ML20086G414
| ML20086G414 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 11/06/1991 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| References | |
| NUDOCS 9112050098 | |
| Download: ML20086G414 (345) | |
Text
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l I l l Rev. l' p .. v VERMONT YANKEE NUCLEAR POVER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 TABLE OF CONTENTS Section Title Rev. 1.0 lEBODUCTION 1.1 Exercise Schedule 1 1.2 Participating Centers / Agencies 0 1.3 Abbreviations and Definitions 0 1.4 References 0 2.0 _ EXERCISE, OlVECTIVES AND EXTENT OF PIAY 2.1 Vermont Yankee 1 2.2 State of Vermont 9/2/91 2.3 State of New Hampthire 9/17/91
-2,4 Commonwealth of Massachusetts 9/4/91 3.0 EXERCISE CUIDELINES AND SCOPE 3.1 Exercise Guidelines 0
, -(f%'j '~ 3.2 3.3 Player Instructions and Cround Rules Procedure Execution List 1 1 4.0 CONTROLLER AND OBSERVER INFORMATIQN 4.1 Assignments 0 4.2 Conts:.!1er and Observer Exercise Cuidance 0 4 . ~3 Controller and Observer Evalu? tion Criteria 0 5.0 EXERCISE SCENARIO 5.1 Initial Conditions 0 5.2 Narrative Summary 0 5.3 Scenario Timeline 0 5,4 Detailed Sequence of Events 1 6.0 L}tERCISE MESSACES 6.1 Command Cards 0 6.2 Hessage Cards 1 l l 7.0 STATION EVENT DATA 7.1 Events Summary 0 7.2 Event Mini-scenarios 0 _ i l
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VERMONT YANKEE NUCLEAR POVER STATION EMERGENCY RESPONSE PREPAREMESS EXFRCISE 1991 IABLE OF CONTENTS l l Secticu 11.tle h I 8.0 OPERATIONAL DATA 0 1 9.0 RADIO 1DCICAL DATA 0 9.1 Asea Radiation Monitors 0 9.2 Process Monitors 0 9.3 In Plant Radiation Levels 0 9.4 Plant Chemistry Data 0
- 9. I Radiological Sample Dose Lates 0 9.6 Plant Vent Stack Release Data 0 9.7 Field Monitoring Maps and Data 1 10.0 METEOROLOGICAL DATA 10.1 On. Site Meteorological Data 0 10.2 Ceneral Area NWS Forecaatn 0 0 10.3 -INS Surface Maps 0 A
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key. 1 Page 1.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 1.1 EXERCISE SCHEDULE A. G2ntroller and Observer Briefing 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
Purpose:
Familiarize Controllers and Observers with Affected Areas O Attendeer: Vermont Yankee and Yankee Atomic Controllers and Observers C. NRC Brivfinc 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. fJercise Date: November 6, 1991 Time: To Be Announced 14 cation: Vermont Yankee Emergency Response Centers and Designated States' Energency Response Centers
Purpose:
. Emergency Response Preparedness Exercise Attendees: Vermont Yankee Emergency Response Organization, State and local Emergency Response Organizations from Vermont, New Hampshire and Massachusetts, Controllers and Observers, NRC Evaluators and Yankee Atomic Engineering Support Center Staff O
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EMERGENCY RESPONSE PREPAREDN2SS EXERCIFE , l 1991 , 1.1 EXERCISE SCHEDULE (continued) E. Exercise Debriefing , Date: Day of Exetcise Time: To be announced during or immediately following the ,' exercise Location: To be determined by the respective Emergency Response [ Facility Controller 1
Purpose:
- Debrief Players, Observers and Controllers ! Attendecs: Controllers, Observers and Key Participants F. Controller Debriefine Date:- After Exercise Debriefing Time: To be announced Location: To be announced
Purpose:
Exercise Debriefing Attendees: Exercise Coordinator and Controllers G.- ' Exercise Critiang Date: November 7, 1991 Time: 12:30 p.m. Location: Vermont Yankee Corporate Offico, Brattleboro, Vermont
Purpose:
Utility Self-Critique /NRC Preliminary Findings Attendees: Vermont Yankee Management, NRC Evaluators, Exercise Controllers (Observers as needed) and Vermont Yankee Key Participants l O
x , .I i 1 l I ! VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXtRCISE i 1991 } l 1 l I 1.2 f.'RTICT D'JZNG CENTERS /ACENCIES l t i 1 I I 2 4 f-4 f
x - i l Rev. O L Page 1.2-1 VERMONT YANP.EE NUCl. EAR POWER STATION , EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 1.2 IlfjCIPATING Celi 1ERS/ACENCIES Xfly.uNT YANPEE NUCLEAR POWER CORPORATION Vermont Yankee Nuclear Power Station:
- Control Room (notification and communications functions only)
- Technical Support Center (2nd floor of Administratien Building) e Operations Support Center (1st floor of Administration Building) ,
o Energy Information Center (Covernor ilunt flouse)
.( Vermont Yankee Training Center:
- Simulator Room (Control Room functions,1st floor of Training Building)
- Emergency Operations Facility / Recovery Center (1st floor of Training Building)
Vermont Yankee Nuclear Power Corporate Office:
- News Media Center (Vermont Yankee and State representatives from VT, Nll and MA)
YANKEE ATOMIC ELECTRIC COMPANY Yankee Atomic Corporate lleadquarters (Bolton, Massachusetts):
- Engineering Support Center ETATE OF U RMONT Vermont Emerpncy Management Agency (State Response Agencies):
- Emergency Operations Facility / Recovery Center (State representatives located in the State Room)
- Emergency Operations Center (Waterbury, Vertuont) 1 l
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- Incident Field Office (Dummerston, Vermont)
Local Emergency Response Centers (Local Response)
- Brattleboro - Brattleboro Town llall e Vernon - Town of Vernon Fire Station
- Dummerston - Lummerston Town Office Building e Guilford - Guilford Town Fire Department STATP OF NEV HAMPS)11}lt New llampshire Office of Emergency Management (State Response Agencies):
e Emergency Operations Facility / Recovery Center (State re pre sentativt> s located in the State Room)
- Emergency Operations Center (Concord, New Hampshire) e DPllS Radiological Units (Concord and Keene, New llampshire)
- Southwestern Fire Mutual Aid Dispatch Center (Keene, New llampshire) e Incident Field Office (Keene, New llampshire)
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- St. ate Police Communications Center (Concord, New llampshire)
Local Energency Operations Centers (Local Response) e Hinsdale - llinsdale Fire Station / Town llall e Chesterfield - Chesterfield Town Office e Richmond - Richmond Civil Defense Building e Vinchester - Vinchester Emergency Service Building e Swanzey - Swanzey Center Fire Station e Keene - Keene Fire Station
- Reception Center - Keene State College, Spaulding Gymnasium COMMONVEALTil 0F _ MASS ACHUSETTS Massachusetts Emergency Management Agency (State Response Agencies):
- Emer6ency Operations Facility / Recovery Center (State representatives located in the State Room) e Emergency Operations Center (Framingham, Massachusetts)
- Area IV Emert,ency Operations Center (Belchertown, Massachusetts)
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- Area IV Faergetwy Operations Cer.'.er (lielchertow,'. Massachusetts) e Massachusetts Depwrtmet t of N$lic Ilealth (EOF, Brattleboro, Verinont.)
local Faergency Operations Centers (local Response) e Greenfield - Fire Station e layden - Fire Station e Bernardston - Fire Station e Gill - Fire Station e Northiiold - Town llall e Varwick - Fire Statton O O
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f t l 4 i VERMONT YANKEE NUCLEAR POWER STATION , 1 ' IFERGENJY RESPONSE l'REPARF9 NESS EXELCISE !
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1991 j l i 'I f l s i 1,3 ABP,REVIATIONS AND DEFINITIONS i- i i a f 5
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Rev. O Page 1.3-1 1.3 ' AHREVlAH011S_.AND_DFEINin0NS A. AbbreYia_tions o AO - Auxiliary Operator o A00 - Advanced Off-Gas System l o APRM - Average Power Range Monitor o ARM - Area Radiation Monitor o ATWS - 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 Center o FEMA - Federal Faergency Management Agency l l o FW - Feedwater l O 2144e
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l l Rev. O Page 1.3-2 o IIPCI - liigh Preseme Coolant Injection I o llPN - llealth Physics Network o HRNG - liigh Range Noble Cos o I.FCI - Low 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 Sampilng System o PCIS - Primary Containment Isolation System o PED - Plant Emergency Director o PVS - Plant Vent Stack o RA - Radiological Assistant o RCIC - Reactor Core Isolation Cooling o REMVEC - Rhode Island, Eastern Massachusetts, and i 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 i I l 2144e
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Rev. O Page 1.3-3 O o SBGTS - Standby Cas Treatment System o SJAE - Steam Jet Air Ejector o SRM - Site Recovery Manager / Source Range Monitor o TSC - Technical Support Center Vermont Yaakee o VY - l o VYNPC - Vermont Yankee Nuclear Power Corporation o VYNPS - Vermont Yankee Nuclear Power Stat 3on o YNSD - Yankee Nuclear Services Division O L l l I I O 2144e
Rev. 0 l' age 1. 3-4 O B. DefiniAipos o Alert - An emergency classification which is defined as an actual or potential substantial degradation of the level of safety of the plant. o Controller - A inember of an exercise conwol group. Each Controller may be assigned to one or more activities or functions for the purpose of keeping the action going according to a scenario, resolving dif f erences, supervising and assisting as needed. o Critique - A meeting of key participants in an exercise, usually held shortly after its conclusion, to identify reaknesses and deficiencies in emergency response capabilities . o Emergency Action - Specific instrument readings, system Levels or event observation and/or O radiological levels which initiate event classification, notification procedures, protective actions, and/or the mobilization of the emergency response organization. These are specific threshold readings or observations indicating system f ailures or abnormalities, 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 representatives as Emergency Plan assembly areas for their respective staffs. o Emergency Operations - An emergency responte 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
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I Rev. O i Page 1.3-5 p-V 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 radium ingestion exposure pathway zone. o Engineering Support - A YNSD emergency response facility Center (Yankee Atomic Electric Corporate Headquarters) established to provide additional engineering support to the affected site in plant assessment and recovery operations. o Exercise - A demonstration of the adequacy of timing and content of emergency implementing procedures, methods, and equipment. o Full Participation - An exercise which tests as much of Exercise the licensee, state, and local plans as is reasonably achievable - without mandatory public participation. 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 Officen. Brattleboro, Vermont) dedicated l to the news media for the purpose of disseminating and coordinating inf ormation concerning accident l-l- conditions. All activities conducted within this center will be the responsibility of the Vermont Yankee Nuclear Information Director. O 2144e l _ _ , . . _ _ _ , _ _ _ _ . . . , . ~ . _ _ _ . _ . _ . _ _ _ _ _ . . _ _ _ . _ _,
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Rev. 0 Page 1.3-6 O-o Observer - A member of an exercise control group. Each Observer may be assigned to one or more activities or functions for the purpose of evaluating, recording, and reporting the strengths and weaknesses, and making recommendations for improvement. o Operations Support - An emergency response facility Center (1st floor Administration Building) established to muster skilled emergency response personnel to perform activities in the plant. o Protective Action - Those emergency measures taken to effectively mitigate the , consequences of an accident by minimizing 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 offera by excessive riska to individual safety in implementing such action. o Scenario - The hypothetical situation, from start to finish, in an exercise which is the theme or basis upon which the action ar play of the exercise follows, o Site - That property within the fenced boundary of Vermont Yankee which ir 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 failuren O- of plant f unctit ss needed f or the protection of the public. 2144e
Rev. O Page 1.3 7 i O 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 goverr. ment agencies, j 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. l Also, assists in accident recovery operations. o Unusual Event - An emergency classification that indicates a potential degradation of plant safety margins which is not likely to affect personnel on-site or the public off-site or result in radioactive releases requiring off-site monitoring. e o Yankee Nuclear Services - A division of Yankee Atomic Division O'NSD) Electric Company. An Engineering support organization which provides emergency response support to Vermont Yankee upon request. O 2144e
t i l i- ; i VERMONT YANKEE NUC11AR POVER STATION f i EMERGENCY RESPONSE PREPAREDNESS EXERCISE a 1991 ! t t I i l i t v i , t 1.4 REFECIJiCIJi k 4
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Rev. O Page 1.4-1 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 1.4 RETEU;1{ CIA
- 1. Vermont Yankee Nuclear Power Station Emergency Plan
- 2. Vermont Yankee Nuclear Power Station Emergency Plan Itrplementing Procedures
- 3. Vermont Yankee Nuclear Power Station Final Safety Analysis Report
- 4. Vermont Yankee Nuclear Power Corporation - Communications Department-Emergency Response Plan and Procedures
- 5. Vermont Yankee Nuclear Power Station Emergency Operating Procedures
- 6. Vermont Yankee Nuclear Power Station Core Damage Assessment Methodology
- 7. Yankee Atomic Electric Company a, ' RASCAL" Computer Model Version 1, Modification 2 O b. "METPAC" (Meteorological Package) 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 l
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a l 4 I ; l i 3 t t VERMONT YANKEE NUCLEAR POWER STATION j EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1 1991 I 1 1 2.0 EXERCISE OBJECTIVES AND EXTCNT OF PLAY l i l-e i i 1 A f l r i h I k
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!:.?W10DJCY RES.PONSE PREPAREDNESS EXERCISE 1991 2.1 VERMONT YANKEE O
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2.1 Q11JECTIVES ANDM _OF PLAY - VER*10hI_TAhTIE Estrnt of Play 1 1 A. Emergency _. Classification _and_Ac.cistent Assenament
- 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 i ~in accordance with pre-established which allows personnel to demonstrate this emergency action levels. objective by implementing Procedure A.P. 3125, Emergency Plan Classification and Action Level Scheme.
l 2. Demonstrate the ability of the Control Room and TSC staff to coordinate the assessment A.2 The scenario will provide technical I of plant conditions and corrective actions information to players which will allow them 4 to mitigate accident conditions. to analyze plant conditions and propose corrective actions.
- 3. Demonstrate that information concerning plant conditions can be transmitted between A.3 Telephone consnunications links will be the Control Room and TSC in a timely manner. established by coannunicators between the i Simulator Control Room and the TSC in order to
) transmit key information and data.
- 4. Demonstrate the ability of the TSC staff to j initiate and coordinate corrective actions A.4 The scenario provides events that will enable in an efficient and timely manner. the TSC to coordinate in-plant corrective
, actions through the use of OSC personnel. 1 2160e
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- 5. Demonstrate the ability of appropriate TSC A.5 The scenario includes events which allow for staff to participate with Contr ? Room and discussion between the Control Room, TSC, and l the EOF /RC in emergency classiiication and EOF staff on classification.
, EAL discussions.
- 6. Derconstrate the ability to ef fectively use A6 ERFIS terminals at the TSC and EOF /RC will be the Emergency Response r'acility Information linked to the Simulator Control Foom to System (ERFIS) in the assessment and receive and transmit scenario data. This will trending of plant conditions. allow Emergency Response Facility staff personnel the opportunity to demonstrate the
! effectiveness of ERFIS under simulated emergency conditions. l l 7. Demonstrate the ability to assess data from A.7 Scenario events will require Chemistry and i appropriate chemistry samples in support of Radiation Protection technicians located at i' accident assessment activities and plant the OSC to simulate taking reactor coolant, i conditions. containment air, or plant vent stack samples to assess plant conditions. Sample results I will be provided by Observers who accompany the technicians during their sampling j activities. (Refer to Procedure CP-3530,
- B. NatiLicatiertanLComcM11Ca11CD " Post-Accident Sampling.")
. 1. Demonstrate that messages are traramitted B.1 Various cousmmications links will be in an accorate and timely manner nnd that B.3 established between the emergency response messages are properly logged and B.4 facilities in order to transmit information documented.* '(Documentation of emergency and data. Record keeping and documentation repair team dose approvals were not entered will be demonstrated in accordance with into TSC Log Book.) Procedure OP-3504, " Emergency Communications." Consunications and transfer of data between facilities will be evaluated Sr timeliness l and completeness.
- Indicates NRC identified improvement items from l the 1990 exercise.
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- 2. Demonstrate the capability to notify B.2 Vermont Yankee staff, NRC, and state federal and state. authorities of emergency authorities shall be notified in accordance classifications and significant changes in with established procedures. WRC will be 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
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j 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 emergency response facilities and federal l and state authorities.
- 5. Demonstrate that off-site monitoring teams B.5 Monitoring teams will be dispatched to the i, can use appropriate sample points field and directed to specific sample points (landmarks) for determining and for monitoring activities.
j connunicating their location. j 6. Demonstrate the ability to provide adequate 3.6 During the period that the off-site monitoring briefings to off-site monitoring teams as teams are in the field, scenario events may l l conditions and information change.* require that updates be transmitted to the (Off-site monitoring teams should be te;tms in the field. l briefed as to, changes in the emergency i action level classification.)
- Indicates NRC-identified improvement items from i the 1990' exercise.
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- 1. Demonstrate the proper transfer of C.1 Scenario events require the activation of the I accident / management responsibilities from Emergency Response Organization. As each j
, the SS/ PED to the Duty Call Officer and position of authority is activated, j subsequ~ntly to the TSC Coordinator and responsibilities associated with that position i Recovery Manager as appropriate.* will be . assumed from the 'S/ FED up to the
- (Transfer of accident management Recovery Manager.
responsibilities should be clarified.) i Demonstrate the' capability of key emergency C.2 All emergency response facilities have t response facility management personnti to designated coordinators who will direct and direct and coordinate their respective coordinate emergency response activities in emergency response activities in an their particular area of responsibility. ,
- ! efficient and timely manner.* (TSC should j prioritize briefings and control of ESG.)
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- 3. Demonstrate appropriate coordination of C.3 The Control Room will initially contact the
! activities with federal and state federal and state agencies, providing them i ] government agencies. with appropriate information on plcat i conditions and emergency status. This ; i function will pass to the TSC and EOF /RC after j l D. EmergP W espenst_ Ear.ilities the facilities are activated. r
- 1. Demonstrate the ability of station and D.1 Scenario events will require activation corporate personnel to activate and staff D.2 and operation of Vermont Yankee emergency i the emergency response facilities in a response facilities. The Simulator Control timely manner. Room, Control Room (comm nication functions j
- only), TSC, OSC, EOF /RC, News Media Center and i
- 2. Demonstrate and test the adequacy and Engineering Support Center will be activated
, effectiveness of emergency response in accordance with established procedures. facilities, operations, and equipment. Dasignated plant and sorporate emergency j response personnel will participate in the i exercise.
- Indicates NRC-identified improvement items from j the 1990 exercise. !
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Rev. I Pege 2.1-$ h i' i - E1rient of Plav ! E. Elan t;_ Augmentation _and_Sla ffing ! 1. Demonstrate the adequacy of plant emergency E.1 Shif t personnel should demonstrate the use: et I notification methods and procedures to the emergency call-in system to augment riant augment plant staf f and resources. staf f as may be required by scenario evt. ats. l 1
- 2. Demonstrate the ability to utilize outside E.2 The Yankee Nuclear Services Division's Engineering Support Center (ESC) will be
! resources to provide technical assistance l and logistical support. contacted and activated for this exercise. The ESC can provide technical and logist_: cal ! support as requested by Vermont Yankee. i
- 3. Demonstrate the ability to maintain shift E.3 Available resources will be evaluated and j staffing and manpower to provide for future assigned to support extended operations.
manpower and logistics needs. i. F. Radiq1pgiraLExposurnlontrni i
- 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 appropriate personnel dosimetry, equipment, equipeent. Inves*igation and repair and protective clothing. activities in the plant will require 4'
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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 OF-3507, " Emergency Radiation Exposure Control.") In addition, the exposure of the eff-site monitoring teams will be monitored and tracked in the EOF.
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O n V~ m.1 c Page 2.1-G Ext _ent of Play h G. RadinlogicaLAssessment )
- 1. Demonstrate that radiological assessment G.1 The scenario will provide information on plant ,
personnel at the EOF- can obtain G.2 conditions and in-plant radiological conditions ; l radiological and meteorological data in a G.3 to players which will allow them to evaluate l timely manner. G.4 potential off-site radiological consequences. G.5 The scenario will pcstulate an of f site ;
. 2. Demonstrate that adequate dose assessment radiological release through the plant vent j l procedures can be performed to determine stack which will allow players to evaluate off-site radiological consequences. off-site radiological conditions. Players l i.
[ will implement appropriate sections of ; Procedures OP-3513, " Evaluation of Off-Site j I 3. Demonstrate the ability to assess potential off-site radiological consequences based on Radiological Conditions" and CP-3511, : i plant conditions. "Off-Site Protective Actions Recommendations."
- 4. Demonstrate the ability to perform timely j j assessment of off-site radiological ,
conditions to support the formulation of j i protective action recommendations for the plume exposure pathway. S. Demonstrate the ability to project the plume trajectory and potentially affected t downwind sectors utilizing the computer i dose assessment model (METPAC). i
- 6. Demonstrate adequate staffing, equipment G.6 Off-site monitoring teams will be assigned at :
readiness check, and deployment (if G.7 the OSC. Players will implement appropriate ! i necessary) of off-site monitoring teams. sections of Procedure OP-3510. "Off-Site and ; Site 'bundary Monitoring. , 7. Demonstrate the use of appropriate equipment and procedures to perform l off-site radiological monitoring. ! 2160e . t
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Rev. l' l Page 2.1-t E.xtent of Pisy j H. F1qtective Action Jecision Making f 1. Demonstrate the ability to implement H.1 On-site protective action measures will appropriate on-site protective measures for include 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.
- 2. Demonstrate the adequacy of the protective H.2 Protective action decision making will be action decision making process to make demonstrated in accordance with !
recomendations concerning of f-site Procedure OP-3511, "Off-Site Protective , radiological consequences. Actions Recot:enendations". ! I. F_uttlic_Informaticu j
- 1. Demonstrate the ability to A N iop and I.1 The News Media Center wi's1 be fully activated.
disseminate timely accurate press release I2 Information on the simulated events occurring , to the public and the news media. I.3 at the plant will be gathered, verified, i l incorporated into a news release, and i I
- 2. Demonstrate the ability to prmvide disseminated to key players. After approval, !
bri-fings for and to interface with the this information will be discussM at the News l public arid news media. Media Canter. In addition, all news releases ' will be coordinated with the state's puolic ! 3. Demonstrate the ability to comunicate and information representatives. , j coordinate news releases between the EOF, l ! News Media Center, and the stat.e's public j i information represente.tives. 3
- 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. l.
- 5. Demonstrate the ability to coordinate news .5 State public information representatives from i releases with the state's public Vermont. New Hampshire, and Massachusetts will ;
information representati es. be prese. at the News Media Center. . Inforcation concerning news releases will be L 2160e coordinated with the states' public i information representatives. t t i
7p- 6 ,
..., { ._ , q.- , ,,v , ,
g - .* * . m ye , . . Rev. 1 Page 2.1-&
'xtarti;_.of Play J. ParalleLand_01her_Attions
- 1. Tcst and evaluate the adequacy of methode J.1 Security activities will be implemented in accordance with established procedures t o to establish and maintain access control control access to the protected area.
and personnel accountability within the Assembly of emergency ressonse personnel and I protected area. evacuation of contractor /.ieltors will be implemented in order to test personnel accountability within the protected area. 1 Ecvever, after the plant evacuation accountability checks have been cumpleted, contractors and visitors will be exempted from additional personnel accountability checks. J.2 Preliminary discussions on plant conditions
- 2. Demonstrate the adequacy of the procedural and status will be conducted to determine the process to transfer from the emergency required criteria to transfer from the classification phase to the recovery mode emergency phase to a recovery mode of of operation.* (De-escalation versus operation.
l recovery procedures should be reviewed.) J.3 Exercise critique will be conducted with
- 3. Demonstrate the licensce's capability for exercise controllers, observers, and players.
self-critique and ability to identify areas Critique items will be compiled and documented needing improvement. by the Exercise Coordinator. Nole: The annual radiological monitoring drill and semi-annual health physics drill will be included as part of the exercise. A separate health physics drill will be held to demonstrate the act al sample collection and analysis of tn-plant chemistry samples which includes the use of j the Post-Accident Sampling System (PASS). l
- Indicates NRC-identified improvement items from the 1990 exercise.
2160e
. . . - - . . . . - . . .. - .. . ~ . . . . - . -. . . - . . . - . .. . - - . - - . . . - - - . . . - . . - - - . - . - - - . - .
4 i VERMONT YANKEE NUCI. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 2.2 STATE OF VERMONT
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_ _. _ - ._. . . _ . _ . . . _m.- ,_ _ . . _ .m. .m . _ _ _ _ _ . _ _ . _ WRMONT EXERCISE oBJECTnts
;r N ERMONT YANKEE NUCLEAR POWER OTATION ERNON,-VERMONT- ,
NOVEMBER 6,1 1991 , OBJECTIVE PARTICIPATION EXTENT OF PLAY , IIM& GM IX-2, STATE LOCAL STATE / LOCAL
- 1. Demonstrate ability to Yes Yes
- State: To include notivate and use class- all activated
-ification Levels (ECLs) facilities through the appropriate
- Local: To include implementation of emerg- -
all Vermont EPZ ency functions and Towns. activitios corresponding , to-sach ECL The four ECLs aret
-notification of unusual event, alert, site arna emergency, and general emergency.
- 2. Demonstrate ability to Yes Yes
- State: State fully alert, mobilize, facilities activated and activate personnel for in accordance with both facility - and field- State Plan. Fiold based emergency functions.- based functions in
- See. Objective 34 for 24-hr., accordance with
" continuous staffing function State-Agency Response
- @ "a within a six-rear time frame. plans. 24 hour capability at selected facilities. ' Sea OBJECTIVE No. 3~ for selected sites.
- Local: Local towns-facilities activated 4
in accordance with Town Response Plans. See OBJECTIVE No. 34-for selected sites. 4
-ACTIVATED-FACILITIES
- STATE: State and Local war:iing Points State Emergency Operations Centers State Incident Field Office Emergency Operations Facility Joint Information Center LOCAL: Town cf Dummerston Emergency Operations Center i Town of Vernon Emergency Operations Center-Town of Guilford Emergency OperationsECenter.
. Town of Brattleboro Emergency Operations Center Reception / Congregate Care center; Bellows Falls Union High School.
u , mmm l _ . . ~ . . _l
l WRMONT i EXERCISE On#4T1vEs l S. Yes Yes Direction, coordination h' . Demonstrate ability to and control to be ;
\- direct and control J emergency activities, domonstrated at all
~Stato and Local facilities.
4* Demonstrate ability to Yes Yoc Communications to be communicate with all demonstrated at All appropriate locations, state and Local organizations, and field Facilities as personnel, appropriate.
- 5. Damonstrato adequacy of Yes Yes Facilities, equipment, facilities and displays d ispig 's , access maps, to support emergency & storic boards personnel. demonstrated at All Stata and kqqal facilities.
- 6. Demonstrate ability to Yes Yes gigtni EOC and IFO continuously monitor and Lgeal: All Local Town control emergency worher EOC's & Response exposure. Personnel.
Demonstrate the appropriate Yes No State: Stc,te level
,, , 7 .
equipment and procedures function with Federal P} (_/ for determining field support ur implement-Radiation measurements. ation of inter state assistance compact, if necessary. Field Teams. Local: Not a local function. B. Demonstrate the appropriate Yes No State: Same as No.7 equipment and procedures for Lp_ gall Not a local the measurement of airborne function. Radio-iodine concentrations as low as 10"-7 (.0000001) microcuries per'cc in the presence of noble gasses.
- 9. Demonstrate the ability Yes No State: State level to obtain samples of function, field particulate activity sampling assistance in the airborne plume obtained by initiating and promptly perform protocols of the I laboratory analysis. Intrastate Radiological Compact; and/or requesting i
federal assistance.
.Ma m*
2 09/02/91
VERMONT EXERCISE OBJECTIVES m ' h/~ ' State Field Monitoring ( teams (2) will demonstrate the proced-ure(s) for obtaining 4 samples. State will j demonstrate primary and ~ back-up resources for transport to laboratory. Actual laboratory analysis at the laboratory will be demonstrated during this exercise. FACILITIES: EOC, State of Vermont, Waterbury, VT. IFO, State of Vermont, Dummerston, VT. Laboratory, State of Vermont, Burlington, VT. Civil Air Patrol, Burlington, VT. AGENCIEst Vermont Department of Health Vermont State Police Civil Air Patrol Q4e Localt Not a local function. i
)
- 10. Demonstrate the ability Yes Yes State: Field data within the plume exposure obtained by assess-pathway, to project ment teams (2); will dosage to the public be utilized along with via plume exposure, utility supplied data.
based on plant and Information assessed-field data, at State EOC-Health Dept., for policy decision and issuing of public protective actions. Local: Not a local function.
- 11. Demonstrate the ab1]ity Yes No State: State policy to make appropriate level decision based protective action upon Health Dept.
decisions, based on assessment, support projected or actual from assisting state dosage, EPA PAG's, agencies in accordance availability of adequate with existing shelter, evacuation time State / Agency Plans, Local: Not a local 7'T estimates and other function. (_) relevant factors, , 3 (N/U2191
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A VERMowr
. EXEACISE oBJECTnTS ,U h'2 h Yes Yes Stater NWS w.ill be' l 3 /l . Demonstrate Q
to initially talert-the n a' bility notified _to activate public within the 10-mile NOAA weather alert EPZ'and.begin dissemination radios in the EPZ. of an instructional An actual' test tone-will be sounded with an
-message within 15 minutes of a decision by appropriato instructional message, state and/or local official (a). Coordination with
- border states, New Hampshire and Massachusetts, will be demonstrated prior to-NOAA Tone and release of information.
Windham County EBS, station WTSA Brattleboro 1450-AM or 96.7 FM, will transmit a ningle radio test announcement. Local: Local communities will simulate route alerting, telephone calla. Sirena Will be
..- s t sounded upon-State
~
instruction.
- 13. Demonstrate.the ability Yes No Statet State will to_ coordinate the disseminate additional formulation and dissem- public instructions and ination of accurate Infor- informationLas_ scenario mation and instructionsoto dependent. Both instant the Public in a timely &-prescripted messages fashion after the initial _ will be used. The State Alert:and Notification EOC through its Public has = occurred. Information Ronource will provide
- information to local
- EOC8a,-IFO, JIC, EOF as pertinent.
Local: Not a local function. 4 09/01/91
WPMONT EXERCISE oDJECTIVE.S p" 14. Demonstrate the ability Yes No Statet Staf f will pro-to brief the mndia in an vide briefings to the accurate, coordinated media, if prosent at and timely manner. State Eoc. Media briefings will be provided at tho Stato EOC; JIC. Information obtained from State operations contor. Infor nation may be instant or prescripted Media kits availuble at Stata EOC. LOSq11 Limited at a 3 local function.(87-73)
.[,glj
- 15. Demonstrato the ability Yes Yes Stalgi State will simG-to establish and operato late (demonstrate) rumor control in a coor- ognration of rumor dinated and timely fashion. control.
Local: Local EOC's will GROUP B - Scenario Dependent simulate (domonstrate) rumor control.
- 36. Demonstrate the ability Yes Yes Statet State liealth to make the decision to will demonstrate recommend t the use of KI proceduros, information to Emergency Workers and release necessary for Institutionalized persons distribution of KI to based on pre-determined Emergency Workers and institutionali2nd, criteria.
actual distribution is r,imulated. Local: Local EOC's, IFO, facilities having EW responsibilities will demonstrate simulate accessing supplies and simulate distribution according to Plan once the decision is made by the State.
- 18. Demonstrate the ability Yes Yes State: State issued and resources necessary notification through 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- Loca11 Local communities ulatien (including transit- (4) will identify dependent persons, Special transit-dependent, Needs populations. handicapped Special Needs groups-9"' persons and institutionalized school, and handicap, 5
0001!91
vent 0NT EXERCISE O!)JrCTIVt.s persons). institutionalized pop-j[h s ulations in each EP2 N community.
- 20. Demonstrate tho' Yes Yes State: State will organizational ability demonstrato the and resourcen necessary decision making, to control evacuation implementation of resources, to octablich traffic flow and to control accenn to ~ and control traffic evacuated and sheltered flow to and from areas, impacted aroaa.
Simulated. Lp_qali. Local EOC's will identify Areas for tne establishment of control points. Simulation.
- 21. Demonstrate the adequacy Yes Yes State: State will act-of procedures, facilition, ivato the Bollown Falls equipment and personal Reception Contor to for the registration, simulate receipt of i'y4 Radiological monitoring EVACUEES. Personnel and decontamination of and vehiclon with simu-(_)3 of EVACUEES. lated contamination will be processed by Bellows Falls Relocation the facility to Congregate Caro center comonstrate capabilition.
Lorali Limited action. Simulated movement of Local EOC to alternate operations.
- 22. Demonstrate the adequacy Yes N/A State: One congregate of facilities, equipment, care facility. Bellows and personnel for Falls U.H.S. will be congregate care'of activated by the State EVACUEES. Agency of Human Services assisted by BFUHS the American Red Cross and Local Resources.
_Loca l : Not a Ir, cal function. (87 20) [Objectiven Nos. 21,22 will be demons.trated out of sequence] (Tentatively scheduled for February, 1992.) ,
'I V 25.
b 09/OU91
VERMONT EXERCISE ODJECTnT.S {$ Ng
'%Y-CROUP c Every six Years
- 34. Demonstrate the ability No Yes State:_ Not applicable.
to naintain 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, f%
'\s' 4*, T.
7 i 7 09/02/91
.. _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _...._..._._.__.__________.._.._...____.m_.. _ . . -, s w ,
( t VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1991 y , 2.3 ST An. . . ~ . , . . s. f 4
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State of New Hampshire Objectives J for the - g[.- Vermont Yankee Nuclear Power Station 1991 Emergency Response Exercise I State Local New Hampshire .lfrisdictions 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 functions.
State and local emergency response organizations will be mobilized. The State EOC, IF0, Media Center, local EOCs, will be activated in accordance with the NHRERP. f.. The Reception Center and Decontamination 4.f; Center mobilization with tnewill be demonstrated Extent of Play for in accord 3nce Objectives 21,:22, and 25 (see Obj. 21, 22 and 25). OPHS laboratory activity will be simulated, except as spet.ified in Objective 99. Yes Yes
- 3. Demonstrate = the ability to direct, coordinate and' control emergency activities.
Yes Yes
- 4. Demonstrate the ability to communicate with all appropriate locations, organizations and field personnel.
l Yes Yes
- 5. Demonstrate tne acequacy of facilities, l
) equipment, displays and other materials to support emergency operations. Yes Yes
- 6. Demonstrate the ability to continuously monitor and control emergency worker-
-exposure.
Yes N/A
- 7. Demonstrate the appropriate equipment and-procedures for determining field radiation l
measurements.
- s
- Two Radiological Monitoring Teams will
' p be dispatched. d . Rev. 9/17/91 52629 I. _ - , e _ -.
State- Local' New Hamoshire Jurisdictions .qp s FD4A objective and Extent of Play ' A5ll Yes N/A
- 8. Demonstrate the appropriate equipment and proceduresforthemeasurementofairborge radiciodine concentrations as low as 10-microcuries'per cc 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 Detector. Yes N/A
- 10. Demonstrate the ability, within the plume exposure pathway, to project dosage to the public via plume exposure, based on plant and field data.
The objective will be de:ronstrated using the METPAC dose assessment model, or other methods as appropriate. Field data obtained
.3 by NHDPHS monitoring teams and from the 4[(;A)r Utility will be used as input for dose V determinations.-
Yes Yes
- 11. Demonstrate the ability to make appropriate protective action decisions, based on projected or actual dosage, EPA PAG's availability of adequate shelter, evacuation time estimates and other relevant factors.
Protective action recommendations will be made using tne criteria as outlined in the NHRERP. Yes Yes
- 12. fDemonstrate .the ability to initially alert the -
public within the 10-mile EPZ and Degin dissemination of an instructional message within 15 minutes of a decision by appropriate State and/or local official (s). O.: , Rev. 9/17/91 - e 52629 . em
State Local New Hampshire Jurisdictions ?,. . FEKA objective and Extent of Play __
- 12. The demonstration of the Public Alert and Notification System activation will occur at the first decision to notify the public. This demonstration will include sounding of.the sirens which are part of the Vermont Yankea notification system, broadcast of a test message over NOAA radios and broadcast of a test EBS message. Subsequent activations will'be simulated. EBS messages will be distributed but no messages other than the EBS test
' message will be broadcast.
Local EPZ communities will demonstrate this Dojective through the receipt of activation times and through the monitoring of siren /EBS activations. Yes Yes
- 13. Demonstrate the ability to coordinate the formulation and dissemination of accurate information and instructions to the public after the initial alert and notification has occurred.
RJblic information messages will De developed
;&g . ' periodically, based upon the requirements of the scenario. Broadcast of these messages either by radio or other news media will be simulated, however, they will be distributed to the EOF, IF0, Media Center, and State EOC. Local communities will receive information concerning PAR's from their respective Local Liaison wno are located at the State EOC. ~
Local communities do not prepare puolic information messages and do not have a representative at the Media Center. Local ccmmunities will monitor EBS radio broadcasts .at the local EOCs. Yes Yes
- 14. Demonstrate tne aDility to brief the media in an accurate, coordinated and timely manner.
The primary responsibility for briefing the meola lies with the State of New Hampshire and occurs at the Media Center. Local EPZ communities may respond to questions aoout local emergency response but are encouraged to refer any press inquiries to
, , , ,~ ,g; u ..
the Media Center. Rev. 9/17/91 52628
. t
State Local-New Hampshire -Jurisdictions 4+1, . FEMA objective and Extent of Play 14.' A control cell will call each locaF community i with a. media inquiry to initiate a local " response. Yes Yes
- 15. Demonstrate the ability to establish and operate rumor control in a coordinated and timely fashion.
The primary responsibility for rumor control lies with Rumor Control personnel who are located at the Media Center. Local communities should refer calls which address issues beyotd local quarter to the Rumor Control number. A control cell call will be made to each local community to initiate a response and referral. Yes Yes 16.-Demonstrate the ability to make the decision to recommend the use of KI to emergency workers-and institutionalized persons, based on predetermined criteria, as well , as to distribute and administer it once the decision is made, if necessitated by
~
radiciodine releases, g,y y i' The decision to use or not to use KI for emergency workers will be demonstrated at the State EOC. The ability to distribute and administer KI will ce demonstrated.
- Actual distribution and administration will be simulated.-
No -N/A
- 17. Demonstrate tne ability to make the decision,-if the State plan so specifies, to recommend the use of KI for the general public, based on
-predetermined criteria, as well as to distribute,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 tne acility and resources necessary to implement appropriate protective actions for the impacted permanent and transient y,.,
tp w plume EPZ population (including ; transit-dependent persons, special ' L needs populations, handicapped .
- persons and institutional 1 zed persons).
Rev. 9/17/91 52629 @-
e .- - .- _ _ - =._ . - _ .
+
State - - Local
, New Hampshire durisdictions 4,p ) FEMA objective and Extent of Play _
~ .
J.ks-/ 18. Special Needs listings are maintained by each comunity. Transportation requests beyond the capability of the community to furnish will be made to a NHOEM local liaison officer who will arrange for the transportation. No persons will be
" actually loaded or transported.
Partial Partial-
- 19. Demonstrate the ability and resources necessary to implement appropriate protective actions for school children within the plume EPZ.
This_ objective was demonstrated fully for NH EPZ schools during the 1990 mini-drill. The extent of play for the demonstration of this objective in this exercise will be to make an initial notification phone call to each facility to determine transportation resource requirements. A call to cransportation providers will be made to determine resource availability. Mobilization is , 11e*4 of actual transportation resources will be
- ( )g - simulated.
Yes Yes
- 20. Demonstrate 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 staf fed 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 maps and rosters. - Local communities that must initiate protective action, will demonstrate tne staffing of at least one traf fic 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 j Control using maps and rosters as well.
,3 ..
Rev. 9/17/91
- 52629 '
l i ( m-.e,,,w.,en.,--,.a.
1 State Local l Jurisdictions FEMA objective and Extent of Play _ few Fbmoshire .
,, 7 c,e Yes N/A
- 21. Demonstrate the adequacy of procedures, facilities, equipment and personnel for the registration, radiological monitoring and decontamination of evacuees.
The Reception Center will be demonstrated out of sequence (in conjunction with Objective #22). This demonstration will consist of setting up and staffing the Reception Center at Keene State College, and registering about 15 evacuees. In addition, a decontamination center supervisor and two decon monitoring units will demonstrate the monitoring and decontamination procedures
- on emergency workers and these same evacuees, which will include at lease one female.
Yes N/A
- 22. Demonstrate the adequacy of f acilities, 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 3.4 , Center at Keene State College. A walk-
.jj; -
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 cojective was demonstratea fully by the 1990 MS-1 Hospital Drill at Cheshire Hospital wnicn was evaluated oy FEMA Regicn I. .An out of sequence drill nas been held on April 10, 1991 to' demonstrate this objective. It is New Hampshire's understancing 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 exposed individuals.
J'.'7, Notification of facilities and
" ~ resources will te demonstrated as apprcpriate. Resources and
- perscnnel will be siculated.
Rev. 9/17/91 52629
._ - ~ - - - - - ' - - - - - _ _ _ _ _ _ , _ _ _ _ _ _ _ _
l State Local l FEMA objective and Extent of Play New Hamoshire pJrisdictions pgg 9:-{j g ' 24. An out of sequence drill has been held _on. April 10, 1991 to demonstrate this objective. It is New Hampshire's understanding that FEMA will not evaluate this drill. Yes N/A
- 25. Demonstrate the adequacy of out of Sequence facilities, equipment, procedures ~
and personnel for decontamination of emergency workers, equipment and vehicles and for waste disposal. Demonstrat_on of this objective will be in conjunction with the Objective 21 Extent of Play and will occur concurrently with the Oojective 21 demonstration. See Extent of Play for Objective 21. 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
. , .p , equipment and procedures for Jg'(iQ) 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 tne appropriate lao 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 puolic for ingestion pathway exposure and determine-appropriate protecti"e measures-based on field data, FDA PAG'S and other relevant factors.
No No
- 30. Demonstrate tne ability to implement both preventive and emergency protective actions for ingestion pathway hazards.
No No
- 31. Demonstrate tne ability to estimate l .f? %
total population exposure. Rev. 9/17/91
-52629 f
State Local New Hamoshire Jurisdictions
;;jf-l2 FEMA objective and Extent of Play _ ,
011\ $ No . No
- 32. Demonstrate the ability to s .
determine appropriate measures for controlled reentry and lecovery based on estimated total population exposure, available EPA. PAG'S and other relevant factors. No No 33. Demonstrate the ability to impleaent appropriate measures for controlled reentry. No No
- 34. Demonstrate the ability to maintain staffing on a continuous 24-hour basis by an actual shift change.
N/A N/A
- 35. Demonstrate the ability to coordinate the evacuation of onsite personnel.
No No
- 36. Demonstrate the ability to carry out emergency response functions (i.e., activate EOCs, mobilize staff that report to the EOCs, establish communications linkages and complete
. 3- .
$Qp'43 telephone call down) during an unannounced off-nours drill or exercise.
..( ,j l
l Revised 9/17/91 52629 l c.?
.i
th 2 -..aah,. 4 4pm__dh..a,.4 .4#---d- J e.T,aNa.4-cC#-lWa-W- J A- ,2f W.i C #4- # J AJ 45.m.h asJa.-iA2.i.. J4<b 4 'AS--AAI'-4,-=n-- -h 4i---A +-duWM a -rA-%-%ew4,4*e.k . Al 4 a 4swe-ma.4%m'a. A._
-M ._h< f VERMONT YANKEE NUCLEAR POWER' STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 2
2.4 COMMONVEALTH OF MASSACHUSETTS O 9
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPARE 0 NESS CXERCISE 1991 COMMONWEALTH OF MASSACHUSETTS OBJECTIVES AND EXTENT OF PLAY REVISION 5 August 1991 4 re.,U t S # d f A tr.O. gn O l l
~
1991 VERMONT YANKLE EAtnL2dc Objective 1 Emergency Clnssification Levels: EPZ Towns (6)
'T~ MEMA Area IV COC vf 1, 's-MEMA Headquarters EOC (Framingham)
EOF MDPH MSP (Troop D) Tri-State Fire Mutual Aid (Franklin County Dispatch)- Objective 2 Mobilization of Emergency Personnel: CPZ Towns (6) MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MDPH MDPH Field Teams MEMA EOF and Media Center Representatives f;z Objective 3 Direction and Controll E EPZ Towns (6) MEMA Srea IV EOC MEMA Headquarters EOC (Framingham) MDPH MEMA EOF Representatives Objective 4 Communications 1 EPZ Towns (6) MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MDPH MDPH Field Teams MEMA EOF Representatives Objective 5 Facilities, Ecuipment and Displav: EPZ Towns (6) MEMA Area IV EOC
; MEMA Headouarters EOC (Framingham) i
[ '/
\' - '
MEMA EOF and Media Center Representatives MDPH MDPH Field Teams
Objective-6 Emsrqency Worker Exposure Controlt f EPZ Towns (6) l MEMA Area IV EOC MEMA Headquarters EOC (Framingham)
' fr~N MOPH , ,
4 . MOPH Field Teams Objective 7 Field Radiological Monitoring: Alnblent : MDPH Field Teams Objective 8 Field Radioloqical Monitorinq: Airborne Iodine: MOPH field Teams Objective 9- Field Radioloqical Monitcrinq: Particulate Activity: MDPH Field Teams Objective 10 Plume Oose Projectiont MOPH EOF Representatives Objective 11 Plume Protective Action Decision Makinq: MEMA Headquarters EOC (Framingham)
% A NEMA and MOPH EOF Representatives Objective 12 Alert, Notification and Emeraenev Information (Initial Alert and Notification);
EPZ Towns (6) MEMA Headquarters EOC (Framingham) 5 t flE 0.s Objective 13 Alert, Notification and Emeroency Information
'Public
( Instructions); MEMA Headquarters EOC (Framingham) MEMA Media Center Representatives Objective 14 Alert, Notification and Emeroency Information (Media); MEMA Headquarters EOC (Framingham) MEMA Media Center Representatives O
Objective 15 Alert, Notification and Emergency Information (Rumor Control): EPZ Towns (6)
\ MEMA Headquarters EOC (Framingham)
MEMA Media Center Representatives Objective 16 Use of KI (Emergency Workers): EPZ Towns (6) MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MOPH Objective 17 Not applicable to Massachusetts. Objective 18 Protective Action - Plumo: CPZ Towns (6) MEMA Area IV EOC ME;1A Headquarters EOC (Framingham) MDPH f -) Protective Action - Schools;
\p'~ Obj ective 19 Will be demonstrated in a special exorcise.
Objective 20 Traffic / Access Control: EPZ Towns (6) , MEMA Area IV EOC MEMA Headquarters EOC (Framingham) MSP (Troop B) Objective 21 Not scheduled for this Exercise. Objective 22 Not scheduled for this Exercise. i O
objoetivo 23 Medical Servicqs (Trnnsporterion)J Will be demonstrated in a special enorcise.
! Objective 24 Medical services (racilitics);
Will be demonstrated in a special exercise.
Objective 25 Decontamination (Emerqency Worknes); EPZ Towns (6) Will be demo *strated out-of-soquence, if needed. Objective 26 Supplementary Assistance (Federal /Othor)J MEMA Headquarters COC (Framingham) MDPH Objective 27 Not scheduled for this Exarcise, through Objective 34 Objective 35 Evacuation of On-Site Personnel: . I N/A f% g3
\- Objective 36 " anced and Off-Hours:
scheduled for this exercise, l 1 \ l l l r jO $ r
co3ectiv+ 1 - tmergency Lanss212 cation Leve2s Demonstrate the ability to monitor, understand, and use Emergency Classification Levels ( (ECLs) through the appropriate implementation of emergency functions and activities corresponding to ECLs, as required by 8, the scenario. The four ECLs are: UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, and'CENEkAL EMERGENCY. Extent of Play EPZ Town EOCs The EPZ towns will receive and acknowledge 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 until MEMA EOCs and town EOCs become operational (Alert level). EOC staff will demonstrate appropriate decision making and coordination capabilities, pursuant j ,s Y" to each ECL, and their RERP plan / procedures. LI NOTE: EPZ town EOCs 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. l MEMA Area IV EOC The Area IV EOC staff will receive initial I notification and accident condition information I in accordance with procedures. The Area,IV EOC is activated at an ALERT level. Communications will be established with EPZ Town EOCs and MEMA Headquarters EOC after they become operational. Appropriate coordination activities will be performed by the EOC staff. l l
MEMA Hacdquarters EOC Initial notification cnd cccident information. will be received in accordance with procedures. MEMA will notify MDPH in .g., accordance with procedures. Changes;fn ECLs T*?'T -
' will continue to .be received throughout the 1 ,
e crcise, rollowing EOC activation and l mobilization of personnel, the staff will take appropriate measures in response to protective actions and coordinate with MDPH and MEMA Area IdEOC. 1' EOF Stato representatives at the utility's EOF will l roccive ECLs and accident information upon ! arrival and throughout the oxercise. MDPH ECL notification will be received in accordance with procedures. MDPH will contact the Vermont Yankee Control Room to obtain additional acciderst information. MDPH will coordinate ( l with MEMA Headquarters concerning necessary , p; protective actions. ELE ( s, MSp Troop D Initial ECL notification will be received by L l Troop B (State Warning Point) from Vermont , Yankee Control Room, in accordance with procedures. MSP Troop 8 will notify Tri-State Subsequent Fire Mutual Aid and MEMA. notification will continue to be received by Troop B and relayed to Tri-State Fire Mutual Aid until MEMA EOCs and the utility's EOF become operational. 1 NOTE: Verification of ECL notification will occur, as required, in accordance with procedures. L I s-w' '
Initial ECL notification will be received by Tri-State Fire' in Tri-State Fire Mutual Aid from MSP Troop 0, Mutual Aid accordance with procedures. Tri-State Fire 4 % - 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. Personnel Objective 2_- Mobilization of Emergency and activate personnel Demonstrate the ability to fully alert, mobilize, for bott facility and field-based emergency functions. Extent of Play Following ALECT notification, E00 staff will EPZ Town COCs mobilize (partial / full activation optional) to initiate response actions in accordance with procedures, fr. Following initial notification of the ECL, the 9 MEMA Area IV EOC Area IV Director will mobilize EOC staff in accordance with procedures. Following initial ECL notification, MEMA sta. MEMA Headquarters EOC will be notified in accordance with procedures. State EOF personnel will be notified in EOF accordance with procedures, be dispatched to the EOF at the proper ECL, and will initiate activation of the State area upon arrival. Following initial ECL notification, MDPH will MDPH Field Teams notify field team personnel in accordance with procedures. Two MDpH Field Teams will mobilize 8, and dispatch to demonstrate Objectives 7, and 9. d
rollciwing initial CCL notification, State Media Center Public Information personnel will be enobilized in accordance with procedures. Representatives
% . will bo dispatched to the Media Conter at the O appropriate ECL, : :
9,biective 3 _Oirection and Control i Demonstrate the ability to direct, coordinatt, and control ernergency activities. Cutent of play, t ' Upon full niobilization of personnel, town EOCs EPZ Town COC will demonstrato direction and control activitice in accordance with procedures. Upon activation of the Area IV COC, the staff
- MCMA Area IV EOC will demonstrate direction, control, and coordination activities in accordance with procedures.
\.
MCMA Headquarters EOC Upon activation of the COC, the staff will demonstrate direction, control, and coordination actitities with appropriate State J MEMA Area IV EOC; MDPH; MSP; port.onnel (e.j., EOF; Media Ceiter; etc), in accordance with procedures.
'Uoon arrival at the utility's COF, State EOF personnel will demonstrate direction, control, and coorsiination activities in accordance with procedures.
Obitetive 4 - Ccmmunications Demonstrate the ability to communicate with all appropriate locations, g orr3r.nizations, and field personnel, f
t
. t
[stentof'Pind ! 4 rollowing mobilisat ion, ' conmiunication CPZ Town COCs f
- activities will be (;crformed in accordance with u,
procedures and operational requirements. Con,munications with porsonnel and facilitics r involved in out-of-sequence objectivos will not
- occur.
i rollowing mobiliration, communications MEMA Area IV COC capabilitics will be demonstrated in accordateo with procedures and operational / coordination requirements. > a MCMA Headquarters COC Tollowing mobilization, communication
~
capabil1 ties will bo demonstrated in accordanco with procedures and operational requirements. , Following mobillration, communication and ' COF-coordination capabilities will to demonstrated go- , '. .a p - in accordance with procedures and operational
'6 requirements. 5 M3pH Field Teams All operational communications will be demonstrated in accordance with procedures and operational support needs.
Objective $ - Facilities, Ecufpment. and Display 2 Demonstrato the adequacy of f acilities, equipment, displays, and other materials to support emergency operations, Extent of Play-All participants will domoastrate- the adequacy of their facilitics, equipment, displays, and materials for response and operational activities. 1 i.' l I 1. I
Obioetive 6 - Em*rgency Worker Caposure Control l Demonstrate the ability to continuously monitor and control omorgency j
;t worker exposure, ,
Extent of Play . Following mobilization of personnel, the EOC EPZ Town EOCs will demonstrato exposure control activities in accordance with procedures (e.g., dosimetry /KI). Exposure control measures will be coordinated with appropriate State authorities, as required. f Will demonstrate the capability to disseminato , MEMA Area IV EOC State exposure control guidance to local EOCs, via the RERP Radio System. MEMA Headquarters E00 Will demonstrate the capability to develop and 1 disseminate state exposure control directivos. pcs 1 Will demonstrate exposure control activities in , MDPH Field Teams accordance with procedures. NOTE: Dosimetry will be isuued to field emergency workers as plans and procedures indicate. Ohioetive 7 - ric1d audiolonical Monitorina Ambient Demonstrate the use of appropriate equipment and procedures for determining field radiation measurements. Extent of play Following mobilization, two MOPH Field Teams MDPH Field Teams will be dispatched. Field radiation 3 measurecaents will be demonstrated sising (f . 4
, ,..#.- -..w .. e .-,-y-,v--,--....w--.~ , , . . . . . - ~,-.,_v,~,,,, ,- -y --
,--.----r,m-v.,
' appropriate equipment to locate and defino .
plume caposure radiation levels (plume verification and tracking). Ctate/ Controllers % .. 4 will provide data. . -(. O Objective 0 - Field Radio h cal MonitorinE' Airborne Iodino f Demonstrate the appropriato equipment and procedures for the measurement f of airborne radiciodine concentrations as low as 10 uCi/cc in the i prosence of noblo gases, t
- Emtent of play- ;
i Two MDPH Field Teams will demonstrate l MDPH Field Teams radiological monitoring measures for airborno [ radiofodino concentrations by utilizing , equipment for air sampling in accordance with , procedures. Data necessary to simulate air sampling results will be provided via an ! exerciso controller. ? P
,i : A MDPH Field Teams will be dispatened for '
sampling purposes, according to scenario ' requirements. Field Team communications will be demonstrated for coordination purposes. Objective 9 Field Radiolooiral Monitorina Particulato Activity Demonstrute the ability to obtain samples of particulate activity in the airborne plume an'd promptly perform laboratory. analysis. . Extent of play Two MDPH Field Teams will demonstrate sampling -
-MDPH Field Teams methods for particulate activity by performing l required actions with necessary. equipment, in accordance with procedures; Simulated samples-i
). :
will be prepared for transport to the MDPH laboratory for analysis. e # M y- h- p g g- e v---h-'-Pg,--ywwv-,w,m.cw-9--ym '
*vv-'
Obiective 10 - Plunge Dose Pro $ection l 1 Demonstrate the ability, within the plumu caposure pathway, to project dosage to the public via plume exposure (s), based on plant and field data.
~O Extent of Plal ,
EOF MDPH personnel located at the utility's COF will demonstrato dose projection methods using simulated plant information and MDPH Field Team sampling data, gbioetive 11 - Plun.o Protective Action Decition Making Demonstrate the ability to make appropriate protective action decisions, based on projected or actual dosage, EPA PAGs, availability of adequate shelter, evacuation time estimates, and other relevant factors. Extent of Ditay MEMA Headquarters E00 EOC (Framingham) staff will demonstrate
# decision--making capability f or the determination of appropriate protectivt.
actions, using available dose projection information, protective action guidance, shelter-in-place capabilities, evacuation time estimatos, and other considerations for public safety (e.g., weather, highway conditions, time of day, etc), i Th'e protective action dectsion-making process will be based upon recommendations received from State representatives located at the utility's EOF, Protective action decisions (for implementation) will be coordinated with contiguous States, as aopropriate, and MEMA Area IV EOC staf f. MEMA Area IV EOC will coordinate and transmit State protective action recommendations to local EOCs, as required,
u. Pads 50Chusetti r3pr3sentottygs ( t1g,,rmf , ,s e n j EOI tha utility's tor will utilizo availeblo inf orn.ation regarding plant release (s) and field survey data, te determine protective
,b action reconimendations.
'.\
These recommendations will be coordinated with the MEMA EOC staf f f or decision-making purposes. Ob{cetive 17 - Alert, Notification, and Emorgency Information: Initial Mert and Notification 10-mile l l Dernonstrate the ability to initially alert the public within the f EPZ and begin dissemination of an instructional tnessage within 15 minutes l I of a decision by aopropriate State official (s). t Evtfnt of Plav EPZ Town EP2s Town EOCn will demonctrate the actionc necessary to perform this objective. Sirens will be activated according to procedure. fp MEMA Headquarters EOC EOO staff will simulate the performance of initial notification action +. necessary to demonstrate this objective. Coordination with contiguous states will be demonstrated, the simulation of EBS shall be as follows: CPCS-1 station will be contacted and a test "Real" trie s sage s will be message broadcasted. used in the EOC, but not broadcasted. NOTE: As part of the Alert and Notification New Hampshire, and System shared by Vermont. Massachusetts, the NOAA weather-alert radio will be activatco' and a test tressage broadcasted. ['_ l
. _ - - - .. - . - - .- . . _ . . . - - . . . . - . - . . - - . . ~ _ .
Obinctivi 13 ' Alert, Notification, nnt Em7rqsney Inform 9tiont public Instructions Demonstrate the ability to coordinate the formulation and dissemination "]'7 s of accurate information and instructions to,,the public in a timely
' (_ )
fashion after the initial alert and notification has occurred. Extent of Play MEMA Headquarters EOC EOC staff will formulate appropriate public information/ instructions. Applicablo EDS information will be simulated. MEMA Headquarters EOC will coordinate media information with the Media Center, Vermont, New 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. ~@ NOTE: Actual dissemination of public s; [. L , I information and instructions will not occur. Media Center operations relating to this objective will be simulated. Related EDS information will be simulated. Objective 34 - Alert, Notification, and Emeroency Information: Media coordinated, Demonstrate the ability to brief-the media in an accurate, and timely manner'. Extent of Play MEMA Headquarters EOC Information for news releases and briefings will be relayed to Media Contor personnel for release in accordance with procedures.
\
v
- - - . . . ~ - - - - , - . - . , , - ., ,,
M2dia Center Stato personnel at the Media Center will dt af t news releases, prepare briefings for the rnedia
A and coonfinate with other Media Center representatives to, ensure that periodic briefings are pro'ided i to the news media, r
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 nade to the local EOCs. COC 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 measures 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 COC. l Media Center Rumor control activities will be demonstrated in accordance with procedures, Matters concerning rumor control will be incorporated i in periodic news briefings and media releases. l
se of KI? E m m enc y wo r w r ,
.Obiective 16 -
n, I Demonstrate the ability to make the decision to recommend the use of H (potassium iodide) to emergency workers based on predetermined crit b as we'll as to distribute and administer it once the decis .on is ma e, d d if
'l necessitated by radiolodine releases. .. .
tJOTE: There are no residential institutions (hospitals, nursing homes, prisons, etc) within the EPI. fatent of play Emergency workers, directed by the State, will-EPI Town E00s demonstrate the capability to distribute and take KI (potassium iodide) according to _p rocedures. All activities related to this objective will be simulated. MDPH staff will demonstrate the ability to EOF evaluate simulated release data in order to
~ -
develop ricomme'nd'aElons and;instruetions.(if b required) for the'use of KI by emergency ' workers. Decisions will be coordinated with i MEMA Headquarters E00. MEMA Headquarters E00
~
After the recommendation for the use of MI is , received from'the EOF, MEMA and MDPH at the E00 will procure authcrization for the use of KI from the Commissioner of Public Health or his designee and coordinate the decision to Area IV and the EPZ towns. 4 Staff will relay decision to distribute and MEMA Area IV EOO take KI to the local 1;nwns. Once the decision to administer KI is made by MDPli, MDPH Field Teams the notification to field personnel will be made, but the administration of KI will'be demonstrated through simulation. . ~
.- . . - - . . - . . _ . . . - - . . . . - ..- _ _ .- ~ - _ _ . _ _ - - . - - -
Obinctive 17 Usn of KI: GinSrol Population Not applicable to the Commonwealth of Massachusetts. , :Qm ' <
'M Objective le - Implementation of Protective Actions: Plume EPZ Massachusetts will demonstrato Objective 18 as required only for the EPZ townJ 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 Protective Actions: Evacuation of Schools This objective will be demonstrated in a special exercise. Objective 20 - Traffic / Access Control Demonstrate the organizational ability and resourers necessary to control rA cAss evacuation traffic flow and to control access to evacuated and sheltered vf( ,/N areas. Extent of Play EPZ Town EOCs EPZ EOCs will demonstrate the ability to direct. control, and monitor' traffic 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.
.'t-
Emergency personnel will respond (non-emergency) to the Traffic Control Point (TCP) location along with local department of Public Works personnel (if required), to i ,-
' simulate traffic control activities.
fJOTE : Traffic control devices (e.g., barricades, traffic cones, signs, etc.) will be delivered to TCP locations but will not be set up, tJormal traffic flow will not be disrupted. MSP Troop D Massachusetts State Police will demonstrrte one Access Control Point (ACP) in a similar manner 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 D required, ge MEMA Area IV EOC EOC staff will coordinate with EPZ Town EOCs I and demonstrate the ability to take additional measures as necessary, obioctive 21 - Relocation Centors: Reqistration, Monitorina, and Decontamination (Evacueesl Will be demonstrated according to procedure, if needed. Obinctive 22 - Relocation Centers; Congregate Care Will be demonstrated according to procedure, if needed.
0,bi&ctive 23 - Medical S?rvices: T rans porta t ion Will be demonstrated in a special exercise. m. Objective 24 - Medical Services: Facilities J Will bo demonstrated in a special exorcise. , Obioetive 25 - Decontamination: _ Emergency Workers. Demonstrate the adequacy of facilities, equipment, supplies, proceduras, and personnel for decontamination of emergency workers, equipment, and vehicles, and for waste disposal. All EpZ towns will demonstrate this objective according to procedures, if needed. . Obiectjve 26 - Supplementary Assistance (Federal /other) Demonstrate the ability to identify the need for and call upon Federal
; .x
(.l and other outside support agencies' assistance. T Extent of play MEMA Headquarters EOC The EOC staff (MEMA/MDpH) will demonstrate the call for outside support agency sssistance, and will make initial contacts with the appropriate agencies. All subsequent contacts will be simulated. 6
, COC staff will coordinsto supplcmantal assistenco information with State personnel at the EOF and with MENA Area IV EOC.
NOTE: MOPH is primarily responsible for determining the citent 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. eF Will make recommendation for supplementary assistance. objgetive 27 - Inaestion Exposure Pathway; Sampling Will not be demonstrated this exercise. e, - tic [ Obiee_tive 28 - Inaestion Exposure Pathway: Lab Operation Will not be demonstrated this exercise. Obinctive 29 - Inaestion Excosure Pathwav; Dose Assessment k)ill not be demonstrated this exercise. < - Objective 30 - Incestion Exposure Pathway: Protective Action Rycommendations Will not be demonstrated this exercise. Obicetive 31 - Recovery, Re-Entrv, and Relocation; Total population Exposure Estimates i Will not be demonstrated this exercise.
~
Objective 32 - Recoverv2.,fte-Entry, and Relocation: Mcasurements Will not be demonstrated this exercise.
"**% )
Obiective 33 - Recovery, Re-f t. d Relocation: Implementation l Will not be demonstrated this exercise. Objectivo 34 - Mobilization of Emergency personnel; 24-Hour Continuous Basis (Shift Chango) s This objective will not be demonstrated. Objectivo 35 - Evacuation of on-site Personnel This objectivo is not applicable to the Commonwealth of Massachusetts. Objective 36 - Unannounced and Off-Hours This objective will not be demonstrated during this exercise. 4% Qa*
'k
. 1 a
- 6
r l i I i i i I VERMONT iANKEE INCLEAR POWER STATION ! l EMERGENCY RESPONSE PREPAREDNESS EXERCISE -
- I
!' 1991 l i
?
l I i 3.0 CUTDELINES AND SCOPE l l t 1 [ t O f l i t D 5 L e a 1
- .
- ~---_ - _.. .._ . - _ . - - - _ . . . .,
O VERMONT YANKEE NUCLEAR l'0VER STATION LMERGENCY RESI'ONSE I'REPAREDNESS EXERCISE 1991 3.1 COIDEL11[Eji O O
Rev. O Page 3.1-1 I 'd VERMONT YANKEE NUCLEAR POWER STATION f11ERGENCY RESPONSE PREPAREDNESS EXERCISE , 1991 3.1 EXERCISIL.GUIDELUiES A. Eurpnat This package provides guidance for conducting the 1991 VYNPS Emergency Response Preparedness Exercise. It provides the framework for demonstrating emergency response capabilities, conducting the exercise and evaluating response activities. B. Ccatcyls of Operations _anLControl of the_ExtIrlac An Exercise Coordinator has been appointed by Vermont Yankee management to oversee all exercise activities. The Exercise Coordinator is responsible for ap3 roving 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 exercise, 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 for documenting and evaluating observed activities. In each facility where an activity takes place, the Controller will make judgment decisions to keep the action going in accordance with the scenario timeline. The Controllers will also provide guidance to Observers and resolve minor problems which may occur. If a serious problem arises, an Observer should first contact the Facility Controller who will then contact the Exercise Coordinator 2154e
b Rev. O Page 3.1-2 O for guidance or resolution of the problem. All major requests for , scenario modifications or holding periods must be cleared through the Exercise Coordinator. Controllers also have the authority to resolve scenario-related prchlems which may occur during the exercise. Observers for the exercise will observe the players as they perform their assigned emergency response functions. Observers are i responsible for being knowledgeable in the area of their assigned function. The Obserwirs will critique the effectiveness of the emergency respons actions taken during the exercise and will also provide a writtw, 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 exercise vill be generated by running tne 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 impicment appropriate emergency plan implementing procedures. These procedures should include a determination of the emergency classification in accordance with the Vermont Yankee Emergency Plan. Notifications will be made to the appropriate federal and state authorities. The hypothesized emergency will continue to develop based on data and information provided to the operators located in the simulator. Wherever possibic, operators should completo 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 facilities to the maximum extent possible in a limited period of time. 2154e
Rev. O Page 3.1-3 O C. G e n e raLG uid an c e_Lo r_t h tC onduc Lc Lt helxe rcis c
- 1. Simul ating_Ia erge ncy_Ec a pon a c_Ac. tion s 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 fencible 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 directions on which actions are to be simulated. Radiation Work Permits (RWPs) have nol been losued for the conduct of the emergency response exercise. If scenario events direct players to areas that are actually RWP-controlled due to high radiation, surface contamination, or airborne radioactivity, players will simulate response activities without actually entering the RWP-controlled area cren if they are authorized on the RWP for some other duty.
- 2. Arciding_ Violations _oLLaws i
Violation of laws is not justifiable during the exercise. To implement this guideline the following actions must be takent
- a. All Evaluators and potential participants must be specifically informed of the need to avoid violating any federal, state and local laws, regulations, ordinances, statutes and other legal restrictions. The orders of all police, sheriffs or other authorities shall be followed as appropriate.
2154e
Rev. O Page 3.1-4 b Participants will not direct illegal actions to be taken b. 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. Arc.iding_lertonnel_and_Ernstriy_Indangerment All participants will be instructed to avoid endangering property (public or private), other personnel responding to the events, members of the general public, animals and the environment.
- 4. Actions to_Minimite Puhlic_Inconysnience It is not the intent, nor is it desirable, to effectively train or test the public response during the conduct of the exercise. Public inconvenience is to be avoided.
The conduct of an exercise could arouse public concern that an actual emergency is occurring. It is important timt conversations that can be monitored by the public (radio, loudspeakers, etc.) be prefaced and conclude with the words, "THIS IS A DRILL; THIS IS A DRILL." D. Emergency Respanan_Impiementationmd_OpmInlinna
- 1. Initial _and_ follow-Up_Notif.iciLtion Initial and follow-up notification of the emergency classification will be made by the plant staff in accordance with existing emergency plan implementing procedures, unless l
directed otherwise. 1
'2154e
Rev. O Page 3.1-5
- 2. ContrcLRecut0perations A Control Room emergency response crew will be positioned in the Simulator, located at the Vermont Yankee Training Center in Brattleboro, Vermont. The support staff normally on duty will initially be simulated until after the ALERT when it will be performed by the emergency response organization. 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 dt.ta, will be provided to the Control Room emergency response crew as necessary. Communications links that duplicate the emergency consnunications 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 transmission of emergency announcements and information (e.g. , Caitronics) will also be utilized.
- 3. IechnicaLSupporLCenter (TSCL0gera.tions The TSC emergency response organization will be activated during the exercise. TSC infortnation will originate from the Simulator Control Room. Information that is normally accessible by TSC personnel irom the plant computer will be provided by Evaluators utilizing 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
Rev. O Page 3.1-6 k-- 4. Ope rationa_Suppor.LCenter_IOSCL0pera tions The OSC emergency response organization will be activated during the exercise. Operations Support Center response activities will be comunicated to the Technical Support 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. Energency.0pm.tationalacilitv/lecorcry_Crnter_LE0E/EU Dys.raLinna The EOF /RC emergency response organization will be activated during the exercise. Infonnation and data will be transmitted to the EOF /RC from the TSC and Control Room (Simulator). EOF Evaluators will provide other data to EOF /RC players as necessary.
- 6. Off-jlitelonitoring._leAma Off-site monitoring teams will be fully activated and dispatched in accordance with existing procedures. Simulated data will be provided to off-site monitoring teams by the-Off-Site Monitoring Team Evaluators.
- 7. Hewaledia center _.0parations The News Media Center will be activated and staffed during the exercise. News Media Ocnter staff will obtain all the necessary information on current plant status through comunications channels with the E0F/RC. Press releases will be generated and disseminated in accordance with the Vermont 2154e s_/
I. . -- --
Rev. O Page 3.1-7 O Yankee Communications Departraent Emergency Response Plan and Procedures. All press releases are to be clearly inarked: Tills IS A DRILL.
- 8. Secutily_0yerations.
All exercise-related security emergency response activities will be irnplemented in accordance with existing procedures. Access control and personnel accountability within the protected area will be demonstrated. At no tirne will actual plant security procedures be violated in support of the exercise. E. ExercisgJtDnination The exercise will be terminated by the Exercise Coordinator when all emergency response actions have been completed in accordance with the exercise time sequence and exercise objectives. The following steps will be irnplemented to terminate the exerciset
- 1. The Exercise Coordinator will obtain inf onnation f rom 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 objectives have been satisfactorily observed.
- 3. Upon receipt of information from the Facility Controllers, the Exercise Coordinator will inform the Lite Recovery Manager and TSC Coordinator that all exercise observations have been completed and that the exercise can be terminated.
1 2154e
Rev. O Page 3.1-8 O 4. A coordinated decision to terminate the exercise will be made between the Site Recove.ry Manager and the TSC Coordinator. The Site Recovery Manager will also receive concurrence from the States to terminate exerciso activities.
- 5. The Site Recovery Manager or TSC Coordinator will terminate the exercise.
The exercise may also be terruinated under the following circumstances:
- 1. An actual plant emergency condition develops coincident with the exercise.
- 2. An actual off-site emergency impacts the response actions of Vermont Yankee exercise participants.
in the event that Item i should occur, the following actions will be taken:
- 1. The Shif t Supervisor will contact the TSC Cootdinator and inforn 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 tuessage may be immediately followed by the appropriate emergency announcements. O 2154e
Rsv. 0 l Page 3.1-9 i b 4. The Exercise Coordinator will be responsible for directing the-actions of all other exercise participants. ; i In the event that Item 2 should occur, the following actions should be taken:
- 1. The Shif t Supervisor will notify the Control 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 the exercise.
- 3. The Exercise Coordinator will be responsible for temporarily halting the exercise until such time a decision is made.
- 4. If the final decision is to cancel the exercise, the Exercise t
Coordinator will be responsibic for directing the activities of all A exercise participants, as well as for the notification of the NRC.
- 5. If the final decision is to continue the exercise, the Exercise ~
Coordinator is responsible for informing all Evaluators of any projected changes to the expected response action (s).
- 6. The Exercise Coordinator will direct the organization as to the appropriate action required to restore the exercise sequence.
2154e
I O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 t i I 3.2 PLAYER 1*'STRUCTIONS AND CROUND RULES 5 0 O
Rev. 1 () Page 3.2-1 VERMONT YANKEE NUC1. EAR POWR STATION EHERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 3.2 PLAYER INSTRUCTIONS AND CROUNL .. RULES . The Vermont Yankee Emergency Response Preparedness Exers !ae 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 llampshire, Commonwealth of Massachusetts and ths local towns within the plume exposure pathway emergency planning zone.
g The successful demonstration of emergency response capabilities will depend on player response and protocol. The following information contains exercise details and instructions for the players regarding the exercise. Department lleads are responsible for ensuring that personnel are trained on this information.
A. General Guidelinen
- 1. Parti:1 pants will include the Ekercise 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.
Controllers, Obse1 vers, (herein referred to as " Evaluators") and Federal Evaluators will be identified by badges.
- 2. Always identify yoitself by name and function to the Evaluators.
. Vear a name tag if one is provided,
-~--s
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i I Rev. 1 () 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 scenario
- b. Area radiation data at the location of emergency teams,
- c. Airborne data at the location of emergency teams after a sample has been properly obtained.
- d. Counting efficiency of all counting equipment.
O e, Activity f rom nose swabs or skin contemination surveys. 4 You may anL ask the following from the Evaluators;
- a. Information contained in procedures, drawings, or instructions,
- b. Jud5ments as to which procedures should be used,
- c. Data which will be made available later in the scenario, d, Assistance in performing actions,
- c. Assistance in performing calculations.
- 5. Play out all actions, as much as possible, in accordance with your plan and p cuedures as if it were an actual emergency, If O an action or data is to be simulated, an Evaluator will provide
I I-Rev. 1 () Page 3.2-3 appropriate direction.
- 6. Always ident;'y and discuss yout action,to the Federal 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 tssigned to complete a response action, be sure to be accompanied by an Evaluator at all times.
I
- 9. If you are in doubt about completing a response action, ask your Evaluscor for ,larification. The Evaluator vill not prompt or coach ycu, Emergency response accions must.not place participanto in any potentially hazardous situations.
- 10. The Evaluator vill periodically issue messages or instructions designed to initiate response actions. You gull accept these messages immediately, They aca essential to the proper conduct of the exercise.
- 11. If an Evaluator intervenes in your response actions and recommends you redirect or reconsider your play actions, it is for a good reason. The Evaluator's direction may be essential to the overall success of the exercise for all participating groups.
- 12. If you disagree with your Evaluator, discuss your concerns.
However, the Evaluator's final decisions must be followed.
- 13. Respond to questions in a timely manner.
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Rev. 1 Page 3.2 -4 [.m %}-
- 14. Do not Secept 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 scenario 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 conditions. Do not ld this confuse you or cause you p to act unwisely. However, no one is exempt from nore'l station C 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 will follo*r the exercise.
Provide any comments or observations to your lead player or
^
Evaluator a ter the exercise. Areas for improvement or weaknesses when corrected will improve the overall emergency response capability. O v
1 i l Rev. 1 [)' QJ Page 3.2-5 B. Player's Sinulation List 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 will be allowed which alters or affects the ongoing operation of the plant. The simulation list is as follows:
- 1. Scenario specific data will be programmed into various Simulated Plant Process Computer (SPPCS) terminals via the simulator. The Control Room's SPPCS terminal will remain tied to the plant process computer (ERFIS).
- 2. A sufficient number of individuals from the Vermont Yankee Emergency Response Organization will be prestaged at the
\s Simulator.
- 3. Meteorological data will be simulated through the simulator SPPCS computer.
- 4. Af ter plant evacuation acccantability 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.
S. 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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Rev. 1 Page 3.2-6
)_
- 8. No emergency response facility evacuation will be demonstrated during the exercise.
- 9. Off-site monitoring teams and security boundary monitoring 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 Caitronics is not available from the simolator; 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 V
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 aqt been issued for the conduct of the exercise.
C. Simulator Control Room Information i The following describes how the Simulator Control Room emergency response activities will be integrated with the plant Control Room functions during the exercise: l
- O) i i
Rev. 1 Page 3.2-7 {)T g
- 1. Players reporting to the plant Control Room will be directed to an area (SS office) that will have a Control Room Evaluator and communications link with the simulator. All Control Room exercise communications should be directed to the Simulator Control Room.
- 2. All exercise-related Caitronics calls to the Control Room and vice versa will be relayed or answered by the Control Room Evaluator. CllANNEL 3 should be utilized for all exercise messages.
- 3. Caitronics plant announcements will be coordinated by the Simulator Evaluator. They will be made by the operating crew in the plant Control Room.
(,- (i,/ 4. TSC Communicators normally assigned to the Control Room and a Radiation Protectior Technician for transmitting initial radiological and meteorological data vill be prestaged in the simulator.
- 5. Personnel movement in and out of the Simulator Control Room will be limited to the Evaluators.
- 6. Communications equipment in the Simulator Control Room is the same as the plant Control Room. The commercial telephone extensions are different but the auto ring down circuits and speaker telephones are operable. The orange Nuclear Alert System (NAS) State telephone and red Emergency 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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i f- _ Rev. 1 ( Page 3 2-8
%)
D. fjaver's Gamesmanship The following is a list of items that should be followed to improve gamesmanship during the exercise:
- 1. Make it known when significant events occur or when you are about to perform a significant action.
- 2. Keep all messagas, status boards, and problem boards accurate, current, timed, and dated.
3, Hold briefings regularly, approximately every 30-45 minutes, or as conditions warrant.
- 4. Key players should wear badges which identify their role. Bound V log books should be used in all emergency response facilities.
- 5. All announcements, including those on the Gaitronics, 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.).
l E. Personnel Accountability and Participation (Exemoted Participants) L Procedures require that all participants be identified. Proper identification will not only help eliminate ennfusion, 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 Office in Brattleboro, (
Rev. 1
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Page 3.2-9 (
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Although it 1. expected that all personnel will respond to the declared emergency as delineated in the applicable procedures, it is recognized that a number of persons (e.g., normal plant operations shift, normal security complement, fire watches, etc.) will not participate due to the 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 by the Emergency Plan. The list of exempt t'
personnel will include 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.
L F. Qff-Site Participation (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 emerEency classifications in accordance with established procedures will be demonstrated as follows: j \,. a. NRC will be notified by utilizing the red ENS-NRC telephone.
Rev. 1 [~'T Page 3.2-10 LJ
- b. Vermont, New Hampshire, and Massachusetts State Police dispatchers and State Emergency Operations Centers (EOCs) will be notified through the orange NAS telephone.
- c. Vermont, New Hampshire, and Massachusetts State officials present at the EOF /RC and the News Media Center (NMC) will be notified by the appropriate Vermont Yankee personnel.
If any state official tries to contact the plant Control Room REGARDING THE EXERCISE, the Vernon switchboard should transfer the call to the Simulacor Control Room in Brattleboro. The NAS orange telephone extension in-the Simulator Control Room is 613. G. Exercise Critlaues ,\m / 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. Emerzenev Response Facility Cririgygg The critique sessions will be conducted by the Controllers. Exercise participants will be debriefed on the findings for their particular emergency response facility (s). Four critique sessions will be held:
- 1. SRM and EOF
- 2. TSC and Simulator Control Room
.s 3. Operations Support Center and Security 7
(_,) 4. News Media Center I l
Rev. 1 m. 1 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. Eggreise Crittaue 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. NRC Exit u
-Immediately following the exercise critique, the NRC will present their preliminary findings. Participant.s will be the same as in the exercise critique session.
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. O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDFESS EXERCISE 1991 f
I 3.3 PROCEDURE EXECUTION LIST
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Rev. 1 Page 3.3-1 3.3 EMERGENCY PIAN IMPLEMENTING PROCEDURE EXECUTION LIST Procedure Number Rev. No. Title AP 3125 10 Emergency Plan Classification and Action level Scherre OP 3500 10 Unusual Event OP 3501 12 Alert OP 3502 24 Site Area Emergency OP 3503 26 General Emergency OP 3504 23 Emergency Communicationa 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 14 Evaluation of Off-Site Radiological Conditions 0? 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 O
O VERMONT YANKEE NUCLEAR P0k'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 4.0 CONTROLLER AND OBSERVER INFORMATION O O
l: O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 4,1 CONTROLLER AND OBSERVER ASSIGNMENTS s NOTE: ASSIGNMENTS WILL BE PROVIDED AT THE EXERCISE BRIEFING SESSION O
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.- 's<
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 l l l 4.2 CONTROLLER AND OBSERVER EXERCISE GUIDANCE I l~ I-
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. -2453e f
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-- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 4.2 CONTROLLEILRiILDASEMEILEKERCISE_GUIDMICE 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 assignments should be discussed at this time. Each Evaluator should ensure that they are familiar with the location (s) required by their assignment.
Emergency response facility 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 terminated, the Controllers will
\~-
meet with the Observers to obtain their concents, observations, and documentation. Each Controller will be responsible for ensuring that the documentetion is provided to the Exercise Coordinator at the conclusion of the exercise. Each Controller is also responsible for providing a brief summary of their facility comments during the player debrieting. 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, checklists, and evaluation forms for documentation purposes. 2453e l [V} l'
Rev. 0 Page 4.2-2 l I
@ The primary role of Evaluators is to evaluate the emergency response activities of the players. In order to document the adequacy of emergency response actions during the exercise, Evaluators are required to complete the Duergency 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. provice a clear, written explanation of the finding, with recommendations for improvement which detail corrective actions, if possible.
Evaluators should not allow their biases to be documented as recognized weaknesses or deficiencies. Comments and recommendations should be further subdivided under the general headings as follows: Facility Activation / Organizational Control, Communications, Adherence to Plans and Procedures, Equipment Capabilities, Scenario Training, Facility Layout. Off-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Comments. O Facility Activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the facility was rativated; (3) when initial activities became well organized; (4) whether personnel performance followed the organized arrangements specified by plant procedures; and (5) the efficiency of methods of authority transfer. If a transfer of 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 connnunications use; (2) whether aufficient 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 consuunications system (i.e. , location relative to 2453e
Rev. 0 Page 4.2-3 O V traffic flow); (6) whether there were any recognized difficulties in the use of computer systems; and (7) whether facility boards were effectively used. Evaluators should document their comments in this area very carefully, ! providing sufficient details to track any recognized deficiencies. I , Plans and Procedural comments should identify: (1) whether personnel were familiar with the details of the overall concepts of applicable procedures; (2) whether situations developed which required deviation f rom the procedures . or plan; (3) whether 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 4 l required to complete an assigned function. < Equipment capability comments should identify: (1) whether all necessary materials and equipment were available and functional; (2) whether emergency response personnel checked operability of equipment prior to conducting their O assi;nment; (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 details deviated from actual procedural requirements; and (3) whether the scenario detail provided any prompting to the player. The adequacy of the scenario in keeping the players active and interested throughout the exercise should also be addressed by the Evaluators. Training comments should identify: (1) whether plant personnel have been provided sufficient training to handle "ad hoc" procedural deviations; and (2) whether training identified improper procedural requirements. 2453e
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Rev. O Page 4.2-4 Comments on facility layout deficiencies / recommendations should identify: (1) whether the available work space was adequate; (2) whether traffic flow hindered the response efforts; (3) whether the noise level hindered emergency response efforts; and (4) whether sufficient references were available to complete the-job assignment. Off-site monitoring team observers should identify: (1) the adequacy of sampling methods; (2) the adequacy of contamination control measures; (3) the adequacy of reporting and documentation measures; and (4) the effectiveness of the team in defining the plume condition and sample locations. Dose projection techniques 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. O ~ 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 posta.g 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. (f- 2453e l E -- -- . _ . . __ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 4.3 CORIROLLER.RD_mSEP3ILEVALUAll0N_CRIIERIA O 2149e
Rev. O Page 4.3-1 (3>
'- VERtiONI_YANKEElU. CLEAR POWERJIAIION EliERGENCY. RESPONSE PREPAREDNESS EXERCISE 1911 4.3 CONIRQLLER AND OBSERVER EVALUATION CRIIERIA As discussed in Sections 4.1 and 4.2, each Evaluator has been assigned specific areas of response to evaluate. This section has been developed to assist the Evaluators in recording and documenting their findings and observations. 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 f acility
/~'N Controller. Each Controller will then submit the attach.nents to the
(,,) Exercise Coordinator for documentation and record keeping. l l
Rev. O Page 4.3-A.1
,/-- 'd-ATTACIM MI_A Velmoni_Yankec_Huclear Power _ Station Emergency Reiponse Exercian/ Drill Evaluator's Observations-Chronological Los
__Ilme ObserYg11DnLCongnent (~~\ '% J Name: Area Evaluated: Date: (9 2149e 'uJ'
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Rev. O Page 4.3-A.2-AHACMiEHLA (Continued) T1me Obagrvation/Conunent
-Name: Area Evaluated: ,
Date: _ _ 2149e
-- . ~- _ _ ~ . .
Rev. O Page 4.3-B.1 f- s ATTACIRiENLB VermonL_ Yankee EmCI&eacY EXergige/ Drill Eyaluation Check ligt INSIRUCIl0BS 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 for improvement, should be included on Attachment C, the Emergency Exercise / Drill Evaluation Form or on a separate piece of paper. Rating Sylnbd Comenta_and_ Suggested Improvements 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. t l l I l
- Comments should also include strong positive strengths that were
! demonstrated by player actions and response. l L
' [s_ ') 2149e l
Rev. 0 Page 4.3-U.2 ATIACIMfliLB (Continued) Engt Ecclisn I. Control Room (Simulator and Actual) 4.3-3.3 II. Technical Support Center 4.3-B 5 III. Operations Support Center 4.3-B.8 IV. Emergency Operations Facility / Recovery Center 4.3-U.11 V. Site and Off-Site Monitoring 4.3-9.14 VI. Security 4.3-B.15 VII. News Media Center 4.3-D.16 O 2149e
i l Rev. 0 l Page 4.3-B.3 f'V-AITAC11 MENT B (Continued) I. CONTROL RQQM Rating QgamaniS A. Ass iden t AssE s smen t /Eme r cen cy_flarif f i c a t ion
- 1. Did the Control Room staf? demonstrate , Yes/No the ability to recognize emergency initiating coeditions 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
- 1. Did the Control Room staff demonstrate the Yes/No ability to notify the plant staff of an (g emergency through the use of alarms and the
( ). public address system?
- 2. Did the Control Room staff demonstrate the Yes/No ability to notify federal and state authorities of emergency classifications in accordance with established procedures?
- 3. Was information flow within the Control Room Yes/Fo and to other appropriate emergency response facilities timely, 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?
i l 2149e I~'}
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.J Rev. O Page 4.3-B.4
_,2~ d ATTACHMENT B (Continued)
- 1. CONTROL ROOT!
LaLing Coments C. Activation _andlesponse
- 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 ves good command and control taken at the Control Room?
CN U Controller / Observer Name: 2149e
Rev. O Page 4.3-B.5 ;
) ATTACHMENT B (Continued)
II. IECHNICAL SUPF_0RT CENTER Rating Coments A. &cident Assessment / Emergency Classifiention
- 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 staf f 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 Yes/No to initiate and coordinate corrective actions in an efficient and timely manner?
- 4. Did the TSC staff demonstrate the ability to Yes/No direct and coordinate the taking of V appropriate chemistry samples to analyze plant conditions?
- 5. Did the TSC staff demonstrate the ability to Yes/No participate with the Control Room and EOF /RC in emergency classification and EAL discussion.
B. Nolitication and Comunication
- 1. Was information flow within the TSC and to Yes/No other appropriate emergency response facilities timely, complete, and accurate?
2149e
i l Rev, O Page 4.3-B.6 O V ATTACHMENT B (Continued) II. IECIINICAL SUPPDELCDiIER Rating Commenta
- 2. Was adegaate 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 inf ormation concerning plant conditions Yes/No disseminated between the Centrol Room and TSC performed in a timely manner?
- 5. Were status boards utilized and maintained Yes/No tu display pertinent accident information at the TSC?
C. Antiration 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 follow them?
- 3. Were initial and continuous accountability Yes/No checks of TSC and CR personnel performed?
- 4. Did the TSC Coordinator establish and Yes/No coordinate access control into the Protected Area and Control Room?
() 2149e
Rev. O fage 4.3-B.7 ;
@ ATIACILMINI_b l (Continued)
- 11. IECMiiCALSUIt0RI_CENIIh IM11ng Coments I
- 5. Did the TSC Coordinator demonstrate the Yes/No )
ebility to maintain conmand 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 750 organization and initiation Yes/No nf activity efficient and well organized?
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l l l l l Controller / Observer Names . . _ _ . . _ . 2149e
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7 _ .. Rev. 0 , Page 4.3-B.8 ! b'.
\ ATIAtlDiENLE (Continued)
- li! -
UDNS_Rfl0RT CENTER Rating Coments A. Holillsation ant.ComunicAL1QD
- 1. Was information flow within the OSC and to .__ Yes/No other appropriate emergency response ,
f acilities tirnely, complete, and accurate?
- 2. Was adequate record keeping of events, actions. __. Yes/No and communications documented and logged by ,
the OSC staff?
- 3. Were adequate emergency consnunications systems Yes/No available in the OSC to transmit data and iniormation to other emergency response
. facilities?
- 4. Were status boards utilfred and maintained to _ Yes/No display pertinent accident information at the 0S07 B. Acti.vation nnd.Responso
- 1. Did the OSC staff demonstrate the ability to Yes/No activate and staff the OSC? 1
- 2. Did the OSC staff demonstrate the ability to Yes/No appropriately implement Emergency Plan Impirmenting Procedures and did they follow then.?
- 3. Were initial and continuous accountability Yes/No checks of OSC personnel performed?
, 2149e l
Rev. O Page 4.3-B.9 ; AITACIMEllLB (Continued) III. DEIEA".10HLSVIIORLCLNIER Rating Coments
- 4. Did the OSC Coordinator and OSC Coordinator's ._ Yes/No Assistant demonstrate the abillty 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 Letivity 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 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 chemistry samples as directed by the TSC7
- 10. Did the OSC staff demonstrate the ability Yes/No to initiate, brief, and dispatch On-Site Assistance Teams?
t l ( { 1 l
-.I - 2149e
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Rev. O Page 4.3-B.10 O ATIACl21RiLit (Continued) 111. OfERAT10NLSURFORLCf.NIEll
- 11. Were on-site assistance teams abic to trouble- __ Yes/No shoot and evaluate problems with plant equipment and systems?
- 12. Were their adequate administrative controls Yes/No and documentation taken to perfonn the necessary repairs of plant equipment and systems during an emergency situation?
O Controller / Observer Names 2149e
Rev. O Page 4.3-D.11 On V ATTACllMMI.lt (Continued) IV. MERGENCYRERATIONS..JACILIIYlRECOVtRLCGIER Rating Conuents A. No.tification_AnLComnunication
- 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 Yen /No available in the EOF /RC to transmit data and information to other emergency response facilitics?
- 3. Was adequate record keeping of events. Yes/No actions, and comniunications documented and logged by the EOF /RC stafff 4 Was information concerning plant conditions Yes/No disseminated between the TSC and EOF /RC performed in a timely manner?
- O
- 5. Were statun boards utilized and maintalv.d Yes/No to diaplay pertinent accident information at the EOF /RC7 B. AcilyAtion_anLResnonac
- 1. Did the EOF /RC staff demonstrate the ability . Yes/No to activate and staff the EOF /RCf
- 2. Did the EOF /RC staff demonstrate the ability Yes/No to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
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l Rev. O Page 4.3-B.17 b ATIACMENI_B (Continued)
\
IV. DiERCINCY_OfLMIl0NS_FACILITYlECOVERY CENIER Enitas Comments
- 3. Did the Corporate Security Force establish Yes/No access control into the EOF /RC?
- 4. Did the EOF Coordinator demonstrate the Yes/No ability to maintain command and control of EOF emergency response activities?
$. Did the EOF /RC keep other emergency response Yes/No facilities advised of 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. Did the Site Recovery Manager demonstrate the Yes/No 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 ability 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. RadiologicaLAnnessment
- 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-35137
[ V{ 2149e l
..._._.._....._.~__.__._._-____..__-.-_.__...m-. _ _- _ ___- - .
Rev. O Page 4.3-B.13 ATIAC11MENLE (Continued) IV. ' DIER0ENCLDIERAIIDHSJACIL11X/ REC 0VERLCENIER Rating Conuncats
- 3. Did the EOF staff demonstrate the ability to Yes/No effectively track and define the plume utilizing the. computerized dose assessment model (METPAC)?
D. Ero.tectivelclion_ Decision-Making
- 1. Did the Radiological Assistant's staff Yen /No demonstrate the ability to perform timely assessment of off-site radiological conditions to support the fot1oulation of protective action reconnendations? ,
- 2. Did the EOF Coordinator obtain and provide _
Yes/No the necessary information to the Site Recovery Manager concerning protective action reconnendations in accordance with O Procedure OP-3511.
- 3. Did the Site Recovery Manager demonstrate Yes/No the ability to make protective action reconnendations to of f-site authorities in accordance with Procedure OP-3511?
Controller / Observer Name: t 2149e L l -.- - - - - . . -. . - . - - - . . , ,- _ . _ ,
_ _ . _ - _ _ _ _ _ _ .=_ . - _ . . _ _ _ - _ . - . - - . - _ _ . . Rev. O Page 4.3-11.14 I V ATIACHMr.NT_Il (Continued) V. SlIE AND OFI-111EJ101UIORING Rating Coments A. Actintion._anLReAponse
- 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, fiold ruonitoring procedures, and what was reouired of them?
- 4. Were off-site monitoring teams able to Yes/No determine and communicate their location O in the fleid using appropriate maps and sample points (landmarks)?
- 5. Were off-site monitoring teams briefed on Yes/No plant conditions and changest g Controller / Observer Name l
2149e
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l Pev . O Page 4.3-It.15 l l s/ ATIACRil2il_3 (Continued) VI. SECURIII Rating Coments
)
A. Activation _and_ Response l
- 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?
Controller / Observer Name: 2149e i
Rev. O Page 4.3-B.16 O ATTAC11MENL1) (Continued) VII. NEWS _ MEDIA _CSTER Rating Connents A. Astivation and.. Response
- 1. Did the News Media staff demonstrate the _ Yes/No ability to activate and staff the News Media Center?
- 2. War, 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 cot.cerning the emergency to the public and the news media?
- 5. Did the News Media staff demonstrate the Yes/No ability to cooroinate news releases with the state's public information representatives?
- 6. Did the News Media staff demonstrate the Yes/No ability to provide briefings for and to interface with the public and news media?
Controller / Observer Name: 2149e
Rev. O Page 4.3-C.1 ATIACE RiT_C Emergency _Excrcine/ Drill Obsetyurin_Ivaluation_foin Observer's Name t _ _. Exercise / Drill Datet Exercise / Drill Title Observer's Location: Titoe Started ._ _ _ _ _ _ Time Ended: Observed I' layer func. tion Overall Performance and Observations: (include the proper and effective use of procedures, equipment and personnel): _ O Recognized Weaknesses and Deficiencies: Comments and Recommendations (Specific): ROIE:
.Use additional pages as required.
Signature: Titlet VYOPF-3505.02 OP-3505. Rev. 15 Page 1 of 1 2149e
Rev. O Page 4.3-C.2 AUACJMfJiLC 7 (Continued) f I l l I t Continued on Additional Pages Yes No Signatures Titius Dates , 2149e i lc i-l
VERMONT YA!P " r>Jt l'O'n'ER STATION IMERGENCY RESi, EDNESS EXERCISE 1991 5.0 f2ERCISE SCENARIQ s
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 5.1 INITIAL CONDITIONS O O O
i Rev. 0 O Page 5,1 1 (d VEMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 : 5.1 INITIAL CONDI RQE (This information will be provided to the players at the start of the exercise).
- 1. The reactor is now at approximately 100% power. The reactor has been operating steady state for the past fif teen inonths with no recent shutdowns.
?
- 2. Night Orders for the operations crew provides the following infortnation:
- a. The llPCI system failed surveillance testing due to flow controller failure putting the plant in a 7 day LCO. IIPCI has O been declared inoperable. In accordance with Technical Specifications, alternate testing is in process by 160.
- b. 160 is performing the functional test of the Automatic Depressurization Systers trip logic. This test ir required as a condition of tech, spec. for llPCI inoperability,
- c. Off gss 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 feel pin leakage.
- 3. All other power generating and safety system equipment is operable.
I l [
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i Rev. O Page 5.1 2
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed, oph (lower / upper) 4.0/5.0 Wind Direction, degrees (lower / upper) 180/185 . i Delta Temperature 'T (lower / upper) 1.0/1.$ Ambient Teinperature 'F 40.0
-Precipitation, inches 0.00
- 5. Re61 onal Meteorological Forecast Inforinction:
A low pressure system is located along the Atlar..;ic seaboard. liigh -- temperatures in the imiddle to upper $0's; low teinperatures in the salddle 40's. Winds from the south at 4 5 mph, swin6 1ng around to the southeast this af ternoon and diininishing in intensity. Winds will continue to shif t, conning around to the north and increasing in intensity to 5+7 aph. ,
)
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l i Rev. O Page 5.1 3 . Tabic 5.1 1
\
" 1Di tial Plant and Reactor System Values , 1 Reactor Vessel Coolant Level 158 Inches Reactor Pressure 1007 psig Reactor Coolant Temperature 528 'r Reactor Power . APRM (average) 100 t i Core Plate D/P 18 paid Total Core Flow 47 x 10' lbm/hr Main Ste n Line Flow Total 6.4 x 10' lbm/hr Main Steam Line Radiation 170 mR/hr Condenser llotwell Level 55 g Condenser Vacuum 1.8 in lig(Abs) Condensate Storage Tank Level $1 % Recire Drive Flov 30 Kgpa/ loop Feedwater Flow 6.3 x 10' lbm/hr O- Reactor Building D/P 1.62 in lig0 Drywell Pressure 17 psia Drywell Temperature 106 'T Torus Vater Level 0.56 ft Torus Temperature 72 'F
^
Drywell/ Torus 0 Concentration 3 2.58 % liigh 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 Cas I/II 150/200 cpm iligh Range Noble Cas Monitor .1 mR/hr O .
Rev.o rose 5.1 4 VERHONT YANKEE DAILY STATUS REPORT
\ THIS IS A DRILL DATE: nov s 1891 MANT OPERATING STATlfS VALUE DATE TIME
- 1. Core thessel remer ( Wt ) l (t) 1593 } 1001 0700
- 3. Gross W e (We ) 536 0700
- 3. Met We (We ) S11 0700
- 4. Usoes Wh f or ps evleus day (Wh) 12523 S. Cote Flow (M11/ tt ) l (t) 47 4 97.91 0700 Pf, ACTOR,, COO 1 ANT ShTEM I6. Conductivity (unholen) 0.065 11/S/91 WOO
- 7. Unideritified Leakage 8 midnigtht ps evious day (gys.# 0.00
- 8. Tot al 1.eak age 8 midnight previuus day ( p pm) 2 45 9, Otoss Activity ( e ps/ml) 150448 11/9/91 0900
- 10. todine*131 Dose Egalveient (uCt/ml) 4.$0f 03 11/5/b1 0900 STACK RELEASES l11. Particulate (et/ period) 4.06t-03 11/4/91 1430 (uCl/see) *100 11/6/91 0115 l122 Averase (uct/see) MONE 11/6/91 0115 l13. Pe ak l14. Discharts Averese Gansna Energy (Mov) 1.12 11/6/91 011$
S. Dose kate to Critical Organe (e.s eat y ee s ) a. 4 2 11/4/91 1630
- 6. lodine-131 (uCi/see) 3.30E 0S 11/4/91 1430 OFF CAS AMALYSIS
$7. EJAF Ote. Release Rate Meast.s ed/ Lattmated (uCl/see) S0000 11/6/91 0115
- 18. $JAt Discharge- Slope of Misture 0.253 11/6/91 011S
- 19. Condenser Air Leak age (cfa) 19.6 11/6/91 0115 IJQUID RELEASES & RIVER TDiPERATURE
- 10. Liquid hetease (Gol) hA
- 21. Liquid Reneese (Gross t Bete. Gowna) (uCi/ml) MA
- 22. Liquid kolease (Trit tum) ( uC1/s.1 ) MA
- 13. Liquid Rolesse (Dissolved Noble Gast (uC1/ml) MA
- 24. River Nn. f 3 Illshest Temp. for previous day (oF) ,S S 2115 BUPJRIP
- 15. Core Avs. Burnup for previous day (WDIST) 10945.75
- 26. Core Cycle Burtiup for previous der (HC/37) t,3 2 5. 4 5 l
REVIEWER: TI!ID IS A DRILL l
l t P
@ VERMONT YANKEE NUCLEAR POVER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 ;
i i t 6 5,2 NARRATIVE Sl%%RY f i i 1 4
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Rev. O Page 5.2 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 5.2 N_ARRATIVE SUK%RY The scenario begins at 0700 with the simulator reactor running at approximately 1006 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 liigh Pressure Coolant Injection (HPCI) system has failed surveillance testing due to flow controller failure. As a result, tha plant han entered into a 7 day Limiting Condition for Operation (LCO) and HPCI has been declared inoperable. Alternate testing requir=d 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 Depressurirstion 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 levels 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 14 per 5 minutes due to suspected fuel pin leakage. All other power generating and safety system equipment is operable. At 0715, 160 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 an 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.). ("% L)
Rev. O Page 5.2 2 G
- The Shift Sige rvist, 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 panalarms 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 Emer6ency Operations Facility / Recovery Center (EOF /RC) will be activated and staffed, se/ 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 vill 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 af ter DC 3 is returned to service, the SCR crew will notice decreasing vacuum in the main condenser. At 1015, a low Main Condenser vacuum alarm is received. The turbine trips on low condenser vacuwn initiating an automatic reactor SCRAM. When the reactor SCRMI signal V occurs, the control rods fail to insert causing the reactor to remain
--' - - - - . > - . , , . ..,m +g y- - - , y m. -- . ---.r-m ,
Rev. 0
/ Page 5.2 3 v ;
critical and an Anticipated Transient Without Scram (ATVS) condition exists. Reactor power will remain above 2 percent. The Main Steam Isolation Valves (MSIVs) remain open and pressure is being regulated l through the turbine bypass valves to the Main Condenser. The operators will attempt to individually drive control rods into the I reactor core. Operators will implement actions to reduce reactor power and stabilize plant conditions. i By 1020, Main Condenser vacuum continues to decrease causing the closure of the MSIVs on Group 1 isolation. The Main Condenser is no longer 11able as a heat sink. Control rods are still not fully inserted and reactor pouer remains above 2 percent. The "B" inboard MSIV fails to isolate as indicated on the SCR board (open indication). p A SITE AREA EMERGENCY should be declared (approximately 1030) based upon U 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
-Mode. At approximately 1045, the circuit breaker for the *C" RRR pump fails. This causes the motor to trip and the "A" RHR 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 Standby Liquid Control (SLC) to bring the reactor.suberitical. Initiation of SLC will cause an isolation of the Reactor Vater Cleanup (RVCU) 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 RWCU system may
-yp. -gp..r--> -
.+>-y 4 w *- .y,fn
i Rev. O Page 5.2 4 occur earlier due to the lowering of reactor water level. Rk'CU V 12 15 will fail to 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 SLC injection. Concurrently, operators will continue to implement actions to insert control rods. Flant personnel should be dispatched to manually close the control Rod Drive (CRD) charging water header isolation valve (CRD 56), k' hen CRD 56 is chut, CRD flow is regained and the rods can be individually inserted using the RMCS. L'hile 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 O 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 ' aserted into the reactor core, operators will commence a reactor cooldown. Plant conditions will stabilize and remain f ai' y constant for the next hour. Plant personnel will be investigating why <1e "B" inboard MS1V remains partially open. At 1200, a small leak occurs from a Reactor Recirculation Line into the drywull. 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 (approximately 20,000 R/hr). O
Rev. O Page 5.2-5 A GENERAL EMERGENCY should be declared (approximately 1215) based upon AP 3125, " Fuel Damage," (loss of two of three fission product barriers with the potential loss of third). At 1255, the Simuistor 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 1.ine B. By 1300, a rapid depress.urization 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 signi ficantly . Release of radioactivity from the plant vent stack (PVS) begins. By 1315, PVS high range monitor is indicating a major release of radioactivity to the envirotunent. By 1400, the Simulator control Room indicatio is 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 source 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 Ces Treatment System. At 1530, the exercise vill be terminated. O
O VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 5.3 1C.ENAR10 TIME LINE O I O
Rev. O Page 5. 3 1 O VERMONT YANKEE NUCLf2R POWER STATION EMERCENCY RESPONSE VREPAREDNESS EXERCISE 1991 5.3 SCENARIO TIME LINE CthCK SCENARIO T1HE TIME DESCRIPTION 0700 0:00 . <... Initial conditions established in the Simulator Control P. nom. 0715 0:15 . <.. 160 reports functional test of ADS is unsatisfactory. 0730 0:30 . < .. UNUSUAL' EVENT.'(AP,312$,114SS;0Pf SYSTEMS!OR EQUf fMENT) Plant
. shutdown required in accordence with 140 in Tech Specs.
0745 0:45 . 0800 1:00 . 1815 1:15 <... Electrical Bus DC 3 is lost. Panalarms on the simulator control s-
/ . Room Board have become inoperable.
0830 1:30 <.. A!,ERT;(AP 3125J1hSS OF SYSTEMS 0R EQUIPMENT) . Loss of Control Room
. Alarm Panels.
0845 1:45 . <... Plant personnel dispatched to investigate problem with Electrical
. Bus DC.3.
0900 2:00 . 0915 7:15 . 1 ? 0930 2:30 . 1 l 0945 2:45 <. .. Electrical Bus DC.3 returned to service. Panalarms on Simulator
. Control Room Board cperable.
1000 3:00 . O
Rev. O Page 5.3 2 5.3 SCENARIO TIME L1EE (continued) CIDCK SCENARIO TIME TIME DESCRIPTION 1015 3:15 <.. 1.ov 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 Group 1 isolation. Control rods still not inserted and
. Reactor Power above 24. Inboard MSIV on Main Steam Line B indicates open.
1030 3:30 . <. . . SITE; ARP.A' EMERGENCY ;(APl 3125 11AS7 0F SYSTEMS ~ OL EQUIPMENT) .
. Failure of Reactor Protection fjetem (RPS) to initiate and
- accomplish a required SCP,AM with the Main Candenser unavailable.
1045 3:45 <... Torus temperature increasing, "C" RilR Pump trips. 1100 4:00 <... Operators continue to implement actions to reduce reactor power and
- stabilize plant conditions. RWCU V1215 vill not close on isolation
. signal.
1115 4:15 . Q130 4:30 . 1145 4:45 . 1200 5:00 . <... Dryvell pressure increasing due to leakage from a recire line into
. the dryvell. Containment high range monitor readings increasing
. significantly.
1215 5:15 . < .. GENERAL EMER0ENCYf(AP 3125,iFUEL DAMAGE) . Loss of 2 of 3 fission
. product barriers with the potential loss of third.
1230 5:30 . 1243 5:45 . 1255 5:55 - <-.- Steam line break occurs between the inboard and outboard MSIV on Main Steam Line B outside primary containment in the steam tunnel. O
I Rev. O
'N Page 5.3-3 I
L -- ) 5.3 ECllBRIO TItiLj.llit (cont inued) CIDCK SCENARIC TIME TIME DESCRIPTION 1300 6:00 . < .. Rapid depressurization of the reactor occurs. Area Radiation
. Monitors in the Reactor Butiding increasing significantly.
RE1JJ.SE OF RADICACTIVITY .TRONL Yt!E PIANT DTACK BEGINS. 1315 6:15 . <... Plant Vent Stack high range monitor indicating a major release of
. radioactivity to the environreent . Significant 1cvels of
- radioactive material are present in the Reactor Building and vill 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 he.s closed. IJAKAGE INTO THE REACTOR BUILDING'IC ID01ATED.
1415 7:15 .
~
( ) u-4430 7:30 . 1445 7:45 . 1500 8:00 . 1515 8: 15 . < -- Plant Vent Stack high range monitor decreasing. SOUBCE OF RELEASE FROM Tite F1 ANT VENT STACI HAS BEEN CONTROL 1.ED. Plant conditions
- stabilizing.
1530 8:30 - <--- EXERCISE IS TERMINATED. 7-i J
(^ - _p) VERMONT YANKEE NUCLEAR POWER STATION EMERGEN0Y RESPONSE PREPAREDNE!,S EYIRCISE 1991 l lt . 1 I j i I 5.4 DETAILED SEOUEFCE OF EVENTS g r
I Rav. 1 IWgs 5.4 1 i l VERMONT YANKEE NUCLEAR POWER STATION
/~'s -E v l- EMERGENCY RESPONSE PREPAREDNESS EXERCISE )
1991 5.4 DETAlt.En SEQUINCE OF EVENTS
-Clock Scenario Message Time Time Event / Action Information Prior to EXPECTED CONTROL A0"n 'c0 ACTIONS WILL BE 0700 00:00 IMPLEMENTED BY AN 4 E OPERATIONS CREW (INCLUD111G SUFFICIENT NUMBER OF PRESTACED INDIVIDUALS FROM THE VERMONT *lANKEE EMERCENCY ORCANIZATION) IDCATED TN THE SIMULATOR COMPLEX IN THE CORPOPATE TRAINING CENTER.
OPERATIONAL CONTROL ROOM DATA WILL BE PROVIDED BY THE SIMULATOR INSTRUMENTATION RESPONSES. IN CASES VHERE SPECIFIC (N INFORMATION NOT HONITORED BY THE SIMUIATOR IS REQUIRED, IT WILL BE ISSUED BY CONTROLLERS /0BSERVERS ON MESSACE CARDS. IN ThE EVENT THAT A SIMULATOR MALFUNCTION OCCURS, THE EXERCISE WILL BE CONDUCTED USINO INFORMATION DEVELOPED FROM SECTION 8.0 AND SECTION 9.0. The Simulator CR Controller issues initial SCR/CR M-1 conditions to tile simulator CR players. SCR C-1 Guidelines for use of Gaitronics and the plant evacuation t.larm are provided to players. I i i o
'w) m
Rov, 1 Pcge 5,4-2 Clock Scenario Message Time. Time Event / Action IDf2Tmation (~')Y Prior to Initiating messages are also provided to all ERF M 1 0700 00:00 emergency centers and facility staffs upon TSC-N 1 (Cont'd) subsequant activations. Operational and TSC-M 2 radiological data vill be available to the ST-H 1 TSC via TSC communicators who normally ST M-2 respond to the CR prestaged in the s imuls, tor , Security will be provided a list of Evaluators and nonparticipants who will not have to be accounted for during the exercise. 0700 00:00 Simulator is put into operation. Reactor is at 100% power. The reactor has begin operating steady state for the past 15 months with no recent shutdowns. O
! j Night orders have instructed the Operations crew that HPCI failed surveillance testing and is inoperable. The plant is in a 7-day 140 in accordance with Technical Specifications. I&C is in the process of performing a functional test of the Automatic Depressurization System (ADS) trip logic,_The off-gas system radiation levels A
are elevated as a result of suspected fuel pin leakage, Reactor Engineering -staff has determined that power changes should not exceed 1% per five minutes in order to minimize the fuel pin leakage. All other power generating and safety system equipment is operable. I
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Rev. 1 Page 5.,4 3 Clock Scenario Message Tiine . Time Event / Action 1DfRIER11RD 0715 00:15 I&C 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 will need to be replaced (refer to Miniscenario 7.2.1). Approx. Approx. The Shift 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/ PED should initiate Procedure OP 3500, UNUSUAL EVENT and refer to Appendix I, the SS/ PED checklist. O 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, r.nd simultaneously performed by a controller directed member of the operating shift crew in the actual Control Room. 9
Rev. 1 Page 5.4 4 Clock Scenario Message Time Time Event / Action Informat tors Approx. 00:30 The SS/ PED should notify Vermont, New 0730 11ampshire , 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 Shift Supervisor should notify Yankee Nuclear Services Division (YNSD) Security and activate the YNSD Personnel Group Paging System. The Security Shift Supervisor should also SEC-C 1 notify New England liydro 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 not(fication 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. 1
Rev. 1 Page 5.4 5 Clock Scenario Message Time Time Event / Action Information 0730 00:30 The TSC Coordinator should assume the (Cont'd) overall supervision and coordination of the on site emergency response activities. This will include escalating the en,ergecy classification as conditions warrant. Activation of the Technical Support Center (TSC) is optional at the UNUSUAL EVENT. 0745 00:45 IF AN UNUSUAL EVENT HAS NOT BEEN DECLARED BY SCR-C-3 THE SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS TIME. 16C initiate repairs to the failed relay in 7.2.1-H 2 order to return the ADS to service. 0815 01:15 Simulator Operator inserts a loss of electrical bus DC-3. This results in a loss of all control board panalarms, various electrical distribution and turbine control indications. Approx. 01:30 Vhen the SS/ PED realize che 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." O
Rsv. 1 Pegs 5.4 6 Clock Scenario Message Time Event /ActiQD Informg1L2D l'~'s Time _ 0830 01:30 The SS/ PED or TSC Coordinator should declare (Cont'd) an ALERT based upon the following EAL: AP 3125, " LOSS OF SYSTEHS OR EQUIPMENT - Loss of Control Room alarm panels". The SS/ PED directs the operations staff to initiate Procedure OP 3501, " ALERT." An ALERT announcesent 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 Housc Information Center and wait for further instructions.
/ At this time, the Technical Support Center l
u (xl (TSC), Operations Support Center (OSC), and the Emergency Operations Facility / Recovery Center (EOF /RC) should be activated and staffed, l l 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 metnod for the ALERT classification. d
Rsv. 1 Page 5.4 7 Clock Scenario Message c Event / Action ( The Time 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 Shift 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 plat.t conditions. 0835 01:35 The Security Shift Supervisor should ensure that an accountability of personnel has been initiated in accordance with procedure OP 3524, " Emergency Actions to Ensure Accountability ar.d Security Response." The TSC Coordinator should respond, activate, and staff the TSC in accordance with Appendix III of OP 3501, " ALERT." O
Rev. 1 Page 5.4 8 Message I Clock Scenario Time Time Event /Act!QD )fformation 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
- 9. Other staff personnel to fulfill the functions of the TSC (i.e., Status Board Keepers, Communicators, Switchboard Operators, etc.).
The Emergency Operations Facility (EOF) Coordinator should activate and staff the EOF /RC in accordance with Appendix IV of OP-3501, " ALERT." O
Rev. 1 l Page 5.4 9 Clock Scenario Message 1122 Time Event / Action Information 0835 01:30 The emergency response staff that reports to (Cont'd) the EOF /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 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." O
Rev. 1 Page 5.4-10 Clock Scenario Message Ilgt _ Time Event / Action Information 0835 01:35 The Plant staff that reports to the OSC (Con t' 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 ;ite Recovery Manager (SRM) and staff should report to the EOF /RC and implement the procedural steps listed in Appendix VIII o f OP 3 501, " ALERT. " 0840 01:40 Radiation Protection Technicians from the OSC may be dispatched to perform dose rate radiation surveys, air sampling, and contamination surveys of the plant. 0845 01:45 IF AN ALERT HAS NOT BEEN DECUJtED BY THE SCR-C-4 SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS TIME. Control Room operators will 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). O
l 1 Rav. - l ' l Pags'5.4 ell- -) Clock- Scenario Message h ,,' Time Event / Action Information 0915 02:15 The repair team-repocts that the immediate 7.2.2 N 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. 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 causir.', the reactor to remain critical. An' Anticipated Transient "Without Scram (ATWS) condition exits.. Reactor power remains above 2%. 1020 03:20~ Condenser vacuum continues to decrease due to air in-leakage problems. Loss _of vacuum causes the closure of the Main " team j Isolation Valves (MSIVs) on Containment
-Croup 1 isolation. The inboard MSIV on Main Steam Line "B" remains in tha open position. ,
Rev. 1 Page 5.4-12 Clock Scenario Message Time Time Event / Action Information 1020 03:20 The Main Condenser is no longer available as (Cont'd) a heat sink. Reactor power is still above 24. Approx. 03:20 The SS/ PED should immediately inforta the TSC 1020 Coordinator and SRM of the AWS condition and that a Group 1 isolation has occurred. The SRM, TSC Coordinator and SS/ PED should evaluate plant conditions against Procedure AP 3125 " Emergency Plan Classification and Action Level Scheme". The SRM w th consultation from the TSC Coordinator and SS/ PED should recognize the need to escalate to a Site Area Emergency. O Approx. 03:30 'Iae SRM should declare a SITE AREA EMERGENCY 1030 based upon the following EAL: 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, 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 SITE AREA EMERGENCY. The SS/ PED will also be directed to make the appropriate plant announcement concerning the escalation to the SITE AREA EMERCENCY. i
Rev. 1 l 1 Page 5.4 13 I. Scenario Message Clock Time. Time _ Event / Action Infortan tion Approx. 03:30 Upgraded notifications should also be made 1030 to YNSD and the NRC. (Cont'd) Upon MSIV isolation, operators will continue 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 t rus temperature and level. 1045 03:45 IF A SITE AREA EMERGENCY HAS NOT BEEN SRM C-1 DECIARED BY THE SRM, HE WILL BE DIRECTED TC DO SO AT THIS TIME. The SCR personnel 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 H-1 rods into the core until the Control Rod P; n (CRD) charging water header isolation
. (CSS 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)
O
[- Rsv. 1 q Pegs 5.4 14 j 1 Clock. Scenario Message l Time Time Event /Ac t ion Information i 1045 03:45 The "C" RMR 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-N 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 level. This will be done in accordance with OE 3102, Alternato Level Control. When SLC is initiated from the control 7.2.5 M-1 bQ 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 RUCU 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 faf.hre . (Refer to Miniscenario 7.2.6.)
'[v
Rsv. 1 Pago 5.4 15 Clock Scenario Message eq Time _. Time Event / Action Jnf,gymation d 1050 03:50 At this time, it is postulated that fuel (Cont'd) inte6rity is damaged due to the thermal and hydraulic shock imposed by the cycling of the SRVs to contro) pressure. This results in a significant increase of fission products in the reactor coolant system. 1055 03:55 The ESC should be providing technical and ESC N-1 engineering support to Vermont Yankee staff. EOF M 1 The ESC meteorologist should provide a specific weather forecast for the Vermont Yankee site. 1145 04:45 The ESC has reviewed the latest NWS forecast ESC M 2 and has updated meteorological information for the site. O An updated weather forecast is available EOF-M-2 from the NWS. ST M-3 1200 05:00 Dryvell pressure continues to increase due to increasing drywell 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. l 1205 05:05 Containment High Range Monitors are reading approximately 20,000 R/tr. The SRM, TSC Coordinator, and SS/ PED should evaluate plant conditions against Procedure l O
\
AP 3125, " Emergency Plan Classification and
/ Action Level Scheme."
Rov. 1 Pago 5,4 16 Clock Scenario Message fy Time Tine Event / Action Information v 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 CENERAL EMERGENCY based upon the followins EAL: AP 3125,
" FUEL DAMAGE - Loss of 2 of 3 fission product barriers with potential loss of third."
l The SRM should inform the representatives of ) Vermont, New Hampshire, and Massachusetts l located at the EOF /RC, and contact each T state's EOCs using the NAS to inform them of (d the escalation to the GENERAL EMERGENCY. l The SS/ PED will also be directed to make the appropriate plant announcement concerning the escalation to the GENERAL EMERGENCY. Upgraded notifications of the CENERAL l EMERGENCY status should be made to YNSD and the NRC. l 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 DECIARED BY THE SRM, HE WILL BE DIRECTED TO DO SO AT SRM-C-2 THIS TIME. l
Rov. 1 Page 5.4 17 Clock Scenario Message [~'T Time Time Event / Action Information N] A casualty will be inserted by Simulator 1255 05:55 Operator that causes a large steam line break cutside the primary containment in the steam tunnel. The break is between the inboard and outboard MSIV os h;L "B". Steam tunnel temperature is increasing significantly. 1300 06:00 A rapid depressurization of the reactor occurs as a reruit 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. I 's 1315 06:15 PVS high range monitor is indicating 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 off-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.
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Rev. 1 Page 5.4 18 Clock Scenario Message ligg_ Time Event / Action Informati2D 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 RUCU V12 15 and MSIV "B". 1400 07:00 SCR board indicates that the inboard MSIV on MSL *B" has closed, Leakage past this MSIV into the Reactor Building has stopped, 1515 08:15 Control Room indicatio>s show that plant conditions are stabilizing and the PVS monitors cre decreasing. The source of the fission product release into the steam () tunnel has been isolated. The release of radioactivity to the environment will continue to decrease over time based upon the volume exchange rate of the Reactor Building through Standby Cas Treatment ~ System. 1530 08:30 Exercise is terminated. A U
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VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 6.0 EXERCISE MESSACES O l-l i i lt l l l.
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Rev. 0 VERMONT YANKEE IWCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO : SCR-C-1 TO: Shift Suoervisor CIDCK 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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Communications systems that are available in the Control Room have been duplicated in the Simulator Control Room (SCR) EXCEPT for GAITRONICS and the PIANT EVACUATION ALARM. Please use the GAITRONICS/P! ANT EVACUATION AIARM in the SCR to complete the required PA announcements. An Exercise controller will then direct a member of the shif t operations crew at the plant to repeat the announcements from the Main Control Room.
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THIS IS A DRILL O l l
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Rev. O Page 6.1-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO COMMANDJd2D FROM: Shift CR Controller COMMAND NO.: SCR-C-2 TO: Shift Suoervisor ClhCK TIME: 0730 IDCATION: Simulator Control Room SCENARIO TIMF: 00:30
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THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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Early in-station actions will be simulated and information requested at this time will be provided by controllers. O
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THIS IS A DRILL
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Rev. O Page 6.1-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ( 1991 SCENARIO COMMAND CARD FROM: Security Controller COMMAND NO.: 1EC-C-1 TO: Security Supervisor CIDCK TIME: 0730 or when needed LOCATION: Security Gatehouse SCENARIO TIME: 00:30 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. FOR EXERCISE FURPOSES, communications with New England Hydro Power Station in Vernon will be simulated. J THIS IS A DRILL
Rev. O Page 6.1 4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO COMMAND CARD FROM: Sirnulator CR Controller COMMAND NO.: SCR-C-3 TO: Shift Sunervisor CLOCK TIME: 0745 IDCATION: Sitnulator Control Room SCENARIO TIME: 00:45 Tills IS A DRILL DO NOT initiate any actions affecting normal plant operations. DECLARE AN UNUSUAL EVENT BASED UPON AP 3125, " LOSS OF SYSTEMS OR EQUIPMENT - Plant shutdown required in accordance with Technical Specifications". TilIS IS A DRILL
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Rev, O Page 6.1 5 VERMONT YANKEE NUCLEAR POWER STATION ~
. EMERGENCY RESPONSE PREPARE h s$ EXERCISE
' ~ 1.991 SCENARIO COMMAND CARD
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FROM: Simulator CR Controller COMMAND NO,: SCR-C-4 TO: .$hift Suoervisor/ PED C1hCK TIME: 9330 14 CATION: Simulator control Room- SCENARIO TIME: 01:30 THIS IS A DRILL - DO NOT initiate any actions affecting normal plant operations.
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DECLARE AN ALEBI BASED UPON AP 3125, "1 DSS OF SYSTEMS OR EQUIPMENT Loss of Control Room Panalarms",
.a THIS IS A DRILL L.. , . _ _ _ . . , . ~ . . _ , . - , . _ . _ _ . . , _ . , _ . . . - .,u._,.- - _ , ;- ._
Rev. O Page 6,1 6 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAIL".DNESS EXERCISE 1991 L SCENARIO COM RND CARD FROM: SRM Controller COMMAND NO,: SRM-C-1 TO: Site Recovery Manager CIDC TIME: 1045 LOCATION: EOF /RC SCENARIO TIME: 03:45
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THIS IS A DRILL RQ EQI initiate any actions affecting normal plant operations. DECIARE A SITE APIA 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". O THIS IS A DRILL {
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Rev. 0 . Page 6,1-7 _ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1991 SCEFARIO COMMAND CAPS FROM: SRM' Controller COMMAND NO.: SRM C-2
.: TO: Site-Recovery Manarer C14CK TIME: 1230 IDCATION: EOF /RC SCENARIO TIME: 05:30 -
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. DECLARE A SENERAL EMERGENCY BASED UPON AP 3125, " FUEL DAMAGE - Loss of 2 of 3 fission product barriers with the potential loss of the third". I
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O VERMONT YANKEE NUC11AR PO'JER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 6.2 ESSAGE CARDS O 4 4
Rsv. 1 Pcgs 6.2 1 VERMONT YANKEE n'UCLEAR POVER STATION EMERGENUY R*UPONSE rR'PAREDNES3 EXERCISE
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1 SCENARIO 1:ESSACE CARD FROM: C2ntro11er MESSAGE NO.: SCR/CR M 1 To: Shift sutie rvi s or/DC0 CIDCK TIME: Start of Drill IDCATION: CR/Sirn CR SCENARIO TIME: Prior to 00:00
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TilIS IS A DRILL DQJ_GtI initiate any actions affecting normal plant operations.
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For initial conditions, see attached pages.
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y - _ Rev. 1 Pao 1 of VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE SCENARIO MESSAGE CARD INFf1AL COND.1T10NS
- 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.
- 2. Hight Orders for the operations crew provides the following information ,
- a. The llPCI system failed surveillance testing due to flow 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 16C.
- b. 16C is performing the functional test of the Automatic Depressuriration System trip logi:. This test is required as 3 condition of tech. spec. for llPCI inoperability.
- c. Off gss system radiation levels have been elevated throughout the operating cycle indicative of minor fuel pin leakage.
- d. Reactor Engineering has instructed that power changes t. hall be limited to less than 14 per five minutes due to the suspected fuel pin leakage.
- 3. All other power generating and safety system equipo:ent is operable.
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THIS IS A DRILL
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t Rev. 1 Page 2 of VDt0NT YANKEE 1RICLEAR POWER STATION EMERGD1CY RESPONSE PREPAREDNESS EXERCISE 1991 EElmg10 MESSAGE CARD
- 4. The following on site meteorological conditions exist at 0700:
Wind 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 Torecast Information:
A low pressure system is located air ,g the Atlantic seaboard. High temperatures in the middle to upper 50's; low temperaturos in the middle 40's. Winds f rom 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. 1 THIS IS A DRILL
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Rev. 1 Page 3 of ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD 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 4 Core Plate D/P 18 psfs Total Core Flow 47 x 10' lbm/hr Main Steam Line Flow - Total 6.4 x 10' lbm/hr Main Steam Line Radiation 170 inR/hr condenser llotwell Level 55 4 Condenser Vacuum 1.8 in, lig( Abs) Condensate Storage Tank Level 51 4 Recirc Drive Flow 30 Kgpin/ loop Feedwater Flow 6.3 x 10' lbm/hr Reactor Building D/P 1.62 in 1I 20 Drywell Pressure 17 psia Drywell Temperature 106 'T
\ Torus Water Level 0.56 ft Torus Temperature 72 'F Dryvell/ Torus 0 Concentration 3 2.58 %
liigh Range Containment Monitors 4 R/hr containment Cas/ Particulate 500/25000 cptn Reactor Building Vent Monitors Cas/Part 190/1530 cpm Reactor Building Vent Exhaust N/S 2.0/2.0 mR/hr Steam Jat Air Ejector (ARM) 250 mR/hr SJAE Discharge Rate 50,000 pCi/sec Stack Gas I/II 150/200 epin High Range Noble Gas Monitor .1 mR/hr
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Rev. 1 tage 4 or 4 VERMONT YANKEE DAILY STATUS IJ. PORT THIS IS A DRILL DATE: mov e 1991 t PLANT OPERATING STATUS VALUE DATE TIMT.
- 1. Core Thermal Power (
- t) l (t) 1593 1 1001 0700 Grose IWe (Plde ) S* 6 0700 2.
Not We (tMe) 511 0700 3.
- 4. Oross Wh for previous day (tWh) 12523 (M1b/ht) l (1) of l 97.9 0700 S. Core Flow
- REACTOR COO 1RIT SYSTEM
- 6. Conductivity tumho/cm) 0.085 11/5/91 0000 P. Unidentified Lohkage 0 midnight previous day ( grah) 0.00 __
- t. Total Lothage O taidnight previous day ( g tn ) 2.45 *
- 9. Grosa Activity ( c pm/mt ) 150448 11/5/91 0900
- 10. todine*131 Dese Equivalent (uct/ml) 4.SCE-03 11/5/01 0900 STACK RELF.ASES (ti/ period) 4.08E-03 11/4/91 1430 l11. Particulate l12. Average tuC1/sec) e100 11/6/01 0115 tuC1/sec) NDHE 11/6/91 011$
l13. Pe ak (Mov) 1 12 11/6/91 0115 _ l14. Discharge Averego Gamma Energy Dese Rate to Critical Organs (mrom/ year) 4 42 11/4/91 1630 S. (uC1/sec) 3.~0E 1 05 11f4/91 1430 ,
- 6. todire 131 OFF-CAS ANA1.YSIS
~
SJAE Dis. Release Ra'.a Measured / Estimated (uct/see) 30000 11/6/91 011S 17.
- 18. SJAE Discharge Slope of Histure -0.253 1./6/91 0115
- 19. Ccmdenser Air Leakage (cfm) 19.6 11/6/91 0115 LIQUID RELEASES 6 RIVER TEMPERATURE 2{ L'. quid Release (Gal) NA
- 21. Liquid kalease (Grose Bete. Dama) (uCl/ml) NA
- 22. Liquid Release (Tritium) (uC1/ml) NA
- 23. Liquid Release (Dissolved Noble Oes) (uC1/ml) NA River Hon #3 Bighest Temp. for previous day (oT) SS 2115 24.
BURNUP-I. *S. Core Avs. Burt.up for previous day ( WD/57) It94S.75
- 26. Core Cycle Burnup for previous day (WD/ ST ) 6325.45 l
l l REVIEWER: THIS IS A DRILL l i l i l- - - - - _ _ _ _ _ ._ ._. .__ . . _ _ _ _, _ _ _ __
,o Rev. 1 Page 6.2 6
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 ECENARIO MESSAGE CARD FROP: Facility Controller MESSAGE NO.: ERF M 1 TO: Facility Coordinator CLOCK TIME: Etart of Drill or LOCATION: Various ERFc SCENARIO TIME: Engility Activation THIS IS A DR7LL DO NOT initiate any actions affecting normal plant operations. For initial conditions, see attached pages.
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s THIS IS A DRILL
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Rev. 1 Page 1 of 2 VERMONT YANKEE NUCLEAR POWER STATION F.NERGENCY RESPONSE PREPARE 0 NESS EXERCISE 1991 SCENARIO MESSACE CARD VERMONT YANKEE DAILY OPERATIONS REPORT NOVEMBER 6, 1991 ;
................................................................. I PLANT STATUst 100% POWER GEN GROSS 510 MWE 1 OFFGAS 50,000 uCI/sec ,
I PLANT OPERATION SUNNARY & SIGNIFIC! ANT EVENTS: i
*THE PLANT HAS DEEN OPERATING FOR 15 MONTHS WITH NO RECENT SHUTDOWNS. CONTINUED FULL POWER OPS. HPCI SYSTEM FAILED !
SURVEILLANCE TESTING DUE TO FI4W CONTROLLER FAILURE. PLANT IS IN A 7-DAY LCO CONDITION. OFF-GAS RAD LEVELS ELEVATED. SOME MINOR FUEL PIN LEAKAGE. SIGNIFICANT NEW NRs
# DESCRIPTION DEPT PRIORITY .yd NONE TECN 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 /CONNENTS ON MAJOR WORK IN PROGRESS: L
- I&C PERFORMING FUNCTIONAL TEST OF THE ADS TRIP LOGIC FOR l 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.
PRoss/ NOTIFICATIONS: NONE L ....... . . . . . .... LONG-TERN PROBLEN8 SOLVED NONE ' i l l THIS IS A DRILL j ****************************************************************************** 1 i
- , . . . - , . , , ,. , ~, _
,. _m.--.. - , . . ~ _ - . . . .. , _ - - ,. -
Rev. 1 rese a of a VERMONT YANKEE DAILY STATUS REPORT THIS IS A DRILL DATE: an a tool PLANT OPERATING STATUS VALUE DATE TIME _.
- 1. Core Thessal Power (PMt) { (1) 1593 ( 1001 0700
- 2. Cross We (Wo) 536 0700
- 3. Nel We (We) $11 0700
- 4. Oross M4h for tirevious sisy (Wh) 12S23 S. Core Flow (M1b/ht) l (1) 47 i 97.9 0700 REACTOR COOLANT SYSTIM
- 0. Conductivity (umho/cm) 0.095 11/S/91 Drno 1 Unidentified Leakage 8 midnight previous day (spm) 0.00
- 6. Totti Leakage 0 aldnight yrevious day ( s ps) 2.45
- 9. Cross Activity (c yn /ml ) 150640 11/S/91 0900
- 10. Iodine-131 Dose Equivalent (uC1/el) 4 50E-03 11/S/91 0900 STACR RELEASES (ct/ period) 6.0eE-03 11/6/91 1430
[11. Partteulate (uC1/sec) *100 11/6/91 0115 l12. Averase (uC1/sec) NONE 11/6/91 011$ l13. Pe ak l14. Discharte Average Gama Energy (Mov) 1.12 11/6/91 0115 Ill. Dees Rate to Critteal Organs (mrom/vear) 4.42 11/4/91 1630
- 6. Iodine-131 (uC1/sec) 3.30E-05 11/6/91 1630 0FF-CAS ANALYSIS
- 17. SJAE Dia. Release kate Measured / I.stinisted fuC1/see) $0000 11/6/91 0115
- 18. 5JAE Discharge Slope of Misture +0.253 11/6/91 0115 (cfm) 19.6 11/6791 0115
- 19. Condenser Air Leakane LIQUID RELEASES & RIVER TEMPEPATURE
- 20. Liquid Releese '(Gal) NA
- 21. Liquid Release (Gross Bete. Gama) -(uC1/ml) NA
- 22. Liq.!d Release (Tritium) (uC1/ sal) NA
- 23. Liquid Release (Dissolved Noble Gas) (uC1/ml) NA River Hon. #3 ifighest Temp. for previous day (oT) SS 2115 24.
BURNUP
- 25. Core Avg. burnup for previous day (HC/ST) 1F945.75
- 26. Core Cycle Burnup for previous day (HC/ST) 632S 45 REVIEWER:
THIS IS A DRILL s I-
Rev. 1 Page 6.2-9 f~' A VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD FROM: TSC Controller MESSACE NO,: TSC M 1 l TO: TSC Coordinglor CLOCK TIME: Upon assienment of-Data Recorder LOCATION: TSC SCENARIO TIME: , _ _ THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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To obtain plant computer parameters that are normally available to TSC staff, use the Controller / Observer telephone in the Plant Computer Room to request the information from the Simulator Computer Room. O ,g- THIS IS A DRILL s ******************************************************************************
i Rev. 1 Page 6.2-10 f~') V VERMONT YANKEE NUC1 JAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD FROM: ISC Controller MESSAGE NO.: TSC M 2 l TO: TSC Coordinator CIDCK TIME: Unon assicnment of Corrarunicaurs 14 CATION: TSC SCENARIO TIME: THIS IS A DRILL DO NOT initiate any actions affectin5 normal plant operations. After assigning your TSC Communicators to the Control Room, the prestaged TSC Communicators at the Simulator Control Room will be made available. C THIS IS A DRILL O O ****************************************************************************** l e + w .sa-- w - - - , - - - - y g- r--w- -
Rev. 1 Page 6.2 11 VERMONT YANKEE NUCLEAR POWER STATION DtERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSAGE CARD MESSAGE NO.: ST.M 1 FROM: EOF _Stete Observer State Reoresentative of VT. MA. NH CLOCK TIME: Upon Arrival at EOF TO: 1DCATION: State Room at EOF /RC SCENARIO TIME: THIS IS A DRILL DO NOT initicte any actions affecting norual plant operations. For initial conditions, see attached page.
***************A**************************************************************
THIS IS A DRILL
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Rev. 1 Page 6.2 12 (N VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPOUSE PREPAREDNESS EXERCISE 1991 1GEMBIO MESSACE CARD DAILY PLANT STATUS DATE 11/6/91 STATE CONTACT TIME OF STATUS 0730 TIME RE"0RTED REPORTED BY CORE THERMAL POWER MW(t) M CROSS MWe M NET MVe Rl PLANT STATUS 100% NOPRAL OPERATION NOTIFICATIONS NONE PLANT ACTIVITIES 11/5/91 2000 DECIARED HPCI INOP DUE TO FLOW CONTROLLER b FAILURE. PIANT IS IN A 7 DAY LCO CONDITION. ALTERNATE TESTINC OF REOUIRED P! ANT SUBSYSTEMS BECAN.
~
11/6/91 0600 150 PERFORMING FUNCTIONAL TEST OF ADS TRIP LOGIC. CONTINUED FULL POWER OPERATION LCO'S HPCI SYSTEM TECH SPEC T3.5.E.3 (7 DAY LCO CONDITION) OTHER THIS IS A DRILL O kj ***********w******************************************************************
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I Rev. 1 Page 6.2-13 [x VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE (.3Q FROM: jitate Controller MESSAGE NO.: ST M 2 TO: State Radiolorical Assistant C1hCK T1HE: Uoon Activation IDCATION: State EOC SCENARIO TIME: . TilIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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06:00 12:00 - General Area Forecast , Partly to mostly cloudy. Winds from the south at 3 5 MPH, swingin6 around to the southeast early this af ternoon and becoming 13 MPH. Winds will become northerly late this af ternoon and increase to 5-7 MPH. High temperature in the upper 50's. O THIS IS A DRILL
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Rev. 1 ( Page 6.2 14 (s) VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSF MEPAREDNESS EXERCISE 1891
$CENARIO MESSACE CARD FROM: ESC Controller , MESSAGE NO.! ESC M-1 TO: ESC Meteorolocist CLOCK TIKE: 10$$
LOCATION: ESC SCENARIO TIHE: 03:55 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. Utilize the attached meteorological information to generate the weather forecast for the Vermont Yankee site.
/-
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THIS IS A DRILL s- / .*****************************************************************************
Rev. 1 O Page 6.2 15 (V VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RE$PONSE PREPAREDNESS EXERCISE 1991 SCENARIO MFSSAGE CARD Date of Forecast: 11-06 91 Tire of Forecast: 09:00 Current Site Meteorology (as of 09:00 ): Time sensor yJud Mind Delta Slab. Precir. Direction Imperature Clans Sr. n d.. Lower 2.8 168 DEG MPH FROM Upper 3.9 173 DEG 0.5 DEC F E O IN/15 - MPH TROM MIN Forecast Site Meteorology: IJan Egnier Wind Eind Delta Stab. Precio._ w Synd pirection Temperature Glaan a _ __. !- f,<9:00 Lower 2.0 155 DEG e +- MPH FROM i 11:00 0.0 Upper 3.0 160 DEC E O IN/15 MPH FROM MIN 11:00 Lower 2.0 125 DEG
- MPH FROM 13:00 1.0 Upper 3.5 120 DEG D 0 IN/15 MPH FROM MIN
, 13:00 Lower 2.0 115 DEG l
- MPH FROM l 15:00 2.0 l Upper 2.5 115 DEG D 0 IN/15 i MPH FROM MIN l
l
- *****************************************************A**********************$t THIS IS A DRILL (q
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3 Rev. 1 k VERl40NT YANKEE NUC1. EAR POWER STATION , EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 i SCENARIO MESSAGE CARD National Weather Service Forecast for site region: Partly to mostly cloudy. Winds from the south at 3 5 MPil, swinging around to the , southeast early this afternoon and becoming 13 MPil. Winds will become northerly late this of ternoon and increase to 5 7 MPil. liigh temperature in the upper. 50's. Special Weather Statements: , r t h r 0 j. i
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Tills IS A DRILL k ************************************d***************************************** l
Rev. 1
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(/ VERMONT YANKEE NUCLEAR POWER STATION PaBe 6.2 17 EMERGENCY RESPONSE PREPAREDNECS EXERCISE 1991 SCENARIO MESSAGE CARD FROM: EOF /RA Controller MESSAGE NO.: EOF M 1 TO: Endiological Assistant CLOCK TIME: 1055 or as reauested LOCATION: EOF / Dose Assessment Area SCENARIO TIME:
******wt**********************************************************************
Tills 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 arouid to the southeast early this af ternoon and becoming 1 3 HPil. Winds will become northerly late this af ternoon and increase to 5 7 HPil, liigh temperature in the upper 50's. f--) L.) 7- THIS IS A DRILL s
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Rev. 1 Page 6.2 18 f VERMONT YANKEE NUCLEAR POWER STATION EHERGENCY RESPONSE PREPARUDNESS PIERCISE 1991 SCENARIO MESSACE C @ FROM: . ESC Centro 11er HESSAGE No.: ESC.M.2 l , TO: ESC Meteorolocist CIDCK TIME: 1145 LDCATION: ESC SCENARIO TIME: 9!O 45 THIS IS A DRILL DO NOT initiate any actions af fecting normal plant operations. Utilize the attached meteorological inforation to generate the weather forecast for the Vermont Yankee site. C E TilIS IS A DRILL \ ***********v******************************************************************
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I Rev. 1 l Page 6.2 19 l ( UERMONT YANY,EE NUCLEAR POWER LTATION ! EMLRGENCY RESPONSE PRE?AREDNESS EXERCISE l 1991 ; 1 SCENARIO MESSAGE CARD l l l Date of Forecast: 11 06 91 { Tiene of Forecast: 11:45 1 Current Site Meteorology (as of 11:45 ): ) l I f
'The Ernsor Eind Wind Delta Stab. Precio. l Speed ELIrf,.tlan Iettperature CIAgA i
i lover 2.2 119 DEC l MPil FROM j Upper 3.1 112 DEG 2.4 DEG F G 0 IN/15 MPil FROM MIN Forecast Site Meteorology: l ' C ( I.imt Sensor Wind Epffj Wind Direction Delta Iggperature Stab. Glass frecio . 13:00 tower 2.0 115 DEC
- MP11 FROM 15:00 Upper 2.5 115 DEG 2.2 C 0 IN/15 MPil FROM MIN 15:00 lower 2.5 100 DEC ;
- MPH FROM l 17:00 Upper 3.5 90 DEG 2.0 D 0 IN/15 MPil FROM MIN l 17:00 lower 4.5 65 DEG l - FPil FROM l 19:00 l Upper 6.0 60 DEG *1.0 D 0 IN/15 l MPil FROM MIN Tills IS A DRILL
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i Rev. 1 : Page, 6.2 20 VERMONT YANKEE NUCLEAR POWER STATION l EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CARD National Vesther Service Forecast for site region: . Partly to mostly cloudy. - Vinds from the southeast shif ting to northerly and increasing to $.7 MPH. liigh temperature in the upper 50's. Clearing later tonight. Temperature in the low 40's. . Special~ Weather Statements: r 't
***************************************************************************ggg THIS IS A DRILL
. - -_ - . - - - - -. . . . . . _ _ . = . - . - _ - _ _ .
I l Rev. 1 Page 6.2 21
,._ VERMONT YANKEE NUCll.AD. POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE '
1991 SCENARIO MESSACE CARD FROM: IQE/g6,,,Gont ro11e r MESSAGE NO.: E0P M 2 70: Radiolorical Assistant _, CIDCK TIME: 1145 or as reauested thCATION: E0P/ Dose Assessment Anga SCENARIO TIME: 04 45 THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations. 12:00 18:00 - General Ares Forecast National Weather Service Forecast for site region: f- Partly to mostly cloudy. Winds from the southeast shifting to northerly and increasing tc 5 7 MPH. High temperature in the upper 50's. Clearing later (~ tonight. Tet+arature in the low 40's. Special Weather Statements: THIS IS A DRILL g
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Rev. 1 Page 6.2 22 s/ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 SCENARIO MESSACE CAPl) FROM: State Controller MESSAGE NO.: ST M 3 70: State Radiological Assistant CthCK TIME: lil 5 j li) CATION: State EOC SCENARIO TIME: 04:45 TilIS IS A DRILL DO NOT 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: o l'artly to mostly cloudy. Vinds from the southeast shifting to northerly and Q increasing to 5 7 MPH. liigh temperature in the upper 50's. Clearing later tonight. Temperature in the low 40's. Special Weather Statements: t g TllIS IS A DRILL .(
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i l i VERMONT YANKEE NUC1. EAR PO'JER STATIO!! ; 1 EMERGENCY RESPONSE PREPARED!lESS EXERCISE 1991 4 P 7.0 EIATION EVENT DATA 7 P E 7 O h
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O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.1 EVENTS
SUMMARY
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Rev. O Page 7.1 1 VER.MONT YANKEE NUCLEAR POVER STATION FAERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.1 EVENTS SlMGRY The following information and supplementary material are provided for those evaluators having in plant control assignments so as to further ensure the proper development of the scenario. The intornation provided in this section assumes that the " players", who are dispatched to perforte repair, rescue, or other activities, vill 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 preclude the possibility that the evaluator vill be required to provide additional information to the players. Approximate Minis _enario Ilmt Event Location Initiation 7.2.1 0745 ADS relay Control Room Simulator failure Controller 7 . 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 Fai'.ure Building Response 7.2.6 1050 RWCU V12 15 Reactor Simulator Failure Building Response O :
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@ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7
7.2 EVENT MINI SCENARIOS l l 1 t ( (
.2_..... .._ _ .._ _ _ _ _ _ ___ _ . _ _ _ _ _ . _ - . . . _ . . . _ _ . . _ - . . . . . , . _ . . . - . . , . . ~ . . _ , . _
Rev. 0 Page 7.2.1 1 VERMONT YANKEE NUC1. EAR p0VER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.1 Miniscenario ADS Relav Failure , I. General Descriotion
.i As a result of the llPCI system being declared inoperable, Technical Specifications require that alternate testing of the Autoicatic 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.
- 11. Descrintion of Player Responses / Observations / Corrective Actions The Shif t Supervisor should declare an UNUSUAL EVENT as a result of the loss of the 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 snaintenance practices should be followed throughout the activity. 111. Eygnt Closeout This event will be closed out when the repair team-informs the evaluator that they have assembled all the necessary tools, 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 leader should inform the SCR that repairs are underway and provide an 1 i
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Rev. 0 ( . Page 1.2.1-2 VERMONT 'YAN. E NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 L. ;. , l6f /N [,f .atin ate of 4 tion. The IGC Team will be released when the time
. , . v specified by d seam leader has elapsed.
3 Messarri The following n iages are applicable to this event. The messages shell he providad to the players at the indicated time or when the evaluator determhes that the information has been " earned" by the ple.yer.
> Massage Approximate Basic
_ umber be Descriotion 7.2.1-M 1 0715 Shift I&C ~1ech: f cian report that ADS relay failed test. 7.2.1-M-2 0745 Shift 16C Technicians initiate repairs to the Ki' failed ADS relay. 4 O l _ . . ~ . . ,
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Rev. 0 Page-7.2.1 3 7
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VERMONT YANKEE NUCLEAR POWER STATION 7g EMEkCENCY RESPONSE PREPAREDNESS EXERCISE 1991 J MINI-SCENARIO MESSAGE CARD FROM: SLR Controller MESSAGE NO.: 7.2.1-M-1 TO: .gbift Suoervisor CIDCK TIME: 0715 LOCATION: SCR (Caitro- 0 SCENARIO TIME: 00 15 THIS IS A DRILL DO NOT initiate any actions affecting' normal plant operations.
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FOTE TO CONTRDLIER: F2 PORT THIS INFORMATION OVER THE SIHULATOR GAITRONICS TELEPHONE
^"TilIS IS fnare of shift T&C Technician 1, WE JUST COMPLETED THE FUNCTIONAL TEST OF. Tile ADS TRIP LOGIC. EVERYTHING CHECKED OUT 0.K., EXCEPT THAT THE 120-SECOND TIMER RELAY 5 TIMED OUT AT 145 SECONDS. THIS IS OUTSIDE THE ACCEPTANCE RANCE ALLOVED_IN THE-TEST cSPEC. WE'RE GOING TO HAVE -TO REPLACE THE REIAY."
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- r% Page 7.2.1 4 U VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 j MINI-SCENARIO MESSAGE CARD j 1
l 1 FRvM: SCR Controller MESSAGE No.: 7 . 2 . ',,f - 2 J TO: Shift Supervisor ,_ CIACK TIME: 0745 , LOCATION: .SCR (Gaitronics) SCENARIO TIME: 00:45
*****************************************************************************w THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
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NOTE TO CONT?OLLER: REPORT TRIS INFORMATION OVER l'IE SIHULATOR GAITRONICS TELEPHONE .i "THIS IS Iname of shift I&C Technician), WE J1JST REMOVED THE BAD RELAY. VE HAVE A i SPARE RELAY OVER IN STORES. WE SHOULD BE ABLE TO GET THE NEW ONE INSTALLED, TESTED AND BACK IN SERVICE IN ABOUT 2 1/2 TO 3 HOURS. vO l l
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Rev. 0 Page 7.2,2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.2 Miniscenario - Loss of Electriq3,1 Bus DC-3
- 1. Generni DenerintinD At approximately 0815 electrical bus DC-3 experiences a losa 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 emerge scy 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. Description of Player Responses / Observations / Corrective Actions O t When power is lost to electrical bus DC-3, the following indications are lost in the Simulator Control Roora:
- 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 tha, the panalarms have been lost, the controlled power reduction may be suspended. An ALERT should be declared and an Auxiliary Operator (AO) dispatched to investigate the loss of DC-3.
When the A0 arrives at the manual bus transfer device, he should attempt to repositior. the manual trannfor to the emergency power source. When this is attempted, the device jams and cannot be moved. When the repair team arrives at the transfer device, they will discover that the switching device is in the NORMAL position and cannot be placed D) (w/ in the EMERCENCY position. When they open the bus transfer housing they I l
Rev 0 T'N Page 7.2.2 2
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 position. When they open the bus transfer housing they can see that the actuator is mechanically bound. Af ter some manipulation, they can physically operate the switching device and place it in both the NORMAL or EMERGENCY position. They may " cycle" the actuator several times, attempting to re-create the malfunction, but the device operates normally. In any event the transfer device will oc returned to service and DC-3 repowered from it's normal source by 0945. III. Event Closcout This event will be terminated when the repair team leader informs the evaluator of all actions that would be taken based on the conc'itions described above. When the evaluator informs the team leader that the 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. tirssares 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 iniormation has been " earned" by the player. Message Approxim+.re Basic Neabe r lig Descrintion 7.2.2-M-1 0915 AO activities when attempting to operate DC-3 Marual Bus transfer device. 7.2.2-M-; 0930 Initial results of inspection of transfer device 7.2.2-M-3 0945 Results of troubleshooting activities.
Rev. O Page 7.2.2-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MIN 1-SCENARIO MESSAGE CARD FROM: OSC Observer _. MESSAGE NO : 7.2.2-M-1 TO: A0 O DC-3 C1hCK TIME: 0915 LOCATION: DC-3 Manual Bus Transfer SCENARIO TIME: 02:15 THIS IS A drill DO NOT initiate eny actions affecting normal plant operations. When you attempt to transfer power to the EMERGENCY aource, the selector switch cannot be repositioned. All efforts to change to the EMERGENCY power source fail. I
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%f VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 i
MINI. SCENARIO MESSACE CAPl) FROM: OSC Observer MESSAGE NO.: 7.2.2 M-2 TO: A0/OSC Renair Team ' Leader 9 DC-3 CLOCK TIF.E: 0930 LOCATION: Area.of DC 3 bus transfer CCENARIO TIME: 02 30
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THIS IS A DRILL DO NOT initiate any actions affecting nota 41 pl mt operations. The selector switch / actuator are mechanically jamined. Af ter some minor adjustment to the connections the linkage operates freely. p ( l l .- 1 i i l
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- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS' EXERCISE 1991 tilyt-SCENARIO MESSAGE CARD
-FROM: OSC Observer MESSAGE NO.: 7.2.2-M 3 TO: A0/OSC 'Renair Team Irader 9 DC-3 ClhCK TIME: 0945 14 CATION: Area of DC-3 bus transfer SCENARIO TIME: D.2245
*************************w**************ck***********w***********;************-
THIS:IS A DRILL DO NOT-initiate any actions affecting normal plant operations. After several manual actuations of the bus transfer device, no' malfunctions have occurred. The bus transfer device can be placed back in service. i l- < s L
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Rev. 0 ( Page 7.2.3 1 k))- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.3 Miniscenario - CRD-V56 Operation I. General DescriotioD When the turbine trips on loss of condenser vacuum, a reactor SCRAM should take ple,ce. Indications on the Reactor Control Board show that the signal was generated, but the control rods did not insert. The 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 initiated, the Control Rod Drive char 81 n6 water header isolation valve (CRD V56) must be shut. II. Descriotion of Player Resoonses/ Observations / Corrective Actiong t' D). When the decision to manually drive the control rods into the core is
.made, an Auxiliar/ Operator- (AO) would be dispatched to the Reactor Building 252'-6" elsvation to shut CRD-V56. When the A0 reaches the valve _ location, the eva' ator will direct that all actions associated with valve manipulation be simulated. The A0 should describe all actions to be taken to reposition the valve to the evaluator and inform the SCR accordingly.
III. Event ' , scout This t. vent is terminated when the A0 reports to the SCR that the valve has been repositioned. n t
Rev. 0- /~3 Page 7.2.3-2 O 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-Number IID.2 Diacd ption 7.2.3-M-1 1045 Auxiliary Operator closes CRD V56.
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.- - , . .._ _ . .- . .. - - - .- -. ~ ..-...~ - - ~ . _.-..~..- . . ....,... ..
Rev O Page 7.2.3 3 f VERMONT YANKEE NUCLEAR POWER STATION
. EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 P MIN 1-SCENARIO MESSACE-CAM
.FROM: 01Q Observer MESSAGE NO.: 7.2.3-M 1
-TO: AO dimostched to shut CRD V-56 CiOCK TIME: 1045 IDCATION: Reactor Buildine SCENARIO TIME 03:4$
************************************************w*****************************
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.
4 t 5 0-t
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Rev. O Page 7.2.4-1 VERMONT YANKEE NUCLEAR POWER ST/*'i'
~
EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.4 Miniscenario - *C" RHR Pumo Trin At approximately 1.015 the turbine trips duo to a loss of condenser vacuum. This results in the Main Condenser being unavailable as the primary heat sink. The operators shov1d initiate RRR in the Torus Cooling mode for reactor temperature and pressure control. This should occur by 1030. At approximately 1045 t.he simulator operator will insert a loss of the "C" RHR Pump. I. Ceneral Dpgerietion When the "C" RHR Pump is lost, the "A" RHD. pump should start to maintain torus cooling via the RHR heat axchangers. An A0 or OSC Team may be b (j dispatched to investigate why thu pump tripped. They should proceed to the Switchgear Room. The breaker tur 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 undervoltaga trip coil has opened, which resulted in the breaker trip.
l l This information should be provided to the OSC and/or the SCR so that L repair activities can be initiated. I' II. Descriotion of Player Responses / Observations / Corrective Actions
-_ A repair team should be assembled, briefed and dispatched to repair the "C" 'RHR Pumi. 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, l
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Rev. 0
/
- Page 7.2.4-2
.\ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 III, Event Clostout This event will be closed out when the repair team informs the evaluator that they have assemblea 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 ev21uator should ask the team leader how long the repair will take to complete , including testing. The team leader shoula inform the OSC that repairs are underway and provide an estimate of job duration. *1he OSC Team will be released when the time specified by the team leader has elapsed. In the event that the area beccines uninhabitable (due to scenario conditions), the Team should return to the OSC and brief the OSC Coordinator accordingly. IV. Messares The following messages are applicable to this event. The messages shall be provided to the plap rs at the indicated time or when the evaluator determines that the infor' nation has been " earned" by the player. Message Approximato Basic Description NumbtI 11mst 7.2.4-M-1 1100 Initial response to the RHR Pump circuit breaker. 7.2.4-M-2 1105 Internal investigation of circuit breaker. 7.2.4-M-3 1130 Results of internal troubleshooting activities. 7.2.4-M-4 1150 Completion of installation and testing of replacement relay. 3 l
- _ - _ . - - - ~ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _
Rev. 0 Page 7.2.4 3 i [ VERMONT YANKEE NUCLEA.R POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSAGE CARD FROM: QSC Observer MESSAGE NO.: 7.2.4-M 1 TO: OSC RHR Eumo Repair Team Leader C1hCK TIME: Acorox. 1100 LOCATION: C RHP I-clo circuit breaker ___ SCENI.RIO TIME: 04:00 THIS IS A DRILL DQ lQI initiate any actions affecting normal plant operations.
************2f***********k************************************************t****
The circuit breaker for RRR Pursp "C" is in the tripped position, f (
Rev. O Page 7.2.4-4. i'j i
- VERMONT. YANKEE NUCLEAR POWER STATION l
. EMERGENCY RESPONSE PREPAREDNESS EXERCICE !
1991
-l KTNIr.SCENARTO MESSAGE CARD FROM:- OSC Observer . MESSAGE NO.: 7.2.4 M-2 TO: Qft,Q_RHR Pumo Repair Team Leader CIDCK TIME: Acorox. 1105 ,
14 CATION: C RHR Pump circuit breaker SCENARIO TIME: 04:05
****************4*************************************************************
THIS IS.A DRILL DO'NOT initiate any. actions affecting normal plant operations, J
***********************************************************>***************A** .
?
' NOTE TO CONTROLLER: PROVIDE THIS INFORMATION AFTER THE REP /IR TEAM LEADER EXPLAINS THAT THEY WOULD PERFORM All INTEP3AL INSPECTION OF THE CIRCUIT BREAKER.
Yout ce the undervoltage trip coil is slightly blackened and the insulation appears 7 to be very brittle, b.] 3 r S 5 1 4 U , r {
. . . = . . - . - . . . , . .
Rev. O Page 7,2,4 5 V VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNEES EXERCISE 1991 LUE-SCQ1ARIO MESSAGE CARD FROM: OSC Obperver MESSAGE NO., 7.2.4-M-3 TO: OSC PRR Pumn Rennir Team Leader CIDC'T_ TIME: Annrox. 1130 LOCA*IION : C RHR Pumn circuit breaker SCENARIO TIME: 04:30 __
-*****************************************************+************************
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
*************************w****************************************************
NOTE TO CONTROLLER: PROVIDE T4IS INFORMATION ONLY AFTEE THE ETPAIR TEAM DESCRIBES THAT THEY WOULD INITIATE RESISTANCE (OR HEGGAR) READINGS OF VARIOUS BREAKER COMPONENTS Resistance across the undervoltage trip coil reads infinity.
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Rev. 0 Page-7,2.4 6 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 d MINI-SCENARIO MESSACE CARD FROM: Q10 Gbserver MESSACE NO.: L2.4 M-4 TO: OSC RHR Pumo Repair Team Leader CLOCK TIME: Aporox. 1150 1DCATION: C RER Pume circuit breaker SOENARIO TIHE: 04:50 THIS IS 4 DRILL DQ,.EQI initiate any actions affecting normal plant cperations.
**k****************************************k***************************i4*****
NOTE TO CONTROLLER: PROVIDE THE FOLIDWING IKFORMATION AFTER THE REPAIR TEAM LEADER EXPLAINS TO YOU HOV THE NEW COIL WOULD BE INSTALLED, TESTED AND THE BREAKER RETURNED TO SERVICE. :F A SPECIFIC TIHE PER10D WOULD BE CONSUMED DURING THE INS 1;.LLATION AND TEST ACTIVITIES, DO NOT RELEASE THE TEAM UNTIL THAT TIME PERIOD ELAPSES. The coil has been installed and tosted. The breaker can be returned to service. S i d a n-u
Rev. O
'" Page 7.2.5 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.5 Miniscenad o - SLC Sauib Valves Fall to Finq I. General DescrinttED !
l In an effort to reduce reactor power, the operators may elect to initiate Standby Liquio Control (SLC) . This is accomplished from the Reactor Control Panel usin6 the appropriate keylock control switches which actuate the explosive Squib valves. When the Reactor Operator actuates the switches, the valves fall to fire.
!I. DggsIJntion of Player Responses /Observarigns/ Corrective Actions When the RO notic s that the squib valves did not actuate, an A0 may be dispatched to manually actuate the valves. This is accomplished in accordanc3 with OE- 3101. Appendix G. This will involve attaching e f' battery to each valve to set off the explosive primer. TFESE ACTION $
WILL BE SIMULATED. When this is demonstrated, the A0 can report that j the valves have been actuated and initiation of SLC can cotamence.
-III. Event Closeogg This event is terminated when the A0 reports to the SCR that the valves have been fired.
-IV. Messares The following messages are applicable to this event. The messages shall
> be provided to the players at the indicated time or when the evaluator s determines that the information has been " earned' by the player. Message Approximate Basic E9mber ling De.9eription 7
~~g: 7.2.5-M-1 1050 Manual firing of Squib vc1ves by AO.
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_ - . . - - - _- ..- - - .~.- . .- . ~ _ - - . . _ - _ . .
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Rev. O Page 7.2.5 2 v-VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINT-SCENARIO MESSAGE CARD FROM: OSC Obr.erver MESSAGE NO.: ]J .5 M-1 To: AO dispatched to fire Souib valves CIDCK TIME: Arm rox . 1050 14 CATION: Reactor Building. Saufb valves SCENARIO TIME: Q3:50 THIS IS A DRILL DO NOT Initiate any actions affecting norinal plant operations,
?OTE TO CONTROLLER: DO NOT ALlLM THE AO TO PHYSICALLY MANIPULATE ANY EQUIPMENT ASSOCIATED WITH THIS ACTIVITY. THE AO SHOULD DEMONSTRATE HOV TO PERF0Fft THIS ACTIVITY, INCLUDING THE LOCATION OF THE BATTERY. ISSUE THIS HESSAGE WHEN THE AO TELLS
') THAT ALL ACTIONS IDENTIFIED IN OE 3101, APP. G llAVE BEEN CGtfPLETE.
1 MANUAL ACTUATION OF THE SQUTb VAINES IS COMPLETE. I l 1 a l' t l- {a l
l
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Rev. 0 1 Page 7.2.6-1
^' ~
VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 7.2.6 Miniscenario - RWCU V12-15 Failure I. Etperal Descrintion a When the automatic isolation signal is sent to the Reactor Water Cleanup (RUCU) system, the primary containment inboard isolation valve (RWCU. V12 15) remains open due to MOV motor controller failure. II. Descrintion of Player Resnonses/ Observations / Corrective Actions An OSC Team should be assembled, briefed and dis}.atched 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
-troublesh uting of the internals. Whe.i they open the controller, they will observe charri::g 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
,sre intact and operabla.
In addition, en I&C Technician may be directed to investigate the
, valve's logic circuit-in the control board. It' this occurs, .he I&C
-Technician will-report that logic circuit checks are satisfactory.
l l ~ III. Fant Closecut; i This event will be terminated when the team demonst rates that ti-a spare parts can be obtained from Stores, installed and tested (simule ,and t report made to the SCR that the controller can be returned to service. s I
Rev. 0
-t t'$.j -- Page 7.2.6-2 v 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 determines that the information has been " earned" by the player, Message Approximate Basic
}{ughnr Tirne Descrintion 7.2.6 M-1 1100 OSC repair tears 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 I6C investigation of valve logic circuit in-control board. 7.2.6-M 4 1150 Motor controller is repaired. L P a L t-r- ' ~f) -
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Rev, 0 Page 7,2.6-3
, 's
[~)N - VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI SCENARIO MI'ISAGE CAEQ
-TROM: QS_C Observer MESSAGE NO.: 7.2.6-M-1 TO: RWCU Valve Repair Team Leader CIDCK TIME: 1100 IACATION: RUCU Valve Motor Operator SCENARIO TIME: 04:00
***i**********************w****ke*********************************************
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
**********+++*****************************************************************
The motor controller external inspection reveals nothing, out of the ordinary. l-( l l ( l r l l l 1 > . 0% (/ t
Rev. G 3 Page 7.2.6 4
-[O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSACE CARD 1 ROM: OSC Observer MESSAGE NO.: 7.2.6-M-2 TO: RWCU Valve Repair Tearn Leader C1hCK TIME: 1110 LOCATION: RUCU Valve Motor Operator SCENARIO TIME: 04:10
********+*********************************************************************
THIS IS A DRILL DO NOT initiate any actions affecting normal plant operations.
**+********ww*****************************************************************
NOTE TO CONTROLLER: PROVIDE THIS INFORMATION WHEN THE REPAIR TEAM LEADER EXPLAINS THAT AN INTERNAL INSPECTION OF THE HOTOR CONTROLIER VILL BE PERFORHED. THE REPA1R TEAM SHOULD TAKE STANDARD ELECTRICAL SAVET1' PRECAUTIONS CONS 1 STENT WITH THE ACTIVITIES TO BE PERFORMED.
.'"(m) You observe minor charring in the area of the main lino contactor. The main line contacts for phases A and C are blackened 'and pitted, the contacts for phase "B" are cracked and partially missing. /m.s s 'V
m,._ . . _ . .. . _ . ._ .. .- _ _ . . _ . - . _ _ . _ _ . _ _ _ . _ . _ . _ . _ . . _ _ . _ . _ t m
+- i Rev. 0
- Page 7.2.6-5 _
g
, VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY-RESPONSE PREPAREDNESS EXERCISE-1991
-MINI-SCENARIO MESSACE CARD
=FROM:: . Control Room Controller MESSAGE NO : 7.2.6-M 3 TO:- I&C Technician checkinn RWCU logic CIDCK TIME: 1110
.IDCATION: Control Room nanel SCENARIO TIME: 04:10 THIS IS A DRILL c
.DO NOT-initiate any actions affecting normal plant operations.
~
,= NOTE TO CONTR0 LIER: PROVIDE THIS INFORMATION AFTER THE T&C TECHNICIAN EXPLAINS THE TROUBLESHOOTING ACTIVITIES TO BE TAKEN (INCLUDING AN ESTIMATE OF HOV IDNG THIS WILL TAKE).- DO NOT F212ASE THE TEAM UNTIL THAT TIME RAS ELAPSED, [ All circuit readings are normal, l' L 4 l i I 'i s I i e _ I: I i-
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Rev. O O Page 7.2.6-6 VERMONT YANKEE NUCIIAR POWER STATION EMERGMCY RESPONSE PREPAREDNESS EXERCISE 1991 MINI-SCENARIO MESSAGE CARD FROM: OSC Observer MESSACE NO.: 7.2.6-M 4
..TO : RVCU Valve Renair Team bender CIhCK TIME: 1150 IDCATION: RVCU Valve Motor Onerator SCENARIO TIME: 04:50 THIS IS A P'.IILI.
DO NOT initiate any actions affecting normal plant operations. NOTE TO CONTROLLER: PROVIDE THIS INFORMATION AYTER THE P2 PAIR TEAM 12ADER EXPLAINS THE REPAIR ACTIVITIES TO BE TAXEN, INCU) DING OBTAINING REPLACEMENT CONTACTS FROM STORES, INSTAL 1 AT10N AND TESTING. IF THE TEAM 12ADER SPECIFIES A LENGTH OF TIME TO COMPLETE THE REPAIR, DO NOT RELEASE THE TEAH UNTIL THAT TIME HAS ELAPSED.
.t(, ).
'd The contacts have been replaced, tested and the unit can be returned to service.
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( O VERMONT YANEEE NUCLEAR PO'n'ER STATION EMERGENCY RESPONSE PREPAREDNESi EXERCISE 1991 8.0 OPERATIONAL D Q 1 E,'i; ;. The operational data is highly dependent on operator actions taken in response to the conditions presented within the scenario. Thu operational data reflects plant conditions assuming certain basic operator response actions being taken. The operational data was taken from the plant t imulator. , W O
) VLDONT TANLEE NUCLY.AR KMER ST ATION Rev 0
'N fMTRGENCY Rf.SIONSE PREPAREDNESS EI5'RCISE Fago 6.0-1
(~ ! 19ill 5.0 OPERATIOliAL DATA 00:00 00:15 00:30 00:45 01:00 01:15 01:30 01:45 SCENARIO TIMr 07:00 07:15 07:30 07:45 08:00 08:15 04:30 ce:45 INSTR. CLOCE IIFO ID DESCRIPTION UNITS ITD4 PA 4TL_ 0 0 0 0 0 1 9-5 TT-23 108-1 BICI TLW CH 0 0 0 1 1 1 1 1
,0 !H 1 1 1 2 9-3 F1-10-139A Ef!R A FLOW _ , ,
1 1 1 1 1 3 9-3 F1-10-1398 RIDt A FLOW O!H 1 1 1 10 10 10 10 10 10 F1-14-50A CS A T10W GN lj 10 4 9-3 to 10 10 it 10 10 10 5 9-3 F1-14 505 C3 B FLOW GtH 10 17 17 17 17 17 17 PS1A 17 17 6 9-3 P1 18-10-12 EiRYWELL PRESS 17 17 17 17 17 17 17 7 9-3 PI-16-19-12 DRYWELL PRESS PSIA 17 0 0 0 0 0 0 0 8 9-4 F1-13-91 RCic F1.N , GN 0 65 65 65 65 65 65 65 9-4 F1 141A RWCU FLOW C,1N 65 9 (5 65 65 f5 65 f5 f5 65 to 9-4 FI-12-1419 1&CU TLOW GTH 526 527 527 526 525 523 522 11 9-4 2-165A RX COOLANT TEMP DEG F 52 8 528 527 527 526 525 523 522 12 9-4 2-165B RX COOLANT TDtP DEG F 528 LGIN 30.6 30.6 29.9 29.4 28.3 25.7 24.4 23.4 13 9-4 2-150A RECIRC A li1OF FLW FGIH 30.6 30.6 29 9 29 4 28.3 25.6 24.3 23,4_ 14 0-4 2-1%B RECIRC B LOOP FIN 99 97 94 67 B+ 81 9-5 7-46A APM/IM A 1 99 9 t! IS 94 87 64 82 1 100 100 98 97 16 0-5 7-46B M RM/TRM B 80 1 98 96 97 96 63 86 83 11 9-3 7-46C A.PRM/IRM C 84 81 1 99 99 98 97 94 a7 18 95 7 460 APNM / n'M D 100 99 95 95 67 85 82 19 9-5 7-46E A.PRM/IRM E 2 100 100 99 98 95 67 64 82 05 7-46F AFEM/IRM F ! 100 20 95 7-43A SRM A CT, 3.70E+05 3.70E+05 3.60E+05 3.50E+05 3 3CE+05 L 60E+ s5 2.50E+05 2.4cE+05 g 23 CPS 4.50E+0S 4. 50E+05 4. 40E+05 a ,30E*05 4 00E+05 3.40E+05 3.00E+05 2.80E*05 22 9-5 7-418 ERM B tiRM C CPS '.00E+05 5.00E+05 4.90E+05 4,80E+05 4.50E+0S 3.80E+05 3. 50E+05 3. 20E+05 w 23 9-5 7-43C 0-5 7-43D MRM D CPS & 20E&05 4.20E+05 4.10E+05 4.00E+05 3.7CE+05 3.20E+05 2.90E+05 2.70E+05 j4 47 47 47 46 44 40 30 37
.: 5 9-5 2-3 95 CORE FLOW MLB/KR 18 18 18 17 17 14 13 12 14 0-5 2-3-95 CORE CP PSID GIN 47.3 47.3 47.3 47.3 47.3 47.3 47.3 47.3 2; 9-5 T1 3-310 CRD FIN 1007 1006 1004 1001 991 987 984
.28 9-5 6-96 WIDE RANT,E FE E S PSIG 1007 1007 1006 1005 1001 Sb2 487 984 29 9-5 6-96 NAR RANGE PEESS PSIG 1007 MLB/ER 6.3 6.4 6.3 6.2 6 !.6 5.3 5.1
'i 9-5 6-97 FEEDWATER FIN K.B/HR 6.4 6.4 6.3 6.2 6 5.6 5.3 5.1
% 9-5 6-07 MAIN STT.AM FLOW 158 158 159 158 158 156 158 158 32 0-5 6-98 N AR RANGE LEVE1 IMORTS 492 469 481 461 455 410 391 372 33 9-5 6-98 WIDE RANGE LEVTL INCUES 51 50 50 50 50 40 47 L1-107-5 CST LEvit 1 51 34 9-6 56 56 56 Se 56 56 75 42 35 9-6 LI-102-5A HOTWLLL LETEL N I 54 54
- 5. 54 54 54 54 54 36 C-6 LI-102-55 ftOTWELL LEVEL S I IN tt3 1.0 1.8 1.8 1.6 1.8 1.7 1.7 1.7 37 9-7 PI-101-29 CONOENSER VACUUM OPE 4 OPEN OPEN OPEN OPEM OPEN OPEM OPEN 38 9-8 dig _A BKR OPEN OPEN Ol'EN OPEN OPEN OPEN OPLN 39 9-8 D/G B BKR OFEN 72 72 72 72 72 72 72 72 40 0-23 16 1b-35AFC Tokus ite P DEG1 FEET 0,56 0.58 0.58 0.56 0.58 0.57 0.57 0.57 41 9-25 LI-46A TORUS LEVEL FEET 0.56 0.58 0.58 0.56 0.58 0.57 0.57 0.57 42 9-25 LT-4EB TORUS LEVEL PSIA 14.6 14.6 14.6 14.6 14.6 14.6 14.6 14.6 43 9-25 TR-16-19-44 TORUS PRESS 17 17 17 17 17 17 13 44 0-25 TP-18-19-44 DRYWELL PRESS PSIA 17 45 9 25 PR-1-156-3 DW/ TORUS DP P5ID 1.88 2.06 2.04 2.03 2.02 2.De 1.99 JE 106 10$ 106 106 106 106 106 46 9-25 TR-16-19-45 DRYWELL TDtP 9EG F tot 9-26 P1-1-125-3A RX BUILDING DP IN 820 -1.62 -1.62 -1.62 -1.62 -1.62 -1.62 -1.62 -1.62 47 IN R2O -1.62 -1.62 - 1. F.2 -1.62 -1.62 -1.62 -1.62 -1 62 48 9-26 F1-1-125-3B RX Bt'1LDING DP
$ 6 6 6 6 6 49 9-26 F1 125- EA SCTS FLOW CIN O O 0 0 0 0 0 0 0 FI-1-125-1B SGTS FLOW CFM 0 50 9-2f I 2.56 ~. 5 5 2.55 2.54 2.54 2.54 2.54 2.53 51 CAD DW/TCRUS O2 CONC.
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d
i VEMONT TANKE! IrJCLEAR KMER STATION Rev. 0 Pase 8.0-2 OY EMERGENCY REF NNSE PREFARIDNESS EXERCISE 1991 0,0 OPERAT10KAL DATA SCDAPIO TIME 02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 CLOCK TIME 09:00 09-13 09:30 09:45 10:00 10:15 10:30 10:45 INSTR. . ITEM PANEL ID DESCRIPTION l' NITS GN 0 0 0 0 0 0 0 0 1 0-3 TT-23-106-1 RPCI F W 2 9-3 F1-10-139A KHRAFW GFN 1 1 1 1 1 1 2 6433 " GM 1 1 1 1 1 2 6497 3 9-3 F1-10-139B RER B FLIM 01H 10 10 to 10 10 16 to 10 4 9-3 Flat 4*SOA C5 A FIN GM 10 10 10 10 10 10 10 10
$ u-3 F1-14-$0B CC B FLN PEIA 1? 17 17 17 17 17 18 18 6 9-3 P!-16-19 12 DRYWELL PRESS PSIA 17 17 17 17 il 17 16 14 7 93 P1-16-10-12 DRYWELL PRESS 0 0 0 0 0 0 0 0 8 9-4 FI-13-91 ROIC FLCW GTH Gm 65 63 65 65 65 65 0 0 9 94 F1 141A RWCU FLCW GTH 65 65 65 65 65 65 e i 10 9-4 FI-12-141B RiCJ FLOW ~
EX COOLANT Tm? DEG f $22 S20 S'40 S10 $17 515 527 s 11 9-4 2-16SA
$22 520 520 51B 517 515 527 44's 12 9-4 2-165B RX COOLANT T NP DEG F 9-4 2-159A RTCIRC A LCOP FLCW EGm 23 21 20.7 19.1 li.7 15.9 0 0 13 5-4 2-1599 RECIRC 2 LOOP FLCW KOM 23 21 20.7 19 17.6 15.9 0 0 la 60 73 74 70 67 63 S 3 15 9-5 7-46A ATM/lRM A 3 75 75 71 C7 63 5 3 16 9-5 7-46B APkM/IRM B 1 SO 1 79 74 74 70 66 62 S 3 17 95 7-46C APRM/IR71 C 80 75 7e 70 67 63 5 3 18 95 7-46D APRM/IRM D 1 ,
1 81 76 75 71 67 63 5 3 19 US 7-46E APRM/1RM E
*-46F APRMIIRM F 1 81 75 75 71 67 63 5 3 20 9-5 9-5 7-43A SRM A CPS 3.40E+06 2.02E* 0 5 1,9 7E+0S 1. 74E+0 S 1.56E+0S 3. $0Et06 3.00E +03 2. 62Z+02 21 22 9-5 7-438 ERM B CPS 7.95E+06 2. 41E+0 5 2. 34f +0 5 2. 07E*05 1. 36F+05 6.10E+06 3.00E+03 1.85E+02
' 23 9-5 7-43C SM C CPS 1.40E+06 2.72E*05 2.64E*05 2.34E+0S 2.00E*05 0.20L+06 3.00E*03 1,47E*02 24 9-5 7 43D SM D CPS 6.10E+05 2. 261+05 2 20E+05 1.95E+05 * . 74Y+05 5.10E+06 3. 00E +03 1. 83E*02 CCREFLN M'8/KR 36 33 32 30 28 26 1 1 25 9-5 2-3-95 .
PSID 12 11 11 10 9 8 3 3 26 9-5 2-3-95 CORE DP F1-3-310 CRD FLOW Gm 47.3 47.3 47.3 47.3 47.3 43.9 45.6 45.9 27 9-S PSIG 983 977 976 972 966 911 932 _ 28 9-5 6-96 WIDE RANGE T1t.ESS ___ 964 PSIG 963 977 976 972 969 965 950 950 29 9-5 6-96 RAR kANGE PRESS 30 9-5 6-97 FEEDWATER F1IW MLE/HR S 4.7 4.6 4.4 4.1 3.9 0 0.2 31 9-5 6-97 MAIN STEAM FLOW MLB/ER S.1 4.7 4.7 4.4 4.2 3.9 0 0 158 159 ISP 158 ISB 159 42 47 32 9-5 6-98 NAR RANGE LEVEL INCHES 364 326 314 294 267 248 42 47 33 9-5 6-98 WIDE RANGk. LEVEL INCHES 47 47 47 46 47 , $1 48 45 34 0-6 L1-107 5 CST LEVEL 'e _ 2 64 64 83 91 65 SS 47 $5 35 9-6 LI-102-5A HOTWELI. LEVEL N 54 54 54 $4 58 53 47 54 16 9-6 Lt-102-5B BOT 1' ELL LEVEL S 2 9-7 PI-101-29 CONDENSER VACUtH IN BG 1.7 1.7 1.6 1.6 1.6 1.8 24.2 29 37 D/G A BKR CPEN OPEM OPD OPEN OFEN OPW OPEN OPEN 36 9-8 39 9-8 D/G B BKR OPD OPLE OPD OFD OPLM CPEN OPEN OPEN DEG F 72 72 72 72 72 72 138 141 40 9-23 16-19-33A/C TORUS TIMP 9-25 LI-46A . TORUS LEVEL FEET 0.57 0.57 0.57 0.57 0.57 0.56 0.90 0.96 41 42 9 25 LT-46B TORUS LINIL FEET 0.57 0.57 0.57 0.57 0.57 w.56 , 0.90 0.96 43 9-25 TR-16-19-44 TORUJ PRESS PSIA 14.6 14.E 14.6 14.5 14.6 14.6 18.6 18,9 PSIA 17 17 17 17 17 17 18 _ 18 44 9-25 TR-16-19-44 DRYWELL PRESS 45 9-25 PR-1-156-3 DW/TGRU3 DP ISID 1.P7 1.95 1.94 1.93 1.52 1.91 -0.49 -0.46 46 9-25 Tk-16-19-45 DRYWELL TfNP DF.C F 106 106 los 105 106 106 106 107 4' 9-26 FI-1-125-3A RX BUILD *% DP IN 820 -1.62 -1.62 -1.62 -1,62 -1.62 -1.62 -0.66 -0.68 42 9-26 PI-1-125-3? RX BUILDIR3 DP IM E20 -1 62 -1.62 -1.67 -1.62 -1.62 -1.62 -0.64 -0.68 49 9-26 F1-1-125-1A GGTS FLOW Cm 6 6 5 6 8 0 1500 1500 FI-1-125-1B SGTS FLOW C7N O O O O O O 1500 1500.__ 50 0-26 tW/ TORUS O2 CONC. I 2 53 2.53 2.53 2.32 2.52 2.58 2.52 2.51 g S1 CAD k 4 ( l
l VIWONT Y ANKII NUCLLAR PWIR STATION Rev.0
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Fase 8.0 3 ( EMERGENCf RISK *SL FREFARIDNESS EXERCISE 1991 8.0 OPERATIONAL DATA SCENARIO TIME 04:00 04:15 04:30 04:45 05:00 05:15 05:30 0$:45 INSTR. CLCK'E TIrtE 11:00 11:15 .1:30 11:45 12:00 12:15 12:30 12:45 IT124 PANE 1. ID CtSCRIf* ION UNITS G1H 0 0 0 0 0 0 0 0 1 9-3 FT-23-104-1 RPCI FLOW 2 9-3 F1-10 139A RER A FLN CIN 6368 6368 6368 63E8 6366 6368 6746___ 6746 , Gm 6497 6497 6497 6497 6497 6497 6e38 6838 3 9-3 F1-10-13sB R3R 8 FLOW 10 10 10 9 10 10 4 9-3 F1-14-50A CSAFLN GIH 10 to GIH 10 10 10 10 to 9 10 10 S 9-3 F1-14 SOB CS B FLOW PSTA 18 18 18 18 18 23 23 22 e 9-3 P1-16-10-12 DRYWELL PRESS , FSIA 18 18 le 18 15 23 23 22 7 9-3 F1-16-19-12 DRYWT.1J. PRESS CfH 0 0 0 0 0 0 0 0
~
8 9-4 F1-13-91 RCIC FLOW Gm 0 C 0 0 0 0 0 0 9 9-4 F1 12-141A RWCU F14M 0 0 0 0 0 0 10 94 F1-12-1419 RWU FtN 01H 0 0 DEG F 447 488 S13 483 456 467 400 403 11 9-4 2-16SA RX COOLANT TD@ RX COOLANT TEMP DEG F 447 488 513 .83 456 4E7 400 46J 12 9-4 2-165B RECIRC A LOOF FLOW KGm 0 0 0 0 0 0 0 0 13 9-4 2-1 SEA RECIRC B LOOP FLOW KGM 0 0 0 0 0 0 0 0 14 9-4 2-159B 1 0 0 0 0 0 0 0 0 13 9S 7 46A ArhM/!RM A AMLM/tRM B 0 0 0 0 0 0 0 0 18 9-S 7-468 1 1 0 0 0 0 0 0 0 0 17 9-S 7-46C AFRM/IRM C 7 46D 0 0 0 0 0 0 0 0 18 9-5 APRM / f RM D 1 _ 0 0 0 0 0 0 0 0 19 9S 7-46E AFRM/IRt1 E 3 0 0 0 0 0 0 0 0 20 9-5 7-46F APRM/IRM F 1
'S S 7-43A SRM A CPS 4.27 E+01 2.21E* 01 1.69E+01 1.34E+01 1.2SE*01 1.16F*01 1.16E* 01 1.18E+00 4.24E+01 2.16t+01 1.64E+01 1. 20E+ 01 1. 21 E + 01 1.13E*01 1.11E+01 1.13E+00
(/%) 2221 9-S 7 438 U.Lt B 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 V 23 9-5 7-43C SRM C CFS 24 9-5 ~ 7-43D SRM D CPS 3.40E+01 2.19E+01 1.35E+01 1 21E+05 1.22E+01 1.15E+01 1.13E*01 1.15E+00 . 2-3-93 CCRI r:/.m Ml.8 / HR 1 1 1 1 1 3 2 1 25 9-S PSID 3 3 3 3 3 3 3 26 9-5 2 S-9$ OdKE DP 3 Gh1 35.5 35.5 35.5 45.1 0 0 0 0 27 9-:s #1 3 310 CED FLIM PSIG 702 901 880 916 688 294 290 28 9-5 8 66 WIDE RANGE PRESS 40_9 29 9-S 6-96 NAR RANGE PRESS PSIG 950 950 950 950 950 950 950 950 30 0-5 6 97 FEEDWATER FlfM MLP/HR 0 0 0 0 0 0 0.1 0.1 0-97 MAIN STEAM F1IN K.B/HR 0 0 0 0 0 0 0 0 31 9-b 6-98 INCHES 88 98 115 145 175 164 157 156 32 9-5 NAR RANGE LEVEL _ 33 95 6-98 WIDE RANGE LEVEL INCHIS 86 98 115 145 ITS 164 137 IS6 44 44 44 43 42 42 41 30 _ 34 9-6 Lt 107-5 CST LEVEL I S6 1,4 S4 54 S4 SS SS 34
- 3. 9-6 LI-102-SA BOTWELL LEVEL N I 9- ? LI*102 SB BOTWELL LEVEL 5 1 55 54 S4 53 53 55 55 $4
,36 37 9-7 PI-101-29 CatCENSER VACUUM IN HG 29 8 2 29.9 29.9 29.9 30 30 30 38 9-8 DrG A BKR OPEN OPEN OPfN OPEN OPEN OPEN OPEN OPTN 39 9-8 D/G B BKR OPEN OPLM OPEN OPEN OPEN OFEN OPEN OPEN 40 0-23 16-19-33A/C TORUS TDiP DFG F 139 136 13S 135 133 137 140 139 41 9-25 LI-46A TURUS LEVEL TEIT 0.99 1.03 1.06 1.06 1.11 1,38 1,44 i.34 42 9-25 LI-46B TCROS 1.ZYEL TEET 0.99 1.03 1.06 1.0? 1.11 1 38 1.44 1.54 43 9-25 TR-16-19-44 TokUS PRESS PSIA 18.6 18.2 le 18.1 17.9 20.5 20.6 20.6 44 9-25 TR-16-19-44 DRYWELL PRESS PSIA 18 18 18 18 18 23 23 22 45 9-25 FR-1 156 3 LM/ TORUS LP PSID -0.21 0.2 0.35 0.32 0.49 2. d 2.66 1.54 48 9 25 TR-16-19-45 DRYWELL TEMP DEG F 107 107 107 106 106 154 154 140 47 9-26 PP1-125-3A RX BUILDING EP 1R B20 -0.65 -0.68 -0.Ei -0.68 -0,68 -0.66 -0.68 -0.68 IN 820 -0 68 -0.66 -0,EB -0.68 -0.68 -0.68 4A 9-26 PI-1+125-3B RX BUILDIN'i DP -0.68 -0.68 CIN 1500 1500 1500 1500 1500 1500 1500 1500 49 9-26 FP 1-125-1A SGTS FLOW 1500 1500 1500 1500 1500 1500 1500 1500 50 9 26 F1-1-125-1B SGTS FLOW CFM 31 CAD DW/ TORUS 02 CCNC. 2 2.51 2.51 2.51 2.51 2.$1 2.2 2.18 2.21 g
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i I ( VIRONT YANKEE NUCLEAR POWER STATION Rev,0 IMERGENCY Td.SPONSE PREFAREONT.SS EXERFISE 1991 P m 8.0-4 8.0 0FERATIONAL DATA SCENARIO TIME 06:00 06:15 06:30 06:45 07:00 INSTR. CLOCK TIME 07:15 0):30 07:45 13:00 13:15 13:30 ITDt PANEL ID DESCRIPTION 13:45 14:00 14:15 14:30 l' NITS 14:45 1 0-3 FT-23-108-1 B!CI FLCW GlH 0 0 0 2 9-3 F1-10-13DA RIN A FLOW 0 0 0 0 GIH 218 6746 0 3 9-3 6746 6746 6746 F1-10+1398 RER 2 FLOW GtH 6746 6746 6746 4 0-3 215 6874 6883 6238 FI-14-SUA CS A fMW GlH 6836 6830 6838 6638 to 81 123 5 9-3 F1-14-508 C3 8 FLC+i 118 104 10 10 GlH 10 10 6 9-3 PI-16-19 12 DRYWELL PRESS al 123 118 104 to 7 PSIA 22 20 20 10 to 93 20 20 2 ') F1-16-19-12 DR1WELL YkESS PSIA 22 20 20 20 8 9-4 F1-13-91 20 20 20 RCIC F W GIN 0 20 20 20 9 9-4 0 0 0 F1-12-141A RWCU FLOW 0 0 0 GIH 0 0 0 10 9-4 0 0 71-12-1418 RWCU FliW GTH 0 0 0 0 0 11 9-4' 2-16 5A EX COOLANT TEMP 0 0 0 0 0 0 0 DEG F 363 288 12 9-4 2 1657 251 243 242 251 RX COOLANT TDff DEG F 363 266 251 251 13 9-4 2-159A 251 243 242 RIC1RC A LCOP FLCW KGlH 0 2*1 251 251 14 9-4 0 0 2-1598 RICIRC B LOOP FLOW EGIH 0 0 0 0 0 0 0 0 15 9-5 7-46A AFRM/1RM A 0 0 0 0 1 0 0 0 16 9-5 7-46B AFRM/!RM B 0 0 0 0 0 t 0 0 0 0 17 93 7-46C AN4/IR*1 C 0 0 0 0 0 1 0 0 1R 9-5 7 46D D 0 0 AP5N/IRM D 1 0 0 0 0 19 9-5 0 0 0 7 46E AIT11/1RH E 0 0 0 0 1 0 0 20 9-5 7-46F 0 0 0 AFRM/1RM F 1 0 0 0 0 {} 21 g ? 22 9*5 9-5 7-43A 7-43B SRM A CPS 0 0 0 0 0 0 0 SRM B
2 3 9-5 7-43C CPS 1.10E+01 1.07E*01 1.07E+01 1.06E+01 1.06E*01 1.21Et01 1.21E+01 1.
24 0- 5 7-43D SRH C CF3 1.06E+01 1.03E+01 1.03E+01 1.02E+01 1.02r+01 1.17E+01 1.17E+01 1.1 SRM D 25 9-5 2-3-95 CPS 1.04E+01 1. 05E+01 1.04E+01 1.04E+01 1.04EG1 1.16E+01 1.18E*01 1 CORE FLOW _ MLDi"A 1.07E+01 2 1.0 g 1_1.04E+01 1.04E+01 1.04E+01 1.16E+01 1.18E*01 1.18t+01 1 _ 26 9-5 2-3-95 CORE DP PSTD 1 2 0 1 1 3 3 1 27 9-5 3 FI-3-310 CRD FLOW GEH 3 3 3 3 3 24 0 0 0-5 6-WB WTDE RANGE PRESS 0 0 0 0 PSIO 97 37 0 0 29 9-5 6-96 21 19 19 RAR RAN^.E PRESS FSIG 43 43 43 950 30 9-5 6-97 950 950 950 FEEDWATER FLOW 950 950 950 MLB/HR 0.5 0 0 950 31 9-5 6-97 MAIN STEAM FLOW 0 0 0 0 32 9-5 K.8/ER 0.2 0.1 0 0 6-98 NAR RANGE LEYEL 0 0 0 0 INCf1ES 156 157 0 33 9-5 6-98 168 190 205 WIDE RANGi; LEVEL INCHIS 198 196 196 34 9-6 156 157 168 L1-107-5 Cst LEVEL 190 205 196 196 1 40 36 38 196 35 9-6 L1-102-5A liOTWILL LEVEL N 37 36 36 36 I 53 34 SS 36 9-6 L!-102-58 54 54 54 HOTWELL LEY.L 3 1 54 54 54 37 53 54 54 e-7 F1-101-29 $4 54 54 00tCDSER V 4UUM IN DG 29.9 30 54 54 38 9-8 30 30 30 DIG A BER CP'N 30 30 30 39 9-8 OPEW OFFN OPEN D/G S BKR OPEN OPEN OPEN OPEN OFEN OPEh 40 0-23 OFEN OFD OPEN
'6-10-33A/C TORUS TDiP CEG F 138 OPEN Oe'EN CPEN 41 9-25 L1-46A 138 134 130 127 TORUS LEVEL 123 123 123 42 9-25 L1-46B FEET 1.39 1.24 1.18 1 14 TORUS LEVEL FEE't 1.14 1.16 1.16 43 9-25 1,39 1.24 1.18 1.14 1.16 TR*16-19-44 TOGUS FRISS 1.14 1,1ci 1.16 FSIA 20.8 20.6 1.16
,1 9-25 TR-16-19-44 tRYWE'.L PRESS FSIA 20 19.5 19.1 .18.1 18.7
'> 9-25 22 20 20 20 16.7 PR*1-156 3 DW/ TORUS DF 20 20 20 FSID 1,66 _
,1 9-25 TR- 16-19-4 5 DRYWELL T&tP DEG F
-0.34 0.1 _ 0.47 1.02 1,58 1.58 20 _
149 136 137
.56 Al P26 FI-1-125-3A RX BJILDING DF 135 137 139 IN E20 -0.66 139 139
>5 e 26 -0.68 *0.68 -0.68 -0.68
PT-1-125-3B RX BUILDINO *P IN B20 -0.68 -0.68
-0.68 -0.68 -0.68 9-26 FI-1-125-1A SGTS ILOW -0.68 -0.61 -0.66 -0.68 50 CIH 1500 1500 1500
-0.68 -0.68 0-26 FI-1-125-1B SCTS FLOW 1500 1500 1500 CIH 1500 1500 1500 1500
, 51 CAD 1500 1500 1500 DW/ TORUS O2 CONC. 1500 1500 1506 I 2.22 2.35 1,38 2.39 2.39 2.39 2.39
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_ . - . . - - . . - - -. - . .n . . - ~ -- . - . - - . .. VEReff YANKEE trJC1. EAR PCWER STATION Rev, 0 DtERGENCY RESPONSE 1%EPAREDMESS EXERCISE Pe8e 8.0*5 1991 ( .0 OPERATIONAL DATA SCENARIO TIME 08:00 08:15 08r30 INSTR. CLOCF TIME 15:00 15:15 15:50 ITIN PANIL ID DESCRIPTION 1AtITS 1 93 FT-23-108-1 EPCI F14W G1H 0 0 0 2 9-3 FI-10-139A RER A FLCW OtH 6746 6746 5746 3 9-3 FI-10-1398 RER 5 FLOW CIH 6838 6638 6838 4 0-3 F1-14*50A CS 4 FLOW CM 10 10 10 5 9+3 FI-14-BOB- CS B FLOW GIH 10 10 10 6 9 PI 19- 12 DRYWELL PE.ESr PSIA 20 20 20 7 9-3 F1-16 10-12 DRYWELL PRESS PSIA 20 20 10 8 9-4 F1 13-91 RCIC FLOW CM 0 0 0 9 9-4 FI+12-141A RiCU FLOW Om 0 0 0 , 10 9-4 FI-12 1413 RWCU FIDW GPM 0 0 0 l 11 9-4 2-165A RX COOLANT TDW DEG F 251 251 251 12 9-4 2-1658 RX COOLANT TEMP DFG F 251 251 251 13 9-4 2-159A RECIRC A LOOP FLOW EGlH 0 0 0 la 9-4 2 159P RECIRC B LOOP FLOW KOM 0 0 0 15 9-5 7 46A APRH/IRM A 1 0 0 0 18 9*5 7-469 APRM/IRM B 1 0 0 0 17 9-5 7-46C APRM/IM C 1 0 0 0 18 95 7-4ED AFRM/TRH D I 0 0 0 19 9-5 7-46E APRH/2RH E I- 0 0 0 0-5 7-46F APRM/TRM F T C 0 0 20 9-5 7-43A 1.21E+01 1.21E+01 1.21E+01 (v 21- SRM A CPS 22 0-5 7-43B SRM B CPS 1.17E*01 1.17E+0i 1.177+01 23 3 7-43C SRH C CPS. 1.18E+01 1.18E+01 1.142+01 24 0 7-43D LM D CPS 1.18E*01 1.1AE+01 1.18E*01 25 9-5 2-3-95 CORE FLOW MLB/HR. 1- 1 1 26 9-5 2-3-95 CORE DP PSID 3 3 3 27 9-5 F1-3-312 CRD FLLM G1H 0 0 0 28 9-5 6-96 WTDE RAN'It PRESS PSIG .3 43 43 29 9-5 6-95 RAR RANGE PRESS PSIG 950 950 940 30 9-5 6-97 FEIDWATER FLOW MLB/HR 0 0 0 31 9-5 6-97 MAIN STEAM FLOW MLB/BR 0 0 0 32 9-5 INCRES 196 196 196 6-99 ___ NAR RAwGE LEVEL 33 0-5 5-98 WIDE RANGE LEVLL INCHES 196 196 196 34 9-6 LI-107-5 CST LEVEL 2 36 36 36 9-6 L1-102*5A - B01MLLL LEVEL N 3 54 54 54 35-36 9d LI-102- 59 UOTWELL LFVIL S T 54 54 54 37 . 9-7 PI-101-29 CONDENSER MCUUH IN BG 30 30 30 38 9-8 D/G A BKR OPE 18 OPEN OPEN 39 9-8 D/G B BKR- 0 FEN OPEN OPEN 40 9 23 16-10-33A/C TORUS TEMP DEG F 123 123 123 41 9-25 LI-46A TORUS LEVEL FEET 3.16 1.16 1,16 4 9-25 L1-ess TORUS LEvZL FEIT 1.16 1.16 1.16 43 9-25 TR-16-19-44 TORUS PRESS PSIA 18.7 18.7 18.7 44 9-25 TR-16-19-44 DRYWrLL PRESS PSIA 20 20 20 45 9-25 PR-1-156-3 DW/ TORUS DP PSID 1.58 1.58 1.58 46 9-25 TR-16-19-45 DRTWELL TEMP DEG F 139 139 130
~ 47 9-26 FI-1*125*3A RX BUILDING DP in R20 -0.68 -0.68 - -0.68 IN 820 -0,68 -0,68 -0.68 5 g .
48- 9-28 P!-1-125-38 RX' BUILDING DD i 49 9-26 FI-1-1251A SGTS FLOW CFH 1500 1500 1500 1 50 9-26 F1-1-125-1B SGTS FLOW C1H 1500 1500 1500 , 51 CAD DW/ TORUS 02 CONC. 2 2.30 2.39 2,39
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<1 41 41 <1 <1 <1 <1 <1 RMS !!-1 9-11 R8/252 RX SLDG HI RADS - N R/MR
<1 <1 <1 <1 <1 <1 41 <1 RMS 11-2 9-11 R8/252 RX BLDG M1 RADS - S R/NR
<1 41 41 <1 <1 41 <1 <1 RMS 11-3 9-11 R8/252 TIP RM Mt R AD R/MR SUPP CAAM8 58 EXT CW 8 8 8 8 8 8 8 8 1 9-11 R8/232 MR/NR 9-11 N rERS0ktiEL EX ELDG MR/NR 4 4 4 4 4 4 4 4 2 RB/252 3 9-11 RB/252 S EcutP RR RX BtDG MP/NR 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 4 9-11 99/252 Rx BLD kEUTRON TIP MR/MR 5 5 5 5 5 5 5 5 9-11 R8/252 PERSONNEL MATCH RX B MR/MG 560 570 5 70 570 560 550 530 510 5
7 7 7 7 7 7 7 7 6 9-11 RB/280 ELEV ENTR 280TT RX MR/NR ' 12 12 12 12 12 12 11 11 7 9-11 RS/252 CR0 REPATR RX BLDG MR/NR 4 4 4 4 4 4 4 4 8 9-11 R8/303 ELEY ENTR 303FT RX MR/hR 4 4 4 4 4 4 4 4 l 9 9-11 R8/303 N20 CLEANUP RX 8tDG MR/MR 7 7 7 7 7 7 7 7 10 9-11 R8/315 ELEV ENTR 312FT RX MR/HR S $ 5 5 5 5 5 4 11 9-11 R8/318 N20 CLEANUP RX 8tDG MR/MR 9-11 Ra/345 ELEV ENTR 348FT RX MR/MR 5 5 5 5 5 5 4 4 12 14 9-11 R8/345 WEST REFUFL Rr BLDG Me/NR 5 5 5 5 5 5 5 5 , 15 9-11 RB/345 SPENT FUEL POC4. RX MR/MR 16 16 1T 16 16 16 16 16 16 9-11 R8/318 NEW FUEL VAULT tr 8 MR/MR 0.48 0.48 0.48 0.48 0.48 0.47 0.47 0.46 1 1 1 1 1 1 1 17 9-11 RW/252 PUMP RM RADWASTE BL MR/NR 1 1 1 1 1 1 1 18 9-11 RV/252 RADW OPER AREA RW 8 MR/kR 1 1 19 9 11 RW/230 PUMP / TANK AREA RW 8 MR/MR 2 2 2 2 2 2 2 2 2' 9-11 TB/248 N ACCESS 248FT TURB MR/NR 2 2 2 2 2 2 2 2 9-11 200 200 200 200 195 190 180 180 21 18/248 MAIN STM VALVE TUR8 MR/MR 22 9-11 78/232 COND DEMIN TUR8 8tD MR/MR 0.3 0.3 0.3 0.3 ') . 3 0.3 0.3 0.3 l 23 9-11 TB/252 DECON/MACN SMOP TS MR/NR 0.2 0.2 0.2 0.2 0.2 0.2 0.2 0.2 24 9-11 TB/272 TURS STM 8 TUR8 BL MR/HR 9 9 9 9 9 9 9 9 25 9-11 AB/272 VIEW GALLI <Y CONT RM Mp/NR 0.8 0.8 0.8 0.8 0.8 0.8 0.8 0.7 26 9-11 78/252 REAR GATE TUR8 WAREN MR/>R 0.17 0.17 0.17 0.17 0.16 0.16 0.15 0.15 13 9-11 T8/228 MOIST SEP AREA TURS MR/MR 150 150 150 150 150 140 140 130
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V .V' VERMONT YANKEE MUCLEAR POWER STATION Rev. 0 EMLRGENCY RESPONSE PREPAREDMESS EXERCISE Page 9.1-2 1991 9.1 AREA RADIATIN MONITORS SCENARIO TIME 2:00 2:15 2:30 2:45 3:00 3:15 3:30 3:45 CLOCK TIMF 9:00 9:15 9:30 9:45 10:00 10:15 10:30 10:45 ARM No. PANEL GLDG/EL*! DESCRIPTION tmITS
<1 <1 <1 <1 <1 <1 <1 <1 RMS 11-1 9-11 PS/252 RX BLDG HI RADS + N R/HR -
41 <1 <1 <1 41 <1 <1 <1 Rats 11 2 9-11 R8/252 RX BLOG HI iADS - S R/HR
<1 <1 <1 <1 <1 <1 <1 <1 RMS 11-3 9-11 RS/252 TIP RM Mt RAD R/3R SUPP chasm hs EXT Cu MP/wp 8 8 8 8 8 8 10 100 1 9-11 R8/232 4 4 4 4 3 4 6 6 2 9-11 R8/252 N PERSONNEL RX BLDG MR/HR 3 9-11 R8/252 S EQUIP RR RX BLOG MR/FR 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 5 5 5 5 5 5 5 5 4 9-11 kB/252 RX BLD NEUTRON TIP MR/HR 9-11 ?ERSONNEL RATCM RX 8 MR/NR 500 480 460 440 430 $10 720 830 5 Rs/252 7 7 7 7 7 7 5 5 6 9-11 RS/280 ELEY ENTR 280FT RX 5 MR/HR 7 9-11 R8/252 CRD REPA1R RX BLDG MR/MR 11 11 10 to 10 11 14 16 8 9-11 E8/303 ELEY EETR 303FT RX a MR/MR 4 4 3 3 3 4 5 5 9 9-11 MR/HR 4 4 4 4 4 4 5 5 RB/303 M20 CLEAMUP RX BLDG 9-11 ELEY ENTR 318FT RX B 6 6 6 6 6 7 8 9 10 R8/318 MR/RR 11 9-11 RB/318 M20 CLEMJP RX BtDG MR/HR 4 4 4 4 4 4 2 3 12 9-11 RB/345 ELEV ENTR 348FT RX B PR/HR 4 4 4 4 4 4 6 6 4 4 4 4 4 5 6 7 14 9-11 RB/345 WEST REFUEL RX BLDG MR/MR 15 15 15 15 14 16 19 20 15 9 11 R8/345- SPENT FUEL POOL RX 8 MR/MR 16 9-11 R8/318 NEW FUEL VAULT RX B MR/MR 0.46 0.46 0.45 0.45 0.44 0.46 0.52 0.4 1 1 1 1 1 1 17 9-11 RW/252 PLMP RM RADWASTE BLD MR/HR 1 1 1 1 1 1 1 1 1 18 9-11 RV/252 RADW OPER AREA RW 8 MR/HR 1 9-11 RW/230 PUMP /TANC AREA RW 8 MP/PR 2 2 2 2 2 2 2 2 19 9-11 18/248 N ACCESS 248Ff Tuts' MR/NR 2 2 2 2 2 2 i 1 20 170 170 160 160 150 170 4 4 21 9-11 T8/248 MAIN STM VALVE TURS MR/MR 9 11 T6/232 CONO DEMIN TURB BLDr- MR/PR 0.2 0.2 0.2 0.2 CT 0.2 0.1 0.1 22 23 9-11 78/252 DECONTAM. TUR8 BLDG MR/HR 0.2 0.2 0.2 0.2 0.2 0.2 0.2 0.2 i 9-11 TURS SIM IN TURB SLD MRIER 9 8 8 8 8 9 7 7 ;
24 TB/272
- 25 9-11 AS/272 VIEW GALLERT CCMT RM MR/MR 0.7 0.7 0.7 0.7 0.6 0.7 0.1 0.1 9-11 18/252 REAR GATE TUr8 WAREN MR/HR 0.14 0.14 0.i' O.13 0.13 0.15 0.01 0.01 i 26 13 9-11 TB/228 MolST SEP AREA TUR8 MR/PR 130 120 120 110 110 130 1 1 m .- _ _ _ _ . _ _ _ _ _ ~ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _
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3 9-11 R8/252 S EQUIP RR R2 .b y MR/NR 0.3 0.4 0.4 0.4 0.4 0.4 0.4 0.4 4 9-11 RX SLD WEUTRON 'Il 6 6 6 6 6 6 6 6 R8/252 MR/MR 880 1100 1200 1300 OsM (>1E4) OSN Osu Osu 5 9-11 R8/252 PERSONNEL MATCH RX 8 MR/NR ELEV ENTR 2807i RX 8 5 5 5 5 5 5 5 5 6 9-11 R8/280 MR/NR 17 19 22 22 22 23 24 24 7 9-11 -88/252 CfD REPAIR RX BLf>G MR/NR 9-11 ELEV ENTR 303FT EX B 6 7 7 8 7 8 8 8 8 R8/303 MR/MR 9 9-11 R8/303 M20 CLEANUF RW SLDG MR/HR 5 5 5 5 5 5 5 5 9 to 11 11 11 12 12 12 10 9-11 K5/318 ELEY ENTR 318FT RX 8 MR/HR 9-11 N20 CLEAMUP RX SLDG 3 3 3 3 3 3 3 3 11 R8/318 MR/MR ELEV Euft 3487T RX 8 7 8 9 9 9 9 10 10 12 9-11 R8/345 MR/MR 14 9-11 28/345 WEST REF'EL RX BLDG PR/HR 7 8 9 9 9 10 to 10 15 9-11 F8/345 ' SPENT FJEL POOL RX S MR/NR 21 24 26 27 26 28 28 29 9-11 R8/318 NEW FUEL VAULT RX 8 MR/WR 0.56 0.6 0.64 0.65 0.64 0.67 0.67 0.68 16 1 1 1 1 1 1 17 9-11 RW/252 PLMP RM RADWASTE BLD MR/MR 1 1 1 1 1 1 1 1 18 9-11 RW/252 RADW OrER AREA RW 8 are/NR 1 1 19 9-11 RW/230 PLMP/TANIC AREA RW 8 MR/HR 2 2 2 2 2 2 2 2 1 1 1 1 1 1 1 20 9-11 T8/248 ' N ACCESS 248FT TL98 MR/MR 1 4 4 4 4 4 4 4 4 21 9-11 T8/248 MAIN STM VALVE TURE MR/NR 22 9-11 T8/232 COND DEN!N TUR8 SiDG MR/NR 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 23 9-11 T8/252 DECON/ MACH SHOP T8 MR/hR 0.2 0.2 0.2 0.2 0.2 0.2 0.2 0.2 9-11 TL98 STM IN TUR8 BLD M/MR 7 7 7 7 7 7 7 7 24 T8/272 25 9-11 A8/272 VIEW GALLERT CONT RM MR/MR 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 26 9-11 78/252 RE AR GATE TUR8 WAREN MR/kR 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 1 1 1 1 13 9-11 .TB/228 MOIST SEP AREA TURB MR/HR 1 1 1 1 OSM= OFFSCALE NIGN I e l i
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$00 500 500 500 CPM 9-2 R8/280 CONTAI M NT MON GAS 25000 24000 13000 22000 CPM 25000 25000 25000 25000 9-2 R8/280 CONTAIN>!ENT se0N-PART 0.1 0.1 0.1 0.1 MR/NR 0.1 0.1 0.1 0.1 9-2 R8/200 STACK HI RANGE 4 4 4 4 3 3 R/NR 4 4 27 9-2 DV!252 DRTWELL CH A 4 4 3 3 4 4 4 4 DV/252 DRivtLL CH s R/NR 28 9-2 190 190 190 180 CPM 190 190 1M 190 9-? R8/280 RW ELDC VENT CAS 1520 tito 1480 1450 CPse 1530 1540 1540 1530 9-2 R8/2SO RX BLDG VE9T - PART 2 2 2 2 2 2 2 2 MP/NR 31 9-10_ R8/2SC RX stDC V S T NORTH 2 2 2 2 2 2 2 MR/MR 2 32 9-10 Rs/280 RX BLOG YENT SOUTH 17 17 16 16 17 17 17 17 MR/NR 453A 9-10 R8/345 SPENT RKL POOL A 17 17 16 16 17 17 17 17 MR/NR 4538 9-10 R8/345 SPENT RiL POOL 5 160 160 150 150 170 170 170 170 MR/MR 9-10 R8/256 MAtw STM LINE A 160 160 150 150 170 170 170 170 MR/MR 9-10 R8/256 MAIN STM LINE B 160 160 160 150 i 170 170 170 170 MR/NR 9-10 RB/256 MA!N SiM LINE C 1M 160 150 150 170 170 17D 170 MR/PR 9-10 R8/256 MAtu STM LINE D 250 240 240 240 250 250 250 250 MR/FS 38 9-10 18/248 SJAE( AIR EJECTOR)
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*MC#GENCY RESPONSE 81EPAREDNESS EXERCISE PAGE 1P.2-2 1991 ,
9.2 PROCESS MONITORS SCEWARIO TIME 2:00- 2:15 2:30 2:45 3:00 3:15 3:30' 3:45 CLOCK TIME 9:00 9:15 9:30 9:45 10:00 10:15 10:30 10:45
' ARM NO. PANEL SLDG/ELV DESCMIPTION LNIITS
'9-2. ST/257 STACK GAS MON-GAS 1 CPM 150 150 150 150 150 150 150 150 -- 'l 9-2 ST/257- STACK GAS MON-GAS 2 CPM 200 200 200 200 200 200 200 200 -]
9-2 RS/280 CONTAINNENT MON GAS CPM 460 440 430 400 400 460 42C90- 39000 , 92 Rs/280 CONYAleNIENT MON-PART CPd 0 20n00 20000 19000 18000 21000 39000 35000 9-2 Rs/280 STACK N1 RANGE M/NR 0.1 0.1 0.1 - 0.1 0.1 0.1 0.1 0.1 27 9-2 DW/252 DRYWLL CM A R/NR 3 3 3 3 3 3 6 5 25 9-2 DW'252 DRTWELL CM 3 E/Pt 3 3 3 3 3 3 6 5 170 170 180 60 73 i 9-2 kB/280 RK stDG VENT GAS CPM '190 180 170 i 9-2 Rs/280 Rx etDG VENT - PART CPM 1430 1400 1380 1350 1320 1440 490 540 31 '9-10 F1/280 RK SLDG VENT NORTN MR/NR 2 2 2 2 2 2 1 1 32 .9-10 R8/280 RX SLDG WNT SOUTH MR/NR 2 2 2 2 2 2 1 1 a 16 10 11 4 453A 9-10' RS/345 SPENT FUEL POOL A M/wR 16 15 15 15 14 4538 9-10 RS/545- SPENT FUEL POOL. 5 M/NR 16 15 15 15 14 16 10 11 9-10 RS/256 MIN STM LINE A M/NR 140 140 130 130 120 _ 130 0 0 - 9-10 'RS/256 ' MAIN STM LINE 8 M/NR 140 140 130 130 120 130 0 0 j 9-10 R8/256 MAIN STM LINE C M/NR 140 140 130 130 12G 130 0 0 ; 9-10' RS/256 MAIN STM LINE D MR/NR 140 140 130 130 120 130 0 0 i 38 9-10 T5/248 SJAE(A!R EJECTOR) M/NR 240 230 230 220 220 200 0 0
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1991 r 9.2 PROCESS MONITORS SCENARIO TIME 4:M 4:15 4:30 4:45 5:00 5:15 5*30 5:45 CLOCK TIME 11:00 11:15 11:30 11:45 12:00 12:15 12:30 12:45 ARM NO. PANEL BLDG /ELY DESCt!PTIota UNITS 9-2 ST/Z57 STACK GAS Mou-GAS 1- CPM' 15G '150 150 150 150 -150 150 150 ; 200 200 200 200 200 200 200 200 9-2 ST/257 STACK GAS MON-GAS 2 CPet 36000 33000 3iOOO 29000 0$"t>1ES) OSN' OSM 054 9-2 Rs/280 CouTAlamENT MON GAS CPM 4300G 51000 57000 53000 OSn(*1t6) OSn Osw - OSn 9-2 29/280 CONTAIMMFmT MON-PAR! CPW 0-2 as/280 : STACK HI ammGE MR/MR . 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 - f 6 7 8 8 8 20000 20000 10000 j 27 v-2 DW/252 DRYWELL CM A a/Ha t/na . 6 7 8 8 8 20000- 20000 18000
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O O O
. TABLE 9.3-1 Rev. O Page 9.3-la Reactor Building Refuel Deck, Elevation 345' (nR/hr unless otherwise.noted)
Clock Scenario Time Time- ARH 12 ARM 14 ARM 15 453 A 453 B Zone I Zone II Zone III Zone IV 0700 0: 00 5 5 1G 17 17 5 17 17 17 0800 1:00 5 5 16 17 17 5 17 17 16 0900 2:00 4 4 15 16 16 4 16 16 16 1000 3:00 '4 4 14 .14 14 4 14 14 15 1015 3:15 4 5- '16 16 16 4 16 16- 15 1030 3:30 6 6 19 10 10 6 10 10 15 1045 3:45 6 7 20. 11 11 6 11 11 15 1100 4:00 7 7 21 11 11 7 11 11 15 1113 4:15 8 8 24- 13 13 8 13 13 15 1130 4:30 9 9 26 14 14 9 14 14 15 1145 4: 45 9 9 27 15 15 9 15 15 15 1200 5:00 9 9 26 14 14 9 14 14 15 1215 5:15 9 10 28 15 15 9 15 15 15 1230 5:30 10 10 28 16 16 10 16 16 15 1245 5: 45 10 10 29 16 -16 10 16 16 15 6:00 2E5 f0SH)>1E4(OSH)>1E(OSH)>1E4 2E5 2E5 2E5 2E5 1300 (OSH)>1E4 1315 6:15 '(OSH) 4E5 (OSH) (OSH) (OSH) 4E5 4E5 4E5 4E5 1330 6:30 (OSH) 4E5 (OSH) (OSH) (OSH) 4E5 4E5 4E5 4E5 1345 6:45 4E5' (OSH) (OSH) -(OSH) 4E5 4E5 4E5 4E5 (OSH) 1400 7:00 (OSH) 4E5 (OSH) '(OSH) (OSH) 4E5 4E5 4E5 4E5 1415 7:15 (OSH) 4E5 (OSH) (OSH) (OSH) 4E5 4E5 4E5 4E5 1430 7:30 (OSF) 4E5 (OSH) (OSH) (OSH) 4E5 4E5 4E5 4E5 1445 7:45 (OSH) 3E5 (OSH) (OSH) (OSH) 3E5 3E5 3E5 3E5 1500 G:00 (OSH) 3E5 (OSH) (OSH) (OSH) 3E5 3E5 3E5' 3 ES ' i 1515 8:15 (OSH) 325 (OSH) (OSH) (OSM) 3E5 3E5 3E5 3E5
.1530 8:30 (OSH) 2E5 (OSH) (OSH) (OSH) 2E5 2E5 2E5 2E5 Notes: Zone readings are average dose rates throughout zene.
General area contamination levels 2K-5K dpm/100 cm2 in al] zones before 1300. General area contamination levels 20K-50K dpm/100 cm2 in all zones after 1300. (OSH) OFF SCALE HIGH
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t TABLE 9.3-2 Rev. O Reactor Building, Elevation 318' Page 9.3-2a (mR/hr unless otherwise noted) Clock 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 0800 1:00 7 5 .5 7 5 300 5 80 .5 .5 0900 2:00 6 4 .5 6 4 300 4 80 .5 .5 1000 3:00 6 4 .5 6 4 200 4 80 .5 .5 1015 3:15 7 4 .5 7 4 200 4 80 .5 .5 1030 3:30 8 2 .5 8 2 200 2 80 .5 .5' 1045 3:45 9 3 .5 9 3 200 3 80 .5 .5 1100 4:00 9 3 .5 9 3 200 3 80 .5 .5 1115 4:15 10 3 .5 10 3 200 3 80 .5 .5
- 1130 4:30 11 3 .5 11 3 100 3 60 .5 .5 1145 4:45 11 3 .5 11 3 100 3 60 .5 .5 1200 5:00 11 3 1 11 3 100 3 60 1 1
, 1215 5:15 12 3 1 12 3 100 3 60 1 1 1230 5:30 12 3 1 12 3 100 3 60 1 1 1245 5:45 12 3 1 12 3 100 3 60 1 1 6:00 SES SES SES 5ES 555 SES SES 1300 (OSH)>1E4 (OSH)>1E4(OSH)>1E2 1E6 1315 6:15 (OSH) (OSH) (OSH) 1E6 1E6 1E6 1E6 1E6 1E6 1330 6:30 (OSH) (OSH) (OSH) 1E6 1E6 1E6 1E6 1E6 1E6 1E6 [ 1345 6:45 (OSH) (OSH) (OSH) 1E6 1E6 1E6 1E6 1E6 1E6 1E6 1400 7:00 (OSH) (OSH) (OSH) 1E6 1E6 1E6 1E6 IE6 1E6 .1E6 1415 7:15 (OSH) (OSH) (OSH) 1E6 1E6 IE6 1E6 1E6 1E6 1E6 . 1430 7:30 (OSH) (OSH) (OSH) 1E6 1E6 1E6 1E6 1E6 1E6 1E6 ; 1445 7:45 (OSH) (OSH) (OSH) 7.5ES 7.5E5 7.5E5 7.5E5 7.5E5 7.5ES 7.5ES 1500 S:00 (OSH) (OSH) (OSH) 7.5ES 7.5ES 7.5ES 7.5E5 7.5ES 7.5ES 7.5ES 1515 8:30 (OSH) (OSH) (OSH) 7.5ES 7.5ES 7.5E5 7.5ES 7.5ES 7.5ES 7.5ES 1530 8:45 (OSH) (OSH) SES SES SE5 SES SE5 SES SES : (OSH) r Uctes: Zone readings are average dose rates throughout-zone. General area ' contamination levels 1K-5K dpm/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
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0 .L/ f3 (" V -( TABLE 9.3-3 Rev. O Reactor Building, Elevation 303' Page 9.3-3a (mR/hr unless otherwise noted) Clock Scenario Time Tine ARM 8 ARM 9 Zone I Zone II Zone III Zone IV Zone V Zone VI Zone VII 0700 0:00 4 4 4 3 600 3 60 0.1 0.2 0800 1:00 4 ;4 4 3 600 3 60 0.1 0.2 0900 2:00 4 4 4 3 600 3 60 0.1 0.2 3 4 4 3 600 3 60 0.1 0.2 1000 3:00. 1015 3:15 4 4 4 3 600 3 60 0.1 0.2 1030 3:30 5 5 5 3 600 3 60 0.1 0.2 1045 3:45 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 3 600 3 60 0.1 0.2 1130 4:30 7 5 5 3 800 3 80 0.1 0.2 1145 4:45 8 5 5 3 800 3 80 0.1 0.2 1200 5: 00 7 5 5 3 800 3 80 0.1 0.2 1215 5:15 8 5 5 3 800 3 80 0.1 0.2 1230 5:30 8 5 5 3 800 3 80 0.1 0.2 1245 5:45 8 3 5 3 800 3 80 0.1 0.2 1300 SES SE5 SE5 SES SES SES. SES 6:00 (OSH)>1E4 (OSH)>1E4 1E6 1315 6:15 (OSH) (OSH) 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 1E6 1E6 1E6 1E6 1400 7:00 (OSH) (OSH) 1E6 IE6 1E6 1E6 1E6 1E6 .1E6 1415 7:15 (OSH) (OSH) 1E6 1E6 1E6 1E6 1E6 1E6 . !M5 1430 7:30 (OSH) (OSH) 1E6 1E6 1EG 1E6 1E6 1E6 1E6 1445 7:45 (OSH) (OSH) 7.5E5 7.5ES 7.5E5 7.5E5 7.5ES 7.5US 7.5E5 1500 8:00 (OSH) (OSH) 7.5ES 7.5E5 7.5E5 7.5ES 7.5E5 7.5ES 7.5ES 1515 8:15 (OSH) (OSH) 7.5E5 7.5E5 7.5ES 7.5E5 7.5ES 7.5ES 7.5E5 1530 8:30 (OSH) (OSH) SE5 SES SES SES 5E5 SES SES Notes: Zone readings are average dose rates throughout zone. General area contccination levels 1K-5K dpm/100 cn2 in all zones before 1300. General area contamination levels 50K-120K dpm/100 cm2 in all zones after 1300. (OSH) OFF SCALE.HIGH
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.Page 9.3-4a Reactor Building, Elevation 280' (mR/hr unless otherwise noted)
RB Vent RB Vent Clock Scenario North South Zone Zone Zone Zone Zone Zene Zone Zone Time Time ARM 6 ARM 31 ARM 32 I II III IV V VI VII VIII 0700 0:00 7 2 2 3 25 9 7 3 1 0.7 0.3 0800 1:00 7 2 2 3 20 9 7 3 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 3 20 8 7 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 3 20 8 5 2 1 0.7 0.3 1115 4: 15 5 1 1 3 20 8 5 2 1 0.7 0.3 4 1130 4:30 5 1 1 3 20 8 5 2 1 0.7 0.3 1145 4:45 5 1 1 2 15 6 5 2 1 0.7 0.3 1200 5:00 5 1 1 2 15 6 5 2 1 0.7 0.3 1215 5:15 5 1 1 3 15 7 5 2 1 0.7 0.3 1230 5:30 5 1 1 3 15 7 5 2 1 0.7 0.3 1245 5:45 5 1 1 3 15 8 5 2 1 0.7 0. 3 ' 1300 6:00 (OSH)>1E4 (OSH)>1E3(OSH)>1E3 IE6 1E6 1E6 1E6 1E6 1E6 1E6 1E6 1315 6:15 (OSH) (OSH) (OSH) 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 2EG 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) 2E6 2E6 2E6 2E6 2E6 2E6 2E6 296 - 1445 7:45 (OSH) (OSH) (OSH) 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 3.5E6 1..13 ? 1500 8:00 (OSH) (OSH) (OSH) 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.SE6 1.5E6 1515 8:15 (OSH) (OSH) (OSH) 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1530 8:30 (OSH) (OSH) (OSH) 1E3 1E3 1E3 1E3 1E3 1E3 1E3 1E3 Notes: Zone, readings are average dose rates throughout zone. < 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. (OSH) OFF SCALE HIGH
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O O O 4 ! TABLE 9.3-5 l Rev. 0 ] Reactor Building, Elevation 252' Page 9,3-Se.1 i (mR/hr unless otherwise noted) i 4 l . clock Scenario RM- Zone Zone Zone Zone Zone Zone Zone i Time Time ARN2 ADM3 ARM 4 ARMS ARM 7 14-29 I II III XV V VI VII i 0700 0 4 .. 5 560 12 100 5 4 .3 50 4 12 24
- 0800 1:00 4 .3 5 560 12 100 5 4 .3 50 4 12 24 j 0900 2:00 4 .3 5 500 11 100 0 4 .3 50 4 11 22
.1000 3:00 4 .3 5 430 10 100 5 4 .3 40 4 10 20 1015 3:15 4 .3 5 510 11 100 5 4 .3 50 4 11 22 l 5 6 6 14 28 1030 3:30 6 .3 5 720 14 100 .3 70 1045 3:45 6 .3 5 830 16 100 5 6 .3 80 6 16 32 i 1100 4:00 7 .3 6 840 17 100 6 7 .3 85 7 17 34 1115 4:15 8 .4 6 1100 19 100 6 E ..
110 8 19 38 1130 4:30 9 .4 6 1200 22 100 6 9 .4 120 9 22 42
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1200 5.00 9 .4 6 (OSH)>1E4' 22 100 6 9 .4 120 9 23 42 i 1215 5:15 100 .4 6 (OSH) 23 100 6 100 .4 130 100 23 46
- 1230 5
- 30 100 4 6 (OSH) 24 100 6 100 .4 130 100 24 48 1245 5:45 500 .4 6 (OSH) 24 100 6 500 .4 140 500 24 48 j 1300 6:00 (OSH)>1E4(OSH)>1E4(OSH)>1E4 (OSH) (OSH)>1E4 50G 1E6 1E6 1E6 lE6 AE6 1E6 1E6 l .1315 6:15 (OSH) (OSH) (OSH) (OSH) (OSH) 500 2E6 2E6 2E6 2E6 2E6 2E6 2E6 l 1330 6:30 (OSH) (OSH) (OSH) (OSH) (OSH) 500 2E6 2E6 2E6 266 2E6 2E6 2E6 i 1345 6:45 (OSH) (OSH) (OSH) (OSH) (OSH) 500 2E6 2E6 2E6 2E6 2E6 2E6 2E6 1400 7:00 (OSH)' (OSH) (OSH) (OSH) (OSH) 500 2E6 2E6 2E6 2E6 2E6 2E6 2E6 1415 7:35 (OSH) (OSH) (OSH) (OSH) (OSH) 500 2E6 2E6 2E6 2E6 2E6 2E6 2E6 4 1430 7:30 (OSH) (OSH) (OSH) (OSH) (OSH) 500 2E6 2E6 2E6 2E6 2E6 2E6 2E6 1445 7:45 (OSH,' (OSH) (OSH) (OSH) (OSH) 500 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1.5E6 1500 8:00 (OSH) (OSH) (OSH) (OSH) (OSH) 500 1.5E6 1.5E6 1.5"" 1.5E6 1.5E6 1.5E6 1.5E6 1515 8:15 (OSH) (OSH) (OSH) (OSH) (OSH) 500 1.5E6 1.5E6 3 1.5E6 1.5E6 1.5E6 1.5ES 1530 8:30 (OSH) (OSH) (OSH) (OSH) (OSH) 500 1E6 1E6 it6 1E6 1E6 IE6 1E6 Notes: Zone readings are average dose rates throughout zone.
General area contamination levels IK-2K dpm/100 cn2 in all zones before 1300. General area contamination levels 100K-200K dpm/100 cm2 in all zones after 1300. (OSH) OFF SCALE HIGH
, , . , .m - _ . . - . . . _ . , _ _ . . _ m _ - - , _ _ _ . _ _ . . - _
I-Rev. O Page 9.3-Sa.2
. TABLE 9.3-5 i (Continued)
Clock Scenario NORTH SOUTH TIP , Time Time RMS II-1** RMS II-2** RMS II-3** 0700 0 <1.0 <1.0 0800 1:00 <1.0 <1.0 <1.0 0900 2:00 <1.0 <1.0 <1.0 1000 3:00 <1.0 <1.0 <1.0 j 1015 3:15 <1.0 <1.0 <1.0 1.0 3 0 .3:30 <1.0 <1.0 <1.0 1045 3:45 <1.0 <1.0 <1.0 1100 4:00 <1.0 <1.0 <1.0 1115 4:15 <1.0 <1.0 <1.0 1130 4:30 <1.0 <1.0 <1.0 '; 1145 4:45 <1.0 . <1.0 <1.0 1200 5:00 <1.0 <1.0 <1.0 Q
- ' 1215 5
- 15 <1.0 <1.0 <1.0 1230 5:45 <1.0 -1.0 <1.0 1245 5:45 <1.0 (1.0 <1.0 1300 6:00 1000 1000 1000 1315 6:15 2000 2000 2000 1330 6:30 2000 2000 2000 1345 6:45 2000 2000 2000 1400 7:00 2000 2000 2000 1415 7: 15 2000 2000 2000 1430 7:30 2000 2000 2000 1445 7:45 1500 1500 1500 i 1500 8:00 1500 1500 1500 1 1515 8:15 1500 1500 1500
- 1530 8:30 1000 1000 1000 j Notes:
** RMS II readings in R/hr (high-range accident ARMS - 1 R/hr to 10,000 R/hr) , - r c e , - , , - - . _ _ - - _ _ _ - - - _ - _ _ - - _ _
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- TABLE 9.3-6 Rev. O Turbine Deck, Elevation 272' Page 9.3-6a (mR/hr unless othe. wise noted)
Turbine Deck Clock Scenario CAM (cpm) Tine Time ARM 24 Zone 1 Zone Il Zone III NG Particulate l _ _ _ _ _ _ _ _ - - - - = 1 0700 0:00 9 100 150 9 250 900 l 0800. 1:00 7 75 .120 7 250 '00 1- , 0900 2:00 7 40 60 7 250 300 ? 1000 3:00 7 20 35 7 250 900 1015 3:15 7 20 35 7 250 900 l 7 250 900 t- 1030 3:30 7 16 30 1045 3:45 7 16 22 7 250 900 F 1100 4:00 7 16 22 7 250 900 1115 4:15- 7 11 22 7 250 900 ! 960 1
- 1130 4:30 7 11 22 7 250 i 1145 4:45 7 11 2 7 250 900 j 1200 5:00 7 10 '20 7 250 900 1- 1215 5:15 7 10 20 7 250 900 I 1230 5:30 7 10 20 7 250 900 1245 5:45 7 10 20 7 250 900 i 1300 6:00 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 1D 20 7 250 900 j 1430 7:30 7 10 20 7 250 900 1445 7:45 7 10 20 7 250 900 1
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-----------------------------------------------------------------=-=--------------------
Notes: Zone readings are average dose rates throughout zone. General area contanination levels <1K dpm/100 cm2.
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- 0700 0 150 3 1 50 150 l 3800 1
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- j. 0900 2:00 120 1 1 20 60 2 30 l- 1000 3:00 '
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!- 1130 4:30 1 1 1 5 15 2 7 ! 1145 4:45 1 1 1 5 15 2 7 l 1200 5:00 1 1 1 5 15 2 7 1215 5:15 1 1 1- 5 15 2 7 1230 .5:30 1 1 1 5 15 2 7 ' 1245 5:45 1 1 1 5 15 2 7 1300 6:00 1 ; 1 1 5 15 2 7 1315 6:15 1' 1 1 5 15 2 7 1330 6:30 1 1 1 5 15 2 7 1345 6:45 1 1. 1 5 15 2 7 1400 7:00 l' 1 1 5 15 2 7 . 1415 7:15 1 1 1 5 15 2 7 1430 7:30 1 1 1 5 15 2 7 1445 7:45 1 1 1 5 15 2 7 1500 8:00 1 1 1 5 15 2 7 1515 8:15- 1 1 1 5 15 2 7 1530 8:30 1 1 1 5 15 2 7 ( ---------- _ _= -___ j Notes: Zone readings are average dose rates throughout zone. General area contanination levels <1K dpn/100 cm2. ) t i
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i t S l J i i - VERMONT YANKEE NUCLEAR POWER STATION ; [ EMERGENCY RESPONSE PREPAREDdESS EXERCISE .! i 1991 t . ! f J
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VERMONT YANKEE NUCLEAR P0tTER STATICH ) DIERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4 Elg.{I CHEMISTRY DATA S191}f.'d fA.91 9.4.1 Reactor Coolant Activity Data.. .. . .. ,, . ..... 9.4.1 1 9.4.2 Primary Containnent Air Activity Data . ... . . ... 9.4.7 1 9.4.3 Reactor P>uilding Air Activity Data. .. . . . . . 9.4.3 1 4 k-3 n . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ . _
-- . _ - - - -_.-- - . - . . . _ . = = - - - . . - . - = - - - .
i , a l I . I l l l i e ! I J VERMONT W'KEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE . i 1991 l I t k i i I I i 4 i r a f. 9,4
- VACTOR COOIANT ACTIVITY DATA e
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_ . _ , . . . _ . _ . . _ . - _ . _ . . _ - - - __ ___._..___._._m._.- 1 i Rev. O i Page 9.4.1-1 .l 1 i o VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 l 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations-(uci/ml) Time i 1030-1045 Isotope Prior to 1030 1045-1100-I-131 2.5F-03 6.53E+02 1.31E+03 f I-132 2.8E-33 7.80E+02 1.56E+03 I-133 5.2E-03 1.28E403 2.56E+03 I-134 4.1E-03 8.60E+02- 1.72E+03 ; 1-135 4.5E-03 1.14E+03 2.28E+03 , - 'fotal. Iodine 1.9E-02 4.7E+03 9.4E+03 ; I-131 Dose 4.5E-03 1.1E+03 2.3E+03 Equivalent i Kr-83m 1.2E-03 4.20E+00 8.40E+00 Kr-85m 2.SE-02 2.83E+00 5.63E+00 Kr-85 4.8E-03 1.54E-01 3.03E , Kr-87 2.9E-03 4.00E+00 8.00E+00 3 Kr-88 1.0E-03 6.80E+00 1.36E+01- , Xu-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 1.60E+01 3.20E+01
. Total: Noble 4.8E-02 1.2E+02 2.3E+02-
- Gas t Note: Reactor c0olant sample dose rates are provided in Section 9.5.1 f .
k T 4 d L - .,,, , m _ . -. . .. . . . . . , , , - - . , . , . - - - , - , . . . , . - , _ . . . - - . . . . - - , - , . _
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' dov. O f Page 9.4.1-2 i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE , 1991 9.4.1 REACTOR Co0LANT ACTIVITY DATA ' 4 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 1-132 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 3.44E403 4.3E+03 3.5E+03 3.42E+03 4.56E+03 5.7E+03 5.5E+03 01-135 ....__. -__.... Total Iodine 1.4E+04 1.9E404 2.4E+04 2 . 2 E+(" I-131_ Dose 3.4E+03 4.5E+03 5.7E+03 5.7E+03 Equivalont , Kr-83m 1.26E+01 1.68E+01 2.1E+01 4.5E+01 Kr-85m 8.44"*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 5.6E402 Xe-135 4.80E+01 6.40E+01 8.0E+01 1.8E402 ,
Total Noble 3.5E+02 4.6E+02 5.8E+02 9.8E402 Gas I I Note: Reactor coolant sample dose rates are provided in Section 9.5.1.
. - _ . .~
Rev. O Page 9.4.1-3 VERMOliT YANKEE IlUCLEAR POWER STATION EMERGE!1CY RESPONSE PREPARED! LEES EXERCISE 1991 9.4.1 REACTOR C001.AllT ACTIVITY DATA
. . . ._c ..
A. Reactor coolant Activity concentrationn (ucl/ml) Timo Inotopo 1200-1215 1215-1230 1230-1245 1-131 3.3E+03 3.3E+01 3.3E+03 I-132 3.4E+03 3.1E+03 2.9F+03 I-133 6.3E+03 6.3E+03 6.2E+03 1-134 2.9E+03 2.4E+03 1.9E+03 I-135 5.4E+03 5.3E+03 5.1E+03 Total Indine 2.1E+04 2.0E+04 1.9E+04 I-131 Doao 5.6E+03 5.6E+03 5.5E+03 Equivalent Kr-83m 6.5E+01 8.2E+01 9.5E+01 Kr-85m ?. 3E+01 1.3E+01 1.2E+01 Kr-85 7.4E-01 7.4E-01 7.4E-01 Fr-87 1.5E+01 1.3E+01 1.2E+01 Kr-88 3.0E+01 2 . 9 E + 01, 2.7E+01 Xc-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 Nobic 1.2E<03 1.4E+03 1. 6E+ 0 3 Gas Note: Reactor ceolant sample dose rates are provided in Section 9.5.1
l 1 O Rev. O Page 9.4.1-4 i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXEFCISE 1991 9.4.1 . REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uC1/ml) . Timo Isotopo 1245-1300 1J00-1315 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 6.4Et02 I-135 5.0E+03 4.6E+03 3.9E+03 3.4E+C3 0d Total Iodine 1.9E+04 1.7E+04 1.4E+04 1.2E+04 1-131 Doce 5.SE+03 5.0E+03 4.5E+03 3.9E+03 Equivalent ; Kr-63m 1.1E+02 1.1E+02 1.0E+02 9. 2 E+ 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 3
^
Kr-87 1.0E+01 8.4E+00 6.4E+00 4.9E+00 Kr-88 y 2.5E+01 2.2E+01 1.8E+01 1.5E+01 Xe-133 1.8E+02 1.7E402 1.6E402 1.5E+02 Xe-135m 7.8E+02 7.2E+02 6.2E+02 5.4C+02 Xe-135 5.4E+02 5.9E+02, 5.BE+02 5.7E+02 Total Hoble 1.7E+03 1.6E+03 1.5E+03 1.4E+03 Gas Notes Reactor coolant sampin dose rates are provided in Section 9 5.1. i g-- T- C$+ -- 9 g , 4s-. *rsy *<--p-..yiy ,aw m y ,,w., ,p---.c.i,,,,,.%,-- g.y.w,..,.c --y n , - - , ,,g , , - .,,e.-e ,>--g-.,. ,-p.-,. - r,-----
Roy. 0 l Page 9.4.1-5 i VERMONT YANKEE HUCLEAR PO%ER STATION ( EMERGENCY RESPONSE PREPARIn1ESS EXERCISE , 1991 i 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity 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 I-132 1.3E+03 1.1E+03 3.0E+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 Iodino 1.1E+04 9.5E+03 9.3E+03 9.1E+03 I-131 Dose 3. 4E+ 03 3.2E+03 3.1E+03 3.1E+03 , Equivalent
-s ,
Kr-83m 8.30+01 7.9E+01 7.9E+01 7.9E+01 Kr-85n 6.5E+00 5.0E+00 5.6E+00 5.4E+00 Kr-05 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. 9 E+ 0 0 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 4.0E+02 ' Xe-135 5.5E+02 5. SE4 02 5.9E+02 6.3E+02 Total Noble 1.2E+03 1.2E+03 1,2E+03 1.3E+03 Gas i Reactor coolant sample done rates are provided in Section 9.5.1. Notel g i O-4 y r- ..r ,...,.~..,.,,,,.,,.-,,..c,
. . ~ . _ , -.
_____._.m._.__.._-..___.__.._-__._._ _ . _ _ _ . _ _ . _ _ _ . _ . . . - _ _. _ -.___...._. _ . i Rov. 0 , Page 9.4.1-0 VERMONT '/ANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uci/ml) .. ... ...
. .. m.. ...... ..... . ..... . .
Time - Isotope 1445-1500 1500-1515 1515-1530 *
... ... .. . ....... l I-131 1.9E+03 1.9E+03 1.9E+03 I-132 8.9E402 8.?E+02 7.7E+02 f I-133 3.5E+03 3,4E+03 3.4E403- ',
I-134 2.0E+02 1.6E+02 1.3E+02 I-135 2.4E+03 2.4E+03 2 3E403 ! Total Indina 8.9E+03 8.7E+03 8.5E+03 , I-131 Dose 3.1E+03 3.1E+03 3.1E4-03 Equivalent . I Kr-83m 7.9E+01 7.8E+01 7.6F.+01 - Kr-85m 5 2E+00 5.0E+00 4.8E+00 Kr-85 4.4E-01 4.4E-01 4.4E-01 i Kr 2.1E+00 1.8E+00 1.6E+00 Kr-88. 9.3E+00 8.8E+00 8.2E+00 ', Xe-133 1.4E+02 1.5E+02 1. 5E4 02 Xe-135m 3.9Ev02 3.0E+02 1.7E+02 Xe-135 6.6E+02 7.OE+02 7.3E+02 , b Total Noble' 3.3E+03 1.3E+03 1.3E+03 ; Gas il r. l; o Reactor coolant sampic done rates are provided in Section 9.5.2.
- Note c
- Post 1530 values continua to declino steadily with time.
i I LO i? l h
- c. ~
_._....u.. . _ _ _ . , . . . . . . _,. . _ , . _ . , . , _ . , . . . . - . . . _ - , - ,_ , . _ , .. ,- , . _ . -
O VERMONT YANKEE tWCLEAR PO'.'LR STATION F.MERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 'l 9.4.2 11WALC0liTAlBifl!I_AlfL_64TIVITY D6IA s O s y N s 0
O) ( , Rev. O Page 9.4.2-1 j VERMONT YANKEE NUCLEAR POWER STATION EMERGE 31CY RESPONSE PREPAREDNESS EXERCIsr 1991 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA , 1 A. Primary containment Air Activity concentrationa (uci/cc) Time bS$bSS$ b5.S$bSbbbb bbbb'.b bb. bbbb~.bb!! . bbbb$bbI i I*131
- 9.4E-01 9.4E-01 9.4E-01 1*132
- 9.8E-01 9.1E-01 8.4E 01 I-133
- 1.8E+00- 1.8E+00 1.BE+00 1-134
- 8.3E-01 6.8E-01 5.6E-01 1-135
- 1.6E+00 1.5E+00 1.5E+00 .
. n .. . . . ..
N Total Iodine
- 6.1E+00 5.8E+00 5.6E+00 I-131'Doso
- 1.6E+00 1.6E+00 1.6E+00 Equiva1ent ,
Kr-83m
- 3,9E+01 3.8E+01 3.7E+01 Kr-85m
- 7.6E+01 7.4E+02 7.CE+01 .
Kr-85
- 4.3E+0u 4.3E+00 4.3E+00 Kr-87
- 8.9E+01 7.7E+00 6.7E+01 Kr-88
- 1.7E+02 1.GE+02- 1.SE+02 Xo-133
- 7.6E+02 7.6E+02 7.6E+02 Xe-135"i
- 1.0E+02 9.8E+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 Cas.
i I s l-
-Note: Primary containment sample dose rate provided in Section 9.5.2.
- Prior to 1200 containinent air activity is below MDA.
.O b
Rev. O Page 9.4.2-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 4 9.4.? PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uci/cc) . . . . . . . . . . . . . . Time isotope 1245-1300 1300-1315 1315-1330 1-131 9.4E-01 9.4E-01 9.4E-01 I-132 7.8E+00 7.2E-01 6.7E-01 I-133 1.8Ee00 1.8E+00 1.7E+00 1-134 4.6E-01 3.8E-01 3.1E I-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.BE+01 6.5E+01 6.3E401 Kr-8S 4.3E+00- 4.3E+00 4 . 3 E4 00 - Kr-87' 5.9E+01 5.1E+01 4.5E+01: Kr-88 1.5E+02- 1.4E+02 1.3E+02 Xc-133 7.6E+02 7.6E+02 7.6E+02 Xo-135m 9.2E+01- 9.0E401 8.7E+01
- Xe-135 2.3E+02 2.4E+02 2.4E+02 Total-Noblo 1.4E+03 1.4E+03 1.4E+03 Gas-Note: Primary containment sample dopo rate provided in Section 9.5.2 -
O V-'Y*- f g g 9d+-"yp=3+-e W g y +meq' % g, p r 9r-g p g,-.,3 q,s.e+yg,e79< -+og,e-+y,-gy.mee et , y
l l Hev. 0 1 Page 9.4.2-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISL 1991 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA l I A. Primary Containment Air Activity Concentrations (uci/cc) i Time ' Isotope 1330-1345 1345-1400 1400-1415 1415-1430 I 1-131 9.3E-01 9.3E-01 9.3E-01 9.3E-01 1-132 6.2E-01 5.8E-01 5.3E-01 5.0E-01 1-133 1.7E400 1.7E+00 1.7E+00 1.7E+00-I-134 2.5E-01 2.1E-01 1.7E-01 1.4E-01 ; I-135 1.3E+00 1.3E+00 1.3E+00 1.2E+00 Total Iodino 4.8E+00 4.7E+00 4.6E+00 4.5E400 1-131' Dose' 1.5E+00 1.5E+00 1.5E+00 1.5E+00 Equivalent O Kr-83m 3.2E+01 3.1E+01 3.0E+01 2.9E+01 Kr-85m 6.0E+03 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- 3.4C+01 3.0E+01. :: . 6 E+ 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 4 Xo-135m 8.5E+01 8.3E+01 8.1E+01 7.9E+01
-Xo -13 5 - 2.5E+02 2.5E+02 2.6E+02 2.6E+02 i Total Noble 1.4E+03- 1.3E+03- 1.3E+03 1.3E+03 i
. Gas ,
Note: Primary containment sample dose rato provided in Section 9.5.2. t.
- l. .
l:
.,:,6_m.,iw .,%y., -m. . , . - ,.- %- ,c . . - ,g..,_,, ..-.%.,%sw ,,,,-o,,m., ,,,,,w,. w,,,,#.,,, ,,,,,,,_%,- 9,,,,.y .9, , . ,,._..,-,w.,-.g%w, y-.,n,p.3, im..p,-,7.- ees, i -c.
. , . . . - . . ~ . --- - - - - . . . - - - - . -. .
l l w ^ J
-[
. a' 1 Rev. O l Page 9.4.2-4 j l VERMONT YANKBE NUCLEAR POWER STATION l
- EMERGENCY RESPONSE PREPAREriESS EXERCISE I 1991 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air-A:tivity Concentrations (uci/ce)
Time Isotope 1430-1445 1445-1500 1500-1515 1515-1530
- 4 I-131- 9.3E-01. 9.3E-01 9.3E-01 9.3E-01
_I-132 4.6E-01 4.3E-01 4.0E-01 3.7E-01 I-133 1.7E+00~ 1.7E+C0 1.6E+00 1.6E+00 I-134 1.1E-01 9.4E-02 7.7E-02 6.3E-02 I-135 1.2E+00 1.2E+00 1.1E+00 1.1E+00-s..... _.. ___ .....__ . . . . . . ..___.. 7
- tj Total Iodine 4.4E+0* 4.3E+00 4.2E+00 4.1E+C0 I-131. Dose 1.5E+0L 1.5E+00 1.5E+00 3.5E+00 e Equivalent Kr-83m .2.7E+01 2.6E+01 2.5E+0". 2.4E+01 Kr-85m 5.2E+01 5.OE+01 4.8E+01 4.6E+01 Kr-85 4.3E+00 4.3E+00 4.3E+00 4.3E+00 i 'Kr-87' 2.3E+01 2.0E+01 1.7E+01- 1.5E+01 Kr-88 9.5E+01 8.9E401 8.4E+01 7.9E401 Xe-133 7.6E+02 .7.6Ev02 7.6E&O2 7.6EvC2 Xe-135m 7.7E+0i 9.5E+01 7.3E+01 7.1E+01 Xe-135- 2.7E+02 2.7E+02 2.8E+02 2.8E+02 l
L Total Noble- 1.3E+03- 1.3E+03 1.3E+03 1.3E+03 l. Gasi l i l L ........___.._. V'+ e : Primary containment sample dose rate provided in Section 9.5.2.
- Post 1530 values-continue to decline steadily with time.
t
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-4 4
VERMONT YANKEE NUCLFAR POWER STATION . l EMERGENCY RESPONFE PREPAREDNESS EXERCISE 5 1991
- i a
5 i
-t i,
P e 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA f n 1 > 1 I 4 . i ' S 9 '.i. if
- f 1 --
, - 4 _-. . . :. ,.,,:,,-..~,,...._.-,_, , . _ , , , . . - . , - . _ . . . ._, _ _ _ . . . . . . _ _ _ . . _ . . _ _ .
Rev. 0 n Page 9.4.3-1 l'y1_ 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 ** 2.7E-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
,'x Equivalent Kr-83m ** 9.9E+00 1.7E+01 1.8E+01 Kr-85m ** 1.9E+01 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 Kr-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 Tocal Noble ** 4.0E+02 6.9E+02 7.6E+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.c factor of 5.
- 3. Reactor Building air sample dose rates provided in Section 9.5.3.
** Prior to 1300 Reactor Building air activity is below MDA.
O
}
Rev. 0 Page 9.4.3-2 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.4.3 PIACTOR BUILDING AIR ACTIVITY DATA A. Reactor Building Air Activity Concentrations (uci/cc)-
- See Notes .Below*
Elevation 252'_and 280' Time Isotope 1345-1400 1400-1415 1415-1430 14 __ ____ __ ___ __ . __ ___ _ 30-1445 I-131 5.4E-01 5.3E-01 5.2E-01 5.1E-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 6.9E-01 6.5E -__ __ _.. ..
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. 4 E+01 1.3E+01 Kr-85m- 3.4E+01 3.2E+01 3.OE+01 2.0E+01 Kr-85 2.5E+00 2.4E+00 2.4E+00 2.3E+00 Kr-8'/ 2.0E+01 1.7E+01 1.5E+01 1.2E+01 Kr-88 6.6E+01 6.1E+01 5.6E+01 5.2E+01 Xe-133 4.4E+02 4.3E+02 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 7.5E+02 7,4E+02 7.0E+02 6.7E+02-Gas
- Notes:
- 1. Reactor Bui'. ding 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.
O I
Rev. O Page 9.4.3-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESG 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 1445-1500 1500-1515 1515-1530 I-331 5.0E-01 4.9E-01 4.8E-01 I-132 2.3E-01 2.1E-01 1.9E-01 I-133 8.9E-01 8.6E-01 9.4E-01 I-134 5.0E-02 4.1E-02 3.?E-02 I-135 6.2E-01 6.0E-01 5.7E-01 Total Iodine 2.3E+00 2.2E+00 2.1E+00 7.8E-01 7.6E-01 9 I-131 Dose Equivalent 8.0E-01 Kr-83m 1.1E+01 1.0E+01 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 L.1E+01 9.1E+00 7.7E+00 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 1.2E+01 1.1E+01 1.1E+01 Total Noble 6.4E+02 6.2E+02 6.0E+02 Gas
- Notes:
- 1. Reactor Euilding Zlevation 303' and 318' - divide concentrations by a factor of 1.
- 2. Reactor Building Elevation 345' ~ divide concentrations by a factor of 5.
- 3. Reactor Builoing air sample dose rates provided in Section 9.5.3.
- 4. Post 1530 values continue to decline steadily with time.
9
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^
i t VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 i' J 'a i 4
! 9.5 RADIOLOGICAL SAMPLE DOSE RATES 3
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- g. 3
- - - -. . ~ . - . -- - .. . - . . . . . . . -- . . - .
l Rev. 0 , Page 9.5.1-1 VERMONY YA!;KEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.5.1 Reactor Coolant Sample Dose Rates A. Gas Samples .e Unshielded (mR/hr per cc)* Shielded (1 in. lead in mR/hr per cc)* Time Contact 1 ft Contact 1 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 1130-1145 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.OE+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. O
. - - , ~ . - - . . _ - . - . ----. - . . .-. . -. - _
- i l Rev. O Page 9.5.1-2 , I ] (s) - VERMONY YANKBE NUCLEAR-POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1991 l 9.5.1 Reactor Coolant Sample Dose Rates i [ ....-__- ..................._____ ....__ B. Liquid (Iodine) 4 Unshielded (mR/hr per cc)* Shielded (1 in. lead in mR/hr per cc) *
- Time Contact 1 ft Contact 1 ft l Prior to l 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 l 1045-1100 7.3E+03 5.1E+01 9.2E+01 6.2E-01 I
1100-1115 1.1E+04 7.6E+01 1.4E+02 9.3E-01 I-1115-1130 1.5E+04 1.0E+02 1.9E+02 1.3E+00 {( 1130-1145 1.9E+04 1.3E+02 2.3E+02 1.6E+00 1145-1200 1. 7 E4 04 1.2E+02 2.1E+02 1.5E+00 i i 1200-1230 1.6E+04- 1.1E+02 2.0E+02 1.4E+00 o 1230-1300 1.5E+04 .1.0E+02 1.9E+02 1.3E+00 l 1300-1315 1.3E+04 9.2E+01 1.7E+02- 1.1E+00 1 1315-3330 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
-( ) Post 1530valuescontinuetodeclinesteadilywithtime.
Notes:
- Values must be multiplied by the sample volume in milliliters for
~
liquid samples to obtain the sample dose rate in mR/tr.
Rev. O Page 9.5.2-1 O \ j VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE 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 Road As Road 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. ,/~~...._____ .......__ . _____ _......-______---....-_-____ ...... .._....._ ....
) Note s* : Values must be multiplied by the sample volume in cubic centimeters for gas samples to obtain the sample dose rate in mR/hr.
Rev. O Page 9.5.3-1 VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.5.3 Reactor Building Air Sample Doso Rates (lodine Cartridge Only)
.___c.__.__ __.
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 As Read 1300 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-OL 1.8E-04 6 415-1430 3.9E+00 1.3E-02 2.4E-02 1.7E-04 1430-1445 1.9E+00 1.3E-02 2.3E-02 1.6E-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. O Page 9.5.4-1 VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONLE 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)* 1 ft Contact 1 ft Time Contact Prior to As Read 1300 ** As Read- As Road - As Read 3.-1E+00 2.2E-02 3.9E-02 2.8E-04 1300-1315 4.0E-02 7.OE-02 5.0E-04 1315-1330 5.7E+00 4.4E-02 7.7E-02 5.5E-04 1330-1345 6.3E+00 4.4E-02 7.7E-02 5.5E-04 1345-1400 6.3E+00 6.0E+00 4.2E-02 7.4E-02 5.3E-04
-1A 0 0-1415 4.0E-02 7.0E-02 5.0E-04
'5-d415-1430 5.7E+00 1430-1445 5.4E+00 3.8E-02 '[.7E-02 4.8E-04 3.8E-02 6.7E-02 4.8E-04 1445-1500 5.4E+00 4.8E+00 3.4E-02 6.0E-02 4.3E-04 1500-1515 3.4E-02 6.0E 4.3E-04 1515-1530 4.8E+00 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. O ** Plant vent stack sample dose rates remain constant from 0700-1300 l- given the same sample volume. i {'
)
l Page 9.5.4-2 I VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY REoPONSE PREPAREDNESS EXERCISE 1991 9.5.4 Plant Vent Stack Sample Doce Rates B. Air Sample (Iodine Cartridge) Unshielded (mR/hr per cc)* Shielded (1 in. lead in mR/hr per cc)* 1 ft Contact 1 ft Time Contact ---- ------- ---- Prior to As Read As Read 1300 ** As Read As Road 1.2E-05 2.1E-05 1.5E-07 1300-1315 1.7E-03 2.8E-03 2.0E-05 3.5E-05 2.5E-07 1315-1330 2.1E-05 3.8E-05 2.7E-07 1330-1345 3.1E-03 2.1E-05 3.7E-05 2.6E-07 1345-1400 3.0E-03 2.9E-03 2.0E-05 3.6E-05 2.6E-07
'00-1415 1.9E-05 3.5E-05 2.4E-07 415-1430 2.BE-03 1430-1445 2.6E-03 1.8E-05 ~5.3E-05 2.3E-07 1.3E-05 3.2E-05 2.2E-07 1445-1500 2.5E-03 1.7E-05 3.1E-05 2.2E-07 1500-1515 2.5E-03 1.6E-05 2.9E-05 2.0E-07 1515-1530 2.3E-03 Post 1530 values continue to decline steadily with time.
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.
O
/~T . 3'") Rev. O Page 9.5.4-3 VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 h 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 r
I
\ 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.
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 9,6 PLANT VQT STACK RE1 EASE DATA O O
r' Rev. 0 (N) Page 9.6-1 VEPMONT 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 Prior to 1300 1300-1313 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 1.3E-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 ()g q, 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 ** 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. 0 E4 01 Gaa l L --------------
- 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. ("N Note: Plant vent stack sample dose rates provided in Section 9.5.4. V L 1
fy Rev.: 0 8 i Page 9.6-2 LA/ <: 1
- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 i I
t 9.6 PLANT VENT STACK RELEASE DA'I A Plant Vent Stack Activity Release Concentrations (uci/cc)
- 4 A.
- --_.....______. .-____ ..... .........____________. .... l Time Isotope 1330-1345 1345-1400 1400-1435 1415-1430-4 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
- f I-131 Dose 1.3E-03 1.3E-03 1.2E-03 1.2E-03
' Equivalent 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 2 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 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.
Note: Plant vent stack sample dose rates provided in Section 9.5.4.
i
-s Rev. 0 Page 0.6-3 7
VERMONT YANKEE E'UCLEA% POWEP. STATION EMERGENC" RESPONSE PREPAREDNESS EXEReygg 1991 9.6 PLANT VENT STACK RELEASE Ef"'A A. Plant Vent Stack Activity Release Concentrations (uci/cc)
- Time Isotope 1430-1445 1445-1500 1500-1515 1515-1530 **
I-131 7.3S-04 7.2E-04 7.0E-04 6.9E-04 I-132 3.6E-04 3.3E-04 2.0E-04 2.7E-04 I-133 1. 3 E- 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-04 8.2E-04 Total Iodine 3.4E-03 3.3E-03 3.2E-03 3.0E-03 gg I-131 Dose 1.2E-03 1.2E-03 1 1E-03 1.1E-03 Equivalent
-( J $
Kr-83m 3.7E-01 3.3E-01 2.9E-01 2.6E-01 Kr-85m 8.2E-01 7.7E-01 7.2E-01 6.8E-03 Kr-85 6.7E-02 6.6E-02 6.4E-02 6.3E-02 Kr-87 3.6E-01 3.1E-01 2.6E-01 2.2E-01 Kr-88 1.5E+00 1. 4 E+ 0 0 1.3E+00 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 ?.4E+00 Total Noble 1.9E+01 1.9E+01 '. 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 rhtes provided in Section 9.5.4. l
VPJ10NY YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.7 EiDD MONITORING MAPS AND DATA O
- O -
t 4 i Rev. 1 Page 9.7 1 VERMONT YANKEE NUCLEAR PWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 9.7 FIELD HQElIQRING MAPS AND DATA 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 (METPAC). Geographical representations of the plume are provided in this section fx each 15 minute average of the meteorological conditions, starting at clock time 1308 (scenario time 6:08) . During the exercise, field team observers will use the information contained in this section to provide field monitoring teams with the appropriate survey results and . radiological data for various times and locations. i ( The designated field monitoring teams will be directed to monitor and-track _the plume relative to the acreorological conditions postulated for the scenario. Figures 9.7 1 through 9,7-11 depict the plume _ location at various times throughout-the scenario. These figures represent a plume width which is equivalent to a 3 sigma value of the centerline conditions. Girce the figures show a plume width relative to the centerline, survey results vera. calculated for various color coded usp areas _(blue, yellow, and Sreen); Field data tables have been developed for Vermont Yankee and-State of _ Vermont field monitoring teams. The tables contained the radiological data to be provided to the field monitoring teams for various times and locations; (The tables follow the figure for a given scenario time period.) Rs.diological data on the tables have been provided for each plume segment and colored map area shown on the associated figures. Radiological. data for locations between two plume _ segments can be-y estimated by r.xtrapolating between the values for those segments. L.O-e 0,J
.o Rev. 1 Page 9.7 2 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 designated , check that the appropriate procedures are followed by team members. This will include the initial equipment check.
- 2. While traveling to assigned monitoring locations, or while traversing the plume, or at assigned monitoring locations, use t.he attached figures and tables to issue appropriate radiolo31 cal 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 readir.g for the gamma q dose rate. Do not issue pocket dosimeter results to team members,
( V unless they actually simulate checking their dosimeter reading. The pocket dosimeters Save specific ranges and intervals in mR or R values. Ask them the ranges 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 equipment they have available for 7 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.
O L
Rev. 1 Page 9.7-3 [] V
- 5. For gamma (whole body dose rates) survey readings taken by field nonitoring teams, the following information should be use:
- a. If an RM 14 AP-210 is used to track the plume, the meter count rate of 3,500 cpm on the RM 14/HP-210 is equivalent to approxime.tely 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. Wher.ever a team takes a " ground level" survey, the results should be the same as the " waist level" se.rvey, c Certain field monitoring teams may take open window and closed window readings with their dose rate survey meters. If a team is located in the plume and air concentration is greater than zero, assume the open window reading is two times the closed window d readinc, for the gamma dose rate reading.
- 6. For air sample measurements taken by field monitoring teams, the following information should be use:
- a. The field monitoring teams will substitute a charcoal cartridge instead of the adsorber media cartridge (silver zoolite) contained in the field monitoring kits. All air sample data will ,
be given as though the adsorber media cartridges (silver zeolite) were being 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 Vermont Yankee and 177 liters for State of Vermont field monitoring teams. If different volumes are collected. the air sample data provided in the tables should be adjusted proportionally,
(] V
- _ ~ . -. . _ . . .- . - . - - - .- . . -
v Rev, 1 W Page 9.7-4 V : c, Air sserte net count rates for the absorber avdia cartridges-(silver geolite) provided in the field data - ta'olen have been developed using METPAC thyroid dose rate proj ec tions. The .
. formula used is as follows:
ConcI-131 (UCl/cc) = "ExVxTW v4, SE-10 uC1-l/dpm-cc - where: E- Iastrument Detector Efficiency in epm /dpm (counts per disintegration) V- Fl.ow rate of sample in Ipm (liters per niinute) T- Sat 4ple collection time in minutes
- d. For air sample net cou.nt 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 (epm) were ostimated from the I-131 air acentration for a.100 liter (Vermont Yankee Plant)-and Liter (Stat e of Vermont) sample volus.t.
NOTE: THE PLUME PLDT FICURES ARE G3APFIO REPPESENTt.TIVES OF ATMOSP]lERIC
. DISPERSION, I.ARCER FIGURES WII.L BE AVAILABLE TO OBSERVERS .40R THEIR USE ON PROVIDING DATA TD FIELD MONITORING TENTS, t
0 9
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1 PAGE 9,7.$A
+y. tD TABT.E 9,7.1 J - ON SITE VERMONT YANKEE FIELD DATA
- P AIR SAMPLE DATA (100 LITERS)*
GAMMA DOSE RATE RM.14** SAM.II RM 14*** , , J(- CONC. PARTICULATE CLOCK MAP PIC 6 RM-14 I-131 SILVER ZEOLITE FILTER h (NET CPM) .l TIME; AREA- (mR/hr) (CPM) uC1/cc -(NET CPM) (NET' CPM) .
'55b555555
'ktbE hkb' 'bhb 'b$bbb'bb+ kbb' ' 'ES kE b "Edb '
YELLOW 76 OSH 0.00E+00 (40 AS READ <40 i- , GREEN 8 26600 0.00E+00 <40 AS READ <40
- ( -1315 1330 BLUE 1400 OSH 0.00E&D0 <40 AS READ <40 1 YELLOW -140 OSH ' O.00E4 00 <40 LAS READ <40 c
- b OREEN 14- 49000 0.00E+00 <40 AS READ <40 1330 1345 BLUE 1500 OSH 0.00E+00 <40 AS READ <40 i YELLOW 150 OSH- 0.00E+00 <40 AS READ <40 CREEN 15 OSH 0.00E+00 <40 AS READ <40
}{ <40
- 1 1345 1400 ELUE 1500 OSH 0.00E+00 <40 AS READ
; YELLOW 150 05H 0.00E+00 <40 AS READ <40 GREEN 15 OSH 0,00E+00 <40 AS READ <40 ' t" 21400 1415 -ELUE 1500- OSH 0. 00 E+ 00 <40 ,AS READ <40 YELLOW 150 OSH -0.00E+00 <40- AS READ <40 L b GREEN 15 0SH 0.00E+00 <40 AS READ <40
.v 1 1415 1430 BLUE 1470- OSH 0,0CE+00 <40- AS READ <40 147 0.00E+00 <40 AS READ <40 1 YELLOW OSH 0 00E+00 <40 AS READ <40
;; GREEN 15 OSA 1430-1445 BLUE 1470 CSH 0,00E+00 (40 AS READ <40
- ./Y 1YELLOV 147 OSH 0.00E&OO <40 AS READ- <40 0.00E+00 <40 AS READ <40 L( ,) GREEN 15 _0SH i- 1445-1500 JBLUE 1340 05H 0.00E+00 <40 AS READ <40
-; YELLOW 134 OSH 0. 00E4 00 <40 AS READ <40 i' GREEN 13 46900 0.00E+00 <40 AS READ <40 a
FF -1500 1915- BLUE- 2000 OSH~ 0.00E+00 <40 AS READ <40 di YELLOW 100- OSH 0.00E+00 <40 AS READ <40 i
- s. GREEN 10- 35000 0.00E+00 <40 AS READ <40 J1515-1530: : BUUE 930 OSH 0.00E+00 <40 AS-READ ~ -<40 EYELLOW- 93 OSH 0.00E+00 <40 AS READ <40 GREEN- 9' 32550- 0.00 E+00 <40 AS READ <40 i
NOTES: -
- Air szmple data are based on a sample volume of 100 liters. -If -different volumes -
1 are collected, the air-sample data provided in the tables should be ad usted pro ortionally. For example, if e 50 liter sam ot 100 liters,. div de the value given in the table by 2 (two)ple andwas collected inatta value to ^ provide the resulting
-the players. ,
a li - ** The_ RM-14 detector efficiency for .I-131 was assumed to be 0.025 cpa/d m with the -
! stiver zeolite cartridFe Therefore ~ 1 131 cone. lite cartridge, k
.the net sample count rato in cpm on: the silver zeo(uct/cc) X 5.6E+09 w 11 calculate -
'i. J
. - *** Thn particulate filter sample count-rate'(cpm) uas estimated from the 1-131 air -
concentration for a 100 liter sample.
, OSH .Off Scale High (Count rate higher chan the -upper scale of the instrumentation),
t I
~r &
b "
PAGE 9.7-5B E PAGE INTENTIONALLY LEFT DLANK tiOTE: STATE OF VEPJ40NT FIELD DATA IS NOT REQUIRED FOR ON-SITE - (PROTECTED AREA) PIAliT SURVEYS
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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) .i
- ! A7R SAMP1.E DATA (100 LITERS)*
GAMMA DOSE RATE RM 14** SAM 11 RM 14*** ! CONG. PARTICULATE 4 PLUME FILTER I SFCMCIT DISTANCE MAP PIC-6 RM 14 1 131 SILVER 2EOLITE uCi/cc (NET CPM) (NET CPM) (NET CPM)
- j. NO, (MILES) AREA (mR/hr) (CPM) i
'"i$b0 bite ~~bLbb' 5bb' ' bib" '5.'32b$5bE4b'kb'kEEb k5b
<40 BOUNDARY YELLOW 80 OSH 4.32E 11 <40 AS READ
<40 j CREEN 8 ?S000 4.32E 12 3.46E 07
<40 1936 AS READ 5807 1383 2.00 0.60 BLUE 1500 OSH 3.46E 08 .194 581 138 l
i
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<40
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- l, '
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- i 2
i
.A 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 bn ad usted of 100 liters, pronortionally.
the For value exampic given in the, table if a 50byliter 2 sam and (two)ple was collected provide the instea resulting value to divide the players.
~
** The RM-14 detector efficiency for 1-131 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-
- q the net sample count rate 'in cpm on the silver zeolite cartridge, i *** 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).
X y . 1-i- REV. 1 PAGE 9.7 6B d L TABLE 9.7,2b
< STATE OF VERMONT FIELD DATA AT CLOCK TIME 1308-3315 (SCENARIO TIME 6:08 - 6:15)-
4 CAMMA SURVEY DATA AIR SAMPLE DATA (177 LITERM* WAIST AND GROUND LEVEL READINCS LUDLUM 2220 G M METER i - PLUME ' CLOSED OPEN CONC, AGX.2** PARTICULATE *** '
- SEGMENT DISTANCE MAP V1NDOW UINDOW I 131 CARTRIDGE FILTER l NO, - (MILES) AREA (raR/hr) (inR/hr) '
uCi/cc (NET CPM) (NET CPM) " l 'k '"i$b0 SiTb' Bi$b' 'hbb' '56bb 4$32b55bEi~Rkkb ~ k5b ' i BOUNDARY YEl. LOW 60 160 4,32E-11 AS READ <50 CREEN 8 16 4.32E.12 AS READ <50 _,
.J '
S 2,00 0.60' BLUE 1500 3000 3.46E 07 11062 2454 i YEl.IDW 150 300 3,46E 08 1106 245 GREEN 15 30 3.46E 09 111 <50 , Ih- :
. l.
It ij l3 1 i i
',4 1 t-a: ,
8 g): , d4 ' NOTES:
- Air sample data are. based on a sample volume of 177 liters. If different volumes
.j are collected, the air sample data provided in the t. ables should be adjusted proportionally. For example, if a 89 liter sam divide the value given in the table by 2 (two)ple andwas collected instead of 177toliters, provide the reeulting value
-d ._ the players.
-** The Ludlum 2220 detecter ef ficiency for I-131 was assumed to be 0,080 cpe/doin with-
,.- the'ACX-2 cartridge. Therefore, I 131 conc. (uci/cc) X 3,2E+10 sill 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 G M survey meter is used s
to obtain the sample count rates. The Illter count rate was estimated from the i- I-131 air concentration for a 177 liter sample volume. 4: t y ,y.. - . . , , , . , y e . -_ .
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- 3 e -
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- Y R e i ,b4 .
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'sa 3,% 'I # 'q ge .,f.,, /
3 ,1 327 g, sm e 3 R'..m_ ] A.,T@f j 0 e ./ [ @. ( J, ._ hrMdls" 3 e r 9 := 5 2 - 1 r- D 1 D t p i
~$ k 7 O J c. . a 'e #,
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d PAGE 9.7 7A TAllLE 9.7.3a
'/ERMONT YANKEE FIELD DATA AT CLOCK 11ME 1315 1330 (SCENARIO TIME 6:15 :30)
AIR SAMPLE DATA (1001.ITERS)* CAMMA DOSE RATE IW 14** SAM.11 RM 14*** ' PARTICULATE PLUME CONC. 4 PIC 6 RM 14 1 131 S11NER ZE01.1TE FILTER SEGMENT DISTANCE MAP (NET CPM) i NO, (MILES) AREA (nJt/hr) (CPM) uCi/cc (NET CPM) (NET CTM)
"$ 5bk$5b Edb' ' k'kkkb ' ' 'E5 b ' '
[$b0 'hiTk 51.bb' '535b' 135
'bhtl OSH 3.40E 11 <40 AS READ <40 BOUNDARY YELLOV <40 GREEN 14 47250 3.40E 12 <40 AS READ 2500 3,63E 07 2033 6098 1452 2.00 0.60 BLUE OSH 203 60 14$
YELLOV 250 OSH 3.63E 08 i CREEN 25 OSH 3.63E 09 <40 1 c4C -i 1.20 1300 OSH 9.26E.07 $185 16556 3704 i , 3.00 9.26E 08 $19 1$56 370 ; 130 OSH
<40 13 45500 9.26E 09 52 156 i
i i t i O ' i i i t, NOTES:
- Air sample data pre based on a cample volume of 100 liters. If differer.t volurnes j Ara collected. the air-sample data rovided in the tables should be ad usted .
proportionally. divide the valueFor example, if a by $ liter sampin was collected insteaandofprovide 100 ' liters, } given in the table 2 (tvo) the resu the pihyers.
** Tbc RM 14 detector. efficiency for 1 131 was assumed to be 0,0k5 com/dpm with the silver zeolite cartridge. Therefore, 1 131 conc. (uCi/cc) X 5.6E40.9 v111 calculate j
the net sample count rate in epm on the stiver zeolite cartridge, i
*** The particulate filter sample count rate (cpm) was estimated from the 1 131 eir
. concentration for a 100 liter sample, 5
l u-OSH Off Scale High (Count rate higher than the upper scale of the instrumentation). O
-)
R
. , - . . . m, - - - - ----e. ._w-, --.,.---,.-,_-m.--y,.,,mm.wme-arm,,m -% w r- --+ nv++ m w v.,,+,v----mn-1--e -rve- -ve-*-v*=e--er---e+,v--w+-+C-- - " 'qr w eser--- gW'r-*
-.. . - -- . . - - ~ - . - - - . . . _ _ - - r REV. 1 PAGE 9.7 7B l
- TABLE 9.7.3b
' $*iATE OF VERMONT FIELD DATA AT CLOCK TIME 13151330 (SCENAE10 TIME 6: 15 6:30) j CAKKA bl%VEY DATA AIR SAMPLE DAT A (177 LITERS)* i WAIST AND GROUND LEVEL READINGS LUDLUM 2720 G.H METER PLUME CIDSED OPEN CONC AGX.2** PARTI CU LATE * *
- StGMENT DISTANCE MAP VINDOW VINDOW I.13i CARTRIDGE FILTER No. uC1 (NET CPM) (NET CPM)
(MILES) AREA (mR h r ) (mR/.hr)
. . . . /..... ... .... ...../.cc ... ......... .......... ,
1.00 SITE BLUE 1350 2700 3.40E.10 AS READ <50 '. BOUNDARY YEllDW 135 270 3.40E.11 AS READ <50 GREEN 14 27 1.40E.12 AS READ <50 2.00 0.60 BLUE 2500 5000 3.63E.07 11615 2577 . YELLOW 250 $00 3.63E.08 1161 258 , GREEN 25 50 3.63E+09 116 <$0 ' 3.00 BLUE 1300 2600 9.26E.07 29630 6574
' 1.20 130 260 9.26E.08 2963 657 .
. YELLOW ' GREEN 13 26 9.26E.09 296 66 i 4 i LO 4 i
' .)
- t
- i-
'! NOTES:
- Air sample data are based on a sample volume of 177 liters. If different volumes 4 1
> are collected the air sample data provided in the tables should be adjusted proportionally,. For example..if a 89 liter sae divide the-value given in the table by 2 (two)ple andwas provide collected insteadvalue the resulting of 177 to liters, ,
the players. - 1,. i ** The Ludlum 2220 derwr. tor efficiency for I.131 was assumed to be 0.080 cpm /dpm with the AGX-2 cartridge. Therefore, I 131 cone. (uC'/cc) X 3.2E+10 will calculate the the net sample count rate in cpm on the ACX.2 cartridge.
*** For analysis of-the particulate filter it is assumed that a C.M survey aeter is used to obtain the sample count, rates. The litter count rate was estimated from the.
1 131 air concentration for a 177 lit sr sample volume. s ,- e 4 v.-m, ,--v wm, vr,-v m,. ,,r. --.L.--~-, .- --,w-,,,w,ww..,,,,,-,. ,-.,s,,-.. r---.c_.~ --c-~!. -
->.--,-.rw---,-v=r'-'**'v
n, .. usa.eA_n.a ..as--,_s_
- s. e._s ,--su- um 6w --A Lr. m._ R - m a a- J w u ru ~::- - n e sa=m.w- -.J A s A s-saa J,A=.ws.ss.L-us e s m.s nses_A s s.a -s. . ~ . . .ae-,
a m, _g 4 r cf /, '\ 4, e r - v- .
+ $ ;
M...u,p& CPM ag 49"tWi 4 e a ,g/1!- . s
,s
'~~
a a/,w .
~
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a .
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- 3 a 7 t
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- z. i t f - --
- e L CL) ( x .
< + L i fH 4 -
1
.I l
PACE 9.7 BA 1
' - TABLI 9.7.4a i l
. VERMONT YANKEE FIELD DATA AT CLOCK TIME 13301345 (SCENARIO TIME 6:30 6:45) l AIR SAMPLE DATA (100 LITERS)*
CAMMA DOSE RATE RM 14t* SAM 11 RM.14*** i CONC, PARTICU! ATE PLUME FILTER SEGMENT DISTANCE MAP PIC 6 RM 14 1 131 SILVER ZEOLITE AREA (mR/hr) (CPM) uC1/cc (NET CPM) (NET CPH) (NET CPM) l NO. (MILES)
i$b0 ~~h5Tk' ' kLbb'
~$bbb' *bSb' 'k$bbh 'b k5b' 'kk'k'kb E k5b^ '
140 OSH 1.60E+ 1 <40 AS READ <40 BOUNDARY YELLOW <40 AS READ (40 GREEN 14 49000 1.00E 12 2.00 0.50 BLUE 2500 OSH 1.89E.07 1058 31/3 756 250 OSH 1,89E.06 106 317 76 YELLDk <40 GREEN 25 OSH 1 89E 09 <40 AS READ 1300 1.76E 06 9652 29556 7037 l 3.00 1.10 BLUE OSH 985 2956 704 YELLOW 130 OSH 1.76E.07 , CREEN 13 45500 1.76E.08 99 296 70 820 5.25E 07 2942 8825 2101 4.00 1.70 BLUE OSH 294 883 210 YELLOW 82 OSH 5.2pE08 <40 88 (40 GREEN 8 28700 5.2sE 09 b 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 thould be adjusted proportionally. For example, if a 50 litar sample was colleated insteac of 100 liters, divido the value given in the table by 2 (two) and provide the resulting value to the players.
.i
** The RM-14 detector- efficiency for-I 131 was assumed to be 0.025 cpm /dpm with the silver I 131 cone. (uC1/ce) X ! .6E+09 will calculate the netzeolite samplecartridge, count rateTherefore, in cpm on t he silver zeolite cartridge.
'l 4 a
*** The particulate filter sample count rate (cpm) was estimated from the I 131 air concentration for a 100 liter sanple.
l OSM Off Scale High'(Count rate higher than the upper scale of the instrumentation), i
- ... _ _ _ . - _ . . _ - . . . _ _ . . . _ _ . _ . . . . _ _ _ _ . _ _ _ . . . - . - . _ . ~ . _ _ _ _ _ . _ . _
1 d REV. 1 PAGE 9.7.BB f TABLE 9,7.4b
! TATE OF VERMONT FIE'.D DATA AT CIDCK TIME 1330 1345 (SCESARIO TittE 0: 30 6:45)
C/.MMA Sl'RVEY DATA AIR SAMPLE DATA {177 1.1TEl S)* VAIST AND CROUND LEVEL READINGS LUDLUM 2 t20 G M miter FLUME ClDS FD OPLN CONC AGX.2** PAliT I CULAT E* *
- SECHENT DISTANCE MAP VIND0V VIND0V 1 13i CARTRIDCE FILTER (mR/hr) (mR/hr) uCi (NET CI'M) (NET CPM)
No. (MILES) AREA
....... ....... ......... ........ ...../.cc i 1400 2800 1.60E.10 AS RIAD <50 1.00 SITE BLUE 280 1.600 11 As READ (50 BOUNDARY YELIDW 140 1 GREEN 14 28 1.600 12 AS RtAD <50 2500 5000 1.89E.07 6044 1341 ; 2.00 0.50 BLUE 604 134 YEllDV 250 500 1.89E-08 i
GREEN 25 50 1.89E.09 60 <50 4 I 3.00 1.10 BIDE YEllrV 2600 260 5200 520 1.76E.06 1.76E.07 56296
$630 12491 1749 1.76E-08 563 125 j CREEN 26 52 1.70 820 1640 5.25E.07 16810 3730 9 4.00 BLUE 5.25E.08 1681 373 YELIDW 82 164 CREEN B 16 5.25E.09 168 <50 T
1 i i
- t
.J 1,
b i d I 1 1 B d
.4 NOTES:
1
- Air varmle data are based on a sample volume of 177 liters. If different volumes
- are collected, the air sample data provided in the tables should be adjusted proportionally.
the value For given example, in the iftable a 89by liter sam andwrs 2 (two)ple collected provide instead of the resulting 177toliters, value divide the players.
** The Ludiwa 2220 cetector ef ficiene 31 for1131wasassumedtobe0.0R0cIm/dpmwith conc. (uC1/cc) X 3,2E+10 vill cal u' tate the
! the AGX-2 cartridge. Therefore, 1 j
the ner su ple count rate in cpta on the ACX 2 cartridge. 4 it is assumed that a C H survey meter is used
*** For to analysis obtain the of the sample particulate count filterrates. The Illter :ount rate was estimated irom the 1 131 air concentraticn for a 17 7 liter sample volume.
g 4 e , --a a' V a g 0'y y em e i,
?
+ yd .
' Y, {}h*'j-(?&a hfb MJ .. ;t 5 .. ,
, ; d M g $h T 4 -- m .
Yfaf ? '
}< nl* a...} w/ m x ..
V /.m 14e9 y:;\h - e m q;- s : m >;g i ef;'g.L' y'f a 4' A! [ ii a
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1
- fx p M.m '
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~
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cr
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]
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cn Od[-[Md$y1 L
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~
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&y ei7 \d f r-5 ny ; i me .s ,q ~en
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- l gy%Q/"t%=f,/psnV:
.. /
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)
q *@ p-- ; j f N . j y j [.mw (4 .
_ _ . _ . . _ - ~ _ _ . - - _ _ _ _ . . . _ _ . _ _ . _ . _ .-_ . ~ . _ . _ . _ _ _ . _ _ _ _ _ _ . _ . _ PAGE 9.7 9A TABLE V.7.Sa
- i. VERMORT YANKEE FIELD DATA Al CLOCK TIME 13451403 (SCEAARIO TIME 6:45 7:00) !
I AIR SAMPLE DATA (100 LITERS)* ' CAMMA DOSE RATE RM 14** SAM Il RM 14*** CONC. PARTICULATE , l'
~
PLUME ' FILTER SEGMENT D10TANCE MAP PIC+6 FM 14 G!!NER ZEOLITE 1-l31 ii .."?:. !"!!!5! ..^"E^. .!!"(h!!. !?!"!... .."?.(!!.!?f!.?!"!!"ET.?!") !"ET.?!"!
<40 1.00 SITE BLUE 1600 OSH 5.93E.10 <40 AS READ 160 OSH 5.93E.11 <40 AS READ <40 BOUNDARY YELLOW <40 AS READ <40 GREEN 16 OSH 5.93E.12
) 10059 2395 2.00 0.60 BLUE 3160 OSH 5.99E 07 3353
- ) YELLOW 316 OSH 5.99E 08 335 1006 't40
.: <40 101 <40 li GREEN 32 OSH 5.99E 09 ,
3000 2.00E-06 11260 33600 8000 i 'x- 3.00 1.10 B1UE OSH 3360 800 s YELIDW 300 OSH 2.00E 07 1120 30 OSH 2.00E 08 112 336 80 >l GREEN 1500 9.57E.07 5358 16074 1827 4.00 1.70 BLUE OSH
-383
-l YELIDV GREEN 150 1$
OSH OSH 9.57E.08 9.57E 09 536
$4 1607 161 <40
$30 3.19E 07 1784 5351 1274 5 5*00 2.30 BLUE OSH 535 121 j ..
YE11DV GREEN 53 5 OSH 18550 3.19E 08 3.19E.09 <40 178 54 <40 4 1 1 <1 r 4 i , f 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 i
proportionally. the value Eor example, given in theiftable a 50 by liter2 sam (two)ple andwas provide collected insteadvalue the resulting of 100to liters, divlde the players., "1 ** The 301 14-detector efficiency for I 131 was assumed to be 0.025 cpm /dpm with the silver zeolite cartridge. Therefore, 1 131 conc. (uct/cc) X 5.6E+09 will calculate
^
the net sample. count rate in epm on the silver zeolite cartridge.
.)
$ *** The particulate filter sample count rate (epm) was estimated from the 1 131 air
+ concentration for a 100 liter sample.
OSH Off. Scale Highf(Count rate higher than the upper scale of the instrunientation). O h CeT'V'Ty- 4*-' awry g)f*-- me ae = = = ' - y ~wg-- gym.Wcy,- up-w--g e=w.e,,,-=y-g. ..y.pg-%- e- ,em+..
j 1 s l j REV. 1 PAGE 9.7 9B TABLE 9.7.5b STATE OF VERMONT FIELD DATA AT CLOCR TIME 1345 1400 (SCENARIO TIME 6:45 7:00) c d GAMMA SURVEY DATA AIR SAMPLE DATA (177 1.1TERS)* Wh!ST AND GROUND LEVEL READINGS LUDLUM 2220 G.M METER l PLUME CUDSED OPEN CONC. AGX.2** PARTICULATE *** { t' SEGMENT DISTANCE MAP WINDOW WINDOV 1 131 CARTRIDGE FILTER 4 NO. (MILES) AREA (mR/hr) uCi/cc (NET CPM) (NET CPM)
< ...... ....... ....... ......... (mR/.hr) 1.00 SITE BLUE 1600 3200 5.93E.10 AS READ <50 BOUNDARY YEL1hW 160 320 5.93E.11 AS READ <50 g <50 GREEN 16 32 5.93E.12 AS READ g_
4 2.00 0.60 BLUE 3160 6320 5.99E.07 19160 4251 i YELIAV 316 632 5.99E.08 1916 425 l
$ GREEN 32 63 5.99E.09 192 <50 l 3 3.00 1.10 BLUE 3000 6000 2.00E 06 64000 14200 1 YELIDW 300 600 2.00E.07 6400 1420 GREEN 30 60 2.00E.08 640 142 j -j 4.00 1.70 BLUE 1500 3000 9.57E.07 30617 6793 YELLOW 150 ,100 9.57E 08 3062 679 GREEN 15 30 9.57E.09 306 68
. i, 5.00 2.30 B1JIE "30 1060 3.19E.07 10193 2261 J,c YELLOW 53 106 3.19E.08 1019 226 CREEN $ 11 3.19E.09 102 <50 .y > d 4 10 $ j.I I, Al '4
?
J ,) . N ['i ' NOTES:
- Air sample data are based on a sample volume of 177 liters. If different volumes
,?
4;- are collet.ted, the air sample data provided in the tables should be adjusted ortionally. For example, if a 89 liter sam uj pro div $de the value- given in the table by 2 (two)ple and wasprovide collected the resulting instead of 177 value to liters, 3 the players.
** The Ludium 2220 detector ef ficiency for I-131 was assumed to be 0.060 e dpm with t.i
- the AGX.2 cartridge. Therefore, I.131 conc. (uC1/cc) X 3.2E+10 will cal ate the fj the net sample count rate in cpm on the ACX.2 cartridge.
A *** For analysis of the particulate filter it is assumed that a G.M survey meter is used to obtain the sample count rates. The litter count rate was estimated from the j I.131 air concentration for a 177 liter sample volume.
a s .u n n.u ~s uu- a-ns a---ast-m*w-a,-ass m a mam---s s, a , s---m m ean-" m--,-- emr ~w-a--asa A<Lk~A--- ' --- x2 --Ar n u - --~x-s4--.---- -
. e s., .qa e c y i .. s .
u
<+,
r m3 3' 2 3e$ e- ;c f['g k' \f 8
- g. 4 il - ..
n na s ; AW .;g. - ..
*4 q
g% E e, i I W l _,, Q,ye NA f 5 2 4*-35 L Nt hj', i b
- W]
"~ d le --
'9 . +g g; g .J a
%~ '
n .- .
; .. )
&.a/.. . ,pf A' .,7[3 q , w;ygu37
.,f a =>
0
., 4 0
2
. g~ m e, m -
g4 v% mu9 s e mal vr% , c :~~~ f. i,.m f,.q s r O. %pa yL Qj,ph o P v M~ vs u "" l Qw# f fji 'T'? ..':
.ull%,'t$)
d)!!; U /iY l 7%Q#It % b" '"- l e M
'% > b)/ sI e C e
g \ r _-_. A, . _ _ , - _ _ , ,- . I 3q 1,1-N gy u m,,- %,; - m 4 1 e ,
.. g, h
n p ))Y j /I ,pq] {l b , , O* %" \ ' g' !Il
~
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/ ' -
+ ,
af s x' V
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- - e 3
jf ( - -. x
+.
-m.-__.___-.____
PAGE 9.7 10A i 1 TABLE P.7.6a
- i. VEhMONT YANKEE FIELD DATA AT CLOCK TIME 1600 1415 ($CFMAR10 TIME 7:00 7:15) :
$l AIR SAMPLE DATA (1001.1TERS)+ ' GAMMA DOSE RATE RM 14** SAM 11 RM 14**d ' CONC PARTICU! ATE ' 4 PLUME FILTER SEGMENT DISTANCE MAP PIC 6 -RM 14 1131 S11NER 7.EOLITE j NO. (MILES) AREA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPH) (NET CPM)
i$b0 55Tb' ki.bE
' ~
55bb' 'bkb" '5'.55k$bkSU'5'kkkb kdb <40 BOUNDARY YEL1DW 150 OSH 8.33E 1 <40 AS READ
<40 CREEN 15 OSH 8.33E.12 <40 AS READ ]' 11407 2716 I 2.00 0.60 BWE 2900 OSH 6.79E 07 3802 YELLOW 290 OSH 6.79E 08 380 1141 272 CREEN 29 OSH 6 79E 09 <40 114 <40 f j-1.20 BWE 2800 OSH 1.91E.06 10716 32148 7654 3.00 3215 765-YELIDW 280 OSH 1.91E.07 1072 GREEN 28 OSH 1.91E 08 107 321 77 1.11E.06 6222 18667 4444 4.00 1.70 BWE 1700 OSH 622 1867 444 ;
YELLOW 170 OSH 1.11E.07 44 o- GREEN. 17 OSH 1.11E 08 62 187 950 5.68E 07. 3180 9541 2272 5.00 2.30 BWE OSH 954 227 YELLOW 95 OSH 5.68E 06 318 CREEN 10 33250 5.68E.09 <40 95 <40 p 360 2.10E 07 1175 3526 840 > 1 6.00 2.90 BWE OSH 353 84 YELLOW 36 OSH 2.10E 08 118
- - GREEN 4 12600 2.10E 09 <40 AS READ <40 li
' ,I 4 t d
.I NOTES:
- Air sample data are based on a sample volume of 100 liters, if different volumes l
are collected,-the air cample data provided-in the-tables should be adjusted f 100 liters,
--divide the valueFor proportionally. example.
given if a 50byliter in the table sam was collected instead oand 2 (two)ple provide the r I4- the players.
-t j ** The PJ414 detector efficiency for I.131 was assumed to be 0.025 com/dr'n with the silver zeolite cartridge. Therefore.--I 131 conc. (uC1/ce).X 5.6E409 v111 c.alculate the net sample count rate in cpm on the silver reolite cartrid 6e.
*** The particulate' filter sample count rate (epm) was estimated from the I.131 air
- concentration for a 100 liter sample.
- 0SH _ Off Scale High (Count rate higher than the upper scale of the instrumentation) .
,---.-,..3,-.-_,,,-..--,.~-..._.e._~._,.....____.,_._,m.,.o.,~m_m,,_, ,-m.myy m.c.m,,.,,,,,,..,m.,,,.,.,,,.~, , ., ,,-,..m yry,r#. ,.,~_,,,,-v_-,,.- -~
4
'l ,
REV . 1 PACE 9.7 108 l l TABLE 9.7.6b l
~ STATE OF VERMONT FIELD DATA AT CLOCK TIME 1400 1415 (SCENARIO TIME 7:00 7:15) l CAMMA $URVEY DATA VAIST AND GROUND LEVEL READINGS AIRSAMPLEDATA{0177 LUDLUM 224 C MLITERS)*
METER PLUME CLOSED OPEN CONC AGX-2** PARTI CULATE * * *
< SEGMENT DISTANCE MAP WINDOW VINDOW I 13i CARTRIDGE FILTER J
i NO. (MILES) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM) i
~
1.00 0.30 BIEE 1500 3000 8.33E 10 AS READ <50
- YELLDW 150 300 8.33E 11 AS READ <50
'j CREEN 15 30 6.33E 12 AS READ <50 2.00 0.60 BUUE 2900 5800 6.79E 07 21728 4821
.i YELLDU 290 560 6.79E 08 2173 482
. CREEN 29 58 6.79E 09 217 <50 i 3.00 1.20 BLUE 2800 5600 1.91E-06 61235 13586 YELLOW 280 560 1.91E 07 6123 1359 GREEN 28 56 1.91E 09 612 136 I 4.00 1.70 BLUE 1700 3400 1.11E 06 35556 7689 a YELLOW 170 340 1.11E-07 3556 789 ' '
; CREEN 17 34 1.11E 08 356 79
) 5.00 2.30 BLUE 950 1900 5.68E 07 18173 4032 YELLOV 95 190 5.68E 08 1817 403 j GREEN 10 19 5.68E 09 182 <50 j 6.00 2.90 BLUL 360 7?O 2.10E 07 6716 1490 YELLOV 36 72 2.10E 08 672 149 GREEN 4 7 2.10E'd 67 <50
'O i
I J k s I j NOTES: i
- Air sample data are based on a sample volume of 177 liters. If different volumes
]' are collected, theairsampledatahrovidedinthetablesshouldbeadjusted proportional 1'/. For example, if a B liter sam divide the value given in the table by 2 (two)ple andwas collected provide the resulting instead of 177toliters.
value the players. 3
** The Ludium 2220 detector efficiency for I 131 was assumed to be 0.080 cpm /dpm with 1
the AGX-2 cartridge. Therefore, I 131 cone, uCi/ce) X 3.2E+10 will calculate the the net sample count rate in epm on the AGX- cartridge.
$ it is assumed that a G M surve meter is used 3 *** For analysis of the particulate filterto obtain tne sample count rates. The Iilter count rate was estimated fr I 131 air concentration for t 177 liter sample volume.
- 1. -
l L . .. . _ . _ . . _ . . _ . . ._. .
lyAca bA AYe +m n/ a .. i3 y w,p.s, al
, . 4 w
/ w- ,
, gn % wd ,
- s. xH 4mp -
[y, fa '
,- hyb f\ ,
a l3
,,a\M (f) l {
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PAGE 9.7 11A g TABLE 9.7.76 VLRMONT YA!TKf E FIELD DATA AT CIDCR TIME 1415 1430 (SCENARIO TIME 7:15 7:30) AIR SAMP1.E DATA (100 LITERS)4 GAMMA DOSE RATE RM.14** SAS 11 RM 14" ' CONC. PARTICULATE FLUME FI LTER SECMENT DISTANCE MAP PIC.6 RM 14 1-131 SILVER ZEOLITE NO. (MILES) ARD. (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET CPM) SITE 1400 OSH 1.36E.10 <40 AS READ <40 1.00 BLUE
<40 AS READ <40 BOUNDARY YELim' 140 OSH 1.36E.11 GREEN 14 49000 1,36E 12 <40 AS READ (40 )
0.$0 2400 1.75E.07 982 2945 701 2.00 BLUE 0 511 295 70 YELLOV 240 0 511 1.75E 08 98
' CREEN 24 OSH 1,75E.09 <40 AS READ <40 1.10 2700 OSH 1.86E.06 10405 31215 7432 3.00 BLUE 743 . YELim 270 0 511 1.86E.07 1040 3121 27 OSH 1.86E.08 104 312 74 GREEN 1800 1.12E.06 6291 18874 4494 i 4.00 1,70 BLUE OSH 629 1807 449 i YELIEV 180 OSH 1.12E.07 CREEN 16 OSH 1.12E.08 63 189 45 2.30 1200 OSH 7.10E.07 3975 11926 2840 5.00 BLUE 1193 284 "l YELIDV 120 OSH 7.10E.08 398 GREEN 12 42000 7.10E.09 (40 119 <40 l 05H 4.01E.07 2247 6741 1605 6.00 2.80 BLUE 690 YELIDV 69 OSH 4.01E.08 225 674 160 GREEN 7 24150 4.01E-09 <40 67 <40 3.50 200 1.56E.07 871 2613 627 7.00 BLUE OSH 261 62 YELIDW 78 OSH 1.56E.08 87 GREEN 3 9800 1. 5 (> E. 0 9 <40 AS READ <40 s
L i NOTES:
- Air sample data are based on a sample volume of 100 liters, if different volumes are collected. the air semple data rovided in the tables should be adjusted p rorso rt ionally . For example, if a 5J liter sample was, collected instcaa of 100 liters, divide the value given in the table by 2 (tvo) cnd provide the resulting valuu to the players.
* ** The M-14 detector efficiency for I.131 was assumed to be 0.025 com/dem with the
! silver :colite cartridge , nerefore, 1 131 conc. (uci/cc) X 5.6E409 will calculate the net sample count rate in epm on the silver zeolite cartridge.
*** The particulate filter sample count rate (cpa) was estimated from the 1 131 air concentration for a 100 liter sample.
OSH Of f. Scale High (Count rate higher than the upper scale of the instrumentation). L___ _____--m______ __.__m__m. __mm.m--_ _ _ - _ _ _ - . _ _ _ _ . _ _ . _. _mm__m___ m_ - _ . _ _ _ _ _ - -
I
- REV. 1 PAGE 9.7 11B TABLE 9.7.7b i
STATE OF VERMONT TIEL9 Dh1A AT C1DCK TIME 1415 1430 (SCENARIO TIME 7:15 7:30) i - GAMMA SURVEY DATA s WAIST AND GROUND LEVEL READINGS AIRSAMP1.EDATA{0177 WDLUM 224 LITERS)* G*M METER s FLUME C14 SED OPEN CONC AGX.2** PARTICU1 ATE * * * $ SEGMENT DISYANCE MAP WINDOW VINIX/J 1 13i CARTRIDCE FILTER NO. (MILES) AREA (tar /hr) uC1 (NET CPfu (NET CPM) ( ...... ....... ....... ......... (mR/.br)
... .-.. ...../.cc ... ......... ..........
i
' 1.00 SITE BWE 1400 2f00 1. 36 E.10 AS RFAD .t3 0 BOUNDARY YELIDW 140 280 1.3bE.11 AS READ <50 GREEN 14 28 1.36E.12 AS RfAD <$0 2.00 0.50 BWE 2400 4800 1.7$E.07 5610 1245 i YEL1DW 240 480 1.75E.08 $61 124 r 1 GREEN 24 48 1,75E.09 56 <50 >
I 3.00 1.10 BLUE 2700 5400 1.86E.06 59457 13192 t YELLOW 270 540 1.86E.07 5946 1319 GREEN 27 54 1.86E 08 595 132 3
] 4.00 1.70 BWE -1800 3600 1.12E.06 35951 7977
+
YELLOW 180 360 1.12E*07 3595 798 j GREEN 18 36 1.12E.08 ,360, 80
]
5.00 2.30 BWE 1200 2400 7.10E.0' 22716 5040 s YELIDW 120 240 7.10E 08 2272 504 1 GREEN 12 24 7.10E.09 227 50.40 j$ 6.00 2.80 BLUE 690 1380 4.01E 07 12840 2849 YELLOW 69 138 4 . 01 E. 08 1284 285 3 GREEN 7 14 4.01E.09 128 <50 d 7,00 3.50 BLUE 280 560 1.56E.07 4978 1104 YELLOW 28 56 1.$6E.08 498 110 ; GREEN 3- 6 1.56E.09 AS READ <50 t t
- j-I I 4*
t .
-4 ,w 3 NOTES: 'i
- Air sample data are based t.n .4 sample volume of 177 liters. If dif ferent volumes
] are collected, the air sample data provided in the tables should be adjusted proportionally. For example if a 8v liter sam
- divide the value given in r.e table by 2 (two)ple and was collected provide the resulting instead value of 177toliters.
the players. (' 4 *4 The Ludlum 2220 detector ef ficiency for 1 131 was assumed to be 0.080 cpm /dpm with ' ' the AGX.2 cartridge. Therefore, 1 131 conc. (uCi/cci X 3.2E+10 will calculate the the net samplo count rate in epm on the AGX.2 cartridge. ^ d' *** For analysis of the particulate ? titer 1 *: is annused that a 0 M surve meter is used to obtain the sample count rates.Thetiltercountratewasestimatedfromthe I.131 air concentration for a 177 liter sample volume. l 1
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9.7-12A T ABLE 9 . 7 . 8 a
. VERMONT YANKEE T1 ELD DATA AT CLOCK TIME 1430 1445 (SCENARIO TIME 7:30 7:45)
AIR S AMPLE DA1 A (100 1.1TERS)* CA W DOSE RATE RM 14** SAM.11 RM 14*** CONC. PARTICULATE PLUME FILTER P10 6 RM.14 1 131 SILVER 2001.1?E
"! SEGMENT DISTANCE MAP
. .b . . . . . .I'W. . f
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1.00 SITE BLUE 1300 OSH 7.41E.11 AS READ 130 OSH 7.41F.12 (40 AS READ <40 BOUNDARY YEllDW <40 <40 GREEN 13 45500 7.61E.13 AS READ 1.0$E.07 56B 1703 42n
- 2.00 0.50 BLUE 2400 0$11 1.05E.08 5 ') 176 42
.' YELIEV 240 OSH
<40
! GREEN 24 OSH 1.05E 09 <40 AS READ 3100 2.04E.06 11407 34222 8148 3.00 1.00 B1xE OSH 2.04E.07 1141 3422 815 s YELLOW 310 OSH 81
< GkEEN 31 05}l 2.04E.06 114 342 1700 1.11E.06 6222 18667 4444 4.00 1.60 SLUE OSH 1.11E.07 622 1867 444
<I YE1. LOW 170 OSH 44 GREEN 17 OSH 1.11E.08 62 187 o
1200 7.41E.07 4148 12444 2963 4 5.00 2.20 BLUZ OSH 7.41E.08 415 1244 296 j YELLOW 120 OSH
<40 CREEN 12 42000 7.4 (E 09 41 124 y
5.06E.07 2835 8504 2025
. 6.00 2.60 BLUE 860 OSH 5.06E.08 283 850 202 YELIEW 86 OS}i
'f GREEN 9 30100 5.06E.09 <40 85 <40 4
O ih 2.99E.07 1673 5019 1195 7.00 3.30 BLUE 530 120 YELI.OU 53 CSH 2.99E 08 167 502 i OLEEN 5 if550 2.99E 09 <40 50 <40 i 681 2043 486
; 8.00 4 00 BLUE 220 0.:H 1.22E 07 49 YELLOW 22 OSH 1.22E.08 68 204 1
7700 1.2?E.09 <40 AS RLAD <40 CREEN 2 [ e n.
', NGTES:
- Air sample data are based on a sample volume of 100 liters. If different volumeu are collected, the air sample data provided in the taoles should be adjusted 0 liters, i proportional 1r. Tor the value example. if a 50 liter saa given in the table by 2 (two)ple was collected instead of 10and provide the res divide the players.
y ** The RM 14 detector et'ficiency for I 13i was amumed to be 0.025 cpm / dom with theX 5.6F409 vill calculate
- ,, i lv e t zeolite I.131 conc. (uCi/cc) samplecartridge. Therefore, cpm on t he silver reolite cartridge.
1 i the net count rate in
*** The particulate filter sample count rate (cpm) was ev.imat ed from the 1-131 air concentration for a 100 liter saeple.
OSH Off Scale High (Count rate higher than the upper scale of the. instrumentation).
-- --------m____ _____
I i ! 1
, REV 1 PACE 9.7 128 TABLE 9.7.8b ,
( STATC OF VERMONT FIELD DATA AT CLOCK TIME 1430 1445 (SCENAR10 TIME 7:30 7:45) CAMMA SURVEY DATA AIR SAMPLE DATA 77 LTTERS
- VAIST AND CROUND LEVEL RE/. DINGS LUDLUM 2 0 G .M ME E8'. '
PLUMF CIDSED OPEN CONC ACX.2** PARTICULATE ***
$CGMENT DISieNCE MAP WINDOW WINDOW I.13i CARTRIDGE FILTER .
NO. (MILL $) AREA (mR/hr) (mR/hr) uCi/cc (NET CPM) (NET CPM) i t i
'? 1.00 SITE BLUE 1 00 2600 7.41E.11 AS READ <SO BOUNDARY Yellow 30 250 7.41E.12 AS READ <50 GREEN 13 2e 7.41E.13 AS READ <$0 ,}_
2.00 0,$0 BLUE 2400 4800 1.05E.07 3360 74$ 4 YELIOV 240 480 1 0$E 08 336 75 i CREEN 24 48 1.05E 09 AS READ <50 h 3.00 1.00 BLUE 3100 6200 2.04L.06 -65185 14463 '4 YELLOW 310 620 2 . 04 E. 0 7 6519 1446 CREEN 31 62 2. 04 E.08 367 81
,9 1 4.00 1.C0 BLUE 1700 3400 1.11E.06 35556 7889 YELLou 170 340 1.11E.07 3556 789 GREEN 17 34 1.11E 08 200 <50 g
5.00 2,20 BLUE 1200 2400 7.410 07 23704 5259 YELLOV 120 240 7.41E 08 2370 526 7.41E 09 133 <50 j 74 GRECl 12 6.00 2.80 BLUE 860 1720 5.06E.07 16108 3594 0 YELLOW 86 172 5.06E 08 1620 359 GREEN 9 17 5.06E 09 91 <50
) 7.00 3.30 BLUn 530 1060 2.99E 07 9560 2121 1 YELLOW 53 106 2.99E.08 956 212
. GREEN 5 11 2.99E.09 54 <50 s
8.00 4.00 BLUE 220 440 1.22E 07 3891 863 j YELLOW 22 44 4 1.22E 08 1.22E.09 389 AS READ 86
<50 -
i GF.EEN 2 i e t 7 i 1 NOTES:
- Air sample data are based on a sample volume of 177 licers; If dif ferent volumes
; are collected the air sanple data provided in the tables should be adjusted proportionally,.-For example, if a 89 liter sam 1 divids the value given in the table by 2 -(two)ple andwas collectedresulting provide-the insteadvalue-to of 177 liters.
the players, d ** J The the AGX-2Ludlum 2220 detector cartridge. Therefore,efficiene(31 1 for1131wasassumedtobe0.080e$ cone. (uct/cc)-X 3.2E+10 will ate'thedpm cal vith i the net sample count rate in cpm on the AGX.2 cartridge.
$ it is assumed that a' G.M surve meter is used -;
*** For analysis of the particulate filtertoobtainthesamplecountrates.Thefiltercountratewasestimatedfromth 1 131 Air concentration for a 177 liter 1.taple volure, i
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l 6 6 9.7 13A , i TABLE 9.7.9a D VERM0tri YANKEE FIELD DATA AT CLOCR TIME 1445 1500 (SCENARIO TIME 7:45 8:00) AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM-14** SAM.11 RM 14*** ! CONC. PARTICULATE I PLUME FILTER SEGhldT DISTANCE MAP PIC 6 RM 14 1 131 SILVER ZEOLITE AREA (mR/hr) (CPM) uC1/cc (NET CPM) (NET CPM) (NET CPM) j NO. (MILES)
'5bb bbb ~ 'h555k'kb ~ 'b b'" "Eh kkkb "b5b
, '~$$b0 ~ kiTb "'5Lbk 140 OSH 7.41E. 1
<40 AS READ <40 ;
BOUNDARY YELLOW <40 <40 GREEN 14 49000 7.41E 2 AS READ 2900 1.05E.07 588 1763 420 2.00' O.60 BLUE OSH 1.05E.08 59 176 42 4 YELLOV 290 OSH
<40 4 GREEN 29 CSH 1.0$E 09 <40 AS READ
-e 1.10 3100 OSH 1.98E 06 11062 33185 7901
.i 3.00 BLUE 1.98E 07- 1 06 3319 790 .* YELLOW 31 OSH 'l 3 OSH 1.98E 08 11 332 79 CREEN 1.11E 06 6222 18667 4444 4.00 1.60 BLUE 1700 OSH 1867 444 YELLOW 170 OSH 1.11E.07 612 44 17 OSH 1.11E 08 61 187
.p _CREEN 2.30 1000 OSH 6.79E.07 3002 11407 2716 k 5.00 BLUE 6.79E.08 380 1141 27?
- i YELLOW 100 -0SH CREEN 10 35000 6.79E.09 <40 114 <40 -
830 4.81E-07 2696 8089 1926 6.00- 2.90 BLUE OSH 4,81E 08 270 809 193 i YELLOV 83 OSH GREEN 8 29050 L.81E 09 <40 81 <40 3.40 620 OSH 3.50E.07 1960 5880 1400 7.00 BLUE 588 140
$ YELLOW 62 OSH 3.50E 08 196 i~ CREEN 6 21700 3.50E 09 <60 59 <40 r 3
400 2.19E 07 1224 3671 874 8.00 4.00 BLUE OSH 122 367 87-YEllDV 40 OSH 2.19E 08 I CREEN 4 14000 2.19E 09 <40 AS READ <40 r 9.00 4.60 BLUE 170 OSH 9.26E 08 519 1556 370
<40
) YELLOW 17 OSH- 9.26E-09 52 156 GREEN 2 $?b0 9.26E 10 <40 AS READ (40 1
d i 2' , t i
. NOTES:
- Air sample data are based on a semple volume of 100 liters. If different volumes 1
<re collected, the air sample data provided in the tables should be ad usted of 100-liters,
, proportionally.
divide the value For given example, in the table if a by 502liter sam was collected insteaand provide (two)ple the resultin the players. J ** The RM 14 detector ef ficiency for I 131 was assumed to be 0.025 epm /dpm with the silver 1 131 conc. (uC1/cc) X 5.6E+09 will calculate. j the netzeolite samplecartridge. count rateTherefore, in cpm on t he silver zeolite cartridge. 4
} *** The particulate filter sample count rate (cpm) was estimated from the 1 131 air concentration for a 100 liter sample.
OSH 10ff-Scale High (Count rate higher than the upper scale of the inst rumentation) .
REV. 1 PACE 9.7 13B TAELE 9.7.9b STATE OF VERMONT FIELD DATA AT CLOCK TIME 14451500 ($CENAR10 TIME 7:45 8:00) CAMMA SURVEY DATA AIR SAMPLE DA*iA (177 LITt RS)* VAIST AND GROUND LEVEL READINGS LUDIUM 2220 G.M METER PUOME CLOSED OPEN CONg. AGX 1** PARTICULATE *** SECMENT DISTANCE HAP VINDOW VINDOV 1.ls1 CARTRtDGE FILTER AREA (mR/hr) uCi (NET CPM) (NET CFN) NO. (MILES)
....... ....... ......... (mR/.hr)
... .... ...../.cc 1.00 SITE BLUE 1400 2800 7.41E.10 AS READ <30 BOUNDARY YE110V 140 280 7.41E.11 AS READ <50 GREEN 14 28 7.41E.12 AS READ <50 2.00 0.60 BLUE 2900 5800 6.79E 07 21728 4821 YELLOW 290 580 6.79E.08 2173 482 GREEN - 29 58 6.79E.09 217 <50 3.00 1.10 BLUE 3100 6200 1.98E.06 63210 14025 YEllDV 310 620 1.98E.07 6321 1402 GREEN 31 62 1.98E 08 632 140 4.00 1.60 BLUE' 1700 3400 1.11E 06 35556 7889 YEllDV 170 340 1.11E.07 3556 789-GREEN 17 34 1.11E.08 356 79 5.00 2.30 BUUE 1000 2000 6.79E.07 21728 4821 YELLOV 100 200 6.79E.08 2173 482.10 GREEN 10 20 6.79E.09 217 <$0 6.00 2.90 BLUE 830 1660 4.81E.07 15407 3419 YELLOV 83 166- 4.81E.08 1541 342 GREEN 8 17 4.81E.09 154 <50 7.00 3.40 BLUE 620 1240 3.50E.07 11200 2485 YELLOV 62 124 3.50E.08 1120 248 GREEN 6 12 3.50E.09 112 <50 ,
8.00 4.00 . BLUE - 400 800 2.19E.07 6993 1551 YEllDW 40 80 2.19E.08 699 155 GREEN 4 8- 2.19E.09 70 <50_ 9.00 4.60 BLUE 170 340 9.26E.08 2963 657 YELLOV 17 34 9.26E.09 296 66 GREEN 2 3 9.26E.10 AS READ <50 NOTES:
- Air somple data are based on a sample volume of 177 liters. If dif ferent volumes
-are-collected, the air sample data provided in the tables should be adiusted proportionally. For example. if a 89 litor sam j -
livide the value given in the table by 2 (two)ple was and collected provide instcaa value the resulting of 177toliters, i the players,
** The Ludlum 2220 detector efficiency for 1 131-was assumed to be 0.080 cpm /dpm with the- AGX.2 cartridge. Theref ore,1 131 conc. .(uci/ce) X 3.2E+10 vill calculate the
.the net sample count rate in cpm on the AGX.2 cartridge.
*** For analysis of the partic.ulate filter it is assumed that a G.M survey meter is used 4
to obtain the sampic coun*c rates. The filtercount rate was estimated from the I-131 air concentration for a 177 liter sample volume. O 1
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9.744A TABLE 9.7.10a VERMONT YANKEE FIELD DATA AT CthCK TIME 1500 1515 (SCENAR10 TIME 8:00 8:15) AIR SAMPLE DATA (100 LITERS)* CAMMA DOSE RATE RM.14'* SAH 11 RM.14*e+ CONC, PARTICULATE PLUME PIC 6 RM 14 1 131 SIINER ZEOLITE riLTER
$ECMENT DISTANCE MAP (NET CPM)
No. (MILES) AREA (mR/hr) (CPM)
~"~'
uC1/cc (NET ' CPM) (NET~ CP!:)
~~~$$0 ~ ~$iTk ~ ~kthE ''ihbb~ 'bSH '5$$5kIb9 $5b'~'"SRbEb Ebb
<40 !
BOUNDARY YELLOW 120 OSH 2,53E.10 <40 AS READ 42000 2.53E.11 <40 AS READ <40 GRELN 12 2200 9.26E.07 5185 15556 3704 2.00 0.70 BLUE OSH 9.26E.08 519 1556 370 ; YELLOW 220 OSH <40 22 OSH 9.76E 09 52 1$6 GREEN 2100 OSit 1.48E 06 8296 24889 $926 3.00 1.40 BLUE 1.48E 07 830 2489 593
- YELLOV 210 OSH 59 GREEN 21 OSH 1.48E 08 83 249 1500 OSH 9.88E.07 5531 16593 L951 L
-4.00 -1.90 BLUE OSH 9.88E.08 553 1659 395 YELLOW 150 166- <40 GREEN 15 OSH 9.88E.09 55 r -
OsH 5.90E 07 3353 10059 2395 5.00 2.40 BLUE 1000 240 YEL10W- 100 OSH 5.99E 06 335 1006 i 10 35000 5.99E.09 <40 101 <43 1 GREEN 1 680 OSH 3,95E.07 2212 6637 1580 6.00 3.00 BLUE 3.95E 08 221 664 158 YELID'.' 68 OSH <40 3 GREEN 7 23800 3.95E.09 <40 66 j. 3.09E.07 1728 5185 1735
'7.00 3.60 -BLUE $70 CSH
$19 123 4
3.09E.08 173 i YELLOW 57 OSH 6 19950 3.09E.09 <40 52 <40 > GREEN 450 2,47E.07 1383 4148 988 8.00 4.10 BLUE OSH 2.47E 08 138 415 99 YELLOW 45 OSH 15750 2.47E.09 <40 AS READ <40 'l Vi "3N 5 1.60E.07 899 2696 642 1 9.00 4.70 B1UE 300 CSd 1,60E.08 90 270 64 l YELLOW 30 0.sH 1.60E.09 <40 AS READ <40 GRELN 2 10500 6.79E.08 380 1141 272 10.00 5.30- BLDE 130 OSH 6.79E 09 <40 114 <40 YFLLOW 13 45500 CREEN 1 4550 6 .- 7 9 E + 10 <40 AS READ <40 , t i j NOTES:
- Air sample data are based on a cample volume of 100 liters. If dif feront volumes are collected the air sample data rovided in the tables should be ad usted of 100 liters, p ropo r tionally, . For example. if a 5 liter sam divlde the value given in the table by 2 (two)ple andwas provide collected instea value to the resulting i the players.
!I ** 'Ibe RM.14 detector ef ficiency for I.131 was assumed to-be 0,025 cpm /dpm with the
'* silver zeolite cartridge, Therefore, 1 131 conc. (uct/cc) X 5.6E+09 will calculate L: the not sample count rate in epn on the silver geolite cartridge. t *** The particulate filter sample count rate-(epm) was estimated frca the I.131 2*r concentration for a 100 liter sample 053 - Off Scale High (Count rate hi6 her than the upper scale of the instrumentation) . 1 i.
.-,.,..-----..,,,....__m,,_,.,_.,~,-,-____,-,,.-_.,-, s , , , , _ . _ , . - _.-,,..-s. ~,-__...-,---,_,_....,.m.-
I 4 REV. 1 PAGE 9.7 14B TABLE 9.7.10b
\ 8:15)
STATE OF VERMONT fiEIS DATA AT C1DCR TIME 15001515 (SCENARIO TIME 8:00 CAMMA SURV Y DATA AIR SAMPLE DATA (t77 LITERS)* + 4 3 UAIST AND CROUNS LE*lEL READINGS LLDLUM 2220 U.M METER j PLUME CLOSED OPEN CONC AGX.2** P ARTI CULAT E* * *- SECKENT DISTANCE HAP WINDOW WINDOW 1 13i CARTRIDGE FILTER (mR/hr) (tuR/hr) uCi (NET CPM) (NET CPH) I NO. (MILES) AREA
......... ........ ...../.cc ... ......... . . . . . . . - . . .
1200 2400 2.53E.09 81 <50 1.00 SITE BLUE 2.53Ev10 AS RLAD <50 B.0UNDARY YELIDW 120 240 GREEN 12 24 2.53E.11 AS READ <S0 , 2200 4400 9.26E.07 29630 6574 j 2.00 0.70 YEllDW BLUE 220 440 9.26E.08 2u63 657 i, GREEN 22 44 9.26E.09 296 66 J 3.00 1.40 81ME 2100 4200 1.4'E 06 47407 10519 '. YELLOV 2j0 420 1.48E.07 4741 1052 GREEN t1 42 1.48E.08 474 105 j.
! 4.00 1.90 PUUF 1500 3000 9.88E.07 31605 7012 YELIDW 150 300 9.88E.00 3160 701 GREEN 15 30 9. 8 B E. te9 316 70
) 4251 5.00 2.40 BIME 1000 200J 5.99F.07 19160 I YELLOW 100 200 5 . 9 9'd . 0 8 1916 425 GREEN 10 20 5.9tE.09 192 <50 j
6.00 3.00 E LUE 680 1160 3.95E 07 12642 2805 J YELLOW 68 136 3 45E.08 1264 280 GRE EN 7 14 ?.95E.09 126 <50 4 7.00 3.60 BUUE 570 1140 3.09E.07 9877 2191 7 YELIDW 57 114 3.09E.08 988 219
; GREEN 6 11 3.09E.09 99 <50
; 8.00 4.10 BLUE 450 900 2.47E 07 7901 1753 Yellow 45 90 2.47 E.08 790 175
,' 9 i
GREEN 5 9 2.47E.09 79 <50 1
. 9.00 4.70 BLUE 300 600 1.60E.07 5136 1140 YELLOW 30 60 1.60E 08 514 114 _
CREEN 3 AS READ 1.60E.09 51 <$0 10.00 5.30 BLUE 130 260 6.79E-08 2173 482 YELLOW 13 26 6.79E-09 217 <50 g GREEN 3 6.79E.10 AS READ <50
) 1 1
l 4 NOTES:
- Air sample data are based on a sample voluna of 177 liters. If different volumes
*4 are collected theFor air example, sample drta if a k)3rovided 8 liter sam in the tables should be adjusted d
pro div de $ortionally. the value given in the table by 2 (two)ple andwas collected provide insteadvclue the resulting of 177 - toliters, i the players. N for1131wasassumedtobe0.080e$atethedpm with Q **TheLudlum2220detectorofficienef31 the AGX-2 cartridge. Therefore, I. cone. (uci/cc) X 3.2E+10 vill cal t the net saaple count rate in epm on the ACX.2 cartridge.
=4
_1 *** 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 177 liter sample volume.
_ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ ________._________________.___.______________._____.______.____________m_ _ _ _ _ _ . _ _ _ _ .
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9.7 15A
*[ABLE 9.7.11a VERMONi YANKEE TIELD DATA AT CIDCK TIME 1515 1530 (SCEN/.RIO TIME 8:15 6:30)
AIR S AMPII. DATA (100 13.TERS)* CAMMA D'iSt. RATE PM 14** SAM.11 RM.14*** CONC, PARTICULATE PLUME FILTER SEGMENT DISTANCE MAP PI C . f- M 14 1 131 SILVER 2.00 LITE No. (MILES) ARIA (mR/hr) (CPM) uCi/cc (NET CPM) (NET CPM) (NET COM) l ...... ..... . ....... ......... ........ ......... ......... ........ 1100 3.52E.09 <40 59 <40 1.00 SITE BLUE OSH
<40 BOUNDARY YEtthW 110 0 511 3.5/E.10 <40 AS READ
<40 CREEN 11 38500 3.520 11 <40 AS RIAD 0.80 blue 1800 OSH 8.64E-07 4840 14519 3457 2.00 484 346 YELLOW 180 OSH 8.64E+08 1452 GREEN 18 OSH 8.64E 09 48 145 <40 3.00 1.70 BLUE 1300 OSH c1. 02 E. 0 7 4494 13481 3210 YELIDW 130 OSH 8.02E 08 449 1348 321 GREEN 13 45500 8.02E 09 45 135 (40 4,00 2.20 DLUE 1100 OSH 6.79E.07 3802 11407 2716 si YELLOW 110 OSH 6.79E 08 380 1141 272 GREEN 11 36500 (.79E.09 <40 114 <40 5.00 2.70 BLUE 900 OSH 5.37E-07 3007 9022 2148 YELLOV 90 OSH 5.37E.08 301 902 215
!- GREEN 9 31500 5.37E.09 <40 90 <40 6.00 3.20 Bl.UE f40 OSH 3.64E.07 2040 6119 1457 1 YELLOV 6 t. OSH 3.64E 08 204 612 146 I GREEN 6 22400 '.64E.09 a <40 61 <40 3.80 460 2.47E.07 1383 4148 988 7.00 BLUE OSH 415 99 YELLOV 46 OSH 2.47E-08 138
' CREFN 5 16100 2.47E 09 <40 AS RIA0 <40 4.40 400 2.22E-07 1244 3733 889 6.00 BLUE OSH YELIDW 40 OSH 2.22E.08 124 373 89 CREEN 4 14000 2.22E.09 <40 AS READ <40 9.00 4.90 BLUE 330 OSH 1.79E.07 1002 3007 716 i YELLOW 33 OSH 1.79E.08 100 301 '
72 GREEN 3 11550 1.79E.09 <40 AS READ <. io 10.00 5.50 BLUE 230 OSH 1.17E-07 637 1970 *69 YEl. LOW 23 OSH 1.170-08 66 197 47 GREEN 2 8050 1.17E 09 <40 AS READ <40 11.00 6.10 BLUE 100 OSH 5.43E.08 304 M3 217 Y ELLOW 10 35000 5.43E 09 <40 91 <40 GREEN 1 3300 5.43E.10 <40 AS READ <40
} NOTES:
Air sample data are based on a san.p3 e volune of 100 litern. If dif f erent volun.cs ate collected. the air sarople data provided in the tables should Ee adjustec. poportionally. For exanple. if a 50 liter sam andwas div.4e the value given in the table by 2 (tvo)ple collected rvcvide instead nf t'aa resulting 100toliters, value the p.. vers.
** The RM-14 detector efficleacy fu I 131 was assuicd to be 0,025 cpm /dpa with the
; silver eolite cartridge. Th'erefore, 1 131 cone. (uCi/cc) X 5.6E+09 v111 calculate 4,
the net samp. count rate in epm on the silver zeolite carcridge. i *** The particulate 'lter sar:ple count rate (cpm) was estimated from the I.131 air 4 concentration for 4. 100 liter sample. OSH Off-Scale High (Count rate higher than the upper scale of the instrumentation).
l l b* - t l REV. 1 PAGE 9.7 15B , i TABLE 9.7.11b STATE OF VERMONT FIELD DATA AT CLOCK TIME 1515 1530 (SCENARIO TIME 8:15 8:30) d GAMMA SURVEY DATA AIR SAMPLE DATA (177 1.1TERS)* VAIST IND CRotrND 1.EVEL READINGS LUDLUM 2220 G M METER PLUME CIDS ED OPEN CONC AGX.2** PARTICUl ATE * *
- SEGMENT DISTANCE MAP WINDOW WINDOW I+13i CARTR1DGE FILTER i .."?.. !"tE'S! ..^^f^. -.!?"('.'!!. !!?fh!!. .."!(!!.!"!!.?!"! ("f?.?!"!.. '
'j t 1.00 f.1TE BOUNDARY YELLOW BLUE 1100 110 2200 220 3.52E 09 3.52E.10 AS READ 113 <50
<$0 t
- GREEN 11 22 3.52E.11 AS READ <50 a
< 2.00 0.80 BLUE 1800 3600 8.64E.07 27654 6136
.h' YELLOW 180 360 8.64E.08 2765 614 GREEN 18 36 8.64E.09 277 61 1 3.00 1.50 BLUE 1300 2600 8.02E.07 25679 5698 2 YELLOW 130 260 8.02E.08 2566 570
- 4 GREEN 13 26 8.02E-09 257 57 8 4.00 2.20 BLUE 1100 2200 6.792 07 21728 4821 YE1J1nt 110 220 6.79E.08 2173 482 GREEN 11 22 6.79E 09 217 <50 ,
j 5.00 2.70 BLUE 900 1800 5.37E 07 17185 3813 . i YEL1DW 90 If? 5.37E 08 1719 331 ! GRE EN 9 A8 S.37E.09 172 <50 1, j 6.00 3.20 BLUE 640 1220 3.64E.07 11654 258o s YELLOW 64 128 3.64E.08 1165 259 GREEN 6 13 3.64E.09 117 <50 h 7.00 3.80 BUUE 460 920 2.47E.07 7901 1753 4 YE11DW 46 92 2.47E 08 790 175 .d - GREEN 5 9 2.47E 09 79 <50 8.00 4.40 B Ut'E 400 800 2.22E 07 7111 1578 l YELLDW 40 80 2.22E.08 711 158 GREEN 4 8 2.22E 09 71 <50 7 9.00 4.90 Bl.UL 330 660 1.79E 07 5728 1271 4 4 YE1 JIM 33 66 1.79E.08 573 127 GREEN 3 AS READ 1.79E 09 57- (50 10.00 5.50 BLUE 230 460 1.17E O' 5753 833 YELLOW 23 46 1.17E 08 375 83 , I GREEN 2 5 1.17E.09 AS READ <50 1
- A1.00 6,10 BLUE 100 200 5.43E 08 173L 386 1/4 YELEDW 10* 20 5.43E.09 <$0 l GREEN . 2 5.43E.10 AS READ <50 NOTES:
d"
- Air sample data are based on a sample volume of 177 liters. If different volumes i ~ ace collect.ed,- the air annple data provided in the tables should be adjusted proportionally. For exanple if a 69 liter sen
( divide the value (iven in the table by 2 (two)ple was and collected provide instesovalue the resulting of 177 to liters, -3 the players.
* ** The the AGX.2 tudlumcartridge. 2220 detector Therefore,efficiene 1 31for1131wasacumedtobe0.080cb$dpmwith cone. (uC1/cc) X 3.2F&l0 will cal ate the
_j the net sample count rate in cpm on the AGX.2 cartrid6 *. , it is assured that a G.M survey meter is nuen 4 j *** For to ebtain analysis theof the particulate sampla count rates. filter The[ilter count rate was estimated from the L 1 131 air concentration for a 117 litet samplu volume.
b
?
a i VERMONT YANKEE NUC1. EAR POVER STATION :. EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1991 P i i 4 l 10.0 tiETE0EDJ4191Q,AL . DATA I f l 4 0
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O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.1 Q!i "ITE METEOROLOGICAL DA?A O
- O
- _ _ . - . . - _ . _ _ . ~ . _ . - .
Rev. O L/" Page 10.1 1 VERMONT YANKEE !TUCLEAR POWER STATI")N EMERGENGY RESPONSE PREPAREDNESS EXERCISE 1991 10.1 QN SITE METEOROLOGICAL DATA (07:00 - 08:30) lin
-07:00 07:15 07:30 07:45 08:00 08:15 08:30 LOWSAV AVG 1DWER 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 LOWER D!R SIGMA 22 20 18 22 24 23 21 UPWDAV AVG UPPER DIklDEG5 185 4d3 180 177 179 178 177 UPWDSD AVG UPPEh DIR SIGMA 20 18 19 17 16 19 20 LOTTAV AVG LOWER TEMP DECS (F) 40.0 42,0 42.5 43.2 43,7 44.0 44.5 1DDTAV AVG LOWER DELTA.T DEGS (F)* 1.0 0.9 0.8 0.7 0.6 0.5 0.4
- UPDTAV AVG '.u *:'l DELTA T DEGS (F)* 1.5 1.3 1.3 1.1 1.0 0.9 0.8 SOLRAV AVG e Ae. ~.AD 1ANGS 0.35 0.40 0.42 0.46 0.50 0.55 0.63 RAINTO 13 'N <
FALL INGHES 0.00 0.00 0,00 0.00 0.00 0.00 0.00
~~
FO ~ 08:45 09:00 09:15 09:30 09:45 10:00 10:15 LOWSAV AVG LOWER SIEED 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
-LOWDAV AVG LOWER DIR DEGS 170 168 166 159 160 157 157
-LOWDSD AVG 14WER DIR~ SIGMA 22 20 18 22 24 23 21
- UPWDAV AVG UPPER DIR DEGS 175 -- 173 170- 167 169 168 167 UFWDSD AV' UPPER D SIGMA 20 18 19 17 16 19 20 LOTTAV AVG LOWER M DEGS (F) 44.7 45.0 45.5 46.2 46.7 47,0- 47.5
. LODTAV AVG LOW 5'" % T DECS (F)* 0.3 0.2 0.2 0.1 0.0 -0.2 0.4 UPDTAV AVG UPJ A T DEGS (F)* 0.6 0.5 0.4 0.3 0.2 0.1 -0.1-SOLRAV AVG SOL A tc 1ANGS 0.35 0.65 0.70 0.70 0.70 0.72 0.73-RAINTO 15 MIN . r% ALL INGHES 0.00 0.00 0.00 0,00 0.00 0.00 0.00
*EQIES:
- 1. The height differential (ah) for the lower delta temperature on the primary tower is 165 ft.
- 2. The height differential (Ah) for the upper delta temperature on the primary tower is 262 f t.
LO
-- . - - . - ~ . - .. _ - ..- _
Rev, O Page 10.1 2 VEPJt0NT YANKEE NUCLEAR POWER STATION
- EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.1 ON SITE METEOROLOGICAL DATA
'(10:30 - 12:00.1 112.1 10:30 10:45 11:00 11:15 11:30 11:45 12:00
- LOWSAV AVG IAWER SPEED MPH 2.0 1.8 1.6 1.5 1,3 1,1 1.3 UPWSaV AVG UPPER SPEED MPH 3.0 2.9 2.7 2.5 2.4 2.2 2.4 LOWDAV AVG LOVER DIR DEGS 150 145 140 135 130 125 120
- LOWDSD AVG LOWER DIR SIGMA 22 20 18 22 24 23 21 UPWDAV AVG UPPER DIR DEGS 185 160 147 136 129 125 123 UPVDSD AVG UPI'ER DIP. SIGMA 20 18 19 17 16 19 20 LOTTAV AVG LOWER TEMP DEGS (F) 48.0 48.4 48.5 49.2 49.7- 50.0 $2.5 1DDTAV AVG LOWER DELTA T DEGS (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 1.0 -1,1 1.2 SOLRAV AVG SOLAR RAD IANGS 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
.(,12:15 - 13:45) nme 12:15 12:30 12:45 13:00 13:15 13:30 13:45 1DWSAV AVG IDWER 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 2.5 2.4 2.1 IDWDAV AVG IAVER DIR DEGS 120 118 116 119 120 117 118 LOWDSD AVG IAVER DIR SIGMA 22 20 18 22 24 23 21 UPWDAV AVG UPPER DIR DEGS 125 123 120 112 110 112 115 UPWDSD AVG UPPER DIR SIGMA 20 18 19 17 16 19 20-LO'iTAV AVG IAWER TEMP DEGS (F) 53.7 54.0 55.5 -56.2 56.7 57.0 57.5 IDDTAV AVG LOWER DELTA 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 SOIAR RAD LANGS 1.25 1.27 1.29 1.30- 1.35 1.33 1,30 RAINTO 15 MIN EAINFALL INCHES 0.00 0,00 0.00 0.00 0.00 0.00 0.00
*g.
- 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.
l l D
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) lin 14:00 14:15 14:30 14:45 15:00 15:15 15:30 LOWSAV 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 1hWDAV AVG IDWER DIR DEGS 117 115 115 110 115 110 115
-IDVDSD AVG 1hWER DIR SIGMA 21 22 20 18 22 24 23 UPWDAV AVG UPPER DIR DEGS 120 118 109 111 112 116 118 UPVDSD AVG UPPER DIR SIGMA 20 20 18 19 17 16 19 1DTTAV AVG 1DWER TEMP DEGS (F) 57.5 57.3 57.1 56.8 56.4 56.0 55,7 LODTAV AVG IDWER 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 SOLAR RAD LANGS 1.30 1.30 1.22 1.14 1.05 0.92 0,80 .RA1NTO 15 MIN RAINFALL INCHES 0.00 0,00 0.00 0.00- 0.00 0.00 0.00 (15:45 - 17:15) 15:45 16:00 16:15 16:30 16:45 17:00 17:15 LOWSAV AVG LOWER SPEED MPH 2.5 2,8 2.6 2.7 3.0 2.8 2.7 UPWSAV AVG UPPER SPEED MPll 3.5 3.9 3.7 3.8 4.3 4.1 4.4 IDVDAV AVG LOWER DIR DEGS 100 95 90 87 83 74 69 LOWDSD AVG LOVER DIR SIGMA 22 20 18 22 24 23- 21 UPWDAV AVG UPPER DIR DEGS 105 96 87 78 72 C7 6 ', .UPWDSD AVG UPPER DIR SIGMA 20 18 19 17 16 19 *0 1DTTAV AVG LOWER TEMP DEGS (F) 55.0 54.4 53.7 53.2 52.7 52.0 51.5 - LODTAV AVG IDWER 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 LANGS 0.45 0.20 0.10 0.05 0.00 0.00' O.00 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 dQIES:
1.The height differential (th) for the lower delta temperature on the primary tower is 165 f t. 2.The height differential (ah) for the upper zielta temperature on the primary to.ier is 262 f t. lO
.m_ sa.,~.- _w.*a4, A A A_ ,_.: L- /e 14AL 4 b4-4 -. 4 a. . J e a ,.aa- n A =
E EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.2 CENERAL AREA NATIONAL VFATHER SERVICE (NWS) FORECASTS O
Rev. O Page 10.2 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE O 1991 10.2 GENERAL AREA NWS FORECAST (See Note) - Synopsis (07:091 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. yalid (07:00-13:00) Winds from the south at %-5 MPH, swinging around to the southeast early this af ternoon and becoming 1-3 MPH. Temperature in the upper 40's increasing to the low 50's. Chance of a shower. _, valid (13:00-19:00) 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. Temperatures in the low 40's. Northerly winds from 2-5 MPH. PLANT / EOF WEATHER OBSERVATIONS (See Note) - Valid (07:00,1s:00) Ilmt General Observations i 07:00 Partly cloudy with light to moderate winds. p' 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 c;oudy with light winds. 12:00 Partly cloudy with light winds. 13:00 Partly cloudy with light winds, 14:00 Partly cloudy with light winds. 15:00 Mostly cloudy with light winds. NOTE: GENERAL AREA NWS FORECASTS SHOULD BE PROVIDED UPON REOUEST. PLANT / EOF WEATHEB OBSERVATIONS WILL BE POSTED AS APPROPRIATE. 9
Rev. O Page 10,2 2 t ( VERMONI YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.2 VERMONT YANKEE SITE FORECAST To be provided to the ESC Meteorologist by the ESC Controller at 09:00. WEATHER FORECAST FOR SITE: VERMONT YANKEE Date of Forecast: 11-06-91 Time of Forecast: 09.00 Current Site Meteorology (as of 09:00 ): Wind speed Detta Tetunerniure SinNiity hecipitation Lme 1c,ry2t J h rection
% n11 Limer 2.8 MPil ItA DEO IROM Upper 3,9 MP11 173 DEG FROM 0.5 DEO F E O INil5 MIN
[O'?orecast Site Meteorology: Wmd Directen Drita Teinnerature Precipitation f[me Eenmt Wind htaNbtv Simi _- __ 0700- I m er 2.0 MPil 155 DFO FROM 11:00 Upper 3.0 MPil 160 DEO FROM 0.0 E O INA5 MIN 11:00 1 m er 2.0 MPil 125 DEO FROM 13.00 Upper 3.5 MPil 120 DEO FROM .l .0 D 0 IN/15 MIN IMG Imer 2.0 MPH 115 DEO TROM 15:00 Upper 2.5 MPll f 115 DEO FROM 2.0 D 0 IN!!$ MIN
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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 afternoon and becoming 1 3 MPH. Winds will become northerly late this afternoon and increase to 5 7 HPH, High temperature in the upper 50'n. Special Weather Statements: 1
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VERMON7 YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991
-10.2 yJRMONT YANKEE SITE FORECAS,I To be o.rovided to the ESC Mt .t,,eg glocist by the ESC Controller at 13:00.
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 Steed Wind Dirretion {Leita Temrerature StsNhty MIfni:Atra Ame SenseI Luer 2.2 MPil 119 DEO MtOM Upper 3.1 MPil 112 DEG FROM -2.4 DEO F C 0INA5 MIN A
;Q krecast Site Meteorology:
Time Semor Wmd Wmd Directioil Detta Temreraturr $1419 fre_c,Jpitalice 52C01 _-- .
' 13:00- Irwer 2.0 MPil 115 DEO FROM 15:00 Upper 2.5 MPli , 115 DEO FROM 2.2 C o iN/15 MIN 15:00- t m er 2.5 MPil ?T DEO M10M -
17:00 Upper 3.5 MPfl W DEO FROM -2.0 D 0 IN/15 MIN a _ 17;00- Inwer (5 MP:t 65 DEO FROM 19.00 - Upper 6.0 MPil 60 DEO FROM 1.0 D 0INA5 MIN 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 te:nperature in the upper 50's. Clearing later tonight. Temperature in the low 40's. i. Special Weather Statements: l t
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VERMONT YANKEE NUCllAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1991 10.3 FAT 10NAL WEATHER SERVICP SURFACE MAPS E
Rev. O Page 10.3 1 g--
'"' 10.3 WS SURFACE MAP (07 :00)
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