ML20085C379
| ML20085C379 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 09/05/1991 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML19343D736 | List: |
| References | |
| NUDOCS 9109110136 | |
| Download: ML20085C379 (359) | |
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{{#Wiki_filter:- - - - - - . . - - - _ _ . _ _ _ _ _ _ _ _ _ . _ . VERMONT YANKEE NUCLEAR P0'JER STATION . l. EMERGENCY RESPONSJ PREPAREDNESS EXERCISE 1991 o N
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l l Rev. O L-- VERMONT YANKEE NUCLEAR POWER STATION , EMERCENCY RESPONSE PREPAREDNESS EXERCISE -- 1991 ! TABLE OF CONTENTS -; J S e c tior. Title iltL. i 1.0 INTRODUCTIOH 1.1 Exercise Schedule 0 1.2 Participating Centers'3gencies c 0 1.3 Abbreviations and Definitions 0 1.4 References 0 2.0 EXERCISE OBJECTIVES AND EXTENT OF PLAY 2.1 Vermont Yankee 0 2.2 State of Vermont 0 2.3 State of New Hampshire 0 2.4 Commonwealth of Massachusetts 0 3.0 EXERCISE GUIDELINES AND SCOPE 3.1 Exercise Cuidelines 0 3.2 Player Instructions and Ground Rules 0 3.3- Procedure Execution List 0 4.0' CONTROLLER AND OBSERVER INFORMATION 4.1 Assignments 0 4.2 Controller and Observer Exercise Guidance 0 4.3 Controller and Observer Evaluation Criteria 0 5.0 EXERCISE SCENARIO 5.1 Initial Conditions 0 5.2 Narrative Summary 0 5.3 Scenario Timeline 0 5.4 Petailed Sequence of Events 0 6.0 EXERCISE MESSAGES 6.1 Command Cards 0 6.2 Message Cards 0 7.0 STATION EVENT DATA 7.1 Events Summary 0 7.2 Event Mini-scenarios 0 i
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VERMONT YANKEE NUCLEAR POWER ST).'.'ON EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 TABLE OF CONTENTS Section Title Es1. 8.0 OPERATIONAL DATA 0 9.0 RADIOLOGICAL DATA 0 9.1 Area Radiation Monitors 0 9.2 Process Monitors 0 9.3 In-Plant Radiation Levels 0
'3 . 4 Plant Chemistry Data 0 9.5 Radiological Sample Dose Rates 0 9.6 Plant Vent Stack Release Data 0 9.7 Field Monitoring Maps and Data 0 10.0 METEORO1DCICAL DATA 10,1 On-Site Meteorological Data 0 10.2 General Area NWS Forecasts 0
- l. 10.3 NWS Surface Maps 0 11
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( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 1.0 JNTRODUCTION
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 a 1,1 fdERCISE SCHEDULE y l l
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(._ Page 1.1-1 l I VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 l 1.1 _ EXERCISE SCHEDULE A. Controller and Observer Briefinz Date: November 5, 1991 Time: 9:30 a.m. Location: Vermont Yankee Corporate Office, Brattleboro. Vermont
Purpose:
Briefing on Exercise Activities and Assignments Attendees: Vermont Yankee and Yankee Atomic Controllers and Observers B. Controller and Observer Plant Tour Date: November 5, 1991 - Time: As necessary (contact Lead Controller) Location: Emergency Response Facilities and Affected In-Station Areas e
Purpose:
Familiarize Controllers and Observers with Affected Areas 8 1. Attendees: Vermont Yankee and Yankee Atomic Controllers and Observers C. NRC Briefine Date: November 5, 1991 Time: 2:00 p.m. Location: Vermont Yankee Corporate Office, Brattleboro, Vermont
Purpose:
NRC Briefing and Review of Exercise Scenario Attendees: NRC Evaluators D. Exercise Date: November 6, 1991
- Time
- To Be Announced Location: Vermont Yankea Emergency Response Centers and Designated Statts' Emergency Response Centers
Purpose:
Emergency Response Preparedness Exercise Attendees: Vermont Yankee Emergency Response Organization, State and-local Emergency Response Organizations from Vermont, New
ampshire and Massachusetts, Controllers and Observers, NRC Evaluators and Yankee Atomic Engineering Support Center Staff l
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Rev. 0 ' 6' Page 1.1 ( VERMONT YANKEE NUCLEAR POVER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 1.1 EXERCISE SCHEDULE (continued) E. Exercise Debriefing Date: Day of Exercise Time: To be announced during or immediately following the exercise Location: To be determined by the respective Emergency Response Facility Controller
Purpose:
Debrief Players, Observers and Controllers Attendees: Controllers, Observers and Key Participants F. Controller Debriefing Date: After Exercise Debriefing Time: To be announced f- Location: To be announced
Purpose:
Exercise Debriefing Attendees: Exercise Coordinator and Controllers C, Exercise Critiaue Date: November 7, 1991 Time: 1:00 p.m. Location: Vermont Yankee Corporate Office, Brattleboro, Vermont
Purpose:
Utility Self-Critique /NRC Preliminary Findings Attendees: Verwont Yankee Management, NRC Evaluators, Exercise Controllers (Observers as needed) and Vermont Yankee Key Participants
A VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCIJE i 1991 J j-G .h ' 4 1.2 PARTICIPATING CENTERS /ACENCIES 4 Y i k a 4 4 4 6 4 J l b
7r Rev. O Page 1.2-1 l l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 1.2 PARTICIPATING CENTERS / AGENCIES VERMONT YANKEE NUCLEAR POWER CORPORATION Vermont Yankee Nuclear Power Station:
- Control Room (notification and communications functions only)
. Technical Support Center (2nd floor of Administration Building) e Operations Support Center (1st floor of Administration Building) e Energy Information Center (Governor Hunt House)
Vermont Yankee Training Center:
- Simulator Room (Control Room functiont, 1st floor of Training Building) e Emergency Operations Facility / Recovery Center (1st floor of Training Building)
Vermont Yankee Nuclear Power Corporate Offica:
- News Media Center (Vermont Yankee and State representatives from VT, NH and MA)
YANKEE ATOMIC ELECTRIC COMPANY Yankee Atomic Corporate Headquarters (Bolton, Massachusetts); e Engineering Support Center STATE OF VERMONT Vermont Emergency Management Agency (State Response Agencies): a Emergency Operations Facility / Recovery Center (State representatives located in the State Room) e Emergency Operations Center (Waterbury, Vermont)
l Rev. O g Page 1,2-2 j x e Incident Field Office (Dummerston, Vermont) Local Emergency Response Centers (Local Response)
- Brattleboro - Brattleboro Town Hall e Vernon - Town of Vernon Fire Station
- Dummerston - Dummerston Town Office Building
- Cuilford - Guilford Town Fire Department STATE OF NEW RAMPSHIRE New Hampshire Office of Emergency Management (State Response Agencies):
- Emergency Operations Facility / Recovery Center (State representatives located in the State Room)
- Emergency Operations Center (Concord, New Hampshire)
- DPHS Radiological Units (Concord and Keene, New Hampshire)
S = Southwestern Fire Mutual Aid Dispatch Center (Keene, New Hampshire)-
- Incident Field Office (Keene, New Hampshire) e State Police Communications Center (Concord, New Hampshire)
Local Emergency Operations Centers (Local Response) e Hinsdale - Hinsdale Fire Station / Town Hall e Chesterfield - Chesterfield Town Office e Richmond - Richmond Civil Defense Building e Winchester - Winchester Emergency Service Building - e Swanzey - Swanzey Center Fire Station e Keene - Keene Fire Station
- Reception Center - Keene State College, Spaulding Gymnasium COMMO%'EALTH OF MASSACHUSETTS Mas. achusetts Emergency Management Agency (State Response Agencies):
- Emergency Operations Facility / Recovery Center (State representatives located in the State Room)
- Emergency Operations Center (Framingham, Massachusetts)
- Area IV Emergency Operations Center (Belchertown, Massachusetts)
Rev. 0 f'- Page 1.2-3
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e Area IV Emergency Operations Center (Belchertown, Massachusetts)'
- Massachusetts Depcrtment of Public Health (EOF, Brattleboro,-Vermont)
Local Emergency Operations Centers (Local Response) e Greenfield - Fire Station e Leyden - Fire Station
- Bernardston - Fire Station e Gill - Fire Station e Northfield - Town Hall
* -Warwick - Fire Station 5
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-VERMONT Y!.NKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS-EXERC13E 1991 1.3 ABBREVIATIONS AND DEFINITIONS
Rev. 0 Page 1.3-1 VERMONT YANKEE NUCLFAR POWER STATION EMERGENCY RESPON PREPAREDNESS EXERCISE i991 1.3 ABBREVIATIONS AND_ DEFINITIONS A. Abbreviations o AO - Auxiliary Operator o A0G - Advanced Off-Gas System o APRM - Average Power Range Monitor o ARM - Area Radiation Monitor o NNS - Anticipated Transient Without Scram o CR - Control Room / Control Rod o CRD - Control Rod Drive
# o CS -
Core Spray o DW - Drywell o EAL - Emergency Action Level o ECCS - Emergency Core Cooling System o ENS - Emergency Notification System o EOC - Emergency Operations Center o EOF - Emergency Operations Facility o EPR - Electric Pressure Regulator o EPZ - Emergency Planning Zone o ESC - Engineering Support Cente-o FEMA - Federal Emergency Management Agency o FW - Feedwater 214Le s--_________---___.------_-___---_--_-_-_-_.___--_-_ - - _ _ - - _ _ . _ _ . _ _ . _ _ _ _ - - . _ _ - - _ _ _ _ _ -
l Rev. 0 Page 1.3-2 o HPCI - High Pressure Coolaat Injection o HPN - Health Physics Network o HRNG - High Range Noble Gas o LPCI - kw Pressure Coolant Injection o MPR - Mechanical Pressure Regulator o MSIV - Main Steam Isolation Valve o NAS - Nuclear Alert System o NG - Noble Gases o NRC - Nuclear Regulatory Commission o OSC - Operations Support Center o PASS - Post-Accident Sampling System o PCIS - Primary Containment Isolation System o PED - Plant Emergency Director o PVS - Plant Vent Stack o RA - Radialogical Assistant o RCIC - Reactor Core Isolation Cooling o REMVEC - Rhode Island, Eastern Massachusetts, and Vermont Energy Control. o RPS - Reactor Protection System o RR - Reactor Recirculation System o RRU - Reactor Recirculation Unit o RWCU - Reactor Water Clean-Up o Rx - Reactor 2144e
Rev. O Page 1.3-3 o SBGTS - Standby Gas Treatment System o SJAE - Steam Jet Air Ejector o SRM - Site Recovery Manager / Source Range Monitor o ISC - Technical Support Center o VY - Vermont Yankee o VYNPC - Vermont Yankee Nu: lear Power Corporation o VfNPS - "Jermoat Yani 4laclear Power Station o YNSD - Yankee Nuclear Services Division e ( l 2144e l
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Rev. O Page 1,3-4 k_ B. Definitions o Alert - An emergency classification which is defined as an actual or potential suostantial degradation of the level of safety of the plant. o Controller - A member of an exercise control group. Each Controller may be assignsd to one or more activities or f unctions for the purpose of keeping the action going according to a scenario *esolving differences. ervising and assisting as n~eved. o Critique - A meeting of key participants in an exercise, usually held shortly after its conclusion, to identify weaknesses and deficiencies in emergency response capabilities . o Emergency Action - Specific instrument readings, system Levels or event observation and/or radiological levels which initiate event clarsification, notificrtion procedures, protective actions, and/or the mobilization of the emergency response organization. These aro specific threshold readings or observations indicating system failures or abnormalitics. o Emergency Assistance - General term used to refer to the Personnel radiation monitoring teams, sample analysis team, and in-plant search, and rescue teams. o Emergency Operations - Areas designated by state / local Center represer .atives as Emergency Plan assembly areas for their respective staffs. o Emergency Operations - An emergency response facility Facility / Recovery (Vermont Yankee Training Center, Center Brattleboro, Vermont) which evaluates off-site accident consequences and coordinates emergency response and assistance with all off-site agencies. 2144e
R v. O Page 1.3-5 ( o Emergency Planning - The areas for which planning is Zones recommended to assure that prompt and effective actions can be taken to protect the public in the event of an accident. The two zones are the 10 mile radius plume exposure pathway zone and the 50-mile radius ingestion exposure pathway zone. o Engineering Support - A YNSD emergency response f acility Center (Yankee Atomic Electric Corporate Headquarters) established to provide additional engineering support to the affected site in plant assessment and recovery operations. Exercise - A demonstration of the adequacy o of timing and content of emergency implementing procedures, methods, and equipment.
! An exercise which tests as much of o Full Participation -
Exercise the licensee, state, and local plans as is reasonably achievable withcut mandatory public particip; tion. o General Emergency - An emergency classification which is defined as actual or imminent substantial core degradation or melting with potential for loss of containment integrity, o News Media Center - An emergency response facility (VYNPC Corporate Offices, Brattleboro, Vermont) dedicated to the news media for the purpose of disseminating and coordinating information concerning accident conditicas. All activities conducted within this center will be the responsibility of the Vermont Yankr$ Nuclear Informatfor Director. 2144e
4 Rev. 0 Page 1.3-6 o Observer - A member of an exercise control group. Each Observer may be ! assigned to one or more activities or functions f or the purpose of evaluating. recording, and reporting the strsngths and weaknesses, and makirig recommendations f or improvement. o Operations Support - An emergency response facility Center (1st floor, Administration Building) established to muster 4 skilled emergency response personnel to perform activities in the plant. d o Protective Action - Those emergency measures taken to effectively mitigate the consequences of an accident by minimicing the radiological exposure that would likely occur if such actions were not undertaken. o Protective Action - Projected radiological dose Guides values to the public which warrant protective actions following an uncontrolled release of radioactive material. Protective actions would be warranted provided the reduction in the individual dose is not offset by excessive risks to individual safety in implementing such action. o Scenario - The hypothetical situation, from start to finish, in ars exercise which is the theme or basis upon which the action or clay of the exercise follows. o Site - That property within the fenced boundary of Vermont Yankee which is owned by the Vermont Yankee Nuclear Power Corporation. o Site Area Emergency - An emergency classification that indicates an event which involves likely or actual major failures of plant func'. ions needed for the protection of the public. 2144e
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P.ev. O Page 1.3-7 I k. o Small-Scale Exercise - An exercise which tests as much of the licensee emergency plan and procedures with minimal, voluntary participation of state and local government agencies. o Technical Support - An emergency response facility Center (2nd floor. Administration Building) with the capability to assess and mitigate the accident using plant parameters and highly qualified technical personnel. Also, assists in accident recovery operations. o Unusual Event - An emergency clar.sification that indicates a potential degradation of plant safety margins which is not likely to affect personnel on-site or the public of f-site or result in radioactive releases requiring off-nite monitoring. o Yankee Nuclear Services - A division of Yankee Atomic 7 Division (YNSD) Electric Company. An Engineering support organization which provides emergency response support to Vermont Yankee upon request. 2144e i
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2 d t+ , VERMONT YANKEE NUCLEAR PO'JER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991
1.4 REFERENCES
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i Rev. 0 Page 1.4-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991
1.4 REFERENCES
- 1. Vermont Yankee Nuclear Power Station Emergency Plan t
- 2. Vermont Yankee Nuclear Power Station Emergency Plan Imp'aementing Procedures
- 3. Vermont Yankee Nuclear Power Station Final Cafety Analysis Report
- 4. Vermont Yankee Nuclear Power Corporation - Communications Departaont Emerfency Response Plan and Procedures
- 5. Vermont Yankee Nuclear }awer Station Emergency Operaf.ing Procedures
- 6. Vermont Yankee Nuclear Power Station Core Damage Assessment Methodology
- 7. Yankee Atomic Electric Company
- a. " RASCAL" Computer Model, Version 1. Modification 2
( b. "METPAC" (Meteorological TACkage) Dose Assessment Computer Model, Version 4.0
- 8. Martin, C.F. , et al., " Report to the NRC on Guidance for preparing Scenarios for Emergency Preparedness Exercises at Nuclear Generating Stations," March 1986, USNRC. NUREG/CR-3365
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4 VERMONT YANKEE NUCLEAR POWER STATION EMERGCNCY RESPONSE PREPAREDNESS EXERCISE 1991 2.0 EXERCISE OBJECTIVES AND EXTENT OF PLAY i
l \ VERMONT YANKEE NUC1. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 2.1 VERMONT YANKEE 1
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4 Rev. O Page 2.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 2.1 EXERCISE OBJECTIVES AND EXTENT OF PLAY - VERMONT YA!!KEE Extent of Play A. Accident Assessment ,
- 1. Demonstrate the ability of Control Room personnel to recognize emergency initiating A.1 The scenario events initiated on the simulator events and properly classify the condition provides the operational and radiological data in accordance with pre-established which allows personnel to demonstrate this ;
emergency action levels. objective by implementing Procedure A.P. 3125,
- Emergency Plar Classification and Action Level Scheme.
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- 2. Demonstrate the ability of the Conttol Room and TSC staff to coordinate the assessment A.2 The scenario will provide technical of plant conditions and corrective actions information to players which will allow them to mitigate accident conditions. to analyze plant conditions and propose i corrective actions.
- 3. Demonstrate that information concerning , plant conditions can be transmitted between A.3 Telephone communications links will be . j the Control Room and TSC in a timely manner. established by communicators between the Simulator Control Room and the TSC in order to transmit hey information and data. 4 Demonstrate the ability of the TSC staff to initiate and coordinate corrective actions A.4 The scenario provides events that will enable , 4 in an efficient and timely manner. the TSC to coordinate in-plant corrective l actions thrcugh the use of OSC personnel. i 2160e 4
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p Rev. 0 Page 2.1-2 Extent of Play Demonstrate the ability of appropriate TSC A.5 The scenario includes events which allow for
- 5. discussion between the Control Room, TSC, and staff to participate with Cottrol Room and EOF staff on classification.
the EOF /RC in emergency classification and EAL discussions. Demonstrate the ability to effectively use A.6 ERFIS terminals at the TSC and EOF /RC will be 6. the Emergency Response Facility Information linked to the Simulator Control Room to receive and transmit scenario data. This will System (ERFIS) in the assessment and allow Emergency Response Facility staff trending of plant conditions. personnel the opportunity to demonstrate the effectiveness of ERFIS under simulated emergency conditions. A.7 Scenario events will require Chemistry and
- 7. Demonstrate the ability to assess data from Radiation Protection technicians located at appropriate chemistry samples in' support of the OSC to simulate taking reactor coolant, accident assessment activities and plant containment air, or plent vent stack samples conditions. to assess plant conditions. Sample results will be provided by Observers who accompany the technicians during their sampling activities. (Refer to Frocedure OP-3530, /
" Post-Accident Sampling."?
B. Notification and Communication Demonstrate that messages are transmitted B.1 Various communications links will be
- 1. B.3 established between the emergency response in an accurate and timely manner and that B.4 facilities in order to transmit information messages are properly logged and and data. Record keeping and documentation documented.* (Documentation of emergency will be demonstrated in accordance with repair team dose approvals were not entered Procedure OP-3504, " Emergency rommunications."
into TSC Log Book.) Communications and transfer of data between ) facilities will be evaluated for timelictss and completeness.
- Indicates NRC identified improvement items from the 1990 exercise.
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- Page 2.1-3 Extent of Play I
I 2. Demonstrate the capability to notify B.2 Vermont Yankee staff. NRC, and state i federal and state authorities of emergency authorities shall be notified in accordance I classifications and significant changes in with established procedures. NRC will be i I plant status in accordance with established notified by utilizing the NRC ENS red phone. procedures.* (There was no formal turnover The State authorities will be notified through [ of the responsibility for off-site the Nuclear' Alert System (Orange Phone). notification.)
- 3. Demonstrate that appropriate status boards are utilized _to display pertinent accident I information at the various emergency response facilities.* (EOF did not post that accountability had been completed.
~ OSC status board was very cryptic.)
- 4. Demonstrate that adequate emergency communication systems are in place to facilitate transmittal of data between the l emergency responre facilities and federal and state authorities.
- 5. Demonstrate that off-site monitoring teams B.5 Monitoring teams will be dispatched to the can use appropriate sample points field and directed to specific sample points '
(landmarks) for determining and for monitoring activities. communicating their location. ) 6. Demonstrate the ability to provide adequate B.6 During the period that the off-site monitoring briefings to off-site monitoring teams as teams are in the field, scenario events may conditions and information change.* require that updates be transmitted to the (Off-site monitoricg teams should be teams in the field. briefed as to changes in the emergency action level classification.) i OIndicates NRC-identifled improvement items from the 1990 exercise. 2160e 1
r Rev. O Page 2.1-4 Extent of Play C. Direction and Control C.1 Scenario events require the activation of the
- 1. Demonstrate the proper transfer of Emergency Response Organization. As each accident / management responsibilities from position of authority is activated, the SS/ PED to the Duty Call Officer and responsibilities associated with that position subsequently to the TSC Coordinator and will be asstimed from the SS/ PED up to the Recovery Manager as appropriate.* Recovery Manager.
(Transfer of accident management responsibilities should be clarified.) C.2 All emergency response facilities have
- 2. Demonstrate the capability of key emergency designated coordinators who will direct and 1 response facility management personnel to coordinate emergency response activities in f direct and coordinate their respective their particular area of responsibility.
emergency response activities in an ' efficient and timely manner.* (TSC should priorit ize briefings and control of ESG.) C.3 The Control Room will initially contact the
- 3. Demonstrate appropriate coordination of federal and state agencies, providing them activities with federal and state with appropriate information on plant Sovernment agencies. conditions and emergency status. This function will pass to the TSC and EOF /RC after the facilities are activated.
D. Emergency Response Facilities D.1 Scenario events will require activation
- 1. Denenstrate the ability of station and D.2 and operation of Vermont Yankee emergency corporate personnel to activate and staff response facilities. The Simulator Control
/ the emergency response facilities in a Room, Control Room (communication functions timely manner. only), TSC, CSC, EOF /RC, News Media Center and Engineering Support Center will be activated
- 2. Demonstrate and test the adequacy and in accordance with established procedures.
ef f ectiveness of emergency response Designated plant and corporate emergency facilities, operations, and equipment. response personnel will participate in the exercise.
- Indicates NRC-identified improvement items from the 1990 exercise.
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!- - f Rev. 0 Page 2.1-5 Extent of Play E. Plant Augmentation and Staffing
- 1. Demonstrate the adequacy of plant emergency E.1 Shift personnel should demonstrate the use of notification methods and procedures to the emergency call-in system to augment plant '
) augment plant staff and resources. staff as may be required by scenario events. I
- 2. Demonstrate the ability to utilize outside E.2 The Yankee Nuclear Services Division's resources to provide technical assistance Engineering Support Center (ESC) will be and logistical support. contacted and activated for this exercise.
The ESC can provide technical and logistical support as requested by Vermont Yankee.
- 3. Demonstrate the ability to maintain shif t E.3 Available resources will be evaluated and staf fing and manpower to provide for future assigned to support extended operations.
manpower and logistics needs. F. Radiological Exposure Control
- 1. Demonstrate the ability to provide adequate F.1 Scenario events will require OSC On-Site radiation protection controls for on-site F.2 Assistance Teams to be dispatched to emergency response personnel. such as investigate problems associated with plant ,
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appropriate personnel dosimetry, equipment, equipment. Investigation and repair and protective clothing. activities in the plant will require i implementation of radiation protection
- 2. Demonstrate the ability to monitor and controls which include monitoring and tracking track radiation exposure of Vermont Yankee of radiation exposure of OSC On-Site emergency response personnel. Assistance Teams. (Refer to Procedure OP-3507, " Emergency Radiation Exposure
- Control.") In addition, the exposure of the
- off-site monitoring teams'will be monitored and tracked in the EOF.
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* .A Rev. O Page 2.1-6 Extent of Play 1
- G. Radiological Assessment
- 1. Demonstrate that radiological assessment G.1 The scenario will provide information on plant personnel et tae-EOF can obtain G.2 conditions and in-plant radiological conditions radiological and meteorological data in a G.3 to players which will allow them to evaluate timely manner. G.4. potential off-site radiological consequences.
G.5 The scenario will postulate an off-site
- 2. Demonstrate that adequate dose assessment radiological release through the plant vent procedures can be performed to determine stack which will allow players to evaluate i off-site radiological consequences. off-site radiological conditions. Players will implement appropriate sections of (
- 3. Demonstrate the ability to assess potential Procedures OP-3513. " Evaluation of Off-Site off-site radiological consequences based on Radiological Conditions" and OP-3511, plant conditions. "Off-Site Protective Actions Recommendations." f
- 4. Demonstrate the ability to perform timely assessment of off-site radiological
, conditions to support the formulation of protective action recommendations for the plume exposure pathway. + 5. Demonstrate the ability to project the l plume trajectory and potentially affected downwind sectors utilizing the computer-dose assessment model (METPAC). a
- 6. Demonstrate adequate staffing, equipment G.6 Off-site monitoring terms will be assigned at readiness check, and deployment (if G.7 the OSC. Players will implement appropriate ,
necessary) of off-site monitoring teams. sections of Procedure OP-3510. "Off-Site and , Site Boundary Monitoring." !
- 7. Demonstrate the use of appropriate.
equipment and procedures to perform -! off-site radiological monitoring. i 2160e 1 i e - -
r Rev. O Page 2.1-7 Extent of Play H. Protective Action Decision Making
- 1. Demonstrate the ability to implement H.1 On-site protective action measures will appropriate on-site protective measures for luelude radiation exposure control and plant emergency response personnel. evacuation of nonessential personnel. After plant evacuation and accountability has been completed, all plant personnel and contractors not directly involved in the exercise may be allowed to return to work.
Demonstrate the adequacy of the protective H.2 Protective action decision making will be 2. action decision making process to make demonstrated in accordance with recommendations concerning of f-site Procedure OP-3511, "Off-Site Protective radiological consequences. Actione Recommendations".
- I. Public Information Demonstrate the ability to develop and I.1 The News Media Center will be fully activated.
1. disseminate timely accurate press release I.2 Information on the simulated events occurring to the public and the news media. I.3 at the plant will be gathered, verified, incorporated into a news release, and
- 2. Demonstrate the ability to provide disseminated to key players. After approval, briefings for and to interface with the this information will be discussed at the News Media Center. In addition, all news releases public and news media.
will be coordinated with the state's public
- 3. Demonstrate the ability to communicate and information representatives.
coordinate news releases between the EOF, News Media Center, and the state'd public information representatives. 4 Demonstrate the ability to provide rumor I.4 A hot line will be established to provide control. rumor control for questions concerning the simulated accident. 2160e i
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Rev. O Fage 7.1-8 Extent of Play i t J.- Parallel and Other Actions
- 1. Test and evaluate the adequacy of methods J.1 Security activities will be implemented in to establish and maintain access control accordance with established procedures to ,
and personnel accountability within the control access to the protected area. ! protected area. Assembly of emergency response personnel and evacuation of contractor / visitors will be implemented in order to test personnel accountability within the protected area. However, after the plant evacuation accountability checks have been completed, contractors and visitors will be exempted from additional personnel accountability checks.
- 2. Demonstrate the adequacy of the rocedural J.2 Preliminary discussions on plant conditions :
- process to transfer from the emergency and status will be conducted to determine the classification phase to the recovery m-de required criteria to transfer from the of operation.* (De-escalation versus emergency phase to'a recovery mode of recovery procedures should be reviewed.) operation.
- 3. Demonstrate the licensee's capability for J.3 Exercise c itique will be conducted with
- self-critique and ability to identify areas exercise controllers. observers, and players.
needing improvement. Critique items will be compiled and docueented by the Exercise Coordinator.
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Note: The annual radiological monitoring diill and semi-annual health physics drill will be included as part of the exercise. i A separate heal'th physics drill will be. held to demonstrate the actual sample collection and analysis of in-plant chemistry samples'which includes the use of the Post-Accident Sampling System (PASS). 0 Indicates NRC-identified improvement items from the 199C exercise. . , 21bde i i
( VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 1 1 2.2 STATE OF VERMONT
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VE2MONT C V:51.V:0X:. YAXIE:E .l X""C:1:5A2 :?OW:22 S:.A"::ON VERNON, VT.
- EX:E2CIS:E - NOV:EM3E2 6, :.991 03J:EC .::V:ES/EX:.ENT OF PLAY
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WRMONT ExtRCISE OsJtem1ts l VERMONT YANKEE NUCLEAR POWER STATION
, VERNON, VERMONT ,
NOVEMBER 6, 1991 OBJECTIVE . PARTICIPATION 2XTENT OF FLAY LQQ L STATE / LOCAL IJJS GH DL-1 S_ TATE
- 1. Demonstrate ability to Yes Yes
- state: To include motivate and use Clann- all activated ification Lavoin (ECLs) facilition through the appropriato
- Local To include implementation of emerg- all Vermont EPZ ency functions and Towns.
activitico corresponding to each ECL. The four ECLo are: notification of-unusual event, alert, cito area emergency, and general emergency. 3.-Demonstrate ability-to Yan Yes
- State.1 State
. fully alert, mobilize, facilities activated and activate personnel for in accordanco with-both facility - and field- State Plan. Field based emergency functions. based functions in '
See Objectivo 34 for 24-hr., accordance with
- j. continuous utaffing function Stato-Agoney Rosponna within a six-year timo frame. plano. 24 hour capability at selected facilition. See OBJECTIVE No. 34 for selected sites.
- Local: Local townn facilitica activated in accordance with Town Naponso Plann.
See OBJECTIVE No. 34 for selected sites. ACTIVATED FACILITIES ,
- STATE: State and Local warning Points Stato Emergency Operations Centers State Incident Field Offico Emergency Operations Facility Joint Information Center l
t 0C AT,1 - Town of Dummerston Emergency Operations Center .' Town of Vernon Emergency Operations Center Town of Guilford Emergency Operationn Center Town of Brattleboro Emergency Operations Center Rocoption/ Congregate Caro conter; Bellows Falla Union High School, i I 09'01'9 t f u I--
- , - ~~,,,.----,..._-_,r.._..... _ _ . _ . , , _ , , , , , , , . . , , , , , . . _ , _ _ . , . , . . _ - , _ , . . _ . . . . - . . _ . . . , . , , , _ , . . . , . _ _ . - - _ . . _ _ . . . _ . _ . _ . . .
l
\TJWONT EXRCISE OnD4TIVr.$
Demonstrate ability to Yes Yes Direction, coordination k J. and control to be direct and control demonstrated at all amargoney activitics, State and Local facilities. Demonstrate ability to Yes Yoc Communications to be 4. communicate with all demonstrated at All plata and Local appropriate locations, Facilities as organizations, and field appropriato. personnel. Demonstrate adequacy of Yes Yes Facilities, equipment,
- 9. displays, access mapc, facilities and displays to support emergency & otatuo boardo personnol. demonstrated at All SIDig and LqgAl facilities.
Yes Yes S t a t o ;_ EOC and TF0 Demonstrate ability to 6. continuously monitor and Logg1;_ All Local Town control emergency worker EOC'c & Responne exposure. Pornonnel.
- 7. Demonstrate the appropriate Yes No S_ tate: State level
; equipment and procedures function with Federal for determining field support or implement-Radiation meanurements, ation of inter state assistance compact, if neconsary. Field Teams.
Local:_ Not a local function.
- 8. Demonstrate the appropriate Yen No State: Same as No.7 equipment and procedures for LQEgli Not a local function.
the measurement of airborne Radio-iodine concentrations as low as 10*-7 (.0000001) microcuries por cc in the presence of noble gasses.
- 9. Demonstrate the ability Yes No State:_ State level function, field to obtain samples of nampling assistance particulate activity obtained by initiating in the airborne plume and promptly perform protocolo of the laboratory analysis. Intrastate Radiological Compact; and/or requenting federal assistanco.
av mTv1
\TAMOMT EXERCISE OBJECTIVES State Field Monitoring k
t6ams (2) will demonstrate the proced-uro(s) for obtaining samples. State will
~
demonstrate primary and back-up recources for transport to laboratory. Actual laboratory analysis at the laboratory will be demonstrated during this exercise. FACILITIEst EOC, State of Vermont, Waterbury, VT. IFO, State of Vermont, Dummerston, VT. Laboratory, State of Vet.nont, Burlington, VT. Civil Air Patrol, Burlington, VT. AGENCIESt Vermont Department of Health Vermont State Police Civil Air Patrol Local _ Not a local ( function.
- 10. Demonstrate the ability Yes Yes - $1algi Field data within the plume exposure obtained by assess-ment teams (2); will pathway, to project be utilized along with dosage to the public utility supplied data, via plume exposure, based on plant and Information assessed field data. at State EOC-Hoalth Dept., for policy decision and issuing of public protective actions.
Local: Not a local function.
- 11. Demonstrate the ability Yes tio _ State: State policy to make appropriate level decision based protective action upon Health Dept.
decisions, based on assessment, support from assisting state projected or actual dosage, EPA PAG's, agencies in accordance with existing sheltor, availability of adequate evacuation time State / Agency Plans, estimates and other Local: Not a local l relevant factors. function. l 3 i W/02 iV f
VERACRT EXERCISE oBJECTIVT,1
- 12. Demonstrate tbc ability Yes Yes Statal NWS W121 be to initially alert the notified to activate public within the 10-mf's NOAA weather alert EPZ and begin dinnomination radios in the EPZ.
of an instructional An actual tant tono message within 15' minutes will be sounded with an of a decision by appropriato instructional monnage. state and/or local of ficial(s) . Coordination with border states, New Hampshire and Massachusetts, will be demonstrated prior to NOAA Tone and release of information. Windham County EDS, station WTSA Brattloboro 1450 AM or 90.7 FM, will transmit a ninglo radio test announcement. LAEAli Local communities will nimulate route alerting, talophone calla. Sironn will bo sounded upon State instruction.
- 13. Demonstrate the ability Yes No Etatet State will to coordinate the disseminate additional formulation and dissem- public instructions and ination of accurate infor- information an aconario nation and instructions to dependent. Both instant the Public in a timely & prescripted messages fashion after tho initial will be uaod. The State Alert and Notification EOC through its Public has occurred. Information Recource will provide information to local EOC'n, IFo, JIC, EOF ao pertinent.
LQcA11 Not a local function. 4 09/01/91
VrRMONT EXTRCISE ODJECTIVES
- 14. Demonstrate the ability You No State: Staff will pro-to brief the media in an vide briefings to the accurate, coordinated media, if prosent at and timely manner. Stato EOC. Media briefings will be provided at tho State EOC; JIC. Information obtained from State Operations conter.
Information may be instant or prescripted Media kits available at State EOC. Local: Limited at a local function.(87-73)
- 15. Demonstrate the ability Yes Yes Statri State will cimu-to establish and operato lato (demonstrato) rumor control in a coor- operation of rumor dinated and timely fashion. control.
Local: Local EOC's will GROUP B - scenario Dupendent simulato (domonstrato) rumor control.
- 16. Demonstrato the ability Yes Yes Statel State Health to make the decision to will demonstrate recommand the use of KI proceduros, information to Emergency Workers and release necessary for Institutionalized persons distribution of KI to based on pro-determined Emorgency Workers and institutionalized, criteria.
actual distribution is simulated. Local: Local EOC's, IFO, facilities having EW responsibilities will demonstrato simulate accessing supplies and simulate distribution according to Plan once the docision is made by the state.
- 18. Demonstrate the ability Yes Yes Etarri State issued notification through and resources necessary to implement appropriate EDS, Local EOC's, JIC protective actions for the for permanent and tran-impacted permanent and sient populations.
transient plume EPZ pop- Local: Local communities ulation (including transit- (4) will identify dependent persons, Special transit-dependent, Needs populations, handicapped Special Needs groups-persons and institutionalized uchool, and handicap, s 0&O2'91
___ .. .. . . _ _ . - . . . _ . .- ~ _. .. VERMONT
. JRCISE OBJTCTIVLS institutionalleod pop-persons).
ulations in each EP2 ( community.
- 20. Demonstrate tho' Yes Yes Statet State will organizational ability demonstrato the and resources necessary decision making, to control evacuation implementation of resources, to establich traffic flow and to control access to and control traffic ovacuated and sheltered flow to and from impacted areas.
areas. Simulated. LEGA11. Local EOC's will identify Areas for the establishmont of control points. Simulation.
- 21. Demonstrate the adequacy Yos Yes Statqi State will act-of procedures, facilition, ivato the Bollows Falls equipment and personal Reception Cantor to for the registration, simulate receipt of Radiological monitoring EVACUEES. Personnel and decontamination of and vehicloc with simu-of EVACUEES. lated contamination the will be processed by Bellows Falls Relocation demonstrate facility to Congregate Care Center capabilities.
Local:_ Limited action. Siaulated movement of Local EOC to alternate operations. N/A State: One congregato
- 22. Demonstrate the adequacy Yes care facility. Bellows of facilities, equipment, and personnel for Falls U.H.S. will ba -
activated by the State congregate care of EVACUEES. Agency of Human Servicos assisted by BFUHS the American Red Cross and Local Resources.
; Local: Not a local function. [87-20)
[Objectivos Nos. 21,22 will be demonstrated out of soquence) [ Tentatively scheduled for February, 1992.) j 25. 6 CA!C2 41 l
VERMONT EXERCISE ODJECTIVES k.
'OROUP c - Once Every six Yeara
- 34. Demonstrate the ability No Yes State: liot applicable.
to maintain staffing on Local: Incident Field a continuous 24-hour Offico, and Town of basis by an actual Vernon will demonstrate shift change. shift changen. Key Personnel only. 7 09 T2'91
.AJ . a-.4. A A am a s ,. - -2.a m 4 J og a - _ ..a VERMONT YANKEE NUCLEAR POWER STATION EHERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 2.3 STATE OF N W llAMPSHIRE ^!
l l l I
5 1 i State of New Hampshire Objectives ( for the Vermont Yankee Nuclear Power Station 1991 Emergency Response Exercise Stato Local New Hampshire Ourisdictions FEMA objective and Extent of Play Yes Yes
- 1. Demonstrate the ability to monitor, understand and use emergency classification levels (ECL) through the appropriate implementation of emergency functions and activities corresponding to ECL's as required by the scenario. The four ECL's are: Notification of unusual event, alert, site area emergency and general emergency.
Yes Yes
- 2. Demonstrate the ability to fully alert, mobilize and activate personnel for both facility and field-based emergency functicas.
State and local emergency response organirations will be mobilized. The State ( EOC, IF0, Media Center, Iccal E00s, will te activated in ac0crdance with the NHP.ERP. The Reception Center and Decentamination Center mobilization will be demonstrated in ' accordance with the Extent of Play for Obi 21, 22 and 25)ectives DPHS 21, 22, and laucratory 25 (see activity wi. 00j1 te simulated, except as specified in Oojective 99. Yes Yes
- 3. Demonstrate the ability to direct, coordinate and control emergency activities.
Yes Yes 4 Demonstrate tne ability to communicate with all appropriate locations, organizations anc fielc personnel. Yes Yes
- 5. Demonstrate tne acequacy of facilities, equipment, displays and other materials to support emergency operations.
Yes Yes
- 6. Demonstrate the ability to Continuously moniter and control emergency worker l
exposure. Yes N/A
- 7. Demonstrate tr.e acprepriate eculpment and l
proce0eres for cetermining field raciation measurements. Two Raciological M:nitcring Teams will te dispate.*ed.
' ' ' ^ ^
= r. v . 7(29/91
. l l
State Local ( FEMA objective and Extent of Play New Hamoshire Jurisdictions _ Yes N/A
- 8. Demonstrate the apf ropriate equipment and procedures for the neasurement of af tborne ladiciodine concentrations as low as 10 I microcuries per c0 in the presence of noble gases.
Yes N/A
- 9. Demonstrate the ability to obtain samples of particulate activity in the airborne plume and promptly perform laboratory analyses.
Selected samples collected by Field Monitoring Teams will be brought to the Keene IFO for screening on a portable laboratory High Purity Germanium Detertor. Yes N/A
- 10. Demonstrate the ability, within the plume exposure pathway, to project dosage to the public via plume exposure, ce:ed on plant and field data.
The cbjective will be demonstratec using ' the METPAC dose assessment model, or other methods as appropriste. Field data octained by NHCPHS monitoring teams and from 'he Ut3' ty will be used as input for dose dets inations. Yes Yes
- 11. Ocmonstr 'ne ability to make appropriate protecti; . .ico ce isions, cased on prcjected or actual dosage, EPA PAG's availacility of adequate shelter, evacuation time estimates and otner relevant facters .
Protective acti:n reccmmendations will ce made using the crite:ia as outlined in the NHRERP. Yes N/A .
- 12. Cemonstrate tne ability t0 initially aler; tne puelle witnin the lo-cile EFZ and begin disseminaticn of an instructicnal message witnin l 15 minutes of a de:isi n ey appropriate State and/or local of ficial(s).
i l f Rev. 7/29/91 52625 i i
State Local i FEMA objective and Extent of Play New Hampshire Alrisdictions
- 12. The demonstration of Public Alert and Notification System activation will occur after declaration of a General Emergency and in conjunction with the first decision by New Hampshire or another State to implement a protective action
- of sheltering or evacuation. Previous or subsequent activation will be simulated, A test message will be broadcast over NOAA Weather Racios. EBS message broadcast will be simulated. However, EBS messages will be prepared and distributed. Sirens will not be sounded.
- 13. Demonstrate the ability to coordinate the Yes N/A formulation and dissemination of accurate information and instructions to the public after the initial alert and notification has occurred.
Public information messages will be developed periodically _ based upon the requn ements of the scenario. Broadcast f of these messages either by radio er other news media wiu De simulated, however they will be distributed tn the EOF, IF0, Media Center, and State EOC. Ye3 N/A
- 14. Denonstrate tne ability to brief the media in an accurate, coordinated and timely manner.
Yes N/A
- 15. Demonstrate tne ability to establist and cperate rumor control in a ecordina*.ed l and timely fasnien.
Yes
- 16. Demonstrate tne ability to make tne decision Yes to recoecend the use of KI to emergency workers and institutionalized persons, based en predete=ined criteria, as well as to distribute and administer it coce the decision is made, if necessit.ted by radioicdine releases.
Tne decision to use er not to use KI for emergency workers will be demonstrated at the State ECC. The acility to cistribute and administer KI will be demonstrated. Actual distribution and administration l will ce simulated. l S2628 Rev. 7/29/91
State _ Local (' FEMA objective and Extent of Play New Hamoshire Jurisdictions No N/A
- 17. Demonstrate the ability to make the decision, if the State plan so specifies, to recernend the use of KI for the general public, based on predetermined criteria, as well as to clistribute and administer it once the decision is made, if necessitated by radiciodine releases.
The NHRERP does not provide for the issuance of KI to the general population. Yes Yes
- 18. Demonstrate the ability and resources necessary to implement appropriate protective actions for the impacted permanent and transient plume EPZ population (including transit-dependent persons, special needs populations, haridicapped persons and institutionalized persons).
Special Needs listings are maintained by each coccunity. Transportation requests teyond the capability of the ccmmunity to furnish will be made to a NHOEM local liaiscn officer who will arrange for the transportation. No persons will be actually leaded or transported.' Partial Partial
- 19. Demonstrate the ability and rescurces necessary to implement acor0eriate protective actions for sen0cl children within the plume EFZ.
Inis objective was demenstrated fully for NH EPZ schools curing the 1990 mini-drill. The extent of play for the cemonstration of th1.s objective in this exercise will ce to make an initial notification phone call to each facility to determine transportatica rescurce requirements. A call to transportation pr0viders will be race te determine resource availsbility. Meolliration of actual transportation rescurces will te simulated. Fev. 7/29/91
t N*.- State Local
/ New Hamoshire @risdictions
( FDQ objective and Extent of Play Yes Yes
- 20. Ocmonstrate the organizational ability and resources necessary to control. evacuation traffic flow and to control access to evacuated and sheltered areas.
One access control point (ACP) will be staffed by the NH State Police during the exercise and the NHOOT will provide traffic control devices. Other ACP's will be demonstrated by use of mitps and resters. Local c.ommunities that mJst initiate protective action, will demonstrate the staffing cf at least one traffic control point (TCP). Other TCP's will be demonstrated by use of maps and rosters. Communities that are not required to initiate protective actions will demonstrate Access & Traffic Control using maps and rosters as well. Yes N/A
- 21. Demonstrate the adegiacy of procedures, facilities, equiptent and personnel for t".e registration, radiological monitoring and decentamination of evacuees.
The Reception Center will be demonstrated out of sequence (in conjunction with COjective 922). This demonstration will consist of setting up anc sta'fing the Reception Center at Keene State College, and registering about 13 evacuees. In addition, a ce:cntaminatien center sucerviser anc two decen acnitcring unite will cemenstrate the monitoring anc cecentamination prececures on emergency werkers anc these same evacuees, which will incluce at lease one female. Rev 7/29/91 52629
- - - - - - - _ - - _-- _ _ _ _ _ _ __" ----_-,____m___ _ , _
r~ I l l l State Local { New Fhmoshir_e Jurisdictions FEMA objective and Extent of Play ___ _ Yes N/A
- 22. Demonscrate the adecuacy of facilities, equipment, and personnel for congregate care of evacuees. ' -
Congregate care facility will be simulated. The American Red Cross will participate at the State ECC and Reception Center at Keene State College, A walk-through of the primary mass care facility will be scheduled out of sequence. Yes N/A
- 23. Demonstrate the adequacy of Out of Sequence) vehicles, equipment, procedures and personnel for transporting contaminated, injured or exposed individuals.
This objective was demonstrated fully by the 1990 HS-1 tbspital Drill at Cheshire Hospital which was evaluated by FEMA Region I. An out of sequence drill has been held on April 10, 1991 to demonstrate 8 this objective. It is New Hampshire's
' understanding that FEMA will not evaluate this drill.
Yes N/A
- 24. Demonstrate the adequacy of medical facilities, equipment, procedures and personnel for handling contaminated, injured or expcsed individuals.
Notificatien of facilities and rescurces will be deacnstrated as appropriate. Rescurces anc personnel will be simulated. An out of sequence crill has been held on April 10, 1991 to demcnstrate tnis oojective. It is New Hampsnire's understanding that FEMA will not evaluate this drill. Yes N/A
- 25. Demonstrate tne adecuacy of Out of Sequence f acilities, equipment, precedures and personnel for decentamination of emergency workers, ecui; ment and vehicles and for waste disposal.
Derenstration cf this cbjective will te in ccnjunction witn the Ccjective 21 Extent of Play and will cccur ccncurrently with the Objective 21 demonstratien. See Extent cf Play fcr C0jective 21.
. _ _ _ - _ _ . _ _ _ _ _ - - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ ~ - - " ~ - - - - - - - - _ _ _ _ _ _ _ _ _ _
r State Local New Hampshire Ourisdictions (' FEMA objective and Extent of Play Yes N/A
- 26. Demonstrate the ability to identify the need for and call upon Federal and other outside support agencies' assistance.
No No
- 27. Demonstrate the appropriate use of equipment and procedures for ,
collection and transport of samples of vegetation, food crops, milk, meat, poultry, water and animal feeds (indigenous to the area and stored). No No
- 28. Demonstrate the appropriate lab operations and procedures for measuring and analyzing samples of vegetation, food crops, milk, meat, poultry, water and animal feeds (indigenous to the area and stored).
No No
- 29. Demonstrate the ability to project dosage to the public for ingestion pathway exposure and determine .
appropriate protective measures based on field data, FCA PAG'S and other relevant factors. clo No
- 70. Demonstrate the ability to implement t'oth preventive cnd emergency protective actions for ingestion pathway ha:ards.
No No
- 31. Demonstrate the acility :: estimate total population ex osure.
No No
- 32. Ceconstrate the soility to determine appropriate measures for centrolled reentry and recovery based en estimated total population exposure, availacle EPA FAG'S and other relevant factors.
No No
- 37. Demonstrate the ability to implement appropriate measures for ecotrolled reentry.
No No 34 Demonstrate tne acility to maintain staf fing en a centinuous 2A-hcur
- basis by an actual snift change.
1/A N/A
- 35. Demonstrate tne ability to coor0inate the evacuation of cosite persennel.
F.ev. 7/29/?1 5262S !
P o State Local New Famoshire Jurisdictions (~ FEMA objective and Extent of Play No No N . Demonstrate the ability to carry out emergency response functions , (i.e.,' activate ECCs, mobilize staff that report to the EOCs, establish ccanunications linkages and complete telephone call down) during an unannounced off-hours drill or exercise. 8 Revisec 7/29/91 52625
'M i=1 -
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 2.4 [pMMONVEALTH OF MASSACHUSETTS ( i
{ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 COMMONWEALTH OF MASSACHUSETTS OBJECTIVES AND EXTENT OF PLAY REVISION 5 August 1991 m
' COMMONWEALTH OF MASSACHUSETTS OB3ECT79ES AND EXTENT OF PLAY FOR THE 3991 VERMONT YANKEE EXERCISE Objective 1 Emergency Classification Levels:
EPZ Towns (6) k MEMA Area IV EOC MEMA Headquarters EOC (Framingham) EOF MDPH MSP (Troop D) Tri-State Fire Mutual Aid (Franklin County Dispatch) Objective 2 Mobilization of Emerggney oersonnell EPZ Towns (6) MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MDPH MDPH Field Teams MEMA EOF and Media Center Representatives J Objective 3 Direction and control: EPZ Towns (6) MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MDPH MEMA EOF Representatives Objective 4 Communications: EPZ Towns (6) MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MDPH MDPH Field Teams MEMA EOF Representatives Objective 5 Facilitice, Equipment and Display: EPZ Towns (6) MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MEMA EOF and Media Center Representatives j MDPH 1 I MDPH Field Teams l I l
l Emergincy Worker Exposure Control: Objective 6 EPZ Towns (6) MEMO Area IV EOC MEMA Headquarters EOC (Framingham) MDPH MDPH Field Teams Objective 7 Field Radiological Monitoring: Ambient: MDPH Field Teams Objective 8 Field Radiological Monitoring: Airborne Iodine: MDPH Field Ieams Objective 9 Field Radiological Monitorinq: Particulate Activity: MDPH Field leams Objective 10 ' Plume Dose Projection: MDPH EOF Representatives Objective 11 Plume Protective Action Decision Making: MEMA Headquarters EOC (Framingham) MEMA and MDPH EOF Representatives Objective 12 Alert, Notification and Emergency Information E (Initial Alert and Notification): EPZ Towns (6) MEMA Headquarters EOC (Framingham) Objective 13 Alert, Notification and Emergency Information (Public Instructions): MEMA Headquarters EOC (Framingham) MEMA Media Center Representativos Objective 14 Alert, No.tification and Emergency Information (Media): MEMA Headquarters EOC (Framingham) MEMA Media Center Representatives
Objective 15, Alert, Notification end Emergtney Information 5 (Rumor Control): P EPZ Towns (6) (s MEMA Headquarters EOC (Framingham) ] MEMA Media Center Representatives Objective 16 Use of KI (Emergency workers): CPZ Towns (6) MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MDPH Objective 17 Not applicable to Massachusetts. Objective 18 Protective Action - Plume: CPZ Towns (6) MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MDPH 1 1 Objective 19 Protective Action - Schools: Will be demonstrated in a special exercise. Objective 20 Traffic / Access Control: EPZ Towns (6) MEMA Area IV EOC MEM0 Headquarters EOC (Framingham) MSP (Troop B) Objective 21 Not scheduled for this Exercise. Objective 22 Not scheduled for this Exercise.
Objective 23 Medical Services (Tranoportation):
- Will be demonstrated in a special exercise.
Objective 24 Medical Services (Facilities): _ Will be demonstrated in a special exercise. Objective 25 Decontamination (Emergency Workers): EPZ Towns (6) Will be demonstrated out-of-sequence, if needed. Objective 26 Supplementary Assistance (Federal /Other): MEMA Headquarters EOC (Framingham) MDPH Objective 27 Not scheduled for this Exercise. through Objective 34 Objective 35 Evacuation of On-Site Personnel:
,, N/A Objective 3f Unannounced and Off-Hours:
Not schoduled for this exercise,
~
Obicetive 1 - Emergency Classification Levels Demonstrate the ability to monitor, understand, and use Emergency Classification Levels ( (CCLs) through the appropriate implementation of emergency functions and activities corresponding to ECLs, as required by the scenario. The four ECLs are: UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY. Egcent of Play EPZ Town EOCs The EPZ towns will receive and acknow)cdg: initial notification of ECLs at their 24-hour warning points (s) from the Tri-State Fire Mutual Aid. Additional notification and follow-up information will continue to be received and acknowledged at each 24-hour warning point unti1 MEMA E00s and town EOCs becomo operational (Alert level). Eoc staff will demonstrate appropriate decision 4-making and coordination capabilities, pursuant to each ECL, and their RERP plan / procedures. NOTE: EPZ. town E00s generally only partially activate at an ALERT level. Full EOC activation generally occurs at a SITE AREA EMERGENCY declaration. EOC staffing will vary from town to town. The CD Director (or designee) declares the EOC operational. MEMA Area IV ECC The Area IV EOC staff will receive initial notification and accident condition information in accordance with procedures. The Area IV EOC is activated at an ALERT level. Communications will be established with EPZ Town EOCs and MEMA L Headquarters EOC after they become operational. Appropriate coordination activities will be performed by the EOC staff. I l
1
' e' ;
l
~
MEMA Hardquarters EOC. Initial notification and accidsnt information . will be received in accordance with- I
,- procedures. MEMA will notify 1MDPH11n J;- accordance with procedures. Changes in ECLs' will continue to b,e received throughout the. ]
exercise, Following EOC activation and , 3 mobilization of personnel, the staff will take
-- appropriate measures in response to protective- ;
actions and coordinate with MDPH and MEMA Area IV EOC.
' State representatives atLthe utility's EOF will EOF' i
receive ECLs and accident information upon i arrival-and throughout the exercise.
~MUPH ECL notification' will be received in accordance -
with procedures. MDPil will contact the vermontL Yankee Control Room-to obtain additional accident information, MDPH will coordinate with MEMA Headquarters concerning necessary , AL protective-actions. MSP Troop B Initial ECL notification will be received by Troop B (State Warning Point) from Vermont Yankee Control Room, in accordance with procedures. MSP Troop B will notify Tri-State Fire Mutual Aid and MEMA. Subsequent notification will continue to be received by Troop B and relaye'd to Tri-State Fire Mutual Aid until MEMA EOCs and the utility's EOF become operational.
' NOTE: Verification of ECL notification will-occur, as required, in accordance with procedures.
I s-l'
Tri-Stato Fire Initial ECL notification will be received by Mutual Aid Tri-State Fire Mutual Aid from MSP Troop B, in accordance-with procedures. Tri-State Fire ( ' Mutual Aid will notify the 6 EPZ towns at their 24-hour warning point (s) . Verification of ECL notification will occur in accordance with procedures. , Objective 2 - Mobilization of Emergency Personnol Demonstrate the ability to fully alert, mobilize, and activate personnel for both facility and field-based emergency functions. Extent of play EPZ Town EOCs following ALERT notification, EOC staff will mobilize (partial / full activation optional) to initiate response actions in accordance with procedures. 4 MEMA Area IV EOC Following initial notification of the ECL, the Area IV Director will mobilize EOC staff in accordance with procedures. MEMA Headquarters EOC- Following initial ECL notification, MEMA staff will be notified in accordance with procedures. EOF State EOF personnel will be notified in accordance with procedures, be dispatched to the EOF at the proper ECL, and will initiate activation of the State area upon arrival.- MDPH Field Teams Following initial ECL notification, MDPH will notify field team personnel in accordance with procedures. Two MDPH Field Teams will mobilize and dispatch to demonstrate Objectives 7, 8, and 9.
Media Canter Following initial ECL notificction, State Public Information personnel will be mobilized in accordance with procedures. Representatives will be dispatched to the Media Center at the appropriate ECL. , Objective 3 - Direction and Control Demonstrate the abi'ity to direct, coordinate, and control emergency activities. Extent of Play EPZ Town EOC Upon full mobilization of personnel, town EOCs will demonstrate direction and control activities in accordance with procedures. MEMA Area IV EOC Upon activation of the Area IV COO, the staff will demonstrate direction, control, and
- coordination activities in accordance with
=
procedures. MEMA Hoadquarters EOC Upon activation of the EOC, the staff will demonstrate direction, contral, and coordination activities with appropriate State personnel (e.g., MEMA Area IV EOC; MDPn; MSP; EOF; Media Center; etc)- in accordance with procedures. EOF Upon arrival at the utility's EOF, State personnel will demonstrate direction, control, and coordination activities in accordance with procedures. Objective 4 - Communications Demonstrate the ability to communicate with all appropriate locations, organizations, and field oorsonnel.
Extent of play
- EPZ Town EOCs following mobilization, communication-activities will be performed in accordance with procedures and operational requirements.
. Communications with personnel and facilities involved in out-of-sequence objectives will not occur.
MEMA Area IV EOC Following mobilization,-communications capabilities will be demonstrated in accordance with procedures and operational / coordination requirements. MEMA Headquarters EOC Following mobilization, connunicat ion capabilities will be demonstrated. in accordance with procedures and operational requirements, EOF Following mobilization, communication and coordination capabilities will be demonstrated
- a, A in accordance with procedures and operational requirements.
MDPH Field Teams All operational communications will be demonstrated in accordance with procedures and operational support needs. Objective 5 - Facilities, Equipment, and Displays Demonstrate the adequacy of facilities, equipment, displays, and other
-materials to support emergency operations.
Extent of Pla,y All participants will demonstrate the adequacy of their facilities, equipment, displays, and materials for response and operational activities.
1 Objective 6 - Emergtney Worker Exposure Control Ocmonstrate the ability to continuously monitor and control emergency {_ worker exposure. Extent of Play EPZ Town EOCs followir>g mobilization of personnel, the EOC will demonstrate exposure control activities in accordance with procedures (e.g., dosimetry /KI). Exposure control measures will be coordinated with appropriate State authorities, as required. MEMA Area IV EOC Will demonstrate the capability to disseminate State exposure control guidance to local EOCs, via the RERP Radio System. MEMA Headquarters E00 Will demonstrate the capability to develop and f disseminate state exposure control directives. MDPH Field Teams Will demonstrate exposure control activities in accordance with procedures. NOTE: Dosimetry will be issued to field _ emergency workers as plans and procedures indicate. Objective 7 - Field Radiological Moniterina Ambient Demonstrate the use of appropriate equipment and procedures for determining field radiation measurements. Extent of Play MDPH Field Teams Follcuing mobilization, two MDPH Field Teams will be dispatchea, Field radiation measurements will be demonstrated using
approprieto equipnint to locate and d2 fine plume exposure radiation levels (plume verification and tracking). State / Controllers
. t: -t will provide data.
Objective 8 - Field Radiological Monitoring Airborne Iodine Demonstrate the appropriate equipment and procedures f ' the measurement of airborne radiciodine concentrations as' low as 10- uCi/cc in the presence of. noble gases. Extent of Play MDPH Field Teams Two MDPH Field Teams will demonstrate radiological monitoring measures for airborne radioiodine concentrations by utilizing equipment for air sampling in accordance with procedures. Data necessary to simulate air sampling results will be provided via an j exercise controller. i MDPH Field Teams will be dispatched for sampling purposes, according to scenario requirements. Field Team communications will. be demonstrated for coordination purposes. Objective 0 - Field Radiological Monitoring Particulate Activity Demonstrate the ability to obtain samples of particulate activity in the l airborne plume and promptly perform laboratory analysis. l t Extent of Play l MDPH Field Teams lwo MDPH Field Teams will demonstrate sampling - methods for particulate activity by performing required actions with necessary equipment, in accordanco with procedures, Simulated samples will be prepared for transport to the MDPH laboratory for analysis. l
i Objectivo 10 - Plume Doso Proinction Demonstrate the ability, within the plume exposure pathway, to project dosage to the public via plume exposure (s), based on plant and field data, ( Extent of Play . EOF MDPH personnel located at the utility's EOF will demonstrate dose projection methods using simulated plant information and MDPH Field Team sampling data. Objective 11 - plume protective Action Decision Making Demonstrate the ability to make appropriate protective action decisions, based on projected or actual dosege, EPA PAGs, availabil'ty of adequate ~ shelter, evacuation time estimates, and other relevant factors. Extent of play MEMA Headquarters EOC EOC (Framingham) staff will demonstrate decision-making capability for the determination of appropriate protective actions, using available dose projection information, protective action guidance, shelter-in-place capabilities, evacuation time estimates, and other considerations for public safety (e.g., weather, highway conditions, time of day, etc). The protective action decision-making process will be based upon recommendations received from State repr esentatives located at the utility's EOF. Protective action decisions (for impleme,tation) will be coordinated with contiguous States, as appropriate, and MEMA Area IV EOC staff. MEMA Area IV EOC will coordinate and transmit State protective action recommendations te local EOCs, as required.
Massachugetts representatives (MEMA/MDPH) at EOF-the utility's COF will utilize available information regarding plant release (s) and (=
' field survey data, to determine protective action recommendations, O These recommendations will be coordinated with the MEMA EOC staff for decision-making purposes.
Objective 12 - Alert, Notification, and Emoraency Information: Initial Alert and Notification ** Demonstrate the ability to initially alert the public within the IC)--mile EPZ and begin dissemination of an instruetional mess' age' within 15 minutes of a decision by appropriate State of ficial(s). Extent of Play Town EOCs will simulate the appropriate actions EPZ Town EOCs necessary to demonstrate this objective. Actual alerting of the public will not take place. Sirens and backup route alerting will be simulated. MEMA Headquarters EOC ECC staf f will simulate the performance of initial notification actions necessary to l demonstrate this objective. Coordination with I contiguous states will be demonstrated. Simulation of EBS shall be as follows: the CPCS-1 station will be contacted and a test message broadcasted. "Real" messages will be used in the EOC, but not broadcasted. t . l-NOTE: As part of the Alert and-Notification and System shared by Vermont, New Hampshire, Massachusetts, the NOAA weather-alert radio will be activated and a test message broadcasted.
** Note: The extent of play for Objective 12 is in the process of being revised based upon FEMA comments.
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- Obimetive 13 - Alert, Notification, and Emtraency Information: Public4
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Instructions q h Demonstrate- the ability: to coordinate the formulation and dissemination. of. accurate information and instructions ' to. the public in a timely I fashion after the initial-alert and notification has occurred. Extent of play - MEMA Headquarters EOC. . EOC staf f will formulate appropriate public
'information/ instructions Applicable EBS information will be simulated. MEMA Headquarters EOC will coordinate media information with- the Media Center, Vermont,1New Hampshire and-MEMA Area IV EOC,-as required.
. Media Center Public information and instructions provided by State / local officials will be disseminated-to the public in accordance with procedures, k~ NOTE: Actual dissemination of public .
information and instructions will not occur. Media Center operations relating to this objective will-be simulated. Related EBS information will be simulated. Obiective 14 - Alert, Notification, and Eme gency Information: Media Demonstrate the ability to brief the-media in an accurate, -coordinated, and timely manner. Extent of play MEMA Headquarters EOC Information for news releases and briefings will be relayed to Media Center personnel for release in accordance-with procedures.
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Media Center State personnel at the Media Center will draf t news releases, prepare briefings for the media k and coordinate with other Media Center representatives to, ensure that periodic briefings are provided to the news media, Objective 15 - Alert, Notification, and public Information: Rumor Control Demonstrate the ability to establish and operate rumor control in a coordinated and timely fashion. Extent of play EpZ Town EOCs Rumor control activities will be performed in accordance with RERP plans and procedures. Calls (simulating local residents) will be made to the local EOCs. EOC staff will demonstrate the ability to handle rumor control relating to their jurisdiction. EOC staff will refer non-town-specific rumor control matters to the State toll free number for rumor control. Local EOC staff will coordinate all local rumor control measuras with MEMA Area IV EOC. MEMA Headquarters EOC Rumor control staff at the EOC will demonstrate the capability to contend with rumor control matters, according to procedures. Rumor control activities will be coordinated with State personnel at the Media Center and MEMA Area IV EOC. Media Center Rumor control activities will be demonstrated in accordance with procedures. Matters concerning rumor control will be incorporated in periodic news briefings and media releases.
Obime :ivo 16 - Use of KI: Emeroency Workers Demonstrate the ability to make the decision to recommend the use of KI-if (potassium iodide) to emergency workers based on predetermined criteria, .
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as well as to distribute and administer it once the decision is made, if neces sitated by radiciodine releases. *
- NOTE: There are no res'idential institutions (hospitals,- nursing homes, prisons, etc) within the EPZ, Extent of play EPZ Town EOCs Emergency workers, directed by ttuo State, will demonstrate the capability to distribute and take KI (potassium iodide) according to -
procedures. All activities related to this objective will be simulated. EOF MDPH staff will demonstrate the ability to evaluate simulated release data in order to
! develop recommendations and instructions (if recuired) for the use of KI by emergency workers. Decisions wi-1;1_ be coordinated with MEMA Headquarters EOC.
MEMA Headquarters EOC- Af ter the recommendation for the use of KI is received from the EOF, MEMA and MDPH at the EOC Will procure authorization for the use of KI-l from the Commissioner of Public Health or his designee and coordinate the decision to Area IV and the EPZ towns. MEMA Area IV EOC Staff will relay decision to distribute and take KI to the local towns.
** Note: The extent of play for objective 16 is in the process of being revised based upon FEMA comments.
Obinctiu* 17 - Uss of KI: Ceniral Populntion 4 Not applicable to the Commonwealth of Massachusetts. Objective IB - Implementation of Protective Actions: Plume EPZ Massachusetts will demonstrate Objective 18 as required only for the EPZ towns affected by the plume. All towns are prepared to provide a list of the special needs population in their town and a list of resources needed to support the special needs-population. Objective 19 - Implementation of Proteet-ive Actions: Evacuation of Schools This objective will be demonstrated in a special exercise. Objective 20 - Traffic / Access Control Oemonstrate the organizational ability and resources necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas. Extent of Play EPZ Town EOCs EPZ EOCs will demonstrate the ability to direct, control, and monitor traf fic flow. Each town will demonstrate one traffic control point, if needed. EOC staff will demonstrate decision-making capabilities and provide an explanation of traffic control measures in accordance with procedures.
1 Emergsney personn21 will respond' n (non-emergency) to the Traffic Control Point-(TCP) location along 'with local department'of Public Works' personnel-(if required), to simulate traffic control > activities. NOTE: Traffic control devices (e.g o barricades,~-traffic cones, signs, etc.) will be delivered to TCP locations but will not be set upi Normal traffic flow will not be disrupted. MSP Troop B- Massachusetts State. Police will demonstrate one-Access Control Point-(ACP) in a similar manner l as described for traffic control points. They will report to the actual locations with the necessary equipment, but normal traffic flow
.will not be-disrupted.
Will-coordinate with and assist local police personnel with traffic control activities as-
-[ required.
MEMA Area IV EOC i with-- EPZ Town EOCs EOC staff will coord' nate and demonstrate the- ability to- take additional measures as necessary,
- Objective 21 - Relocation Centers: Registration l Monitoring, and Decontamination-(Evacuees)-
Will be demonstrated according to' procedure, if needed. Objective 22 - Relocation Centers; Congregate Care-Will be. demonstrated according to procedure, if needed. l l-l-
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Obiective 23 - Medicel Ssr,iens: Trans portation Will be demonstrated in a special exercise. Ob_iective 24 - Medical Services: Facilities Will be demonstrated in a special exercise. Objective 25 - Decontamination: Emergency Workers Demonstrate the adequacy of facilities, equipment, supplies, procedures, and personnel for decontamination of emergency workere, equipment, and vehicles, and for waste disposal. All EPZ towns will demonstrate this objective according to procedures, if - needed. Obiective 26 - Supplementary Assistance (Federal /other) Demonstrate the ability to identify the need for and call upon Federal 4 and other outside support agencies' assistance. Extent of Play MEMA Headquarters EOC The EOC staff (MEMA/MDPH) will demonstrate the call for outside support agency assistance, and will make initial contacts with the appropriate j agencies. All subsequent contacts will be j simulated. l l l
t EOC staff will co:rdinato supplcmentol assistance information with State personnel at the EOF and with MEMA Area IV EOC. NOTE: NOPH is pri,marily responsible for determining the exter.t of assistance (supplementary) required to support dose assessment, field sampling, radiological monitoring, and decontamination activities. These decisions will be accomplished by MDPH liaison at the MEMA Headquarters EOC (Framingham) and through coordination with representatives at the EOF. EOF Will make recommendation for supplementary - assistance. , Objective 27 - Ingestion Exposure Fathway: Sampling Will not be demonstrated this exercise. Objective 28 - Ingestion Exposury_ Pathway; Lab Operation Will not be demonstrated this exercise. Objective 29 - Ingestion Exposure Pathway: Dose Assessment Will not be demonstrated this exercise. Objective 30 - Ir.gestion Exposure Pathway; Protective Action
,,ocommendations Will not be demonstrated this exercise.
Objective 31 - Recoverv, Re-Entry, and Relocation: Total Population Extosure Estimates Will not b? demonstrated this exercise.
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Ooiective 37 - Recoverv, Re-Entry, ano Relocation; Measurcments a Will not be demonstrated this osercise. Objective 33 - Recovery, Re-Entry, and Relocation: J plementation Wi!.1 not be demonstrated this exercise. Objective 34 - Mobillration of Emergency Per s or.nel : 24-Hour Continuous Basis (Shif t Chango) . This objective will not be demonstrated. l Objective 35 - Evacuation of On-Site Personnel This objective is not applicable to the Commonwealth of Massachusetts. Objective 36 - Unannounced and Off-Hours This objective will not be demonstrated during this exercise. . A
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__ . . ,. _ _ . - _ _ _ . . _ . . . _ , - ~ . . _ _ . _ _ _ . . . _ . _ . _ . _ . .__. _ ( l i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 3*O EELRC1BE R 1DELINES AND BCQtE f i t l l l l L. 2154e l l
i 1 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAPEDNESS EXERCISE 1991 3.1 EXERCISE CUIDELINES f
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1 Rev. O Page 3.1-1 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 3.1 I:KERCISE_GillDE11 ties A. Eurinic This package provides guidance for conducting the 1991 V""PS Emergency Response Preparedness Exercise. It provides the framework for demonstrating emergency response capabilities, conducting the exercise and evaluating response activities. B. Esacepts of Qp.cIAliQas_Attd_fontInLJf the Exerging An Exercise Coordinator has beet. appointed by Vermont Yankee management to oversee all exercise activities. The Exercise Coordinator is responsible for approving the objectives and developing the scenario time sequence. The Exercise Coordinator is also responsible for the selection and training of the personnel required to conduct and evaluate the exercise. Vermont Yankee will supply Controllers and Observers (Evaluators) for major locations where an emergency response action will be demonstrated. Prior to the exerciwe, the Evaluators will be provided with the appropriate materials necessary for their assigned function. The material will include any maps and messages to be used and forms f or documenting and evaluating observed activities. In each facility where an activity takes place, the Controller will makte judgment decisions to keep the action going in accordance with the scenario timeline. The Controllers will also provide guidance to Observers and resolve minor problems which may occur. If a serious problem arises, an Observer should first contact the Facility Controller who will then contact the Exercise Coordinator 2154e
Rev. O Page 3.1-2 for guidance or resolution of the problem. All major requests for g,g scenario modifications or holding periods must be cleared through the Exercise Coordinator. Controllers also have the authority to resolve scenario-related problems which may occur durirg the exercise. Observers for the exercise will observe the players as they perform their assigned emergency response f unctions. Observers are responsible for being knowledgeable in the area of their assigned function. The Observers will critique the ef fectiveness of the emergency response actions taken during the exercise and will also provide a written evaluation to their Facility Controller. The exercise initial conditions will be provided to a Control Room operations crew, located in the Simulator, by the Simulator Controller. The plant and reactor system parameters for the f exercise will be generated by running the accident scenario on the simulator. Additional exercise message cards and scenario parameters will be provided by Evaluators at the times indicated in
- the exercise sequence of events, or when requested by the players.
As information is provided to the players, they should determine the nature of the emergency and implement appropriate emergency plan implementing procedures. These nrocedures should include a determination of the emergency clacaification in accordance with the Vermont Yankee Emergency Plan. Notifications will be made to the appropriate federal and state authorities. The hypothesized emergency will continue to develop based on data and information provided to the operators located in the simulator.
- Wherever possible, operators should complete activities as if they
! were actually responding to the plant events. Inconsistencies in the scenario may be intentional and may be required to test the capabilities of the emergency response f acilities to the maximum . extent possible in a limited period of time. 2154e i
Rev. O Page 3.1-3 ( C. Etneral Guidance for the Conduct of the Exercise
- 1. Simulating _faergencv Respanae_ Actions Since the exercise is intended to demonstrate actual capabilities as realistically as possible, participants should act as they would during an actual emergency. Wherever possible, simulation of response activities should be avoided. ,
Emergency response actions should be simulated only when it is not feasible to perform an action or when the action has been previously identified as being simulated during the exercise (refer to Section 3.2). When an emergency response is to be simulated, the Evaluator will provide verbal or written directionr. on which actions are to be simulated. Radiation Work Permits (RWPs) have not been issued for the
' conduct of the emergency response exercise. If scenario events direct players to areas that are actually RWP-controlled due to high radiation, surf ace contamination, or airborne radioactivity, players will simulate response activities without actually entering the RWP-controlled area gren if they are authorized on the RWP for some other duty.
- 2. Avoiding Violatisns of Laws r
Violation of laws is not justifiable during the exercise. To implement this guideline the following actions must be taken:
- a. All Evaluators and potential participants must be l
l specifically informed of the need to avoid violating any i federal, state and local laws, regulations, ordinances, statutes and other legal restrictions. The orders of all police, sheriffs or other authorities shall be followed as appropriate. 2154e 1
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Rev. O Page 3.1-4 (
- b. Participants will not direct illegal actions to be taken by other participants or members of the general public.
- c. Participants will not intentionally take illegal actions when responding to scenario events. Specifically, local traffic laws (i.e., speed limits) will be observed.
- 3. Arciding_.lersonnel_and Propertv Endangerment All participants will be instructed to avoid endangering property (public or private), other persomiel responding to the events, members of the general public, animals and the environment.
- 4. Actions _to_Minimiz u_lublis__laconreniente 8 It is not the intent, nor is it desirable, to elfectively train or test the public response during the conduct of the exercise. Public inconvenience is to be avoided.
The conduct of an exercise could arouse public concern that an actual emergency is occurring. It is important that conversations that can be monitored by t.5e public (radio, loudspeakers, etc.) be pref aced and conclude with the words, "THIS IS A DRILL; THIS IS A DRILL." D. fagrgency RespDase Imp 1tmentation_ and_02cIAlioDS
- 1. Inilial_and_follaw_-Ep_Holific at ion Initial and follow-up notification of the emergency classification will be made by the plant staff in accordance with existing emergency plan impicmenting procedures, unless direct *d otherwise.
2154e
m Rev. O Page 3.1-5
- 2. Control Room Optr.ationg i
A Control Room emergency response crew'will be positioned in the Simulator, located at the Vermont Yankee Training Center in 4 Brattleboro, Vermont. The support staff normally on duty will initially be simulated until after the ALERT when it will be _ perf ormed by the emergency response organisation. The plant and reactor system parameters will be provided to the Control
~ Room emergency response crew by the simulator control board and the' Controllers. Other information, such as radiological data '
and meteorological data, will be provided to the Control Room emergency response crew as necessary. Communications links ; that duplicate the emergency communications capabilities , available at the Control Room will be used to communicate between the Simulator Control Room and other emergency response facilities. The actual Control Room communication system for . , 4 transmission of emergency announcements and information i 1 (e.g., Caitronics) will also be utilized. t
- 3. IcchnicaLSuppar.t_ Canter (Tsc) Operations ,
The TSC emergency response organization will be activated during the exercise. TSC information will originate from the Simulator Control Room. Information that is normally accessible by TSC personnel from the plant computer will be provided by Evaluators utilizin telephone' communications , between the simulator area and plant computer room. In addition. TSC Communicators, who would normally be assigned to the Control Room to provide TSC requested plant data, will be staged at the Simulator. 2154e I f L
Rev. O Page 3.1-6 I ( '
- 4. OptIA11Dns SuppDIl_Ctattr_IDSC1_DptIAL1Qns l
The OSC emergency response organization will be activated ;
.during the exercise. Operations Support Center response activities will be communicated to the Technical Support l Center. OSC Observers will accompany all OSC teams dispatched during the exercise and will provide appropriate operational and radiological data to the players. No team participating in the exercise should leave the Staging Area without an Evaluator.~ ,
- 5. Emergency...Qggrations Facility / Recovery Center-(EOP/RC)
Detr&Linna The EOF /RC emergency response organization will be activat'ed during the exercise. Infonnation and data will be transmitted to the EOF /RC from the TSC and Control Room (Simulator). EOF f' Evaluators.will provide other data to EOF /RC players as { necessary.
- 6. Off-Site Monitoring T RAEA Off-site monitoring teams will be fully activated and dispatched in accon nee with existing proceduren. Simulated data will be pro ved to off-site monitoring teams by the Off-Site Monito Ang Team Evaluators.
- 7. News Media _Ctater_Qparations The News Media Center will be activated and staffed during the exercise. News Media Center staf f will obtain all the necessary information on current plant status through communications channels with the EOF /RC. Press releases will be generated and disseminated in accordance with the Vermont l
2154e
Rev. O Page 3.1-7 i Yankee Connunications Department Emergency Response Plan and Procedures. All press releases are to be cleerly marked: THIS IS A DRILL.
- 8. Security Optraliana All exercise-related security emergency response activities will be implemented in accordance with existing procedures.
Access control and personnel accountability within the protected area will be demonstrated. At no time will actual plant security procedures be violated in support of the exercise. E. Tzgrrise Termination The exercise will be terminated by the Exercise Coordinator when all r emergency response actions have been completed in accordance with the exercise time sequence and exercise objectives. The f ollowing steps will to implemented to terminate the exerciset
- 1. The Exercise Coordinator will obtain information from the Facility Controllers regarding the status of player actions and the demonstration of the exercise objectives.
- 2. The Facility Controllers are responsible for informing the Exercise Coordinator of their facility status and whether the emergency response actions and objectiv(s have been satisfactorily observed.
- 3. Upon receipt of information from the Facility Controllers, the j- Exercise Coordinator will inform the Site Recovery Manager and TSC Coordinator that all exercise observations have been completed and that the exercise can be terminated.
2154e
Rev. O Page 3.1-8 ( 4. A coordinated decision to terminate the exercise will be made ! between the Site Recovery Manager and the TSC Coordinator. The Site Recovery Manager will also receive concurrence from the States to terminate exercise activities.
- 5. The Site Recovery Manager or TSC Coordinator will terminate the exercise.
The exercise may also be terminated under the following circumstances:
- 1. An actual plant emergency condition develops coincident with the exercise.
- 2. An ectuni off-site emergency impacts the response actions of Vermont Yankee exercise participants.
In the event that Item 1 should e'av /, the following ections will be ( taken:
- 1. The Shif t Supervisor will contact the TSC Coordinator and inform him of the plant status. The TSC Coordinator will, in turn, contact the Site Recovery Manager and inform him of the plant status;
- 2. The Site Recovery Manager will immediately inform any State representatives at the EOF of the nature of the emergency; 3.- Concurrent with the notification in Step 2, the Control Room will announce the following statement over the plant paging system "The emergency plan exercise has been terminated. I repeat.
The emergency plan exercise has been terminated." This message may be impediately followed by the appropriate emergency announcements. 2154e
Rey, O Page .3.1-9
- 4. The Exercise Coordinator will be gesponsible for directing the actions of all other exercise participants.
In the event that item 2 should occur, the f ollowing actions should be takent
- 1. The Shif t Supervisor will notify the Contral Room Controller who, in turn, will notify the Exercise Coordinator.
- 2. A coordinated decision will be made in conjunction with the Site Recovery Manager and/or the TSC and EOF Coordinators concerning the completion of tSe exercise.
- 3. The Exercise coordinator vill be responsible for tersporarily halting the exercise ur.til such time a decision is made.
# If the final decision is to cancel the exercise, the Exercise 4.
Coordinator will be responsible for directing the activities of all , exercise participants, as well as for the notification of the NRC.
$. If the final decision is to ' continue the exercise, the Exercise Coordinator is responsible for informing all Evaluetors of any projected changes to the expected response action (s).
- 6. The Exercise Coordinator will direct the organization as to the appropriate action required to restore the exercise sequence.
2154e -
l VERHONT YANKEE NUCLEAR POVER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 3.2 E1AYER INSTRUCTIONS AND CROUND RULES o_ _. _ _ _ . - - _ i__m. --_.-_.- -._. -~___ _._-_____.__m. _ _ _ . - ____. - _ _ _ _ . _ _ _ _ _ _ . _ _ _ - _ _ _ _ . __ -
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I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1991 3.2 PIAYER INSTRUCTIONS AND CROUND RULES The Vermont Yankee Emergency Response Preparedness Exercise will be ; conducted on November 6. 1991. All emergency response facilities will be fully activated, and the scenario will be driven by the simulator, as in past exercises. The exercise being conducted is a full-scale exercise with planned participation from Vermont Yankee, Yankee Atomic, State of Vermont, State of New Hampshire, Commonwealth of Massachusetts and the local towns within the plume exposure pathway emergency planning zone. y The successfu1~ demonstration of emergency response capabilities will 4 depend on player response and protocol. The following information contains exerciso details and instructions for the players regarding the ; exercise, Department Heads are responsible for ensuring that personnel
.are trained on this inforamtion. ,
i A. General Guidelines
- 1. Participants will include the Exercise Coordinator, Players, Controllers, observers, and Federal Evaluators. -Controllers and Observers will provide players with command and message cards to initiate emergency response actions. Controllers, Observers and Federal Evaluators will also evaluate and note player actions.
..ontrollers. Observers, (herein referred to as " Evaluators") and Federal Evaluators will be identified by badges.
- 2. Always identify yourself by nace and function to the Evaluators.
Vear a naae tag if one is provided,
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.!J Rev. O f- Page 3.2-2
- 3. You may ask the Evaluator for information such as:
- a. Initial conditions of the plant and systems including:
o operating history of the core o initial coolant activity o general weather conditions o availability of systems according to the acenario
- b. Area radiation data at the location of emergency teams,
- c. Airborne data at the location of emergency teams after a sample has been properly obtained.
- d. Counting efficiency of all counting equipment.
I^
- e. Activity from nose swabs or skin contamination surveys.
4 You may nar ask the following from the Evaluators:
- a. Information contained in procedures, drawings, or instructions.
- b. Judgments as to which procedures should be used,
- c. Data which will be made available later in the scenario,
- d. Assistance in performing actions,
- e. Assistance in performing calculations.
- 5. Play out all actions, as much as possible, in accordance with your plan and procedures as if it were an actual emersency. If an action or data is to be simulated, an Evaluator will provide
1 l Rev. 0 (,- Page 3.2-3 uppropriate direction.
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- 6. Always identify and discuss your actions to the Federal i Evaluators.
- 7. Periodically speak out loud, identifying your key actions and decisions to the Evaluators. This may seem artificial, but it will assist the-evaluators and is to your benefit.
- 8. When you are assigned to complete a response action, be sure to be accompanied by an Evaluator at all times.
- 9. If you are in doubt about completing a response action, ask your ,
Evaluator for clarification. The Evaluator will not prompt or coach you. Emergency response actions must not place , A participants in any potentially hazardous situations.
- 10. The Evaluator will' periodically issue messages or instructions designed to initiate response actions, . You aggt accept these messages immediately. They are essential _to the proper conduct of the exercise. -
- ll. If an Evaluator intervenes in your response actions and recommends you redirect or reconsider your play actions, it'is >
l for a good reason. The Evaluator's direction may be essential o to the overall success of the exercise for all participating '
-groups.
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- 12. If you disagree w .th your Evaluator, discuss your concerns.
However, the Evaluator's final decisions must be followed. l\ i L -13. Respond to questions in a timely manner. 1 I t-
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- 14. Do not accept any messages / instructions from Federal Evaluators.
They are required to work through your Evaluator if they want to initiate additional emergency conditions. However, you may answer questions directed to you by Federal Evaluators. If you do not know the answer, refer them to your lead player or Evaluator.
- 15. You must respond as if elevated radiation levels are actually present based on the scer.ario information you receive. This may require you to wear protective clothing, respirators, or additional dosimetry.
- 16. Evaluators are exempt from simulated radiation levels and other emergency cotiditions. Do not let this confuse you or cause you to act unwisely. However, no one is exempt from normal station radiological practices and procedures.
- 17. Utilize status boards and log books as much as possible to document and record your actions.
- 18. Always begin and end all communications with the words "THIS IS A DRILL," so that these communications are not confused with an actual emergency.
19 Keep a list of items which you believe will improve your plans and procedures. A player debriefing vill follow the exercise. Provide any comments or observations to your lead player or Evaluator after the exercise. Areas for improvement or weaknesses vhen corrected will improve the overall emergency response capability.
Rev. O Page 3.2-$ B. Player's simulation List , f The following describes those specific actions which do not have to be performed and can be simulated by participants. All other actions are to be performed in accordance with plant procedures. No action l will be allowed which alters or affects the ongoing operation of the plant. The simulation list is as .follows:
-1. Scenario specific data vill not be programmed into the plant process computer. This will be provided by Evaluators utilizing telephone communications between the Simulator and plant .
Computer Room.
- 2. A sufficient number of individuals from the Vernont Yankee Emergency Response Organization v.11 be prestaged at the
-{ Simulator.
- 3. Meteorological data will be simulated using cue cards provided by Evaluators at the appropriate emergency response facilities.
- 4. After plant evacuation accountability has been completed, plant personnel and contractors / visitors not directly_ involved in the exercise will be allowed to return to work, at the discretion of ;
the TSC Coordinator.
- 5. The distribution of potassium iodide (KI) will be simulated. .
- 6. Charcoal cartridges will be used in place of silver zeolite cartridges during off-site monitoring activities.
- 7. The YNSD Site Responders will be prestaged in the area. .
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- 8. No emergency response facility evacuation will be demonstrated
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Rev. 0 Page ".2-6 ( during the exercise. l
- 9. Off-site monitorin5 teams and security boundary monitoring i personnel will not wear protective clothing and/or respirators.
- 10. The inner gate and electrically controlled doors will not be left in the open position during the exercise.
- 11. The plant Caitronies is not available from the simulator; actual plant announcements will be made from the Vermont Yankee plant Control Room.
- 12. Evaluators will not be issued dosimetry unless plant access is required prior to the exercise. Security will be notified of their assigned location.
- 13. All decontamination actions associated with the scenario events may be simulated after discussion and approval by the Evaluator.
14 The use of respiratory protection equipment may be simulated by plant personnel after discussion and approval by the Evaluator.
- 15. Radiation Work Permits (RWPs) have D21 been issued for the conduct of the exercise.
C. Simulator Control Room Information The following describes how the Simulator Control Room emergency response activities will be integrated with the plant Control Room functions dur.ing the exercise:
- 1. Players reporting to the plant Control Room will be direc.ted to an area (SS office) that will have a Control Room Evaluator and
_ _ _ . _ _ , _ . . . _ . _ _ _ ~ - - . _______ _ _ - . _ _-_ __
Rev. 0 Pago 3.2-7 ( communications link with the simulator. All Conttol Room exercise communications should be directed to the Simula:.or Control Room.
- 2. All exercise-related Caitronics calls to the Control Room and vice versa vill be relayed or answered by the Control Room Evaluator. CHANNEL 3 should be utilized for all exercise messages.
- 3. Caitronics plant announcements will be coordinated by the Simulator Evaluator. They wi31 be made by the operating crew in the plant Control Room.
- 4. TSC Communicators normally assigned to the Control Room and a Radiation Protection Technician for transmitting initial j
I radiological and meteorological data will be prestaged in the simulator.
- 5. Process computer ID data, normally accessible by TSC personnel, will be provided by a designated person in the simulator via personnel in the plant Computer Room.
- 6. Perscnnel movement in and out of the Simulator Control Room will be limited to the Evsluators.
- 7. Communications equipment in the Simulator Control Room is the same as the plant Control Room. The commercial telephone exten; ions are different but the auto ring down circuits and speaker telephones are operable. The orange Nuclear Alert-System (NAS) State telephone and red Energency Notification System (ENS)-NRC telephone will be operable. The orange NAS telephone extension is 613. The red ENS-NRC telephone will be operable until the TSC takes over this communication function.
. . .-. _ .-_. . ..-. . . - . . . . . - - . . . ~ . - . - ~ . - . . . . . _ - . - . . . .~ _ _
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Rev. O ; Page 3.2-8
- t D. Player's Camenannable ;
The following is a list of items that should be followed to improve gamessanship during the exercise:
- 1. Make it known when significant events occur or when you are about to perform a significant action.
2.- - Keep all messages, status boards, and problem boards accurate, current, timed, and dated. a
- 3. Hold briefings regularly, approximately every 30-45 minutes, or ,
as conditions warrant. , l' .
- 4. Key players should wear badges which identify their role. Bound-log books should be used in all emergency response facilities.
- 5. All announcemente, including those on the Caitronics, should -
state "THIS IS A DRILL."
- 6. Avoid simulation unless it has been specified. Use protective clothing where called for (e.g., step-off pads, etc.).
E. Personnel Accountability and Particioation
'(Exemoted Particicants)
Procedures require that all participants be identified. ' Proper identification will not only help eliminate confusion, but is necessary for security and accountability. This requirement applies-to all areas within the plant fence, Governor Hunt House, EOF /RC, simulator area, News Media Center, and the Vermont Yankee Corporate , i Office in Brattleboro.
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Rev. 0 Page 3.2-9 ( Although it is expected that all personnel vill respond to the decisred emergency as delineated in the applicable procedures, it is recognized that a number of persons (e.g. , normal plant operations shift, normal security complement, fire watches, etc.) will not participate due to the nature of their normal activities. The Department Heads should review their area of responsibility and provide the Exercise Coordinator with a list of names and positions for anyone that should be exempted from participation. The number of exempt personnel should be minimized. As in the past, people evacuated from the plant will be allowed to return to their normal duties upon approval from the TSC Coordinator. Plant Security will be provided with the list of exempt personnel for the exercise. All other personnel, not listed, are expected to
< participate as required ~oy the Emergency Plan. The list of exempt personnel will is,ciude the On-Shift Security Crew, Operating Crew, and Duty Chemistry and Radiation Protection Technician and the individuals identified by the Department Heads. Security at the Training Center entrance will limit access through the doors to participants for the duration of the exercise.
F. Off-Site Particination (Federal . State and Local) This year, Vermont Yankee is conducting a full scale exercise which will involve the State of Vermont, State of New Hampshire, Commonwealth of Massachusetts, and the local towns within the plume exposure pathway emergency planning zone. The capability to notify federal, state, and local authorities of emergency classifications in accordance with established procedures will be demonstrated as follows:
- a. NRC will be notified by utilizing the red ENS-NRC telephone.
Rev. 0 Page 3.2-10 (-
- b. Vermont, New Hampshire, and Massachusatts State Police dispatchers and State Emergency Operations Centers (EOCs) will be notified through the orange NAS telephone,
- c. Vermont, New Hampshire, and Kasst:chuaetts State officials present at the EOF /RC and the News Media Center (NHC) will be notified by the appropriato Vermont Yankee personnel.
If any state official tries to contact the plant Control Room REGARDING THE EXERCISE, ths Vernon switchboard should transfer the call to the Simulator Concrol Room in Brattleboro. The NAS orange telephone extension in t,he Simulator Control Room is 613. C. Exercise Criticues The following is a brief description of the critique sessions that will be held after the exercise. The critique sessions are held to determine whether the stated exercise objectives were met, verify the effectiveness of the emergency plan and procedures, and identify-areas for future improvements. The specific schedule for the critique sessions will be announced at the conclusion of the exercise. Emercency Response Facility Criticues The critique sessions will be conducted by the Controllers, Exercise participants vill be debriefed on the findings for their particular emergency response facility (s). Four critique sessions will be held:
- 1. SRM and EOF
- 2. TSC and Simulator Control Room
- 3. Operations Support Center and Security 4, News Media Center
Rev. 0 Page 3.2-11 ( Controller Debriefine This session will be conducted by the Exercise Coordinator to compile all exercise comments and findings. Participation is limited to Exercise Controllers. Exercise Criticue This session will be conducted by the Exercise Coordinator to present to management a summary of all major findings identified during the exercise. Participants include Vermont Yankee management, Exercise Controllers, key players, and the NRC, g NRC Exit { Immediately following the exercise critique, the NRC will present their preliminary findings. Participants will be the same as in the exercise critique session. l
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 e 3.3 PROCEDURE EXECUTION LIST r
^' ^ - - - - _ _ - - . _ _ _ _ _ _ _ _
l l 1 Rev. O Page 3.3-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE l'REPAREDNESS EXERCISE 1991 3,3 EMERGENCY PIAN IMPLEMENTING PROCEDURE EXECUTION LIST Procedure Number Rev. No. Title AP 3125 10 Emergency Plan Classification and Action Level Scheme OP 3500 10 Unusual Event OP 3501 11 Alert OP 3502 23 Site Area Emergency OP 3503 25 Gutaral Emergency (
, OP 3504 22 Emergency Communications OP 3507 19 Emergency Radiation Exposure Control OP 3510 18 Off-Site and Site Boundary Monitoring OP 3511 5 Off-site Protective Actions Recommendation OP 3513 13 Evaluation of Off-Site Radiological Conditions OP 3524 9 Emergency Actions to Ensure Accountability and Security Response OP 3525 5 Radiological Coordination OP 3530 14 Post-Accident Sampling OP 3531 4 Emergency Call-In Method l
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 4.0 CONTROLLER AND OBSERVER INFORMATION ,; ' - - - - . -.~ . . . _ . _ _ _ _ _ ,
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 4.1 CONTROLLER AND OBSERVER ASSIGNMENTS l-NOTE: ASSIGNMENTS WILL BE PROVIDED AT THE EXERCISE BRIEFING SESSION
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t VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 4.2 CONTROLLER AND OBSERVER EXERCISE CUIDANCE , f e i 2453e i i
Rsv. O Page 4.2-1
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VERMONT YANKEE NUCLEAR POWER STATION DMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 < 4.2 CONIRDLLEILAND_011ERVER EXERCISE GUIDANCE Prior to the exercise, each Evaluator will be provided a scenario package and the plant emergency plan implementing procedures which correspond to their assignment. It is the responsibility of the Evaluator to read the contents of the package and review the procedures. An Evaluator briefing will be conducted prior to the exercise. Any questions regarding the scenario or arsignments should be discussed at this time. Each Evaluator should ensure that they are familiar with the location (s) required by their assignment.- Emergency response facility tours are available after the Evaluator briefing. The Controller is responsible for directing Observer activities throughout the course of the exercise. When the exercise is terrainated, the Controllers will meet -with the Observers to obtain their comments, observations, and documentation. Each Controller will be responsible for ensuring that the documentation is provided to the Exercise Coordinator at the conclusion of the exercise. Each Controller is also responsible for providing a brief summary cf their facility comments during the player debriefing. Evaluators should identify themselves to the players and explain their role in the-exercise. Players should be informed that any actions which deviate from standard plant or emergency procedures should be identified to the Evaluators. Evaluators should keep a detailed log throughout the exercise. This log should note the time, location, and player responses. Section 4.3 contains log sheets, checklicta, and evaluation forms for documentation purposes. 2453e
Rev. O Page 4.2-2 4 The primary role of Evaluators is to evaluate the emergency renponse activities of the players. In order to document the adequacy of emergency response actions during the exercise, Evaluators are required to complete the Emergency Exercise / Drill Observers Evaluation Form. When completing this form, Evaluators should attempt to differentiate their comments into either adequate or potential weaknesses. For identified weaknesses of personnel, equipment, etc. provide a clear, written explanation of the finding, with recommendations'for improvement which detail corrective actions, if possible. Evaluators should nat allow their biases to be documented as recognized weaknesses or deficiencies. Comments and recommendations should be further subdivided under the general headings as follows: Fceility Activation / Organizational Control, Communications, Adherence to Plans and Procedures Equipment Capabilities, Scenario, Training, Facility Layout, Of f-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Comments. Facility Activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the facility was activated; (3) when initial activities became well organized; (4) whether personnel performance followed the organized arrangements specified by plant procedures; and (5) the efficiency of methods of cuthority transfer. If a transfer of responsibility occurred, then the Evaluator should determine if all affected personnel were aware that the transfer had occurred. Communication comments should identify: (1) personnel familiarity with emergency communications tse; (2) whether sufficient communications were available to ensure a timely, efficient, and effective flow of information; (3) whether there were enough communications personnel to make use of all available equipment; (4) the adequacy of communications logs and the effectiveness of data transfer; (5) whether there were any problems in the design of the existing communications system (i.e., location relative to 2453e
Rev. O Page 4.2-3 ( traffic flow); (6) whether there were any recognized dif ficulties in the use of computer systems; and (7) whether facili'v boards were effectively used. Evaluators should document their comments in this area very carefully, providing sufficient details to track any recognized deficiencies. Plans and Procedural comments should identify: (1) whether personnel were familiar with the details of the overall concepts of applicable procedures; (1) whether situations developed which required deviation f rom the procedures or plan; (3) whsther personnel were overwhelmed with procedural requirements which distracted them from performing their required emergency response function, and (4) whether the procedures adequately described the actions required to complete an assigned f unction. Equipment capability comments should identify: (1) whether all necessary materials and equipment were available and f unctional; (2) whether emergency response personnel checked operability of equipment prior to conducting their assignment; (3) whether backup equipment was readily available when
' malfunctions were reported; (4) whether the available systems provided an adequate service; and (5) whether equipment malfunctions impacted the expected emergency response.
Scenario related comments should address: (1) whether sufficient data were available to ensure appropriate player response; (2) whether the scenario detaile deviated from actual procedural requirements; and (3) whether the scenario detail provided any prompting to the player. The adequacy of the scenario in keeping the players active and interested throughout the exercise should also be addressed by the Evaluators. Training comments should identify: (1) whether plant personnel have b(en provided sufficient training to handle "ad hoc" procedural deviations; and (2) whether training identified improper procedural requirements. 2453e
Rev. O Page 4.2-4 Comments on facility layout deficiencies / recommendations should identify: (1) 1 whether the available work space was adequate; (2) whether traffic flow hindered the response efforts; (3) whether the noise level hindered emergency j response efforts; and (4) whether sufficient references were available to complete the job assignment. Off-site monitoring team observers should identify: (1) the adequacy of sampling methods; (2) the adequacy of contamination control measures; (3) the adequacy of reporting and documentation measures; and (4) the effectiveness of the team in defining the plume condition and sample locations. Dose projection tec. siques should be evaluated in conjunction with this general category. Observations regarding dose projection technique should identify: (1) the effectiveness of the system in allowing the correct interpretation of off-site conditions, and (2) the effectiveness of using the projection technique in positioning off-site teams. f Evaluation of Personnel Dosimetry / Exposure Control activities should identify: (1) the timeliness and effectiveness of dosimetry distribution; (2) the effectiveness of protective measures, such as administration of potassium iodide; (3) the adequacy of established contamination control access points; (4) the adequacy of exposure planning measures afforded in plant activities; and (5) the adequacy of decontamination and posting techniques. The Evaluators evaluation and documentation forms are found-in Section 4.3. All such documentation must be provided to the Controller after the exercise and prior to the plant critique. 2453e
-f.
VERMONT YANKEE NUCLEAR POWER STATION' EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 4.3 CDNIROLLER AND. OBSERVER EVALUATION CRITERIA
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l ( i l 2149e l
Rsv. O Page 4.3-1 4+ s VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISI 1121 4.3 CONTROLLEE! AND OBSERVER EVALUATION CRITERIA l As discussed in Sections 4.1 and 4.2, each Evaluator has been assigned i specific areas of response to evaluate. This section has been developed to assist the Evaluatorr in recording and documenting their findings and obse rvations . The completed material will be an official record of the exercise observations. Attachment A consists of forms to be used in maintaining an event chronology log. Attachment B contains evaluation checklists for each emergency response facility. Each Evaluator should complete the appropriate checklist. Attachment C contains an evaluation form which should be used to summarize major findings and observations. This form MUST BE completed by each Evaluator. All three attachments should be completed and submitted to the facility g- Controller. Each Controller will then submit the attachments to the Exercise Coordinator for documentation and record keeping. 2149e l' l
R2v. O Page 4.3-A.1
. ATTACHMDiI_A VcImQat._ Yankee Nuclear Power _ Elation Emergenev Reiponte_lKRIrittIDrill Evaluator's Observations-Chronologien1 Loc Time Observation /Coment k
Name: Area Evaluated: Date: t 2149e l i t l l
Rev. O Fage 4,3-A.2 ATIAQ21ENT. (Continued) me Observation /Commtat _.
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wo v Name: Area Evaluated: Date: 2149e
Rev. O Page 4.3-B.1 ATTACHMENT B Vermont._ Yankee Emergency Exercise / Drill Evaluation._ Check List INSIEUCIIDMS The following evaluation check lists are provided to assist the Evaluator with their evaluation of the drill / exercise. The Evaluator should complete the check list (s) for their assigned location (s). To complete the evaluation check list (s), utilize the rating scale listed below. Any comments or suggestions f or improvement, should be included on Attachment C, the Emergency Exercise / Drill Evaluation Form or on a separate piece of paper. Rating Ssubn1 Coments_and_ Suggested Imprarements Adequate A May be followed by comments and suggestions for improvements, especially if rating is marginal.* Inadequate I Must be followed by comments, together with suggestions for improvement. Not Observed or N No comments or suggestions Not Applicable are required.
- Comments should also include strong positive strengths that were demonstrated by player actions and response.
2149e
Rev. O Page 4.3-B.2 ATTACIIMENT B (Continued) Engg Section 4.3-B.3 I. Control Room (Simulator and Actual) 4.3-B.5 Technical Support Center II. Operations Support Center 4.3 ').8 III. 4.3-B.11-IV. Emergency Operations Facility / Recovery Center Site and Off-Site Monitoring 4.3-B.14 V. 4.3-B.15 VI. Security News Media Center 4.3-B.16 VII. .{ 2149e
Rev. O Page 4.3-B.3 ATTACRMENT B (Continued) I. CONTROL RODM Rating Comments A. Accident Assessment /Emernency Classification
- 1. Did the Control Room staff demonstrate Yes/No the ability to recognize emergency initiating conditions and classify the events in accordance with AP-3125.
- 2. Did the Control Room staff demonstrate Yes/No the ability to coordinate the assessment of plant conditions and corrective actions with the Technical Support Center?
B. Notification and Communication Did the Control Room staff demonstrate the Yes/No 1. ability to notify the plant staff of an emergency through the use of alarms and the public address system? Did the Control Room staff demonstrate the Yes/No 2. ability to notify federal and state authorities of emergency classifications in accordance with eatablished procedures? Was information flow within the Control Room Yes/No 3. and to other appropriate emergency response facilities t'mely, complete, and accurate?
- 4. Was adequate record keeping of events, actions Yes/No and communications documented and logged by the Control Room staff?
- 5. Were adequate emergency communication systems Yes/No available in the Control Room to transmit data and information to other emergency response facilities?
2149e
Rev. O Page 4.3-B.4 i ATTACINENT B I (Continued) l I. CQHIROL ROOM Rating Catments C. Activation and Respanat
- 1. Did the Control Room staff demonstrate the Yes/No ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
- 2. Was the person in charge in the Control Room Yes/No clearly identifiable and was good command and control taken at the Control Room?
i Controller / Observer Name: 2149e
s i Rav. 0 .
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Page 4.3-B.5 _ ATTACHMENT B (Continued) II. IECHNICAL SUPPORT CENTER Rains Consaents A. Accident Assessment / Emergency Classification
- 1. Did.the TSC staff demonstrate the ability to Yes/No support the Control Room staff in identifying the cause'of the incident, mitigating the consequences-of that incident. and placing the plant in a stable condition?
- 2. Did the TSC ataff demonstrate the ability to Yes/No coordinate the assessment of plant conditions and corrective actions.with the control Room?
- 3. Did the TSC staff demonstrate the ability to Nes/No to-initiate and coordinate errrective actions in an efficient and timely manner?
- 4. 'Did the TSC staf f demonstrate the ability to .Yes/No direct and coordinate the taking of
(~ appropriate chemistry samples to analyze plant conditions? Did the TSC staff' demonstrate the ability:to Yes/No 5
. participate with the Centrol Room and EOF /RC in emergency classification and EAL discussion.
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B. Notif1 cation-and CommunicAtiDD
- 1. Was information flow within the TSC and to Yes/No-other appropriate emergency response facilities timely, complete, and accurate?
l I .
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Rev. 0 Page 4.3-B.6 ATTACHMENT B (Continued) II. TECHNICAL SUPPORT CENTER , Rating Comments
- 2. Was adequate record _ keeping of events, Yes/No actions, and communications documented and logged by the TSC staff?
- 3. Were adequate emergency communications systems Yes/No available in the TSC to transmit data and information to other emergency response facilities?
- 4. Was information concerning plant conditions Yes/No disseminated between the Control Room and TSC performed in a timely manner?
- 5. Were status boards utilized and maintained Yes/No to display pertinent accident information at the TSC7 ,
- C. Activation and Response
- 1. Did the TSC staff demonstrate the ability Yes/No to activate and staff the TSC?
- 2. Did the TSC staff demonstrate the ability Yes/No to appropriately implement Emergency Plan Implementing Procedures and did they follcw them?-
- 3. -Were initial and continuous accountability Yes/No checks of TSC and CR personnel performed?
- 4. Did the TSC Coordinator establish and Yes/No coordinate access control into the Protected Area and Control Room?
2149c
Rev. O Page 4.3-B.7 fs. AIIACIIMENI_B (Continued) II. IECHNICAL SUPPORT CENIER Ratint CQmmen11
- 5. Did the TSC Coordinator demonstrate the Yes/No ability to maintain command and control of TSC emergency response activities?
- 6. Did the TSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had developed?
- 7. Was the TSC organization and initiation Yes/No of activity efficient and well organized?
i Controller / Observer Name: 2149e l
i Rev. 0
.Page 4.3-B 8 i
ATTACHMENT _]) ! i ! (Continued) a: A i . !i 111. OPERATIONS SUPPORT CENTER t Rating Cssumenta f' . 1: .
- A. Notification and Carnrnunication V
Yes/No g 1.- WasLinformation flow within the OSC and to
- other appropriate emergency. response facilities timely, complete,.and accurate?
- 2. ,Was adequate record keeping of events, actions. Yes/No J
- and communications' documented and logged by' j- the OSC staff?
- 3. Were adequate: emergency conruunications systems Yes/No ;
available inithe OSC to transmit. data and l 'information to other emergency response ] i facilities? l
- 4. -Were status boards utilized and maintained to Yes/No display pertinent accident information at the
.f : (l OSC7
'B.- Activation and Response
!! 1.- Did.the OSC staff demonstrate the ability to Yes/No Y activate and' staff the OSC7~ i .f -2. Did the OSC staff demonstrate the ability to Yes/No. j! -appropriately implement Emergency Plan-i- Implementing Procedures and did they follow them? 4 5-3 .- Were initial and continuous-accountability Yes/No checks of~0SC personnel performed?~ S e e k
;,. 2149e J-
I Rev. O Page 4.3-B.9 ATTACHMENT B (Continued) III. OPERATIONS SUPPORT CENTER EAling Comments
- 4. Did the OSC Coordinator and OSC Coordinator's Yes/No Assistant demonstrate the ability to maintain command and control of OSC emergency response activities?
- 5. Did the OSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had developed?
- 6. Was the OSC organization and the initiation Yes/No of activity efficient and well organized?
- 7. Did the OSC staff demonstrate the ability to Yes/No provide adequate radiation protection controls for on-site emergency response f personnel?
- 8. Did the OSC staff demonstrate the ability to Yes/No monitor and track radiation exposure of on-site emergency response personnel?
- 9. Did the OSC staff demonstrate the ability Yes/No to obtain and analyze appropriate chemis' cry samples as directed by the TSC?
- 10. Did the OSC staff demonstrate the ability Yes/No to initiate, brief, and dispatch On-Site Assistance Teams?
2149e
R2v. O Page 4.3-B.10 ( ATTACEMENT B (Continued) III. OPERATIQRS._SUfPORT CENTER Yes/No
- 11. Were on-site assistance teams able to trouble-shoot and evaluate problems with plant equipment and systems?
- 12. Were their adequate administrative controls Yes/No and documentation taken to perform the necessary repairs of plant equipment and systems during an emergency situation?
8, Controller /Obsecver Name: 2149e
Rsv. O Pags 4.3-B.11 ATTACHMENT B (Continued) IV. EMERCENCY OPERATIONS FACI M lRECOVERY CENTER Rating Comments A ., Natification and Communiention
- 1. Was information flow within the EOF /RC and Yes/No to other appropriate emergency response facilities timely, complete, and accurate?
- 2. Were adequate emergency communications systems Yes/No available in the EOF /RC to transmit data and information to other emergency response facilities?
- 3. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the EOF /RC staf f ?
- 4. Was information concerning plant conditions Yes/No y disseminated between the TSC and EOF /RC performed in a timely manner?
- 5. Were status boards utilized and maintained Yes/No to display pertinent accident information at the EOF /RC?
B. Activation and Response
- 1. Did the EOF /RC staff demonstrate the ability Yes/No to activate and staff the EOF /RC7
- 2. Did the EOF /RC staff demonstrate the ability Yes/No to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
l l 2149e i t l l.
Rev. 0-Page-4.3-B.12
~fi ATTACHMENT B (Continued)
IV. - EMERGENCY OPERATIONS FACILITY / RECOVERY CENTER Rating Comments
- 3. Did the Corporate Security Force establish Yes/No access control into the EOF /RC7
- 4. Did the EOF Coordinator demonstrate the Yes/No ability to maintain en-mand and control of
-EOF' emergency response activities?
5.- Did the EOF /RC keep other emergency response-Yes/No 1 facilities advisedaof the status of their activities and information which they had developed?
- 6. Were the EOF /RC organization and the initiation Yes/No of activity efficient and well organized?
- 7. Pld the_ Site Recovery Manager demonstrate the Yes/No g
ability to maintain the command and control of ( the overall emergency response effort and organization?-
- 8. Did the Site Recovery Manager demonstrate the_ _ Yes/No Jability to de-escalate from the emergency phase into the recovery phase?
9.- Were preliminary-recovery plans established Yes/No and-discussed between the Site Recovery _ Manager _and: appropriate personnel? C. Radiological Assessment
- 1. Was information concerning radiological and Yes/No meteorological data obtained by appropriate EOF personnel in a timely manner?
- 2. Did the EOF staff demonstrate the ability _, Yes/No to perform off-site dose assessment in accordance with Procedure OP-3513?
2149e e 1 y e , m -w+ - - -
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i Rsv. O Page 4.3-B.13 ATIACHMENT B (Continued) IV. DiERGENCY OPERATIONS FA'JILITY/RECQVERY CENTER 4 Ratins - Comments
- 3. Did the EOF staff demonstrate the ability to Yes/No' effectively track and detine the plume utilizing the computerized dose assessment model (METPAC)?.
-D. hctgetive Action. Decialon-Mak4nn
- 1. -Did the Radiological Assistant's-staff Yes/No-demonstrate the ability to perform timely-assessment ~of off-site radiological' conditions to support the formulation of '
protective _ action recommendations?
- 2. Did the EOF Coordinator obtain and provide Yes/No the necessary information to-the Site
- . Recovery Manager concerning protective
.f action recommendations in accordance with 1 Procedure OP-3511.
- 3. Did the Site Recovery Manager demonstrate Yes/No the ability to make protective action recommendations to'off-site authorities in accordance with Procedure OP-35117 Controller / Observer Name:
2149e i t a . - - + , . - . . . .-v. - -- + . - , , e , ,, ,-,-- n -,-w, . - - . . . n a p ,c--- -an-
Rsv. O Page 4.3-B.14
- ATTACHMENT B (Cor.tinued)
V. SITE AND OFF-SITE MONIT0HING Rating Comments A. Activation _and Respongs
- 1. Did the site and off-site monitoring teams Yes/No demonstrate the ability to transmit information over the radio utilizing proper units and terminology in accordance with Procedure OP-35107
- 2. Were site and off-site monitoring teams Yes/No dispatched and deployed in a timely manner?
- 3. Were team members familiar with the use of Yes/No equipment, field monitoring procedures, and what was required of them?
- 4. Were off-site monitoring teams able to Yes/No determine and communicate their location in the field using appropriate maps and sample points (landmarks)?
'5. Were of f-site monitoring teams briefed on Yes/No
~
plant conditions and changes? Controller /0bserver Name: 2149e i
Rcv. O Pcgs 4.3-B.15 k' ATTACHMENT B (Continued) VI. SECEIH Eating Comeats A. Activation and Respsnge
- 1. Did the Security staff demonstrate the ability Yes/No to perform accountability of personnel within the Protected Area in accordance with Procedures OP-35247
- 2. Were access control points established and Yes/No maintained to control access at the site and the Protected Area?
- 3. Did the Security staff demonstrate the ability Yes/No to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
1 Controller / Observer Name: 2149e l 1 1
4 Rsv. O Pege 4.3-B.16
- AIIACHMENT l (Continued)
\'li. HESJEDIA CMIER RALing Comments A. htivation and Resopnsa
- 1. Did the News Media staff demonstrate the Yes/No ability to activate and staff the News Media Center?
- 2. Was information flow between the News Media Yes/No Center and EOF /RC timely, complete, and accurate? ,
- 3. Were the News Media staff familiar with their Yes/No plans and procedures and do they follow them?
- 4. Did the News Media staff demonstrate the Yes/No ability to provide accurate and timely information concerning the emergency to the
,g public and the news media?
- 5. Did the News Media staff demonstrate the Yes/No ability to coordinate news releases with the state's public inf ormation representatives?
- 6. Did the News Media staff demonstrate the Yes/No ability to provide briefings for and to interf ace with the public and news media? _
Controller / Observer Name: 2149e
Rev. O Pcgs 4.3-0.1 ) AIIACIDfENT C Emergency Exercise / Drill Observer's Evaluation Form Observer's Name: Exev.ise/ Drill Date: Exercise / Drill
Title:
Observer's Location: Time Started: Time Ended: Observed: Player Function Overall Performance and Observations: (include the proper and effective use of procedures, equipment and personnel): A 4. Recognized Deficiencies: Comments and Recommendations (Specific): EQIE: Use additional peges as required. Signature:
Title:
VYOPF-3505.02 OP-3505, Rev. 14 Page.1 of 1 2149e
Rev. O Fage 4.3-0.2 h ATTACHMENT C (Continued) 3 1 Continued on Additional Pages Yes No Signature:
Title:
Date: l l 1149e I i
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VERMOWT YANKEE NUCLEAR POWER STAT. 14 EHERGENCY RESPONSE PREPAREDNESS EXERCISE 1991
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(.. s VERMONT YANKEE NUCLEAR P0k'ER STATION EMERGENCY RESPONSE ?REPAREDNESS EXERCISE I 1991 l l l l 5.1 INITIAL CONDITIONS i
Rev. 0 Page 5.1 1 ( VEPJt0NT YANKEE NUCLEAR PO'JER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 5.1 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The reactor is now at approx 'tely 1006 power. The reactor has been operating steady state .,r the past fifteen months with no recent shutdowns.
- 2. Hight Orders for the operations. crew provide.v the following information:
a .- The llPCI system failed surveillance testing due to flow o controller failure putting the plant in a 7 day LCO. IIPCI has been declared inoperable. In accordance with Technical Specifications, alternate testing is in process by 160.
- b. 16C is performing the functional test of the Automatic Depressurization System trip logic. This test is required as a condition of tech, spec. for llPCI inoperability,
- c. Off gas system radiation levels have been elevated throughout the operating cycle indicative of minor fuel pin leakage,
- d. Reactor Engineering has instructed that power changes shall be limited to less than it per five minutes due to the suspected fuel pin leakage.
- 3. All other power generating and safety system equipment is operable, i
I i
i l Rev. 0 l Page 5.1 2 - ( . l
- 4. The following on site meteorological conditions exist at 0700: i Vind Speed, aph (lower / upper) 4.0/5.0 Wind Direction, degrees (lower / upper) 180/185 Delta Temperature 'T (lower / upper) 1.0/1.5 Ambient Temperature, 'F 40.0 Precipitation, inches 0.00
- 5. Regional Meteorological Forecast Information:
A low pressure system is located along the Atlantic seaboard, liigh temperatures in the middle to upper 50's; low temperatures in the middle 40's, Winds from the south at 4 5 mph, swinging around to the southeast this afternoon and diminishing in int'ensity. Winds will continue to shif t, coming around to the north and ~ increasing-in intensity to 5-7 aph. I
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l 1 Rev. O Page 5.1 3 { Table 5.1 1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 158 Inches Reactor Pressure 1007 psig Reactor Coolant Temperature 528 'F Reactor Power APRM (average) 100 % Core Plate D/P 18 psid Total Core Flow 47 x 10' lbm/hr Main Steam Line Flow Total 6.4 x 10' lba/hr Main Steam Line Radiation 170 uR/hr Condenser Hotwell Level 55 t Condenser Vacuum 1.8 in. Hg(Abs) Condensate Storage Tank Level $1 % Recire Drive Flow 30 Kgpm/ loop - ! Feedwater Flow 6.3 x 10' lbm/hr Reactor Building D/P -1.62 in H 30 Drywell Pressure 17 psia Drywell Temperature 106 *F Torus Water Level 0.56 ft Torus Temperature 72 'T Drywell/ Torus 0 2 Concentration 2.58 % High Range Containment Monitors 4 R/hr Containment Cas/ Particulate 500/25000 cpm Reactor Building Vent Monitors Cas/Part 190/1530 cpm Reactor Building Vent Exhaust N/S 2.0/2.0 mR/hr Steam Jet Air Ejector (ARM). 250 mR/hr SJAE Discharge Rate 50,000 pCi/sec Stack Gas 1/11 150/200 cpm High Range Noble Gas Monitor .1 mR/hr
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1 m:v.o ress 5.1 4 VERMONT YANKEE DAILY STATUS REPORT (' THIS IS A DRILL DATE: un a 1991 PIANT OPERATING STATUS VALUE DATE TIME
- 1. Core Thermal Power (Wt ) l (1) 1593 $ lect 0700 (We) S36 0700
- 2. Gross We (W 8 ) 511 0700
- 3. Not W e Gross MJh for previous day (Wh ) 12S23 4.
(Mlb/hr) l (1) 47 l 97.91 0700
- 5. Core Flow REACTOR COO 1 M T SYSTEM
( tanhe / ca ) 0.0$$ 11/S/91 0930
- 6. Conductivity ~
Unidentified Leak age 8 midnight previous y,v g 'pa) 0.00 7 ,
- 8. Totst Leak age 8 sidr.ight pr evious day ,,
' giro) 2.e5 spn/ml) 150446 11/5/91 0900
- 9. Gross Activity
- 10. 10 dine-131 Dose Equivalent , (utils1) 4.50E-03 11/S/91 0900
. .s STACM RELEASES (ti/ period' 4.06E-03 11/4/91 1630
- 11. Farticulate (uC1/sec) e100 11/6/91 0115 12 Averspe (uC1/sec) NONE 11/6/91 011S
- 13. Pe ak (Mev) 1.12 11/6/91 0115
- 14. Discharge Aversse Ganssa Energy Dose Rate to Critical Org ans (aram/ year) 4.42 1174/91 143n
. 15. 3.30E-0$ 1430 (uC1/sec) 11/a/91
- 16. lodine-131 OFF CAS ANALYSIS (uC1/sec) S0000 11/6/91 0115
- 17. SJAI Dia. Release Rate Measured / Estimated
-0.253 11/6/91 0115
- 18. EJAI Discherse Slope of MLrture Condenser Air Leakage (cfa) 19.6 11/6/91 0115 19.
LIQUID RELEASES 6 RIVER TEMPERATURE
- 20. Liquid Release (Gal) NA
- 21. Liquid Release (Gross Bete. Game ) (uC1/ml) RA (uC1/m1$ NA
- 22. Liquid Release ( T r it iute )
- 23. Liquid Release (Dissolved Noble Gas) (uC1/mt) HA Rive r Pbn . 93 Eithest Temp. for previous dev (oF) SS 2115 24 M WUP Core Avg. Burnup for previous day (WDIST ) 16945.75 25.
- 26. Core Cycle Burnup for previous day (PSC / ST ) 6325.45 REVIEWER:
THIS IS A DRILL i
l VERHONT YANKEE NUCIJAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 5.2 NARRATIVE SlMMARY 3 0
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Rev. 0
' Page 5.2 1 l
VEPEONT YANKEE NUCLEAR POWER STATION I EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 5.2 NARRATIVE SlMMARY The scenario begins at 0700 with the simulator reactor running at approximately 1004 power. The reactor has been in a steady state for the past fifteen months with no recent shutdowns. Night orders have informed the operations crew that the !!igh Pressure Coolant Injection (HPCI) system has failed surveillance testing due to flow controller failure. As a result, the plant has entered into a 7 day Limiting Condition for Operation (LCO) and HPCI has been declared inoperable. Alternate testing required by Technical Specifications (Tech. Specs.) is in the process of being completed by Instrumentation and Control (16C) . The 16C Department is also performing the functional test of the Automatic Depressurization System (ADS) trip logic. The ADS functional test is required by tech, spec. to be completed because of the HPCI problem. The off-gas system radiation IcVels have been elevated throughout the operating cycle indicative of a small fuel pin leak. Reactor Engineering has included instructions to limit power changes to less than it per 5 minutes due to suspected fuel pin leakage. All other power generating and safety system equipment is operabic. At 0715 I6C reports that the ADS logic functional test was not satisfactory. A relay in the circuit has failed and must be replaced. Upon notification that ADS logic is inoperable, the Shift Supervisor should declare en UNUSUAL EVENT (approximately 0730). The UNUSUAL EVENT is based upon AP 3125, " Loss of Systems or Equipment" (plant shutdown required in accordance with LCO of Tech. Specs.). i i l
i Rev 0
- Page 5.2 2 The Shift Supervisor should initiate the appropriate notifications concerning the declaration of the UNUSUAL EVENT and changing plant conditions. The shift operations crew will begin a controlled power reduction in accordance with Tech. Spec. 3.5.E.3 which requires an orderly shutdown be initiated and the reactor pressure be reduced to 120 psig within 24 hours.
At 0815, electrical bus DC 3 is lost. The Simulator Control Room (SCR) board panalaros have become inoperable. When the SCR personnel recognize the loss of the panalarms, the Shift Supervisor should declare an ALERT (approximately 0830). The ALERT is based upon AP 3125, " Loss of Systems or Equipment", (loss of Control Room alarm panels). Following the ALERT declaration, the Technical Support Center (TSC), Operations Support Center (OSC), and Emergency Operations y Facility / Recovery Center (EOF /RC) will be activated and staffed. Notifications should be made to the appropriate personnel including the state and federal authorities. The Control Room staff will initiate actions to stabilize the plant, and dispatch plant personnel to investigate the loss of electrical bus DC 3. This investigation reveals that the bus transfer mechanism failed. The failure is such that DC-3 has lost power from DC 2 and cannot be shifted to DC 1. In order to return bus DC 3 to service, the transfer device will have to be repaired. Plant personnel should be dispatched to repair the failed device. The Shift Supervisor may elect to suspend shutdown activities until the panalarms are returned to service (this should occur by 0945). Shortly after DC-3 is returned to service, the SC,R crew will notice decreasing vacuum in the main condenser. At 1015, a low Main Condenser vtscuum alarm is received. The turbine trips on low condenser vacuum initiating an automatic reactor SCRAM. When the reactor SCRAM signal l l occurs, the control rods fail to insert causing the reactor to remain
__._._.__._7 I Rev. 0 Page 5.2-3
-k critical and an Anticipated Transient Without Scram (ATWS) condition ,
exists. Reactor power will remain above 2 percent. The Main Steam Isolation Valves (MSIVs) remain open and pressure is being regulated through the turbine bypass valves to the Main Condenser. The operators will attempt to individually drive control rods into the reactor core. Operators will implement actions to reduce reactor power and stabilize plant conditions. By 1020, Main Condenser vacuum continues to decrease causing the closure -j of the MSIVs on Group 1 isolation. The Main Condenser is no. longer , available as a-heat sink. Control rods are still not-fully inserted and I reactor power remains above 2 percent. The "B" inboard' MSIV fails to isolate as indicated on the SCR board (open indication).
- A SITE AREA EMERGENCY should be declared (approximately 1030) based upon ,
i AP 3125, " Loss of Systems or Equipment", (failure of Reactor Protection System (RPS) to initiate and accomplish a required SCRAM with the Main condenser unavailable). Upon ~ MSIV isolation operators will implement actions to stabilize the plant. This will include using the Safety Relief Valves (SRVs) with the , torus as the heat sink to control reactor _ pressure. During this evolution, the operators will monitor _ torus temperature and level. ; By 1045, torus temperature is increasing. RHR will be in Torus Cooling l Mode. At approximately .045, the circuit breaker for the "C" RitR pump fails. This causes the motor to trip and the "A" RRR pump to start. An OSC Team should be dispatched to investigate the unit failure. Before torus temperature reaches 110 degrees, operators will attempt to initiate i I Standby Liquid Control (SLC) to bring the reactor subcritical. Initiation of SLC will cause an isolation of the Reactor Vater Cleanup (RWCU) system. When the isolation signal is received, RWCU V-12 15 fails to close due to MOV motor controller failure. (Note: The isolation of the RUCU system may
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Rev. O Page 5.2 4 occur earlier due to the lowering of reactor water level. RWCU V-12 15 will fail Lo close upon either isolation signal.) An OSC team should be dispatched to the Reactor Building to investigate the problem. The initiation of SLC will be unsuccessful when both squib (explosive) valves fail to actuate upon initiation. Plant personnel should be dispatched to
- manually actuate the squib valves to initiate S14 injection.
Concurrently, operators will continue to implement actions to insert control rods. Plant personnel should be dispatched to manually close the Control Rod Drive (CRD) charging water header isolation valve (CRD-56). When CRD 56 is shut, CRD flow is regained and the rods can be individually inserted using the RMCS. While plant actions are taking place to allow for control rod insertion, the SCR operators will be lowering reactor water level as another means of
- reducing reactor power. At this time, it is postulated that fuel damage occurs due to pressure transients associated with cycling of the SRVs for pressure control.
Reactor power reduction and pressure control will continue. Once all control rods have been inserted into the reactor core, operators will commence a reactor cooldown. Plant conditions will stabilize and remain fairly constant for the next hour. Plant personnel will be investigating why the "B" inboard M51V remains partially open, At 1200, a small leak occurs from a Reactor Recirculation Line into the drywell. High Drywell pressure alarm exists and is increasing. The containment high range monitor readings are increasing significantly. By 1205, the containment high range monitor readings have increased to greater than 10,000 R/hr (approximstely 20,000 R/hr).
Rev. O Page 5.2 5 A CENERAL EMERGENCY should be declared (approximately 1215) based upon AP 3125, " Fuel Damage," (loss of two of three fission product barriere with the potential loss of third). At 1255, the Simulator Operator will insert a casualty that causes a large steam line break outside the primary containment in the steam tunnel. The steam line break is between the inboard and outboard MSIV on Main Steam Line B. By 1300, a rapid depressurization of the reactor will occur as a result of the steam line break. Area Radiation Monitors in the Reactor Building are increasing significantly. Steam tunnel temperatures have increased-significantly. Release of radioactivity from the plant vent stack (PVS) begins. , By 1315, PVS high range monitor is indicating a maj or release of ( radioactivity to the environment. By 1400, the Simulator Control Room indications show that the inboard MSIV on Main Steam Line B has closed, thereby isolating the leakage into the Reactor Building. By 1515, the PVS high range monitor is decreasing. The 'ource of the release into the Reactor Building has been controlled. The release of radioactivity to the environment will continue to decrease over time based upon the volume exchange rate of the Reactor Building through the Standby Cas Treatment System. At 1530, the exercise will be terminated. ,
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l i l9 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 5.3 SCENARIO TIME LINE e a w p- 9 --w- - - - y yy y y e.g yy -v9ygr- -.ro gma y gy vw ga am- .. , -semr. -, --.m m --i's--+ m-.e--+-eee- -rmv+>t +- ' , M-v-e - , - + + .
Rev. O Page 5.3 1 {' VERMONT YANKEE NUC1. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 5.3 SCENARIO TIME LINE CIDCK SCENARIO TIME TIME DESCRIPTION 0700 0:00 . <... Initial conditions established in the Simulator Control Room. 0715 0:15 $ < . 160 reports functional test of ADS is unsatisfactory. 0730 0:30 $ <... LINUSUAlf EVENTj (APJ3125,214SS)F'SYSTDIS?0R'; EQUIPMENT), . Plant
. shutdown required in accordance with LCO in Tech. Specs.
0745 0:45 . 0800 1:00 . I 0815 1:15 . <.-. Electrical Bus DC-3 is lost. Panalarms on the Simulator Control
. Room Board have become inoperable.
0830 1:30 <.-. SEPT"(AP 31252 LOSS OFLSYSTEMSJO,R; EQUIPMENT) . Loss of Control Room 3 _
. Alarm Panels.
0845 1:45 . <... Plant personnel dispatched to investigate problem with Electrical
. Bus DC.3.
0900 2:00 L 0915 2:15 . 0930 2:30 . 0945 2:45 $<.--ElectricalBusDC-3returnedtoservice. Panalarms on Simulator
. Control Room Board operable.
1000 3:00 -
Rev. O Page 5.3 2 5.3 SCENARIO TIME LINE (continued) CIDCK SCENARIO TIME TIME DESCRIPTION ' 1015 3:15 . <- - Lov Main Condenser Vacuum alarm. Turbine trips. Rx SCRAM signal
. occurs with control rods not inserting. ATWS condition exists.
1020 3:20 . < .. Main Condenser vacuum continues to decrease which causes MSIV
. closure on croup 1 isolation. Control rods still not inserted and
. Reactor Power above 24. Inboard MSIV on Main Steam Line B indicates open.
1030 3:30 . <... BITE"ARrfEMER0ENCYf(API 3125IjuS5;OCSTSTEMS10R^RQUIPMENT), . ,
. Failure of Reactor Protection System (RPS) to initiate and
. accomplish a required SCRAM with the Main Condenser unavailable.
1045 3:45 . <... Torus temperature increasing, "C" RHR Pump trips. 1100 4:00 . < .. Operators continue to implement actions to reduce reactor power and
. stabilize plant conditions. RWCU V1215 will not close on isolation
- signal.
1115- 4:15 .
.e .
1130 4:30 . 1145 4:45 .
~
1200 5:00 . <--- Drywell pressure increasing due to leakage from a recire line into
. the dryvell, Containment high range monitor readings increasing
. significantly.
1215 5:15 . <... GENERAL;EMERCENCYJ(AFj3125{TUEL} DAMAGE) - less of 2 of 3 fission
- product barriers with the potential loss of third.
1230 5:30 . 1245 5:45 . 1255 5:55 5 <... Steam line break occurs between the inboard and outboard MSIV on Main Steam Line B outside primary containment-in the steam tunnel.- --: l l l a - -. -., . . _ . _ _ . . _ . . , _ . , _ _ _ , _ , _ _ _ _ _ _ _ _ _ _ . , . ,_ , _, ._
Rev. 0 Page 5.3 3 ( 5.3 SCENARIO TIME LINE (continued) CIEX SCENARIO TIME TIME. DESCRIPTION 1300 6:00 . <. .. Rapid depressurization of the reactor occurs. Area Radiation
. LMonitors in the Reactor Building increasing significantly.
. EELEASE,,0 FJEADICACTIVITEFRDW; TEE;FIANTISTACE:3EGINS.
1315 6:15 - < ... Plant Vent Stack high range monitor indicating a major release of
. radioactivity to the environment. Significant levels of
. radioactive material are present in the Reactor Building and will-be released through the Plant Vent Stack.
1330 6:30 . 1345 6:45 . 1400 7:00 - <. . . Simulator Control Room indications show that'the-inboard MSIV on
. MSL B has closed. LEAEACE; INT 0'THE 1EACTOR;BUILDINGTIS"IS01ATED. s 1415 7:15 .
1430 7:30 .
--1445. 7:45 .
1500 8:00 . 1515 8:15 . <- . . Plant Vent Stack high *ange monitor decreasing. SOURCETOFl RELEASE FROM THEfPLANT.cVENTfSrACKLEAElBEEWiCONTROLLED. Plant conditions
- stabilizing.
1530 8:30 . <. . . EXERCISE IS TERMINATED. 4
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VERMONT YANKEE NUCLEAR POWER STATION , i 1 EMERGENCY RESPONSE PREPAREDNESS EXERCISE
\
1991 i i 1 5.4 DETAILED SEOUENCE OF EVENTS l
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Rev. O Pege 5.4 1 VERMONT YANREE NUCLEAR POWER STATION ( EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 l 5.4 DETAILED SEOUENCE OF EVENTS Clock Scenario Message Titre . Titre Event / Action Information Prior to EXPECTED CONTROL ROOM (CR) ACTIONS WILL BE 0700 00:00 IMPLEMENTED BY AN EXERCISE OPERATIONS CREW (INCLUDING SUFFICIENT NUMBER OF PRESTAGED INDIVIDUALS FROM THE VERMONT , WKEE EMERCENCY ORGANIZATION) IhCATED IN TIIE SIMU1ATOR COMPLEX IN THE CORPORATE TRAINING CENTER. OPERATIONAL CONTROL ROOM DATA WILL BE PROVIDED BY Tile SIMU1ATOR INSTRUMENTATION RESPONSES. IN CASES VHERE SPECIFIC INFORMATION NOT MONITORED BY THE SIMULATOR IS REQUIRED, IT WILL BE ISSUED BY CONTROLLERS /0BSERVERS ON MESSAGE CARDS. IN THE EVENT THAT A SIMU1ATOR MAIJUNCTION OCCURS, Tile EXERCISE WILL BE CONDUCTED USING INFORMATION DEVEIAPED FROM SECTION 8.0 AND SECTION 9.0. The Simulator CR Controller issues initial SCR M-1 conditions to the simulator CR players. SCR C 1 Guidelines for use of Caitronics and the plant evacuation alarm are provided to players.
Rsv. O Pege 5.4 2 Clock Scenario Message Tine. Tire E:ent/ Action Information Prior to Initiating messages are also provided to all CR-M 1 0700 00:00 emergency centers and facility staffs upon TSC M 1 (Cont'd) subsequent activations. Operational and TSC M 2 radiological data will be available to the TSC M 3 TSC via TSC communicators who normally OSC M 1 respond to the CR prestaged in the SRM M-1 simulator. Security will be provided a list EOF M 1 of Evaluators and nonparticipants who will ESC M 1 not have to be accounted for during the ST M 1 exercise. ST H 2 0700 00:00 Simulator is put into operation. Reactor is at 1006 power. The reactor has been operating steady state for the past 15 months with no recent shutdowns. J Night orders have instructed the Operations crew that HPCI failed surveillance testing and is inoperable. The plant is in a 7 day LCO in accordance with Technical Specifications. 16C is in the process of performing a functional test of the Automatic Depressurization System (ADS) trip logic. The off-gas system radiation levels are elevated as a result of suspected fuel pin leakage. Reactor Engineering staff has determined that power changes should not exceed 14 per five minutes in order to minimize the fuel pin leakage. All other power generating and safety system equipment is operable.
Rsv. O Pegs 5.4 3 Scenario Message Clock Information Time. Time Event / Action [
. 0715 00:15 16C reports that the functional test of the 7.2.1 M 1 ADS trip logic was unsatisfactory. A relay
- in the circuit failed to operate in the time , specified by the test document. The relay l will need to be replaced (refer to Miniscenario 7.2.1). Approx. Approx. The Shif t Supervisor should declare an 0730 00:30 UNUSUAL EVENT based upon the following EAL: AP 3125, ' LOSS OF SYSTEMS OR EQUIPMENT - Plant shutdown required in accordance with Technical Specifications." The SS/PID should initiate Procedure OP 3500, UNUSUAL EVENT and refer to Appendix 1, the S.5/ PED checklist.
'k Operators should begin a controlled power reduction in accordance with Tech. Specs.
FOR EXERCISE PURPOSES, EARLY IN STATION SCR C-2 ACTIONS MAY BE CONTROLLED AND PERFORMED BY THE SIMULATOR CONTROLLERS. The SS/ PED should announce the UNUSUAL EVENT over the Plant Paging System. This activity will be performed by players in the Simulator CR, and simultaneously performed by a Controller directed member of the operating shift crew in the actual control Room. i l
Ecv. O Pogs 5.4 4 Message Clock Scenario Time Event / Action Informat i on Time Approx. 00:30 The SS/ PED should notify Vermont, New 0730 Hampshire, and Massachusetts State Police Agencies using the Nuclear Alert System (NAS) (orange telephone) and provide the appropriate message to each agency. The SS/ PED should notify the NRC (red telephone) and maintain communications until relieved by the TSC. The Security Shift Supervisor should implement Procedure OP 3531, " Emergency call In Method," to notify the appropriate emergency response personnel. The Security Shif t Supervisor should notify Yankee Nuclear Services Division (YNSD) Security and activate the YNSD Personnel Croup Paging System. The Security Shift Supervisor should also SEC-C-1 notify New England Hydro Power Station of the UNUSUAL EVENT. THIS CALL WILL BE SIMULATED. The Primary and Secondary Duty and Call Officers (DCOs) should report to the plant after notification of the UNUSUAL EVENT Status. The DCOs should contact the SS/ PED to be advised of the situation. Responsibility for TSC and EOF Coordinator assignments would be discussed, as appropriate.
Rsv. O Pegs 5.4 5 Scenario Message Clock Information Time.. Time -Event / Action { 0730 00:30 The TSC Coordinator shoeld assume the (Cont'd) overall supervision and coordination of the on site emergency responas activities. This will include escalating the emergency classification as conditions warrant. Activation of the Technical Support Center (TSC) is optional at the UNUSUAL EVENT. 00:45 IF AN UNUSUAL EVENT HAS NOT BEEN DECLARED BY SCR-C-3 0745 THE SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS TIME. 160 initiate repairs to the failed relay in 7.2.1-H-2 order to return the ADS to service, f 0815 01:15 Simulator Operator inserts a loss of electrical bus DC-3. This results in a loss of all control board panalarus, various electrical distribution and turbine control indications. Approx. 01:30 When the SS/ PED realize the loss of 0830 panalarms, the SS/ PED should notify the TSC Coordinator of the changing plant conditions. The TSC Coordinator and SS/ PED should review the plant conditions against Procedure AP 3125. " Emergency Plan Classification and Action Level Scheme." w y- v.w. - - - --, ., .- -
-+ , - - ~ a - .
I Rsv. O Pogs 5.4 6 Clock Scenario Message f Time Time Event / Action Information k 0830 01:30 The SS/ PED or TSC Coordinator should declare (Cont'd) an ALERT based upon the following EAL: AP 3125, "! ASS OF SYSTEMS OR EQUIPMENT - Loss of Control Room alarm panels". The SS/ PED directs the operatiorm staff to initiate Procedure OP 3501, " ALERT." An ALERT announcement should be made over the plant page instructing emergency personnel to report to their assigned emergency response facilities, and other personnel, contractors, and visitors report to the Governor Hunt House laformation Center and wait for further instructions. J At this time, the Technical Support Center 1 (TSC). Operations Support Center (OSC), and tha Emergency Operatio;,s Facility / Recovery Center (EOF /RC) should be activated and staffed, The SS/ PED should notify the Vermont, New Hampshire, and Massachusetts State Police Agencies using the NAS of the escalation to the ALERT emergency classification. The NRC should be notified of the escalation to the ALERT. The Security Shif t Supervisor should initiate the emergency call-in method for the ALERT classification.
Rev. O Pega 5.4-7 Clock Scenario Message limt_ Time Event / Action Information 0830 01:30 The Security Shift Supervisor should notify (Cont'd) Yankee Nuclear Services Division (YNSD) Security of the escalation to the ALERT status. Upon ALERT notification, the YNSD Engineering Support Center (ESC) is activated. The Security Shif t Supervisor should notify the New England Hydro Power Station in Vernon of the escalation to the ALERT status. THIS CALL WILL BE SIMULATED. The TSC Coordinator should notify REMVEC of the ALERT status and plant conditions. 0835 01:35 The Security Shift Supervisor should ensure that an accountability of personnel has been initiated in accordance with procedures SP 0906, " Emergency Procedures" and OP 3524,
" Emergency Actions to Ensure Accountability and Security Response."
The TSC Coordinator should respond, activate, and staff the TSC in accordance j vith Appendix III of OP 3501, " ALERT." l l l l l l
1 Rsv. 0 l Pcgs 5.4 8 Clock Scenario Message ! Time Titte Event / Action Information (~ 0835 01:35 TSC staff representing the following (Cont'd) departments should assemble at the TSC following the declaration of an ALERT:
- 1. Instrument and Control Supervisor
- 2. Radiation Protection Supervisor or designated alternate
- 3. Reactor and Computer Supervisor
- 4. Operations Supervisor
- 5. Maintenance Supervisor
- 6. Engineering Support Supervisor
- 7. GE Resident Engineer (as necessary) *
- 8. Plant Services Supervisor J. Other staff personnel to fulfill the functions of the TSC (i.e., Status Board Keepers, Communicators, Switchboard 1 Operators, etc.).
The Emergency Operations Facility (EOF)
- Coordinator should activate at.J staff the EOF /RC in acccrdance with Appendix IV of OP-3501, " ALERT."
Rsv. O Psgs 5.4-9 Clock Scenario Message
# Time Time Event /ActiqD Information
- k. .
0835 01:30 The emergency response staff that reports to (Cont'd) the ECF/RC includes the following:
- 1. Site Recovery Manager and designated corporate staff
- 2. EOF Coordinator
- 3. Purchasing Supervisor
- 4. Public Information Liaison
- 5. Additional trained plant staff members to assume the following tag board assignments:
- EOF Coordinator's Assistant
- Radiological Assistant
- Manpower and Planning Assistant Communications Assistant
- Radiological Coordinator
- Personnel and Equipment Monitoring Team
- 6. Corporate Security Force 4
The Operations Support Center (OSC) Coordinator (assigned by the TSC Coordinator) should activate and staff the OSC in accordance with Appendix VII of OP 3501, " ALERT.*
Rsv. O Pegs 5.4 10 Scenario Message Clock Time Event / Action Information Time 0835 01:35 The Plant staff that reports to the OSC (Cont'd) includes the following:
- 1. Radiation Protection and Chemistry Assistants and Technicians
- 2. Control Instrument Specialists
- 3. Maintenance Staff
- 4. Status Board Caretaker
- 5. Other personnel as required.
The Site Recovery Manager (SRM) and staff should report to the EOF /RC and implement the r~ocedural steps listed in Appendix VIII of OP 3501, " ALERT." 0840 01:40 Radiation Protection Technicians from the OSC may be dispatched to perform dose rate f radiation surveys, air sampling, and contamination surveys of the plant. IF AN ALERT HAS NOT BEEN DECLARED BY THE SCR-C 4 0845 01:45 SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS TIME, Control Room operators vill initiate actions to stabilize the plant. This may include an interruption of the power reduction until the panalarms are returned to service. A repair team should be dispatched to investigate the loss of DC-3 (Refer to Miniscenario 7.2.2). l 1
Rav. O Peg 2 5.4 11 Clock Scenarit Message f Time Time Event / Action Information f' 0915 02:15 The repair team reports that the immediate 7.2.2 M 1 area of the DC 3 transfer device has a strong odor of ozone and a humming sound is coming from the DC-3 transfer device. 0930 02:30 The repair team reports that a cam in the 7.2.2-M-2 ) manual transfer actuator device had apparently jammed when the operator attempted to switch power sources. The transfer device has been tested several times and the fault has not repeated. The unit will be put back in service within 10 - 15 minutes. 0945 02:45 Electrical Bus DC-3 is returned to service, 7.2.2-M-3 control board panalarms have been restored. 4 The controlled power reduction should resume, 1015 03:15 Main Condenser Low Vacuum Alarm followed by a turbine trip. Reactor SCRAM signal initiated due to the turbine trip. When the reactor SCRAM signal occurs, the control rods fail to insert causin5 the reactor to remain critical. An Anticipated Transient Without Sciam (ATWS) condition exits. Reactor power remains above 24. 1020 03:20 Condenser vacuum continues to decrease due to air in leakage problems. Loss of vacuum causes the closu';e of the Main Steam Isolation Valves (MSIVs) on Containment Group 1 isolation. The inboard MSIV on Main Steam Line "B" remains in the open position. I i
R0v O Pagn 5.4-12 Clock Scenario Message Time Time Eyent/ Action 1Dformation 1020 03:20 The Main Condenser is no longer available as (Cont'd) a heat sidk. Reactor power is still above 24. Approx. 03:20 The SS/ PED should immediately inform the TSC 1020 Coordinator and SRM of the ATWS condition and that a Group 1 isolation has occurred. The SRM, TSC Coordinator and SS/ PED chould evaluate plant conditions against Procedure AP 3125, " Emergency Plan Classification and Action Level Scheme" . The SRM with consultation from the TSC Coordinator and SS/ PED should recognize the need to escalate to a Site Area Emergency. ' t. Approx. 03:30 The SRM should declare a SITE AREA EMERCENCY 1030 based upon the following EAT.: AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT - Failure of Reactor Protection System (RPS) to initiate and accomplish a required SCRAM with the Main Condenser unavailable". If present, the SRM should notify the representatives of Vermont, inw Hampshire, and Massachusetts located at the EOF /RC and contact each State's EOCs using the NAS to inform them of the escalation to the SITE AREA EMERGENCY. The SS/ PED will also be directed to make the appropriate plant announcement concerning i the escalation to the SITE AREA EMERGENCY. l t
Rev. 0 j Page 5.4 13 l h Message Clock Scenario Time Time Event / Action Information Approx. 03:30 Upgraded notifications should also be made 1030 to YNSD and the NRC. (Cont'd) Upon MSIV isolo?. ion, operators wl'.. eentinue control rod insertion and implement actions to stabilize the plant. This will include using the Safety Relief Valves (SRVs) with the torus as the heat sink to control reactor pressure and cooldown. Operators will also start RHR in the torus cooling mode and monitor torus temperature and level. 1045 03:45 IF A SITE AREA EMERGENCY HAS NOT BEEN SRM-C 1 DECL\ RED BY THE SRM, HE VILL BE DIRECTED TO DO f.0 AT THIS TIME. The SCR nersonnel will be working to stabilize plant conditions and will be attempting to manually drive control rods into the core. Operators will not be able to insert control 7.2.3-M-1 rods into the core until the Control Rod Drive (CRD) charging water header isolation valve (CRD V56) is closed. When CRD-V56 is closed, the operators will be able to drive control rods into the core using the Reactor Manual Control System (RMCS). (Refer to Miniscenario 7.2.3)
Rev. O Page 5.4 14 Message Clock Scenario Time Event / Action Information Time 1045 03:45 The "C" RHR Pump trips. The "A" pump is (Cont'd) started to continue torus cooling via the RHR heat exchangers. An OSC Team should be assembled and 7.2.4 M 1 dispatched to investigate the cause of the 7.2.4-M 2 pump trip. (Refer to Miniscenario 7.2.4.) 7.2.4-M-3 7.2.4-M-4 1050 03:50 Control Room staff will implement actions necessary to reduce reactor power level. This may include lowering reactor water Icvel. This will be done in accordance with OE 3102, Alternate Level Control. When SLC is initiated from the control 7.2.5-M-1
# board, the explosive " squib" valves fail to fire. An Auxiliary Operator should be dispatched to actuate the valves locally in accordance with OE 3101, App. G (Refer to Miniscenario 7.2.5).
When the attempt to initiate SLC is made, an 7.2.6-M-1 isolation signal is sent to the Reactor 7.2.6 M-2 Water Cleanup (RWCU) system. As the RWCU 7.2.6 M-3 isolation takes place, the primary containment inboard isolation valve, RWCU-V12-15, fails to shut. An OSC Team should be assigned to investigate the valve failure. (Refer to Miniscenario 7.2.6.)
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Rsv. 0-Pegs 5.4 15-
. Message Clock . Scenario- .
Information Time. Timp, . Event / Action (-. At this tice,-,it is postulated that fuel-1050 03i50 (Cont'd) irtegrity is damaged due to the' thermal and hydraulic shockLimposed by the cycling of~ the SRVs to control pressure. This results in a significant increase of fission products in the reactor coolant system. The ESC should be providing technical and ESC-M-2 1 1055- 03:55 engineering support to Varmont Yankee staff. EOF-M-2
-The ESC meteorologist should provide a specific weather forecast for the' Vermont Yankee. site.
The ESC has reviewed the latest NWS forecast ESC M-3 1145 04:45 and-has updated meteorological information
.for.the site.
An: updated weather forecast is available EOF M 3 from the NWS. ST-M 3 1200 05:00 Drywell pressure continues to increase due to increasing drywe11' temperature. This is a result of a-leak coming from a faulted recirc line in the, Reactor Recirculation System. This leakage also causes the containment high range monitors to increase significantly. 1205 .05:05- Containment High Range Monitors are reading approximately 20,000 R/hr. The SRM, TSC Coordinator, and SS/ PED should evaluate plant conditions against Procedure AP 3125, " Emergency Plan Classification and Action Level Scheme . "
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Rev. O Page 5.4-16 Clock Scenario Message Time Time Event / Action Information 1205 05:05 Reactor power reduction and pressure control (Cont'd) will continue. 1210 05:10 The SRM, with consultation from the TSC Coordinator and SS/ PED, should recognize the need to escalate to a GENERAL EMERGENCY. 1215 05:15 The SRM should declare a GENERAL EMERGENCY based upon the following EAL: AP 3125, "fVEL DAMAGE - Loss of 2 of 3 fission product barriers with potent: c' loss of third." The SRM should inform the representatives of Vermont, New Hampshire, and Massachusetts located at the EOF /RC, and contact each
- ( state's EOCs using the NAS to inform them of the escalation to the CENERAL EMERGENCY.
The SS/ PED will also be directed to make the appropriate plant announcement concerning the escalation to the GENERAL EMERGENCY. Upgraded notifications of the GENERAL EMERGENCY status should be made to YNSD and the NRC, The SRM should implement Procedure OP 3511 "Off-Site Protective Action Recommendations," to formulate and recommend protective actions to State authorities based upon plant conditions. 1230 05:30 IF A GENERAL EMERGENCY HAS NOT BEEN DECLARED BY THE SRM, HE WILL BE DIRECTED TO DO SO AT SRM-C-2 THIS TIME.
Rev. O Page 5.4-17 Message Clock scenario Inf ormation Time Event / Action ( T ine .. . 05:55 A casualty will be inserted by Simulator 1255 Operator that causes a large steam line break outside the primary containment in the steam tunnel. The break is between the inboard and outboard MSIV on MSL "B". Steam tunnel temperature is increasing significantly. 1300 06:00 A rapid depressurization of the reactor occurs as a result of the steam line leak. Steam tunnel temperature continues to increase. Area radiation monitors in the Reactor Building are increasing significantly and a release of radioactivity from the Plant Vent Stack (PVS) begins. 4 1315 06:15 PVS high range monitor is indicatin6 a major release of radioactivity to the environment. The appropriate EOF staff should initiate Procedure OP 3513, " Evaluation of Off-Site Radiological Conditions," to determine of f-site dose projections. Off-Site Monitoring Teams should be dispatched to monitor the plume in the downwind direction. The EOF Coordinator and Radiological Assistant should initiate Procedure OP 3511, "Off-Site Protective Action Recommendations," to formulate protective action recommendations based upon off-site radiological conditions.
Rsv. O P de 5.4 18 Clock Scenario Message Time Time ~ Event / Action Information Approx. Approx. OSC should be requested to obtain a plant 1320' 05:20 vent stack sample (refer to Procedure OP 3530, " Post Accident. Sampling"). TSC personnel should also be investigating the problems associated with RWCU V12-15 and , MSIV "B".
.1400 07:00 SCR board indicatas that the inboard MSIV on
-MSL "B" has closed. Leakage past this MSIV ;
into the Reactor Building has stopped. 2 1515 08:15 Control Room indications show that plant a conditions are stabilizing and the PVS monitors are decreasing. The source of the fission product release into the steam , i tunnel-has been isolated. The release of
-s radioactivity to the environment will continue to decrease over time based upon the volume exchange rate of the Reactor Building through Standby Gas Treatment System.
1530 08i30-- Exercise is terminated. i -- l t I i; G E P g w-c--- w- * -3y,%y' q,ge p- y
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 6,0 EXERCISE MESSAGES i-l l l l i l A
VERMONT YANKEE NUCLEAR' POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE
'1991 6,1 COMMAND CARDS 4'
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Rev. O Page 6.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE { 1991-SCENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO.: SCR-C-1 Shift Supervisor CIDCK TIME: Prior to 0700 TO: IDCATION: Simulator Control Room SCENARIO TIME: Prior to 00 00 THIS IS A DRILL _D0 NOT initiate any actions affecting normal plant operations. Communications systems that are available in the Control Room have been duplicated in the Simulator Control Room (SCR) EXCEPT for CAITRONICS and the PLANT EVACUATION ALARM. Please use the GAITPONICS/PIANT EVACUATION ALARM in the SCR to complete the required PA announcements. An Exercise controller will then direct a member of the shif t operations crew at the plant to repeat the announcements from the Main 4 Control Room. THIS IS A DRILL
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Rav, 0 P:ge 6.1-2 VERMONT YANY,EE NUCLEAR POWER STATION EMERCENCY RESPONSE FREPAREDNESS EXERCISE 1991
.~
SCENARIO COMAND CARD FROM: Shift CR Controller COMMAND NO.: SCR-C 2 TO: Shift Supervisor CIDCK TIME: 0730 II) CATION: Simulator Control Room SCENARIO TIME: 00:30 e.***********************+ *=***********************************************
IS IS A DRTLL DO NOT initio . <- affecting normal plant operations. ***********************- . +***************************************
Early in-station actions a ; and information requested at this time vill be provided by_contro,. ( THIS IS A DRILL
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Rsv, O Page 6.1-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 [ SCENARIO COMMAND CARD , FROM: Security Controller COMMAND NO.: SEC-C TO:- Recurity Supervisor C1hCK TIME: 0730 or when needed IDCATION: Security Catehouse SCENARIO TIME: 00:30-THIS IS A DRILL DO NOT initiate any actions affecting normal plant _ operations. FOR EXERCISE PURPOSES, communications with New England Hydro Power Station in Vernon will be simulated. ( 1 THIS IS A DRILL l
Rav. O
.Pcgs 6,1 ' VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991-SCENARIO COMMAND CARD-i COMMAND NO.: SCR-C-3 FROM: Simulator CR Controller
' TO: Shift Supervisor ClhCK TIME: 0745 IhCATION: Simulator Control Room SCENARIO TIME: 00:45 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
DECIARE AN UNUSUAL EVENT BASED UPON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT - l _ Plant shutdown required in accordance with Technical Specifications". y THIS IS A DRILL
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Rev. O Page 6.1-5 VERMONT YANKEE NUCLEAR POWER STATION I EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 (- SCENARIO COMMAND CARD _ COMMAND NO.: SCR-C-4 FROM: Simulator CR Controller CIDCK TIME: 0830 TO: Shift Suoe rvis or /I ED IDCATION: Sitnulator control Room SCENARIO TIME: 01 30 THIS IS A DRILL DO NOT initiate any actic. eff.ct. lag normal plant operations. DECLARE AN ALERT BASED UPON AP 3125, "IDSS OF SYSTEMS OR EQUIPMENT - Loss of Control Room Panalarms". I 1 THIS IS A DRILL
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Rev. O Fage 6.1-6 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991-- SCENARIO COMMAND CARD FROM: SRM Controller COMMAND NO.: SRM-C-1 TO: Site' Recovery Manager CIDCK TIME: 1045 IDCATION: EOF /RC SCENARIO TIME: 03:45 THIS IS A DRILL DO-NOT initiate any actions affecting normal plant operations. DECIARE A SITE AREA EMERGENCY BASED UPON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT - Failure of the Reactor Protection System (RPS) to initiate and accomplish a required SCRAM with the Main Condenser unavailable".
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THIS IS A DRILL l- **********************************************************+******************* I
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Rev. O Page 6.1-7 VERMONT YANKEE. NUCLEAR ~ POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO COMMAND CARD FROM: SRM Controller COMMAND NO.: SRM C-2 TO: Site Recovery Manacer CIDCK TIME: 1230 1DCATION: EOF /RC SCENARIO TIME: 05:30 , l THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. DECIARE A GENERAL EMERGENCY BASED UPON AP 3125, " FUEL DAMAGE . Loss of 2 of 3 fission product barriers with the potential loss of the third". , i
's s.
ll P b THIS IS A DRILL
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3 Er- '*- h- F--L' 4 * - - ,1-- (- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 6,2 MESSAGE CARDS
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Rev. 0-Page 6.2 1 VERMONT YANKEE NUCLEAR POWER STATION
-EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991-f SCENARIO MESSAGE CARD FROM: . Simulator CR Controller - MESSAGE NO,: SCR-M-1 TO: Shift Supervisor CLOCK TIME: Prior to 0700 LOCATION: Simulator Control Room SCENARIO TIME: Prior to 00:00 THIS IS A DRILL DO NOT initiate.any actions affecting normal plant operations.
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.For-initial conditions, see attached pages, 3
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THIS IS A DR.ILL
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Rev. O Page 6.2-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991
\ SCENARIO MESSAGE CARD INITIAL CONDITIONS
- 1. The reactor is now at approximately 1004 power. The reactor has been operating steady state for the past fifteen months with no recent shutdowns.
for the operations crew provides the following
- 2. Night Orders information:
- a. The HPCI system failed surveillance testing due to flow controller failure putting the plant in a 7-day 140. HPCl has been declared inoperable. In accordance with Technical Specifications, alternate testing is in process by I&C.
- b. I&C is performing the functional test of the Automatic Depressurization System trip logic. This test is required as a condition of tech, spec. for HPCI inoperability.
- c. Off-gas system radiation levels have been elevated throughout the operating cycle indicative of minor fuel pin leakage.
- d. Reactor Engineering has instructed that power changes shall be limited to less than 1% per five minutes due to the suspected fuel pin leakage.
- 3. All other power generating and safety system equipment is operable.
Rev. O f Page 6.2-3 (' VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY. RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CAPl)
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed, sph (lower / upper) 4.0/5.0 Wind Direction, degrees (lower / upper) 180/185 Delta Temperature, 'F (lower / upper) 1.0/1,5 Ambient Temperature, 'F 40.0 Precipitation, inches 0.00
- 5. Regional Meteorological Forecast Information:
A low pressure system is located along the Atlantic seaboard. High temperatures in _ the middle to upper 50's; low temperatures in the middle 40's. Winds from the south at 4-5 mph, swinging around to the southeast this af ternoon and diminishing in intensity. Winds will continue to shift, coming around to the north and increasing in intensity to 5-7 mph. THIS IS A DRILL
4 Rev. 0 Page 6.2-4 .('- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CARD Initial Plant and Reactor System Values Reactor Vessel Cools.nt Level 158 Inches Reactor Pressure 1007 psig Reactor Coolant Temperatare 528 *F Reactor Power - APRM (average) 100 % Core Plate D/P 18 psid Total Core Flow 47 x 10' lbm/hr Main Steam Line Flow - Total 6.4 x 10' lbm/hr Main Steam Line Radiation 170 mR/hr Condenser Hotwell Level 55 % Condenser Vacuum 1.8 in. Hg(Abs) Condensate Storage Tank Level 51 % Recire Drive Flow 30 Kgpm/ loop Feedwater Flow 6.3 x 10' lba/hr Reactor Building D/P -1.62 in H O 2 Drywell Pressure 17 psia Drywell Temperature 106 *F Torus Water Level 0.56 ft i Torus Temperature 72 *F Drywell/ Torus 0 Concentration 2 2.58 % High Range Containment Monitors 4 R/hr Containment Gas / Particulate 500/25000 cpm Reactor Building Vent Monitors Gas /Part 190/1530 cpm Reactor Building Vent Exhaust N/S 2.0/2.0 mR/hr Steam Jet Air Ejector (ARM) 250 mR/hr SJAE Diecharge Rate 50,000 pC1/see Stack Cas I/II 150/200 cpm High Range Noble Gas Monitor .1 mR/hr
*****k****************************************************k********a**********
THIS IS A DRILL
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Rev. 0 Page.6.2-5 ,
.- {J -VERModT YANKEE NUCLEAR POWER STATION EMERGENCY-RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD a
FROM: -Control Room Controller- MESSAGE NO.: CR-M-1 CLOCK TIME: Prior to 0700 - TO: Qntrol Room Communicator IDCATION: Control Room SCENARIO TIME: 00:00 !
****ws************************************************************************
THIS IS A DRILL DO NOT initiate any actioas affecting normal plant operations. For init'ial conditions, see attached pages, i
' ~
i :. l THIS IS A DRILL l l l-o i i. I i I:
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Page 6.2 6
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VERMONT YANKEE NUCLEAR POWER STATION = EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD INITIAL CONDITIONS
- 1. The reactor is now'at approximately 1004l power. The reactor has been operating steady state for_ the past fifteen months with no recent- i shutdowns.
2, Night -Orders for the operations crew provides the following-information:
- a. The HPCI system failed surveillance testin6 due to flow controller failure putting the plant in a 7-day LCO. HPCI has been declared-inoperable. In accordance with Technical Specifications, alternate testing is in process by I6C.
7-
- b. I&C is- performing the functional test of 'the Automatic Lepressurization System trip logic. This test is required as a condition of. tech, spec, for HPCI inoperability.
- c. Off-gas system radiation levels have been elevated throughout the Loperating' cycle' indicative of minor fuel pin leakage,
- d. Reactor Engineering has instructed that power changes shall be limited to less than 1% per five minutes due to the suspected fuel pin leakage.
- 3. All other power generating and safety. system equipment is operable.
Rev. 0 , tz Page 6.2-7 E7 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991-SCENARIO MESSAGE CARD
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed, sph'(lower / upper) 4.0/5.0 Wind Direction, degrees (lower / upper) 180/185 Delta Temperature, 'F-(lower / upper) 1.0/1.5 Ambient Temperature, 'F 40.0 Precipitation,. inches 0.00
- 5. Regional Meteorological Forecast Information: ,
A low pressure system is' located along the Atlantic' seaboard. -High temperatures in the middle to upper 50's; . low temperatures = in the middle 40's. Winds from the south at 4 5 mph, swinging around to the < southeast this afternoon and diminishing in intensity. Winds will-
} continue to shift. coming around to the north and increasing in intensity to 5-7 mph.
F b; , THIS IS A DRILL 1. I d~-_.
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Rev. 0 Page 6.2-8 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CAFl) Initial Plant and Reactor System Values Reactor Vessel Coolant Level 158 Inches Reactor Pressure 1007 psig Reactor Coolant Temperature 528 'F Reactor Power - APRM (a'rerage) 100 t Core Plate D/P 18 psid Total Core Flow 47 x 10' lbm/hr Main Steam Line Flow - Total 6.4 x 10' lbm/hr Main Steam Line Radiation 170 mR/hr condenser Hotwell Level 55 t Condenser Vacuum 1.8 in. Hg(Abs) Condensate Storage Tank Level 51 % Recire Drive Flow 30 Kgpm/ loop Feedwater Flow 6. 3 x 10' lbm/hr Reactor Building D/P -1,62 in H 2 O Drywell Pressure 17 psia '
, Drywell Temperature 106 *F Torus Water Level 0.56 ft Torus amperature 72 'F D- ./ Torus 02 Concentration 2.58 %
.<ange Containment Monitors 4 R/hr
,ainment Cas/ Particulate 500/25000 cpm
. actor Building Vent Monitors.Cas/Part 190/1530 cpm Reactor Building Vent Exhaust N/S 2.0/2.0 mR/hr 2 team Jet Air Ejector (ARM) 250 mR/hr SJAE Discharge Rate 50,000 pCi/see Stack Gas I/II 150/200 cpm High Range Noble Gas Monitor .1 mR/hr THIS IS A DRILL s
Rev. 0
/ Page 6.2 9 \ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD FROM: TSC Controller MESSAGE NO.: TSC M-1 CIDCK TIME: Upon TSC Activation TO: TSC Coordinator LOCATION: TSC SCENARIO TIME:
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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For initial conditions, see attached pages, if A THIS IS A DRILL
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Rev. 0
-( Page 6.2-10 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 <
SCENARIO MESSAGE CARD VERMONT YANKEE-DAILY OPERATIONS REPORT NOVEMBER 6, 1991
====----=============--===============r=.r....-=========--=======
PLANT STATUSI' 100% POWER GEN GROSS 510'MWE OFFGAS 50,000 uCI/sec PLANT OPERATION
SUMMARY
_& SIGNIFICANT EVENTS
*THE PLANT HAS BEEN - OPERATING FOR 15 MONTHS WITH NO RECENT SHUTDOWNS. CONTINUED FULL POWER OPS. HPCI SYSTEM FAILED SURVEILLANCE TESTING DUE TO FLOW CONTROLLER FAILURE. PLANT IS IN A 7-DAY LCO CONDITION.
OFF-GAS RAD LEVELS ~ ELEVATED. SOME MINOR FUEL PIN LEAKAGE.
==============================:.======r===========================
p- SIGNIFICANT NEW MRs
;~ # DESCRIPTION DEPT PRIORITY NONE
=================================================================
.TECE. SPEC /LCO EQUIPMENT OUT OF SERVICE SYSTEM / COMPONENT TECH SPEC DATE/ TIME ALLOWABLE TIME HPCI' T3.5.E.3 11/5/91 2000 7-DAY LCO
------.. .. --- -.- --.-...-......- ,,,,,,,,,,,,,,,,,,,,,,u,,,,,,,,,,,,
STATUS / COMMENTS ON MAJOR WORK IN PROGRESS
- I&C PERFORMING. FUNCTIONAL TEST OF-THE ADS TRIP LOGIC FOR CONDITION OF. TECH. SPEC. OF HPCI INOP.
- RE INSTRUCTIONS TO LIMIT POWER CHANGES TO LESS THAN 1% PER FIVE MINUTES DUE TO SUSPECTED FUEL PIN LEAKAGE.
====== --
PRO'S/ NOTIFICATIONS: NONE
=======--
LONG TERM PROBLEMS SOLVED l- NONE
======_ _ _ -
=
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THIS IS A DRILL
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Rev 0 Fase 6.2 VERMONT YANKEE DAILY - STATUS REPORT THIS IS'A DRILL ( DATE: mov s 1991
- PIANT OPERATING STATUS VALUE DATE TIME
- 1. Core Thermal Power ( *t ) l (1) 1593 l 1001 s-s 0700
- 2. Gross W e ( We) 536 + 0700
- 3. Not We ( We) 511 >
0700
- 4. Gross Wh for previous day ( WtO 12523 -
S. Core Flow (M1b/br) l (1) 47 / 97.9 ~ e vt 0700 REACTOR COO 1 ANT SYSTEM
- 6. Conductivity (unho/ca) 0.085 11/5/91 0900
- 7. Unidentified Leakage 8 midnight previous day (gium) 0.00
- 8 Total Leakage 8 midnight previous day ( spn) 2.45 '-x >
- 9. Gross Activity (cpm /ml) 150448 11/5/91 0900
- 10. Iodine-131 Dose Equivalent (uC1/ml) 4.50E-03 11/5/91 0000
. STACK RELEASES
- 11. Particulate (ci/ period) 4.08E-03 11/4/91 1430
- 12. Average (uC1/sec) e100 11/6/91 0115
- 13. Feak (uC1/sec) NONI 11/6/91 0115 14 Discharge Average Gamme Energy (Mov) 1.12 11/6/91 0115 f-
- 15. Dose Rate to Critical Organs (aram/ year) 4.42 11/4/91 1430 g 6. Todine-131 (uC1/sec) 3.30E-05 11/4/01- 1430 OFF-CAS ANALYSIS 17; SJAZ Dis. Release kate Messured/ Estimated (uC1/sec) 50000 11/6/91 0115
- 18. SJAI Discharge Slope of Mixture -0.253 11/6/91 0115 i 19. Condenser Air Leakage (cfa) 19.6 11/6/91 0115 LIQUID RELE c5 & RIVER TEMPERATURE
- 20. Liquid Release (Gal) MA
- 21. Liquid Release (Grose Beta, Ganna) (uct/al) RA 22 Liquid Release (Tritium) (uC1/al) MA _
, 23. Liquid Release (Dissolved Noble Gas) (uC1/ml) BA
- 24. -River Mon. 93 Bishest Temp. for previous day -(oF) SS 2115 BURNUP
- 25. Core Avg. Burnup for previous day (WD/ST) 16945.75
- 26. Core Cycle Burntrp for previous - day (WD /ST ) 6325.45 REVIEWER:
THIS IS A DRILL 1
Rev. O fA Page 6.2 12 VERMONT YANKEE NUC11AR POVER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD FROM: TSC Controller MESSACE NO.: TSC M-2 TO: ISC Coor31nator , CIDCK TIME: Uoon essientrent of Data Recorder 14 CATION: TSC SCENARIO TIME: .. THIS IS A drill DO NOT initiate any actions affecting normal plant operations. To obtain plant computer parameters that are normally available to TSC staff, use the Controller / Observer telephone in the Plant Computer doom to request the information from '.he Sinulator Computer Room. THIS IS A DRIII
.. ..-_ _ .. .- . . _ _ _ _ _ _ _ _ _ . . . . _ . _ _ - . - _ . __._-.._._m_.m.____ _ _ _ _ _ . . ..-
P 4 Rev 0
~
Page 6.2 13
-g. - .( VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PILIPAREDNESS EXERCISE 1991 r
I _ SCENARIO MESSACE CARD i I MESSAGE NO.: TSC M 3 TROM: TSC Controller TO: E poordinator C1hCK TIME: Uoon assirunent of ; Communicators ; IhCATION: TSC SCENARIO TIME: . :
- **************************************************************************+***-
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
****************************************************************************** t After assigning your TSC Communicators to the Control Room, the' prestaged TSC Communicators at the Simulator Control Room will be made available.
t 7 r l THIS IS A DRILL
-.w-r--ym--r---e.--sw4--a,-v.m--e,w ,r--,mem--,m-m
Rev. 0 Page 6.2 14 (- VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE
)
1991 l SCENARIO MESSACE CARD l FROM: OSC Controller MESSAGE NO.: OSC M 1 OSC Coordinator C14CK TIME: Upon OSC Activation TO: OSC SCENARIO TIKE: l thCATION: l THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. For initial conditions, see attached pages. I 2
?
i ( l l l l I (- . g THIS IS A DRILL
Rev. 0 Page 6.2 15 (. VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PK2PAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD VERMONT YANKEE DAILY OPERATIONS REPORT NOVEMBER 6, 1991 * , PLANT STATUst 100%. POWER GEN GROSS 510 MWE OFFGAS 50,000 uCI/sec PLANT OPERATION
SUMMARY
& SIGNIFICANT EVENTS
*THE PIANT HAS BEEN OPERATING FOR 15 MONTHS WITH NO RECENT SHUTDOWNS. CONTINUED FULL POWER OPS. HPCI SYSTEM FAILED SURVEILLANCE TESTING DUE TO FIDW CONTROLLER FAILURE. PLANT IS IN A 7-DAY LCO CONDITION.
OFF-GAS RAD LEVELS ELEVATED. SOME MINOR FUEL PIN LEAKAGE. , SIGNIFICANT NEW MRs
# DESCRIPTION DEPT PRIORITY NONE
----------------u------u------------------------------.......-----
TECH SPEC /LCO EQUIPMENT OUT OF SERVICE SYSTEM / COMPONENT TECH SPEC DATE/ TIME ALI4WABLE TIME HPCI T3.5.E.3 11/5/91 2000 7-DAY LCO STATUS / COMMENTS ON MAJOR WORK IN PROGRESS
- I&C PERFORMING FUNCTIONAL TEST OF THE ADS TRIP LOGIC FOR CONDITION OF TECH. SPEC. OF HPCI INOP.
- RE INSTRUCTIONS TO LIMIT POWER CHANGES TO LESS THAN 1% PER FIVE MINUTES DUE TO SUSPECTED FUEL PIN LEAKAGE. =
PRO'8/ NOTIFICATIONS NONE LONG TERM PROBLEMS SOLVED NONE
- - - - - - - = = - -
- - - - - = = = = = = = - - _ _ _ - - -
THIS IS A DRILL
***************************************************t************************** . . . _ , . . . . . - . ~ . . _ . . _ . _ . , , ....__-- - ..._. . -
m _ . . _ _ _ _ _ _ - - _ _ . . . . ..___-_.-_.- _ ___ _ .-_._..m._mm_____... 1 Rey,0 Pass 6.2=16 VERMONT YANKEE DAILY STATUS REPORT
/L THIS IS A DRILL DATE: mov s 1e91 Pl. ANT OPERATING STATUS VALUE DATE TIME
- 1. Core Thermal Power ( *t ) $ (3) 1S93 l 2001 e 0700
- 2. Gross We ( We) $36 0700
- 3. Det W e ( We ) 511 ^
0700
- 4. Gross PWh for previous day ( Wh ) 12S23 S. Core Flow (Hib/ht) l (2) 47 / 37.9 0700 l
REACTOR COOIANT SYSTEM
- 6. Conductivity (unho/ce) 0.08S 11/5/91 0900
- 7. 17nider!tified Lemkage.9 midnight previous day (gpe) 0.00 - -
- 8. Total Leak age 8 stdnight previous day (sps) 2.45 *
- 9. Grose Aettvity (e ps/el) 1$0448 11/S/91 0900
- 10. Iodine-131 Dose Equivalent (uct/al) a.50f-03 11/S/91 0900 r
STACK RELEASES
- 11. Particulate (et/ period) s.08E-03 11/4/91 1630
- 12. Average (uci/sec) *100 11/6/91 0115
- 13. Fe mk (uC1/sec) NONE 11/6/91 011S
- 14. Discharge Average Gaarna Energy (Mov) 1.12 11/6/91 0115 IS. Dose Rate to Critical Organs (area / year) 4.42 11/4/01 1430
- 16. lodine *131 (uC1/see) 3.30E*05 11/4/91 1630 t
OFF.CAS ANALYSIS t7. SJAE Dio. Release Rate Measured / Estimated (uC1/see) $0000 11/b/91 011S
- 18. EJAE Discharge Slope of Histure *0.253 11/6/91 011S
- 19. Condenser Air Leakage (cfm) 19 6 11/t/91 0115 LIQUID RELEASES 6 RIVER TEMPERATURE
- 20. Liquid Release (Gel) RA
- 21. Liquid Release (Gross t Bete. Gaasme) (uC1/el) NA
- 22. Liquid Release (Tritt m) (uct/al) MA
- 23. Liquid Release (Dissolved Noble Gea) (uC1/ml) RA
- 24. River Hon. d3 Blahest Temp. for previous day (OT) SS s -- 2115 l
l BURNUP
- 25. Cese Avg. Burnup for previous day (WD /57 ) 16 94 5. 7.e
- 26. Core Cycle Burnup for previous day (WD/ST) 6325.4$
REVIEWER: L THIS IS A DRILL
Rev. O f Page 6.2 17 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CAPE l FROM: SRM Controller MESSAGE NO.: SRM-M-1 , TO: Site Recoverv Manarer C1hCK TIME: Upon Activation thCATION: RC SCENARIO TIME: , 2 THIS IS A drill DO NOT initiate any actions affecting nortnal plant operations.
****************************************************************************** ,j For initial conditions, see attached pages.
8 THIS IS A drill
. . . _ _ _ . , . _ _ _ _ _ . , _ _ . . _ _ , . _ . . ~ . _ . . . . _ - _ . . _ . _ . , . . . . . _ _ _ _ _ _ , _ . _ _ . , , _ , . . , . . _ _ . _ , _ _ , _ . _ , . _ . _ _ , _ . . . . . . .._
l l Rev. 0 . Page 6.2 18 i ' \ VERMONT YANKEE NUCLEAR POWER STATION
- EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CARD VERMONT YANKEE DAILY OPERATIONS REPORT NOVEMBER 6, 1991
+
PLANT STATUS: 100% POWER GEN GROSS 510 MWE OFFGAS 50,000 uCI/sec PLANT OPERATION
SUMMARY
& SIGNIFICANT EVE!!TS
*THE PLANT - HAS BEEN OPERATING FOR 15 MONTHS WITH NO RECENT SHUTDOWNS. CONTINUED TULL POWER OPS. HPCI SYSTEM FAILED SURVEILLANCE TESTING DUE TO FLOW CONTROLLER FAILURE. PLANT IS IN A 7-DAY LCO CONDITION.
OFF-GAS RAD LEVELS ELEVATED. SOME MINOR FUEL PIN LEAKAGE. f SIGNIFICANT NEW MRs
# DESCRIPTION DEPT PRIORITY NONE
..............................................=..................
TECM SPEC /LCO EQUIPMENT OUT OF SERVICE SYSTEM / COMPONENT TECH SPEC DATE/ TIME ALLOWABLE TIME HPCI T3.5.E.3 11/5/91 2000 7-DAY LCO STATUS / COMMENTS ON MAJOR WORK IN PROGRESS:
- I&C PERFORMING FUNCTIONAL TEST OF THE ADS TRIP LOGIC FOR-CONDITION OF TECH. SPEC. OF HPCI INOP.
- RE INSTRUCTIONS'TO LIMIT POWER CHANGES TO LESS THAN 1% PER FIVE MINUTES DUE TO SUSPECTED FUEL PIN LEAKAGE.
PRO'G/ NOTIFICATIONS NONE' -- LONG TERM PROBLEMS SOLVED: NONE - - - THIS IS A DRILL
**********k*******************************************tt KAA@k****************
. . . . . - . ~ . . . - - . . - . . - - - .,. .- , . - - - - - - . . , - - - - . . - - . - . , , .
_ _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ - ._ ___m . Rav.0 enes s. M s VERMONT YANKEE DAILY STATUS REPORT { THIS IS A DRlLL DATE: nov s 2001 PIANT OPERATING STATUS - VALUE DATE TIME
- 1. Core Thesimal Power ( *t ) l (I) 1S93 l 1001 e --
C T'Jo
- 2. Gross W e ( We) S36 ~ - 0700
- 3. Det We ( We) $11 0700 l
- 4. Gross PWh for previous day ( Wh ) 12S23 l S. Core Flow (M1b/hr) j (1) 47 / 97.9 , 0700 REACTOR CODIANT SYSTEM 6, Conduc ti .-* ty (unho/ce) 0.005 11/5/91 0000
- 7. Unidentified Leakepe 9 midnight previous day ( gym) 0.00
- 8. Total Leakage 8 midn16ht previous day (gges) 2.45 ----
- 9. Gross Activity (cpe/al) 150449 11/5/91 0900
- 10. lodine 131 Dose Equivalent (uC1/ml) 4.50E-03 11/S/91 0900 STACK RELEASES l11. Ferticulate (et/ period) 4.08E-03 11/4/91 1630 12, Average (uC1/see) e100 11/6/91 0115
- 13. Peak (uC1/see) ROME 11/6/91 0113
- 14. Discharge Average Ga.ma Energy (Mov) 1.12 11/6/91 0115
- 15. Dose hete to Critical Organs (aren/ year) 4.42 11/4/91 la30
.f 16. Iodine-131 (uC1/see) 3.30E OS 11/4/91 1630
'OTP GAS ANALYSIS
- 17. EJAE Dis. helsese Este Measured / Estimated (uC1/ tees 50000 11/6/91 0113
- 18. SJAE Discharge Slope of Histure *0.253 11/6/91 0115
- 19. Condenser Air Lestege (efs) 19.6 11f6/91 0115 i
LIQUID RELEASES 6 RIVER TEMPEPATURE
- 20. Liquid Release (Gel) MA
- 21. Liquid Release (Gross i Bete. Gamme) (uC1/el) NA
- 22. Liquid Release (Trittum) (uC1/al) NA f
- 23. Liquid Release (Dissolved Noble Ges) (uct/al) MA
- 24. River Mon. #3 816 hest Temp, for Frevious day for) SS 2115 EUPNUP
- 25. Core Avg. Barnup for previous day (WD/ST) 16945.75
- 26. Core Cycle Burnup for previous day (WD/ST) 6325.45 ~'
REVIEWER: THIS IS A DRILL
.-.- -,.w..w,w - . , , - . . . , 4.,-,< - . . , . r..,,._, . , , . , , . , ,_ ,, m,.. . .,_...,..e,.,, ...y,. , ,., ,,,.3.., , p.,, , ,,p.
Rev. 0 Page 6.2 20 ( VEPJ40NT YANKEE NUCLEAR POWER STATION EHERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CAPl) FROM: EOF Controller MESSAGE NO.: EOF-M 1 EOF Coordinator CLOCK TIME: Upon Activation TO: IDCATION: EOF SCENARIO TIME: THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. For initial conditions, see attached pages. f
*****w************************************************************************
THIS IS A DRILL
_ _ _ . . _ __ _ _ . _ _. ___ . . _ ___ ~ _ .__ _ _ _ ___ I i l Rey, O l Page 6.2 21 l , V mMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPARE!> NESS EKERCISE l 1991
]
SCENARIO MESSAGE CARD ; VERMONT YANKEE DAILY OPERATIONS REPORT NOVEMBER 6, 1991 PLANT STATUS 100% POWER GEN GROSS 510 MWE OFFGAS 50,000 uCI/sec 4 PLANT OPERATION
SUMMARY
& SIGNIFICANT EVENTS:
*THE PIANT HAS BEEN OPERATING FOR 15 MONTHS WITH NO RECENT '
SHUTDOWNS. CONTINUED FULL POWER OPS. HPCI SYSTEM FAILED SURVEILIANCE TESTING DUE TO FLOW CONTROLLER FAILURE. PIANT IS IN A 7-DAY LCO CONDITION. OFF-GAS RAD LEVELS ELEVATED. SOME MINOR FUEL PIN LEAKAGL. SIGNIFICANT NEW MRs
# DESCRIPTION DEPT PRIORITY
~ NONE
------ .........==-.....--------==================...-- .==....--
TBCE SPEC /LCO EQUIPMENT OUT OF SERVICE SYSTEM / COMPONENT. TECH SPEC DATE/ TIME ALLOWABLE TIME HPCI - T3.5.E.3 11/5/91 2000 7-DAY LCO
- STATUS / COMMENTS ON MAJOR WORK IN PROGRESS:
- IGC PERFORMING FUNCTIONAL. TEST OF THE ADS TRIP IDGIC FOR CONDITION OF TECH. SPEC. OF HPCI INOP.
- RE INSTRUCTIONS TO LIMIT POWER CHANGES TO LESS THAN 1% PER FIVE MINUTES DUE TO SUSPECTED FUEL PIN LEAKAGE.
! PRO'S/ NOTIFICATIONS: . l NONE : LONG TERM PROBLEMS SOLVED: NONE
****************h*************************************************************
THIS IS A DRILL
--w-s 3.- 1-y-9..,y-,e gm_,wyw- e,y mgp , _p.r y. e s e % e.f . + . . w w ,,. w,,.
Rsv.0 Fass 6.3-12 VERHONT YANKEE DAILY STATUS REPORT Ti!IS IS A DRILL ( DATE: un a le01 P1 ANT OPERATING STATUS VALUE DATE TIME
- 1. Core Thermal Power ( Wt ) l (t) 1S93 l 1001 0700
- 2. Grose W e ( We ) 536 0700
- 3. Det We ( We ) S11 0700
- 4. Gross Wh for previous day ( Wh) 12S23 S. Core Flow (M1b/br) l (t) 47 / 97.9 0700 REACTOR COO 1 ANT SYSTEM
- 6. Conductivity (umholes) 0.08S 11/S/91 0900
- 7. Unidentified Leakage 8 midnight previous day ( gte ) 0.00
- 8. Total Leakase 8 aidnight previous day ( s ta) 2.45
- 9. Gross Activity (cinfal) 150448 11/$/91 0900
- 10. lodine-131 Dose Equivalent tuC1/al) 4.50E-03 11/S/91 0900 STACK RELEASES
- 11. Particulate (et/ period) 4.08E-03 dio/91 1430
- 12. Aversse (uC1/sec) a100 11/6/91 011S
- 13. Pe ak (uC1/sec) NON7 11/6/91 0113
- 14. Distharge Average Ganste Energy (Mov) 1.12 11/6/91 011S IS. Dose Kate t.o Critical Orsans (area / year) a.42 11/a/91 1430 f 16. lodine-131 (uC1/sec) 3.3tt-05 11/a/91 1430 Qff-CAS ANALYfl3
- 17. $JAE Dis. Release Rate Measured / Estimated (uC1/sec) S0000 11/6/91 0115
- 18. $JAE Discharge Elope of Mixture -0.253 11/6/91 0115
- 19. Condenser Air Leakage (cle) 19.6 11/6/91 0115 LIQUID RELEASES 6 RIVER TEMPERATURE
- 20. Liquid kolosse (Gal) MA
- 21. Liquid Release (Gross Beta. Game ) (uC1/el) RA
- 22. Liquid Eelease (Tritium) (uC1/al) RA
- 23. Liquid kelease (Dissolved Noble Gas) (uC1/al) RA
- 24. River Hon. f3 Bishest Temp. for previous day (or) SS 2115 BURNUP
- 25. Core Avg. Burnup for previous day (MC/ST) 16945.7S
- 26. Core Cycle Burnup fer previous day (HCiET) 6325.45 REVI E'w'ER :
TIJIS IS A DRILL
_ _ . _ . . . _ . _ . _ - . . . _ _._ _ _ =_ - _ __ _ _.. _ __ _ __ _ _ _._. _ . _ _ _ .-.. _ -- _ . _
- s. c Rev. 0 ,
Page 6.2 23 , ( ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 , i I SCENARIO MESSAGE CARD 1 v FROM: ESC Controller MESSAGE NO. : ESC-M 1 CLOCK TIME: Upon Activation TO: ESC Director IDCATION: ESC SCENARIO TIME: THIS IS A DRILL DO NOT initiate atty actions affecting normal plant operations. Tcr initial conditions, see attached pages. , k i. i l L l THIS IS A DRILL
*****************************************************+************************
l
-. ..i.,_.__.. . , ,, . .,~,.,-,m,,-,,_,,.--m , . . . . . , -,,.....e.....-,,.m ,yr-_..ym ,
Rev. 0 Page 6.2 24 (~'- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CARD VERMONT YANKEE DAILY OPERATIONS REPORT NOVEMBER 6, 1991
---=====================================..... . -=========---===
PLANT STATUS: 100% POWER CEN GROSS 510 MWE ' OFFGAS 50,000 uCI/sec PLANT OPERATION
SUMMARY
& SIGNIFICANT EVENTS:
*THE PLANT HAS BEEN OPERATING FOR 15 MONTHS WITH NO RECENT SHUTDOWNS. CONTINUED FULL POWER OPS. HPCI SYSTEM FAILED SURVEILLANCE TESTING DUE TO FIDW CONTROLLER FAILURE. PLANT IS IN A 7-DAY LCO CONDITION.
OFF-GAS RAD LEVELS ELEVATED. SOME MINOR FUEL PIN LEAKAGE.
======================--=========================================
'g SIGNIFICANT NEW MRs f DESCRIPTION DEPT PRIORITY NONE-
==================================--===============--============
TECK SPEC /LCO EQUIPMENT OUT OF SERVICEI SYSTEM / COMPONENT TECH SPEC DATE/ TIME ALLOWABLE TIME HPCI T3.5.E.3 11/5/91 2000 7-DAY LCO
.= .
STATUS / COMMENTS ON MAJOR WORK IN PROGRESS I
- I&C PERFORMING FUNCTIONAL TEST OF THE ADS TRIP IDGIC FOR CONDITION OF TECH. SPEC. OF HPCI INOP.
- RE INSTRUCTIONS TO LIMIT POWER CHANGES TO LESS THAN 1% PER FIVE MINUTES DUE TO SUSPECTED FUEL PIN LEAKAGE.
j l PRO'S/WOTIFICATIONS: l NONE --______ ____... -- I- ====.. =_ - . - - LONG TERM PROELEMS SOLVED: NONE _ _ _
=====-- -
-.= _ - - --
***************kt*************************************************************
i l THIS IS A DRILL l *******************************++********************************************* l
Rev.c Pass s.2-25 VERMONT YANKEE Da.ILY STATUS REPORT k THIS IS A DRILL DATE: par e tool PIANT OPERATING STATUS TIME VALUE DATE 1593 4 1001 0700
- 1. Core Thermal Power ( *t ) ) (1)
( We) 536 0700
- 2. Gross We 0700
- 3. Met. We
( We) S11 Gross Wh for previous day ( Wh ) 12S23
- 4. 0700 (M1b/hr) l (!) 47 / 97.9 S. Core Flow REACTOR COOLANT SYSTR1 tumho/ce) 0.085 11/5/91 0900
- 6. Conductivity linidentified Leakage 0 stdnight previous day (glan) 0.00 7.
Total Leakage 8 eidnight previous day (g pe) 2.45
- 6. 11/$191 0900 (cpm /al) 150648
- 9. Gross Activity 4.50E-03 11tS/t1 0900 l10. Iodine 131 Dose Equivalent (uC1/ml)
STACK RELEASES (ct/ period) 4.081-03 11/4/01 1630
- 11. Particulate 011$
(uCitase) <100 11/6191
- 12. Averste 11/6/91 0115 (uC1/sec) N3NE
- 13. F eak 0115 (Mov) 1.12 11/6/91 14 Discherpe Average Gannt,a Energy (str ee / y e ar ' 4.42 11/4/91 1430
- 15. Dose Rate t.o Critic al Org ans f'
3.30E-05 11/4/91 1430 ( uC1/ s e c ) E. Iodine-131 OFF-CAS ANALYSIS S0000 11t6/91 0115 l 17. SJAE Dis. Release Rate Hessured/ Estimated tuC1/see)
-0.253 11/6/91 0115
- 18. SJAE Discharge $1cre of Mistura (cfa) 19.6 11/6/91 0115
- 19. Condenser Air Leskape LIQUID RELf.ASES & RIVER TEMPERATURE
- 20. Liquid Release (Gal) MA
- 21. Liquid Release (Gross i bete. Game) (uCi/al) RA
- 22. Liquid Re.leese (Tritium) (uC1/ml) MA tuC1/ml) RA
- 23. Liquid Rele6se (Dissolved Noble Ges) 2115 River Hon. d3 Bishest Temp. for previous dev (oF) SS 24 BURNUP Core Avg. Burnup for previous day (WD /57) 16945.75 25.
(WD /ST ) 6325.45
- 26. Core Cycle Eartup for previous day REVIEVER:
THIS IS A DRILL
. _ _ _ . . _ . . ~ . -- _ _ . . _. _ _ . . . - . _ . - _ _ _ . - .. _._ __ _ ____.__._______ .
i Rev. O e Page 6.2-26
'( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD FROM: Vermont State Controller MESSAGE NO.: ST M 1 CLOCK TIME: Upon Activation TO: State Nuclear Enrineer IDCATION: EOC SCENARIO TIME:
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. for initial conditions, see attached page. 3 L s THIS IS A DRILL g
l Rev. O j Page 6,2 27
\ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 l
SCENARIO MESSACE CARD DAILY PLANT STATUS DATE 11/6/91 STATE CONTACT State Nuclear Eneineer TIME OF STATUS 0730 TIME REPORTED REPORTED BY CORE THERMAL POWER MW(t) 119.2 GROSS MWe ill NET MWe _I.Bl t PLANT STATUS 1004 NORMAL OPERATION NOTTFTCATIONS NONE PLANT ACTIVITIES 11/5/11 2000 DECIARED HPCI INOP DUE TO FLOV CONTROLLER i- FAILURE. PIANT IS IN A 7-DAY LCO CONDITION. ALTERNATE TESTING OF REOUIRED PLANT SUBSYSTEMS BEGAN. , , 11/6/91 060016C PERFORMING FUNCTIONAL TEST OF ADS TRI? IDCIC. CONTINUED FULL POVEB OPERATION _, l i L(: S HPCI SYSTEM TECH SPEC T3.5.E.3 (7-DAY LCO CONDITION) OTHER I I l THIS IS A DRILL
a Rev. O Page 6.2 28 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CARD MESSACE NO.: ST-M 7 FROM: State Controller C.ACK TIKE: Upon Activation TO: State Radiolocient Health Rev. IDCATION: State EOC SCENARIO TIME:
*********************************4********,6*v**************************w******
THIC IS A DRILL DO NOT initiate any actions affecting normal plant operations. 06:00 12:00 - General Area Forecast Partly to mostly cloudy. Winds from the south at 3 5 MPH, swinging around to the southeast early this af ternoon and becoming 1-3 MPH. Winds will become northerly late this af ternoon and increase to 5 7 MPH. High temperature in the upper 50's. THIS IS A DRILL
t Rev. O Page 6.2 29 f' VERMONT YANKEE NUCLEAR POWER STATION (. EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD MESSAGE NO.: ESC.M 2 PROM: ESC Controller C1hCK TIME: 1055 TO: ESC Meteoro1orist LOCATION: ESC SCENARIO TIME: 03t55 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
*******************efe*********************************************************
Utilize the attached meteorological information to generate the weather f'orecast for the Vermont Yankee site. i
\
1 THIS IS A DRILL
, ---.~.m.m. , , , - , , . . . . . . . . , , - . . . . _ . . . . . _ , . . , - . , - - - - , _ . , _ . - - _ , . . - . . _ . . , , - - - _ - - . . . . . _ . - -
I i Rev. 0 Page 6.2 30 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESEACE CARD t Date of Forecast: 11 06 91 Time of Forecast: 09:00 Current Site Meteorology (as of 09:00 ).
- Senaor Mind & Stab. Freein.
11EW. Mind Soeed Direction Temperature Class Lower 2.8 168 DEG MPH - ROM { Upper -3.9 173 DEG 0.5 DEG F E O IN/15 MPH FROM MIN-t Forecast Site Meteorology: g: Ijag Sensor. F.ind Mind Delta 11&L ELt.C1 Soecd Direction Temocrat.urg- Class 09:00 Lower 2.0 155 DEG ' MPH FROM ~ 11:00 0.0 E -0 IN/15 Upper 3.0 160 DEG MPH FROM MIN-11:00 Lower '2.0 125 DEG
- MPH FROM' .
13:00 120 DEG- 1.0 D 0 IN/15 Upper 3.5 MPH FROM MIN-13:00 Lower 2.0 115 DEG
- . MPH FROM 15:00 2.0 D 0 IN/15 Upper. 2.5 115 DEG MPH- -FROM MIN __ . _ -
THIS IS A DRILL
*rv+-' t e- ~ T rr- W-m vvc e-- 'e w- iev e -wis -v er e- vr--ev'-v ww-mi'+--ve*--rw--ew,---=w-'v-v*-*-* *-+-w n-++-r+-e---- -hv---*=w*---*--U---E
_ -. _ _ . - _ _ _ . _._ _ . _ _ _ _ _ . _ . _ . _ -_ _ _ . _ - . _ . _.._.__. _ _ _ _.-._ _ ._ ._.m. 6 Rev. 0 ( VERMONT YANKEE NUC1. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO. MESSAGE CARD t National Weather Service Forecast for site region: ! Partly to mostly cloudy. Winds from the south at 3 5 MPH, swinging around to the southeast early this af ternoon and becoming 1 3 MPH. Winds will become northerly late this af ternoon and increase to 5 7 MPH. High temperature in the upper 50's. Special Weather Statements: e 4 2 THIS IS A DRII.L I c e- -
-r 5r --% r, -r e e r .. , ee-- , cer 5.<-.,- -v---.c -.c.,s e e, m., ..-m---c.- , w..-~ .w.m,,4-.+--w.w . wr yy.y .w r, e -- re-e.q,,em < m e, w.v,. ,w,.,am-t--r,*
- . ~ . . - . - _.~ . . _ . - . ~ . - - - . _ - - _ . - - . ~ . - . _ _ - - - ._ _
Rev. 0 Page 6.2 32 (' VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE , 1991 : SCENARIO MESSAGE CARD FROM: EOF /RA Controller MESSAGE NO.: EOF-M 2 TO: Radiolonical Assistant CLOCK TIME: 1055 or as reauested IDCATION: EOF / Dose Assessment Area SCENARIO TIME: THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations, ,
****************************w*************************************************.
06:00-12:00 - General Area Forecast
- Partly to mostly cloudy. Winds from the south at 3 5 MPH, swinging around to the southeast early this af ternoon and becoming 1 3 MPH. Winds will become northerly late this af ternoon and increase to 5-7 MPH. High temperature in the upper 50's. 4- ;
A V THIS IS A DRILL
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Rev. 0 Page 6.2 33 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD MESSAGE tio. : ESC M 3 FROM: ESC Controller ESC Meteoro1orist CIDCF TAKE: 1145 TO: 9 IDCATION: ESC SCENARIO TIME: 04:45 THIS IS A DRILL ELEQI initiate any actions affecting normal plant operations. Utilize the atta:hed meteorological information to generate the weather forecast
-for the Vermont Yankee site.
( THIS IS A DRILL
Rev. O Page 6.2-34 j. VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD Date of Forecast: 11 06 91 Time of Forecast: 11:45 Current Site Meteorology (as of 11 45 ): Wind Delta Stab. Ergh Ilme Sensor Wind Speed Direction Temocrature Class .m . Iower 2.2 119 DEC MPH FROM Upper 3.1 112 DEG 2.4 DEG F C 0 IN/15
-FROM MIN MPH Forecast Site Meteorology:
Hind Delta Stab. Precio. (. IAEA Sensor Eind Gigag-Soeed Direction Temocrature g 13:00 Lower 2,0 115 DEG
- MPH FROM
- 15:00 2.5 115 DEG -2.2 C 0 IN/15 Upper MPH FROM MIN 15:00 Lower 2.5 .100 DEG
- MPH FROM 17:00 90 DEG -2.0 D- 0 IN/15 Upper. 3.5
.FROM MIN MPH
.17:00 Lower 4.5 65 DEC
- MPH FROM l
19:00 -1.0 D 0 IN/15 Upper- 6.0 60 DEG FROM MIN MPH l l
*****************************************+************************************
THIS IS A DRILL
_ . . . _ .. _ _ ._ .._._. ..___.__.___._._._.___._____m._.__._.. __. _.._ ._ Rev. O Page 6.2 35 ( VERMONT YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1991 SCENARIO MESSAGE CARD National Weather Service Forecast for site region: Partly to mostly cloudy. Winds from the southeast shif ting to northerly and increasing to 5-7 MPH. High temperature in the upper 50's. Clearing later , tonight. Temperature in the low 40's. i i Special Weather Statements: r 1
~ 4 .
.h a
l l THIS IS A DRILL
****************************************************4*************************
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Rev. O Page 6.2-36 f '\ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CARD FROM: EOF /RA controller MESSAGE NO.: E0P M-3 TO: Radiological Assistant CIDCK TIME: 1145 or as reauested IDCATION: EOF / Dose' Assessment Area SCENARIO TIME: 04:45 l
****************************************************************************** 1 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
****************************************************************************** 1 12:00 18:00 - General Area Forecast National Weather Service Forecast for site region:
Partly to mostly cloudy. Winds from the southeast shifting to northerly and
; increasing to 5-7 MPH. High temperature in the upper 50's. Clearing later tonight. Temperature in the low 40's.
Special Weather Statements:
**********************+*******************************************************
THIS IS A DRILL
Rev. 0
? age 6.2 37
("^ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY REGPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CARD FROM: State Controller MESSAGE NO.: ST-M 3 TO: State Radiolocien1 Health Reo. CIDCK TIME: 1145 LDCATION: State EOC SCENARIO TIME: 04:45 THIS IS A DRILL DO NOI . initiate any actions affecting normal plant operations.
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12:00-18:00 - General Area Forecast National Weather Service Forecast for site region: Partly to mostly cI sudy. Winds from the southeast shifting to northerly and +
- increasing to 5-7 MPH. High temperature in the upper 50's. Clearing later
-tonight. Temperature in the low 40's.
'Special Weather Statements: ,
P THIS IS A DRILL
.u . - -
s"_u .i ---r.J-- s2.a. -_*a= A + - --u-- al. +4- - - - -ah4- p.-464 e m- - i ( VERMONT YANPEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7,0 STATION EVENT DATA f r 4
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VERMONT YANKEE FUCLEAR PO'JER GTATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.1 EVDTTS
SUMMARY
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Rev. O Page 7.1-1 g
\
VERMONT YAWEE NUCLEAR p0WER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.1 EVENTS
SUMMARY
The following intmu. tion and supplementary naterial are provided for those evaluators having in plant control assignments so as to further ensure the proper development of the scenario. The information provided in this section assumes that the " players", who' are dispatched to perform repair, rescue, or other activities, will take certain actions in response to the scenario. The evaluator must be cognizant of the actions of those players to which assignments are given and . provide information regarding the results of the players' actions, as appropriate. The information provided in this section does not precJ,d> the possibility that the evaluator will be required to provide additional informction to the players. I ApproxitLte Location Initiation
- Miniscenario I. int LY.tDI 7.2.1 0745 ADS relay Control Room Simulator failure controller 7.2'.2 0845 Loss of DC-3 Switchgear Simulator Room Response 7.2.3 1045 CRD-V56 Reactor Simulator Operation Building Response 7.2.4 1045 "C" RHR Switchgear Simulator Pump Trip Room Response 7.2,5 1050 SLC Squib Reactor Simulator Valve Failure Bui1Cing Response Reactor Simulator 7.2.6 1050 RWCU V12-15 Failure Building Response
1 i VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE l 1991 l 1 l l l I f l 7.2 EVENT MINI-SCENARIOS ; I I I i i
Rev. O Page 7.2.1-1 VERMONT YANKEE NUCLFAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.1 Miniscenario - ADS Relav Failure I. General Description As a result of the HPCI system being declared inoperable, Technical Specifications require that alternate testing of the Automatic Depressurization System (ADS) be completed. At the start of the exercise, a simulated 160 test group is performing a functional test of the ADS. A controller will inform the Shift Supervisor that the 120-second timer relay failed to operate in accordance . with the test document specification. The timer will have to be replaced before the system can be returned to service. II, Description of Player Restonses/ Observations / Corrective Actions 1 The Shif t Supervisor should declare an UNUSUAL EVENT as a result of the loss of t'e ADS. A repair team should be assembled and dispatched to assemble the necessary materials (spare relay, tools, procedures, etc.) to replace the relay. If possible, an actual relay should be located in Stores , BUT NOT REMOVED, before any " replacement" activity commences. Standard station maintenance practices should be followed throughout the activity. III. Zvent closeout This event will be closed out when the repair team informs the evaluator that they have assembled all the necessary tocls, equipment and software (replacement parts , manufacturer's procedure / prints , etc. ) and are ready to install the new relay. The evaluator should ask the team leader how long the repair will take to complete, including testing. The team 1cader should inform the SCR that repairs are underway and provide an l l l
- . - . . . . . - _ _ . .~ ... . .- -. .... -. .~ .._-
Rev. 0
. Page 7.2.1 2 VERMONT YANKEE NUCLEAR POWER STATION-EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 T
estimate of job' duration. The I&C Teata vill be released when the time specified by -the team leader has elapsed. IV. Ht.EEasta ~ The' following messages are applicable to this event. The messages shall' be provided to the players at the indicated time or when the evaluator determinen that the information has been " earned" by the player. Message Approxim.ite . Basic Number Ijgg Descrintion , 7.2.1-M-1 0715' Shift 16C. Technician report that ADS relay failed test. 7.2.1-M-2 0745 Shift I&c . Technicians initiate repairs to the d' failed ADS relay. e e , - --e
- _. . - - - ~. -- = - -. .. . . . -
Rev. 0-Page 7.2.1 3 VERMONT YANKEE NUCLEAR: POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 d MINI-SCENARIO MESSACE CARD FROM: SCR Controller MESSAGE NO.: 7.2.1-M-1 TO: Shift-Suocrvisor CIDCK' TIME: 0715
' 1DCATION: SCR (Gaitronics) SCENARIO TIME: 00:15-
-THIS IS A DRILL DO NOT. initiate any actions affecting normal plant operations.
. NOTE TO CONTROLLER: ' REPORT THIS INFORMATION OVER THE SIMULATOR CAITRONICS TELEPHONE "THIS IS (name'of shif t I&C Technician), WE JUST COMPLETED THE FUNCTIONAL TEST OF-THE ADS TRIP LOGIC. EVERYTHING. CHECKED OUT O.K., EXCEPT THAT THE 120-SECOND TIMER RELAY
- TIMED OUT AT 145 SECONDS. THIS IS OUTSIDE THE ACCEPTANCE RANGE ALLOWED IN THE TEST-SPEC. WE'RE GOING'TO HAVE TO REPLACE THE RELAY."
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Rev, 0-Page 7,2.1 4 {-- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINT-SCENARIO MESSACE CARD FROM: JCR Controller MESSAGE NO.: 7.2.1-M 2 TO: Shife Suoervisor CIDCK TIME: 0745 IDCATION: SCR (Caitronics) SCENARIO TIME: 00:45 THIS IS A DRILL
.DO NOT' initiate any actions affecting normal plant operations.
REPORT THIS INFORMATION OVER THE SIMULATOR GAITRONICS TELEPHONE i NOTE TO CONTROLLER:
"THIS IS (name of shift 160 Technician),- WE JUST REMOVED THE BAD REIAY. WE llAVE A SPARE REIAY OVER IN STORES. : WE SHOULD BE ABLE TO CET THE NEW ONE INSTALLED TESTED AND BACK IN SERVICE IN ABOUT 2 1/2 TO 3-HOURS.
o i' l
Rev. O Page 7.2.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.2 Miniscenario - Loss of Electrical Bus DC-3
- 1. Cencral Description At approximately 0815 electrical bus DC 3 experiences a loss of power.
When the Control Room operators realize this, they should dispatch an A0 to the Manual Bus transfer switch in the Switchgear Room. The A0 will have to manipulate the transfer switch in order to power the bus from its emergency power source. During the switching process, the actuator jams midway through the process. The A0 will not be able to reposition the switch and should contact the SCR and inform them of the situation. II. Descriorion of Player Resoonses/ Observations / Corrective Actions When power is lost to electrical bus DC-3, the following indications are ( lost in the Simulator Control Room:
- Panalarms e Various Electrical Distribution Control indications e Various Turbine Control indications The loss of these items may not be readily apparent to the operators, based on plant conditions and activities in progress (i.e. controlled power reduction) at the time of the power loss. When the Shift Supervisor realizes that the panalarms have been lost, the controlled power reduction may be suspended. An AIE.RT should be declared and an l
Auxiliary Operator (AO) dispatched to investigate the loss of DC-3. When the A0 arrives at the manual bus transfer device, he should attempc to reposition the manual transfer to the emergency power source. When f this is attempted, the device jams and cannot be moved, g I When the repair taam arrives at the transfer device, they will discover that the switching device-is in the NORMAL position and cannot be placed in the EMERGENCY position. When they open the bus transfer housin6 they
Rev.-0 Page 7;2.2-2 1
-VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 position. When they open the bus transfer housing they can see that the actuator is ._ mechanically bound. After some manipulation, they can physically operate the switching device and place it in both the _ NORMAL or' EMERGENCY position. They may " cycle" the actuarnr several times.
attempting to re-create the malfunction, but the ' device ' operates normally. In_ any event the transfer device will be returned to service and DC-3 repowered from it's normal source by 0945. III. -Event Closeout-This event will'be terminated when the repair team leader informs the evaluator of all actions that would be taken based on the conditions described above. When the evaluator informs the team leader that the I - transfer device is operating as designed, the team leader should report this information to the'SCR and recommend that the bus be put back inservice, powered from the emergency bus. . IV. tietsares The'following messages are applicable to this event. The messages shall
~be.provided to the players at the indicated time or when the evaluator-
' determines that the information has'been " earned" by the player.
Message Approximate Basic Number. Iig.g Descriorion 7.2.2-M 1 0915 A0 activities when attempting to operate DC-3 Manual Bus transfer device. 7.2.2-M-2 0930 Initial results of inspection of transfer device. 7.2.2-M-3 0945 Results of troubleshooting activities.
Rev. 0 Page 7.2.2-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSAGE CARD FROM: OSC observer MESSAGE NO,: 7.2.2-M-1 TO: A0 0 DC 3 CIDCK TIME: 0915 LOCATION: DC-3 Manual Bus Transfer SCENARIO TIME: 02:15 THIS IS A DRILL Do~NOT initiate any actions affecting normal plant operations. When you attempt to transfer power to the EMERGENCY source, the selector switch cannot be repositioned. All efforts to change to the EMERGENCY power source fail, i
n, . Rev. 0 . Page 7.2 2 4 b-- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSAGE CARD OSC Observer MESSAGE NO.: 7.2.2-M 2 FROM: AO/OSC Recair Team Iaader O DC-3 CIDCK TIME: 0930 TO: Area of DC-3 bus transfer SCENARIO TIME: 02:30
'IDCATION:
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
-The selector switch / actuator are mechanically jammed. Af ter some uninor adjustment to the connections the linkage operates freely, d
. . . . .- .. -.- . . . - ~ - - - . . .. . ~ , . . . - .
Rev. 0 Page 7.2.2-5
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' VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE-PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSACE CARD FROM: OSC Observer MESSAGE NO.: 7.2.2-M-3
- TO:
A0/OSC Renair Team Leader O DC-3 C1hCK TIME: 0945 -
- IDCATION: Area of DC 3 bus transfer SCENARIO TIME: 02:45-THIS-IS A-DRILL D0'NOT initiate any-actions affecting normal plant operations.
Af ter . several - manual actuations of the bus transfer device ,- no - malfunctions . have occurred. The-bus transfer device can be placed back in service. 1 a. 5 4 z i i
. ~. ., . . . . . . . _ . _ . . _ . . _ . . _ ._. . . _ . . . . _ _ . . .
Rev. O Page 7.2.3-1
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- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.3 Miniscenario - CRD-V56 Oceration I. Ceneral Descriution 4 When the turbine trips on loss of condenser vacuum, a reactor SCRAM -
should take place. . Indications on the Reactor Control Board show that the signal- was generated, but the control rods did not insert. The 3 Shift . Supervisor will follow OE 3101, " Reactivity Control Emergency Procedure". Control rods will be manually inserted from the simulator control board. Before this can ' be in'itiated, the Control' Rod Drive charging water header- isolation valve (CRD V56) must be shut. II.
'Descriotion of Player'Resoonses/ Observations / Corrective Actions f
s When the decision'to manually drive the control' rods into the core'is made,- an Auxiliary Operator -(AO) would be dispatched to the _ Reactor Building 252'-6" elevation to shut CRD-V56. When the A0 reaches the
. valve location, the evaluator will direct that all actions associated with valve manipulation be sineslated. The - A0 should describe all actions to be taken to reposition the valve to the evaluator and inform the SCR accordingly f
III. Event Closecut This event is terminated when the A0 reports to the SCR that the valve has been repositioned.
Rev. O Page 7.2.3-2
-VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991-
--IV. Messages The following messages are applicable to this event.- The messages shall be provided to'the, players at the indicated-time or when the evaluator ;
i determines that the information has been " earned" by the player. Message- Approximate Basic Number ligg Descrintion-
- 7 . 2.3 M l'- 1045 Auxiliary Operator closes CRD-V56.
6 ,4 4 1 4 y -
Rev. O Page 7.2.3-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSAGE CARD FROM: OSC Observer MESSAGE NO. : 7.2.3-M-1 AO disostched to shut CRD-V-56 CLOCK TIME: 1045 TO: Reactor Buildine SCENARIO TIME: 03:45 1DCATION:
********************************************************c*********************
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. Simulate all activities associated with closing the charging water header isolation valve, except for appropriate communications with the Control Room, f t
Rev. 0 ' Page 7.2.4-1 VERMONT YANKEE NUCLEAR POVER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.4 Miniscenario "C" RHR Pumo Trio At approximately 1015 the turbine trips due to a loss of condenser vacuum. This results in the Main Condenser being unavailable as the primary heat sink. The operators should initiate RHR in the Torus Cooling mode for reactor temperature and pressure control. This should occur by 1030. At approximately 1045 the simulator operator will insert a loss of the "C" RHR Pump. I. General Descriotion When the "C" RHR Pump is lost, the "A" RHR pump should start to maintain torus cooling via the RRR heat exchangers. An AO or OSC Team may be dispatched to investigate why the pump tripped. They should proceed to the Switchgear Room. The breaker for the pump will be in the open (tripped) position. They may reset the breaker and inform the SCR of their actions. If they attempt to restart the pump, it will immediately trip. Further investigation of the breaker will reveal that the undervoltage trip coil has opened, which resulted in the breaker trip. This information should be provided to the OSC and/or the SCR so that repair activities can be initiated. II. Descriotion of Player Resoonses/ Observations / Corrective Actions A repair team should be assembled, briefed and dispatched to repair the "C" RER Pump circuit breaker. They should follow standard tagging procedure to ensure the breaker is de-energized, obtain spare parts from Stores and follow standard maintenance and radiological controls practices and applicable manufacturer's repair procedures.
. . . . - .. .~ . .- - . . . .. - .- . . _ .
i Rev. O Page 7.2.4-2 VERMONT. YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 III.- Event Closecut This event will be closed out when the repair team informs the evaluator that they have assembled all the necessary tools, equipment and sof tware (tagging procedure / approval, replacement parts, manufacturer's-
- procedure / prints,_ etc.) and are ready to install the new relay. The evaluator should ask the team leader how long the_ repair will take to complete, including testing. The Mam leader should inform the OSC that repairs aro underway and-provide an estimate of job duration. The OSC Team will be released when the time specified by the t.eam leader has elapsed. In the' event ~ that the area becomes uninhabitable (due to scenario conditions), the Team should return to the OSC and brief_ the OSC Coordinator accordingly.
IV. Messaces . The following messages are applicable to this event. The messages shall be provided to the players at the indicated time or when the evaluator determines that the information has been " earned".by the player. Message Approximate Basic Number T.ima Descrintion 7.2.4-M-1 1100 . Initial response to the RHR Pump circuit breaker. i 7.2.4-M 1105 Internal investigation of circuit breaker. 7.2.4-MJ3 1130 Results_ of internal troubleshooting activities.
-7.2.4-M-4 1150 Completion - of installation and testing of replacement relay. ,
l Rey, O Page 7.2.4-3 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSAGE CARD FROM: "SC Observer MESSACE NO.: 7.2.4-M-1 TO: OSC RHR Pumo Repair Team Leader CIDCK TIKE: Anorox. 1100 IDCATION: C RHR Pturo circuit breaker SCENARIO TIME: 04:00 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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The circuit breaker for RHR Pump "C" is in the tripped position.
Rev. O Page 7.2.4-4 f -\. VERMON! YANKEE NUCLEAR POWER STATION. EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO KESSACE CARD
-FROM: OSC Observer . MESSAGE NO.: 7.2.4 M-2 -
CLOCK TIME: Acorox. 1105 TO: QSC'RER ramo Renair Team Leader C RHR Pumo circuit breaker SCENARIO TIME: 04:05 IDCATION:
********************************************e;;;;;;.;**************************
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
-NOTE TO CONTROLLER: PROVIDE THIS INFORMATION AFTER THE REPAIR TEAM LEADER EXPLAINS THAT THEY WOULD PERFORH AN INTERNAL INSPECTION OF THE CIRCUIT BREAKER.
You notice the undervoltage trip coil is slightly blackened and the insulation appears [, to be very brittle.
Rev. O Page 7.2.4-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991
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MINI-SCENARIO MESSAGE CARD-FROM: OSC Observer MESSAGE NO,: 7.2.4-M-3 OSC RHR Pumo Repair Team Leader CIDCK TIME: Approx. 1130 TO: LOCATION: C RHR Pumo circuit breaker SCENARIO TIME: 04: 30 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. NOTE TO CONTROLLER: PROVIDE THIS INFORMATION ONLY AFTER THE REPAIR TEAM DESCRIBES THAT THEY WOULD INITIATE RESISTANCE (OR HEGGAR) READINGS OF VARIOUS BREAKER COMPONENTS Resistance across the undervoltage trip coil reads infinity.
_. . _ - . . . - , . . _..m - Rev. 0 Page 7.2,4-6
.- (. VERMONT YANKEE NUCLEAR-POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSAGE CARD FROM: -OSC Observer MESSAGE NO.: 7.2.4-M-4
- TO : OSC RHR Pumo Repair Team Leader CIDCK TIME: Anorox. 1150 LOCATION . C RHR'Pumn circuit breaker SCENARIO TIME: 04:50
**************************************e;.eet.e;.e********************************
THIS IS~A DRILL DO NOT initiate any actions affecting normal plant operations. NOTE TO CONTROLLER: PROVIDE THE FOLLOWING INFORMATION AFTER THE REPAIR TEAM LEADER
' EXPLAINS TO YOU HOW THE NEV COIL WOULD BE INSTALLED, TESTED AND THE BREAXER RETURNED TO SERVICE. IF A SPECIFIC TIME. PERIOD WOULD BE CONSUMED DURING THE INSTALLATION AND TEST ACTIVITIES, DO NOT RELEASE THE TEAM UNTIL'THAT TIME PERIOD ELAPSES, f
1 The coil has been installed and tested. The' breaker can be returned to service. 4 e e
Rev. 0 Page 7.2.5-1 [ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.5 Miniscenarlo - SLC Sauib Valves Fail to Fire I'. General Description In - an effort to reduce reactor power, the operators may elect to initiate Standby Liquid Control (SLC). This is accomplished from the
~
Reactor Control Panel using the appropriate keylock control switches which actuate the explosive Squib valves. When the Reactor Operator actuates the switches, the valves fail to fire. II. Description of Plaver Responses / Observations / Corrective Actions When the RO notices that the squib valves did not actuate, an A0 may be dispatched to manually actuate the valves. This is accomplished in 4 accordance with OE 3101, Appendix G. This will involve attaching a battery to each valve to set off the explosive primer. THESE ACTIONS WILL BE SIMULATED. When this is demonstrated, the A0 can report that the valves have been actuated and initiation of SLC can commence. III. Event Closeou_t; This event is terminated when the AO reports to the SCR that the valves have been fired. IV. Messages The following messages are applicable to this event. The messages shall be provided to the players at the indicated time or when the evaluator determines that-the information has been " earned" by the player. Message Approximate Basic Number Time Description 7.2.5-M-1 1050 Manual firing of Squib valves by AO.
Rev. 0 Page 7.2.5 2 { VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991. MINI-SCENARIO MESSAGE CARD-
-FROM: OSC Observer MESSAGE NO.: 7.2.5 M-1 TO: ~A0 dispatched to fire Sauib valves' CIDCK TIME: Acerox. 1050-LOCATION: Reactor Buildinc. Souib valves SCENARIO TIME: 03*50
~
~
THIS IS A DRILL DQ_l!QI initiate any actions affecting normal plant operations. NOTE TO CONTROLLER: - DO NOT ALLOV THE A0 TO PHYSICALLY HANIPULATE ANY EQUIPHENT ASSOCIATED WITH THIS ACTIVITY. _THE A0 SHOULD DEMONSTRATE HG TO PERFORM THIS ACTIVITY, INCL 1] DING THE LOCATION OF AHE ' BAITERY. ISSUE THIS HESSAGE WHEN THE AO TELLS YOU THA* ALL ACTIONS IDENTIFIED IN DE 3101, APP. G HAVE BEEN COMPLE~E. > MANUAL ACTUATION OF THE SQUIB VALVES IS COMPLETE.
+-
Rev. 0 Page 7.2.6-1 ( VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.6 Miniscenario - RUCU V12-15 Failure I, General Descrintion When the automatic isolation signal is sent to the Reactor Water Cleanup (RWCU) system, the primary containnent inboard isolation valve (RWCU-V12-15) remains open due to MOV motor controller failure. II. Descriotion of Player Resoonses/ Observations / Corrective Act 4 m t An OSC Team should be assembled, briefed and dispatched to the Motor Control Center containing the controller for this MOV. When they arrive, they should secure incoming power to the controller, perform a visual inspection of the controller's exterior and commence troubleshooting of the internals. When they open the controller, they will observe charring of the main line contactor. Contacts A and C are pitted and contact B is partially missing. The contacts will have to be replaced in order to return the MOV to service. All.other components are intact and operable. In addition, an I6C Technician may be directed to investigate the valve's logic circuit in the control be,ard. If this occurs, the I&C Technician will report that logic circuit checks are satisfactory. III. Event Closecut This event will be terminated when the team demonstrates that the spare parts can be obtained from Stores, installed and tested (simulated), and report made to the SCR that the controller can be returned to service.
l l
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I Rev. O Page 7.2.6-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 IV. Messaces The following messages are applicable to this event. The messages shall be provided to the players at the indicated time or when the evaluator determines that the information has been " earned" by the player. Message Approximate Basic Ntteber Time Descrintion 7.2.6-M-1 1100 OSC repair team reports to the area of the RWCU Valve motor controller. 7.2.6-M-2 1110 Results of internal inspection of motor controller. 7.2.6-M-3 1110 16C investigation of valve logic circuit in control board. 7.2.6-M-4 1150 Motor controller is repaired. (
Rev. 0 _Page 7 2.6-3 [ VERMONT YANKEE NUCLEAR POWER STATION EMGCENCY RESPONSE PREPAREDNESS EXERCISE 1991 . MINI-SCENARIO MESSAGE CARD FROM: OSC Observer MESSAGE NO.: 7.2.6-M-1 TO: RUCU Valve Reoair Team Leader _ CIDCK TIME: 1100 LOCATION: RWCU Valve Motor Ooerator SCENARIO TIME: 04:00
-********************************************;;;;. ;;;;,a************************
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. The motor controller external inspection reveals nothing out of the ordinary. 4 t I l l. i-
-- . , .- . . . . . . - . - - . . . - ~ - - - - . . - _ - . . ~ . . . ..
f Rev. 0 Page 7.2.6-4 <E { VERMONT. YANKEE NUCLEAR POWER STATION I
-EKERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSACE CARD
-KESSAGE NO : 7.2.6-M 2
'FROM: OSC' Observer CIDCK TIME: 1110
.TO: RUCU Valve Renair Team Imader SCENARIO. TIME: 04 10 .3; LOCATION: RWCU-Valve Motor Ooerator
****************** *** *** * ***** ** :. :. ;. ; a ;, ;. ;. ;. ;. ;. ;. ;. ; ; :. ;. ;. ;. : *********************+* ***
THIS.IS A DRILL DO NOT: initiate any actions'affecting normal plant operations.
*****************************************************THE NOTE TO CONTROLLER: PROVIDE THIS INFORMATION WHEN REPAIR TEAM LEADER EXPLAINS THAT AN INTERNAL INSPECTION OF THE MOTOR CONTROLLER VILL BE ^
PERFORMED. THE: REPAIR TEAM SHOULD TAKE- STANDARD ELECTRICAL SAFETY PRECAUTIONS CONSISTENT WITH THE ACTIVITIES -' TO BE FERFORMED. r. 1
. Yow observe minor charring in the' area of.the-main line contactor. The main "B" are line.
' contacts for phases A and.C are blackened and pitted, the contacts for phase N
cracked and partially missing. F f k v d 4
l l I Rev. O Page 7.2.6-5 g
\ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSAGE CARD Control Room Controller MESSAGE NO.: 7.2.6-M-3 FROM:
I6C Technician checkinc RWCU logie CIDCK TIME: 1110 TO: IDCATION: Control Room vanel SCENARIO TIME: 04:10 THIS IS A DRILL 4 DO NOT initiate any actions affecting normal plant operations. s NOTE TO CONTROLLER: PROVIDE THIS INFORMATION AFTER THE I&C TECHNICIAN E? PLAINS THE TROUBLESHOOTING ACTIVITIES TO BE TAKEN (INCLUDING AN ESTIMATE OF HOW LONG THIS WILL TAKE). DO NOT RELEASE THE TEAM UhTIL THAT TIME HAS ELAPSED. All circuit readings are normal.
Rev. 0 Page 7.2.6-6 / \ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 M NI SCENAFJO MESSAGE CARD FROM: OSC Observer MESSAGE No.: 7.2.6-M-4 RUCU Valve Repair Team Leader CIDCK TIME: 1150 TO: RWCU Valve Motor Operator SCENARIO TIME: 04:50 1DCATION: THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. NOTE TO CONTROLLER: PROVIDE THIS INFORMATION AFTER THE REPAIR TEAM LEADER EXPLAINS THE REPAIR ACTIVITIES TO BE TAKEN, INCLUDING OBTAINING REPLACEMENT CONTACTS FROH STORES, INSTALLATION AND TESTING. IF THE TEAM LEADER SPECIFIES A :ENGTH OF TIME TO COMPLETE THE REPAIR, DO NOT RELEASE THE TEAH UNTIL THAT TIME HAS ELAPSED. The contacts have been replaced, tested and the unit can be returned to service. 1
VERMONT YANKEE IGCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 8,0 OPERATIONAL DATA
/-
NOTE: The operational data is highly dependent on operator actions taken in response to the conditions presented within the scenario. The operational data reflects plant conditions asswning certain basic operator response actions being taken. The operational data was taken from the plant simulator. l-
YERKET TANEEE N'JCLEAR KWER BfATION Rev. O IHERGDCT RISK *EE FREFAREDNESS EXERCISE FaBe 6.0-1 1991 8.0 0FDATIONAL DATA 00:00 00:15 00:30 00:45 01:00 01:15 01:30 01:45 SC D ARIO TIME CLOCK TDIE 07:00 07:15 07:30 07t45 08:00 08:15 08:30 08:4$ . INSTR. TL ID DESCRIPTION 11 NITS a n. . Om 0 0 0 0 0 0 0 0 O FT 23 108-1 BFCI FIDW 1 CM 1 1 1 1 1 1 1
' ~
o F1-10-139A RRR A FliW 1
. 3 Fl*10 1398 kER B FLOW GM 1 1 1 1 1 1 1 Om 10 10 10 10 10 10 10 10 4 93 F1-14*$0A Cs A FLOW GM 10 to 10 10 10 10 10 10
$ 93 Fl*14-508 CS B FliW 17 17 17 17 17 17 17 17 8 93 F1-16-19 12 DRYWELL PRESS PSIA 17 17 17 17 17 17 17 17 7 9-3 F1 16-19 12 DRYWELL FRESS PSIA CM 0 0 0 0 0 0 0 0 8 94 F1 13 91. RCIC FLOW GM 65 65 65 65 65 65 65 65 9 9-4 F1-12-141A RWCU FLOW Om 65 85 65 65 65 65 6S 65 10 9-4 F1-12 141B RWrU FLOW S28 S26 $27 527 $26 $25 $7.3 S22 11 9-4 2-16SA RX COOLANT TIMP DEO F
$78 S75 S27 527 526 125 523 $22 12 94 2-165B RX COOLANT TD9 DEG F EGm 30.6 30.6 29.9 29.4 28.3 25.7 24.4 23.4 13 9-4 2 159A REC 1kC A LOOP FLCW RECTRC B LOOP F1IW EON 30.6 30.6 29 9 29.4 28.3 25.6 24.3 23.4 14 04 2-159B 99 99 98 97 94 87 84 91 15 0-S 7-46A AFM/1kN A 1 100 100 08 97 94 87 84 82 16 0-S 7-467 ArkM/fRM S 1 1 98 98 97 96 93 66 83 80 17 9-S 7-4bC AFRM/1hM C 1 99 99 98 97 94 87 84 81 18 9-S 7-46D APRM/IRM D 1 100 100 99 98 95 67 85 82 19 9-S 7 46E AFhM/3RM E 1 100 100 99 98 95 67 84 82 20 0-5 7-Aff APRM/1RM F
. 21 9-5 7-43A TAM A CP5 3.70E+0S 3.70E+0S 3.60E+0S 3.50E*05 3.40E+0S 2.801.+0S 2.SCE+0S 2.40E+0S 22 0-5 7-43B BRM B CPS 4.SOf+0S 4.50E*05 4.40E+0S 4.30E+0S 4.00t+0S 3.40E+0S 3.00E+0S 2.60E+0S 23 9-S 7 43C EkN C CPS S.CCE+0S S.00E+0S 4.90E+0S 4.60E+0S 4.50E+0S 3.80E+0S 3.50E+0S 3.20E+0S 24 9S 7 43D ERM D CPS 6.20T+0S 4.20E+0S 4.10!+0S 4.00f *05 3.70f*05 3.20E+0S 2.00E40S 2.7CT+0S 47 47 47 46 44 40 38 37 25 9-3 2-3 95 CORE FIDW MLB/HR PSID 18 18 lb 17 17 14 13 12 26 9-5 2 3-95 CORE DP GM 47.3 47.3 47.3 47.3 47.3 47.3 47.3 47.3 27 9S #1-3-310 CRD FLCW 984 PS10 1007 10D7 1006 1004 1001 991 987 28 9-5 6-96 WIDE RANGE PRfSS FS10 1007 1007 1006 100$ 1001 992 987 984 29 9-S 6-96 RAR RANGE PRES $
MLB /liR 6.3 6.4 6.3 6.2 6 S.6 S.3 S.1 30 9-S 6-97 FEEDWATER FLOW K.B/HR 6.4 6.4 6,3 6.2 6 S.6 S.3 S.1 31 9-3 6-97 MAIN STEAM FLOW NAR RANGE LEVEL . INCEES 158 158 159 158 158 158 158 158 32 9S 6 98 I K.HES 492 489 481 481 455 410 391 372 33 9-3 6-98 WIDE RANGE LEVT.L 1 51 S1 SO SO SO SD 48 47 34 96 L1-107 5 CST LTVTL 2 $6 56 S6 56 56 56 73 82 35 9-6 L1-102 SA BOTWELL LINEL M S4 $4 S4 S4 $4 S4 S4 $4 36 9-6 L1-102-58 POTWELL LtVEL 5 I IN BQ 1,8 1.8 1.8 1.8 1.8 1.7 1.7 1.7 37 9-7 F1-101-29 iONDD SER %ACUUM OPEN OPEN OPEN OPEN OPEW OPEN OPEN OP118 38 98 DIO A ?KR ~ 9-8 9/G B BKR OITN OFD OFD OFD OFD OPD OPEN Ordi 39 DEO F 72 72 72 72 72 72 72 72 40 0 23 16-10 33A/C TORUS TEMP 9 25 L1-46A TCRUS LEVEL FEET 0.S6 0.58 0.S6 0.58 0.56 0.37 0.57 0.57 41 0.S6 0,58 0.58 0.58 0.58 0.S? 0.S7 0.57 42 0-25 L1-46B TORUS LEVEL FEET FSIA 14.6 14.6 14.6 14.6 14.6 14.6 14.6 14.6 43 9-25 TR-16-19-44 TORUS FRESS PSIA 17 17 17 17 17 17 17 17 44 9-25 TR-16-19*44 DRYWEtt PRESS PSID 1.48 2,06 2.04 2.03 2.02 2.00 1.99 1.98 45 9-25 PR-1-156-3 DW/ TORUS DP DEO F 106 106 106 106 106 106 106 106 46 0-25 TR-16-19-4S DRYWELL TEMP IN 1120 +4.62 *1.62 -1.62 -1.62 *1.62 -1.62 *1.62 -1.62 47 9-26 F1-1 12S 3A R1 BUILDING DP TN R20 -1.62 -1.62 -1.62 -1.62 -1.62 -1.62 -1,62 -1.62 48 9-26 PI 1 125-3B RX BUILDING DP Cm 0 0 6 6 6 6 6 6 49 9-26 F1-1 125-1A SGTS FLOW Cm 0 0 0 0 0 0 0 SS 9-26 F1+1-125-1B SOTS F10W , ___0 DW/ TORUS O2 CONC, t 2.M 2.$$ 2.55 2.54 2.54 2.54 2.54 2.53
$1 CAD
_ . _ _ _ . , . . _ _ _ _ . . _ _ _ _ . . _ _ _ _ _ _ m = _ . VERT ST YANE*.! FUCLEAR POWER STATION Rev. O EMDWENCY RISIONSE FRIFAREDKfSS IXDCIT.E Fase 8.0-2 1991 8.0 OPERAT10RAL DATA 02:00 02:15 02:30 02:4S 03:00 03:15 03:30 03:4S SCENARIO TIME 09:00 09:15 09:30 09:45 10:00 10:15 10:30 ' vie $ INSTR. CLOCK T1HE ID DESCh!PT10N 11N!TS 17FN PANEL 0 0 0 0 0 0 0 0 1 9-3 FT 23 106-1 Eft! FLOW GIH 1 1 1 2 6433 2 93 F1 10 139A Rf!R A FLrW GIN 1 1 1 1 1 1 2 6497 3 9-3 F1 10-1398 RJIR S FLW GIN 1 1 1 10 10 10 10 10 10 o 0-3 F* 14-$0A C8 A FLOW CfM to 10 10 10 10 10 10 10 9 9-3 F1-14 S05 CS 9 Fim GIN 10 10 17 17 17 17 17 18 18 6 9-3 P! 16 10-12 DRYWitt PRESS PSIA 17 17 17 17 17 17 18 18 7 9-3 Pl*16 19-12 DRYWELL PRESS PSIA 17 0 0 0 0 0 0 0 94 F1-13 91 RCIC Fim OfH 0 _8 9-4 F1 12-141A RWCU FLOW GIN t, S 65 63 63 65 65 0 0 9 0 65 65 65 65 65 t$ 0 10 0-4 F1 12-141B RwCU FIN CIH S20 518 317 S15 527 443 11 9-4 2-16SA RX COOLANT TEMP DEO i 522 S20
$20 S20 $18 $17 $15 S27 443 12 9-4 2 1659 RX COOLANT TEMP DEO F S22 RICIRC A IJX)? F1w KGIM 23 21 20.7 19.1 17.7 15.9 0 0 13 9-4 2-139A 0 E0fH 23 21 20.7 19 17.6 15.9 0 to 04 2a1597 RFCIRC B LOOP FLOW 3 80 73 74 70 67 63 5 3 15 93 7-46A APRM/1RM A 75 71 67 63 $ 3 APRM/1RM $ 1 80 75 16 05 7 469 3 79 74 74 70 66 62 S 17 9-S 7-46C APW1RM C I 75 74 70 67 63 S 3 9-S 7-46D APRM/1RM D t 40 18 3 81 76 73 71 67 63 5 19 9-5 7 46E AFhM/1kM E I 61 15 75 71 67 63 S 3 20 9-5 7 46F AftM/1kM F 1 21 9-3 7*43A ERM A CPS 3.40E+08 2.02E+0S 1.97E*05 1.74E*05 1.56E+0S 3.$0E+06 3.00E+03 2.82E+02 32 9-$ 7-439 ERM B CPS 7. 00E+06 2. 41E+0S 2. 34r+0S 2.07t+0S 1. 86t+0S 6.10!+06 3.001603 1.8SE+02 33 9-S 7 43C SRM C CPS 1.40E+06 2.72E+0S 2.64E+0S 2.34E+0S 2.09E+0S 6.20E+06 3.00E+03 1.87E+02 ERM D CPS 6,10E+06 2.26F405 2.20f +0S 1,95t+0S 1.74E+0S S.1CE+06 3.00E+0S 1.83t+02 24 0S 7 43D 36 33 32 30 28 26 1 1 25 0-3 2395 CCRE Fi m ML8 / tfR 11 10 9 8 3 3 239S CORE DP PSFD 12 11 36 9-S GIN 47.3 47.3 47.3 47.3 47.3 45.9 45.0 45.9 37 9-S TI-3-310 CRD FLOW 964 911 932 P510 983 077 976 972 CE8 38 9S 6-96 WIDE RANGE PRESS 950 963 977 976 972 969 965 950 9-S 6-96 RAR RANGE PRIES PSIG 39 4.4 4.1 3.9 0 0.2 '
MLP / ftR S 4.7 4.6 30 9-S 6-97 FEEDWATER FLOW MLB /IIR S.1 4.7 4.7 4.4 4.2 3.9 0 0 S1 9-5 6 67 MAIN STEAM FLOW 42 47 INCETS 158 159 158 158 IS8 159 32 9-S 6 98 NAR RANGE 1.EVEL 364 328 314 294 267 248 42 47 33 9-5 6-96 WIDE RANGI LEVEL INCHES 47 47 47 46 47 $1 48 45 34 9-6 L1-107-5 Cst LEVEL 1 84 83 81 65 $$ 47 SS 9-6 L1-102-SA DOTWELL LEVEL M 2 64 SS 47 54 54 54 54 S4 58 S3 S t. 9-6 L1 102-SB BOTWE L 1.TVE1. S t IN BG 1.7 1.7 1.6 1.6 1.6 1.8 24.2 29 37 9-7 P1-101 29 OONDENST.R VACUUM OITN OPEN OPEN OPEN OPEN OPEN OPEN OPEN Se 9-8 D/0 A BKR OFEN OITN OPEN OP!JI OPEN OPI.N CPEN OPEN 39 9-8 D/G $ BKR DEO F 72 72 72 72 72 72 138 141 40 0-23 16-19-33A/C TORUS TEMP FEIT 0.37 0.37 0.57 0.37 0.S7 0.56 0.00 0.96 01 9-25 L1-4 6A TORUS LEVEL 0.57 0.$6 0.90 0.96 0.57 0.S7 0.57 0.S7 42 0 25 L1-466 TORUS LEVEL FEET 14.6 10.6 16.9 P51A 14.6 14.6 14.6 14.6 14.6 43 9-25 TR 16-19-44 TORUS Pf255 17 18 18 PSIA 17 17 17 17 17 04 9-25 TR-16 19-44 DRYWELL PRESS PSID 1.97 1.96 1.94 . 93 1.92 1.91 -0.49 -0.48 43 9-2S FR-1-156-3 DW/ TORUS DP 106 106 108 107 DTO F 106 106 106 106 66 9-25 TR-16-19-45 DRYWELL T1MP IN B20 -1.62 -1.62 -1.62 -1.62 -1.62 -1.62 -0.68 -0.68 47 9-26 F1-1 125-3A EX BUILDING DP +1.E2 IN 820 1 62 -1.62 -1.62 -1.62 -1,62 -0.68 -0.68 66 0-26 PI-1-125 3R RX BUILDING DP 1300 CFN 6 8 8 6 6 0 1500 09 9-26 T3 1-123-1A SGTS TLCW 0 1500 1S00 CPM 0 0 0 0 0 50 9-26 F1 1-125-1B scTS FLOW 2.52 2 2.53 2.53 2.53 2.52 2.52 2.58 2.51 51 CAD DW/ TORUS O2 CONC. i i i
1 YptONT TANE.EE NUCLEAR KWF.R STAT 10N Rev.0 2HERGENCT RESl9NSE FRIFAREDNESS EXERCISE PaSe 8.0-3 1991 8.0 OPERATIONAL DATA 04:00 04:1$ 04:30 04:45 0$200 05:1$ C5:30 0$t4S SCENARIO TIME click TIME 11:00 11:15 11:30 11:45 12:00 12:1$ 12:30 11:45 IftSTR . ITD4 FANEL to DtSCR1FTION UNITS 0 0 0 0 0 0 GlH 0 0 1 93 FT 23*108 1 EfC1 FLCW 6368 6366 6366 6746 6746 CfH 6368 6368 6368 8 9-3 F1-10-139A R!fR A FLOW 6497 6838 6838 GIH 6497 6497 8407 6497 6497 3 9-3 F1-10 1395 RER S FLOW 0 10 10 CIH 10 10 10 10 10 4 03 F1-14 50A CS A FLOW 10 10 GiH 10 10 10 10 10 9 9 9-3 F1-14*S08 CS B Fl4M 23 22 FSIA 18 18 18 18 18 23 6 0-S F1 16 19 12 DRYWELL PRFSS 22 18 18 18 18 23 23 7 9-3 F1-16 19 12 DR1'WELL FRESS FSIA 18 0 0 0 0 0 0 0 8 9*4 F1 13-91 RCIC F1/W GIH 0 0 0 0 0 0 0 9 94 F1 12 141A RWCU ILOW GM 0 0 0 0 0 0 0 0 ofH 0 0 10 04 F1 12-1419 RWCU FLIW 456 467 400 403 DEG F 447 488 513 483 11 0-4 2 16SA EX COOLANT TDir 403 447 488 513 483 456 467 400 18 9-4 2 1ESB RX N TANT TDtP DTG F 0 0 0 0 0 0 0 2 1$9A RECIRC A LOOP FLOW KGIN 0 13 94 0 0 0 0 KSfH 0 0 0 0 14 94 2*1506 RICIRC B LOOP FL(W 0 0 0 0 0 0 0 7 46A AFRM/1RM A 1 0 15 9-S 0 0 0 0 1 0 0 0 0 16 9-5 7 469 APRM/IRM B 0 0 0 0 0 0 0 0 A WM/IEN C 1 17 9-3 7 46C 0 0 0 0 1 0 0 0 0 18 95 7*46D APRM/1RM D 0 0 0 0 0 0 0 0 APRM/1kN E 1 19 9-5 7*46E 0 0 0 0 1 0 0 0 0 80 9-S 7-46f APRM/1RM F 21 9-3 7 43A $RM A CPS 4.27E*01 2.21E+01 1.69E+01 1.24E+01 1.2SE*01 1.16t+01 1.16E+01 1.18E+00 ( i 82 0-S 7-43B SRM B CPS 4.24t+01 2.16t+01 1.64E+01 1.20F+01 1.21E+01 1.13f+01 1.11E+01 1.13F+00 T3 9-S 7 43C DHC CPS 3.32E+ 01 1.73E+01 1.3SE*01 1.22E+01 1.23E+01 1.1SE+01 1.13E+01 1.15E+00 24 0-5 7*43D ERM D CPS 3.40!+01 2.19E+01 1.3SE+01 1. 217.+ 01 1.22E*01 1.1SE+01 1.13r+01 1.15t+00 1 1 1 1 3 2 1 8S 9-5 2*3-95 CORE FLOW HLB /IIR 1 3 3 3 7 3 3 3 FSID 3 86 9-S 2395 CORE DP 0 0 CRD FliM GM 35.5 35.5 35.5 45.1 0 0 57 9-S F1-3-310 688 409 294 200 FS10 702 901 688 916 28 9-5 6-96 WIDE RAN3E PRESS 950 950 950 950 950 950 950 950 39 9-S 6-06 RAR RANGE FRESS FSIG 0 0 0 0 0 0 0.1 0.1 30 0-5 6-97 FEEDWATER FLOW MLB/HR
- 0 0 0 0 0 0 9-S 6-97 MAIN STEAM FLOW ML2/HR 0 31 157 156 INCHES 86 98 11$ 145 175 164 32 9-5 f-98 NAR RANGE LFVEL 68 98 115 145 175 164 157 156 33 9-S 6-98 WIDE RANGE LEVEL INCHES 44 44 43 42 42 41 40 1 44 34 9-6 L1-107 $ CST LEVEL
$$ 34 1 56 $4 S4 S4 $4 SS 35 9-6 L1-102 SA BCTWELL LEVEL N 53 SS $5 54 1 SS 54 Se $3 36 9-6 L1 102 SE HOTWELL LEVEL 8 30 CONDUSER VACVJM IN BG 29 8 2 29.9 29.9 29.9 30 30 37 9-7 F1-101 29 OPEN OPEN OPEN OPEN OPEN OPEN OPEN OPEN 38 9-8 D/O A BKR orLN Orp orp Oru OrLN OPEN OFD OPEN 39 98 D/G B BKR 136 135 13S 133 137 140 139 00 0-23 16 19-33A/C TORUS T!MP Dto F 139 FEET 0.99 1.03 1.06 1.08 1.11 1.38 1.44 1.34 41 9-25 L1*46A TC8tUS LEVEL 1.11 1.38 1,44 1.34 FEET 0.00 1.03 1.06 1.08 42 9-25 L1 46B TORUS LEVEL 20.5- 20.6 20.6 FSIA 18.6 18.2 18 18.1 17.9 43 9-23 TR-16-19*44 TORUS FFISS 18 23 23 22 FSIA 18 18 18 18 44 0-25 TR-16-19-44 DRYWELL PRESS 2.66 1.$4 FSID -0.21 0.2 0.35 0.32 0.49 2.58 45 9-23 FR-1 156-3 DW/ TORUS DP 106- 154 IS4 140 DEG F 107 107 107 106 46 9-25 TR-16 19 45 DRYWELL TEMP -0.68 -0.68 IN E20 -0.68 -0.68 -0.68 -0.68 -0.68 -0.68 47 9-26 F1-1-12S-3A RX BUILDING DF -0.68 -0.68 -0.68 -0.68 48 9-26 P1-1-125-3B RX BUILDING DP IN 820 -0.68 -0.68 -0.88 -0.68 1500 1500 1500 1500 1500 1500 1500 49 9 26 F1 1-125-1A SGTS FLCM CTM 1500 1500 1500 1500 1500 1500 1500 1500 50 9-26 F1-1 125-19 SOTS FLOW C1H 1500 I 2,51 2.51 2.31 2,$1 2.31 2.2 2.78 2.21 31 CAD DW/ TORUS 02 CONO.
_ - -. .- _ _ .~ . _- VIMONT TAKKEE IrJCLEAR 19f13 STATION Rev.0 IHERGENCY RESKSSE 1%EFAREDNTES 2:EIRC15E FaSe 8.0 4 f 1991 8.0 CPEAATIORAL DATA SCERARIO TIME 06:00 06:15 06:30 06;45 07:00 07:15 07:JO 07:45 INSTR. C10CK TIME 13:00 13:15 13:30 13:45 14:00 14:15 14:30 14 45 17tN FANEL ID DESCRIPT!DN tfMITS GIN 0 0 0 0 0 0 0 0 1 93 FT-23-108 1 EFCI FLOW 9-3 F1 10 139A RHR A F11W OfH 218 6746 6744 6746 6746 6746 6746 6746 2 GlH 213 6874 6883 6838 6838 6838 6838 6838 3 9-3 FI+10-1398 Rf!P 8 FLOW CS A FlfW GIH 10 81 123 118 104 10 10 10 4 0-3 F1-14 $0A CS B T1IM GfM 10 81 123 118 104 10 10 10 9 9-3 F1 14*$0B 6 93 F1-16-19-12 DRYWTLt. PRrtS PSIA 22 20 20 20 20 20 20 20 PSIA 22 20 20 20 20 20 20 20 7 93 Fl*16-19-12 DRfWELL 1%E53 8 94 F1 13-81 RCIC F1IW CIH 0 0 0 0 0 0 0 0 OIN 0 0 0 0 0 0 0 0 9 9** F1 141A kWCU T14W CIH 0 0 0 0 0 0 0 0 10 9-4 F1-12 141B RWCU FIIW 11 94 2-16SA RX COOLANT TDiP DEG F 363 288 2S1 243 242 251 251 251 9-4 2*1638 RX COO 1 ANT TDiP Dr.G F 363 288 2$1 243 242 2$1 251 251 12 LGIN 0 0 0 0 0 0 0 0 13 9-4 2 159A REC 1hC A LOOP 114M EGlH 0 0 0 0 0 0 0 0 14 9-4 2 159B RfCIRC 81 TOP FirW AfhM/IhM A 0 0 0 0 0 0 0 0 13 9-5 7-46A 3 0 0 0 0 0 0 0 0 18 9-S 7*46B APRM/TRM P 1 0 0 0 0 0 0 0 17 9S 7 40C AFRM/1kM C 3 0 0 0 0 0 0 0 0 0 18 9-S 7 46D APRM/fRM D ! O O O O O O 19 9-5 7-46E ArhM/1RM E I O O E O O 0 0 0 80 9-5 7-afF APP.M/IRM F I O O r 31 9S 7-43A ERM A CPB 1.10E+01 1.01E*01 1.07E+01 1.0t.E*01 1.06t+01 1.21E*01 1.21E+01 1.21E*01 22 95 7 43B EkM B Cis 1 06F*01 1 03t*01 1.03t+01 1.02f*01 1.02E+0! 1,17f*01 1,1?E+01 1.17T+01 b 83 9-3 7-43C ERM C CF5 1.00E*01 1.0SE*01 1.04E+01 1.04E*01 1.04E*01 1.181+03 1.18E*01 1.161+01 24 9-S 7-43D ERM D CPS 1.07t+01 1. 0 4 f +01 1,0414 01 1.04F+01 1 04F+01 1.1hF*01 1.16t+01 1.18t401 9-S 2 3*SS CEE 114M MLBIHk 2 1 1 2 0 1 1 1 SS PSfD 3 3 3 3 3 3 3 26 9-5 2-3-95 CORE DP 3 GiH 0 n 0 0 0 0 0 27 9-5 F1 3 310 ChD F14M C PS10 97 37 21 19 19 43 43 43 28 9-S 6-96 WIDE RANGE PRFSS FEIG 950 CSD 950 950 950 950 950 930 89 9-3 6-96 NAR kANGE 1%E58 HLB /PR 0,$ 0 0 0 0 0 0 0 30 0-S 6-97 FttDWATER TLrW MLB/HR 0.2 0.1 0 0 0 0 0 0 31 9*3 6-97 MAIN ST*'AM
. FLOW NAR RANGr ITVII. INCHtt 156 1 57 168 100 205 106 196 196 32 9*S 6-98 6-98 WIDE MANGE LEVEL INCHES 156 157 160 190 20$ 196 196 196 33 9+$
CST trVEL 40 38 38 37 36 36 36 36 34 06 L1-107 S I S3 54 $4 S4 54 54 54 54 35 9-6 L1 102-SA BOTWELL LEVEL M I 53 54 54 54 Se $4 S4 $4 36 96 L1 102-56 fl0TWELL LTVEL 8 3 IN BG 29.9 30 30 30 30 30 30 30 37 97 F1-101-29 CONDD 5ER VACUUM OPEN OPEN OPEN 01TN 07TN OPT N OPTN OPEH 34 9-8 D/G A 20 68 D/G B BKk OFD Ort.N 000 OPU Orf.M OPD DPD OPEN 39 D00 F 138 138 134 110 127 12S 123 123 40 0-23 16-19 33A /C TORUS T!HP 41 0 25 LI-46A TORUS LEVEL TEET 1,39 1.24 1.18 1.14 1.14 1.16 1.16 1.16 62 0-2S L1 46P TORUS LFVII. Ftr7 1 39 1.24 1.18 1.14 1.14 1.16 1.16 1.16~ 43 6-23 TR*16-19*44 TCRUS IRESS FS!A 20.6 20.6 20 19.5 19.1 18,7 18.7 1{7 PSIA 22 20 20 20 20 20 20 20 44 9-25 TR-16-19-44 DRYWELL PRFES OS 9-25 Pk-1-156 3 DW/ TORUS DP PSID 1.66 -0.34 0.1 0.47 1.02 1.S8 1.58 1.58 Dtc F 140 136 137 133 137 159 130 139 66 9-25 TR-16-19-4 5 DRYWE1.L TTMP 47 9-26 F1-1 125-3A RE SUILDING DF 1R R2O -0.68 -0.68 -0.68 -0.68 -0.68 0.68 -0.66 -0.68 68 9-26 P!-1 125-3P RX BUILDING OP IN R20 -0.86 0.68 -0.68 -0.68 -0,68 -0 68 -0 68 0.68 1500 1500 1500 1500 1500 1500 1500 1500 49 9-26 F1-1-125-1A SGT5 FLOW CFM SC 9 2r FI 1-125-1B SGTS FLOW CfH 1500 1500 1500 1500 1%00 15 0'. , , ! SOS 1500 CAD IM/ TORUS 02 CONO. I 2,22 2,35 2.38 2.36 2.39 2.34 $ 39 2.39 31
VERMONT TANKEE FJCLEAR POWER BfATION R v. O IlHERGENCY RI$10NSE 15EFAREDNESS EKERC15E Ps8e 9.0-S 1991
.0 OPERATIOKAL DATA SC?JLARIO TIME 08:00 08:15 08:30 INSTR. CLOCK TIME 15:00 15:15 15:30 ffEM PANEL ID DESCR!rTION UNITS 1 0-3 FT 23 106-1 BPCI FLOW GM 0 0 0 2 93 Fl=10 139A RER A TLW OfN 6746 8746 6746 3 9-3 F1 10-1398 RER 8 FLOW Om 6838 6838 6834 4 93 F1-14-$0A C8 A FLN CIH 10 10 to S 9-3 FI 14*SDB C5 5 FLAM GM 10 10 10 6 9-3 FI-16-19-12 DRYWELL l'PJ25 l'SI A 20 to to 7 93 F1-16 10-12 DRTWELL 11(185 PSIA 20 20 20 8 94 F1 13-91 RCIC FIN Om 0 0 0 0 94 Fl*12 141A RCU F10W GM 0 0 0 10 9-4 FI*12-141B RCU FLOW ofH 0 0 0 11 0-4 2-16SA RX COOLANT T1MP DT.0 F 251 251 251 12 94 2-1tSB RN COOLANT TEMP Dto F 251 251 251 13 94 2 159A RECIRC A LOOP ITN KGIN 0 0 0 14 0-4 2-159B RICTRC B LOOP FL W EGtH - 0 0 0 1S 9-S 7-46A APRM/1RM A 1 0 0 0 16 9-S 7-4CB APRM/fkM P 1 0 0 0 9-S 7-46C APRM/IRM C 1 O 0 0 17 18 9S 7-40D APRM/TRM D 3 0 0 0 19 9-S 7-46E APRM/IRM E I O O 0 20 0S 7-4tF APRM/IP.H F t 0 0 0 f 21 9-S 7 43A SRM A CPS 1.21E+01 1.21E+01 1.21t + 01 , 22 9S 7-432 ERM B CPS 1.17F401 1.17f+01 1.17E+01 23 9S 7 43C ERM C CP3 1.18t+01 1.18E+01 1.181+01 24 9-S 7 43D ERM D CPS 1.18t+01 1.18F+01 1.18t+01 9-5 1-3-95 CORE FIAM MLB/HR 1 1 1 25 9-S 2-3 95 COFJ DP PSID 3 3 3 26 27 9-5 TI-3 310 CRD FLOW CM 0 0 0 26 9-S 6-96 WIDE RANGE PRESS PS10 43 43 43 29 9-S 6-96 RAR RANGE PRESS PSIG 950 950 950 30 0-5 6-97 FEfDWATER TLN K P/ER 0 0 0 31 9-S 6-97 MAIN STIAM FIN MLE/BM 0 0 0 32 9-S 6-98 BAR RANGE LEVTL INCHTS 196 196 196 33 05 6 98 WIDE RANGT LEVEL INCHES 196 196 196 34 0-6 L1 107-S CST LEVEL 2 36 36 36 35 9-6 L1-102-SA BOTWELL LEVEL M I S4 S4 S4 36 t7-j " %* 2 Se $4 S4
- 9. A. _
. N Lt L_EVEL 5 37 9-7 Fl*101 29 CONDENSER h"UUM IN BG 30 30 30 38 9-8 D/0 A BER OPEN OPEN OFTN 39 98 D/0 2 BER OPEN OPEN OPEN 40 0-23 16-19-33A/C TORUS TEMP DEO F 123 123 122 41 9-23 L1-46A TURUS LEYEL FEIT 1.16 1,16 1.16 42 0-2$ Lf 46B TORU! LfvrL FETT 1.16 1.16 1.16 43 9-25 TR-16-19 44 TC5tUS FRESS PSIA 18.7 18.7 18.7 44 0-25 TR-16-19-44 DRYWELL PRESS PSIA 20 to 20 45 9-25 FR-1-158-3 DW/ TORUS DP PSID 1.58 1.58 1.58 46 9 25 TR-16-10-45 DRYWEL1. TIMP DEG T 139 139 139 47 9-26 P1-1-125-3A RX BUILDING DP IN E20 -0.68 -0.66 0.66 48 9-26 PT-1-125-37 RX PUILDING DP IN E20 - 0 . f. 8 -0.f8 -0.fB 49 9-26 FI 1-125-1A SGTS FIN CIH 1$00 1500 1500 50 9 2f, F1-1-125-1B SGTS FLN Cm 1500 1500 1500
$1 CAD DW/70RUS O2 CONC, I 2.39 2.39 2.39
VERM0h"I YAhTEE NUCLEAR ID'JER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9,0 RADIOLOGICAL DATA f f
I ( e VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 ( 9,1 AREA RAPIATION MONITORS h 4 e,- -.,w . , ,-,u -3m',, .,e, ., ,r._, , - . . - - - - . . . , , . . . , . . - . - - . , .-..-..s-- - 4m., .~., . - . . , - - - . - # .-,-,... .
1 l i VERMONT YANKEE NUCLEAR POWER STATION Rev. 0 Page 9.1 1 EMERGENCY RESPONSE PREPAREDNESS EXERCISE d ( 1991 1 \ 1
)
9.1 AREA RADIATION MONITORS J i l 00:15 00:30 00:45 01:00 01:15 01:30 01:45 l SCENARIO flME 00:00 08:15 08:30 08:45
.i CLOCK flME 07:00 07:15 07:30 07:45 08:00 ~j
- ARM BLD0/
PANEL ELEV. DESCRIPfl0N UWlfS CO. q
<1 <1 <f <1 <1.............................
<1 41 41 kMS 11 1 9 11 RB/252 Rx BLDG Mi RADS
- N R/ht
<1 <1 <1 <1 <1
<1 <1 <1 RMS 1t*2 9 11 B8/252 Rx BLDG Mi RADS
- 5 R/HR
<1 <1 <1 <1 <1 <1 R/MR <1 <1 ? RMS 11 3 9 11 Rs/252 flP RM MI RAD a 8 8 8 8 8 8 8 8 ! 1 9 11 RS/232 $UPP CKAM8 RB ext C1J MR/HR 4 4 4 4 4 4 4 4
- 2 9 11 88/252 N pet $0NNEL RX SLDG MR/HR
) .3 .3 .3 .3 .3 .3 9 11 RB/252 S E0 VIP RR Rx BLDG MR/HR .3 .3 k 3 5 5 5 5 5 l S 5 5 1 6 9 11 RB/252 RX BLD NEUTRON TIP MR/NR i
570 560 550 530 510 5 70 570 9 5 9 11 Rs/252 PEttoNwfL MATCH Rx e MR/NR . 560 k 7 7 7 7 7 7 9 11 R8/280 ELEY EN1R 280FT pr e Ma/>R 7 7 .J- 6 i 12 12 12 12 12 12 11 11 7 9 11 RB/252 CRD REFAlt Rx BLDG MR/HR 4 4 4 4 4 4 4 4
, 8 9 11 RB/303 ELEV EN1R 303FT 8x 8 MR/MR 2 4 4 4 4 4 4 4 4 9 9 11 R8/303 H2O CLEANUP RX BLDG MB/NR
\ 7 7 7 7 7 7 7 7 y 10 9-11 88/318 ELEV ENTR 31871 RX t MR/ha 5 5 5 5 4 5 5 5 11 9 11 88/318 H2O CLEANUP RX BLDG MR/nt
$ 5 5 4 4 5 5 5 12 9 11 88/345 ELEV ENTR 348FT RX B MR/MR 5 5 5 5 5 5 5 l.
14 9 11 RS/345 WEST REFUEL Rx sLDG mR/ht 5 16 16 16 16 16 16 17 l 15 9 11 RS/345 SPENT FUEL Po3L Rx e :R/nR 16 48 48 48 .47 47 46 48 3 16 9 11 RS/318 WEW FUEL VAULT Rx B MR/NR 48 1 1 1 1 1 1 1 i 4 17 9 11 RW/252 PUMP RM R ADWA$tt SLD MR/NR 1 1 1 1
.1 1 1 1 1 18 9 11 RW/252 RADW OPER AREA RW s MR/HR h 2 2 2 2 2 2 2 2 5 19 9 11 RW/230 PUMP /TAWK AREA RW 8 MR/HR
's 2 2 2 2 2 2 2 2 20 9 11 15/248 W ACCESS 248FT Tuts MR/hR 200 195 190 180 180
- 01) 18/2(8 MAlW STM VALyt Tute kR/kR 200 200 200
., 21
.3 .3 .3 .3 .3 .3 .3 9 11 18/232 CoWD DEMlW TURS SLDG MR/NR .3 22
.2 .2 .2 .2 .2 .2 9 11 18/252 DECON/ MACH SMOP 18 MR/HR .2 .2 23 g 9 9 9 9 9 9 9 9
24 9 11 18/272 TURS stM IN TURS BLD MR/HR
.8 .8 .8 .8 .8 .8 .7 25 9 11 AS/272 view CALLERY COW 1 RM MR/MR .8
$ .15 .15
.17 .17 .17 .17 .16 .16 26 9 11 18/252 REAR Calf TURB WAREM MR/kR 150 150 140 140 130 150 150 13 9 11 18/228 Molst SEP ARE A TURB MR/HR 150
VERMONT YANKEE NUCLEAR POWER STATION Rev. O Page 9.1 2 EMERCENCY RESPONSE PREPAREDNESS EXERCISE {- 1991 9.1 AREA RADIATION MONITORS SCthAR10 TIME 02:00 02:15 02:30 02:45 03:00 CLOCK flMt 09:00 09:15 09:30 09:45 10:00 ARM SLOG / Wo. PAktL ELIV. Dt$CtlPfl0N UW11$
.............................................................................................+..
41 <1 <1 <1 <1 RCS 11 1 9 11 R8/252 Rx BLDG M1 RAos . W t/>R
<1 *1 <1 *1 *1 RMS 11 2 9 11 RS/252 Rx BLDG M1 RAD $ * $ t/Mt t/NR 41 41 41 si el RCS 11 3 9 11 88/252 flP RM N1 RAD 8 8 8 8 8 1 9 11 ts/232 $UPP CMAMS 88 EXT CV Mt/NR 4 4 4 4 3 3 9 11 RB/252 N Pit $0hhtL 8x BLDG MA/NR
.3 .3 .3 .3 .3 3 9 11 88/252 $ 10 VIP Rt RX sLDG Mt/NR 5 5 5 $ $
6 9 11 88/252 RX BLD NEUIRON 11P Mt/WA 480 460 440 430
$ 9 11 RS/252 Ptt$0hhtL MATCH Ax 8 MR/Mt 500 7 7 7 6 9 11 88/280 ELEV twit 280Ff px a Mt/et 7 7 9 11 88/252 Cap ttPAlt Rx stDG Mt/HR 11 11 to 10 10 7
4 4 3 3 3 8 9 11 25/303 ELEV twit 303FT RX 8 Mt/HR 4 4 4 4 4
;! 9 9 11 88/303 M20 CLEANUP Rx SLDG Mt/N4 1
6 6 6 6 6 10 9 11 ts/318 ELEV twit 31871 Rx e Mt/HR 4 4 4 4 4 11 9 11 RB/318 M20 CLEANUP tz SLDG Mt/kt 4 4 4 12 9 11 R8/345 Etty thit 348FT tx s kt/>R 4 4 i 4 4 4 4 4 l 14 9 11 RS/345 Vtst Strutt ax sLDG Mt/HR 15 15 15 14 15 9 11 ts/345 $Pthi FutL POOL R1 B MR/Mt 15 46 .45 45 44 16 9 11 28/318 htV FutL VAULT RX 8 MR/HR 46 1 1 1 1 1
; 17 9 11 RW/252 PUMP RM RADWA$1t SLD Mt/NR 1 1 18 9 11 kW/252 RADW Opte AttA tw a Mt/HR 1 1 1 2 2 2 2 2 19 9 11 kW/230 PUMP /1AWK AttA RW 8 ME/NR
)*
9 11 18/248 W ACCESS 248FT TURS Mt/ht 2 2 2 2 2 20 1 170 160 160 150 21 9 11 TS/248 MAIN STM VALVE tutB Mk/NR 170
.2 .2 .2 .2 .2 22 9 11 18/232 COND DtMIN futs stDG kt/HR
.2 .2 .2 .2 .2 23 9 11 18/252 DECONTAM. TURS BLOG ht/HR 9 8 8 8 8 j 24 9 11 18/272 TUR8 STM IN TURS BLO Mt/Mt 1
.7 .7 7 .7 .6 9 11 AB/272 VitV GALLtti cont RM MA/et 25
.14 .14 14 13 .13 i 26 9 11 TB/252 atAR GATE TURB WAttM Mt/HR 120 120 110 110 13 9 11 TB/228 Molti stP Att A tuts ut/NR 130
VERMONT YANY.EE NUCLEAR POWER STATION Rev. 0 Page 9.1-3 EMERGENCY RESPONSE PREPAREDNESS EXERCISE ( 1991 9.1 APIA RADIATION MONITORS 03:30 03:45 04:00 04:15 04:30 04:45 05:00 SCthAtto ilmt 03:15 11:45 12:00 Ct0CK TIME 10:15 10:30 10:45 11:00 11:15 11:30 ARM BLDG /
- 00. FAWEL ELEV. DISCRIPTION UWils
<1 <1 <1 <1 <1 <1 <1 <1 RMs 11 1 9 11 RS/252 Rx BLDG HI kADS . k R/HR
<1 <1 <1 <1 <1
<1 <1 <1 RMs II.2 9 11 RS/252 Rx sLDG HI RADS . s R/HR s1 <1 <1 <1 <1 <1 R/NR <1 <1 RMS 11 3 9 11 RS/252 flP RM HI RAD 8 10 100 500 it3 SE3 (OsM ult 4 (OsH)>114 1 9 11 RB/232 $UFP CHAMS R8 LIT CW MR/HR 6 7 8 9 10 9 4 6 2 9 11 RS/252 N Pf R$0NhtL RX BLDG MR/HR
.3 .3 .3 4 4 4 0.4 3 9 11 RS/252 s toute RR Rx BLDG MR/kt .3 5 6 6 6 6 6 5 5 4 9 11 Rs/252 Rx BLD htutRON 11P MR/PR 720 &30 880 1100 1200 1300 (OsH) sit 4 5 9 11 R8/252 PtR$0khrt HATCH Rx B MR/HR 510 5 5 5 5 5 9 11 Rg/280 ELEV thtt 280FT RX B MR/HR 7 5 5 6
16 17 19 22 22 22 11 14 7 9 11 RE/252 CRD REPAlt Rx BLDG MR/HR 6 7 7 8 7 4 5 5 8 9 11 Rs/303 ELiv EW1R 303FT Rx s MR/HR 5 5 5 5 5 9-11 RS/303 H2O CLEAkup Rx BLDC MR/bt 4 5 5 9 9 9 10 11 11 11 9 11 R8/318 ELtv thTR 318FT Rx : MR/HR 7 8 10 3 3 3 3 3 3 4 2 11 9 11 RS/318 H2O CLEANUP Rx BLDG MR/HR 6 7 8 9 9 9 4 6 12 9 11 Rs/345 ELEV ENTR 34&FT Rx $ MR/HR 7 7 8 9 9 9 5 6 [ 14 9 11 R8/345 wtst Rtrutt Rx sLDc MR/HR 19 20 21 24 26 27 26 15 9 11 RS/345 SPthi Futt Poot Rx $ MR/HR 16 46 .52 .54 .56 .60 .64 .65 0.64 16 9 11 R8/318 htW Futt \ AULT Ax e MR/HR 1 1 1 1 1 1 1 1 17 9 11 RW/252 PUMP RM RADwASTt SLD MR/HR 1 1 1 1 1 1 1 1 18 9 11 RW/252 RADW OPER ARIA RW B MA/HR 2 2 2 2 2 2 9 11 RW/230 PLMP/T Aht AREA RW 8 MR/HR 2 2
. 19 1 1 1 1 1 2 1 1 20 9 11 18/248 W ACCtss 248FT TURB MA/HR 4 4 4 4 4 4 4
21 9 11 T8/248 MAIN stM VAlvt TURB MR/HR 170
.t .1 1 .1 1 0.1 22 9 11 18/232 COND DEMIN futs BLDC MR/HR .2 1
.2 .2 .2 .2 .2 .2 .2 0.2 23 9 11 1s/252 DECOM/ MACH Shop 18 ke/HR 7 7 7 7 7 7 7 24 9 11 18/272 Tuts sTM IN TUR6 BLD MR/NR 9
.1 .1 1 1 .1 0.1 25 9 11 AB/272 VitW CAtttRY CONT RM MR/HR .7 1 l 01 .01 .01 0.01 15 .01 .01 01 26 9 11 18/252 REAR CATE TURB WAttu MR/HR 1 1 1 1 1 1
13 9 11 T8/228 Holst stP ARIA tuRs MR/ A 130 1
_ . _ _ _ _ _ __ _ ~ - - _. _ _ _ _ - . _ _ __ . . _ _ _ m ._ Rev. O VERMONT YANKEE NUCLEAR POWER STATION Page 9.1 4 f- EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.1 AREA RADIATION MONITORS 01:45 06:00 06:15 06:30 06:45 07:00
$CENatlo timt 05:15 05:30 14:00 12:30 12:45 13:00 13:15 13:30 13:45 CLOCK TIME 12:15 ARM BLDG /
PANtL ELiv. Dt$CRIPfl0W UN115 NO.
<1 <1 *1 1000 2000 2000 2000 2000 RM$ 11 1 9 11 RS/252 RX BLDG HI RADS . N R/HR '
<1 1000 2000 2000 2000 2000
*1 <1 I RM$ 11 2 9 11 88/252 RX BLDG Mi RAD $ . 8 R/hR I <1 1000 2000 2000 2000 2000
<1 <1 RM$ 113 9 11 38/252 11P RM MI RAD t/HR (0$N) (O$N) (0$N) (0$N) (DSM) (0$N) 9 11 RS/232 $UPP CKAM8 Rs (XT CW MR/Hk (0$N)>1E4 (OSM) 1 500 (0$H)>1t3 'o$N) (0$H) (0$N) (0$N) 100 100 j 3 9 11 RS/252 W PitschhtL ex BLDG MR/HR 4 4 (0$N)>1E4 (0$N) (0$N) (OtN) (CSN) 4 3 9 11 at/252 5 t00lP tR Rx $(DG MR/HR i 6 6 (0$H)>1E4 (0$H) (0$H) (OSM) (0$N) 9 11 98/252 tx SLO NEUlt0N flP MR/HR 6 6
(0$N) (0$N) (0$N) (0$N) (OSM) (DSM) (0$N) j $ 9 11 R8/252 PitschhtL HAICH ex $ MR/HR (DSM)
$ 5 (O$N)*i[4 (0$N) (0$N) (0$N) (0$N) 9 11 88/280 f tty (NTR 280FT tz R MR/HR 5 6
24 24 (0$N)>1[4 f0$M) (0$H) (0$N) (0$N) 9 11 88/2$2 CBD AtPAlt Rx 8LDG MR/HR 23 7 8 $ (0$H)>1E 4 (DSM) (0$H) (0$N) (0$N) 9 11 88/303 (Liv ENTR 303FT ex s Ma/HR 8 8 5 (0$h)>114 (0$N) (OSH) (0$N) (0$N) 5 5
- 9 9 11 RB/?O3 N20 CLEAhuP Ar BLDG MR/HR 12 (0$N)>1t4 (0$N) (0$N) (OSH) (DSM) 12 12 10 9 11 28/318 f(tv thtR 31871 ex 8 Mf/HR 7'(0$N)>1t4 (0$N) (0$N) (0$N) (0$n) 3 3 11 9 11 88/318 H2O CLEANUP ax etDG MR/NR 10 10 (0$N)>1t4 (0$M) (0$H) (OSM) (0$N) 9 1 12 9 11 LB/345 (Ltv ENTR 348Fi nx s Ma/HR 10 10 10 2t5 415 4t5 415 4E5 14 9 11 as/345 WEST atfutt as SLOG MR/HR 28 29 (0$N)>1t4 (0$N) (0$N) (0$N) (0$M) 9 11 RB/345 $ PENT FUtl POOL Rx 8 MR/HR 28 15
.67 .68 (0$N)>1t2 to$N) (0$H) (0$N) (0$N) 16 9 11 R8/318 htW FutL VAULT ax s MR/HR .67 1 1 i i 1 1 1 1 17 9 11 RW/252 PUMP RM RADWA$1t SLD MR/HR 4 1 1 1 1 1 1 1 1 18 9 11 RW/252 RADW OPER AttA nW e MR/Ha l
2 2 2 2 2 2 2 2 19 9 11 kW/230 PUMP /TAhE AREA RW B MR/HR 4 1 1 1 1 1 1 1 1
', 20 9 11 75/248 N ACCESS 248rt TURS MR/HR
.' 4 4 4 4 4 4 4 4 f 21 9 11 78/248 KAIN $tM VALVE tutt MR/MR 1 .i 1 .1 .1 .1 .1 1
22 9 11 18/232 CohD DtMIN TURB SLDG MR/MR j .2 .2
.2 .2 .2 .2 .2 .2 j 23 9 11 ts/252 DECON/xACu Saon is MR/HR 7 7 7 7 7 7 7 7 24 9 11 TB/272 TURS STM IN tuas SLD MR/HR
.1 .1 .1 .i 1 .1
$ 9 11 AB/272 VltW GALLERY Cohi eM MR/HR .
.1 l 25 1 .01 .01 .01 .01 .01 .01 -
.01 .01 l
26 9 11 TB/252 atAR CAtt tuRU WARtH MR/FR ! 1 1 1 1 1 1 1 1 13 9 11 18/228 M0!$t $tP AttA TURS NR/HR
VERMONT YANKEE NUCLEAR POWER STATION Rev. 0 Pag,e 9.1 5 EMERGENCY RESPONSE PREPAREDNESS EXER 0ISE ( 1991 9,1 AREA RADIATION MONITORS i 6F 15 07:30 07:45 D8:00 08:15 08:30
$cthAtl0 flME 15:D0 15:15 15:30 CLOCA 11Mt 14:15 14:30 14:45 ARM $ LOG /
PAktL ELEV. DESCRIPfl0N UNITS No. 2000 2000 1500 1500 1540 1000 AMS 11 1 9 11 RS/252 RX BLDG HI LADS . W t/HR 2000 1500 1500 1500 1000 2000 RCs 11 2 9 11 as/252 er BLOG HI RADS . $ R/He 2D00 1500 1500 1500 1000 t/HR 2000 RMS 113 9 11 RS/252 fir RM HI RAD (osH) (osH) (OsH) (osH) (osH) (OSH) 1 9 11 48/232 suPP CHAMB RB EXT CW ME/HR (0$H) (DSM) (05H) (OSN) (0$H) 9-11 88/252 N PitLONhtL Ex BLDG MR/HR (D$H) 3 (05H) (0$N) (Q$H) (Q$N) (DSM) 9 11 88/252 $ EDUIP tt RX BLDG ME/NR (0$N) 3 , (OsH) (osH) *0$N) (05H) (05H) 9 11 RB/252 Ex DLD htuitDN TIP MR/HR (05H) , 6 (0$N) (D$H) (DSM) (05H) (0$H) 9 11 88/230 PttE0hWIL HATCH Rx 0 MR/HR (0$N) 5 (D$N ) (O$N) (D$N) (D$H) (OsH) (05H) 6 9 11 t8/280 EltV (Wta 260F1 Rx e MR/HR (OSM) (0$H) (0$H) (OSN) 9 11 28/252 Cao atPAlt er BLOG MR/NR (05H) (OSM) 7 (O$N) (DSM) (O$H) (DSN) (OSN) 9 11 88/303 EttV EWit 303FT RX B MR/HR (0$H) . 8 (0$N) (DSN) (D$N) (OSH) 9 11 28/303 k20 CLEAWUP Ex SLDG MR/HR (D$H) (05N) 9 (OSM) (O$N) (OSN) (0$N) (DSM) 10 9 11 ts/318 Etty thit 31871 as e MR/HR (0$N) (OsH) - (OsH) (05H) (0$N) (D$H)
-9 11 ts/303 H2O CitAwup ax SLOG MR/HR (OsH) 11 (05H) (OSM) (Osu) (0$H) (osH) 12 9 11 28/345 ELfy thTR 34BFT ex MR/NR (OSH) 4t$ 4E5 3t5 3t$ 3E5 2t5 14 9 11 88/345 WEST REFUtl ax BLOG MR/HR (OSM) (OSN) (Q$N) (0$H) (0$H) 9 11 RB/345 $ PENT FutL POOL tr 8 MR/HP (OSH) 15 (OSM) (OSH) (OSM) (0$H) (OSM) 9 11 28/318 htW FUEL VAULT tr 8 MR/HR (0$H) 16 1 1 1 1 1 1 17 9-11 RW/252 PUMP RM RADWAsit BLO MR/HR 1 1 1 1 1 1 18 9 11 kW/252 RADW ortt ARIA tw a MR/HR 2 2 2 2 2 2
19 9-11 RW/230 PUMP /1Ahr AREA RW B MR/HR 1 1 1 1 1 1 20 9 11 T5/248 N ACCT &5 248FT TURS MR/HR 4 4 4 4 4 4 21 9 11 18/248 KAlk $1M VALVI TURB MR/HR
.1 .1 .1 .1 .1 1 22 9 11 Ts/232 COMO Dtmlw tuas SLOG MR/NR
.2 .2 .2 .2 .2 9-11 18/252 ctCON/ MACH SHOP is MR/Ha .2 23 7 7 7 7 7 7
24 9 11 T8/272 TUR8 STM la Tuts 6LD MR/HR
.1 .1 .1 .1 9 11 AS/272 VIEW CALLERT CONT eM MR/HR .1 .i g 25
.01 .01 .01 .01 .01 9 11 78/252 REAR GAtt TURS WAREN MR/HR .01 26 1 1 1 1 1 1 13 9 11 18/228 M015Y StP AREA TURB MR/HR
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( ! VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE > 1991 9.2 PROCESS MONITORS
VERMONT YANKEE NUCLEAR POWER STATION Rev. 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 9.2 1 [ 1991 g 9.2 PROCESS MONITORS 00:15 00:30 00:45 01:00 01:15 01:30 01:45 SCENARIO TIME 00:00 08:45 07:15 07:30 07:45 08:00 08:15 08:30 CLOCK flME 07:00 ARM BLOG/ PAhEL ELEY. DESCRIPil0N UNITS Wo. 150 150 150 150 150 150 150............... 150 92 STACs: GAS MON GA51 CPM 200 200 200 200 200 200 200 92 STACK CAS MON GAS 2 CPM 200 500 500 500 500 500 500 500 92 CONT AlkMEhi MON GAS CPM 500 25000 25000 25000 25000 24000 23000 22000 92 CONTA1WNENi McW Pati CPM 25000
.1 .1 .1 .1 .1 .1 .1 92 STACK Ml RANGE MR/MR .1 4 4 4 4 4 3 3 DR M LL CH A R/HR 4 2F 92 4 4 4 4 4 3 3 R/MR 4 28 92 DR WELL CM B 190 190 190 190 190 180 RX BLDG VENT CAS CPM 190 190 9-2 1540 1530 1520 1510 1480 1450 PAKI CPM 1530 1540 92 RX BLOG VENT 2 2 2 2 2 2 Rx ALDG VENT NORTM MR/HR 2 2 31 9 10 2 2 2 2 2 2 2 2 32 9 10 RX BLDG vtWT $0UTH MAJ MR 17 17 17 17 16 16 MR/MR 17 17 13A 9 10 $ PENT FUEL POOL A 17 17 17 17 16 16 17 17 4538 9 10 $ PEW 1 FUEL POOL B MR/HR 170 170 160 160 150 150 MAIN $1M LikE A MR/hR 170 170 9 10 170 170 160 160 150 150 MAIN SIM LlWE $ MR/HR 170 170 9 10 170 170 170 160 160 160 150 9 10 MAlW STM Likt C MR/NR 170 170 170 160 160 150 150 9 10 MAlW $1M LINE D MR/NR 170 170 250 250 250 250 240 240 240 38 9 10 SJAE(AIR EJECTOR) MR/NR 250
VERMONT YANKEE NUCLEAR POWER STATION Rev. 0 EMERCENCY RESPONSE PREPAREDNESS EXERCISE Page 9.2 2 1991
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9.2 PROCESS MONITORS SCENAtto flmt 02:00 02:15 02:30 02:45 03:00 CLoct Time 09:00 09:15 09:30 09:45 10:00 ARM BLOG/ PANEL ELLY.- DESCRIPfl0N - LINITS Wo. STACK gas McN gas 1 CPM 150 150 150 .150 150 92 STACK gat MON GAS 2 CPM 200 ' 200 200 200 200
.- 9 2 460= 440 430 400 400 92 CONTAINatNT MON GA$- CPM 20000 20000 19000 18000 9 2. CONTAINatNT le3N PART CPM 20000
.1 .1 .1 .1 .1 92 $ FACE M1 RANCE MR/HR 3 3 3 3 9*2 DRYWELL CH A - R/NR 3 27 3 3 3 3 3 28 92 DRYWELL CN 8 R/NR 180 180 170 170 170 92 RK BLDG YtNT GAS CPM 1400 1380 1350 1320 92 RX BLOG YE*1 PART CPM- 1430 2 2 2 2 2 31 9 10 - K2 BLDG YENT NORTH M/HR RX BLDG VENT $001N MR/NR 2 2 2 -2 2 g 32 9 10 15 15 15 14 5 .53A 9 10 $ PENT futL Pool A MA/NR 16 15 15 15 14 4538 9 10 $PtWT FUEL Pool B MR/HR 16 140 130 130 120 9 10 MAlu $1M LINE A MR/HR 140 140 130 130 120 9 10 MAIN $1M LINE s MR/MR 140 140 130 130 120 9 10 MAIN $1M LINE C MR/NR 140 140 130 130 120 9 10 ' MAIM 51M LINE D MR/MR 140 U0 230 220 220 38 9 10 $JAE(Alt EJECTC4t) MR/HR 240 l
L i t l l. I
VERMONT YANKEE NUCLEAR POWER STATION Rev. O EMERGENCY RESPONSE PREPAREDNESS EXERCISE Page 9.2 3 g 1991 9,2 PROCESS MONITORS 03:45 04:00 04:15 04:30 04:45 05:00 scthAtle TIME 03:15 03:30 10:45 11:00 11:15 11:30 11:45 12:00 Cloct 11ME 10:15 10:30 AR1 BLOC / PANEL ELiv. Dr$CRIPfl0N UWlf$ No. 150 150 150 150 150 150 150 150 92 STACC M 1 MON + GAS 1 CPM 200 200 200 200 200 200 200 200 92 StACC CAS MON.GA$ 2 CPM 460 420M 39000 36000 33000 31000 29000 O$N(*1t6) 92 CONTAlWHENT MON GAS CfH 39000 35000 43000 51000 57000 53000 otM(*1t6) 92 CONTAINMENT MON PAnf CPM 21000
.1 92 $fAtt HI RANGt MR/HR .1 .i .i .1 .1 1 .i 6 7 8 8 8 R/NR 3 6 5 27 92 DRYWELL CH A 6 7 8 8 8 R/HR 3 6 5 28 92 DRYWELL CN 8 70 80 90 90 90 CPM 180 60 70 92 RK DLDG VENT CA$
560 640 700 720 690 1440 490 540 92 RK BLDG YtW1 . PARf CPM 1 1 1 1 1 1 Rx BLDG VENT NantM MR/Ha 2 1 31 9 10 2 i i i 1 1 1 1 12 9 10 RK BLOG VtWT 50U1H kR/H# y 13 14 15 14 16 10 11 11
.23A 9 10 stikT futL POOL A MR/HR 13 14 15 14 16 10 11 11 4536 9 10 $Pthf futL POOL B MR/HR 0 0 0 0 0 130 0 0 9 10 MIN stM LINE A MR/NR 0 0 0 0 0 Mt/Mt 130 0 0 9 10 min STM LINE 8 0 0 0 0 0 MR/kt 130 0 0 9 10 MIN SYM Likt C 0 0 0 0 0 MR/km 130 0 0 9 10 MIN STM LINF D 0 0 0 0 0 MR/NR 200 0 0 38 9 10 SJ AE( AIR (JECTOR) i 1
VERMONT YANKEE NUCLEAR POWER STATION Rev. 0 EMERCENCY RESPONSE PREPAREDNESS EXERCISE Page 9.2 4 (- 1991 9.2 IROCESS MONITORS SCENARIC TIME 05:15 05:30 05:45 06:00 06:15 06:30 06:45 07:00 CLott flME 12:15 12:30 12:45 13:00 13:15 13:30 13:45 14:00 ARQ BLDG / l CO. PANEL ELEV. DE$talP?!ON UNITS 150 150 O$M(>1E6) 0$N 0$N 0$N I 92 STACK GAS MON GAS 1 CPM 150 150 200 200 200 200 0$N(>1E6) 0$M OSM 0$N 92 $fACK GA$ MON GAS 2 CPM 0$M OSM 0$N 0$M OSM 0$N 0$M OSM 92 CONTAlkMENT MON GAS CPN 0$N 0$M 0$M OSM 0$M p(M 0$N 0$M 92 CONTAlWMENT MONaFART CPM
.1 .1 .1 .1 48000 78000 80000 80000 92 STA:C MI RAhCE MR/HR R/HR 20000 20000 18000 17000 16000 15000 15000 15000 29 9-2 DR M LL CM A 20000 18000 17000 16000 150(rb 15000 15000 28 92 DR M LL CM B R/HR 20000 90 100 100 0$N(>1E6) CSM OSM 0$M 0$M 92 RX BLDG VENT CAS CPM 750 770 780 0$N(>1E6) 0$M 0$N 0$N 0$N 92 RX BLOG vtNT . PART CPM 1 0$k(*1E3) 0$M 0$N OSM 0$N 31 9 10 Rx BLDG vthi h0RTM MR/HR 1 1 1 1 0$H(>1E3) OSM 0$M 0$N OSM 4 32 9 10 RX BLDG VENT $0JTM MR/NR 1 16 0$M(*iE4) 0$N 0$N 0$M 0$H i .$3A 9 10 $ PENT FutL Pool A MR/kR 15 16 15 16 16 0$N(*1E4) 0$N 0$N 0$N 0$H 653B 9 10 $ PENT FUEL PO3L B MR/ M.:
0 0 0 2E5 1E5 5ES SE5 18 9 10 MAIN STM LINE A MR/HR 0 0 0 2E5 1E5 5E5 5ES 20 9 10 MAIN STM LlhE B MR/HR 9 10 MAIN STN LINE C MR/HR 0 0 0 2E5 1E5 5E5 5t$ 18 0 0 0 2E5 1E5 SES SE5 18 9 10 MAIN STM LihE D MR/NR 0 0 0 0 0 0 0 0 ! 38 9 10 $JAE(AIR EJECTOR) HR/HR l l l l l
l VERMONT YANKEE NUC11.AR POWER STATION Rev. O EMERCENCY RESPONSE PREPAREDNESS EXERCISE Page 9.2 5 g \ 1991 9.2 PROCESS MONITORS ! sctkARIO 11Mt 07:15 07:30 07:45 08:00 08:15 08:30 CL0ct flME 14:15 14:30 14:45 15:00 15:15 15:30 ARM BLDG / Wo. PAktL ELEV. DESCRIPflCW UWl18 0$N OEM 0$N 0$N 0$M OSH 92 STACK GAS MON LAS 1 CPM OSH 054 0$N OSM 0$N OSN 92 STACK GAS MON GAS 2 CPM OGM OSH OGM O5M OSM 0$N 92 CONTAlWMINT MON CAS CPM 0$N OSM 0$N 0$N 0$N 0$N 92 CONTAl4 MENT MON PART CPM 70000 65600 62000 50000 45000 40000 92 sTAtt M1 RAuct Ma/Ma R/Mt 14000 13500 13000 12500 12000 12000 27 9-2 0tYWELL CH A R/Ha 14000 13500 13000 12500 12000 12000 28 92 DRYVELL CM t CPM 0$N OSM 0$M 0$N 0$N OSM 92 RX SLDG YtNT GAS OSH 0$M OSH 0$N 0$N 92 ex BLOG vthi PART CPM OSM 0$N OSM OSM (,$H 0$N 9 10 RE BLDG vtNT WORTM Mt/MR 0$H 31 . 0$N 0$N OSH OSH OSM 0$M 12 9 10 RX SLDG vthi SOUTM Mt/MR 0$N 0$N 0$N 0$N 0$N 0$N
.s3A 9 10 $PtWT futL POOL A km/Ma 0$N OSM 0$N 0$N 0$N 6538 9 10 S&fui futL POOL 8 MA/Ma OSP 1 1 1 1 1 9 10 MAIN $1M Llht A MR/Ha 1 1 1 1 1 1 9 10 MAIN $1M LINE B MR/HR 1 1 1 1 1 1 9 10 MAlk 51M Llht C MR/Ma 1 1 1 1 1 9 10 MAlh SIM Likt D MA/M8 1 1 0 0 0 0 0 0 38 9 10 $JAt(AIR tJECTOR) MR/Mt
VERMONT YANKEE NUCLi%R POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.3 IN. PLANT RADIATION LWEts 4
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" .m TABLE 9.3-1 Rev. O Page 9.3-la Reactor Building Refuel Deck, Elevation 345' (mR/hr unless otherwise noted)
Clock Scenario Time Time ARM 12 ARM 14 ARM 15 453 A 453 B Zone I Zone II Zone III Zone IV
- =-------------------- - =-------------
------------------------------------------------==
0:00 5 5 16 17 17 5 17 17 17 0700 0800 1:00 5 5 16 17 17 5 17 17 16 0900 2:00 4 4 15 16 16 4 15 16 16 3:00 4 4 14 14 14 4 14 14 15 1000 3:15 4 5 16 16 16 4 16 16 15 1015 3:30 6 6 19 10 10 6 10 10 15 1030 3:45 6 7 20 11 11 6 11 11 15 1045 4:00 7 7 21 11 11 7 11 11 15 1100 4:15 8 8 24 13 13 8 13 13 15 1115 4:30 9 9 26 14 14 9 14 14 15 1130 4:45 9 9 27 15 15 9 15 15 15 1145 5:00 9 9 26 14 14 9 14 14 15 1200 9 10 28 15 15 9 15 15 15 1215 5:15 15 5:30 10 10 28 16 16 10 16 16 1230 5:45 10 10 29 16 16 10 16 16 15 1245 6:00 2E5 (OSH)>1E4(OSH)>1E(OSH)>1E4 2E5 2E5 2E5 2E5 1300 (OSH)>1E4 4E5 4E5 1315 6:15 (OSH) 4E5 (OSH) (OSH) (OSH) 4E5 4E5 6:30 4E5 (OSH) (OSH) (OSH) 4E5 4E5 4E5 4E5 1330 (OSH) 4E5 6:45 4E5 (OSH) (OSH) (OSH) 4E5 4E5 4E5 1345 (OSH) 4E5 7:00 4E5 (OSH) (OSH) (OSH) 4E5 4E5 4E5 1400 (OSH) 4E5 7:15 4E5 (OSH) (OSH) (OSH) 4E5 4E5 4E5 1415 (OSH) 4E5 7:30 4E5 (OSH) (OSH) (OSH) 4E5 4E5 4E5 1430 (OSH) 7:45 3E5 (OSH) (OSH) (OSH) 3E5 3E5 3E5 3E5 1445 (OSH) 3E5 8:00 3E5 (OSH) (OSH) (OSH) 3E5 3E5 3E5 1500 (OSH) 3E5 3E5 (OSH) (OSH) 3E5 3E5 3E5 1515 8:15 (OSH) (OSH) 2E5 2E5 1530 8:30 (OSH) 2E5 (OSH) (OSH) (OSH) 2E5 2E5 Notes: Zone readings are averase dose rates throughout zone. General area contamination levels 2K-5K dpm/100 cm2 in all zones before 1300. General area contamination levels 20K-50K dpm/100 cm2 in all zones after 1300. (OSH) OFF SCALE HIGH
REACTOR BUILDING w -N ELEV AT!' 345' l MONITORS I Ii I y . i { I h HEACTOR DUltDING ELEVATOR ENTRANCE - i liATCtf (ii) REACIOR BUltDtNG WEST REFUELING AREA C ruEt Poot wtsT (4$33A , II - l - 0s3. seEnr ruEt POOt , , I CAM I" ,
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m L TABLE 9.3-2 Rev. O ! Reactor Building, Elevation 318' Page'9.3-2a (mR/hr unless otherwise noted) ClocP. Scenario Time Time ARM 10 ARM 11 ARM 16 Zone I Zone II Zone III Zone IV Zone V Zone VI Zone VII 0700- 0:00 7 5 .5 7 5 300 5 80 .5 .5 7 5 .5 7 5 300 5 80 .5 .5 0800 1:00 2:00 6 4 .5 6 4 300 4 80 .5 .5 0900 6 4 .5 6 4 200 4 80 .5 .5 1000 3:00 7 4 7 4 200 4 80 .5 .5 1015' 3:15 .5-8 2 .5 8 2 200 2 80 .5 .5 1030 3:30 9 3 .5 9 3 200 3 80 .5 .5 1045 3:45 9 3 .5 9- 3 200 3 80 .5 .5 1100 4:00 4:15 10 3 .5 10 3 200 3 80 .5 .5 1115 4:30 11 3 .5 11 3 100 3 60 .5 .5 1130 11 3 .5 11 3 100 3 60 .5 .5 1145 4:45 1 5:00 11 3 1 11 3 100 3 60 1 1200 12 3 1 12 3 100 3 60 1 1
'1215 5:15 1 1 5:30 12 3 1 12 3 100 3 60 1230 5:45 12 3 1 12 3 100 3 60 1 1 1245 SES SES SES SES SE5 5ES SE5 1300 6:00 (OSH)>1E4 (OSH)>1E4(OSH)>1E2 1E6 1E6 1315 6:15 (OSH) (OSH) (OSH) 1E6. 1E6 1E6 1E6 1E6 6:30 (OSH) (OSM) 1E6 1E6 1E6 1E6 1E6 1E6 1E6 1330 (OSH) 1E6 1E6 1E6 1E6 1E6 1E6 1E6 4
1345 6:45 (OSH) (OSH) (OSH) 1E6 7:00 (OSH) (OSH) 1E6 1E6 1E6 1E6 1E6 1E6 1400 (OSH) 1415 7:15 (OSH) (OSH) (OSH) 1E6 1E6 1E6 1E6 1E6 1E6 1E6 1430 7:30 -(OSH) (OSH) 1E6 1E6 1E6 1E6 1E6 1E6 1E6 (OSH) 1445 7:45 (OSH) 7.5ES 7.5ES 7.5ES 7.5ES 7.5ES 7.5ES 7.5ES
-(OSH) (OSH) 8:00 (OSH) 7.5ES 7.5ES 7.5E5 7.5E5 7.5ES 7.5E5 7.5ES 1500 (OSH) (OSH) 1515 8:30 (OSH) (OSH) 7.5ES -7.5ES 7.5ES 7.5ES 7.5ES 7.5E5 7.5E5 (OSH) 8:45 5ES SES SE5 SES. SES SES SES 1530 (OSH) (OSH) (OSH)
Notes: Zone readings are average dose rates throughout zone. General area contamination levels 1K-5K dpa/100 cm2 in all zones before 1300 ~ General area contamination levels 50K-120K dpm/100 cm2 in'all zones after 1300 (OSH) OFF SCALE HIGH 4 1
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1 i i i i TABLE 9.3-3 Rev. O I Reactor Building, Elevation 303' Page 9.3-3a (mR/hr unless'otherwise'noted) I Clock Scenario Zone V Zone VI Zone VII
' Time Time ARM 8 ARM 9 Zone I; Zone II Zone III Zone'IV l
4 3 600 3. 60 0.1 0.2 i 0700 0:00 4 4 4' ? 600 3 60 0.1 0.2 l 0800 1:00 4 4 4 3 600 3 60 0.1 0.2 l 0900 2:00 4 4 4 4- 3 600 3- 60 0.1 0.2 { 1000 3:00 3 4 4 3 600 3 60 0.1 0.2 ! 1015 3:15 4 5 3 600 3 60 0.1 0.2 i 1030 3:30 5 5 3 600 3 60 0.1 0.2 1045 3:45 5 5 5 5 3 600 3 60 0.1 0.2 1100 4:00 6 5 5 3 600 3 60 0.1 0.2 1115 '4:15 7 5 5 3 800 3 80 0.1' O.2 1130 4:30 7 5 5 3 800 3 80 0.1 0.2 1 1145 4:45 8 5 3 800 3 80 0.1 0.2 1200 5:00 7 5 5 8 5 5 3 800 3 80 0.1 0.2 1215 5:15 80 0.1 0.2 1230 5:30 8 5 5 3 800 3 5 3 800 3 80 0.1 0.2 1265 5:45 8 5
'5ES SES SES SE5 SES SES 1300 6:00 (OSH)>1E4 (OSH)>1E4 SES 1E6 1E6 1E6 IE6 IE6 1E6 1E6
, 1315 6:15 (OSH) (OSH) 1E6 1E6 ' 1E6 1E6 1E6 1E6 1E6 1330 6:30 (OSH) (OSH) 1E6 1E6 1E6' 1E6 1E6 1E6 1E6 1345 6: 45 (OSH) -(OSH) 1E6 1E6 1E6 7:00 (OSH) 1E6 1E6 1E6 1E6 1400 (OSH) 1E6 IE6 1E6 7:15 (OSH) 1E6' 1E6 1E6 1E6 1415 (OSH) 1E6 IE6 1E6 1E6 1E6 1E6 1E6 2 1430 7:30 (OSH) (OSH) 7.5ES 7.5ES 7.5ES 7.5E5 j 1445 7:45 (OSH) (OSH) 7.5ES 7.5ES 7.5E5 7.5ES 7.5ES 7.5ES 7.5E5 7.5ES 7.5ES 7.5E5 1500 8:00 (OSH) (OSH) 7.5ES 7.5ES 7.5E5- 7.5ES 7.5E5 7.5ES 7.5ES (OSH) 1515 8:15- (OSH)' .5E5 SE5- SES 8:30 SES. SES SES SES 1530 .(OSH) (OSH) Notes: Zone readings are average dose rates throughout zone. General area. contamination levels 1K-5K dpa/100 cm2 in all. zones before 1300. General area contamination levels 50K-120K dpa/100 cm2 in all zones after 1300. (OSH) OFF SCALE HIGH .
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gs I TABLE 9.3-4 Rev. O Page 9.3-4a Reactor Building, Elevation 280 (mR/hr unless otherwise noted) RB Vent RB Vent Zone Zone Zone 'I South Zone Zone Zone Zone Zone i Clock Scenario North III IV V VI VII VIII ~ Time Time ARM 6 ARM 31 ARM 32 I II 3 25 9 7 3 1 0.7 0.3 0700 0:00 7 2 2 3 20 9 7 3 1 0.7 0.3 0800 1:00 7 2 2 3 20 8 7 2 1 0.7 0.3 0900 2:00 7 2 2 3 20 8 7 2 1 0.7 0.3 , 1000 3:00 7 2 2 3 20 8 7 2 1 0.7 0.3 ; 1015 3:15 7 2 2 1 3 20 8 5 2 1 0.7 0.3 1030 3:30 5 1 1 3 20 8 5 2 1 0.7 0.3 1045 3:45 5 1 1 3 20 8 5 2 1 0.7 0.3 1100 4:00 5 1 1
- 5 2 1 0.7 0.3 5 i 1 3 20 8 1 1115 4:15 5 2 1 0.7 0.3 .i
' 5 1 1 3 20 8 1130 4:30 5 2 1 0.7 0.3 t 5 1 1 2 15 6 1145 4:45 6 5 2 1 0.7 0.3 1200 5:00 5 1 1 2 15 4 3 15 7 S 2 1 0.7 0.3 i 1215 5:15 5 1 1 ' i 3 15 7 5 2 1 0.7 0.3 l 1230 5:30 5 1 1 3 15 8 5 2 1 0.7 0.3 ' 1245 5:45 5 1 1 1E6 1E6 1E6 1E6 1E6 1E6 1E6 1E6 1300 6:00 (OSH)>1E4 (OSH)>1E3(OSH)>1E3 2E6 2E6 2E6 2E6 2E6 2E6 1315 6:15 (OSH) (OSH) (OSH) 2E6 2E6 2E6 2E6 2E6 2E6 2E6 2E6 2E6 2E6 1330 6:30 (OSH) (OSH) (OSH) 2E6 2E6 2E6 2E6 2E6 2E6 2E6 2E6 1345 6:45 (OSH) (OSH) (OSH) 2E6 2E6 2E6 2E6 2E6 2E6 2E6 2E6 1400 7:00 (OSH) (OSH) (OSH) 2E6 2E6 2E6 2E6 2E6 2E6 2E6 2E6 1415 7:15 (OSH) (OSH) (OSH) 2E6 2E6 2E6 2E6 2E6 2E6 2E6 2E6 ,
- 1430 7:30 (OSH) (OSH) (OSH) 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1445 7:45 (OSH) (OSH) (OSH) 1.5E6 1.5E6 1.5E6 (OSH) 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1500 8:00 (OSH) (OSH) 1.5E6 1.5E6 1.5E6 (OSH) 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6
] 1515 8:15 (OSH) (OSH) 1E3 1E3 1E3 1E3 (OSH) 1E3 1E3 1E3 1E3 1530 8:30 (OSH) (OSH) Notes: Zone readings are average dose rcues throughout zone. , i General area contamination levels 1K-2K dpm/100 cm2 in all zones before 1300. General area contamination levels 100K-200K dpm/100 cm2 in all zones after 1300. j (OSH) OFF SCALE HIGH i i
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TABLE 9.3-5 Rev. O Reactor Building, Elevation 252' Page 9.3-Sa.1 (mR/hr unless otherwise noted) RM- Zone Zone Zone Zone Zone Zone Zone Clock Scenario ARM 5 ARM 7 14-29 I II III IV V VI VII Time Time ARM 2 ARM 3 ARM 4 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - .3
- - - - -50
- - - - - - - - - - 24 0 4 .3 5 56f 12 100 0700 100 5 4 .3 50 4 12 24 1:00 4 .3 5 c50 12 0800 100 5 4 .3 50 4 11 22 2:00 4 .3 5 930 11 0900 100 5 4 .3 40 4 10 20 4 .3 5 430 10 1000 3:00 11 100 5 4 .3 50 4 11 22 1015 3:15 4 .3 5 510 720 14 100 5 6 .3 70 6 14 28-1030 3:30 6 .3 5 830 16 100 5 6 .3 80 6 16 32 3:45 6 .3 5 34 1045 11 100 6 7 .3 85 7 17 4:00 7 .3 6 .840 38 1100 19 100 0 8 .4 110 8 19 1115 4:15 8 .4 6 1100 22 42 6 1200 22 100 6 9 .4 120 9 1130 4:30 9 .4 22 42 1300 22 100 6 10 .4 130 10 1145 4:45 10 .4 6 42 100 6 9 .4 12G 9 22 1200 5:00 9 .4 6 1200 22 23 46 6 1300 23 100 6 100 .4 130 100 1215 5:15 100 .4 130 100 24 43-6 1300 24 100 6 100 .4 1230 5:30 100 .4 500 140 500 24 48 500 .4 6 1400 24 100 6 .4 1245 5:45 1E6 1E6 1E6 1E6 .1E6 1E6 1E6 1300 6:00 (OSH)>1E4(OSH)>1E4(OSH)>1E4(OSH)>1E4(OSH)>1E4 500 500 2E6 2E6 2E6 2E6 2E6 2E6 2E6 1315 6:15 (OSH) (OSH) (OSH) (OSH) (OSH) 2E6 2E6 500 2E6 2E6 2E6 2E6 2E6 6:30 (OSH) (OSH) (OSH) (OSH) (OSH) 2E6 2E6 1330 500 2E6 2E6 2E6 2E6 2E6 1345 6:45 (OSH) (OSH) (OSH) (OSH) (OSH) 2E6 2E6 2E6 500 2E6 2E6 2E6 2E6 1400 7:00 (OSH) (OSH) (OSH) (OSH) (OSH) 2E6 500 2E6 2E6 2E6 2E6 2E6 2E6 1415 7:15 (OSH) (OSH) (OSH) (OSH) (OSH) 2E6 2E6 2E6 500 2E6 2E6 2E6 2E6 7:30 (OSH) (OSH) (OSH) (OSH) 1430 (OSM)
(OSH) (OSH) 500 1.5E6 1.5E61.5E6 1.5E6 1.5E61.5E6 1.5E6 1445 7:45 (OSM) (OSH) (OSH) 1.5E6 1.5E61.5E6 1.5E6 8:00 (OSH) (OSH) (OSH) (OSH) (OSH) 500 1.5E6 1.5E61.5E6 1500 (OSH) (OSH) 500 1.5E6 1.5E61.5E6 1.5E6 1.5E61.5E6-1.5E6 1515 8:15 (OSH) (OSH) (OSH) 1E6 1E6 1E6 IE6 1E6 (OSH) (OSH) (OSH) 500 1E6 1E6 1530 8:30 (OSH) (OSH) Notes: Zone readings are average dose rates thrcughout zone. General area contamination levels 1K-2K dps/100 cm2 in all zones before 1300. General area contamination levels 100K-200K dpm/100 cm2 in all zones after 1300. (OSH) OFF SCALE HIGH
, ,A Rev. O Page 9.3-Sa.2 TABLE 9.3-5 (Continued)
SCFTli TIP Clock Scenario NORTII RMS II--2** RMS II-3** Time Time RMS II-1** ______________________________ _________________________________________1.0
<1.0 <
0700 0 <1.0 <1. is 0800 1:00 <1.0 <1,0 <1 0 0900 2:00 <1.0 <1 0
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1015 3:15 <1.0 <1.0
<1.0 <1.0 1030 3:30 <1.0 <1.0 1045 3:45 <1.0 <1.0
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<1.0 <1.0 1130 4:30 <1.0 <1.
1145 4:45 <1.0 < 1. f
<1.0 <1.0 1200 5:00 <1.0 <1.0 1215 5:15 <1.0 <1.0
<1.0 <1.0 l 1230 5:45 <1.0 <1.0 1
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8 TABLE.9.3-6 Rev. O Turbine Deck, Elevation 272' Page 9.3-6a (mR/hr unless otherwise noted) Turbine Deck Clock Scenario CAM (cpm) Time Time ARM 24 Zone I Zone II Zone III NG. Particulate 0700 0:00 9 100 150 9 250 900 0800 1:00 7 75 120 7 250 900 0900 2:00 7 40 60 7 250 900 1000 3:00 7 20 35 7 250 900 1015 3:15 7 20 35 7 250 900 1030 3:30 7 16 30 7 250 900 1045 3:45 7 16 22 7 250 900 1100 4:00 7 16 22 7 250 900 1115 4:15 7 11 22 7 250 900 1130 4:30 7 11 22 7 250 900-1145 4:45 7 11 22 7 250 900 1200 5:00 7 10 20 7 250 900 1215 5:15 7 10 20 7 250 900 1230 5:30 7 10 20 7 250 900 1245 5:45 7 10 20 7 250 900 1300 16:00 7 10 20 7 250 900 1315 6:15 7 10 20 7 250 900 1330 6:30 7 10 20 7 250 900 1345 6:45 7 10 20 7 250 900 1400 7:00 7 10 20 7' 250 900 1415 7:15 7 10 20 7 250 900 1430 7:30 7 10 20 7 250 900 1445 7:45 7 10 20 7 250 900 1500 8:00 7 10 20 7 250 900 1515 8:15 7 10 20 7 250 900 1530 8:30 7 10 20 7 250 900 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2.
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Rev. O TABLE 9.6-7 Page 9.3-7a Turbine Building Truck Bay, Make-Up Demineralization Cond. Demineralization Areas, Elevation 252' (mR/hr unless otherwise noted) Clock Scenario RM-14-36 RM-14-23A Zone II Zone III Zone IV Time (cpm) ARM 26 (cpm) Zone I Time ________________________ ___..______m._______________________________________________0.2 0.1 0.2 0700 0 150 0.17 150 0.2 0.2 150 0.5 0.3 0.2 0800 1:00 150 0.16 0.2 0.2 0.14 150 0.5 0.3 0900 2:00 150- 0.3 0.2 0.2 150 0.14 150 0.6 1000 3:00 0.6 0.3 0.2 0.2 3:15 150 0.13 150 0.2 1015 150 0.7 0.3 0.2 1030 3:30 150 0.13 0.2 0.2 0.13 150 0.7 0.3 1045 3:45 150 0.3 0.2 0.2 4:00 150 0.01 150 0.7 0.2 1100 150 0.7 0.3 0.2 1115 4:15 150 0.01 0.2 0.2 0.01 150 C.7 0.3 1130 4:30 150 0.3 0.2 0.2 4:45 150- 0.01 150 0.7 0.2 1145 150 0.7 0.3 0.2 1200 5:00 150 0.01 0.2 0.2 0.01 150 0.7 0.3 1215 5:15 150 0.3 0 . 2. 0.2 5:30 150 0.01 150 0.7 0.2 1230 150 0.7 0.3 0.2 1245 5:45 150 0.01 0.2 0.2 0.01 150 0.7 0.3 1300 6:00 150 0.3 0.2 0.2 150 0.01 150 0.7 1315 6:15 0.3 0.2 0.2 6:30 150 0.01 150 0.7 0.2 1330 150 0.7 0.3 0.2 1345 6:45 150 0.01 ~0.2 0.2 0.01 150 0.7 0.3 1400 7:00 150 0.3 -0.2 0.2 7:15 150 0.01 150 0.7 0.2 1415 150 0.7 0.3 0.2 1430 7:30 150 0.01 0.2 0.2 0.01 150 0.7 0.3 1445 7:45 150 0.3 0.2 0.2 8:00 150 0.'01 150 0.7 0.2 0.2 ISt o 150 0.7 0.3 1525 8:15 150 0.01 0.2 0.2 l 0.01 150 0.7 0.3 1530 8:30 150 Notes: Zone readings are average dose-rates throughout zone. General area contamination levels <1K dpm/100 cm2. l 1 ____-__ ~ . . - . . - . . _ .. . . . . . . ,__ ___ =q--
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TABLE 9.3-8 Rev..O Turbine Building Cond. Bay, Elevation 248' Page 9.3-8a (mR/hr unless otherwise noted) Clock Scenario .one Z VI Zone VII Zone VII Time Time ARM 20 ARM 21 Zone III Zone IV Zone V
---------------------- --------------------------- 2 2
4 8 200 2 0700 'O 2 200 2 195 2 2 4 4 195 2 0300 1:00 3 4 170 2 2:00 2 170 2 2 , 0900 3 3 170 2 1000 3:00 2 170 2 1 2 4 1 1 3 3 4 1015 3:15 2 1 4 1 1 2 3 4 1030 3:30 1 4 1 1 4 1 1 2 3 1045 3:45 2 4 1 4 1 1 2 1100 4: 00 1 2 2 4 1 4:15 1 4 1 1 1115 1 1 4 1 1130 4:30 1 4 1 1 1 1 1 1 4 1 1145 4:45 1 4 1 1 1 1 4 1 1200 5:00 1 4 4 1 1 1 1 4 1 1215 5:15 1 4 1 4 1 1 1 1 1230 5:30 1 4 1 4 1 1 1 1 1245 5:45 1 4 1 4 1 1 1 1 1300 6:00 1 4 1 4 1 1 1 1 1315 6:15 1 4 1 4 1 1 1 1 1330 6:30 1 4 1 1 4 1 1 1 1 1345 6:45 1 4 1 1 4 1 1 1 1400 7:00 1 1 4 1 7:15 1 4 1 1 1415 1 1 1 4 1 7:30 1 4 1 1430 1 1 1 4 1 -l 1445 7:45 1 4 1 4 1 1 1 1 4 1 . 1500 8:00 1 4 1 4 1 1 1 1 1515 8:15 1 4 1 4 1 1 1 1 1530 8:30 1 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2.
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, Turbine Building, Demineralization /OG Areas, Elevation 232'-
,(mR/hr unless otherwise noted)
Clock Scenario Time ' Time ARM 22 ARM 38 Zone I Zone II- Zone III g g g g 0800 1:00 0.3 40 0.2 0.5 0.2 0900 2:00 0.2 D/S 'O.2 0.5~ 0.2 1000 3:00 0.2 D/S 0.2 0.5 0.2 1015 3:15 0.2 D/S 0.2 0.5 0.2 1030 3:30 0.2 D/S 0.2 0.5 0.2 1045 3:45 0.2- D/S 0.2- 0.5 0.2 1100 4:00 0.1 D/S ,0. 2 0.5 0.2 1115 4:15 0 .1' D/S 0.2 0.5 0.2 1130 4:30 0.1 D/S- 0.2 0.5 0.2-1145 4:45 0.1 D/S 0.2 0.5 0.2 4 1200 5:00 0.1 D/S 0.2 0.5 0.2 1215 5:15 0.1 D/S 0.2 0.5 0.2 1230 5:30 0.1 D/S 0.2 .0.5 0.2 1245 5:45 0.1 D/S 0.2 0.5 0.2 1300 6:00 0.1 D/S 0.2 0.5 0.2 1315 6:15 0.1 D/S 0.2 0.5 0.2 1330 6:30 0.1 D/S 0.2 0.5 0.2 1345 6:45 0.1 D/S 0.2 0.5 0.2 1400 7:00 .O.1 D/S 0.2 0.5 0.2 1415 7:15 0.1 D/S 0.2 0.5 0.2 1430 7:30 0.1 D/S 0.2 0.5 0.2 1445 7:45 ' O .1 D/S 0.2 0.5 0.2 1500 8:00 0.1 D/S 0.2 0.5 0.2 1515 8:15 0.1 D/S .0.2 0.5 0.2 1530 8:30 0.1 D/S 0.2 0.5 0.2 Notes: Zone readings are averacJe dose rates throughout zone. General area contamination levels <1K dpm/100 cm2. D/S = Downscale reading. i
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TABLE 9.3-10 Rev. O Turbine Building Cond. Bay, Elevation 222'6" & 228'6" . (mR/hr unless otherwise noted) l Clock Scenario Zone VI Time Time' -ARM 13 Zone I Zone II. Zone III Zone IV Zone V
.0 150 3 1 50 150 2 75 0700 55 0800 1:00 140 3 -1 35 110 2 .
120 1 1 20 60 2 30 0900 2:00 15 3:00 1 1 1 10 30 2 i 1000 2 10 1015 3:15 1 1 1 5 20 3:30 1 1 1 5 20 2 10 1030 2 7 1045 3:45 1 1 1 5 15 1 1 1 5 15 2 7 1100 4:00 7 1115 4:15 1 1 1 5 15 2 1 1 1 5 15 2 7 1130 4:30 2 7 1145 4:45 1 1 1 5 15 1 1 1 5 15 2 7 1200 5:00 7 5:15 1 1 1 5 15 2 1215 7 1230 5:30 1 1 1 5 15 2 1 1 1 5 15 2 7 1245 5:45 15 2 7 1300 6:00 1 1 1 5 1 1 1 5 15 2 7 1315 6:15 15 2 7 1330 6:30 1 1 1 5 1 1 1 5 15 2 7 1345 6:45 15 2 7 1400 7:00 1 1 1 5 .
- 1. 1 1 5 15 2 7 1415 7:15
.2 7 1430 7:30 1 1 5 15 1 1 1 5 15 2 7 1445 7:45 15 2 7 1500 8.00 1 1 1 5 1 1 5 15 2 7 1515 8: 15 1 2 7 1530 8:30 1 1 1 5 15 Notes: Zone readings are average ~ dose rates throughout.zolae.
General area contamination-levels <1K dpm/100 cm2.
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4 O Rev. O Page 9.3-11a TABLE 9.3-11 Torus Catwalk (mR/hr unless otherwise noted) Clock Scen- ' Time Time ARM 1 Zone 5 0700 0:00 8 8 0800 1:00 8 8 0900 2:00 8 8 1000 3:00 8 8 1015 3:15 10 10 1030 3:30 100 100 1045 3:45 500 500 1100 4:00 1000 1000 1115 4:15 5000 5000 1130 4:30 (OSil) >1E4 12000 1145 4:45 (OSil) 15000 1200 5:00 (OS11) 100000 1215 5:15 ( 0 S 11) 100000 1230 5:40 (OSil) 100000 1245 5:45 (OSil) _s0000 1300 6:00 (OSil) 100000 1315 6:15 - (OSil) IF000 1330 6:30 (OSII) 100'100 1345 6:45 ( 0 511) 100000 1400 7:00 ( 0 S 11) 100000 1415 7:15 (OSII) J0000 1430 7:30 (OSil) 1000c0 1445 7:45 (OSII) 100C09 1500 8:00 (OSII) 100000 1515 8:15 (OSli) 100000 1530 8:30 (OSli) 100000 l Notes: Zone readings are average dose rates throughout zone. l (OSil) OFF SCALE IIIGli i l I
PCge 9.311b FIGURE 9.3-11 4 V H
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@ REACTOR BUILDING SUPPRESSION CHAMBER EXT. CATWALK 4
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4' PLANT CHEMISTRY DATA SECTION ZAQE 9.4.1 Reactor Coolant Activity Data......................... 9.4.1-1 9.4.2 Primary Containment Air Activity Data................, 9.4.2-1 , 9.4,3_ Reactor Building Air Activity Data.............. .... 9.4.3-1 9
- ,.,.<,,e ,e- .., , .n . - -- -.-- -
A4, a- ,a 4 - - - M a a a m A - ,s y-b S VERMONT YANKEE NUCLEAR POWER STATION -- EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.1 REACTOR COOIANT ACTIVITY DATA
'( Rev.-O Page 9.4.1-1 VERMONT YANKEE NUCL2AR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCi/ml)
Time Isotope Prior to 1030 1030-1045 1045-1100 I-131 2.5E-03 6.53E+02 1.31E+03 I-132 2.8E-03 7.80E+02 1.56E+03 I-133 5.2E-03 14 28E+03 2.56E+03 I-134 1 1E-03 8.60E+02 1.72E+03 I-135 4.5E-03 1.14E+03 2.28E+03 e Total Iodine 1.9E-02 4.7E+03 9.4E+03 I-131 Dose 4.5E-03 1.1E+03 2.3E+03 Equivalent Kr-83m 1.2E-03 4.20E+00 8.40E+00 Kr-85m 2.5E-02 2.83E+00 5.63E+00 Kr-85 4.8E-03 1.54E-01 3.03E-01 Kr-87 2.9E-03 4.00E+00 8.00E+00-Kr-88 1.0E-03 6.80E+00 1.36E+01 Xe-133 5.3E-03 2.80E+01 5.60E+01 Xe-135m 5.8E-03 5.40E+01 1.08E+02 Xe-135 2.2E-03 1.50E+01 3.20E+01 Total Noble 4.8E-02 1.2E+02 2.3E+02 Gas Note: Reactor coolant sample dose rates are provided in Section 9.5.1 8
( Rev. O Page 9.4.1-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 I 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCi/ml) Time Isotope 1100-1115 1115-1130 1130-1145 1145-1200 I-131 1.96E+03 2.61E+03 3.3E+03 3.3E+03 I-132 2.34E+03 3.12E+03 3.9E+03 3.7E+03 I-133 3.84E+03 5.12E+03 6.4E+03 6.3E+03 I-134 2.58E+03 3.44E+03 4.3E+03 3.5E+03 I-135 3.42E+03 4.56E+03 5.7E+03 5.5E+03 Total Iodine 1.4E+04 1.9E+04 2.4E+04 2.2E+04 I-131-Dose 3.4E+03 4.5E+03 5.7E+03 5.7E+03 Equivalent Kr-83m 1.26E+01 1.68E+01 2.1E+01 4.5E+01 Kr-85m 8.44E+00 1.13E+01 1.4E+01 1.4E+01 Kr-85 4.52E-01 6.01E-01 7.4E-01 7.4E-01 Kr-87 1.20E+01 1.60E+01 2.0E+01 1.8E+01 Kr-88 2.04E+01 2.72E+01 3.4E+01 3.2E+01 Xe-133 8.40E+01 1.12E+02 1.4E+02 1.4E+02 Xe-135m 1.62E+02 2.16E+02 2.7E+02 5.6E+02 Xe-135 4.80E+01 6.40E+01 8.0E+01 1.8E+02 Total Noble 3.5E+02 4.6E+02 5.8EF02 9.8E+02 Gas Note: Reactor coolant sample dose rates are provided in Section 9.5.1.
Rev. O Page 9.4.1-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCi/ml) Time Isotope 1200-1215 1215-1230 1230-1245 I-131 3.3E+03 3 . 3 E+ 0 3 -- 3.3E+03 I-132- 3.4E+03 3.1E+03 2.9E+03 I-133 6.3E+03 6.3E+03 6.2E+03 I-134 2.9E+03 2.4E+03 1.9E+03 I-A35 5.4E+03 5.3E+03 5.1E+03 I Total Iodine 2.1E+04 2.0E+04 1.9E+04 I-131 Dose 5.6E+03 5.6E+03 5.5E+03 Equivalent Kr-83m 6.5E+01 8.2E+01 9:5E+01 Kr-8Em 1.3E+01 1.3E+01 1.2E+01-Kr s - 7.4E-01 7.4E-01 7.4E-01 Kr- 7 1.5E+01 1.3E+01 1.2E+01 Kr-68 3.0E+01 2.9E+01 2.7E+01 Xe-133 1.5E+02 1.6E+02 1.7E+02 Xe-135m 7.0E+02 7.6E+02 7.8E+02 Xe-135 2.7E+02 3.7E+02 4.6E+02 Total Noble 1.2E+03 1.4E+03 1.6E+03 Gas Note: Reactor coolant sample dose rates are provided in Section 9.5.1
i 1 Rev. 0-Page 9.4.1-4 VERMONT YANKEE NUCLEAR POWER STATION' EMERGENCY' RESPONSE PREPAREDNESS EXERCISE 1991 - , 9.4.1 REACTOR COOLANT ACTIVITY DATA-A._. Reactor Coolant Activity Concentrations (uCi/ml) Time Isotope _1245-1300 1300-1315 1315-1330 1330-1345 I-131- -3.3E+03 3.0E+03 2.7E+03 2.4E+03
-I-132 2.7E+03 2.4E+03 1.9E+03 1.6E+03 I-133' ~6.1E+03 5.7E+03 5.0E+03 4.4E+03 I-134 1.6E+03 1.2E+03 8.8E+02 6.4E+02 I-135 5.0E+03 4.6E+03 ~3.9E+03 ' 3 . 4 E+ 0 3 -
A
' Total. Iodine 1.9E+04 1.7E+04 1.4E+04 l'.2E+04 I-131 Dose 5.5E+03 5.0E+03 4.5E+03 3.9E+03 Equivalent i
Kr-83m 1.1E+02 1.1E+02 1.0E+02 9.2E+01 Kr-85m -1.2E+01: 1.1E+01- 9.0E+00 7.6E+00 +
-Kr-85 7.4E-01 6.9E-01 -6.1E-01 5.4E-01 Kr-87 1.0E+01 8.4E+00 '6.4E+00 4.9E+00 Kr-88 2.5E+01 2.2E+01 1.8E+01 1.5E+01-
- Xe-133 1.8E+02 1.7E+02 1.6E+02 1.5E+02 Xe-135m 7.8E+02- 7.2E+02 6.2E+0'- 5.4E+02 Xe-135 5.4E+02 5.9E+02 5.8E+0 5.7E+02 Total-Noble 1.7E+03 1.6E+03 1.5E+03 1.4E+03 Gas Note: Reactor coolant' sample dose rates are provided in Section 9.5.1.
t W w h,- .r1 ..=r - i,~r r y,r . ,e, . ,..s.-_,.-w ,-.-,.~2-.. s -. .-- ...,-,,-,_---.m-.
Rev. O Page 9.4.1-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activit'_J _______________________ Concentrations (uCi/ml) TIME Isotope 1345-1400 1400-1415 1415-1430 1430-1445 I-131 2.1E+03 1.9E+03 1.9E+03 1.9E+03 I-132 1.3E+03 1.1E+03 1.0E+03 9.6E+02 I-133 3.8E+03 3.5E+03 3.5E+03 3.5E+03 I-134 4.6E+02 3.6E+02 2.9E+02 2.4E+02 I-135 2.9E+03 2.6E+03 2.6E+03 2.5E+03 Total Iodine 1.1E+04 9.5E+03 9.3E+03 9.1E+03 I-131 Dose 3.4E+03 3.1E+03 3.1E+03 3.1E+03
,- Equivalent Kr-83m 8.3E+01 7.9E+01 7.9E+01 7.9E+01 Kr-85m 6.5E+00 5.8E+00 5.6E+00 5.4E+00 Kr-85 4.7E-01 4.4E-01 4.4E-01 4.4E-01 Kr-87 3.8E+00 3.1E+00 2.7E+00 2.4E+00 Kr-88 1.3E+01 1.1E+01 1.1E+01 9.9E+00 Xe-133 1.3E+02 1.3E+02 1.3E+02 1.4E+02 Xe-135m 4.6E+02 4.2E+02 4.1E+02 4.OE+02 Xe-135 5.5E+02 5.5E+02 5.9E+02 6.3E+02 Total Noble 1.2E+03 1.2E+03 1.2E+03 1.3E+03
. Gas
__________g__ Note: Reactor coolant sample dose rates are provided in Section 9.5.1. T
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VERMONT: YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991
~
9.4.1 REACTOR COOLANT ACTIVITY DATA A.- Reactor Coolant Activity Concentrations (uci/ml) ~ Time
; Isotope 1445-1500 1500-1515 1515-1530 *
'I-131: 1.9E+03 1.9E+03 1.9E+03 EI-132 8.9E+02 -8.2E+02 7.7E+02 I-133- 3.5E+03 3.4E+03' 3.4E+03
-I-134- 2.0E+02 1.6E+02 1.3E+02
~I-135 2.4E+03 2.4E+03 2.3E+03 Total Iodine 8.9E+03 8.7E+03 8.5E+03-I-131 Dose 3.1E+03 3.1E+03 3.1E+03
-Equivalent k
-Kr-83m. 7.9E+01 7.8E+01 7.6E+01 Kr-85m 5.2E+00 5.OE+00- 4.8E+00
=Kr-85 4.4E-01 4.4E-01 4.4E-01
-Kr-87 2.1E+00 l'.8E+00 1.6E+00 Kr-88 9.3E+00 8.BE+00 8.2E+00 _
Xe-133 1.4E+02 1.5E+02 1.5E+02 Xe-135m' 3'.9E+02 3.8E+02- 3.7E+02 g :Xe-135 6.6E+02 7.0E+02 7.3E+02 l L . Total Noble 1.3E+03 1.3E+03 1.3E+03 Gas: l I l; Note: Reactor coolant sample dose rates are provided in Section 9.5.1.
- Post 1530 values continue to decline steadily with time.
'" 4 a VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA 4
( Rev. O Fage 9.4.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uci/cc) \ Time 1 Isotope Prior to 1200 1200-1215 .1215-1230 1230-1245 1 I-131
- 9.4E-01 9.4E-01 9.4E-01 I-132
- 9.8E-01 9.1E-01 8.4E-01 I-133
- 1.8E+00 1.8E+00 1.8E+00 I-134
- 8.3E-01 6.8E-01 5.6E-01 I-135
- 1.6E+00 1.5E+00 1.5E+00 Total Iodine
- 6.1E+00 5.8E+00 5.6E+00
~I-131 Dose
- 1.6E+00 1.6E+00 1.rE+00 Equivalent Kr-83m
- 3.9E+01 3.8E+01 3.7E+01 Kr-85m
- 7.6E+01 7.4E+02 7.0E+01-Kr-85
- 4.3E+00 4.3E+00 4.3E+00 l Kr-8't
- 8.9E+01 7.7E+00 6.7E+01 Kr-88
- 1.7E+02 1.6E+02 1.5E+02 l 7.6E+02 1 Xe-133
- 7.6E+02 7.6E+02 Xe-135m
- 1.OE+02 9.BE+01 9.SE+01 Xe-135
- 2.1E+02 2.2E+02 2.2E+02 Total Noble
- 1.5E+03 2.0E+03 1.4E+03 Gas Note: Primary containment sample dose rate provided in Section 9.5.2.
- Prior to 1200 containment air activity is below MDA.
Rev. O Page 9.4.2-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA
.A. Primary Containment Air Activity Concentrations (uci/cc)
Time Isotope 1245-1300 1300-1315 1315-1330 I-131 9.4E-01 9.4E-01 9.4E-01 1-132 7.8E+00 7.2E-01 6.7E-01 I-133 1.8E+00 1.8E+00 1.7E+00 I-134 4.6E-01 3.8E-01 3.1E-01 1-135 1.4E+00 1.4E+00 1.4E+00 Total Iodine 1,2E+01 5.2E+00 5.0E+00 I-131 Dose 1.8E+00 1.6E+00 1.5E+00 Equivalent Kr-83m 3.6E+01 3.5E+01 3.4E+01 Kr-85m 6.8E+01 6.5E+01 6.3E+01 Kr-85 4.3E+00 4.3E+00 4.3E+00 Kr-87 5.9E+01 5.1E+01 4.5E+01 Kr-88 1.5E+02 1.4E+02 1.3E+02 Xe-133 7.6E+02 7.6E+02 7.6E+02 Xe-135m 9.2E+01 9.0E+01 8.7E+01 Xe-135 2.3E+02 2.4E+02 2.4E+02 Total Noble 1.4E+03 1.4E+03 1.4E+03 Gas Note: Primary containment sample dose rate provided in Section 9.5.2.
Rev. 0-Page 9.4.2-3 [ . VERMONT YANKEE NUCLEAR POWER STATION
- 'E EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA l
'l A. Primary Containment Air Activity Concentrations (uCi/cc) 1 Time Isotope 1330-1345 1345-1400 1400-1415 1435-1430 I-131' 9.3E-01 9.3E-01 9.3E-01 9.3E-01 I-132 6.2E-01 5.8E-01 5.3E-01 5.0E-01 I-133. 1.7E+00 1.7E+00 1.7E+00 1.7E+00 I-134 2.5E-01 2.1E-01 1.7E-01 1.4E-01 1-135 1.3E+00 1.3E+00 1.3E+00 1.2E+00 Total Iodine 4.8E+00 4.7E+00 4.6E+00 4.5E+00 I-131 Dose 1.5E+00 1.5E+00 1.5E+00 1.5E+00 Equivalent Kr-83m- -3.2E+01 3.1E+01 3.0E+01 2.9E+01 Kr-85m 6.0E+01 5.8E+01 5.6E+01 5.4E+01 Kr-85 4.3E+00 4.3E+00 4.3E+00 4.3E+00 Kr-87 3.9E+01 3.4E+01 3.0E+01 2.6E+01 Kr-88 1.2E+02 1.1E+02 1.1E+02 1.0E+02 Xe-133' 7.6E+02 7.6E+02 7.6E+02 7.6E+02 Xe-135m 8.5E+01 8.3E+01 8.1E+01 7.9E+01 Xe-135 2.5E+02 2. 5E4 02 2.6E+02 2.6E+02 Total Noble 1.4E+03 1.3E+03 1.3E+03 1.3E+03 Gas Note: Primary containment sample dose rate provided in Section 9.5.2.
i -- l l-t l
e i Rev. O Page 9.4.2-4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.? PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Cort ninment Air Activity Concentrations (uci/cc) . . __ __________ . __
. Time Isotope 1430-1445 1445-1730 1500-1515 1515-lbJO
- I-131 9.3E-01 9.3E-01 9.3E-01 9.".;J-01 I-132 4.6E-01 4.3E-01 4.0E-01 3.7E-01 I-133 1.7E+00 1.7E+00 1.6E+00 1.6E+00 T-134 1.1E-01 9.4E-02 7.7E-02 6.3E-02
-135 1.2E+00 1.2E+00 1.1E+00 1.1E+00 .
Total Iodine 4.4E+00 4.3E+C0 4.2E+00 4.1E+00 I-131 Dose 1.5B+00 3.5E+00 1.5E+00 1.5E+00 Equiva1ent Kr-83m 2.7E+01 2.6E+01 2.5E+01 2.4E+01 Kr-85m 5.2E+01 5.0E+01 4.8E+01 4.6E+01 Kr-85 4.3E+00 4.3E+00 4.3E+00 4.3E+00 Kr-87 2.3E+01 2.0E+01 1.7E+01 1.5E+01 Kr-88 9.5E+01 8.9E+01 8.4E+01 7.9E+01 Xe-133 7.6E+02 7.6E+02 7.6E+02 7.6E+02 Xe-135m 7.7E+01 7.5E+01 ' 7.3E+01 7.1E+01 Xe-135 2.7E+02 2.7E+02 2.8E+02 2.8E+02 Total Noble 1.3E+03 1.3E+C3 1.3E+03 1.3E+03 i Gas Note: Primary containment sample dose rate provided in Section 9.5.2.
- P.ost 1530 values continue to decline steadily with time.
~~ m- . n.
f VERMONT YA!EEE NUCLEAR POWER STATION , EMERGENCY RESPONSE PREPAREDNESR EXERCISE 1991 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA O
. . - _ - _ _ _ _ _ _ _ _ _ _ _ m _ . _ _ . _
Rev. 0 Page 9.4.3-1 [ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.3 REACTOR BUILDING AIR ACTIVITY . _____ DATA A. Reactor Building Air Activity Concentrations (uCi/cc)-.. . . .. . . Elevation 252' and 280' - See Notes Below* Time Isotope Prior to 1300 1300-1315 1315-1330 1330-1345 I-131 ** s.7E-01 4.8E-01 5.3E-01 I-132 ** 2.1E-01 3.5E-01 3.5E-01 I-133 ** 5.1E-01 9.0E-01 9.9E-01 I-134 ** 1.1E-01 1.6E-01 1.4E-01 I-135 ** 4.0E-01 7.0E-01 7.6E-01 Total Iodine ** 1.5E+00 2.6E+00 2.8E+00 I-131 Dose ** 4.5E-01 8.0E-01 8.8E-01 Equivalent Kr-83m ** 9.9E+00 1.7E+01 1.8E+01 Kr-85m ** ".9E+0'. 3.2E+01 3.5E+01 Kr-85 ** 1.2E+00 2.2E+00 2.4E+00 Kr-87 ** 1.5E+01 2.3E+01 2.2E+01 hr-88 ** 3.9E+01 6.6E+01 6.9E+01 Xe-133 ** 2.2E+02 3.9E+02 4.3E+02 Xe-135m ** 2.2E+01 3.3E+01 3.4E+01 Xe-135 ** 6.8E+01 1.2E+02 1.4E+02 Xe-133m ** 6.4E+00 1.1E+01 1.3E+01 Total Noble ** 4.0E+02 6.9E+02 7.6E+02 Gas
- Notes:
- 1. = Reactor Building Elevation 303' c.nd 318' - divide concent. rations by a factor of 2. divide concentrations by a
- 2. Reactor Building Elevation 345' -
factor of 5.
- 3. Reac'or c Building air sample dose rates provided in Section 9.5.3.
** Prior to 1300 Reactor Building air activity is below MDA.
Rev. O Page 9.4.3-2 j VERMONT YANKEE NUCLEAR POWER STATION EMI.*GENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA A. Reactor Building Air Activity Co.eentrations (uci/cc)- Elevation _ .. 252'_and
. ______ ___ ____ __ 280'_- See Notes Below*
Time Isotope 1345-1400 1400-1415 1415-1430 1430-1445 I-131 5.4E-01 5.3E-01 5.2E-01 S 1E-01 I-132 3.3E-01 3.0E-01 2.8E-01 2,5E-01 I-133 9.9E-01 9.7E-01 9.4E-01 9.1E-01 I-134 1.2E-01 9.7E-02 7.8E-02 6.3E-02 I-135 7.5E-01 7.2E-01 6. 9 E-01
- 6.5E-01 Total Iodine 2.7E+00 2.6E+00 2.5E+00 2.4E+00 I-131 Dose 8.8E-01 8.7E-01 8.4E-01 8.2E-01 Equivalent Kr-83m 1.7E-01 1.6E+01 1.4E+01 1.3E+01 Kr-85m 3.4E+01 3.2E+01 3.0E+01 2.8E+01 Kr-85 2.5E+00 2.4E+00 2.4E+00 2.3E+00 Kr-87 2.0E+01 1.7E+02 1.5E+01 1.2E+01 Kr-88 c.6E+01 6.1E+01 5.6E+01 5.2E+01 Xe-133 4.4E+02 4.3E+02 g 4.2E+02 4.1E+02 Xe-135m 3.3E+01 2.3E+01 1.1E+01 5.7E+00 Xe-135 1.4E+02 1.4E+02 1.4E+02 1.3E+02 Xe-133m 1.3E+01 1.3E+01 1.2E+01 1.2E+01 Total Noble 7.SE+02 7.4E+02 .7.OE+02 6.7E+02 Gas
- Notes:
~
- 1. Reactor Building Elevation 303' and 318' - divide concentrations by a factor of 2.
- 2. Reactor Building Elevation 34f- - divide concentrations by a factor of 5.
- 3. Reactor Building air sample dose rates provided in Section 9.5.3.
Rev. O Page 9.4.3-3 j VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1991 I 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA A. Reactor Building Air Activity Concentrations (uci/cc)- I Elevation 252'_and 280'_- See Notes Below* Time
-Isotope 1445-1500 1500-1515 1515-1530 I-131 5.0E-01 4.9E-01 4.8E-01 I-132 2.3E-01 2.1E-01 1.9E-01 I-133 8.4E-01 8.6E-01 8.4E-01 I-134 5.LE-02 4.1E-02 3.3E-02 I-135 6.2E-01 6.0E-01 5 '. 7 E- 01 Total Iodine 2.3E+00 2.2E+00 2.1E+00.
g I-131 Dose. 8.0E-01 7.8E-01 7.6E-01 Equivalent i Kr-83m 1.1E+01 1.0E401 9.0E+00 Kr-85m 2.7E+01 2.5E+01 2.4E+01 Kr-85 2.3E+00 2.2E+00 2.2E+00 Kr-87 1.1E+01 9.1E+00 -7 . 7 E+ 0 0 Kr-88 4.8E+01 4.4E+01 4.1E+01 Xe-133 4.0E+02 3.9E+02 '3.9E+02 Xe-135m 2.9E+00 1.5E+00 7.8E-01 Xe-135 1.3E+02 1.2E+02 1.2E+02 Xe-133m 1. 7.E+ 01 1.1E+01 1.1E+01 Total Noble 6.4E+02 6.2E+02 6.0E+02 Gas
- Notes:
- 1. Reactor Building Elevation 303' and 318' - divide concentrations by a factor of 2.
- 2. Reactor Building Elevation 345' - divide concentrations by a factor of 5.
- 3. Reactor Building air sample dose rates provided in Section 9.5.3.
- 4. Post 1530 values continue to decline steadily with time.
{ VERMONT YANKEE NUCLEAR P0'JER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.5 RADIOLOGICAL SAMPLE DOSE RATES
, ~ - - - . . - ,
- . . . - - -- -. . . . - . - - . _ _ . - = - _ - - . - .- . - .
Rav. O Page 9.5.1-1 ( VERM0!W YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.5.1 neactor Coolant Sample Dose Rates A. Gas Samples Unshicided (mR/hr per cc)* Shielded (1 in. Icad in mR/hr per cc) A Time Contact 1 ft Contact i ft Prior to . 1030 1.4E-02 9.6E-05 1.7E-04 1.2E-06 1030-1045 3.5E+01 2.4E-01 4.3E-01 3.0E-03 1045-1100 6.7E+01 4.6E-01 8.2E-01 5.8E-03 1100-1115 1.0E+02 7.0E-01 1.2E+00 8.8E-03 1115-1130 1.3E+02 9.2E-01 1.6E+00 1.2E-02 .
#f1130-1145 1.7E+02 1.2E+00 2.1E+00 1.5E-02 1145-1200 2.9E+02 2.0E+00 3.5E+00 2.5E-02 1200-1215 3.5E+02 2.4E+00 4.3E+00 3.0E-02 1215-1230 4.1E+02 2.8E+00 5.0E+00 3.5E-02 1230-1245 4.7E+02 3.2E+00 5.7E+00 4.0E-02 1245-1300 4.9E+02 3.4E+00 6.0E+00 4.3E-02 -
1300-1315 4.7E+02 3.2E+00 5.7E+00 4.0E-02 1315-1330 4.4E+02 3.0E+00 5.3E+00 3.8E-02 1330-1345 4.1E+02 2.8E+00 5.0E+00 3.5E-02 1345-1430 3.5E+02 2.4E+00 4.3E+00 3.0E-02 1430-1530 3.8E+02 2.6E+00 4.6E+00 3.3E-02 Post 1530 values continue to decline steadily with time. Notes:
- Value must be multiplied by the sample volume in cubic centimeters-for gas samples to obtain the sample dose rate in mR/hr.
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Rav. O Page 9.5.1-2 ( VERMONY YANKEE NUCLEAR POWER STATIOh EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.5.1 Reactor Coolant Sample Dose Rates ' B. Liquid (Iodine) Unshielded (mR/hr per cc)* Shielded (1 in. lead in mR/hr per cc)* ___......_c-_____ Time Contact 1 ft Contact 1 ft Prior to 1030 1.5E-02 1.0E-04 1.9E-04 1.3E-06 1030-1045 3.7E+03 2.5E+01 4.6E+01 3.1E-01 , 1045-1100 7.3E+03 5.1E+01 9.2E+01 6.2E-01 1100-1115 1.1E+04 7.6E+01 1.4E+02 9.3E-01 1115-1130 1.5E+04 1.0E+02 1.9E+02 1.3E+00
'130-1145
. 1.9E+04 1.3E+02 2.3E+02 1.6E+00 1145-1200 1.7E+04 1.2E+02 2.1E+02 1.5E+00 1200-1230 1.6E+04 1.1E+02 2.0E+02 1.4E+00 1230-1300 1.5E+04 1.0E+02 1.9E+02 1.3E+00 1300-1315 1.3E+04 9.2E+01 1.7E+02 1.1E+00 1315-1330 1.1E+04 7.6E+01 1.4E+02 9.3E-01 1330-1345 9.4E+03 6.5E+01 1.2E+02 7.9E-01 1345-1400 8.6E+03 6.0E+01 1.1E+02 7.3E-01 1400-1415 7.4E+03 5.1E+01 9.3E+01 6.3E-01 1415-1430 7.3E+03 5.0E+01 9.1E+01 6.1E-01 1430-1445 7.1E+03 4.9E+01 8.9E+01 -6.0E-01 1445-1500 6.9E+03 4.8E+01 8.7E+01 5.9E-01 1500-1515 6.8E+03 4.7E+01 8.5E+01 5.8E-01 1515-1530 6.6E+03 4.6E+01 8.3E+01 5.6E-01
?ost 1530 values continue to decline steadily with time.
Notes:
- Values must be multiplied by the sample volume in milliliters for liquid samples to obtain the sample dose rate in mR/hr.
Rsv. O Page 9.5.2-1 VERMONY YANKEE NUCLEAR POWER STATION
/ EMERGENCY RES1'ONSE PREPAREDNESS EXERCISE 1991 9.5.2 Primary Containment Sample Dose Rates A. Gas Samples Unshielded (mR/hr per cc)* Shielded (1 in, lead in mR/hr per cc)*
Time Contact 1 ft Contact 1 ft Prior to 1200 As Read As Read As Read As Read 1200-1215 4.3E+02 3.0E+00 5.3E+00 3.8E-02 1215-1230 5.8E+02 4.0E+00 7.1E+00 5.0E-02 1230-1345 4.0E+02 2.8E+00 5.0E+00 3.5E-02 1345-1530 3.7E+02 2.6E+00 4.6E+00 3.3E-02 Post 1530 values continue to decline steadily with time. Notes:
- Values must be multiplied by the sample volume in cubic cintimeters tor gas samples to obtain the sample dose rate in mR/hr.
j Rsv. O Page 9.5.3-1 f VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.5.3 Reactor Building Air Sample Dose Rates (Iodine Cartridge Only) Elevation _______....___ 252'_and ________ 280'_- See Notes __.____.. ______ Below Unshielded (mR/hr per cc)*.._________________ Shielded (1 in. lead in mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 1300 As Read As Read As Read As Read 1300-1315 1.2E+00 8.0E-03 1.5E-02 1.0E-04 1315-1330 2.0E+00 1.4E-02 2.5E-02 1.8E-04 1330-1345 2.2E+00 1.5E-02 2.7E-02 1.9E-04 1345-1400 2.1E+00 1.4E-02 2.6E-02 1.8E-04 1400-1415 2.0E+00 1.4E-02 2.5E-02 1.8E-04 1415-1430 1.9E+00 1.3E-02 2.4E-02 1.7E-04 1430-1445 1.9E+00 1.3E-02 2.3E-02 1.6F-04 1445-1500 1.8E+00 1,2E-02 2.2E-02 1.6E-04 1500-1515 1.7E+00 1.2E-02 2.1E-02 1.5E-04 1515-1530 1.6E+00 1.1E-02 2.0E-02 1.4E-04 Post 1530 values continue to decline steadily with time. Notes:
- 1. Reactor Building Elevations 303' and 318' - divide dose rates by a factor of 2.
- 2. Reactor Building Elevation 345' - divide dose rates by a factor of 5.
- Values must be multiplied by the sample volume in cubic centimeter to obtain the sample dose rate in mR/hr.
Rev. 0 , Page 9.5.4-1 i VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.5.4 Plant Vent Stack Sample Dose Rates A. Gas (Grab Sample) Unshielded (mR/hr per cc)
- Shielded (1 in. lead in mR/hr per cc)*
Tire Contact 1 ft Contact 1 ft Prior to 1300 ** As Read As Read As Read As Read 1300-1315 3.1E+00 2.2E-02 3.9E-02 2.8E-04 1315-1330 5.7E+00 4.0E-02 7.0E-02 5.0E-04 1330-1345 6.3E+00 4.4E-02 7.7E-02 5.5E-04 1345-1400 6.3E+00 4.4E-02 7.7E-02 5.5E-04 1400-1415 6.0E+00 4.2E-02 7.4E-02 5.3E-04
.415-1430 5.7E+00 4.0E-02 7.0E-02 5.0E-04 1430-1445 5.4E+00 3.8E-02 '5.7E-02 4.8E-04 1445-1500 5.4E+00 3.8E-02 6.7E-02 4.8E-04 1500-1515 4.8E+00 3.4E-02 6.0E-02 4.3E-04 1515-153C 4.8E+00 3.4E-02 6.0E-02 4.3E-04 Psst 1530 values continue to decline steadily with time.
I Notes: *Value must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rates in mR/hr.
** Plant vent stack sample dose rates remain constant from 0700-1300 given the same sample volume.
l l
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Rev. O Page 9.5.4-2 f VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.5.4 Plant Vent Stack Sarple Dose Rates B. Air Sample (Iodine Cartridge) 1 Unshielded (mR/hr per cc)* Shielded (1 in, lead in mR/hr per ec)* Time Contact 1 ft Contact 1 ft Prior to As Read 1300 ** As Read As Read - As Road 1300-1315 1.7E-03 1.2E-05 2.1E-05 1.5E-07 1315-1330 2.8E-03 2.0E-05 3.5E-05 2.5E-07 1330-1345 3.1E-03 2.1E-05 3.8E-05 2.7E-07 1345-1400 3.0E-03 2.1E-05 3.7E-05 2.6E-07
**00-1415 2.9E-03 2.0E-05 3.6E-05 2.6E-07 1415-1430 2.8E-03 1.9E-05 3.5E-05 2.4E-07 1430-1445 2.6E-03 1.8E-05 3h3E-05 2.3E-07 1445-1500 2.5E-03 1.8E-05 3.2E-05 2.2E-07 1500-1515 2.5E-03 1.7E-05 3.1E-05 2.2E-07 2.3E-03 1.6E-05 2.9E-05 2.0E-07 1515-1530 Post 1530 values continue to decline steadily with time.
Notes: *Value must be multiplied by the sample volume in cubic contimeters to obtain the sample dose rates in mR/hr.
** Plant vent stack sample dose rates remain constant from 0700-1300 given the same sample volume.
l
. -,.---. _. , ~ _ , . . , _ - - . _ _ - . _ - . _ - - . - - .
k Rev. O Page 9.5.4-3 VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.5.4 Plant Vent Stack Sample Dose Rates C. General Area Exposure Rates at Stack (R/hr) Time At Stack Door Inside Prior to 1300 As Read
- As Read
- 1300-1315 1 10 1315-1330 2 20 1330-1345 2.5 25 1345-1400 2.5 23 1400-1415 2 21 1415-1430 2 20 1430-1445 2 18 1445-1500 2 17 1500-1515 2 16 1515-1530 1.5 15 Post-1530 Dose Rates Continue to Decline
- Background as read on survey meter.
. . = - - - . . - . - ..- - - - - - - - - - - . . . . _ . . . . . . - . . - . . _ . .-.. . ..-
1 VERMONT YANKEE NUCLEAR FCVER STATION EMERGENCY RESPONSE P17E?AREDNESS EXERCISE 19S} e 9.6 FIANT VENT STACK RELEASE P6 1 s 9 9 h* l I \ t-l
1 Rev. O Page 9.6-1 (- VERMOh. .. JKEE NUCLEAR POWER STATION EMERGENC~. RLSPONSE PREPAREDNESS EXERCISE 1991 9.6 PLANT VENT STACK RELEASE DATA A. Plant Vent Stacx Activity Release Concentrations (uC1/cc)
- Time Isotope Prior to 1300 1300-1315 1315-1330 I-131 . 3.3E-13 3.9E-04 7.0E-04 I-132 4.8E-13 3.0E-04 5.0E-04 I-133 7.5E-13 7.3E-04 14 3E-03 I-134 6.6E-13 1.6E-04 2.3E-04 I-135 6.3E-13 5.8E-04 1.0E-03 Total Iodine 2.9E-12 2.2E-03 3.7E-03 I-131 Dose 6.1E-13 6.5E-04 1.2E-03 Equivalent Kr-83m ** 2.9E-01 4.9E-01 Kr-85m ** 5.4E-01 9.3E-01 Kr-85 ** 3.5E-02 6.3E-02 Kr-87 ** 4.3E-01 6.7E-01 Kr-88 ** 1.1E+00 1.9E+00 Xe-133 s* 6.2E+00 1.1E+01 Xe-135m ** 6.5E-01 9.6E-01 Xe-135 ** 2.0E+00 3.6E+00 Total Noble ** 1.1E+01 2.0E+01 Gas i
s
- Activity concentrations (in uCi/cc) may be converted to activity release rates (uci/sec) by multiplying by the assumed stack flow rate of 4.9E7 cc/sec.
** Noble gas release rates are minimal at this time and below MDA of the multi-channel analyzer.
Note: Plant vent stack sample dose rates provided in Section 9.5.4.
. -- - - - - -~. - - - _ _ . - . _ . . . - _
Rev. O f Page 9.6-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.6 PLANT VENT STACK RELEASE DATA A. Plant Vent Stack Activity Release concentrations (uci/cc)
- Time Isotope 1330-1345 1345-1400 1400-1415 1415-1430 I-131 7.7E-04 7.8E-04 7.7E-04 7.5E-04 I-132 5.1E-04 4.8E-04 4.4E-04 4.0E-04 I-133 1.4E-03 1.4E-03 1.4E-03 1.4E-03 I-134 2.1E-04 1.7E-04 1.4E-04 1.1E-04 I-135 1.1E-03 1.1E-03 1.0E-03 9.9E-04 Total Iodine 4.0E-03 3.9E-03 3.8E-03 3.6E-03' I-131 Dose 1.3E-03 1.3E-03 1.2E-03 1.2E-03 1 Equivalent r
l Kr-83m 5.2E-01 5.0E-01 4.6E-01 4.1E-01 Kr-85m 9.9E-01 9.7E-01 9.2E-01 8.7E-01 Kr-85 7.0E-02 7.1E-02 7.0E-02 6.9E-02 Kr-87 6.4E-01 5.7E-01 4.9E-01 4.2E-01 Kr-88 2.0E+00 1.9E+00 1.8E+00 1.6E+00-Xe-133 1.2E+01 1.2E+01 1.2E+01 1.2E+01 Xe-135m 9.8E-01 9.6E-01 6.7E-01 3.4E-01 Xe-135 4.0E+00 4.1E+00 4.1E+00 4.0E+00 Total Noble 2.2E+01 2.2E+01 2.1E+01 2.0E+01 cac
- Activity concentrations (in uCi/cc) may be converted to activity release rates (uci/sec) by multiplying by the assumed stack flow rate of 4.9E7 cc/sec.
Note: Plant vent stack sample dose rates provided in Section 9.5.4.
Rev. 0 ( Page 9.6-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.6 PLANT VENT STACK RELEASE DATA A. Plant Vent Stack Activity Release Concentrations (uCi/cc)
- Time Isotope 1430-1445 1445-1500 1500-1516 1515-1530 **
I-131 7.3E-04 7.2E ^4 7.0E-04 6.9E-04 I-132 3.6E-04 3.3E-04 3.0E-04 2.7E-04 I-133 1.3E-03 1.3E-03 1.2E-03 1.2E-03 I-134 9.1E-05 7.3E-05 5.8E-05 4.7E-05 I-135 9.4E-04 9.0E-04 8.6E-O4 S.2E-04 Total Iodino 3. 4 E-03 3.3E-03 3.2E-03 3.0E-03 I-131 Dose 1.2E-03 1.2E-03 1.1E-03 1.1E-03 Equivalent Kr-83m 3.7E-01 3.3E-01 2.9E-01 2.6E-01 Kr-83m 8.2E-01 7.7E-01 7.2E-01 6.8E-01 Kr-85 6.7E-02 6.6E-02 6.4E-02 6.3E-02 Kr-87 3.6E-01 3.1E-01 2.GE-01 2.2E-01 Kr-88 1.5E+00 1.4E+00 1.3E+p0 1.2E+00 Xe-133 1.2E+01 1.2E+01 1.1E+01 1.1E+01 Xe-135m 1.8E-01 9.6E-02 5.7E-02 3.8E-02 Xe-135 3.8E+00 3.7E+00 3.5E+00 3.4E+00 Total Noble 1.9E+01 1.9E+01 1.7E+01 1.7E+01 Gas
- Activity concentrations (in uCi/cc) may be converted to activity release rates (uci/sec) by multiplying by the assumed stack flow rate of 4.9E7 cc/sec.
** Post 1530 values continue to decline steadily with time.
Note: Plant vent stack sample dose rates provided in Section 9.5.4.
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i b {- f VERMONT YANKEE INCLEAR P0k'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 ; t 9.7 FIELD MONITORING MAPS AND DATA l' b p I s b d e-e r - -r,~n,,r-o-== . rw r- - - = -- e~rvrec-. c w- x- vn~--r,- .esr. co.- e er----..---w w <wvn---,e-- e- ,re rw- --e- w -,-m,,,www--- - , , --n~- - - - - -- --- - - J
P Rev. O Page 9.7 1 : . I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.7 FIELD MONITORING MAPS AND DATL Plume whole body dose rates and radiciodine concentrations have been estimated as a function of time and distance from the plant site using a variable trajectory dose assessment model (HETPAC). Geographical representations of the plume are provided in this section for each 15 minute average of the meteorological conditions, starting at clock time 1308. During the exercise, field team observers will use the information contained in this section to provide field monitoring te r.ms with the appropriate survey results and radiological data for various times and locations. i The designated field monitoring teams will be directed to monitor and track the plume relative *o the meteorological conditions postulated for the scenario. Figures 9.7-l'through 9.7 11 depict the plume location at various times throughout the scenario. These figures represent a plume width which is equivalent to a 3-sigma value of the centerline conditions. Since the figures show a plume width relative to the centerline, survey results were calculated for various color coded map areas (blue, yellow, and green). Field data tables have been dweloped for Vermont Yankee and State of Vermont field monitoring teawe. The tables contained the radiological data to be provided to the field monitoring teams for various times and locations. (The tables follow the figure for a given scenario time period.) Radiological data on the tables have been provided for each plume segment and colored map area shown on the associated figures. Radiological data for locations be tween two plume segments can be estimated by extrapolating between the values for those segments.
. ~. . . . . - - _. _ . . . . _ _ _ _ _ . . . - _. -_ _ - - _ _ . - ,
Rev. O Page 9.7-2 , F Prior to the exercise, training will be provided to field monitoring observers on the use of the figures and tables. The field monitoring observers should use the following specific instructions:
- 1. As field monitoring teams are dzsignated , check that the appropriate ,
procedures are followed by team members. This vill include the , initial equipment check.
- 2. While traveling to assigned monitoring locations, or while traversing the plume, or at assigned monitoring locations, use the attached figures and tables to issue appropriate radiological data.
- 3. Attempt to estimate the team's accrued radiation exposure as a function of time spent in an affected area. Use the values provided for the PIC 6 or the closed window, waist level reading for the gamina dose rate. Do not issue pocket dosimeter results to team cenibers ,
{ unless they actually simulate checking their dosimeter reading. The pocket dosimeters have specific ranges and intervals in mR or R values. Ask them the - re.nges associated with the pocket dosimeter utilized. Attempt to provide values that reflect the team's accrued exposure and range of the pocket dosimeter. 4 Ask the field monitoring teams what equipw. they have available for their use. Ask them the scales associated with the equipment log the answers to ensure that you do not provide them with data which is not consistent with the range of the equipment. If a situation occurs where the lower range or upper range of the equipment is exceeded, issue them an "off-scale low" value and "off scale high" value, respectively. l l
. . , . . - - ,_ .- , , , _ .. -_, .- _ , _ ~ - . -
Rev. O Page 9.7-3
- 5. For gamma (whole body dose rates) survey readings taken by field monitoring teams, the following information should be use:
- a. If an RM-14/HP-210 is used to track the plume, the meter count rate of 3,500 cpm on the RM-14/HP-210 is equivalent to approximately 1.0 mR/hr. Therefore, 14 mR/hr will cause the RM 14/HP-210 to read "off-scale high." The upper range of the RM 14/HP-210 is 50,000 cpm.
- b. Whenever a team takes a " ground level" survey, the results should be the same as the " waist level" survey.
- c. Certain field monitoring teams may take open vindow and closed window readings with their dose rate survey meters. If a team is located in the plume and air concentration is greater than zero, assume the open window reading is two times the closed window reading for the gamma dose rate reading.
- 6. For air sample measurements taken by field monitoring teams , t :..
following information should be use:
- a. The field monitoring teams will substitute a charcoal cartridge instead of the adsorber media cartridge (silver zeolite) contained in the field monitoring kits. All air sample data vill e
be given as though the adsorber media cartridges (silver zeolite) were bein5 used in the kits.
- b. Air sample volume assumptions have been used in the calculation of the net count rates for the air sample results. The sample volume was assumed to be 100 liters for both Vermont Yankee and State of Vermont field monitoring teams. If different volumes are collected, the air sample data provided in the cabics should be adjusted proportionally.
l l
Rev. 0 Page 9.7 4 (
- c. Air sample net count rates for the absorber media cartridges (silver zeolite) provided in the field data tables have been developed using METPAC thyroid dose rate projections. The formula used is as follows:
ConcI-131 (UCi/cc) = "Ex VxT'#'A" x 4 . 5 E-10 uC1-1/ dpm- cc where: E- Instrument- Detector Efficiency in cpm /dpra (counts per disintegration) V- Flow rate of sample in ipm (liters per minute) T- Sample collection time in minutes
. For air sample net count rate for the particulate filter paper, it is assumed that a G M survey meter is used to obtain the sample count rates. Filter count rates (cpm) were estimated from
- the I-131 air concentration for a 100 liter sample volume.
NOTE: THE PLUME PLOT FIGURES ARE GRAPHIC REPRESENTATIVES OF ATMOSPHERIC DISPERSION. LARCER FIGURES WILL BE aVAILABLE TO OBSERVERS FOR THEIR USE ON PROVIDING DATA TO FIELD MONITORING TEAMS. 2-__-_
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PACE 9.7-5A TABLE 9.7.1 . ON-SITE VERMONT YANKEE FIELD DATA AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM 14** SAM II RM-14*** CONC. PARTICULATE CLOCK MAP PIC-6 RM 14 I-131 SILVER ZEOLITE FIUTER TIME AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) 55bh5555 ~~blEb" ~~~~~)6b" " bhE~ ' " "b$bbE+bb~~~Edb"~~~5"kkkb ~~~k5b"~~ YELLOW 76 OSH 0.00E+00 <40 AS READ <40
. CREEN 8 26600 0.00E+00 <40 AS READ <40, 8315-1330 BLUE 1400 OSH 0.00E+00 <40 AS READ <40 YELLOW 140 OSH 0.00E+00 <40 AS READ <40 GREEN 14 49000 0. 00E+ 00 <40 AS READ <40 1330-1345 BLUE 1500 OSH 0.00E+00 <40 AS READ <40 YELLOW 150 OSH 0.00E+00 <40 AS READ <40 GREEN 15 OSH 0.00E+00 <40 AS READ <40 1345 1400 BLUE 1500 OSH 0.00E+00 <40 AS READ <40 YELLOW 150 OSH 0.00E+00 <40 AS READ <40-GREEN 15 OSH 0.00E+00 <40 AS READ <40 1400-1415 BLUE 1500 OSH 0.00E+00 <40 AS READ <40 YELLOW 150 OSH 0.00E+00 <40 AS READ <40 GREEN 15 OSH 0.00E+00 <40 AS READ <40 1415 1430 BLUE 1470 OSH 0.00E+00 <40 AS READ <40 YELLOW 147 OSH 0.00E+00 <40 AS READ <40 GREEN 15 OSH 0.00E+00 <40 AS READ <40 1430-1445 BLUE 1470 OSH 0.00E+00 <40 AS READ <40 YELLOW 147 OSH 0.00E+00 <40 AS READ <40 CREEN 15 OSH 0.00E+00 <40 AS READ <40
( 1445-1500 BLUE 1340 OSH 0.00E+00 <40 AS READ <40 YELLOW 134 OSH 0.00E+00 <40 AS READ <40 GREEN 13 46900 0.00E+00 <40 AS READ (40 1500-1515 BLUE 1000 OSH 0.00E+00 <40 AS READ <40 YELLOW 100 OSH 0.00E+00 <40 AS READ <40 GREEN 10 35000 0.00E+00 <40 AS READ <40 1515 1530 BLUE 930 OSH 0.00E+00 <40 Ar READ <40 YELLOW 93 OSH 0.00E+00 <40 AS READ <40 GREEN 9 32550 0.00E+00 <40 AS READ <40 l l NOTES:
-
- Air sample data are based on a sample volume of 100 liters. ~ If different volumes are collected, the air sample data provided in the tables should be adfusted proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas collected provide the rcinstead of 100
.ulting value to liters,
, the players. l
** The RM 14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge. Therefore, I-131 conc. (uci/cc) X 5.6E+09 will calculate l ;e the net sample count rate in epm on the silver zeolite cartridge. . *** The particulate filter sample count rate (epm) was estimated from the I 131 air - concentration for a 100 liter sample.
l^ OSH off-Scale High (Count rate higher than the upper scale of the instrumentation).
- ?
l
PAGE 9.7-5B PAGE INTENTIONALLY LEFT DLANK NOTE: STATE OF VERMONT FIELD DATA IS NOT REQUIRED FOR ON-SITE * (PROTECTED AREA) PLANT SURVEYS t I 1 l l
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PAGE 9.7-6A TABLE 9.7.2a VERMONT YANKEE FIELD DATA AT CLOCK TIME 1308-1315 (SCENARIO TIME 6:08 - 6:15) AIR S AMPLI DATA (100 LITERS)* GAMMA DOSE RATE RM 14** SAM II RM-14*** CONC. PARTICULATE PLUME FILTER SECMENT DISTANCE MAP PIC-6 RM 14 1-131 SILVER ZEOLITE AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) No. (MILES)
i$b0 ~ ~ biTb' ~ ~ bLbb' ~ ~ ~ ~ ~ bbb' 'bbb' 'd$3hk'5b~~"kbb'~Eb~Rbb 4.32E 11 <40 AS READ
~~~kbb'
<40 BOUNDARY YELLOW 80 OSH 8 28000 4.32E 12 <40 AS READ <40
. GREEN 1500 3.46E-07 1936 5807 1383 2.00 0.60 BLUE OSH 194 581 138 YELLOW 150 OSH 3.46E-08 i
15 OSH 3.46E-09 <40 58 <40 GREEN f i 4 i 4 l J i i ( Y e NOTES:
- Air sample data are based on a sample volume of 100 liters. If different volumes il are collected, the air sample data provided in the tables should instead be adjusted of 100 liters, proportionally. For example the value given in the table by 2 (two)ple , if a 50 liter sam and provide was the re:ulting value to collected divide
- the players
~d ** The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the j silver =colite cartridge. Therefore, I-131 cone. (uC1/ce) X 5.6E409 will calculate j the net s ample count rate in epm on the silver zeolite cartridge.
$ *** The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample.
- OSH Off-Scale High (Count rate higher than the upper scale of the instrumentation).
. - . . . - . . . . ~ . . _ - . . _ . . _ -. - _- _. - __ - _ . _ .. _. . . . . ~ . - .
PAGE 9.7 6B TABLE 9.7.2b STATE OF VERMONT FIELD DATA AT CLOCK TIME 1308-1315 (SCENARIO TIME 6:08 6:15) GAMMA SURVEY DATA AIR SAMPLE DATA (100 LITERS)* WAIST AND GROUND LEVEL READINCS LUDLUM 2220 G M METER PLUME CLOSED OPEN CONC. AGX 2** PARTICULATE *** SEGMENT DISTANCE MAP WINDOW WINDOW I 131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) ~ uCi/cc (NET CPM) ~ (NET CPM)
~~~i[b0 ~~55Tk' Ebbb~ ~~~~~5bb Ebbb " 4$55b5b~~Eb~REkb ~~kbb'~~~
BOUNDARY YELLOW 80 160 4.328 11 AS READ <50
. GREEN 8 16 4.372-12 AS READ <50 0.60 1500 3000 3.46E-07 6222 1383 2.00 BLUE 3.46E 08 622 138 YELLOW 150 300 GREEN 15 30 3,46E 09 62 <50 r
NOTES:
- Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instea'd of 100 liters, divide the value given in the table by 2 (two) and provide the resulting value to the players.
** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 cpm /dpm with g
the AGX-2 cartridge. Therefore, I 131 cone. (uci/cc' X 1.8E+10 will calculate the
- the net sample count rate in cpm on the AGX-2 cartridge.
*** For analysis of the particulate filter it is assumed that a C-M survey meter is used to obtain the sample count rates. The Illter count rate was estimated from the I-131 air concentration for a 100 liter sample volume.
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PAGE 9.7-7A TABLE 9.7.3a , VERMONT YANKEE FIELD DATA AT C1hCK TIME 1315-1330 (SCENARIO TIME 6:15 - 6:30) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM-14** SAM-II RM-14*** CONC. PARTICULATE PLUKE FILTER SEGMENT DISTANCE MAP PIC 6 RM-14 I-131 SILVER ZEOLITE AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) NO. (MILES) ~~~~
~ ~~ii5b' 'bhH ~5$5bb$5h ~ ~ ~kdb~ 'Eh~k'kbE - ~~~E5b~~~
~i$b0 ~~EiTb' ~~BLbk" 3.40E-11 <40 AS READ <40 BOUNDARY YELLOW 13.5 OSH GREEN 14 47250 3.40E-12 <40 AS READ <40 2500 3.63E-07 2033 6096 1452 2.00 0.60 BLUE OSH 610 145 YELLOW 250 OSH 3.63E-08 203 GREEN 25 OSH 3.63E-09 <40 61 <40 1.20 1300 OSH 9.26E-07 5185 15556 3704 3.00 9.26E-08 519 1556 ~370 130 OSH
<40 13 45500 9.26E-09 52 156 i
l l r NOTES:
- Air sample data are oased or a sample volume of 100 liters. If different volumes are collecteu, the air sample dcta provided in the tables should be ad usted proocrtionally. For example, if a 50 liter sample was collected instea of 100 liters, divide the value given in the table by 2 (two) and prowide the resulting value to the players.
** The RM-14 detector efficiency for I 131 was assumed to be 0.025 cpm /dpm with the silver zeolite-cartrid e-f Therefore, I-131 conc. (uC1/ce) X 5.6E+09 v111 calculate the net sample counc rate ir epm on the silver zeolite cartridge.
*** The particulate filter semple count rate (cpm) was estimated from the I-131 air concentracion for a 100 liter sample.
OSH Off-Scale High (Count rate higher than the upper scale of the instrumentation).
_ _ . _ . _ _. _. - . _ _ . - _ m . _ PAGE 9.7-7B TABLE 9.7.3b ( STATE OF VERMONT FIELD DATA AT CLOCK TIME 1315-1330 (SCENARIO TIME 6:15 6:30) 2
+
GAMMA SURVEY DATA AIR SAMPLE DATA (100 LITERS)*
+
WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G.M METER l PLUME CLOSED- OPEN CONC. AGX.2** PARTICULATE *** SEGMENT DISTANCE MAP VINDOW WINDOW I.131 CARTRIDGE FILTER
.) NO. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM)
(NET CPM) i 1.00 SITE BLUE 1350 2700 3.40E.10 AS READ <50 1 BOUSD;lY YELIDW 135 270 3.40E-11 AS READ <50 14 27 3.40E.12 AS READ <50
]4 GREEN 2.00 0.60 -BLUE 2500 5000 3.63E.07 6533 1452
. *) 250 500 3.63E.0d 653 145 YELLOW
. GREEN 25 50 3.63E.09 65 <50
.j 3.00 1.20 BLUE 1300 2600 9.26E.07 16667 3764 YELLDW 130 260 9.26E.08 1667 370 2
GREEN 13 26 9.26E.09 167 <50 -1
). >l
'i - 5 l - ,l I i -5' NOTES:
^
- Air sample data are based on a sample volume of 100 liters. If different volumes
- are collected, the air sample data provided in the tables should be ad usted
. proportionally. For example, if a 50 liter samnle was collected instea of 100 liters,
; divide the value given in the table by 2 (two)'and provide the resulting value to
; the players.
* ** The the ACX-2Ludlumcartridge.
2220 detector ef f'ciency Therefore, forI.131wasassumedtobe0.080e!$opmwith I-131 conc. uCi /cc) X 1.8E+10 vill cal ate the
] the net sample count rate in cpm on the AGX- cartridge.
'! . *** For analysis of the particulate filter it is assumed that a G-M survey meter is used to obtain the sample count rates. The filter count rate was estimated from the
'- I-131 air concentration for a 100 liter sample volume.
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1 l 1 PAGE 9.7-8A j TABLE 9.7.4a VERMONT YANKEE FIELD DATA AT CLOCK TIME 1330-1345 (SCENARIO TIME 6:30. 6:45) AIR SAMPLE DATA (100 LITEhS)* GAMMA DOSE RATE RM-14** SAM II RM-14*** PLUME CONC. PARTICULATE SECMENT DISTANCE MAP PIC 6 RM-14 I-131 SILVER ZEOLITE FILTER NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM)
~~~i$b0 ~~5iTk'~~5Lbb ~~~~5bb' 'bhb' 1$6bb55b~~'kbb'kh'Rbkb
<40
~EEb
<40 BGJNDARY YELLDV 140 OSH 1.60E-11 AS READ GREEN 14 49000 1.60E-12 <40 AS READ <40 2.00 0.50 BLUE 2500 OSH 1.89E-07 1058 3173 756 YELLOW 250 OSH 1.89E-08 106 317 76 GREEN 25 OSH 1.89E-09 <40 AS READ <40 3.00 1.10 BLUE 1300 OSH 1.76E-06 9852 29556 7037 YELLOW 130 OSH 1.76E-07 985 2956 704 GREEN 13 45500 1.76E-08 99 296 70 4.00 1.70 BLUE 820 OSH 5.25E 07 2942 8825 2101 YELLOW 82 OSH 5.25E-08 294 883 210 GREEN 8 28700 5.25E 09 <40 68 <40
( s NOTES:
- Air sample data are based on i sample volume of 100 liters. If different volumes are collected, the air sample d-ta provided in the tables should be adfusted proportionally. Forgiven the value ey. ample, in theiftable a 50 by liter2sam (two)ple andwas collected provide instead of the resulting value100toliters, divide the players.
=* The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge. Therefcre, 1-131 cone. (uci/cc) X 5.6E+09 v111 calculate the net sample count rate in cpm on the silver zeolite cartridge.
*** The particulate filter sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter sample.
OSR Off-Scale High (Count rate higher than the upper scale of the instrumentation).
PACE 9.7.PB
- TABLE 9.7.4b
( 6:45) STATE OF VERMONT FIELD DATA AT CLOCK TIME 13301345 (SCENARIO TIME 6:30 GAMMA SURVEY DATA AIR SAMPLE DATA (100 LITERS)* WAIST AND GROUND LEVEL READINGS UUDLUM 2220 G.M METER PLUME- CLOSED OPEN CONC. AGX.2** PARTICULATE *** SEGMENT DISTANCE MAP WINDOW VINDOW 1 131 CARTRIDGE FILTER NO. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM) 1.00 SITE BLUE 1400 2000 1.60E.10 AS READ <50
. BOUNDARY YELLOW 140 280 1.60E-ll AS READ <30 GREEN 14 28 1.60E-12 AS READ <50 2.00 0.50 BLUE 2500 5000 1.89E.07 3400 756 YELLOW 250 500 1.89E.08 340 76 GREEN 25 50 1.89E.09 AS READ <50 3.00 1.10 BLUE 2600 $200 1. 7 e E. 06 31667 7037 YELLOW 260 520 1.76E.07 3167 704 GREEN 26 52 1.76E.08 317 70 4.00 1.70 BLUE 820 1640 5.25E-07 9456 2101 YELLOW 82 164 5.25E.08 946 210 GREEN 8 16 5.25E.09 95 <50 1
.. i i' NOTES:
- Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example. if a 50 liter sam divide the value given in the table by 2 (two)ple andwas collected provide instead of the resulting value 100toliters.
the playets. I I ** The the Ludlum 2220 detector AGX.2 cartridge. efficienef Therefore, I. 31forI-131wasassumedtobe0.080ebuatedpm conc. (uCi/ce' X 1.8E+10 will cal with the the net sample count rate in cpm on the AGX.2 cartridge.
*** For analysis of the particulate filter it is assumed that a G-M survey meter is used to obtain the sampic count rates. The Illter count rate was estimated from the I-131 air con:entration for a 100 liter sample volume.
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PAGE 9.7-9A
. TABLE 9.7.5a i
VERMONT YANKEE FIELD DATA AT CLOCK TIME 1345-1400 (SCENARIO TIME 6:45 - 7:00) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM-14** SAM II RM-14*** PLUME CONC. PARTICULATE , SECMENT DISTANCE MAP PIC 6 RM-14 I-131 SILVER ZEOLITE FILTER
; NO. (MILES) AREA (mR/hr) (CPM)
' ~
uCi/cc (NET CPM) (NET CPM) (NET-CPM)
~~~i$b0 ~ ~ hETk' BLbE' 56bb' 'bhH 5$95k25b~~~Edb''E5'kkkb EEb' , BOUNDARY YELLOW 160 OSH 5.93E 11 <40 AS READ <40 GREEN 16 OSH 5.93E-12 <40 AS READ <40 l
l- 2.00 0.60 BLUE 3160 OSH 5.99E 07 3353 10059 2395
! YELLOW 316 OSH 5.99E-08 335 1006 240 GREEN 32 OSH 5.99E-09 <40 101 <40 2 3.00 1.10 BLUE 3000 OSH 2.00E-06 11200 33600 8000 YELLOW 300 OSH 2.00E-07 1120 3360 800 1 GREEN 30 OSH 2.00E-08 112 336 80 4.00 1.70 BLUE 1500 OSH 9.57E-07 5_'58 ; '4 3827 -l YELLOW 150 OSH 9.57E 08 516 .eu? 383 GREEN 15 OSH 9.57E-09 S t. 161 <40 ! 5.00 2.30 BUUE 530 OSH 3.19E-07 1764 5351 1274
-l YELLOW 53 OSH 3.19E-08 178 535 127 CREEN 5 18550 3.19E-09 <40 54 <40 t i i 5 i k' 1 NOTES:
.
- Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted
; proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas provide collected instead of the resulting 100toliters, value the players, d ** The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the 1 silver reolite cartridge. Therefore, I-131 conc. (uC1/cc) X 5.6E+09 vill calculate the net sample count rate in cpm on the silver zeolite cartridge. . *** The particulate filter sample count rate (cpm) was estimated from the'I-131 air concentration for a 100 liter sample.
OSH Off-Scale High (Count rate higher than the upper scale of the instrumentation).
PAGE 9.7-9B TABLE 9.7.5b
.l. 7:00)
STATE OF VERMONT FIELD DATA AT CLOCK TIME 1345 1400 (SCENARIO TIME 6:45 CAMMA SURVEY DATA AIR SAMPLE DATA (100 LITERS)*- WAIST AND GROUND LEVEL READINGS LUDLUM 2220 G.M METER PLUME CLOSED OPEN CONC. AGX.2** PARTICULATE *** WINDOW WINDOW I 131 CARTRIDGE FILTER SEGMENT DISTANCE MAP NO. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET GPM) (NET CPM) SITE 1600 3200 5.93E.10 AS READ <50 1.00 BLUE 5.93E-11 AS READ <50
. BOUNDARY YEL1DW 160 320 GREEN 16 32 5.93E.12 AS READ <50 0.60 3160 6320 5.99E 07 10778 2395 2.00 BLUE 632 5.99E.08 1078 240 YELLOW 316 '
GREEN 32 63 5.99E 09 108 <50 3.00 1.10 BLUE 3000 6000 2.00E.06 36000 8000 YELLOW 300 600 2.00E.07 3600 800 GREEN 30 60 2.00E.08 360 80 1.70 1500 3000 9.57E.07 17222 3827 4.00 BLUE 9.57E.08 1722 383 YELLOW 150 300 GREEN 15 30 9.57E-09 172 <50 2.30 530 1060 3.19E-07 5733 1274 5.00 BLUE 3.19E.08 573 127 YELLOW 53 106 GREEN 5 11 3.19E.09 57 <50 J i NOTES:
- Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally.
divide -Se value For example, given in the iftable a 50by liter sam andwas 2 (two)ple provide collectedthe resultinginstead value of 100toliters , the players. forI131wasassumedtobe0.080e!$atethedpm with
** Thethe Ludlum AGX-2 cartridge. 2220 -detector efficiene[31 Therefore, I. conc. (uci/cc) X 1.8E+10 will caI 3
the net sample count rate in cpm on the AGK-2 cartridge.
*** For analysis of the particulate filter it is assumed that a G-M survey meter is used to obtaih the sample count rates. The lilter count rate was estimated from the I-131 air concentration for a 100 liter sample volume.
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PACE 9.7-10A-TABLE 9.7.6a I VERMONT YANKEE FIELD DATA AT CLDCK TIME 1400 1415 (SCENARIO TIME 7:00 - 7:15) AIR SAMPLE DATA (100 LITERS)*-
-CAMMA DOSE RATE RM 14** SAM 11 RM 14***
PLUME CONC. PARTICULATE SECMENT DISTANCE MAP PIC 6 RM 14 I 131 SILVER ZEOLITE FILTER NO. (MILIS) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM)
~5.~b0 ~~b5TE'~~ELbb' '55bb' 'bhH 'k$55k$5b~ Ebb~~hRbb kEb ~
BOUNDARY YELLOW 150 OSH 8.33E 11- <40 AS READ <40 CREEN 15 OSH 8.33E 12 <40 AS READ <40 2.00 0,60 blue . 2900 OSH 6.79E 07 3802 11407 2716 YELLOW 290 OSH 6.79E-08 380 1141 272-CREEN 29 OSH 6.79E-09 <40 114 <40 3.00 1.20 BLUE 2800 OSH 1,91E 06 10716 32148 '/654 YELLOW 280 OSH 1.91E 07 1072 3215 765 GREEN 28 OSH 1.91E 08 107 321 77 4.00 1.70 BLUE 1700 OSH 1.11E 06 6222 18667 4444 YELLOW 170 OSH 1.11E-07 622 1867 444 CREEN 17 OSH 1.11E-08 62 187 44 5.00 2.30: BLUE 950 OSH 5.68E 07 3180 9541 2272 YELLOW 95 OSH 5.68E 08 318 954 227 CREEN 10 33250 5.68E-09 <40 95 <40 6.00 2.90 BLUE 360 OSH 2.10E-07 1175 3526 840 YELLOW 36 OSH 2.10E 08 118 353 84 GREEN 4 12600 2.10E 09 <40 AS READ <40 .g-
- l
>i 'l NOTES:
,'
- Air sample data are based on a sample volume of 100 liters. If dif ferent volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sample was collected instead of 100 liters, divide the value given in the table by 2 (two) and provide the reculting value to
- .the players.
** The RM-14 detector efficiency for I-131 was assumed to be 0.025 com/dpm with the silver zeolite cartridge. Therefore. I-t31 conc. (uC1/cc) X 5.6E+09 will calculate j
the net sample count rate in epm on thr silve zeolite cartridge.
*** The particulate filter sample count rate (cpm) was estimated from the I 131 air concentration for a 100 liter sample.
OSH ^ Off-Scale High (Count-rate higher than the upper scale of the instrumentation).
, - , , . - . . , . . - . -- , , -. . -y., , , _ . - ,, ,,1 --.-.
I PACE 9.7-10B TABLE 9.7,6b
,' STATE OF VERMONT FIELD DATA AT CLOCK TIME 1400-141. ' SCENARIO TIME 7:00 - 7:15) i CAMMA SURVEY DATA .IR SAMPLE DATA (100 LITERS)*
- WAIST AND CROUND LEVEL READING', LUDLUM 2220 C M METER l PLUME CLOSED OPEN CONC. AGX-2** PARTICULATE ***
SECMENT DISTANCE MAP VINDOW VINDOW I-131 CARTRIDGE FILTER I .... .. fh . .. h. .I 5.. I 5.. ..I $$. f. . .. 1;00 0.30 BLUE 1500 3000 8.33E 10 AS READ ,<50 a . YELLOW 150 300 8.33E-11 AS READ <50 l- GREEN 15 30 8.33E-12 AS READ <50 t
$ 2.00 0,60 BLUE 2900 5800 6.79E-07 12222 2716 4 YELLOW 290 580 6.79E 08 1222 272 l GREEN 29 58 6.79E-09 122 <50 j 3,00 1.20 BLUE 2800 5600 1.36E-06 33444 7432
? YELLOW 280 560 1.86E-07 3344 743 4
CREEN 28 56 1.86E 08 334 74 I 4,00 1.70 BLUE 1700 3400 1.11E-06 20000 4444
' YELLOW 170 340 1.11E-07 2000 444 CREEN 17 34 1.11E-08 200 <50 4
l 5.00 2.30 BLUE 950 1900 5.68E-07 10222 2272 i YELLOW 95 190 5.68E 08 1022 227 GREEN 10 19 5.68E-09 102 <50 j 6.00 2.90 BLUE 360 720 2.10E 07 3778 840 J- YELLDW 36 72 2.10E 08 378 84 3 GREEN 4 7 2.10E-09 AS READ <$0 J
~3 i
?
i
'J 3 NOTES:
d
- Air sample data are based on a sample volume of 100 liters. If different volumes
. # are :ollected, the air sample data provided in the tables should be adjusted
- j proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas collectedresulting provide-the instead of 100toliters, value
; the players.
'5 .
** The Ludlum 2220 + .ector efficiency for I-131 was assumed to be 0.080 cpm /dpm vish the AGX-2 cartrioge. Therefore. I-131 conc. (uC1/cc) X 1.8E+10 vill calculate the I -; the net sample count rate in cpm on the AGX-2 cartridge.
J *** For snalysis of the particulate filter it is assumed that a C M survev meter is used
-. to obtaih the sample count rates. The Illter count rate was estfT-ted from the I-131 air concentration for a 100 liter sample volume.
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PAGE 9.7-11A
,= TABLE 9.7.7a f
VERMONT YANKEE FIELD DATA AT CLOCK TIME 1415-1430 (SCENARIO TIME 7:15 - 7:30) AIR SAMPLE DATA (103 LITERS)* GAMMA DOSE RATE RM-14** SAM-II RM-14*** PLUME CCNC. PARTICULATE SECMENT DISTANCE MAP PIC 6 RM-14 I-131 SILVER ZEOLITE FILTER NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM)
~~~i$b0 ~~5iTE
~ "
BbbE ibbb bhh 5$36k$5b~~~kbb'"~~b'k'kb E ~kbb~ BOUNDAR YELLOW 140 OSH 1.36E-11 <40 AS READ <40 GREEN 14 49000 1.36E 12 <40 AS READ <40 2400 1.75E 07 982 2945 701 2.00 0,50 BLUE OSH 295 70 YELLOW 240 OSH 1.75E-08 98 GREEN 24 OSH 1.75E-09 <40 AS READ <40 3.00 1.10 BLUE 2700 OSH 1.86E-06 10405 31215 .7432 YTi LOW 270 OSH 1.86E-07 1040 3121 743 ikEEN 27 OSil 1.86E 08 104 312 74 1.70 1800 1.12E-06 6291 18874 4494 4.00 BLUE OSH 629 1887 449 YELLOW 180 OSH 1.12E-07 . GREEN 18 OSH 1.12E 08 63 189 45 5400 2.30 BLUE 1200 OSH 7.10E-07 3975 11926 2840 YELLOW 120 OSH 7.10E 08 398 1193 284 GREEN 12 42000 7.10E 09 <40 119 <40 6.00 2.80 BLUE 690 USH 4.01E-07 2247 6741 1605 YELLOW 69 OSH 4.01E-08 225 674 160 GREEN 7 24150 4.01E-09 <40 67 <40 7.00 3.50 BLUE 280 OSH 1.56E-07 871 2613 622 YELLOW 28 OSH 1.56E-08 87 261 62
, GREEN 3 9800 1.56E-09 <40 AS READ <40 l
I i NOTES: !
- Air sample data are based on a sample volume of 100 liters. If different volumes I are collected, the air sample data provided in the tables should be adjusted was collected instead of 100 liters, proportionally. For example, if a 53 liter sam divide the value given in the table by 2 (two)p12and provide the resulting value to the players.
** The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpm /dpm with the l
silver zeolite cartridge. Therefore, I-131 conc. (uCi/cc) X 5.6E+09 will calculate l-the net sample count rate in cpm on the silver zeolite cartridge.
*** The particulate filtar sample count rate (cpm) was estimated from the I-131 air concentration for a 100 liter samp?e.
OSH Off-Scale High (Count rate higher than the upper scale of the instrumentation).
PAGE 9.7 11B TABLE 9.7.7b STATE OF VERMONT FIELD DATA AT CLOCK TIME 14151430 (SCENARIO TIME 7:15 7:30) CAMMA SURVEY DATA AIR SAMPLE DATA (100 LITERS)* WAIST AND CROUND LEVEL READINGS LUDLUM 2220 C.M METER CLOSED OPEN CONC. AGX.2** PARTICULAfE*** PLUME VINDOW VINDOW I.131 CARTRIDGE FILTER SEGMENT DISTANCE MAP uCi/cc (NET CPM) (NET CPM) NO. (MILES) AREA (mR/hr) (mR/hr) 2800 1.36E.10 AS READ <50 1.00 SITE BLUE 1400 <50
. BOUNDARY YLL1DW 140 280 1.36E-11 AS READ 14 28 1.36E-12 AS READ <50 GREEN 2400 4800 1.75E-07 3156 701 2.00 0.50 BLUE 480 1.75E.08 316 70 YELLOW 240 <50 GREEN 24 48 1.75E.09 AS READ 2700 5400 1.86E.06 33444 7432 3.00 1.10 BLUE 540 1.86E.07 3344 743 YELLOW 270 334 74 GREEN 27 54 1.86E.08 3600 1.12E.06 20222 4494 4.00 1.70 BLUE 1800 2022 449 YELLOW 180 360 1.12E.07 36 1.12E.08 202 <50 GRLEN 18 2400 7.10E.07 12778 2840 5.00 2.30 BLUE 1200 1278 284 YEILOW . 120 240 7.10E.08 ,
24 7.10E.09 128 <50 ! GREEN 12 690 1380 4.01E.07 7222 1605 6,00 2.80 : BLUE 138 4.01E 08 722 160 YELLOW 69 <50 7 14 4.01E.09 72 GREEN
- 560 1.56E.07 2800 622 7.00 3.50 BLUE 280 280 62 YELLOW 28 56 1.56E.08 3 6 1.56E.09 AS READ <50 GREEN 9
I i j. jj NOTES: If different volumes
- Air aresample data are based on a sample volume of 100 liters.the air sample data provided in th collected, proportionally. For example, if a 50 liter sample was collected instead of 100 liters,
!- divJde the.value given in the table by 2 (two) and provide the resulting value to the players. forI.131wasassumedtobe0.080c!$stethedpm with
** The the Ludlum 2220 detector ACX-7 cartridge. efficione(31 Therefore, I. conc. (uC1/cc) X 1.8E+10 will cal
! the net sample count rate in epm on the AGX-2 cartridge.
*** For analysis-of the particulate filter it is assumed that a G-M survey meter is used to obtain the sample count rates. The Illter count rate was estimated from the 1-131 air concentration for a 100 liter sample volume.
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I 9.7-12A TABLE 9.7.8a VERMONT YANKEE FIELD DATA AT CLOCK TIME 1430-1445 (SCENARIO TIME 7:30 7:45) l l AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM 14** SAM-II RM-14*** CONC. PARTICULATE i PLUME PIC-6 RM-14 I-131 SILVER ZEOLITE FILTER SECHENT DISTANCE MAP (NET CPM) uCi/cc (NET CPM) (NET CPM) 4 NO. (MILES) AREA (mR/hr) (CPM)
~~~~
53bb' bhH ~$ 7 die 555~~~kdb~kh'RkkD Ebb I
~~~i$b0 ~ ~hiTb' ~ ~5LbE <40 <40 BOUNDARY YELLOW 130 OSH 7.41E-12 AS READ
<40 l'
GREEN 13 4~~90 7.41F.-13 <40 AS READ 2400 1.05E-07 588 1763 420 2.00 0.50 BLUE OSH 176 42 YELLOW 240 OSH 1.05E-08 59
<40 GREEN 24 OSH 1.05E-09 <40 AS READ j
3100 2.04E-06 11407 34222 .8148 3.00 1.00 BLUE OSH 1141 3422 815 YELLOW 310 OSH- 2.04E-07 81 l GREEN 31 OSH 2.04E-08 114 342 ] j 1700 1.11E-06 6222 18667 4444 l 4.00 1.60 BLUE YELLOW -170 OSH OSH 1.115-07 622 1867 444 2 17 OSH 1.11E-08 62 187 44 GREEN 2.20 1200 7.41E-07 4148 12444 2963 ~; 5.00 BLUE OSH 415 1244 296 YELLOW 120 OSH 7.41E-08
-4 i CREEN 12 42000 7.41E-09 41 124 <40 2.80 860 5.06E-07 2835 8504 2025 6.00 -BLUE OSH 283 850 202 YELLOW 86 OSH 5.06E-08 g
GREEN 9 30100 5.06E 09 <40 85 <40 7.00 3,30 BLUE 530 OSH 2.99E-;7 1673 5019 1195 f' YELLOW 53 OSH 2.99E-08 167 502 120 GREEN 5 18550 2.99E 09 <40 50 <40
]
8.00 4.00 BLUE 220 OSH 1.22E-07 681 2043 486 YELLOW 22 OSH 1.22E 08 68 204 49 GREEN 2 7700 1.22E-09 <40 AS READ <40 I k
-i i
2 ,
; NOTES:
- Air sample data are based on a sample volume of 100 liters. If different volumes
- are collected, the air sample data provided in the tables should be adjusted
; proportinnally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas collected provide instead of the resulting 100 l' o*.ers, value
.he players.
** The RM-14 detector efficiency for I-131 was assumed to be 0.025 cpr/dpm with the silver zeolite cartridge. Therefore, I-131 cone. (uci/cc) X 5.6E+09 will calculate
{ the net sample count rate in cpm on the silver zeolite cartridge.
) *** The particulate filter sample count rate-(cpm) was estimated from the I-131 air
; concentration for a 100 liter sample OSH Off-Scale High (Count rate higher than the upper scale of the instrumentation).
i
PAGE 9.7-12B TABLE 9.7.8b-
'( STATE OF VERMONT FIELD DATA AT CLOCK TIME 1430-1445 (SCENARIO TIME 7:30 7:45)
GAMMA SURVEY DATA AIR SAMPLE DATA (100 LITERS)* UAIST AND GROUND LEVEL READINGS LUDLUM 2220 G-M METER PLUME CLOSED OPEN CONC. AGX-2** PARTICULATE *** SEGMENT DISTANCE MAP WINDOW .VINDOW I-131 CARTRIDGE FI LTER NO, (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM) 1.00 SITE BLUE 1300 2600 7.41E-11 AS READ <50
. BOUNDARY YELLOW 130 260 7.41E-12 AS READ <50 GREEN 13 26 7.41E 13 AS READ <50 2.00 0.50 BLUE 2400 4800 1.0$E 07 1889 420 YCLLOW 240 480. 1.05E 08 .
189 ~ <50 GREEN 24 48 1.05E 09 AS READ <50 3.00 1.00 BLUE 3100 6200 2.04E-06 36667 8148 YELLOW 310 620 2.04E-07 3667 815 GREEN- 31 62 2.04E 08 367 81 4.00 1,60 BLUE 1700 3400 1.11E-C6 20000 4444 ' YELLOW 170 340 1.11E 07 2000 444 GREEN 17 34 1.11E 08 200 <50 5.00 2.20 BLUE 1200 2400 7.41E-07 13333 2963 YELLOW 120 240 7.41E-08 1333 296 GREEN 12 24 7.41E 09 133 <50 6.00 2.80 BLUE 860 1720 5.06E-07 9111 2025 YELLOW 86 172 5.06E-08 911 202 GREEN 9 17 5.06E-09 91 <50 7.00 3.30 BUIE 530 1060 2.99E-07 5378 1195 YELLOW $3 106 2.95; 08 538 120 2.99E-09 <50 4 GREEN 5 11 54 8.00 4.00 BLUE 220 440 1.22E-07 2189 486-YELLOW 22 44 1.22E 08 219 <50 GREEN 2 4 1.22E 09 AS READ <50 l i NOTES:
- Air sample data are based on e. sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sam I divide the value given in the table by 2 (two)ple andwas collected provide insteadvaluo the resulting of 100 to liters, the players.
I e ** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 cpm /dpm with the AGX 2 cartridge. Therefore. 1-131 cone. (uC1/cc) X 1.EE+10 vill calculate the the net sample count rate in epm on the AGX-2 cattridge.
*** For analysis of the particulate filter it is assumed that a C M survey meter is used to obtaih the sample count rates. The Illter count rate was esticated from the I-131 air concentration for a 100 liter sample volume.
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9,7-13A TABLE 9.7.9a [ VERMONT YANKEE FIELD DATA AT CLOCK TIME 1445 1500 (SCENARIO TIME 7:45 - 8:00) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM-14** SAM-II RM 14**w CONC. PARTICULATE PLUME FILTER SECMENT DISTANCE MAP PIC-C RM-14 I 131 SILVER ZEOLITE l- NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM)
~ ~ ~" ~
iEbb 'bhH 7$bik25b~'"Edb'~~~Ih'kkEb ~~~E5b'~
~~~5$b0 ~~biTk'~~BbbE 140 OSH 7.41E-11 <40 AS READ <40 BOUNDARY YELLOW <40 GREEN 14 49000 7.41E-12 <40 AS READ 2900 1.05E-07 588 1763 420 2.00 0.60 BLUE OSH 1.05E-08 59 176 42 YELLOW 290 OSH 4
GREEN 29 OSH 1.05E-09 <40 AS READ <40 I t 3.00 1.10 BLUE 3100 OSH 1.98E-06 11062 33185 .7901 s YELLOW 310 OSH 1.98E-07 1106 3319 790 f- 1.98E-08 111 332 79
; GREEN 31 OSH 1.60 1700 1.11E-06 6222 18.667 4444 4.00 BLUE OSH 622 1867 444 YELLOW .170 OSH 1.11E-07 44 GREEN 17 OSH 1.11E-08 62 187 l
5.00 2.30 BLUE 1000 OSH 6.79E-07 3802 11407 2716 ] YELLOW 100 OSH 6.79E-08 380 1141 272 4 GREEN 10 35000 6.79E-09 <40 114 <40 1 6.00 2.90 BLUE 830 OSH 4.81E-07 2696 8089 1926 YELLOW 83 OSH 4.81E 08 270 809 193 CREEN 8 29050 4.81E-09 <40 81 <40 7.00 3.40 BLUE 620 OSH 3.50E-07 1960 5880 1400 YELLOW 62 OSH 3.50E-08 196 588 140 GREEN 6 21700 3.50E-09 <40 59 <40 I
-400 OSH 2.19E-07 1224 3671 874 8.00 4.00 BLUE 367 87 YELLOW 40 OSH 2.19F-08 122 GREEN 4 14000 2,1c e <40 AS READ <40 9.00 4.60 BLUE 170 OSH 9.26e s 519 1556- - 370 YELLOW 17 OSH 9.26E-09 52 126 <40 .. GREEN 2 5950 9.26E-10 <40 AS READ <40 f
J NOTES:
- Air sample data are based on a sample volume of 100 liters. If different volumes J
e are collected, the air sample datt provided in the tables should be adjusted
. proportionally.
divide the value For example, given in the iftable a 50byliter 2 sam (two)ple was and collected provide instead of the resulting value100toliters, the players. J ** The kM-14 detector efficiency for I-131 was assumed to be 0.025 cpe/dpm with the silver zeolite cartridge. Therefore, he I-131 cone. silver (uci/ce) zeolite X 5.6E+09 will calculate cartridge. the net sample count rate in epm on t
~J
*** The parciculate filter sample count rate (cpm) was estimated from the 1-131 air concentration for a 100 liter sample.
OSH Off-Scale High (Count rste higher than the upper scale of the instrumentation).
PAGE 9.7-13S TABLE 9.7.9b
- STATE OF VERMONT FIELD DATA AT CLOCK TIME 1445-1500 (SCENARIO TIME 7:45 - 8:00)
GAMMA SURVEY DATA AIR SAMPLE DATA (100 LITERS)* VAIST AND GROUND LEVEL READINGS LUDLUM 2220 G M METER PLUME CLOSED OPEN CONC. AGX.2** PARTICULATE *** WINDOW WINDOW I-131 CAI ' RIDGE FI LTER SEGMENT DISTANCE MAP f.
..?.- .. . ..I 5. .I 5. ..Y $$..... --
1400 2800 7.41E.10 AS READ <50
-1.00 SITE BLUE 280 7.41E-11 AS READ <50 7
BOUNDARY YELLOV 140 GREEN 14 28 7.41E-12 AS READ <50 l 1 2900 5800 6.79E 07 12222 2716 { 2.00 0.60 BLUE 6.79E-08 1222 272 e YELLOW 290 580 GREEN 29 58 6.79E 09 122 <50 i 3.00 1.10 BLUE 3100 6200 1.98E.06 35556 7901 YELLOW 310 620 1.98E.07 3556 790 [ GREEN 31 62 1.98E-08 356 79-l 3400 1.11E-06 20000 4444 3 4.00 1.60 BLUE 1700 2000 444 YELLOW 170 340 1.11E-07 GREEN 17 34 1.11E 08 200 <50 2.30 1000 2000 6.79E-07 12222 2716 5.00 BLUE 6.79E-08 1222 271.60 YELLOW 100 200 CREEN 10 20 6.79E-09 122 <50 2.90 830 1660 4.81E.07 8667 1926 i 6.00 BLUE 4.81E-08 867 193 4 YELLOW 83 166 GREEN 8 17 4.81E.09 87 <50 3.40 620 1240 3.50E-07 6300 1400
)' + 7.00 BLUE 3.50E 08 630 140 YELLDW 62 124 GREEN 6 12 3.50E 09 63 <50 400 800 2.19E-07 3933 874
[ 8.00 4.00 BLUS 2.19E-08 393 87 YELLOW 40 80 j CREEN 4 8 2.19E-09 AS READ <50 g 340 9.26E-08 1667 370 9.00 4.60 BLUE 170 9.26E-09 167 <50 YELLOW 17 34 GREEN 2 3 9.26E 10 AS READ <50
?
4, M NOTES: 1
- Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be ad usted of 100 liters, proportionally.
divide the valueFor example, if a 50byliter sam and 'j given in the table 2 (two)ple was provide collectedthe r'nstea
.ulting value to the playcrs.
** The Ludlum 2220 detector efficiency for I-131 was assumed to be 0.080 cpm /dpm with
,7 the AGX.2 cartridge. Therefore, I 131 conc. (uC1/cc) X 1.8E+10 will calculete the the net sample count rate in cpn on the ACX-2 cartridge.
!I '*** For analysis of the particulate filter it is assumed that a G M survey meter is used i" to obtain the sample count rates. The tilter count rate was estimated from th'e I-131 air concentration for a 100 liter sample volume. i
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9.7-14A TABLE 9.7.10a j' VERMONT YANKEE FIELD DATA AT CLOCK TIME 1500 1515 (SCENARIO TIME 8:00 - 8:15) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM 14** SAM II RM 14*** CONC. PARTICULATE PLUME SILVER ZEOLITE FILTER SEGMENT DISTANCE MAP FIC-6 RM-14 I 131 (NET CPM) NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM)
5$b0 ~~biTb'~~bLbb ~ihbb b5b~ ~5$53b5bh~~~E5b'E5'kkkb E5b
120 OSH 2.53E-10 <40 AS READ <40 BOUNDARY YELLOW <40 <40 GREEN 12 42000 2.53E-11 AS READ 2200 9.26E-07 5185 15556 3704 2.00 0.70 BLUE OSH 9.26E-08 519 1556 370 YELLOW 220 OSH
<40 GREEN 22 OSH 9.26E-09 52 156 2100 1.48E-06 8296 24889 5926 3.00 1.40 BLUE OSH 1.48E-07 830 2489 593 YELLOW 210 OSH 59 GREEN 21 OSH 1.48E-08 83 249 1500 OSH 9.88E-07 5531 16593 3951 4.00 1.90 BLUE 9.88E 08 553 1659 395 YELLOW 150 OSH <40 GREEN 15 OSH 9.88E-09 55 166 1000 5.99E-07 3353 10059 2395 5.00 2.40 BLUE OSH 5.99E-08 335 1006 240 YELLOW 100 OSH
<40 GREEN 10 35000 5.99E-09 <40 101 680 OSH 3.95E-07 2212 6637 1580 6.00 3.00 BLUE 3.95E-08 221 664 158 7EI LOW 68 OSH 7 23800 3.95E-09 <40 66 <40 GREEN 3.09E 07 1728 5185 1235
. 7.00 3.60 BLUE 570 OSH 173 519 123 YELLOW 57 OSH 3.09E-08 <40 GREEN 6 19950 3.09E-09 <40 52 450 2.47E-07 1383 4148 988 8.00 4.10 BLUE OSH 2.47E-08 138 415 99 YELLOW 45 OSH i GREEN 5 15750 2.47E-09 <40 AS READ <40 1.60E-07 899 2696 642 9.00 4.70 BLUE 300 OSH 1.60E-08 90 270 64 YELLOW 30 OSH 1-GREEN 3 10500 1.60E-09 <40 AS READ <40 6.79E-08 380 1141 272 10.00 5.30 BLUE 130 OSH
<40 114 <40 YELLOW 13 45500 6.79E-09 GREEN 1 4550 6.79E-10 <40 AS READ <40' NOTES:
*
- Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted f 100 liters,
"' proportionally. the value For example, given if a 50byliter in the table sam was collected instead oand 2 (two)ple provide the re divide
!- the players,
** The RM-14 detector efficiency for 1-131 was assumed to be 0.025 epm /dpm with the i i
- silver zeolite cartridge. Therefore, I-131 cone. (uCi/cc) X 5.6E+09 will calculate
- the net ample count rate in crc on the silver zeolite cartrid 5 8-
*** The particulate filter sa=ple count rate (cpm) was estiaated from the I-131 air concentration for a 100 liter sample.
OSH Off-Scale High (Count rate higher than the upper scale of the instrumentation).
PACE 9.7 14B TABLE 9.7,10b l' 8:15) STATE OF VERMONT FIELD DATA AT CLOCK TIME 15001515 (SCENARIO TIME 8:00 CAMMA SURVEY DATA AIR SAMPLE DATA (100 LITERS)* UAIST AND CROUND LEVEL READINGS LUDLUM 2220 C.M METER CLOSSD OPEN CONC. AGX-2** PARTICULATE *** PLUME I.131 CARTRIDGE FILTER SECNENT DISTANCE' MAP WINDOW UINDOW (MILES) AREA (mR (mR/hr) uCi/cc (NET CPM) (NET CPM) NO.
...... ....... ....... ..../.hr) 1200 2400 2.53E.09 AS READ <50 1.00 SITE BLUE 2.53E.10 AS READ <50
. BOUNDARY YELLOW 120 240 GREEN 12 24 2.53E.11 AS READ <50 2200 4400 9.26E.07 16667 3704 2.00 0.70 BLUE 440 9.26E-08 1667 370 YELLOW 220 GREEN 22 44 9.26E-09 167 <50 2100 4200 1.48E.06 26667 5926 3.00 1.40 BLUE 420 1.48E.07 2667 593 YELLOW 210 59 GREEN 21 42 1.48E.08 267 1500 3000 9.88E.07 17778 3951 4.00 1.90 BLUE 9.88E.08 1778 395 YELLOW 150 300 GREEN 15 30 9.88E-09 178 <50 1000 2000 5.99E.07 10778 2395 5.00 2.40 BLUE 5.99E.08 1078 240 YELLOW 100 200 GREEN 10 20 5.99E.09 108 <50 680 1360 3.95E-07 7111 1580 6.00 3.00 BLUE 3.95E-08 711 158 Y ELLO'.' 68 136 GREEN 7 14 3.95E.09 71 <50 570 1140 3.09E 5556 1235 7.00 3.60 BLUE 3.09E.08 556 123 l YELLOR 57 114 CREEN 6 11 3.09E.09 56 <50 450 900 2.47E.07 4444 988 8.00 4.10 BLUE 2.47E.08 444 99 YELLOW 45 90 GREEN 5 9 2.47E-09 AS READ <50 300 600 1.60E-07 2889 642 9.00 4.70 BLUE 1.60E.08 289 64 YELLOW -30 60 CREEN 3 6 1.60E.09 AS READ <50 130 260 6.79E.08 1222 272 10.00 5.30 BLUE 6.79E.09 122 <30 YELLOW 30 60 GREEN 3 6 6.79E.10 AS READ <50
-1 NOTES:
- Air sample data are based on a sample volume of 100 liters.. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally.
divide the value For example. given in theiftable a 50 byliter2 sam and was (two)ple provide the resulting collected insteadvalue to liters, of 100
.the players.
.1
** The.Ludium 2220 detector efficiency for I.131 was assumed to be 0.080 cpm /dpm with the AGX.2 cartridge. Therefore, I.131 cone. X 1.8E+10 will calculate the the ner sample count rate in cpm on the AGX-2(uCi/ct)dge.
cartri it is assumed that a G-M survey meter is used
*** For aralysis.of to obtain the particulate the sample count rates.filterfilter The count rate was estimated Irom the I.131 air concentration for a 100 liter sample volume.
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l l 9.7 15A TABLE 9.7.11a I VERMONT YANKEE FIELD DATA AT CLOCK TIME 1515-1530 (SCENARIO TIME 8:15 - 8:30) AIR SAMPLE DATA (100 LITERS)* GAMMA DOSE RATE RM 14** SAM-II RM-14*** PLUME CONC. PARTICULATE SECMENT DISTANCE MAP PIC 6 RM-14 1-131 SILVER ZEOLITE FILTER NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) 5$b0 " hiTk' B[5k' ~~55bb' 'bSE ~3552k'b9 ' ' 'Ekb' ' ' ~ ~ ~ ' ' 5 9 E5b BOUNDARY YELLOW 110 OSH 3.52E-10 <40 AS READ <40 GD.EEN 11 38500 3.52E 11 <40 AS READ <40 2.00 0.80 3LUE 1800 OSH 8.64E 07 4840 14519 3457 ELLOW 180 OSH 8.64E-08 484 1452 346 GREEN 18 OSH S.64E-09 48 145 <40 3.00 1.70 BLUE 1300 OSH 8.02E 07 4494 13481 3210 YELLOW 130 OSH 8.02E-08 449 1348 321 GREEN 13 45500 9.02E 09 45 135 <40 4.00 2.20 TTJE 1100 OSH 6.79E-07 3802 11407 2716 YELLOW 110 OSH 6.79E-08 380 1141 272 GREEN 11 38500 6.79E-09 <40 114 <40 5.00 2.70 BLUE 900 OSH 5.37E-07 3007 9022 2148 YELLOW 90 OSH 5.37E 08 301 902 215 GREEN 9 31500 5.37E-09 <40 90 <40 6.00 3.20 BLUE 640 OSH 3.64E-07 2040 6119 1457 YELLOW 64 OSH 3,64E-08 204 612 146 GREEN 6 22400 3.64E-09 <40 61 <40 7.00 3.80 BLUE 460 CSH 2.47E-07 1383 4148 988
, YELLOW 46 OSH 2.47E-08 138 415 99 GREEN 5 16100 2.47E-09 <40 AS READ <40 8.00 4.40 BLUE 400 OSH 2.22E-J7 1244 3733 889 YELLOW 40 OSH 2.22E-08 124 3L 89 GREEN 4 14000 2.22E-09 <40 AS READ <40 l , 9.00 4.90 BLUE 330 OSH 1.79E-07 1002 3007 716 YELLOW 33 OSH 1.79E-05 100 301 72 i'
GREEN 3 11550 1.79E-09 <40 AS READ <40 10.00 5.50 BLUE 230 OSH 1.17E-07 657 1970 469 YELLOW 23 OSH 1.17E-08 66 197 47 GREEN 2 8050 1.17E-09 <40 AS READ <40 L . 00 6.10 BLUE 100 OSH 5.43E 08 304 913 217 YELLOW 10 35000 5.43E-09 <40 91 <40 GREEN 1 3500 5.43E-10 <40 AS READ <40 J NOTES:
- Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be ad usted
. proportionally. For example, if a 50 liter sample was collected instea of 100 liters, divide the value givet. in the table by 2 (two) and provide the resulting value to
- the players.
, ** Yhe RM-14 detector ef ficiency for 1-131 was assumed to be 0.025 cpm /dpm with the
'j -ilver zeolite cartridge. Therefore, I-131 conc. (uci/cc) X 5.6E+09 will calculate g
the net sample count rate in cpm on the silver zeolite cartridge, j *** The particulate filter sample count rate (cpm) was estimated from the I-131 air i concentration for a 100 liter sample. OSH Off-Scale High (Count rate higher than the upper scale of the instrumentation).
PAGE 9.7 15B TABLE 9.7.11b
-- STATE OF VERMONT FIELD DATA AT CIDCK TIME 1515 1530 (SCENARIO TIME 8:15 8:30)
GArMA SURVEY DATA AIR SAMPLE DATA (100 LITERS)* VAIST ANL' GROUND LEVEL READINGS LUDLUM 2220 G.M METER PLUME CLOSE3 OPEN CONC. ACX.2** PARTICU1 ATE *** SEGMENT DISTANCE MAP WINt0W VINDOW I-131 CARTRIDGE FILTER NO. (MILES) AREA (mL/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM) 1.00 SITE BLUE 1100 2200 2.78E-09 AS READ <50
. BOUNDARY YILLOW 110 220 2.78E.10 AS READ <50 GREEN 11 22 2.78E.11 AS READ <50 2.00 0.80 BLUE 1800 3600 8.64E.07 15556 3457 YELLOW 180 360 8.64E.08 1556 346 GREEN 18 36 8.64E-09 156 <50 3.00 1.50 BLUE 1300 2600 8.02E.07 14444 3210 YELLoiJ 130 260 8.02E.08 1444 321 GREEN 13 26 8.02E-09 144 <50 4.00 2.20. BLUE 1100 2200 6.79E-07 12222 2716 YELLOW 110 220 6.79E-08 1222 272 GREEN 11 22 6.79E-09 122 <50 5.00 -2.70 BLUE 900 1800 5.37E-07 9667 2148 YELLOW 90 180 5.37E 08 967 214.81 GREEN 9 18 5.37E.09 97 <50 6.00 3.20 BLUE 640 1280 3.64E.07 6556 1457 YELLOW 64 128 3.64E 08 656 146 GREEN 6 13 3.64E-09 66 <$0 r 7.00 3.80 BLUE 460 920 2.47E.07 4444 988 YELLOW 46 92 2.47E.08 444 99 GREEN 5 9 2.47E-09 AS READ <30 8.00 4.40 BLUE 400 800 2.22E-07 4000 889 YELLOW 40 80 2.22E.08 400 89 GREEN 4 8 2.22E-09 AS READ <50 9.00 4.90 BLUE 330 660 1.79E.07 3222 716 YELLOW 33 66 1.79E.08 322 72 GREEN 3 7 1.79E-09 AS READ <50
.10.00 5.50 BLUE . 230 460 1.17E.07 2111 469 YELLOW 33 66 1.17E-06 211 <50 GREEN 3 7 1.17E-09 AS READ <50 11.00 6.10 BLUE 100 200 5.43E.08 978 217 YELLOW 10 20 5.43E-09 98 <50
-GREEN =1 2 5.43E.10 AS READ <50 NOTES:
- Air sample data are based on a sample volume of 100 liters. If different volumes are collected, the air sample data provided in the tables should be adjusted proportionally. For example, if a 50 liter sam divide the value given in the table by 2 (two)ple andwas provide collected instead of 100toliters, the resulting-value the players.
~
** The Ludium 2220 detector effie.iency for I-131 was assumed to be 0.080 cpm /dpm with the ACX-2 cartridge. Therefore, 1-131 conc. (uCL/cc) X 1.8E+10 will calculate the' i the net sa=ple count rate in cpm on the ACX.2 cartri'.ge.
*** For analysis of the particulate filter it is assumed that a G.M survev-meter is used to obtain the sample count rates. The filter count rate was estimated Irom the 1-131 air concentration for a 100 liter sample volume.
VERMONT YANKEE NUCLEAR POVER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.0 METEOROLOGICAL DATA
-- ---- _ _ _ _ _ _ _ _ . _ _ , _ , _ _ _ _ . _ _ _ _ _ _ _ _ _ _ ~ . _ . _ _ . _ - _ . _ . . - _ . -
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10,1 ON-SITE METEOROIDGICAL DATA f t
Rev. O Page 10.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.1 ON SITE METEOROLOGICAL DATA (07:00 - 08:30) 11H3. 07:00 07:15 07:30 07:45 08:00 08:15 08:30 IDVSAV AVG IDVER SPEED MPH 4.0 3.8 3.6 3.5 3.3 3.1 3.3 UPWSAV AVG UPPER SPEED MPH 5.0 4.9 4.7 4.5 4.4 4.2 4.4
~
LOWDAV AVG LOWER DIR DEGS 180 178 176 179 180 177 177 LOWDSD AVG LOVER DIR SIGMA 22 20 18 22 24 23 21 UPWDAV AVG UPPER DIR DEGS 185 183 180 177 179 178 177 UPVDSD AVG UPPER DIR SIGMA 20 18 19 17 16 19 20 LOTTAV AVG LOWER TEMP DEGS (F) 40.0 42,0 42.5 43.2 43.7 44.0 44.5 LODTAV AVG LOWER DELTA T DEGS (F)* 1.0 0.9 0.8 0.7 0.6 0.5 0.4 UPDTAV AVG UPPER DELTA T DEGS (F)* 1.5 1.3 1.3 1.1 1.0 0.9 0.8 SOLRAV AVG SOLAR RAD LANGS 0.35 0.40 0.42 0.46 0.50 0.55 0.63 RAINTO 15 MIN RAINFALL INCHES v.00 0.00 0.00 0.00 0.00 0.00 0.00 (08 30 - 10:15) 11r1 08:45 09:00 09:15 09:30 09:45 10:00 10:15 LOWSAV AVG LOWER SPEED MPH 3.0 2.8 2.6 2.5 2.3 2.1 2.3 UPWSAV AVG UPPER SPEED MPH 4.0 3.9 3.7 3.5 3.4 3.2 3.4 IDWDAV AVG LOWER DIR DEGS 170 168 166 159 160 157 157 LOWDSD AVG LOWER DIR SIGMA 22 20 18 22 24 23 21 UPWDAV AVG UPPER DIR DEGS 175 173 170 167 169 168 167 UPWDSD AVG UPPER DIR SIGMA 20 18 19 17 16 19 20 LOTTAV AVG LOWER TEMP DEGS (F) 44.7 45.0 45.5 46,2 46.7 47.0 47.5 LODTAV AVG IDWER DELTA T DEGS (F)* 0.3 0.2 0.2 0.1 0.0 0.2 -0.4 UPDTAV AVG UPPER DELTA T DEGS (F)* 0.6 0.5 0,4 0.3 0.2 0.1 -0.1 SOLRAV AVG SOLAR RAD LANGS 0.35 0.65 0.70 0.70 0.70 0.72 0.73 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- NOTES:
- 1. The height differential (oh) for the lower delta temperature on the primary tover is 165 f t,
- 2. The height differential (Ah) for the upper delta temperature on the primary tower is 262 f t.
T
Rev. 0 Page 10.1-2 i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.1 ON-SITE METEOROLOGICAL DATA (10:30 - 12:00) IIItt 10:30 10:45 11:00 11:15 11:30 11:45 12:00 LOWSAV AVG IDWER SP5'ED MPH 2.0 1.8 1.6 1.5 1.3 1.1 1.3 UPWSAV AVG UPPER SPEED M7H 3.0 2.9 2.7 2.5 2.4 2.2 2.4 14WDAV AVG LOVER DIR DEGS 150 145 140 135 130 125 120 s LOWDSD AVG LDVER DIR SIGMA 22 20 18 22 24 23 21 UPWDAV AVG UPPER DIR DEGS 185 160 14) 136 129 125 123 UPWDSD AVG UPPER DIR SIGMA 20 18 19 17 16 19 20 IDTTAV AVG LOWER TEMP DEGS (F) 48.0 48.4 48.5 49.2 49.7 50.0 52.5 LODTAV AVG IDWER DELTA T DECS (F)* -0.5 -0.6 -0.7 -0.8 -0.9 -1.1 1.2 UPDTAV AVG UPPER DELTA T DEGS (F)* -0,3 -0,5 -0.7 -0.8 1.D -1.1 1.2 SOLRAV AVG SOLAR RAD 1ANGS 0.85 0.90 0.92 0.96 1.00 1.05 1.15 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 L12 :15 - 13 :45) 1192 12:15 12:30 12:45 .13:00 13:15 13:30 13:45 14WSAV AVG LOVER SPEED MPH 3.0 2.8 2.6 2.2 2.0 1.8 1.7 UPWSAV AVG UPPER SPEED MPH 4.0 3.9 3.7 3.1 2.3 2.4 2.1 LOWDAV AVG IDVER DIR DEGS 120 118 116 119 120 117 118 LOWDSD AVG LOWER DIR SIGMA 22 20 18 22 24 23 21 i UPWDAV AVC UPPER DIR DEGS 125 123 120 112 110 112 115 UPWDSD AVG UPPER DIR SIGMA 20 18 19 17 16 19 20 LOTTAV AVG IDWER TEMP DEGS (F) 53.7 54.0 55.5 56.2 56.7 57.0 57.5 LODTAV AVG LOVER DELT/. T DEGS (F)* -1.4 -1.4 -1.4 1.5 -1.5 -1.5 -1.5 UPDTAV AVG UPPER DELTA T DEGS (F)* -1.4 -1.7 -2.0 -2,4 -2.2 -2.4 -2.3 SOLRAV AVG S01AR RAD 1ANGS 1.25 1.27 1.29 1.30 1.35 1.33 1.30 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 '
- NOTES
- 1. The height differential (Ah) for the lower delta temperature on the primary tower is 165 f t.
- 2. The height differential (ah) for the upper delta temperature on the primary tower is 262 f t.
i s
l f Rev. O Page 10.1-3 { VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.1 ON-SITE METEOROLOGICAL DATA (14:00 - 15:30) 1121 14:00 14:15 14:30 14:45 15:00 15:15 15:30 1DVSAV AVG LOWER SPEED MPH 1.7 2.0 1.8 1.6 1.8 2.3 2.1 UPWSAV AVG UPPER SPEED MPH 2.4 2.5 2.1 2.0 2.5 3.0 3.2 LDWDAV AVG IDWER DIR DEGS 117 115 115 110 115 110 ^115 LOWDSD AVG LOWER DIR SIGMA 21 22 20 16 22 24 23 UPWDAV AVG UPPER DIR DEGS 120 118 109 111 112 116 118 UPWDSD AVG UPPER DIR SIGMA 20 20 18 19 17 16 19 1DTTAV AVG LOWER TEMP DEGS (F) 57.5 57.3 57.1 56.8 56.4 56.0 55.7 LODTAV AVG LOWER DELTA T DEGS (F)* -1.5 -1.5 -1.6 -1.7 -1.6 -1.6 -1,6 UPDTAV AVG UPPER DELTA T DEGS (F)* -2.3 -2.2 -2.2 -2.3 -2.4 -2,2 2.3 SOLRAV AVG S01AR RAD LANGS 1.30 1.30 1.22 1.14 1.05 0.92 0.80 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 (15:45 - 17:15) liEt 15:45 16:00 16:15 16:30 16:45 17:00 17:15 LDWSAV AVG LOWER SPEED MPH 2.5 2.8 2.6 2.7 3.0 2.8 2.7 UPUSAV AVG UPPER SPEED MPH 3.5 3.9 3.7 3.8 4.3 4.1 4.4 LOWDAV AVG LDWER DIR DEGS 100 95 90 87 83 74 69 LOWDSD AVG LOWER DIR SIGMA 22 20 18 22 24 23 21 UPWDAV AVG UPPER DIR DEGS 105 96 87 78 72 67 62 UPWDSD AVG UPPER DIR SIGMA 20 18 19 17 16 19 20 LOTTAV AVG LOWER TEMP DEGS (F) 55.0 54.4 53.7 53.2 52.7 52.0 51.5 1DDTAV AVG LOWER DELTA T DEGS (F)* -1.4 -1.4 -1.4 -1.3 -1.2 -1.2 -1.2 UPDTAV AVG UPPER DELTA T DEGS (F)* -2.1 -2.0 -2.0 -1.9 -1.7 -1.6 -1.5 SOLRAV AVG SOLAR RAD 1ANGS 0.45 0.20 0.10 0.05 0.00 0.00 0,00 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00
- NOTES.
1.The height differential (Ah) for the lower delta temperature on the primary tower is 165 f t. 2.The height differential (Ah) for the upper delta temperature on the primary tower is 262 ft.
i. k, VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 l l 10.2 GINERAL AREA NATIONAL VEATHER SERVICE (NWS) FORECASTS u- _ _ _ , _ ____ -- ---- - - - - ~- - - ~~^'
L Rev 'O Page 10.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ( 1991 10.2 GENERAL AREA NWS FORECAST (See Note) - Synoosis (07:00) A low pressure system is located along the Atlantic seaboard. High temperatures in the middle to upper 50's; low temperatures in the middle 40's. Winds from the south at 4-5 MPH, swinging around to the southeast thir af ternoon and diminishing in intensity. Winds will continue to shift, coming around to the north and increasing in intensity to 5-7 MPH. Valid (07:00-13:2Q1 Winds from the south at 4-5 MPH, swinging around to the southeast early this afternoon and becoming 1-3 MPH. Temperature in tra upper 40's increasing to the low 50's. Chance of a shower. Valid (13:00-19:CQ1
-Winds shifting to the north late in the period and increasing to 5-7 MPH. Showers are possible. High temperature in the upper 50's.
Valid (19:00-01:00)
. Clearing out. Tamperatures in the low 40's. Northerly winds from'2-5 MPH.
PLANT / EOF VEATHER OBSERVATIONS (Seo Note) - Valid (07:00-15:00) Time General Observations 07:00 Partly cloudy with light to moderate winds. 08:00 Partly cloudy with light to moderate winds. " 09:00 Partly cloudy with light winds. 10:00 Partly cloudy with light winds. 11:00 Partly cloudy with light winds. 12:00 Partly cloudy with light winds. 13:00 Partly cloudy with light winds. 14:00 Partly cloudy with_ light vinds. 15:00 Mostly cloudy with light winds. NOTE: GENERAL AREA NWS FORECASTS SHOULD BE PROVIDlQ UPON REOUEST. PLANT / EOF VEATHER OBSERVATIONS VILL BE-POSTED AS APPROPRIATE. 1
i Rev. O Page 10.2 2 k VERMONT YANKEE NIJCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.2 VERMONT YANKEE SITE FORECAST To be orovided to the ESC Meteorolorist by the ESC Controller at 09:00. UEATHER FORECAST FOR SITE: VERMONT YANKEE Date of Forecast: 11-06-91 Time of Forecast: 09:00 Current Site Meteorology (as of 09:00 ): lime Senmr Wmd Speed Wind Direction Delta Temocrature Stability Precinitation Lcutt 2.8 MPli 168 DEG WOM Upgr 3.9 MPil 173 DEG WOM 0.5 DEG F E O IN115 MIN lorecast Site Meteorology: Time }cnwr Wmd Wind Direction Detta Temperature Stabihty Precipitatvm Speed 09.00- 11mer 2.0 MP)I 155 DEG FROM 11:00 Upper 3,0 MPil 160 DEG MOM 0.0 E O IN/15 MIN 11:00- Imr 2.0 MPil 125 DEG FROM 13:00 Upper 3.5 MPl! 120 DEG FROM 1.0 D 0 IN/15 MIN 13 00- L a er 2.0 MPil 113 DEG FROM 15:00 Upper 2.5 MPil 115 DEG FROM 2.0 D 0 IN/15 MIN National Weather Servics Forecast for site region: Partly to mostly cloudy. Winds from the south at 3 5 MPH, swinging around to the southeast early this afternoon and becoming 1 3 MPH. Winds will become northerly late this afternoon and increase to 5-7 MPH. High temperature in the upper 50's. Special Weather Statements: l
Rev. O Page 10.2 3 l l l l VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 1 10.2 VERMONT YANKEE SITE FORECAST To be orovided to the ESC Meteorolocist by the ESC Controller at 13:E WEATHER FORECAST FOR SITE: VERMONT YANKEE Date of Forecast: 11-06 91 Time of Forecast: 13:00 Current Site Meteorology (as of 13:00 ): Wind Speed Wind Direction Detta Temrmtug StaNitty Precipitation Ilmf Sensor 1 m er 2.2 MPil 119 DEO FROM Upper 3.1 MP11 112 DEO TTIOM -2.4 DEO F C 0 IN/15 MIN lorecast Site Meteorology: \ Senior Wind Wind Direction Detta Tetntmture SisN1ity Precipitation Igg Speed 13.00- 1 m er 2.0 MPli 115 DEO FROM 1100 Upper 2.5 MPH 115 DEO ROM -2.2 C 0 inn 5 MIN - 15:00- I m er 2.5 MPH 100 DEO FROM - 17:00 Upper 3.5 MPH 90 DEO FROM -2.0 D 0 IN/15 MIN 17:00- t m er 4.5 MPil 65 DEO FROM 19:00 Upper 6,0 MPH 60 DEO FROM 1,0 D 0 IN/15 MIN National Weather Service Forecast fer site region: Partly to.mostly cloudy. Winds from the southeast shifting to northerly and increasing to 7 MPH. High temperature in the upper 50's. Clearing later tonight. Temperature in the low 40's. Special Weather Statements:
~. . -k VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.3 NATIONAL WEATHER SERVICE SURFACE MAPS 4
a
Rev, O i Page 10,3-1 1 10,3 WS SURFACE MAP (07:00) D L h' Q. . , Surface weather Moo at 7:00 $ EST J f Not Avoilable As No ne be g Contours d 7 00 LW gcse
/ .n Temperoture
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