.) NOTE: IF THE INOPERABILITY OF THE CONTAINMENT SPRAY SYSTEM IS' IDENTIFIED, A GENERAL EMERGENCY SHOULD BE DECLARED DUE TO LOSS OF REACTOR COOLANT ~AND LOSS OF ALL CONTAINMENT SPRAY CAPABILITY. 1945' 0150 THE RCS-LEAK WORSENS TO ABOUT. 350-400'GPM.
/"'4 AT THIS TIME SIGNIFICANT FUEL FAILURE OCCURS, RESULTING IN RAPIDLY INCREASING CONTAINMENT DOSE LEVELS.
THE REMAINING HPSI PUMP P14-B WILL SEIZE. A GENERAL EMERGENCY should be declared due to loss-of-reactor-coolant and failure of HPSI following loss-of-coolant (failure to provide adequate overpressure for core to secondary side heat transport). ! 1950 0155 Off-site monitoring teams should have been dispatched to downwind site boundary locations. Small increases in off-site monitoring results are reported due to a leak in' ] containment'through the personnel hatch and small increases it} containment radiological levels. The team working on HPSI Pump, P-14S, will report back to the Control Room that P-14B has seized due to apparent bearing failure with repair unlikely. 1
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2000 0165' CONTAINMENT ISOLATION AND SAFETY INJECTION ACTUATION' OCCUR'AS CONTAINMENT PRESSURE EXCEEDS S PSIG (IF NOT ALREADY MANUALLY ACTUATED). CONTAINMENT MONITOR READS . 2 x 100 (R/hr).
. FOLLOWING CI THE DECAY HEAT RELEASE VALVE, MS-A-162. ~
CANNOT BE USED FROM THE CONTROL ROOM FOR DECAY HEAT REMOVAL UNTIL CIS SIGNAL IS BLOCKED.
~i .The.0SC should dispatch a team to open decay heat release valve MS-A-162 (refer to Miniscenario 7.2.4). .] 'The' operators may line up the auxiliary charging pump to provide 30 gpm to the' reactor, but this will have little' l
['N.-)/D ' impact.on the overall conditions. 2010 01751 0FF-SITE MONITORING TEAMS' REPORT THAT SITE BOUNDARY DOSE RATES ARE CONTINUING TO INCREASE.
'\
CORE CONDITIONS OVER THE NEXT HOUR WILL CONTINUE TO !
. DETERIORATE AND THE CORE WILL BEGIN TO UNCOVER.
2015 0180 REACTOR CORE EXIT THERMOCOUPLES READ SUPERHEAT. CONTAINMENT RADIOLOGICAL LEVELS AND OFF-SITE DOSES DUE TO THE LEAK IN CONTAINMENT WILL CONTINUE TO INCREASE. The Technical Support Center may undertake the following. actions: 1471e
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; js g ;' 5/18/87 L! j; - Page 5.2-6 .%g Clock _ Scenario-Time Time 2015 0180 o Determination of the time to core uncovery' assuming (Cont'd) 'that no HPSI is avaliable.
o Initiation of containment spray to reduce containment pressure. o' Detennination of additional means to improve decay heat removal. o- Consider reflux core cooling via S/Gs. oD Consider RC pressure reduction options to. initiate
. 'LPSI.
214'5 0270 THE MAINTENANCE TEAM REPAIRING HPSI P14-S REPORTS THAT THE PUMP IS OPERATIONAL.
.2150 0275' Operators should valve in and' start HPSI P14-S returning the HPSI system to service.
i 2155. 0280 CORE EXIT THERMOCOUPLES INDICATE SATURATION TEMPERATURE. ; I 2200 0285 HPSI flow should be decreased to minimum necessary'to maintain subcooling. 2205 0290 CONTAINMENT PRESSURE HAS REDUCED TO LESS THAN 4.0 PSIG. S/Gs at 260 F,-RCS (Incore thermocouples) at approximately 300 F and 10 Subcooled margin. CONTAINMENT RELEASE HAS' ESSENTIALLY STOPPED. O .1471e
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Rev. 1 5/18/87 s Page 5.2-7 v\' i 1 Clock Scenario Time Time 1 2205 0290 0FF-SITE TEAMS REPORT RADIATION DECREASING j (Cont'd) Core Cooling occurring via HPSI through RCS Break and S/G reflux. 2210 0295- The exercise is terminated. 2215 0300 Recovery discussions and actions are initiated. O,.. I i l D), 1471e
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' MAINE YANKEE GRADED EXERCISE JUNE 1987 l
5.3 NARRATIVE
SUMMARY
O 1512e l l
4, Rev. 1 15/18/87 Page 5.'3-1 D-MAINE YANKEE GRADED EXERCISE JUNE 1987
'5.3 NARRATIVE
SUMMARY
;The scenario begins at 1715 with the simulator reactor running at full power for the past 14 months. Charging /HPSI Pump P-14A is out of service for motor repairs and awaiting spare parts. One train of containment spray is inoperable due to stem damage to the spray header isolation valve, CS-M-1. In addition, HPSI Pump P-14S has a failed discharge ' flange gasket which is presently being. repaired. All other plant conditions are normal. 6 At 1725, a Reactor Coolant System leak in containment is indicated on the
- simulator. At 1735, the leak _ rate will incre.ase to approximately 30 gpm. Shortly after, operators will realize the Emergency Action Level-
,i for an Unusual Event has'been exceeded (leakage greater than 10 gpm) and they will classify the conditions accordingly. In conjunction with.the appropriate emergency response notification and coordination actions, the PSS.may also initiate a~ rapid controlled power reduction in order to shut down the reactor in accordance'with A0P 2-10.
At 1803,'the maintenance team, which was working on the containment I personnel hatch inner seal, will report that the outer door may also not be properly sealed. At 1815, vacuum in the condenser is lost which results in a turbine and reactor trip and isolation of the condenser steam dump. At 1820, the RCS leak grows to approximately 200 gpm as indicated on the simulator. Within ten minutes, the operators should recognize that the
) 1512e 4
l Rev. 1 5/18/87 Page 5.3-2 100 gpm RCS leakage EAL has been exceeded and classify an Alert. Shortly after, the containment high pressure alarm (3 psig) is received on the control board. Exact plant conditions will vary depending on operator actions on the simulator. The Technical Support Center (TSC), Operations Support Center (OSC), and Emergency Operations Facility (EOF) should be activated and staffed between 1835 and 1900. Notifications will be made to the State, NRC, MYNSD, and Yankee Nuclear Support Division. The Safety Injection Actuation Signal (SIAS) and Containment Isolation System (CIS) may be initiated manuelly by operators, based on plant conditions or automatically when containment pressure exceeds 5 psig. If containment spray has been previously initiated, a complete flow blockage will occur at 1925. Attempts to initiate containment spray between 1925 and 2100 will be prevented by the failure of CS-M-2 to open. An auxiliary operator or OSC Team may be sent to the Spray Building to investigate. Manual attempts to open the valve are unsuccessful. An OSC Maintenance Team should then be dispatched to the Spray Building. After disassembly of the operator with no damage found, they noticed that the reach rod assembly is bent and bound at a lower elevation. The reach rod must be cut away such that the valve can be manually opened. The valve will not be opened and the Containment Spray System returned to service before 2100. At 1945, the RCS leak grows to approximately 350-400 gpm and significant fuel failure will occur causing containment dose levels to increase rapidly. Also, at 1945, the remaining operational HPSI Pump P-14B will seize. The Maintenance Team working in the area reports that the pump seizure was the result of apparent bearing failure and that repair was unlikely. Shortly after, it will be recognized that the Emergency Action Level for a General Emergency has been exceeded (loss of reactor coolant and failure of HPSI) and classify a General Emergency. By 2000, off-site 1512e
f Rev. 1-5/18/87 E/N Page 5.3-3 monitoring teams' dispatched.to downwind site boundary locations begin to notice increasing radialogical levels. . Dose rates in the personnel hatch area preclude repair activities. LAt'2000, containment pressure will reach 5 psig and containment. isolation. and safety injection actuations will automatically occur, if not L- previously manually actuated. Containment monitor readings are 2 x.10 R/hr.= Operators should reco6nize that the decay heat release valve is-blocked closed by CIS, and an auxiliary operator or OSC Team should be dispatched:to remove the CIS signal. At this time, the operators'may line up the. auxiliary charging pump to provide 30 gpm of reactor. makeup. The HPSI Pump P-14S gasket repair effort continues. Over the next hour, core conditions will continue to deteriorate and containment and off-site doses continue to' increase. Reactor core M thermocouples are indicating superheat conditions. At 2145, the U. Maintenance. Team repairing HPSI Pump P-14S, reports that repairs are complete and the pump is operational. Operators will start the pump and
~
return the HPSI System to service. HPSI flow will be established such as to maintain core subcooling. i At 2205, containment pressure has reduced to less than 4 psig and the containment leakage has essentially stopped. Off-site monitoring teams report.that radiation levels are decreasing. 1 At 2210, the exercise is terminated, followed by the initiation of l recovery discussions. Recovery plans should address continued cooldown and clean-up' activities, containment entry preparations, and methods to locate and isolate the leak. 1512e f
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MAINE YANKEE GRADED EXERCISE JUNE 1987 L 5.4 RADIOLOGICAL DEVELOPMENT O O 1513e
Revision 1 f]. 05/18/87 . N' Page 5.4-1 MAINE YANKEE GRADED EXERCISE JUNE 1987 , 5.4 RADIOLOGICAL DEVELOPMENT This scenario postulates a loss-of-coolant accident within containment. During the first hour the leak is relatively small. Since primary coolant activities are near technical specification levels, the containment monitors begin to see small increases early due to the ; coolant leakage. Results of sample analysis will not be available until after 1940 due to collection and analysis time. When the RCS leak increases to about 400 GPM at approximately 1945, the containment monitor, primary coolant activities, and containment air activities will begin to increase rapidly due to apparent fuel damage due to flow .(q d
! perturbations within the reactor caused by the RCS break, As containment pressure increases, it is postulated at approximately 1950 that containment pressure has increased such as to cause the personnel hatch to leak and off-site releases begin. The release flows ~
through the containment hatch area and into the valve house. The release goes to the environment through either the containment hatch area vent or through the slits in the roof of the alve house. l The environment plume travels directly over the containment and sections of the plant as shown in Section 9.8. In plant monitors that would be affected by the overhead, plume have been altered to indicate the elevated radiological levels due to the plume. Dose rates indicated on in plant survey maps from Section 9.9 also indicate the radiation from the overhead plume. For areas of the plant which are not shown on in plant survey maps and which are not near any radiation monitors shown in I section 9.0, Controllers / Observers may provide radiological information (O) from the on-site monitoring data plume in Section 9.8. For in-plant areas, however, the radiological levels should be reduced in accordance a 1513e l
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with the amount of. shielding offered by the' surrounding walls-or ceiling. .For_ higher. elevations, a good estimate _of in plant' levels
.would be to cut the plume numbers in half. For lower elevations.where there are :several floors of concrete between the. plume and the in-plant areap the plume can be considered negligible or about 1% of the plume ' dose' rate.
Two other areas of the. plant which are affected radiologically are the Spray Building and the HPSI pump cubicle. The Spray' Building elevations i 21and 36! adjacent to the personnel hatch area. increase due'to the large source' term so. nearby. The pump area cubicle has been. contaminated at the beginning of the scenario due to a failed flange. At 2205, containment pressure has reduced to less than 4~psig, and the containment leakage has essentially stopped. ~ 0ff-site monitoring teams L report that radiation levels are decreasing.'
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~ 1513e ~ ... . . . . . . ,
i i MAINE YANKEE GRADED EXERCISE i JUNE.1987
}
t 4 1 4 1 I l j 1 1 5.5 SCENARIO TIMELINE 'f 1 1 d l l
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s t t r o g i a r d n a a P t e t r u e o e e b a e s t 0 p i r r h s l p s a t g g g n e o o e n E 8 i i e s s r i N 1 d e e H s a i s p m I n t p t r e i r L o a i a t o l t t e E e c r r r n w e n S n t M T e r e 4 e l k k m k m 1 m e I T a a r a n a e n - n s
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a S n S f n S n O R i S x A n C e C o C f o P o R R R C R O C H C E N I E C t S 1 1 2 3 4 5 6 7 8 9 0 1 1 1 5 0 5 -;
- I
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.i-l: '..
e ; l i l MAINE YANKEE GRADED EXERCISE JUNE 1987 L. 5.6 DETAILED SEQUENCE OF EVENTS l l'. t J 4 O 1501e
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Page 5.6-1 MAINE YANKEE GRADED EXERCISE- ,
,c, JUNE 1987. </ ,
I
-. j I ' .5.6 -DETAILED SEQUENCE OF EVENTS Scenario
- T Clock- Time
. Time (Minutes) Event Message Command 7
, ~1715 0 EXPECTED CONTROL ROOM (CR) ACTIONS. WILL BE IMPLEMENTED BY AN EXERCISE , OPERATIONS CREW LOCATED IN THE SIMULATOR COMPLEX IN THE STAFF BUILDING.
"/
OPERATIONAL CONTROL ROOM DATA WILL BE PROVIDED BY THE SIMULATOR
/ INSTRUMENTATION RESPONSES. IN CASES .WHERE SPECIFIC INFORMATION NOT MONITORED BY THE SIMULATOR IS ,
REQUIRED, IT WILL BE. ISSUED BY OBSERVERS ON MESSAGE CARDS. IN THE EVENT THAT A SIMULATOR MALFUNCTION OCCURS THE EXERCISE WILL BE-CONDUCTED USING MESSAGE CARD INFORMATION DEVELOPED FROM SECTION 8.0. j The CR Observer issues Initial CR-M-1 CR-C-1-' Conditions to simulator CR players.
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Scenario-Clock Time Time (Minutes) Event Message Command 1715 0 Initiating messages are also provided TSC-M-1 to all emerCency centers and facility OSC-M-1 J / Cont'd) j staffs upon subsequent activations. EOF-M-1 EOF-C-1 OPERATION L AND RADIOLOGICAL DATA Security-M-1 WILL BE AVAILABLE IN THE TSC AND EOF MEEOC-M-1 OVER THE SPDS LINKS TO THE SIMULATOR. ESC-M-1 Security will be provided a list of. PI-M-1 controllers / observers who will not EOF-M-2 have to be accounted for during the TSC-M-2 exercise. A maintenance team shall be prepositioned in the maintenance
* ,,,;1 office and a team of HP technicians in the PAB (refer to Miniscenarios 7.2.1(a) and (b)).
Initiating messegos shall be provided to each team. 1725 10 AN RCS LEAK OF 5 GPM OCCURS. 1730 15 RCS leakage in containment should be evident to operators as indicated by:
- 1. Radiation Monitoring System (RMS) increase.
- 2. Volume Control Tank (VCT) level I decrease.
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s 4 v iRevision 1~ 05/18/87, 73 g. Page 5.6-3 e.
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M . Scenario 2 k . Clock . Time 1- l Time '. (Minutes ) . ' Event' Message Command 1730 L15= 3. Loop 2 containment-smoke detector.
.(Cont'd).
- (heat sensor) alarm. -1: ,
j
.4., Containment sump:. level; increase. '5.' Containment.' Air Particulate ~
Detector (APD) increase.-
, l I
Meteorological forecast will be- CR-M-2--
-l available to EOF,:CT, TSC, MEE00,. EOF-M-3 l !and ESC.upon request.' ',TSC-M ] . ESC-M-2 l #,-vk '
MEE00-M-la i
'Q .;
l
.FOR EXERCISE PURPOSES, CONTAINMENT ,
i RADIATION MONITOR READINGS WILL BE. j AVAILABLE UPON REQUEST FROM THE-CONTROL ROOM..TSC, AND EOF OBSERVERS. CONTROL BOARD AND SPDS INDICATIONS- ! FOR CONTAINMENT RADIATION FROM'THE
-SIMULATOR SHOULD BE IGNORED.
I 1733 18 operators should notify the maintenance .; crew working on the personnel hatch of increased radiation levels and possible leakage. Operators recommend . an-immediate evacuation of containment. l I l D :1501e
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-[,a gT Page 5.6-4~ j - \, , -1 Scenario' )
Clock Time J Time (Minutes) Event Message Command' L1735 20 THE RCS LEAK-RATE INCREASES TO APPROXIMATELY 30 GPM. This increased leakage is~ indicated by changes in containment sump. level and charging / letdown flow mismatch. FOR EXERCISE PURPOSES, ANY ATTEMPT TO ESCALATE THE EMERGENCY CLASS.TO ALERT WILL BE CONTROLLED' VERBALLY BY THE FACILITY CONTROLLERS UNTIL 1820.
'1736 21. Operators should commence a rapid controlled power reduction to shut down Sr"'C the reactor in accordance with .t 's--) AOP 2-10 and in compliance.with. Technical . Specifications 3.0.A and 3.14.
1745 30 Operators should declare an Unusual Event based upon reactor coolant system leakage to containment in
. excess of 10 gpm in accordance with l Procedure 2.50.0, " Declaration and Categorization.of Emergency-Conditions." Operators may decide to . trip the plant.
Operators may implement Procedure E0P 2-70-2,
" Loss-of-Coolant-Accident."
1501e- ] f
e Revision 1 fm 05/18/87 t ) Page 5.6-5 v Scenario Clock Time Time (Minutes) Event Message Command 1745 Operators may dispatch auxiliary (Cont'd) operators to perform in-station tasks associated with normal sbutdown procedures. FOR EXERCISE PURPOSES, CR-C-4 IN-STATION A0 RESPONSES FROM THE CR SHALL BE SIMULATED. Simulator Staff should initiate Procedure 2.50.1, " Notification of Unusual Event." 30 THE CONTROL ROOM CONTROLLER SHOULD CR-C-5 DIRECT THE PSS TO CONTACT THE ACTUAL CONTROL ROOM AND REQUEST INITIAL ACTIVATION OF THE PLANT EVACUATION ALARM AND NOTIFICATION OF THE NRC VIA THE RED TELEPHONE (ENS) THAT THE EXERCISE HAS STARTED AND AN UNUSUAL EVENT HAS BEEN DECLARED. PSS should instruct CR Staff to announce message in Appendix A.3.b of l Procedure 2.50.1 over the plant page (FEMCO) which should direct personnel to continue what they are doing. 1 PSS should notify Maine State Police (' (Procedure 2.50.17) and provide
'k message in Appendix A.4.b of j Procedure 2.50.1 over the plant page.
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1. Revision 1-05/18/87' Page 5.6-6 Clock : Time LTime' (Minut's)- e Event Message Command 1745' ' Shift' Engineer'(SE) should report to (Cont'd) the CR'and review the. incident classification with the PSS and confirm. PSS should notify the Duty Call l Officer per Procedure 2.50.17, j Appendix A.2. l
- 30. After n'otifying the Plant Manager,- i the Duty Call' Officer may elect to report to the Control Room ~and assume j the role of Emergency Coordinator.
10-The PSS should transfer the responsibility.of the' Emergency Coordinator's role to the Duty Call Officer when he arrives. The PSS should brief the Duty Call Officer / Emergency Coordinator on plant conditions, emergency class I declaration, and initial message.- The Emergency Coordinator in concert , s with the PSS may elect to direct a j precautionary evacuation of visitors t 1 and contractors to the Staff Building. i , 1501e >
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Scenario
. Clock ; Time.. .
Time -(Minutes)- Event Message . Command.
~
1745' If personnel are to be evacuated, then
.(Cont'd) . Security will'be directed to dispatch officers to.the Staff Building to coordinate accountability of visitors and contractors.-
PSS or designate should notify the Central Maine Power ~(CMP) dispatcher. 30 NSE should notify Maine Yankee Nuclear Services Division Staff per Procedure 2.50.17,'" Emergency Notification."
}~{ . PSS should assign a CR Staff member .Q to maintain a log of events.
Upon notification of an Unusual Event, the Maine Yankee Public Affairs Director (PAD) will implement Procedure 2.50.15, " Release of.Public Information During Emergencies", and receive the facts and significance of the Unusual Event from the plant or senior management of Maine Yankee to determine the need for a press release. ti J J J(}
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1 Revision'1 05/18/87' Page 5.6-8.- j- . Scenario (bj . ~ Clock Time Time' . (Minutes). Event'. Message- Command.
.1745 The PAD will prepare any necessary press (Cont'd) releases lconcerning the nature of the Unusual Event declaration. Approval of press releases will'be obtained from the' Maine Yankee Manager.of Public-Affairs and the Executive Vice President or Manager of. Operations, if practicable.
Before issuing any necessary press releases concerning the Unusual Event, the PAD will coordinate with the Maine Division of. Health Engineering Director and the Governor's Press Secretary, if possible. -fN. ' 30 PLAYING OF ALL THE PRERECORDED EMERGENCY PI-C-1 MESSAGE TAPES ON THE PUBLIC INFORMATION TELEPHONE WILL BE SIMULATED BY THE
. SECURITY OFFICER THROUGHOUT THE EXERCISE. -Containment entry preparations may be CR-C-6 initiated to identify the source of OSC-C-1 RCS leakage. ANY ATTEMPTS TO ENTER CONTAINMENT SHALL BE SIMULATED. . Security should implement the applicable section of Procedure 2.50.9,." Security Force Radiation Emergency Plan."'
The gatehouse attendant should develop a list of contractor / visitor l personnel on-site. 1501e-I
Revision 1 ["'j 05/18/87 V .Page 5.6-9 Scenario Clock Time Time (Minutes) Event- Message Command l 1745 The PSS should take action on any (Cont'd) unaccounted for personnel. 1 SECURITY CONTROLLER WILL ISS~UE SEC-C-1 SECURITY COMMAND CARD 2 TO THE SECURITY CAPTAIN INSTRUCTING HIM TO SIMULATE THE PLAYING OF ALL PRERECORDED EMERGENCY MESSAGE TAPES ON THE PUBLIC INFORMATION TELEPHONE THROUGHOUT THE EXERCISE. 1753 38 The containment high range RMS alarm is
) received.
1800 45 IF AN UNUSUAL EVENT HAS NOT BEEN CR-C-7 DECLARED BY THE PSS, HE WILL BE DIRECTED TO DO SO AT THIS TIME. 1803 48 THE MAINTENANCE CREW WORKING ON THE CR-M-3 CONTAINMENT HATCH REPORTS THAT IN THEIR HASTE TO EXIT THE PERSONNEL HATCH THEY BELIEVE THE OUTER DOOR SEAL MAY HAVE BEEN DAMAGED. REPAIRS TO THE INNER DOOR SEALS HAD NOT BEEN COMPLETED (see Miniscenario 7.2.2). 1815 60 VACUUM IN THE CONDENSER IS LOST DUE TO LOSS OF THE TURBINE GLAND SEAL STEAM LINE. i
,s LOSS-OF-VACUUM CAUSES A TURBINE TRIP, A REACTOR TRIP, AND ISOLATION OF CONDENSER l STEAM DUMP. S/G SAFETY VALVES LIFT.
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Scenailo Clock- Time Time '(Minutes)~ Event Message Command
- 1817 62 Operators should open the decay heat release valve to effect a cooldown.
The PSS may instruct-the HP Department to.take an RCS sample and ' a secondary coolant sample for
-isotopic analysis of iodine activity in accordance with A0P.2-25, "High' Radiaticin Levels."
f 1820 65 THE RCS LEAK RATE INCREASES TO 200 GPM (WHICH IS THE MAXIMUM
/N CAPACITY OF THE CHARGING PUMP).
T Operators should recognize major leakage is occurring probably greater than 100 gpm by charging flow increase and drop in pressurizer level and declare an ALERT in accordance with Procedure 2.50.0. 1833 78 AN ALERT IS DECLARED DUE TO RCS LEAK RATE EXCEEDING 100 GPM. IF NECESSARY, CR-C-8 THE PSS WILL BE DIRECTED TO DO S0. i Upon notification of the Alert status, the PAD and the Maine Yankee Technical Representative (TRS) will report to the State Emergency Operations Center (E00), Bureau of Civil Emergency
,D Preparedness Offices, located at the State Office Building.
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; Page 5.6-11 k L.- ; Scenario Clock Time- .T!me _1(M N *er) - a Event Message Command W-
. x. , 1833;. If it is determined that a press
- (Cena ' d) ~ release is 1ecessary prior to reporting i to'the Stati E00, the PAD will follow .the steps outlined.above to prepare and obtain approval for press releaser.-
78 Upon arriyol at the EOC, the PAD and TRS will cc gdinate all media
' communications and new releases with the Governor's Press Secretary. The Governor's Press Secretary will be the single contact for communicating with the news media and issuing press releases.
The PAD and TRS will remain in contact with the Maine Yankee Emergency Coordinator (EC)' located at the Emergency Operations Facility (E0F) for information concerning plan status updates and other pertinent facts to assist in the development of news i and media' press releases. ; The PAD and TRS will assist the . I Governor's Press Secretary in the . l preparatio'n.of news releases and j conducting media briefings, as needed. l (Media briefings will be conducted j at the Governor's Cabinet C Room.) 1501e 3 l
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' Scenario 'Q~- ^
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~T ime- '(Minutes) Event Message Command 1833 The PAD may. activate the' Central Maine-l(Cont 'd ) : : Power Public and Employee Communication
- Department.to assist.in providing 4information or. logistical support.-
78 The PAD wil1~also coordinate with' State Rumor Control-personnel to assist in-
-controlling any. rumors or erroneous.
- public information.
L The' PAD and TRS will. continue to' provide support.and pertinent-information to the State for news
-releases and rumor control throughout 'N , the exercise.-
(f All operational and radiological data ~ normally available in the EOF and TSC via the Safety Parameter Display System-will be available. Operators should initiate Procedure 2.50.2, " Alert." The PSS should instruct personnel to sound the evacuation alarm and make announcement on the FEMCO (plant page). ! I NOTE: THE EVACUATION ALARM AND FEMC0
. ANN 0UNCEMENT SHOULD BE REQUESTED OF THE ACTUAL CR STAFF. , 1501e -
i Revision'1 F 05/18/87 Page 5.6-13 . l[
%, _ _ Scenario Clock Time' , ' Time (Minutes)- Event Message Command i 1833 _78 : All'off-site notification (Cont'd) responsibility, except the Maine State , Police contact, will be directed by= .the Emergency Coordinator who would-report ^to the EOF.to initiate its actisation.'
PSS should activate pager notification in accordance with Procedure 2.50.17.
,PSS should notify Maine State Police
- in accordance with Procedure 2.50.2.
,F/},,N ..
NSE should activate the Yankee Nuclear-Services Division (YNSD) pager system in accordance with Procedure 2.50.17.. NSE should-notify the'NRC of transition status. NSE should initiate manual call-up of Maine Yankee NSD personnel. The containment high pressure alarm is received (approximately 3 psig). OPERATORS SHOULD SWAP CHARGING PUMP SUCTION TO RWST DUE TO LOW VCT ; LEVEL OR INITIATE HPSI. 1501e
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Scenario Clock Time Time (Minutes) Event Message Command NOTE - Exact plant conditions may vary depending on actual operator actions. 1835 80 AT APPROXIMATELY THIS TIME, CHARGING PUMP SUCTION WILL AUTO SWITCH TO RWST ON LOW VCT LEVEL. 1845 90 ACTIVATION OF THE PEAS SHALL BE ME0C-C-1 SIMULATED FOR THIS EXERCISE. Emergency response facilities (TSC, ($ t OSC, EOF) should be staffed in accordance with E0P 2.50.2. The State EOC should be activated. Local community EOCs should be activated. The first member arriving at the TSC location would establish voice communications with the Control Room (CR) and document the reported event history and current plant status. TSC Staff representing the following I departments should assemble at the j TSC following the declaration of j an " Alert": ! (~'\' 1. Operations Department l '\_/ 1501e I I a
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Page.5.6-15_ Scenario LClocks . Time: Time" '(Minutes), , Event Message Command 1
- 18451 90 2. Reactor Eng'ineering
(:"
.(Cont'd)
- 3. Instrumentation and Control
- 4. Chemistry s
- 5. Computer 6.-Plant Engineering
- 7. Radiological-Controls (Specialist)
- 8. Nuclear _ Safety-95 Maintenance The TSC' Coordinator should implement Procedure 2.50.19 " Technical Support -
' Center."
The CR should provide a plant status
-report to the'TSC.
The Emergency Coordinator may report to the EOF, establish communications with the Control Room,'and coordinate manpower needs and off-site communications from this location. h --
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Clock- . Time ~ -
, LTime '(Minutes) Event Message Command 11845 90 The EmergencyICoordinator (EC) should -(Cont'd)- alert Security as to appropriate -access control measures'if a decision is = made to. evacitate visitors.
The PSS and EC should discuss I emergency level and classification. e The Emergency Coordinator shduld { assume the responsibility for l off-site notifications. se The' Emergency Coordinator.would-coordinate HP response in support.of the PSS. As personnel arrive in the EOF, the Emergency Coordinator will brief them and staff the following positions: 1.-Coordinator's Assistant
- 2. Communication's Assistant-
- 3. Radiological Evaluation Assistant
- 4. Manpower and Planning Assistant i
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Time (Minutes) Event Message Command l I l 1845 90 The Radiological Data Evaluator (RDE) { (Cont'd) may request that a PVS and RCS sample ) be taken. I l The RDE should perform off-site dose assessment calculations. l ANY RECOMMENDED ADMINISTRATION OF CR-C-9 l KI FOR THE EXERCISE SHALL BE OSC-C-2 SIMULATED. EOF-C-2 TSC-C-1 l I l
,-g 't V) 1920 125 AN EOF OBSERVER SHOULD BE ASSIGNED TO EACH OFF-SITE MONITORING TEAM DISPATCHED. EACH EOF OBSERVER WILL ISSUE DOSE RATES AND AIR SAMPLE RESULTS AT SPECIFIC DOWNWIND LOCATIONS AS PROVIDED FROM SECTION 9.0.
ACTIVATION OF THE EMERGENCY VENTILATION TSC-C-2 SYSTEM SHALL BE SIMULATED FOR THIS l EXERCISE. i Staff Building habitability should be determined. AN OSC OR E0F OBSERVER WILL ISSUE HABITABILITY DATA "AS READ". s
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\ '- Scenario Clock Time Time (Minutes) Event Message Command 1920 125 Radiological access'and control (Cont'd) measures should be established for the Staff Building. The Communication's Assistant should establish communications with other emergency facilities and teams.
Status boards should'be maintained. AS METEOROLOGICAL DATA OR WEATHER FORECAST IS ACCESSED BY THE EOF STAFF DURING THE EXERCISE, THE EOF OBSERVER WILL PROVIDE THE NECESSARY INFORMATION FROM INFORMATION FROM
,s, i i SECTION 10.0. \~/
TSC should review primary safety parameters and calculate leak rates. The TSC Coordinator would review and aid in coordinating in-plant { activities with the Plant Shift Superintendent (PSS), Shift Engineer l l (SE), and/or the Operations Department Head (if on-site) relative to bringing I the plant to a safe condition.
/T
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.- . Revision 1 ,!,.,Y. 05/18/87 D Page 5.6-19 Scenario-Clock Time ' Time- (Minutes) -Event Message Command 1920 125- Communications should be established with' '(Cont'd) the EOF to determine if the habitability of the Staff Building Emergency Center has been determined and if'the State is .
being informed of the situation. I ~ TSC accountability should.be performed once the TSC is. operational. j
-TSC-Staff should' commence assessing I . plant status, coordinate the y preparation, review, and approval of any special procedures required for .the mitigation of the emergency.
The TSC Coordinator should contact the OSC Coordinator to ensure corrective actions are being taken in accordance with the proposed plan to mitigate the consequences.of the ! emergency. ]
. ) .The TSC Coordinator should direct TSC-C-2 i activation of the TSC/ EOF Emergency Ventilation System. ACTIVATION OF THE EMERGENCY VENTILATION SYSTEM, HOWEVER, SHALL BE SIMULATED. l O
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' Clock . Time Time' (Minutes) ' Event ~ Message Command l .o ~
L1920 '125 The'TSC Coordinator should direct
.(Cont'd) completion of Form 1, " Plant Status "
Part I, which is used to update State CEP on plant conditions and send Form 1 to,the Radiological Evaluation Assistant (REA) for completion ] of.Part.II.
.The TSC' Coordinator should determine ~
the.present'and' potential release d conditions from the PSS.and fill'out ! Form 2, " Release Data," having a-
. ~ Communications Aide (CA) copy and . (] distribute.
l The TSC Coordinator should notify the EC, using the telephone or Channel 2 of the plant paging system, when in-plant operational changes could change in-plant and/or off-site radiological conditions, particularly changes in the PVS and meteorological conditions. i l The TSC Coordinator should receive plant status update from the PSS. I i Q O 1501e-i i i I
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Scenario
- Clock-- Time':
Time (MinutesJ Event - Message Command-1920.' :125 The.TSC Coordinator should assume the~- (Cont'd): . responsibility for maintaining open- j communications-with the NRC'(red. ,
, -telephone)..
The'TSC Coordin'ator should contact-the-EOF and request a Communications
-Aide to log events and take telephone calls.
The TSC' Coordinator should assign one person to be responsible-for
'/9. 4 maintaining the TSC status board.
V. OSC Staff representing the'following departments should assemble at the OSC following declaration of-an
" Alert:"
- 1. Operations
- 2. Chemistry
- 3. Radiological Controls i
The responding Supervisor'(i.e., . Maintenance Section Head or PSS) assumes the position of OSC Coordinator. o 1501e l
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Page 5.6-22 Scenario
- Clock Time-Time -(Minutes)-' Event Message ~ Command 1920 125 OSC Coordinator should implement 2(Cont'd) Procedure'2.50.18, " Operations Support Center."
Communications should'be established with~the Control Room (CR), TSC, and EOF. - OSC accountability should be performed..
'The OSC Coordinator should assign a lh. person to maintain the in-plant radiation level status board.
A Communications Aide should be requested f rom the EOF to maintain a center log. 1 l The OSC Coordinator should check with l the Emergency Coordinator to verify J i that Staff Building habitability has ] been determined. I AS HABITABILITY IS EVALUATED DURING THIS EXERCISE, THE OSC OBSERVER WILL PROVIDE INFORMATION AS NECESSARY. I
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Revision 1 05/18/87 gg Page 5.6-23 s U'J - Scenario Clock Time Time (Minutes) Event Message Command 1920 125 The TSC Coordinator should contact (Cont'd) the 0SC Coordinator to request team , preparation for radiological surveys and/or corrective action missions. The Plant Assistance team (s) dispatched from the OSC, proceed to the HP Control Point and quickly assemble any additional protective equipment or survey meters that may be needed. Security Staff should implement the
) section of Procedure 2.50.9 applicable to Alert.
Security should verify site evacuation and response to emergency centers by the response organization. Any unaccounted for personnel should be reported to the Security Captain who will inform the Emergency Coordinator. (_,/ 1501e
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( ). Page 5.6-24 l Scenario Clock Time Time (Minutes) Event Message Command , 1 1925 130 IF CONTAINMENT SPRAY HAS PREVIOUSLY l BEEN INITIATED, AN UNKNOWN COMPLETE l FLOW BLOCKAGE WILL OCCUR AT THIS TIME. WHILE IF THE DECISION TO INITIATE CONTAINMENT SPRAY IS MADE BETWEEN NOW AND 2100, VALVE CS-M-2 WILL FAIL TO I l OPEN. AN AUXILIARY OPERATOR OR l MAINTENANCE TEAM WILL BE SENT TO INVESTIGATE (refer to Miniscenario 7.2.3). ' t NOTE: IF THE OPERABILITY OF THE CONTAINMENT SPRAY SYSTEM IS IDENTIFIED, [ A GENERAL EMERGENCY SHOULD BE DECLARED DUE TO LOSS OF REACTOR COOLANT AND LOSS OF ALL CONTAINMENT SPRAY CAPABILITY. 1940 145 The Emergency Coordinator should check for any of the unaccounted for personnel in the TSC, OSC, and EOF and, if necessary, dispatch rescue t. t- personnel. f O 1501e
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-S 05/18/87 l t i Page 5.6-25 LJ Scenario Clock Time Time (Minutes) Event Message Command 1940 145 The Security Captain should assign (Cont'd) four officers to control access to the Staff Building (EOF, TSC, OSC) as !
follows:
- 1. One on the road;
- 2. One in the parking lot;
- 3. One at the Staff Building l entrance; and
/'~'i 4. One at the tunnel entrance.
v' The OSC Coordinator would assist the E0F in monitoring personnel exposure and keeping the exposure within the limits provided in Procedure 2.50.14
" Emergency Radiation Exposure Control."
The Radiological Data Evaluator (RDE) may request that a containment air and RCS sample be taken, l 1945 150 THE RCS LEAK WORSENS TO ABOUT 350-400 GPM. AT THIS TIME SIGNIFICANT FUEL FAILURE OCCURS RESULTING IN RAPIDLY INCREASING ' [N CONTAINMENT DOSE LEVELS. . 1501e
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,, I Revision 1 05/18/87 ,(m 4
Page 5.6-26 Scenario ! I Clock Time Time '(Minutes) Event Message Command. l 1945- 150- THE REMAINING HPSI PUMPi P14-B,.WILL i
. SEIZE (see Miniscenario~7.2.1(c)). OSC-M-2 A GENERAL EMERGENCY should be declared due 1 1
to loss-of-reactor-coolant and failure of i I HPSI following loss-of-coolant (failure to f provide adequate overpressure for core to secondary side heat transport). L l. 1950 ~' 155 ' CONTAINMENT MONITOR READS 20,000 (R/hr). Off-site monitoring teams.should have ;
,C ' been dispatched to downwind site boundary locations. .Small increases in'off-site i
monitoring'results are reported due to a q 1eak in containment through the hatch and small' increases in containment radiological l
' levels. -
2000 165 CONTAINMENT ISOLATION AND SAFETY INJECTION ACTUATION OCCUR AS CONTAINMENT PRESSURE l EXCEEDS 5.0 PSIG. (IF NOT ALREADY MANUALLY ACTUATED) CONTAINMENT MONITOR READS 23,000 (R/hr.). 1 FOLLOWING CI THE DECAY HEAT RELEASE VALVE, MS-A-162. CANNOT BE USED FROM THE CONTROL ROO_M FOR DECAY HEAT REMOVAL UNTIL CIS SIGNAL IS BLOCKED. 1501e l l
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.Revis' ion l' 05/18/87- .;
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Page 5.6-27 _ Scenario ClockL . Time
. Time: '(Minutes) Event Message' Command 20007 :165L -Operators should dispatch a' team to ~
(Cont'd)' open. Decay Heat Release Valve MS-A-162 (see Miniscenario 7.2.3). . The' operators may'line upythe auxiliary charging pump-to provide 30 gpm to the reactor, but this will have little. impact on'the overa11' conditions.
-2010< .175" :0FF-SITE MONITORING TEAMS REPORT THAT SITE BOUNDARY DOSE-RATES ARE CONTINUING TO -INCREASE.
CORE' CONDITIONS.0VER THE.NEXT HOUR WILL CONTINUE.TO. DETERIORATE AND THE CORE WILL BEGIN T0 UNCOVER.
'2015 180 REACTOR VESSEL LEVEL CORE EXIT.THERMOCOUPLES READ SUPERHEAT.
INCREASING CONTAINMENT RADIOLOGICAL LEVELS AND OFF-SITE DOSES DUE TO THE-LEAK IN CONTAINMENT WILL CONTINUE TO INCREASE.
'I The Technical Support Center may 1 undertake the following actions:
o Determination of the time to core uncovery assuming that no HPSI is s /~ available. i 1501.0-
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Revision 1-05/18/87 Page 5.6-28 Clock. Time Time -(Minutes) Event Message Command
- .! L 201' 5 ' 180' o I'nitiation of containment _ spray to (Cont'd) reduce containment pressure.
- o. Determination of' additional means to improve decay heat removal.-
o: Consider reflux core cooling via SGs. o Consider RC pressure reduction options to initiate LPSI. 2100 o Valve CS-M-2 is repaired and is OSC-M-3 g operational. d 2145 270- THE MAINTENANCE TEAM REPAIRING OSC-M-4 HPSI P14-S IS TOLD THAT THE PUMP IS OPERATIONAL. 2150- 275 Operators should valve in and start HPSI P14-S returning'the HPSI System to service. 2155 280- . CORE EXIT THERMOCOUPLES INDICATE SATURATION TEMPERATURE.
~
2200 285 HPSI flow should be decreased to-minimum necessary to maintain subcooling. 5 1501'e l-t 1 I I i
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! 05/18/87 , -J'~i Page 5.6-29 Scenario Clock Time -Time' (Minutes) Event- Message Command .2205 290 -CONTAINMENT PRESSURE HAS REDUCED TO LESS THAN 4.0 PSIG, Containment release has essentially-stopped..
SGs.AT.260 F. RCS (incore thermocouples) at approximately 300 F, and 10 Subcooled margin. Core cooling' occurring via HPSI through RCS break and SG reflux. O .OFF-SITE TEAMS REPORT RADIATION DECREASING. 2210 295 The exercise is terminated. 2215 _300 Recovery discussions and actions are initiated. s O 1501e t
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) . MAINE YNAKEE GRADED EXERCISE ' JUNE 1987 9 6'.1 EVENT MESSAGES I
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MAINE YANKEE Rev. O GRADED EXERCISE 4/9/87 JUNE 1987 Page 6.1-1 SCENARIO MESSAGE FORM FROM: C ntr 1 Room Observer MESSAGE NO. CR-M-1 Plant Shift Superintendent CLOCK TIME: 1 15 TO: Simulator Control Room 0 min. LOCATION: SCENARIO TIME: PARTICIPANT' MESSAGE
**** THIS IS A DRILL ****
5.1 INITIAL COh*DITIONS AT 171$ 1 The reactor has been operating at full power for the last fourteen ,mc months and is nearing the end of core life. 1 ( ,/ 2. The reactor is operating at! 2610 Nit { 888 Ka'e s 576 Ta ve (*II 2235 Pressuriser Pressure (psig) 58 Pressuriser Level (1)
- 3. The latest reactor coolant analysis completed and verified l>y Chemistry indicates 0.9 uC1/g dose equivalent 1-131 (at Technical Specification limit) and 8.0 uC1/g noble gas.
6 BPS! Pump P-16-A is out of cornission for motor repairs and is awaiting spare parts. When operators attempted to valve in the spare BPSI Pump. P-14-S. at 1635 hours today, a flange gasket failure occurred, rendering the purp inoperable. The necessary paperwork to perform the replacement are being prepared including the stores . requisition for the new gasket. (Refer to Miniscenario 7.2.1(a).) The immediate area around the charging pumps is experiencing elevated dose rates of 300 (mR/hr) and contamination surveys in the area are indicated as 100.000 (dpm/rn?). The area has been roped off and marked in accordance with HP Procedure 9.1.6. " Establishing and Posting Controlled Areas." Decontamination ef f orts have been initiated. (Refer to Miniscenario 7.2.l(b).)
- 5. Containment personnel hatch inner door failed an 0-ring test at 1545. A maintenance crew is replacing the 0-rings.
- 6. Yesterday, at 1805. while performing routine maintenance on valve CS-M-1, damage to the valve stem was f ound which most likely occurred during last closure as a result of torque switch f ailure. The valve was declared inoperable and the remedial action of Technical (N
- Specification 3.6 is invoked. A new stem is expected on-site by 2000 }
'n today. J ( **** THIS IS A DRILL ****
. i, c ;:o MAINE YANKEE Rev. 0- < GRADED EXERCISE 4/9/87 l . JUNE .1987 Page 6.1-2 SCENARIO COMMA!H) FORM .. Control Room Controller COMMAND NO.
CR-C-1 Plant _ Shift Superintendent CLOCK TIME: 1715 imu at r Control. Room SCENARIO TIME. O min LOCATION: PARTICIPANT MESSAGE
****- THIS IS A DRILL ****
ACTIVATION OF Tile PEAS SHALL-BE SIMULATED. O j. m
.^ .l '**** THIS IS A DRILL **** ' k .{. .i
4.1 1 1 h V ~NAINE YANKEE- Rev. O j GRADED EXERCISE 4/9/87 j [ JUNE 1987 Page 6.I- 3 SCENARI0' MESSAGE FORM
. Te'chnical Support Center Observer TSC-M-1 FROM: MESSAGE NO. .j TO:
TSC Coordinator CLOCK TIME: U P on Activation
. LOCATION:-
Technical Support. Center SCENARIO TIME: PARTICIPANT- MESSAGE
**** THIS IS A DRILL' ****
5.1' INITIAL,CONDIT10NS' At m $ . l- 1. The reactor has been operating at f ull power f or the'last fourteen I
- p- months and is nearing the end of core life. , ]
- 2. The reactor is operating at:
2610 MWt I s 888 K4e I 576 Tay, ('F) 2235 Pressuriser Pressure (psig)
.58 Pressuriser Level (1) -3. The latest reactor coolant analysis completed and verified by Chemistry indicates 0.9 uCi/g dose equivalent I-131 (at Technical '
Specification limit) and 8.0 uC1/g noble gas. 4 BPS! Pump P-14-A is out of coenission for motor repairs as.o is awaiting spare parts. When operators attempted to valve in the spare BPS 1 Pump, P-14-S. at 1635 hours today, a flange gasket failure occurred, rendering the pump inoperable. The necessary paperwork to perform the replacement are being prepared including the stores requisition for the new gasket. Otefer to Min! scenario 7.2.1(a).) The lanediate area around the charging pumps is experiencing elevated dose rates of 300 (sJt/hr) and contamination surveys in the area are indicated as 100.000 (dpm/m2). The area has been roped ofI and marked in accordance with HP Procedure 9.1.6, " Establishing and Posting Controlled Areas." Decontamination efforts have been initiated. (Refer to Miniscenario 7.2.l(b).)
- 5. Containment personnel hatch inner door failed an 0-ring test at 1545. A maintenance crew is replacing the 0-rings.
- 6. Yesterday, at 1805, while performing routine maintenance on valve CS-N-1, damage to'the valve stem was found whlet most likely occurred s during last closure as a result of torque switch f ailure. The valve f was declared inoperable and the remedial action of Technical i Specification 3.6 is invoked. A new stem is expected on-site by 2000
( today. i **** THIS IS A DRILL **** 1
Qm
} 'f b MAINE- YANKEE- Rev. O <, GRADED EXERCISE 4/9/87 , ' JUNE 1987 . Page 6.1-4 i/
SCENARIO MESSAGE -FORM
. Operations Support Center Observer MESSAGE NO. -"~
FROM: TO:
' OSC ' Coordinator'~ CLOCK TIME:
U P on Activation LOCATION: Operations Support Center SCENARIO TIME: PARTICIPANT MESSAGE
**** THIS IS A DRILL **** ).1 . INITIAL C0ht!TIONS . AT 1715
- 1. The reactor has been operating at full power for.the last fourteen months and is nearing the end of core life,
~
t 2. The reactor la operating ats (_./ 200 MWt 888 MWe 576 T ve' ('F) 2235 Pressurizer Pressure (psig) 58 Pressuriser Level (1)-
- 3. The latest reactor coolant analysis completed and verified by Chemistry indicates 0.9 uct/s dose equivalent 1-131 (at Technical Specification limit) and 8.0 uCi/g noble gas.
.4. EPSI Pump P-14-A is out of comission for motor repaire and la awaiting spare parts. When operators attempted to valve in the spare BPSI Pump, P-16-S, at 1635 hours today, a flange gasket failure occurred, rendering the pump inoperable.' The necessary paperwork to perform the replacement'are being prepared including the stores requisition for the new gasket. (Refer to Miniscenario 7.2.1(a).) . The issuediate area around the charging pumps la experiencing elevated dose rates of 300 (mR/hr) and contamination surveys in the area are indicated as 100.000 (dpm/m2). The area has been roped off and marked in accordance with itP Procedure 9.1.6 " Establishing and Posting Controlled Areas." Decontamination ef f orts have been initiated. '(Refer to Miniscenario 7.2.1(b).)
- 5. Containment personnel hatch inner door failed an 0-ring test at
'1545. A maintenance crew is replacing the 0-rings, 6~ Yesterday, at 1805, while performing routine maintenance on valve CS-N-1, damage to the valve stem was found which most likely occurred during last closure as a result of torque switch failure. The valve was declared-inoperable and the remedial action of Technical y Specification 3.6 is invoked. A new stem is expected on-site by 2000 l today. -b '(' **** THIS IS A DRILL ****
i
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?
k: m 1 MAINE _ YANKEE Rev. 0-(~) GRADED EXERCISE 4/9/87 Page.6.1-5 j JUNE 1987 l SCENARIO -MESSACE FORM
~
MOM Emergency Operations Facility ObservebSSAGE NO. EOF-M-1 TO: Emergency Coordinator CLOCK TIME: U P on Activation LOCATION:. Emergency Operations Facility SCENARIO TIME: , i PARTICIPANT' MESSAGE
**** THIS IS A DRILL **** . 5.1 INITIAL CONDITIONS AT 1715
- 1. The reactor has been operating at full power for the last fourteen sooths and is nearing the end of core life.
'{ .
- 2. The reactor'is operating"ati
.(( ,
2610 MWt-B88 MWe-
- 576 Teve ('F) 2235 Pressuriser Pressure (psig).
58 Pressuriser level (1)
- 3. The latest reactor coolant anstysis completed and verified by
- Chemistry indicates 0.9 uti/g dose equivalent I-131-(at Technical Specification limit) and 8.0 uC1/g noble gas. ~
- 4. 'BPSI Fump P-14-A is out of connission for setor repairs and is awaiting spare parts. L?.cn operators attempted to valve in the spare BPSI Pump P-14-3, at 1635 hours today, a flange gasket failure occurred, rer4ering the pump inoperable. The necessary paperwork to 7 perfor1r the replacenent are being prepared including the stores requisiticn fa. the new gasket. (Refer to Miniscenario 7.2.1(a).)
The inmediate area around the charging putnps is experiencing elevated dose rates of 300 (eS/hr) and contamination surveys in the area are indicated as 100,000 (dpm/m2). The area has been roped off and marked in accordance with HP Procedure 9.1.6, " Establishing and Posting Controlled Areas." Decontamination efforts have been initiated. (Refer to Miniscenario 7.2.1(b).)
- 5. Containment personnel hatch inner door failed an 0-ring test at 1545. A maintenance crew is replacing the 0-rings.
- 6. Yesterday, at 1805, while performing routine maintenance on valve CS-ft-1, damage to the valve stem was found which most likely occurred during last closure as a result of torque switch failure. The valve was declared inoperable and the remedial action of Technical Specification 3.6 is invoked. A new stem is expceted on-site by 2000 I today.
I
**** THIS IS A DRILL ****
s: (~ - MAINE YANKEE- Rev. 0 GRADED EXERCISE 4/9/87 l ( .- Page 6.1- 6
. JUNE 1987-SCENARI0' COMMAND' FORM _
EOF Controller COMMAND NO.. EOF-C-1
. FROM:
EOF Staff / Emergency Coordinator CLOCK TIME: Up n Activation-TO: EOF LOCATION: SCENARIO TIME PARTICIPANT MESSAGE-
**** .THIS -IS A ' DRILL ****
ACTIVATION OF Tile PEAS SHALL BE SIMULATED. O < w.. 3 I I 1 j 1' **** TilIS IS A DRILL **** l l
I .g\ i b MAINE YANKEE Rev. O GRADED EXERCISE 4/9/87 JUNE 1987 Page 6.1-7 SCENARIO MESSACE FORM Security Controller SEC-M-1 FROM: MESSAGE NO. Security Captain 1715 TO: CLOCK TIME: LOCATION: Security Gatehouse SCENARIO TIME: 0 min. PARTICIPANT- MESSACE
**** THIS IS A DRILL ****
5.1 INITIAL CONDITIONS At t?is
- 1. The reactor has been operating at full power for the last fourteen
[] months and is nearing the end of core life. ( f
- 2. The reactor is operating at:
l k 2610 MWt j 868 MWe > 576 Te ve (*F) l 2235 Pressuriser Pressure (psig) 58 Pressurizer Level (1)
- 3. The latest reactor coolant analysis completed and verified by Chemistry indicates 0.9 uC1/g dose equivalent 1-131 (at Technical i Specification limit) and 8.0 uti/g noble gas.
4 BPSI Purcp P-14-A is out of comission for motor repairs and is awaiting spare parts. When operators attempted to valve in the spare BPSI Pump P-14-5, at 1635 hours today, a flange gasket failure occurred, rendering the pump inoperable. The necessary paperwork to perform the replacement are being prepared including the stores requisition for the new gasket. (Refer to Miniscenario 7.2.l(s).) The innediate area around the charging pumps is experiencing elevated dose rates of 300 (mR/hr) and contamination surveys in the area are indicated as 100,000 (dpm/m2). The area has been roped off and marked in accordance with HP Procedure 9.l.6, " Establishing and Posting Controlled Areas," Decontamination efforts have been ialtisted. (Refer to Miniscenario 7.2.l(b).)
- 5. Containment personnel hatch inner door f ailed an 0-ring test at 1545. A maintenance crew is replacing the 0-rings.
- 6. Yesterday, at 1805, while performing routine maintenance on valve CS-N-1, damage to the valve stem was found which most likely ocrerred l l
during last closure as a result of torque switch failure. The valve Og was declared inoperable and the remedial action of Technical j (w j Speelfication 3.6 is invoked. A new stem is expected on-site by 2000 todsy. j I
**** TilIS IS A DRILL ****
l l l I
o
,l ! ] ,, '1 . .f - .. \ MAINE LYANKEE Rev. 0
( ,. GRADED EXERCISE 4/9/87 .;
.iUNE 1987 Page'6.1-8 i SCENARIO MESSAGE FOPJi FROM: ,
b5 EOC Controller MESSAGE NO. MEEOC-M-1 TO:. CLOCK TIME: UPon Activation LOCATION: Maine.EOC. SCENARIO TIME: . PARTICIPANT MESSAGE
**** THIS 'IS A DRILL ****
5.1 INITIAL CONDITIONS AT 1715
- 1. The reactor has been operating at full power for the last fourteen -
.W months and is nearing the end of core life. ,
- 2. The reactor is operating at:
<(: 2610 MWt 888 MWe . }
576 Teve (*F) 2235 Pressuriser Pressure (psig)
-58 Pressuriser Level (1)
- 3. The latest reactor coolant analysis completed and verified by Chemistry indicrtes 0.9 uCi/g dose equivalent 1-131 (at Technical Specification limit) and 8.0 uCi/g noble gas.
4 8 PSI Pump P-14-A is out of cossnission for motor repairs and is awaiting spare parts. When operators attempted to valve in the spare .l' BPSI Pump. P-16-S. at 1635 hours today, a flange gasket failure occurred. rendering the pump inoperable. The nucessary paperwork to perform the replacement are being prepared including the stores-requisition for the new gasket. (Refer to Min! scenario 7.2.1(a).) The immediate area around the charging pumps is experiencing elevated dose rates of 300 (mR/hr) and contamination surveys in the area are indicated as 100.000 (dpm/m2). The area has been roped off and j marked in accordance with HP Procedure 9.1.6. 'Tstablishing and i Posting Controlled Areas." Decontamination efforts have been initiated. (Refer to Miniscenario 7.2.1(b).)
- 5. Containment personnel hatch inner door fa!!ed an 0-ring test at 1545 A maintenance crew is replacing the 0-rings.
- 6. Yesterday, at 1805. while performing routine maintenance on valve CS-M-1, damage to the valve stem was found which most likely occurred during last closure as a result of torque switch failure. The valve r was declared inoperable and the remedial action of Technical
'( Specification 3.6 is ir,voked. A new stem is expected on-site by 2000 ..( today.
h .
**** THIS IS A DRILL ****
i 4
.p: h MAINE'. YANKEE Rev. O CRADED EXERCISE. 4/9/87-
. JUNE 1987 Page 6.1 9 SCENARIO MESSAGE FORM Engineering Support Center Controllf!ESSAGE NO. ESC-M-1 FROM:.
TO: ESC Sta R CLOCK TIME: LOCATION: Engineering Support Center SCENARIO TIME: PARTICIPANT MES9 ACE
**** THIS IS A DRILL '**
5.1 INITIAL CONDITIONS AT 1715 l
- 1. The reactor has been operating at f ull power for the last fourteen months and is nearing the end of core life.
fN . Is_ 2. The reactor is operating at -l-2610 MWt 888 MWe I 576 T v. (*F) , 2235 Pressuriser Pressure (psig) 58 Pressuriter Level (1)
- 3. The latest reactor coolant analysis completed and verified by {
~ Chemistry indicates 0.9 uCIVg dose equivalent I-131 (at Technical j Specification limit) and 8.0 uCi/g noble gas. ~
- 4. BPSI Pump P-14-A is out of commission for motor repairs and is awalting spare parts. When operators attempted to valve in the spare "
HPSI Pump. P-14-S. at 1635 hours today, a flange gasket failure occurred, rendering the pump inoperable. The necessary paperwork to perform the replacement are being prepared including the stores requisition for'the new gasket. (Refer to Miniscenario 7.2.l(a).) The immediate area around the charging pumps is experiencing elevated dose rates of 300 (mR/hr) and contamination surveys in the area are indicated as 100.000 (dpm/m2). The area has been roped off and marked in accordance with HP FroccJure 9.1.6. " Establishing and Posting Controlled Areas." Decontamination efforts have been initiated.- (itef er to Miniscenario 7.2.1(b).) .
- 5. Containment personnel hatch inner door f ailed an 0-ring test at I' 1545. A maintenance crew is replacing the 0-rings. ,
- 6. Yesterday, at 1805, while performing routine maintenance on valve CS-M-1 damage to the valve stem was found which snost likely occurred during last closure as a result of torque switch fa!!ure. The valve was declared inoperable and the remedial action of Technical p Specification 3.6 is invoked. A new stem is expected on-site by 2000 today.
i
**** THIS IS A DRILL ****
gE - ( ),1 0# MAINEiYANKEE Rev. 0--
' GRADED EXERCISE 4/9/87-- ' ' JUNE 1987 ; Page 6.1 10 SCENARIO MESSAGE FORM FROM:
EOC Controller _ MESSAGE NO.-
~
T0: . Pdlic AHairs Director- ~CL'OCK TIME: UPon Activation LOCATION: P@lic I' nformation Area SCENARIO TIME: i PARTICIPANT MESSAGE
**** THIS IS A DRILL ****
5.1 INITIAL CONDITIONS AT 1715
- 1. .The reactor.has been operating at full power for the last fourteen
.. months and is nearing the end of core life. .
- 2. The reactor is operating att
-2610 MWt 888 MWe 576 Tave.('F) '2215 Pressuriser Pressure (psig) 58 Pressuriser 1.evel (1)
- 3. The latest reactor coolant analysis completed and verified by Chemistry indicates 0.9 uC1/g dose equivalent 1-131 (at Technical Specification limit) and 8.0 uCi/g noble gas.
- 4. RPSI Pump'F-14-A is out of corrnission for motor repairs and is '!
- awaiting spare parts. When operators attempted to valve in the spare BPSI Pump. P-lls-S. 4t 1635 hours today, a flange gasket failure'-
occurred, rendering the pump inoperable. The necessary paperwork to j perform the replacement are being prepared including the stores requisition for the new gasket. (Ref er to Miniscenario 7.2.1(a).) - The isnediate area around the charging pumps is experiencing elevated dose rates of 300 (mR/hr) and contamination surveys in the ares are indicated as 100.000 (dpm/rn2). The area has been roped off and-marked in accordance with HP Procedure 9.1.6.'" Establishing and ; Posting Controlled Areas." Decontamination efforts have been i initiated. (Befer to Miniscenario 7.2.l(b).) ) 4
- 5. ' Containment personnel hatch inner door failed an 0-ring test at 1545. A maintenance crew is replacing the 0-rings.
- 6. Yesterday, at 1805. while performing routine maintenance on valve CS-N-1, damage to the valve stem was found which most likely occurred during last closure as a result of torque switch failure. The valve was declared inoperable and the remedial action of Technical
. Specification 3.6 is ir.voked. A new stem is expected on-site by 2000 today. **** THIS IS A DRILL ****
I l l
,~ . )- MAINE YANKEE Rev. 1 ]
CRADED EXERCISE 5/27/87 i Page 6.1-11 l JUNE 1987 l SCENARIO MESSAGE FORM EOF Observer MESSAGE NO. EOF-M-2 FROM: TO: EOF StaH CLO G N : D " EOF SCENARIO TIME: LOCATION: PARTICIPANT MESSAGE
**** THIS IS A DRILL **** ;
ALL OPERATIONAL AND RADIOLOGICAL DATA NORMALLY AVAILABLE OVER SPDS WILL BE AVAILABLE DIRECTLY FROM THE SIMULATOR.
!7 ]) ~ ,'
FOR EXERCISE PURPOSES CONTAINMENT RADIATION MONITOR READINGS WILL BE AVAILABLE UPON REQUEST FROM THE CONTROL ROOM, TSC, AND EOF OBSERVERS. CONTROL BOARD AND SPDS INDICATIONS FOR CONTAINMENT RADIATION FROM THE SIMULATOR SHOULD BE IGNORED. , l n b l **** THIS IS A DRILL **** l l f
d $,.
'ih \ ); . - Rev.-1 - ' MAINE ~ YANKEE GRADED EXERCISE- 5/27/87-JUNE 1987 Page 6.1 12 SCENARIO MESSAGE FORM TSC Observer MESSAGE NO. Tsc_u_9 FROM:
CLOCK TIME: Upon Activation. TO: TSC Staff TSC SCENARIO TIME: LOCATION: l PARTICIPANT MESSAGE'
'**** THIS IS A DRILL ****
9 ALL'0PERATIONAL AND' RADIOLOGICAL DATA NORMALLY
,AVAILABLE'OVER~SPDS UILL BE AVAILABLE DIRECTLY N FROM THE SIMULATOR.
FOR' EXERCISE PURPOSES CONTAINMENT RADIATION MONITOR READINGS WILL BE AVAILABLE UPON REQUEST FROM THE CONTROL ROOM, TSC, AND EOF OBSERVERS. CONTROL BOARD AND SPDS INDICATIONS 4 FOR CONTAINMENT RADIATION FROM THE SIMULATOR SHOULD BE '1 IGNORED. i 1 l i i i O
**** THIS IS A DRILL -****
s 1 A
.ji 's MAINE YANKEE' Rev . - 1 GRADED EXERCISE 5/19/87 JUNE 1987 Page 6.1 13 SCENARIO' MESSAGE FOPI MESSAGE NO. CR-M- 2 FROM: Control Room Dose Assessment Personnel UPon Request TO: Control Room Controller CLOCK TIME:
LOCATION: Control Room SCENARIO TIME: 4
. PARTICIPANT- MESSAGE **** THIS IS - A DRILL ****
A. weak high' pressure system will dominate the central and coastal Maine areas late Wednesday thru Thursday. Light variable winds with a chance of an occasional shower. High
~ -f' temperatures'in the mid to upper 60's. Variable cloudiness ' with fog likely in low lying areas Wednesday night and Thursday morning.
i-l
*THEFORECASTSHOULDONLYBEPROVIDEDAFTERThEPLAYERS DEMONSTRATE THEIR ABILITY TO OBTAIN THIS INFORMATION FOR EXERCISE PURPOSES CONTAINMENT RADIATION MONITOR READINGS WILL BE AVAILABLE UPON REQUEST FROM THE CONTROL ROOM, TSC, AND EOF OBSERVERS. CONTROL BOARD AND SPDS INDICATIONS FOR CONTAINMENT RADIATION FROM THE SIMULATOR SHOULD BE \ ~
IGNORED.
..TH.I.S..
I S A DRILL **** ! i
k' 4 c
.! l b- MAINE ' YANKEE Rev. 1 GRADED EXERCISE 5/19/87 JUNE.1987 Page 6.1- 14 i
SCENARIO ' MESSAGE FORM f FROM: Emeroency Operations Facility MESSAGE NO. EOF. M- 3 Dose Assessment Personnel i Emergency Operations Facility CLOCK TIME: Upon Request TO: Controller LOCATION: Emergency Operations Facility SCENARIO TIME: 4 i e PARTICIPANT- MESSAGE
**** THIS IS A DRILL ****
A weak high pressure system will dominate the central and coastal Maine areas late Wednesday thru Thursday. Light 3 variable winds with a chance of an occasional shower. High. I yariable cloudiness 1 temperatures in the mid to upper 60's.
.n' ' }
with fog likely in' low lying areas Wednesday night and Thursday morning.
*******.e ********************* +
- THE FORECAST SHOULD ONLY BE PROVIDED AFTER THE PLAYERS l
, DEMONSTRATE THEIR ABILITY TO OBTAIN THIS INFORMATION ,
I
)
l l 1 D
.k **** THIS IS A DRILL ****
}. a e , J l \ - (
/
to . MAINE , YANKEE' Rev. 1- . j 5/19/87 Tj
-GRADED' EXERCISE; JUNE'1987 Page 6.1- 15 1
SCENARIO MESSAGE FORM' 1 i h , a d MESSAGE NO.. TSC-M-q FROM: Technical Support Center Dose-Assessment Personnel UPon Request? TO: Technical Support Center Controller CLOCK; TIME: LOCATION: Technical Support Center SCENARIO TIME:
/
PARTICIPANT MESSAGE
**** THIS IS A ' DRILL ****
A weak high pressure system will dominate the central and coastal Maine areas late Wednesday thru Thursday.. Light variableL winds with a chance of an occasional shower. . High ~3 f"'v temperaturec 'in the mid to. upper 60's. Variable cloudiness l ( )1 with fog likely in low lying' areas. Wednesday night and Thursday morning. i [ l e t . t e e e t'$ $ 6 .9 .*..******9 ...*..
- THE FORECAST SHOULD ONLY BE PROVIDED AFTER T E PLAYERS *
, .i
- oEnoNSTRATE TnEIR A.1t1TY To o.TAIn THIS zuroRxA2 Ion i
'I l
DR'.L1,- **** f
**** THIS IS A )
y
n l
. k. Rev. 1 MAINE YANKEE GRADED. EXERCISE 5/19/8'7-Page 6.1- 16 JUNE 1987 n
SCENARIO MESSACE FORM' SC Controller MESSAGE NO. ESC-M-2 FROM: ESC Coordinator / ESC Staff CLOCK TIME: UPon Request TO: Engineering' Support Center SCENARIO TIME: LOCATION: 1 PARTICIPANT- MESSAGE
**** THIS IS A DRILL **** i A weak high pressure system will dominate the central and f coastal Maine areas late Wednesday thru Thursday. Light variable winds with a chance of an occas ional shower. High j temperatures in the mid to upper 60's. Variable cloudiness ,/~N) l 5 \> 'with fog likely in low lying areas Wednesday night and Thursday morning.
I i ..
- THE FORECAST SHOULD ONLY BE PROVIDED AFTER THE PLAYERS DEMONSTRATE THEIR ABILITY TO OBTAIN THIS INFORMATION
- b .
**** THIS IS A DRILL ****
t .j \
;(,,). MAINE YANKEE Rev. 1 GRADED EXERCISE 5/19/87 JUNE 1987 Page 6.1-16a , SCENARIO MESSAGE FORM j
FROM: MEEOC CONTROLLER MESSAGE NO. MEEOC-M-la TO: MEEOC~ STAFF CLOCK TIME: Upon Request LOCATION: - MEEOC SCENARIO TIME: i PARTICIPANT MESSAGE
^**** THIS IS A DRILL ****
A weak high pressure system will dominate the central and coastal Maine areas late Wednesday thru Thursday. Light- ! variable-winds with'a chance of an occasional shower. -High ry
-temperatures in the.mid to upper 60's.
( ). Variable cloudiness with fog likely in low lying areas Wednesday night and Thursday morning.-
- THE FORECAST SHOULD ONLY BE PROVIDED AFTER THE PLAYERS DEMONSTRATE THEIR ABILITY TO OBTAIN THIS INFORMATION ,
i (M
; \j ~ **** THIS IS A DRILL ****
i o MAINE YANKEE
-GRADED EXERCISE Rev. 0-4/9/87 i . JUNE 1987 . Page 6.1- 17 i
SCENARIO COMMAND FORM FROM: Control Room Controller. COMMAND NO. CR-C-2 TO: Plant Shift Superintendent CLOCK TIME: Shutdown Initiation LOCATION: Simulator Control' Room SCENARIO TIME . PARTICIPANT MESSAGE.
'**** THIS 'IS A DRILL' **** 'i O
I THIS COMMAND HAS BEEN DELETED. l l
.**** THIS IS A DRILL **** , - I I
i
i I , MAINE YANKEE Rev. 0 GRADED EXERCISE 4/9/87
. JUNE 1987 Page 6.1 18 -
SCENARIO-COMMAND FORM CR Controller CR-C FROM: . COMMAND NO. PSS / CR Staff' CLOCK. TIME: Upon Discussion Of Trip TO. Simulator. Control. Room SCENARIO TIME
- Prior'to 1815. . LOCATION:
PARTICIPANT MESSAGE
**** THIS IS A DRILL **** 1 THIS COMMAND HAS BEEN DELETED.
l i l l
**** THIS IS A DRILL ****
+ . l m
~ B--[)Mi - ; MAINE ' YANKEE Rev. O' GRADED EXERCISE __ 4 /9/87
-JUNE 1987 Page 6.1 .19 -SCENARIO COMMAND FORM:
CR Controller COMMAND N0; CR-C-4 FROM: PSS /CR Staff CLOCK TIME:. Initiation of-Shutdown TO: u a or Control Room ~ SCENARI0' TIME-LOCATION: j PARTICIPANT MESSAGE
****- THIS IS A DRILL- ****
l FOR EXERCISES' PURPOSES'IN-STATION'A0 RESPONSES ASSOCIATED WITH NORMAL SHUTDOWN ACTIVITIES SHALL BE SIMULATED.-
'i 1 's t
I
={- l i -
i , MAINE YANKEE'- Rev.-0 GRADED EXERCISE 4/9/87_ JUNE 1987 -Page 6.1 '
' SCENARIO COMMAND FORM-FROM: CR Controller COMMAND NO. cn_c_s-Upon Unusual Event- I .TO: PSS'/ CR Staff CLOCK TIME:
LOCATION: Simulator Control Room SCENARIO TIME PARTICIPANT MESSACE
**** THIS IS A DRILL **** !
CONTACT THE ACTUAL CONTROL ROOM AND REQUEST INITIAL ACTIVATION OF THE PLANT EVACUATION' ALARM'AND_ NOTIFICATION i0F THE NRC VIA THE RED TELEPHONE (ENS) THAT THE EXERCISE. HAS STARTED AND AN UNUSUAL EVENT HAS'BEEN DECLARED. ALSO DIRECT THE CONTROL ROOM STAFF TO MAKE THE APPROPRIATE DRILL ANNOUNCEMENT IN ACCORDANCE WITH PROCEDURE 2.50.17. t
**** THIS IS A DRILL ****
I
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.g Rev. O j MAINE . YANKEE .
GRADED EXERCISE 4/9/87 ~ > ' JUNE 1987-' Page 6.1 21 ; SCENARIO COMMAND FORM-COMMAND NO. PI-C-1 FROM: cA airs Direcetor Upon Activation TO: CLOCK TIME: EEOC' SCENARIO TIME
. LOCATION:
PARTICIPANT. MESSAGE a
' **** THIS IS'A DRILL **** - THE PLAYING OF ALL' PRERECORDED EMERGENCY MESSAGES ON THE PUBLIC INFORMATION TELEPHONE SHALL BE SIMULATED THROUGHOUT .Q. .THE EXERCISE. .V !l t
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**** THIS IS A DRILL ****
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p,_ i l. b Ln .Y. MAINE YANKEE Rev. O 4/9/87 GRADED EXERCISE
. . JUNE 1987 Page'6.1-22 SCENARIO COMMAND FORM i .CR Controller: COMMAND NO.
CR-C .FROM: TO:
- S / CR Staff CLOCK TIME: 1745.
- Simulator Control Room SCENARIO TIME 30 min LOCATION:
PARTICIPANT MESSAGE .,
**** THIS IS A DRILL ****
l.
, i 'ANY ATTEMPTS TO ENTER THE CONTAINMENT SHALL BE SIMULATED.
l i
' \
ANY ATTEMPTS TO ENTER.ANY HIGH RADIATION
' AREAS SHALL ALSO BE SIMULATED. T l
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**** THIS IS A DRILL **** ~
i l i I rx 1 i 4
\,,J:
1 MAINE YANKEE Rev. O GRADED EXERCISE 4/9/87 JUNE 1987 Page 6.123 ; SCENARIO COMMAND FORM , i OSC Controller OSC-C-1 FROM: COMMAND NO. OSC Coordinator /'OSC Staff CLOCK TIME: 1745 or Upon Activation T0: OSC SCENARIO TIME 30 min LOCATION: PARTICIPANT MESSAGE , 1
**** THIS IS A DRILL ****
ANY ATTEMPTS TO ENTER THE CONTAINMENT SHALL BE SIMULATED. (~~) ANY ATTEMPTS TO ENTER ANY OTHER HIGH RADIATION AREAS SHALL ALSO BE SIMULATED. 7 4 i LJ
**** THIS IS A DRILL **** I l
1
t r s(
! MAINE 1 YANKEE Rev. O GRADED' EXERCISE 4/9/87 i-JUNE 1987 Page 6.1 24 SCENARIO COMMAND FORM Security Controller ~ SEC-C-1 FROM: COMMAND NO.
y 'i
' Security Captain CLOCK TIME: .1745' TO: .
Security Gatehouse SCENARIO TIME D I" LOCATION: PARTICIPANT MESSAGE
**** THIS IS A.. DRILL **** 'THE PLAYING OF A14 PRERECORDED EMERGENCY MESSAGE TAPES p ON THE 'PUBLIC INFORMATION TELEPHONE SHALL BE SIMULATE 1}
G THROUGHOUT THE EXERCISE. O
**** THIS IS A DRILL ****
I 4
^
MAINE YANKEE Rev. 0 , l GRADED EXERCISE 4/9/87 JUNE 1987 Page 6.1- 25 SCENARIO COMMAND FOPJ1 CR Controller COMMAND NO. CR-C-7 i FROM: PSS CLOCK TIME: 1800 TO: Simulator SCENARIO TIME 45 min LOCATION: PARTICIPANT MESSAGE
**** THIS IS A DRILL" 1 DECLARE AN UNUSUAL EVENT BASED UPON " REACTOR COOLANT 1 J /~N SYSTEM LEAKAGE GREATER THAN 10 GPM". , %) I E
I r~ S
**** S A DMLL ****
1 i
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' L: f j MAINE YANKEE Rev. 0
[ CRADED EXERCISE 4/9/87 JUNE 1987' Pa ge 6.'l- ' SCENARI0' MESSAGE FORM CR Observer MESSAGE NO. CR-M-3 FROM: CR Staff / PSS' CLOCK TIME: 1803 TO: A- i n' Si"* CR SCENARIO TIME: 48 min LOCATION': PARTICIPANT' MESSAGE
**** THIS IS A DRILL ****
THE MAINTENANCE CREW WORKING ON THE CONTAINMENT HATCH CALLED THE CONTROL ROOM TO REPORT THAT IN THEIR HASTE TO EXIT-i
.e THEY BELIEVE THE OUTER DOOR SEAL'WAS DAMAGED. REPAIRS TO THE-t INNER DOOR SEALS HAD NOT BEEN COMPLETED.
P i s n fO 11 ****' THIS IS A DRILL **** g;i
l
' .o .., .> .,7 ,6 i a ~'7. .I ) Rev. 1 - (M ~ -MAINE' YANKEE- l GRADED EXERCISE- 5/19/87 JUNE 1987 Page 6.1-27 SCENARIO COMMAND FORM k
CR-C 8' FROM: C Controller- COMMAND NO. bb CLOCK TIME: 1Aqq TO: Sim. Control Room SCE!;ARIO TIME 78 t - LOCATION: ci PARTICIPANT MESSAGE 'N
- E .' ., e
**** THIS- IS A' Sp LL,, **d .y 1-n. * '?
DECLARE AN ALERT AT THIS TIME BASED UPON "T.C% LEAK-RATE EXCEEDING 100 GPM". s
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) '. l ...s' 6,- 1 1f l sm , **** T!!IS
IS A. DRILL ****
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MAINE YANKEE - Rev.-0 GRADED. EXERCISE 4/9/87' I ~' JUNE 1987 Page 6.'l ,
- j. , f. '^
. SCENARIO COMMAND FORM' COMMAND NO. MEOC-C-1 FRdM: MEEOC Controller.
l CLOCK TIME: 1845 or ALERT Declaration
.. TO: . MEEOC Coordinator / Staff -
MEEOC SCENARIO TIME. LOCATION: p, PARTICIPANT ' MESSAGE
**** THIS IS A DRILL ****
ACTIVATION OF THE PEAS SHALL BE SIMULATED FOR THIS EXERCISE. x)b 4 l t
.( **** THIS IS A DRILL ****
l
/' 'N MAINE YANKEE Rev. 1 '\ _j GRADED EXERCISE 5/19/87 C
JUNE 1987 Page 6.1 29 SCENARIO COMMAND FORM FROM: CR Controller COMMAND.NO. CR-C-9 TO: PSS'/ CR Staff CLOCK TIME: Upon discussion of LOCATION: Sim. Control Room SCENARIO TIME issuance PARTICIPANT MESSAGE i
**** THIS IS A DRILL- ****
ADMINISTRATION OF KI SHALL BE SI!ULATED FOR THIS EXERCISE. ; .f%
\ -s l
l
**** THIS IS A DRILL ****
(3 ( l Rev. 1
#- MAINE YANKEE t
GRADED EXERCISE 5/19/87 JUNE 1987 Page 6.1-30 SCENARIO COMMAND FORM FROM: OSC Controller COMMAND NO. OSC-C-2 CLOCK TIME: Upon discussion TO: OSC Coordinator SCENARIO TIME of issuance LOCATION: OSC PARTICIPANT MESSAGE 1
**** THIS IS A DRILL ****
l I ADMINISTRATION OF KI SHALL BE SIMULATED FOR TIIIS EXERCISE.
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'O l ' **** TllIS IS A DRILL **** i l
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.f 1- MAINE YANKEE Rev. 1 '+ GRADED EXERCISE 5/19/87 JUNE 1987 Page 6.1-31 SCENARIO COMMAND F0FJi FROM:
EOC Controller COMMAND NO. EOF- C- 2 TO : . Emergency Coordinator CLOCK TIME: Upon discussion-EOF f ssuance LOCATION: SCENARIO TIME PARTICIPANT MESSAGE L
**** THIS IS A DRILL ****
ADMINISTRATION OF KI SHALL BE SIMULATED FOR THIS EXERCISE. Oi
-()
I
**** THIS IS A DRILL ****
1
( m{; Rev. 1
\_ ,/ 'HAINE YANKEE 5/19/87 GRADED EXERCISE JUNE 1987 Page 6.1-32 SCENARIO COMMAND FORM TSC Controller COMMAND NO. TSC-C-1 FROM:
CLOCK TIME: Upon- discussion TO: TSC Coordinator LOCATION: TSC SCENARIO TIME of issuance PARTICIPANT MESSAGE
**** THIS IS A DRILL **** l 'I ADMINISTRATION OF KI SHALL BE SIMULATED FOR THIS EXERCISE. .f v t
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' **** THIS IS A DRILL ****
i . l
, x, ', l MAINE YANKEE .Rev. O CRADED EXERCISE 4/9/87 . JUNE 1987 Page 6.1 33 SCENARIO COM'iAND FORM FROM: TSC Controller COMMAND NO. TSC-C-2 TO: TSC Coordinator CLOCK TIME: 1930 LOCATION: TSC SCENARIO TIME 135 PARTICIPANT MESSAGE **** THIS IS A DRILL ****
ACTIVATION OF THE EMERGENCY VENTILATION SYSTEM SHALL BE SIMULATED.
-~.. \s' l /N s v - **** THIS IS A DRILL ****
MAINE YANKEE Rev. 1 L [~ .. GRADED' EXERCISE 5/19/87
- JUNE 1987 Page 6.1- 34 SCENARIO MES SAGE FORM bsener DSC-M-2 FROM:
MESSAGE FO. OSC Team at HPSI P-14S CLOCK TIME: 1945 TO: PAB Elevation 21' SCENARIO TIME: 150 LOCATION: l
)
I PARTICIPANT MESSAGE l l
**** THIS IS A DRILL ****
While working on HPSI P-14S you hear loud knocking sounds coming from the P-14B cubicle. Upon investigation you - observe oil dripping f rom the pump to the floor. The pump-has apparently seized. (3' L) i
es MAINE YANKEE Rev.'l GRADED EXERCISE 5/19/87
.( #)
JUNE 1987 Page 6.1- 35 SCENARIO MESSAGE FORM FROM: OSC Observer MESSAGE NO. OSC-M-3 TO: OSC Team CLOCK TIME: 2100 LOCATION: SP ray Building Valve CS-M-2 SCENARIO TIME: 225 PARTICIPANT MESSAGE
**** THIS IS A DRILL ****
i l Attempts to . manually open Valve CS-M-2 have been successful.
/m. 1
( I-t i l
**** THIS IS A DRILL ****
MAINE'. YANKEE Rev. 0 ( GRADED EXERCISE. 4/9/87-Page' 6.1 36 JUNE 1987 SCENARIO MESSAGE- FORM OSC ' Ob se rver. OSC-M-4 FROMi MESSAGE NO. 0SC'Tenm. 2145 TO: . CLOCK TIME: at HPSI P14-S ,270. LOCATION:- SCENARIO TIME: r PARTICIPANT MESSAGE
****'THIS' IS A -DRILL '****
YOUR ATTEMPTS TO REPAIR HPSI P14-S.HAVE BEEN SUCCESSFUL.
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+ **** THIS IS A DRILL ****
O MAINE YANKEE GRADED EXERCISE JUNE 1987 7.0 STATION EVENT DATA l O 1503e
l l MAINE YANKEE GRADED EXERCISE JUNE 1987 .; 1 1 I 7.1 EVENTS
SUMMARY
j i i l l i 1503e ! l i l
......a
'I y ,,.
i Rev.' 0 4/7/87 n- Page 7.1-1
~
l MAINE YANKEE GRADED EXERCISE -l JUNE 1987 7.1 EVENTS ~
SUMMARY
The following information and supplementary' mat'erial-are provided for-those controllers having in-plant' control assignments so as to further ensure the proper development of the scenario'. The:information provided in this section assumes that the " players " who are dispatched to perform.- repair,. rescue, or other activities, will'take certain actions in response to.the scenario. The controller / observer must be cognizant'of the actions of those " players" to which he is assigned and' provide information regarding the results of the " players" actions as appropriate to those actions. The information provided in this'section does not.-
' preclude the possibil'ty i that the controller will be required to provide additional information to the " players." 'l Approximate Miniscenario Time _ Event Location Initiation 7.2.1(a) 1715 HPSI Pump, P-14S Maintenance ' Initial Gasket Failure Office Condition Repair 7.2.1(b) 1715 HPSI Pump PAB Initial Cubicle -Condition Decontamination 7.2.1(c) 2000 HPSI Pump, P-14B, PAB Control Board Failure Indications' and Noise in PAB 7.2.2 1803 Personnel Hatch Hatch Area Reported by Seal Damage Maintenance Crew 15 f ' . ,
Rev. 0 [] 4/7/87 'y/ Page 7.1-2 MAINE YANKEE .; GRADED EXERCISE JUNE 1987 Approximate Miniscenario Time' Event Location Initiation 7.2.3 1830 Valve CS-M-2 Spray Building Control Board Will Not Open Indication 7.2.4 2000 MS-A-162 CIS Inoperable from Control Room
- Block CIS Control Room f Signal by Jumpering
,f s. Contacts, or (s'
- Operate from Control Room ASP l
1 i i i I <m) U 1503e ) l j
O l l MAINE YANKEE GRADED EXERCISE JUNE 1987 7.2 EVENT MINISCENARIOS O i l 1 0 1503e 11 { 1 I I I
p Rev. 0
. -4/7/87 Page 7.2-1
- /]
.' Q MAINE YANKEE GRADED EXERCISE-JUNE 1987 7.2.1(a) .MINISCENARIO 1.~ ' General' Description At approximately:1635, a discharge flange gasket failure ' occurred on'HPSI. Pump,.P-14S rendering the pump inoperable. As.of 1715, actions are' underway to prepare.the necessary paperwork to obtain from stores and install-the.new gasket.
- 2. Description of' Player Responses / Observations / Corrective Actions TheOSC willLdirect the continued repair activities and maintenance team to return HPSI Pump, P-14S, to service as quickly as possible.
The necessary paperwork will be completed to perform the gasket replacement,' including RWF, DR/RO, and Stores Requisition. Work will have to be coordinated with the HP crew decontaminating the pump ~
. cubicle'. (Refer to Miniscenario.7.2.1(b).
Once the gasket and necessary tools have been obtained and cubicle entrance'is permitted, the maintenance team will (simulation only) drain the necessary piping and proceed to disassemble flange, prepare flange faces, install new gasket, reassemble, fill, and vent the affected piping. i
- 3. Event Closecut ,
For scenario purposes, the gasket replacement will be successfully completed and the pump made operational at 2145. 1503e
L' , Rev. 0 TN 4/7/87 D Page 7.2-2 MAINE YANKEE GRADED EXERCISE JUNE 1987 7.2.1(b) MINISCENARIO
- 1. General Description At approximately 1635, a discharge flange gasket' failure occurred.on HPSI Pump, P-14S, rendering the pump inoperable. As of 1715, the pump cubicle
-has been' roped off and' decontamination efforts within the area have been initiated.
- 2. Description of Player Responses / Observations / Corrective Actions The dose rate within the cubicle is measured at 300 mR/hr and
' g. contamination surveys indicate 100,000 dpm/m. A complete dose map of the d area is provided in Section 9.0.
The OSC will direct a team of HP technicians to continue the decontamination activities and to assist the maintenance crew in gaining access to the cubicle. (Refer to Miniscenario 7.2.1(a).) The HP technicians will simulate' decontamination activities and establish the appropriate RWP requirements for the maintenance team.
- 3. Event Closeout It is estimated that the malntenance team will be ready to enter the' pump cubicle at 1815. HP should support this schedule.
O 1503e
Rev.:0-
'4/7/87 p(l -~
- Page 7.2-3 V ,
MAINE YANKEE. GRADED EXERCISE JUNE 1987" 7.2.1(c) MINISCENARIO1
' 1'. General Description
- At approximately'1945, the'RCS leak will increase-to about 350 to 400 gpm. At that time, control board instrumentation will' indicate a
.. loss of all HPSI flow as a result of~the failure of HPSI; Pump P-14B.
- 2. " Description of Player / Observations / Corrective Actions At approximately;1'945, the maintenance team working on HPSI Pump P-14S will'. hear a knocking noise from the P-14B cubicle. As they reach the-
. cubicle, the pump will seize as a' result of apparent bearing failure.- '3.. Event Closeout The maintenance team will report back to the Control Room that the damage.
to HE I Pump P-14B is significant and that repair is not possible. O 1503e
Rev. 0 4/7/87 Page 7.2-4 MAINE YANKEE GRADED EXERCISE JUNE 1987 ; 7.2.2 MINISCENARIO
- 1. General Description At approximately 1545, the' containment personnel hatch failed an inner 0-ring test. A maintenance crew is in the process of making repairs..
Following being informed of the RCS leak,'the maintenance crew quickly leaves the hatch area at 1735. ..In doing so, they believe-that.the outer door seal may have been damaged. Repairs to the inner door had not been completed. j i
- 2. Description gf Player Responses / Observations / Corrective Actions
.f
' ? At'the start of the exercise,'the potential inner hatch door damage will' I l be stated as an initial condition. At 1803, the Control Room will be informed of the possible damage to the outer door seal. Prior.to 2200, the radiation levels in the hatch area (refer to [. Section 9.0) will preclude access for. repairs. After 2200, the radiation levels' decrease dramatically (refer to Section 9.0) and repairs may be considered. Any attempt,to seal hatch will be unsuccessful until 2200.
- 3. Event Closeout For scenario purposes,'the personnel hatch will be sufficiently sealed and containment pressure reduced so as to discontinue the release at 2200.
1503e
s Rev. 0 4/7/87 Page 7.2-5 GRADEL EXERCISE
.. JUNE 1987 7.2.3 MINISCENARIO i
- 1. General Description
' Yesterday at.1805, while performing routine maintenance on Valve CS-M-1, damage to the valve stem was found requiring the valve to be' declared inoperable. A new stem is expected on-site later tonight.
l At 1830, contiainment pressure reaches 3 psig. Should a decision be'made ! to'use containment. spray before 2100, CS-M-2 will fail to open as-indicated on the control board. (NOTE: After 2100, the' valve'should open and oneLtrain of containment spray be operational.
., 2. Description of Player / Observations / Corrective Actions 1%.
V If the decision is made to initiate containment spray prior to 2100, CS-M-2 will fail to'open as indicated on the control board. The Control-Room will send an auxiliary operator to the Spray Building to manually open the valve. Entrance to the building shall be made from the west side to preclude passing through the hatch area. This action will be unsuccessful and an OSC team should.be dispatched to repair the valve. When the OSC team responds, they carefully inspect the motor operator and can find no apparent damage. They discover that the reach rod assembly is. bent and bound at a lower elevation. Dose maps of the Spray Building are provided in Section 9.0. After obtaining RWP and necessary tools, the team should cut away reach rod assembly and open manually at the valve. i p-
- 3. Event Closecut After 2100, Valve CS-M-2 can be opened, or if repair actions were
?.n a i s ' ~
- s. n . ' vtions will be successful. p l et r ,1 % ! % J e.
i
Rev. O h < 4/7/87 j, Page 7.2-6
- ()'.
MAINE YANKEE GRADED EXERCISE JUNE 1987 7.2.4 MINISCENARIO.
- 1. . . General Description At 1815, condenser vacuum was lost which necessitated the use of the Decay Heat Release Valve MS-A-162 for plant.cooldown.
I i At approximately 2000, containment isolation occurs. Following the CIS, MS-A-162 cannot be operated'from the Control Room until the CIS is
. blocked. '2. Description of Player /Observatio'ns/ Corrective Actions. . At 2000, a team may be dispatched by the OSC to open Valve MS-A-162, ? which can be opened by one of the following:
- a. At the Alternate Shutdown Panel, in the Emergency Feedwater Pump Room, by positioning the key-locked switch to the alternate position. Radiation levels in the room will be provided in Section 9.0. NOTE: All panel actions shall be simulated.
- b. To block CIS at the rear of the simulator control board by simulating the jumpering of the CIS wire.
3 .' Event Closeout Once the required actions are taken to open the valve, the Control Room shall be so notified that MS-A-162 is operational. 1503e
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l O. MAINE YAKEE GRADED' EXERCISE
' JUNE 1987 I
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, . .1@j MAINE YANKEE GRADED. EXERCISE i
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s s-e , ,e y a .or n , , '.w E e$% am gg =c a t N. A ,n. 0== w .. . = 6-= z= .h.* e = D em ,32 41 J* ca,~.a c . ..., a $.'; da o-c.r.s es - v **- -W ~; O tr ~ 9, - U u W $ f 'o , f* d w .~. m# 2 ", 2_ a-W sJ ** go S -,a e: Oa -3 S-ae 45 3 g a g sh. - enm s. *= + *w &. e 6 - - 44m 2 63. 4.x. 1 MAINE YANKEE GRADED EXERCISE JUNE 1987'. O' 9.6 CONTAINMENT AIR SAMPLE' DOSE RATES i O l 1 [~ ' Rev.1 J \~-) MAINE YANKEE ! !b * ~ GRADED EXERCISE "9" JUNE 1987 9.6. CONTAINMENT AIR SAMPLE DOSE RATES UNSHIELDED SHEILDED ( R/hr per cc)* ( 1 in. lead in mR/hr per-cc)* CLOCK SCENARIO TIME TIME (min.) CONTACT 1 FT. CONTACT 1FT. 1715 0 AS READ AS READ AS READ AS READ 1725 10 0.02 1.4E-4 AS READ AS READ 1730 15 0.10 7.0E-4 AS READ AS READ 1735 20 0.80 5.7E-3 1.0E-2 7.2E-5 1745 30 1.8 1.3E-2 2.3E-2 1.6E-4 1753 38 4.5 3.2E-2 5.6E-2 3.8E-4 1800 45 90 6.3E-2 1.1E-1 7.7E-4 1815 60 18 1.2E-1 2.2E-1 1.1E-3 1825 70 19 1.3E-1 2.3E-1 1.2E-3 1845 90 20 1.4E-1 2.6E-1 1.3E-3 1900 105 21 1.5E-1 3.0E-1 1.4E-3 1915 120 22 1.6E-1 3.2E-1 1.5E-3 1935 140 125 8.8E-1 1.6 1.0E-2 ! 1945 150. 160 1.1 2.0 1.4E-2 2000 165 200 1.4 2.5 1.7E-2 2015 180 230 1.6 2.9 2.0E-2 2030 195 250 1.8 3.1 2.2E-2 2045 210 265 1.9 3.3 2.3E-2 2115 240 275 2.0 3.4 2.4E-2 2145 270 290 2.1 3.6 2.5E-2 2200 285 290 2.1 3.6 2.5E-2 i 2210 295 290 2.1 3.6 2.5E-2 2215 300 290 2.1 3.6 2.5E-2 ; 1
- Given dose rates must be multiplied by sample volume in cubic centimeters (cc).
(v l \ l ( ; I I l l MAINE YANKEE GRADED EXERCISE JUNE 1987 I 9.7 0FF-SITE MONITORING TEAM OBSERVER INSTRUCTIONS / DATA i l 1 I j l I ~ l 1505e Rev. 1 5/14/87 r3 Page 9.7-1 G' MAINE YANKEE GRADED EXERCISE JUNE 1987 9.7 0FF-SITE MONITORING TEAM OBSERVER INSTRUCTIONS / DATA Off-site plume centerline whole body and thyroid 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 provided in this package for each 15 minute average of meteorological conditions, starting at 2000. 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 Radiological Sample Coordinator will direct off-site monitoring teams to monitor locations relative to the meteorological conditions postulated for the exercise scenario. Use Figures 9.7-1 through 9.7-11 to provide survey results to the off-site monitoring teams. Figures 9.7-1 through 9.7-11 depict the plume conditions at various times throughout the exercise. Each figure will be used for a 15-minute time i interval as indicated in each' key. 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, gamma dose rates can be estimated for the outer edges of the plume by multiplying the centerline rates by 0.01. 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 particular segment at centerline. Dose and count rates for locations between two segments can be estimated as a function of the values at those segments. (] \) 1505e Rev. 1 5/14/87 Page 9.7-2' All dose rate values reflect closed window readings. Open window readings can be obtained by multiplying the gamma dose rate in Figures.9.7-1 through 9.7-11 by 1.2. Prior to the exercise, training will be provided to the off-site monitoring team observers on the use of this package. The following are l specific. actions-which off-site monitoring team observers should take . j during the exercise:
- 1. As off-s'ite. monitoring. teams are designated, check that Procedure ]
Number 2.50.12 is followed by team members. This will include the { J initial' equipment check. j i -2. While enroute to the assigned monitoring 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 l-their' continual job assignment. Do not issue pocket dosimeter results to team members, unless they actually simulate checking their dosimeter reading. The pocket dosimeters in the kits 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, then issue them an "off-scale high" value. 1505e Rev. 1 5/14/87 L Page'9.7-3
- 5. If th'e off-site monitoring team stops to take'an air sample:
- a. Report the appropriate whole body dose levels at that location.
i b.- As' sample counts.are completed, report the appropriate data'from Figures 9.7-1 through 9.7-l . These figures assume that a 15-minute air sample was taken. In some_ instances, the teams may be directed to take a shorter sample period. Under these circumstances, you should adjust the figure values by a ratio x/15, where x is the actual sample period in minutes.
- c. If the team attempts to count the samples while still in the plume, then the observer should estimate the E-140, HP-210 radiation survey instrument background count rate using the following relationships, and add them to the given count rates:
0.,. .o 1 mR/hr will cause the E-140, HP-210 survey instrument to read 3,500 cpm above the sample dose rate, due to backgroun6. ) O 1505e i l so Y sju , I .t O ~f *L / , D Y: 4-kC
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l'ICUILE 9.7 1 J Of f-Site Ratllological Conditiotta at Clot:k Time if S S-3O u f-l.i r DIETANCE CONC. CAMMA EM-14 CAM-II LEL RATE F:EL RATE PLUME 15 CF H3 1-131 NO MILES I-131 DOSE RATE r> uCi/ cec uC1/r,ec uC / S ER ZEO TE i J :sze::: 2 es=22ss==:===reszzursen===ncr=cesas===cs:s 160 :sseter=:rzs=rzzsz 164 1372 1103000 BB2.4 SD 0.5 0.0132151 .33 0.136772 %20 300 2004 11C3000 882.4 2 970 5495 40966 1103000 802.4 1 .06 2.453072 **'.' / 2, % - .' ,N WIS C A S SET l ' a : .' t. . - f ,s 4 j _... . e ' :j: 4 569- ' ' ~ ~ * ~ ~ ~ * *
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. n s ,,,, g 9 3 o h, Yhk,bY?he4 s c. + o/- /. pu. L.. l ' }j} ,,~ g4 jl ), lh ' Jr e v . u er I , , g . e avne s l~ > p-- f / I' a - O. y w j/ e ,r , f ~ F1CifRE 9,7 2 O of f-tite Radiological conditions at Clock Tis:e 20:00-20:15 REL RATE REL RATE PLUME DISTAriCE CCt10. CAMMA RM-14 SAM-11 !!G 1-131 ID MILES I-131 DOSE RATE 15 CF uCi/cc SILVER ZEOLITE ,/ ' uC1/see uCi/see CPN + X 10E-0 mR/HR CPM secuzessrzz:cenzz:::: rzs==z== ==zsnmese======= ssessens==sessme:sss=ses 2211.2 CB .5 0.000700 210 1359 10133 . e 2704000 100 010 4546 1935000 1540 3 .73 0.272222 2 9 2211.2 2 .42 0,710049 230 1004 11950 y 2764000 1200 3941 20360 g 2704000 2211.2 1 .00 1.759259 # " 1970 ece .d v ~ ':c / , ; 3 l wis c A S SET 1;;. , l -q ] ~ ;a..- , 1 , v ,.g N / x ., - l & J .wn . , ., ~ b / . \ y ,,i. ., '4=@N mn / , s, . _a ymg .Of x L / . m h g * % , d: S. **k 1 b)4 wm -~ a ) .. l. @ > @C . 7,p, ./d 53 / M h.< < E, Et , t ; :/;) -g& ) w '
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,1 { ! jd N i:.' /M h.L . N [.# Nl Ml.= N,s% urv-ru3e '>.'i-i <' ,) [ [ ! k gf - g < - se y u p r 1 ) 4r ricupt 9.7-3 of t-r,ite Hadi c ic91081 C 6di t IS"5 ** Cl'"'" II'* ib' F5 (d ITL I. ATE ITL RATE l'LU!S DI ST A! ICE CONC. G/diA RM-14 CAM-Il r;G 1-131 12 0 f t1 LEO I-131 DUCE RATE 15 Ci; uCJ/sec u C1/c <e r UC1/cc !!1 LVEI. 4~ E.0 LITE 1CE-0 ti./la C h-l cit! \ n* r41bb b4bb CL .b b.b bob b 1b 5 193 t-00 0 1543 4 2 .15 O. 1967C 70 L'2 4340 ,, 2704000 2211.2 3 .05 0.311111 150 CD7 1190
- 3041000 'J 4 3 2 , 0 2 .42 0.14LC79 270 Ibb4 14123 3041000 2402.0 1 .G6 13 02050 1420 9
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p - = 1 - ) 7 ,, . / . an p a J . . ..v, q ,a.f?;. w l . ]J : :jf,7 X.' (* -.a e w m; u n/a . .yl s u"' ;n< *Q 1 ; ~~e .m:fy.O , ;ga C] ]. / [ g 29 e ,+ p: h i m. 3 lj/n y J- .qAs. wn 5 . 5 , .. .= , - - c . i ~y agwcm a s 1, a u90 .3. / 'l _/ f ' o e ,; 1 @ %4 ' Sa o f '%a! FICilRE 9 *i-4 Off-Site Radiological Conditions at Clock Time Af~' 2". L 20:45 T(g} , REL RATE REL PATE l'LUME DISTANCE CONC. GAMMA RM-14 SAM-II IG I-131 No MILES 1-131 DOGE RATE 15 CF + s uC1/r.oc uC1/sec uC1/cc X 10E-0 mR/hR EILVER '4EOLITE CPM CPM $/ ========a==s=================s==========c====:===u==============e======= c 0957000 7965.6 SB .5 0.720305 770 1032 12104 5800000 4046.4 5 1,57 0.090296 100 216 1008 .g "7-8290000 0127000 GC38.4 7301.0 4 3 1,27 ,85 0.107037 0.306006 300 490 419 021 3124 0123 ~ er i 9057000 7905.0 2 .42 0.919753 000 2000 15360 0957000 7965.0 1 .06 21.11111 4650 47289 052550 ] j i j~ , W l S'C A S S E T ' / ~ u . ., . - , j , 4 ' N / / .b.,nl . p i . T ~ 4 eiscass [ '6;l:.. g rib y, \ ~ + myvy E '8 3 7,' .,1 s o) L 't p- , y ,s i , / w!?! = 21 e .ma ' 0 v e,k V ) . ./ = .5% = wait n 79 .a i ,, / , . ,,p*
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- X 10E-0 rR/HR CPM CFM c=====s======tus======c===s=======:=====s=======s=====r===z=====s:ss====
10790000 0632 SB .5 1.117203 1190 2503 10C59 e 5800000 4040.4 0 1.60 0.075308 130 169 1258 8200000 6030.4 5 1.57 0.141975 240 310 2371 1 9 9127000 7301.6 4 1.14 0.251051 300 504 4200 , D!,57000 7005.6 3 .72 0.402716 600 1081 8001 .i l 10790000 8032 2 .3 1.007407 1500 4273 31854 / 10790000 0032 1 .0G 02.40740 7130 72593 641204 'N- , , -~ WIS C A S SET ; q )x..c ~ s ~ . / .' g N y, . .l M * l N ( 4 .u.is .* / .. e j .')gs u > y/__ ~ e . .s .. ,? =W f ,s A .s , . <r'.. e ' ' 4 i A> f ID = / )4 .a . . . wa n a ,y jN ca ,. ., q qh i o . .c 4 , o q.h / i ,+, -, s .j m~ .ia) psa nl s . . t !' W yo- d.. ~ W d [h t . yy g - w g ~ , s o ( '/ , y A, l/ t 3.o _s& l}= Q .i=,==mgg,- / 5 m p. A. - e , q 020NE 18, a f' k' . '. F ' / , /' dif ' .f . . .. s L ~ f , ,r%'* , s ' I := W fl . , kn , . p s i g,. r# , , y/ , . p j ,,. r.' r g < g e ,,, , ,7 3 . )n ". p g) a y us , c,. m ~ ./7 r=r.4 V 3 k > , e ;;.
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. = l 2 M I. s .. ; . i, F #;_, I p , : b.q ,i,,. . tdOi5 ' -j"f "' ' ^ f . t / * -- .m= 1 _ l g l' l ( x 7 Nl.c( l. ,, M y ?./ W 'a .)e= l k=l .4 i o . + . . .. ~ n % ..). - 9 r!CURr. 9.7-6 Of f. Site Radiological Corula tions at Cicck time 21:00-21:15 GAMMA RM-14 GAM-11 g- REL RATE REL HATE 11G I-131 PLUME DICTAtJCE NO MILE 3 CO!!C 1-131 . .DOCE RATE 15 CF S1 L v t.;t Zh.v;, f; t. l uCi/cc uCi/see uCi/sce j X 10E-6 mR/HR CPM CFM i .
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- 0. M 7 901 0."!92SJ 870 17C1 12060 3 5296 .5 2.401401 1950 LLL3 41441 11620000 i
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~ f,. ,, P 1 ~Y.... 1 . h(*Y e l g , Page ') . 7 - 3 0 g5 % .+ o j , ~\ b o l . . .Y u. \ " F1GURE 9.7-7 / al off-site P.adiologncal Conditions at Clock Time 21:1',-21:30 w b REL RATE REL RATE PLUME DIGTANCE CONC. GAMMA RM-li' SAM-31 e br' liG I-131 11 0 MILES I-131 DOSE RATE 15 CF uC1/nec uC1/sce uC1/cc SILVER ZCOLITE ' X 10E-6 mR/HR CPM CIM ==st:me=========sss::=:r=ce=r===z:zc=======:2:=z====ser====s=:r=====z=== a 124b0000 9060 ED .5 1.290123 1370 2890 21545
- 5800000 4G40.4 8 2.40 0.050370 100 113 641
.0290000 6630.4 7 2.16 0.090740 180 203 1515
- 9127000 7301.0 0 1.74 0.144444 260 324 2412 9957000 7505.0 5 1.32 0.229012 370 513 3825 i 0.474074 050 1002 7087 10790000 8032 4 .9 3.
110.20000 12450000 9006 9960 3 2 .0 .3 0.987054 2.000493 1140 2090 2212 5060 10493 44430 h 7 12450000 9900 1 .06 37.34507 0230 03054 023673 , , 6\ , i ' W l S'C A S S E T .- j w s sa p - 3 of, , g - a s { a 'S N hk 4 y wiscAss i.. V l' / - < /E c / / s ! =i v y / . ~ d u, ( 3 k s , 9 l I . ., ( - I 15~ ' v ~f" : ,s P gy f ff 4 e a 3 d (q ; 7l ~l ?f fd. a# 3 t. G c3, A~ l 3 t % 3. o . " ,' /,% / , .=ak = ,' ba g d' =M 4} * ~' Ur Y ,, flg- + .' $ y j *W 23: gEile,
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- p. CONT AINMENT H ATCH ARE A
\, 1 Counter inst. Type & No. Date Eff; NOTE: Dose Rate in MR!HR Time i Contamination readings are circled 2 Bkg. in DPM/100 cm Tech. NOTE: All Dose Rate reading in MR/HR. All Contamination readings are circled in DPM/100cm2 , i ( O ill (A S9 RAY t 'P)L bG . CTmT Y )\ p Tc h Gp, N4 I t Q v 6 $ 6 6 T S uP g O Y / i s 40 P'" -- 9 .- w:, l l Rev, c MAIEE YANKEE 4/16/67 CRAOED EXERCISE Page 9.9 1 JUNE 1957 clock SCENARIO DOSE P ATE ( R/h r ) == TIME TIMI(ein.) A , 1716 0 AS kEAD 1600 45 As READ f j 1900 105 AS REAL g l 19th 2000 160 165 10 5.0 hb Y f I p 2015 18C 2$ t ;030 195 76 ?CC 210 10: 21( ; db 17+ p,e I ;11! 44; ,s 1 213L 15 It, l l 2145 75 ! y gg M 8 - , ~ , ;7-; 2% , g 9 15- MY llP 13'i M2 M AINE Y ANKEE ~ ATOMIC POWER COMPANY s CONTAINMENT HATCH AREA V). ' Count:r Inst. Type & No. Date Eff, NOTE: Dost Rate in MR/HR Time Contarnination readings are circled 2 . Bk g. in DPM/100 cm Tech. l l NOTE: All Dose Rate readings in MR/HR. All Contamination readings are circled in DPM/100cm2, i si ca s yna-( O hLbG , CTMT q gpTch E, Nk (7 ',
- 0
\ g b b 6 xs up \ O d [ t k LM ,a s" 9 .. .e , O i l l \ pov. O MAINE YANKEE 4/1L/67 CRADED EXERCISE Page 9.9-l JUNE 1967 Cl4CK $CENAR10 DOSE RATE (R/hr) TIMI TIMEltin.) A 1785 0 AS REAL 1000 45 AE R ear-1900 105 A3 REAL 1955 160 5.0 2000 165 10 7 2015 IGC 25 203C 195 75 l 2C45 210 100 l ;1CC ..t 175
- q l 111!. 240 200 2136 s'S 150 l yyte 2145 27C 75
,,, 22co 285 25 'j . 2;15 30. y a f d' MY HP.3172 MAlNE YANKEE ATOMIC POWER CO. ,- SPRAY BUILDING ROUTINE SURVEY PAGJ 1 V) INST SURVEY INST & NO DATE EFF. NOTE: Dose Rate in MR/HR TIME Contamination readings are circled BKG, 2 TECH in OPM/100 cm Emen L'9""*Y deege n,c y 8"Netch s s u' 5 E l. ,
- e~s 8 .
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M I h ai me4-+ ,+ a. $9 l g :. /- Rev. C , Mall.E YANKEE 4/16/8, GRADED EXERCIEE Page 9,9., JUNE 1967 Cl4CK SCENARIO FCSE RATE ( stP /t r
- TI VE TIME (sin.I A b P- (o f 1715 0 AS READ AS REA; M 941 P.12 e F-12 looo 45 As aEAD o E 3B 15 B
- 19oo ic5 u atu As nEn u aEc)
. (% "I . 1955 160 1,CCO 2 CG O 1 2WC 16 5 1,' C 3.0 / R 2015 166 2,CLO 4,0(: C 20 0 195 3,s 0( (, LADDEA iC4' 21L 4,0( C E CC.
- 21. . . u 5,.s it ,6 2115 240 6,000 19,00 .
2130 255 7,000 21,00. .- 214S 2? C+ 0,00C
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e100 265 7,000 . , vu 2215 30; 1,C00 3,CCC MY HP 7 71 Rev. 2 RADI ATION SURVEY - PRIM. AUX. BLOG - 2 nd FLCOR - Rev. O MAINE YANKEE 4/16/67 cRieED EXERCISE Page 9.9-3 COUNTER " " *'87 - O VEY INST. 6 NO.
- CLCCK ECENARI D fr RATES (mR/hr) CONATMINATION (& cM '
C ( )ICIENCY TIME TIME (min.) A B C A B 0 300 AS PEAD AS READ 100,000 AS READ 10 F Err - 1715 45 300 AS READ AS READ 100,000 AS RED AS REI!~ 1600 105 300 AS READ AS READ 100,000 AS READ AS RE E i 1900 I 160 305 5 5 100,000 AS READ AS READ 1955 7 %_ 2000 165 310 10 10 100.000 AS READ AS RIII' j y p - 2015 180 315 15 15 100,000 AS READ AF F.LA i I, t 320 20 20 100,000 AS READ AS RLA'. 195 ~*~ [ 2030 2045 210 325 25 25 100,000 AS READ AS P E A. , [-, m/ 225 330 30 30 100,000 AS READ Af REll , - 2100 240 340 40 40 100,000 AS READ AS RElf 2115 255 350 AS REA0 AS READ 100,000 AS READ AS RE7- -*- 2130 100,000 AS READ AS ret.. 2145 270 345 AS READ AS READ , 285 310 AS READ AS READ 100,000 AS READ AS l.1 ; 2200 g .. - 2215 300 300 AS READ AS kEAD 100,0C0 AS READ AI kt?2 'O 1 i~ / / i,, 'd 1 V ! J g yW D o t Y pf Q / l O 'p I P-lM R l d 1 > CG J O o 'm o -I c ist i 1 (A f - J // /w i e-es s i 8 g O / / / O ( _ r O { ._ _ _ o o o O O es.fi MuP Itc 10 O w on. e % e o l i l e f I - i o _J N, NOTE:(t) DOSE R ATE REAOINGS INOCATE t.*CCM/HR AT Y.mST LEVEL UNLESS OTiiERWISE SPECIFIED. (2)CCNTAv! NATION SU5MY WSORTED IN CF'M/:00 cu UNITS INDICATE LCGTICN a ACTtvlTY WITiletRes F D NC AOINr. MY HP-204-25 MAINE YANKEE ATOMIC POWER COMPANY fN] L AUX FEED PUMP ROOM m HE y m EE Rev. 1 GRADED EXERCISE 5/20/87 JUNE 1987 Fage 9.9-4 C14CK SCENARIO DOSE RATE TIME TIME A Counter inst. Type & No. ,,33 , 3, ,,,, 1800 45 As Read Eff. 19 15 As Read 1955 160 1.4 2000 105 1.7 Bkg. 2015 180 2.0 2030 195 2.0 NOTE: All Dose Rate readings in MRlHR. All Contamination readings are circled in DPM/100cm'. 2$$ 2:15 240 [{ 5.7 2130 255 As Read 2145 270 Ae Pead 2200 285 As Read 2215 300 As Read f' l/////////// CTMT Purge Values ////// // ///// p j L%cd) ,O / () O / /// // ///\ )APD O Y//// //////// / / / // f / r , - !!/ / !/ / / / /// // /AFW / /}A 39 l l /), Motor / / W 3 ' l / l ATW A 201 g ' ~ ~ , ? ji , /' { gW A 101 I- * /' I U /t / i P 25 A } / /t % Q *olo, U Hydraulic oery! h8d S.D. / P 25 C Tank 6dal Panel \%eG/ // PRIMARY [// ' VENT / '/ i7 // / //%y// ////// ( STACK . 1 i l/ // / // / // // ////////// \ l 4 MY-HP-6 71 Rev. 3 - RADIATION SURVEY -PRIMARY AUXILIARY BLDG. 1ST FLOOR f} s COUNTEp SURVEY IN8T. & NO. PA 6 el. It' c,,cK ,.,,, ,a e DATE. cRActo ExtRcIst ,c,yx,,, JUNE 1987 @'W.3 oc3, 332, ,,,3f,g EFFICIENCY tur rmt a e BKG m5 0 As Read As Read 1800 45 As Read As Read 1900 105 As Read As head 1955 100 - 10 As Read ~ ~ 2000 165 12 As Read..- O - . . - - O -20is iso 15 As Read .,f., O 2030 195 45 As ReaJ. ' ' k, )L., _ 2045 210 52 As Read 53 As kend ~ . /. ~ (_** 2100 2115 225 240 45 As Read -i ! .. 2130 255 As Read ~ As Read .E O r
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A,e so-pts , l l U l J t ( ) NOTE: (1) DOSE RATE READINGS INDICATE MREM /MR AT WAIST LEVEL UNLESS OTHERWISE SPECIFIED. (2) CONTAMINATION SURVEY REPORTED IN DPM/100CM2 UNITS INDICATt! LOCATION & ACTIVITY WITH CIRCLED READING. l MY HP-8 71 Rev.1 RADIATIDN SURVEY-PRI. AUX. CLDG.- 3rd FLOOF; DATE ~ SUfBEY INT. & N0. Tiug KFFICIM E T(Cal C~ mm 8AWK5 = L u s(-) _ , s O M__ . DH , PLEHum 0 - l . EE Ju - 'l MAINE YANKEE Rev, 1 GRADED EXERCIEE 5/20/87 ;j JUNE 1987 Fege 9.9-6 CLOCK SCENARIO DOSE RATE (mR/hr) ' TIME TIME A B l f45h, 1715 0 As Read As Read g m , O fA4IE[ 1800 , 45 As Read As Read 1900 105 As Read As Read 1955 160 37 As Read , 42 As Read 2000 2015 165 180 51 As Read O 9 2030 195 67 As Read As Read ) -i I 2045 210 95
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! r. ^ MAINE YANKEE ATOMAC POWER COMPAfW ' j i y .STE@ AND FEED VAL;VE HOUSE $ ' = [; , < ,p , f. c ,, j ,. [ t-CCUNTER z.,' ,1NST. *iVPE & NO. I DATE .', ,s,3- 1 r .,, J ' \'
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- 'BKG. :i .7ECH. , , . 1 NOTE: All Dose Rata in MM4R. All Contamination Readings in DPM/100ern?. t; i ? < ) .- i ( l , < G , p. l ") ,- + ! !'d i ** /b j.U, ~ PER7)n4nEL- ... f<# f T-I %, . W f, J hT P4 1K-l . }, FILD PIA 4P ggg g Pff TRIW.H I O l }- [ l ca =1 b [* k # m t,Y 00ER AA C M") . 4 3 # INST R ACH% i I/' , .'.J f{I 'f f MAINE YANKEE GRADED EXERCISE Rev. 1 5/20/67 ~! JUNE 1987 Page 9.9-7 (( ; , CLOCK BCENARIO DOSE RATE (R/hr) l 6 TIME TIME A B r 1715 0 As Read As Read ; J. 1000 45 As Read As Read ) ' 1900 105 As Read As head i 1955 160 3.0 1.5 2000 165 0.0 2.0 % 2015 180 13 5.0 1 .. ) 2030 2045 195 210 45 55 21 23 .+ 2100 225 ?! 31 f 2115 240 9C 42 '!. 2130 255 60 27 b' 2145 270 45 21 2200 ' '
- 285 221b 300 e.v ea
O 1 MAINE YANKEE GRADED EXERCISE JUNE 1987 j l 10.0 METEOROLOGICAL DATA 6 O 1504e Revision 1- ;) ' - 05/20/87' l
- t : -Page 10.0-1 :
-N. I
- 10.0 METEOROLOGICAL DATA / JUNE 1987
'i l i i I Primary Tower Average Average Delta Time.. Wind Speed (MPH) Wind Direction Temperature T Total (Local) 10M 30M ; 10M 30M 10M( F) 10-30( F) Precip 1600 .4.50 6.20 .148. 137. 61.60 -1.00 0.00- ; ,-~s 1700 4.20 7.00 146. 145. 60.40 -1.00 0.00 .N_, ) .1800 ,2.90 4.00 140. 135. 58.90 -1.00 0.00 1900. 2.00 1.00 187. 194. 57.60 0.00 0.00-2000 1.70 1.70 155. 156. 57.60 .70 0.00 2100- 1.20 .60 170. 178. 57.60 .60 0.00 2200- 6.60 6.60 70. 78. - 56.10 .60 0.00 2300 5.40 5.60 359. 5. 55.50 .50 0.00 2400 5.20 6.00 350. 5. 55.40 1.20 .0.00
- Forecasts will be provided in NWS format on request and by YAEC *
- meteorologist from ESC, Framingham, Massachusetts.
- P.M. - Conditions similiar to June 6-7, 1986.
- 1504e
Rev 1 5/19/87 n Page 10. 0-2 s )- %J 10.1 METEOROLOGICAL DATA / JUNE 1987 NWS Forecast A weak high pressure system will dominate the central and coastal Maine areas late Wednesday thru Thursday. Light variable winds with a chance of an occassional shower. High temperatures in the mid to upper 60's. Variable cloudiness with fog likely in low lying areas Wednesday night and Thursday morning. V , General area forecast available locally.after 1800, , + June 1987. This data should only be provided +
- after a player demonstrates their ability to obtain *
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MAINE YANKEE NUCLEAR POWER STATION ] I GRADED EXERCISE JUNE 1987 d To be Provided to the ESC Meteorologist by the ESC Controller at 1945 FORM: YA-REG-410.1 REVISION: 0 DATE: 3/87 1 WEATHER FORECAST FOR SITE MAINE YANKEE' Date'of Forecast: June 10, 1987 Time of Forecast: 2000 Current Site Meteorology.(as of' 1930 ): Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower 2.0 mph' '190 deg from 0F' - in/15 min ' e'i Upper 1.0 mph 190-deg from 0.0 0F E - Forecast Site Meteorology:- . Delta-Time , Wind Speed Wind Direction Temperature Stability Precipitation - in/15 min ~ A. 2000-2100 Lower 2 mph 180,deg from 0F Upper- 2 mph 180 deg from 0F D B. 2100-2200 Lower 2 mph 360 deg from 0F - in/15 min Upper 2 mph 360 deg from- 0F D C. 2200-2300 Lower 2 mph 360 deg from 0F - in/15 min Upper 3 mph 360 deg from 0F D National Weather Service Forecast for site region: A weak high pressure system will dominate the central and coastal Maine areas late ' Wednesday through Thursday. Light variable winds with a chance of an occassional shower. High temperatures in the mid to upper 60's. ~ Variable cloudiness with fog likely in low lying areas Wednesday night and Thursday morning. Severe Weather Reports: I I'g '** NOTE ** Winds are light and variable; a wind shift may occur around 2200, A 'resulting in northerly winds. ~ 5484R i (7 Ravision 1 5/20/87 ,as Page 10.0-8 -Q_ MAINE YANKEE NUCLEAR POWER STATION GRADED EXERCISE JUNE 1987 To be Provided to the' ESC Meteorologist by the ESC Controller at 2045 - FORM: YA-REG-410.1 ' REVISION: 1 DATE: 3/87 WEATHER FORECAST FOR SITE MAINE YANKEE Date of Forecast: June 10, 1987 Time of Forecast: 2100 Current Site Meteorology'(as'of 2030 ): Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower 1.7 mph 155 deg from 0F - in/15 min Upper 1.7 mph 155 deg from -0.70 0F E )ForecastSiteMeteorology:- Delta- . Time Wind Speed Wind Direction Temperature Stability Precipitation A. 2100-2200 Lower 2 mph 180 deg from 0F D - in/15 min Upper 2 mph 180 deg from 0F B._2200-2300 Lower 2 mph 360 deg from 0F D VL in/15 min i Upper 3 mph 360 deg from 0F C. 2300-2400 Lower 2 mph 360 deg from 0F D VL in/15 min Upper 3 mph 360 deg from 0F National Weather Service Forecast for site region: A weak high pressure system will dominate the central and coastal Maine areas late . Wednesday through Thursday. Light-variable winds with a chance of an occassional j shower. High temperatures in the mid to upper 60's. Variable cloudiness with fog' ! .likely in low lying areas Wednesday night and Thursday morning. Severe Weather Reports: ** NOTE ** Winds shift expected around 2200; slight chance of an accompanying light shower. Fog likely in areas south and east of the plant early a.m. t ~ Precipitation (in/15 min) Very Light (VL) Light (L) Medium (M) Heavy (H) .01 .05 .05 .09 .10 .19 .20 .30 '5484R ; Revision 1 5/20/87 Page 10.0-9 MAINE YANKEE NUCLEAR POWER STATION GRADED EXERCISE JUNE 1987 To be Provided to the ESC Meteccologist by the ESC Controller at 2145 FORM: YA-REG-410.1 REVISION: 1 DATE: 3/87 WEATHER FORECAST FOR SITE MAINE YANKEE Date of Forecast: June 10, 1987 Time of Forecast: 2200 Current Site Meteorology (as of 2130 ): Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower 3.5 mph 76 deg from 0F - in/15 min p- , Upper 3.6 mph 76 deg from -0.60 0F D ) - ' Forecast Site Meteorology: Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation A. 2200-2300 Lower 2 mph 360 deg from 0F D - in/15 min Upper 3 mph 360 deg from 0F B. 2300-2400 Lower 2 mph 360 deg from 0F D VL in/15 min Upper 3 mph 360 deg from 0F C. 2400-0100 Lower 2 mph 360 deg from 0F D VL in/15 min Upper 3 mph 360 deg from 0F National Weather Service Forecast for site region: l A weak high pressure system will dominate the central and coastal Maine areas late I Wednesday through Thursday. Light variable winds with a chance of an occassional shower. High temperatures in the mid to upper 60's. Variable cloudiness with fog likely in low lying areas Wednesday night and Thursday morning. 1 Severe Weather Reports: ** NOTE ** Precipitation less likely this evening; clouds diminishing and fog likely after midnight; low temperature tonight 450F. 7 } Precipitation (in/15 min) Very Light (VL) Light (L) Medium (M) Heavy (H) .01 05 .05 ."o .30 .19 .20 .30 5484R}}