ML20055H045
| ML20055H045 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 07/17/1990 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| References | |
| NUDOCS 9007250107 | |
| Download: ML20055H045 (295) | |
Text
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Rov. O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE , t 1990 TABLE OF CONTENTS SectiQn Page
1.0 INTRODUCTION
1.1 Exercise. Schedule............................................ 1.1-1 1.2 Participating Centers / Agencies............................... 1.2-1 1.3 Definitions.................................................. 1.3-1 1.4 References................................................... 1.4-1 2.0 EXERCISE OBJECTIVES AND EXTENT OF PLAY............................ 2.0-1 , 3.0 EXERCISE GUIDELINES AND SCOPE 3.1 Guidelines................................................... 3.1-1 3.2 Player Instructions and Ground Ru1es......................... 3.2-1 3.3 Procedure Execution Li s t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-1 i 4.0 CONTROLLER /0BSERVER INFORMATION i
; 4.1 Con t rolle r /Ob s e rve r As s ignmen t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-1 ;
4.2 Controller / Observer Exercise Guidance........................ 4.2-1 i 4.3 controller / Observer Evaluation Criteria...................... 4.3-1 5.0 EXERCISE SCENARIO 5.1 Initial conditions........................................... 5.1-1 5.2 Narrative Summary............................................ 5.2-1 5.3 Scenario Time Line........................................... 5.3-1 5.4 Detailed Sequence of Events.................................. 5.4-1 6.0 EXERCISE MESSAGES 6.1 Command Cards................................................ 6.1-1 6.2 Message' Cards................................................ 6.2-1 7.0 STATION EVENT DATA 7.1 Events Summary............................................... 7.1-1 7.2 Event Mini-Scenarios......................................... 7.2.1-1 8.0 OPERATIONAL DATA.................................................. 8.0-1 2143e
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5 Rev. 0 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 M OF CONTENTS (Continued) 9.0 RADIOLOGICAL DATA-9.1 Area Radiation Monitors...................................... 9.1-1 9.2 Process Radiation Monitors...................e............... 9.2-1 9.3 In-Plant Radiation Leve1s.................................... 9.3-1 9.4 -Plant Chemistry Data......................................... 9.4-1 9.5 Radiological Sample Dose Rates............................... 9.5.1-1 9.6 Plant Vent Stack Release Data................................ 9.6-1 9.7 Off-Site Monitoring Maps and Data............................ 9.7-1 10.0 METEOROLOGICAL DATA 10.1 On-Site Meteorological Data.................................. 10.1-1 10.2 General Area National Weather Service Forecasts.............. 10.2-1 10.3 National Weather Service Surface Maps........................ 10.3-1 O V i i lii-L 'V t. 2143e l l l
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_ _ _ _ ._ _ . _ _ _ _ _ . _ __ _ _~ ._ l J R;v. 1 l Page 1.1-1 VERMONT YANKEE NUCLEAR POWER STATION 1 EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 1.1 EXERCISE. SCHEDULE A. CQntroller/ Observer Brialing Date: July 17, 1990 Timn 9:30 a.m. Location: Vermont Yankee Corporate Office (Brattleboro, Vermont)
; Purpose Controller / Observer Briefing on Scenario and Assignments Attendees Vermont Yankee and Yankee Atomic Controllers / Observers B. ControllarL0batIygr Plant Tour Date: July 17, 1990 Tims: As necessary (contact Lead Controller)
Location: Emergency Response Facilities and In-Station Areas Purposes Familiarine Controllers / Observers with Affected Areas Attendees: Controllers / Observers () 2146e
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\- C. HRC Briefine j
Date: July 17, 1990 1 Times 2:00 p.m. ; Location: Vermont Yankee Corporate Office (Brattleboro, Vermont) ; 3
Purpose:
NRC 3riefing and Review of Exercise Scenario , l Attendees: NRC Evaluators l l D. Extrsias Date: July 18, 1990 , i - Time: To be announced l I Location: Vermont Yankee Emergency Response Centers Designated States Emergency Response Centers j 1 Purpose Emergency Response Preparedness Exercise [ t Attendees Vermont. Yankee Emergency Response Organization, NRC , Region I Incident Response Team, Select State (Vermont, New Hampshire, and Massachusetts) Emergency Response Organizations, Controllers / Observers, NRC Evaluators, and Yankee Atomic Engineering Support Center Staff
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R3v. 1 Page 1.1-3 , A k- s E. Exercise Debriefing - Date: Day of Exercise Time: To be announced during or immediately following exercise Location: Location to be designated by the Emergency Response Facility Controller Purpose Players and Controller / Observer Debriefing Attendees: Controllers / Observers, Key Participants F. Controller Debriefing Date: After Exercise Player Debriefing O . Time: To be announced Location: To be announced Purpose Exercise Debriefing Attendees Exercise Coordinator and Contro11ecs G. Exercise Critione 1 Date: July 19, 1990 I Time 1:00 p.m. l l Location: Vermont Yankee Corporate Of fice (Brattleboro, Vermont) () 2146e
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Rcv. 1 Page 1.1-4 Purpose Utility Self-Critique /NRC Preliminary Findings Attendeest Vermont Yankee Management, NRC Evaluators, Exercise Controllers (Observers need not ettend), and Vermont . Yankee Key Participants O O "-
O VERMONT YANKEE NUCLEAR POWER STATION EMEPGENCY RESPONSE PREPAREDNESS EXERCISE 1990 0 1.2 FARTICIPATING CENTERS / AGENCIES O O
R:v. O Page 1.2-1 A h VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISC 1990 0 1.2 IARTICIIAIING CENTERS /ACENCIES VERtiONI_IANKELEUCLEAILP.0WER_C0AE_0RATl.QN Vermont Yankee Nuclear Power Stations o Control Room (notification and comunication functions only) , o Technical Support Center (2nd floor of Administration Building) o Operations Support Center (1st floor of Administration Building) o Energy Information Center (Governor Hunt flouse) , i Vermont Yankee Training Centers o Simulator Room (Control Room functions - let floor of Training Center) o Emergency Operations Facility / Recovery Center (1st floor of Training Center) News Media Center (Vermont Yankee Nuclear Power Corporation Offices - Brattleboro, Vermont) XANKELAI0tilC_ ELECTRIC _C0tifA!Q' i Yankee Atomic Corporate lleadquarters ; l l o Engineering Support Center (Bolton, Massachusetts) ! l 2147e I l
Rsv. O Page 1.2-2 NECLEAR RECULATORY C0ff1ISSION o NRC Region I Incident Response Base Team (King of Prussia, Pennsylvania) o NRC Region I Incident Response Site Team (Vermont Yankee Emergency Response Facilities) STATE OF VElQiodI Vermont Emergency Management Agency (State Response Agencies): o Emergency Operations Facility / Recovery Center (State representatives located in the State Room) o Emergency Operations Center (Waterbury. Vermont) O SIAIE OF NEW HAMPSHIRE New Hampshire Emergency Management Agency (State Response Agencies): o Emergenef Operations Facility / Recovery Center (State representativei located in the State Room) o Emergency Operations Center (Concord, New Hampshire) CQMMONWEALTH OF MASSACHUSETIS Massachusetts Civil Defense Agency (State Response Agencies):
, o Emergency Operations Facility / Recovery Center (State representatives located in the State Room)
O \j o Emergency Operations Center (Framingham, Massachusetts) 2147e
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. VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990
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l 1.3 MIATIONS AND DEFINITIgg j O
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i R:v. O Page 1.3-1 l l VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 1.3 ABBREVIATIONS AND DEFINITIONS A. Abbreviations o ACR0 - Alternate Control Room Operator o AO - Auxiliary Operator o A0G - Advanced Off-Gas System
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o APRM - Average Power Range Monitor o ARM - Area Radiation Monitor o AWS - Anticipated Transient Without Scram o CR - Control Room / Control Rod o CRD - Control Rod Drive O O o CRP - Control Room Panel o CS - Core Spray o CTP - Core Thermal Power o DC0 - Duty and Call Officer l 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 Emergency Management Agency o FW - Feedwater l 1 2144e
1 Rsv. O Page 1.3-2 ( o HPCI - High Pressure Coolant Injection ! o HPN - Health Physics Network I o HRNG - High Range Noble Gas 1 o I&C - Instrumentation and Control ; i o LPCI - Low Pressure Coolant Injection ' o MCC - Motor Control Center ) o MPR- - Mechanical Pressure Regulator j o MSIV - Main Steam Isolation Valve i o MSL - Main Steam Line ; l o NAS - Nuclear Alert System o NG - Noble Gases o NRC - Nuclear Regulatory Commission 1 p o NWS - National Weather Service ; I
!] o OP - Operating Procedure o OSC - Operations Support Center o OT - Operational Transient o PASS - Post-Accident Sampling System o PCIS - Primary Containment Isolation System o PED - Plant Emergency Director l
o PVS - Plant Vent Stack l o RA - Radiological Assistant o RCS - Reactor Coolant System l o RCIC - Reactor Core Isolation Cooling o REMVEC - Rhode Island, Eastern Massachusetts, and Vermont Energy Control. l o RERP - Radiological Emergency Response Plan o RHR - Residual Heat Removal 2144e
Rev. O Page 1.3-3 O o RPS - Reactor Protection System o RR - Reactor Recirculation System o RRU - Reactor Recirculation Unit o RV - Relief Valve o RWCU - Reactor Water Clean-Up o Rx - Reactor o SAE- - Site Area Emergency o SBGTS - Standby Cas Treatment System o SJAE - Steam Jet Air Ejector o SRM - Site Recovery Manager / Source Range Monitor o SRV - Safety Relief Valve o TAG - Technical Administrative Guideline o TS - Technical Specification o TSC- - Technical Support Center o UE - Unusual Event o VY - Vermont Yankee o VYNPC - Vermont Yankee Nuclear Power Corporation o VYNPS - Vermont Yankee Nuclear Power Station o WSI - Weather Services International o YNSD - Yankee Nuclear Services Division-2144e
Rev. O Page 1.3-4 B. Definitions 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 member of an exercise control group. Each Controller may be assigned to one or more activities or functions for the purpose of keeping the action going according to a scenario, resolving differences, supervising and assisting as needed. , o Critique - A meeting of key participants in an exercise, usually held shortly after its conclusion, to identify weaknesses and deficiencies in emergency response capabilities . o Emergency Action - Specific . instrument readings, system Levels or event observation and/or radiological levels which initiate q event classification, notification procedures, protective actions, and/or the mobilization of the emergency response organization. These are specific threshold readings or observations indicating system failures or abnormalities. 1 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 l staffs. o Emergency Operations - An emergency response facility Facility / Recovery (Vermont Yankee Training Center, Center Brattleboro, Vermont) which evaluates off-site accident ! consequences and coordinates emergency response and assistance with all off-site agencies. 1 G 2144e
R3v O Page 1.3-5 ' l o Emergency Planning - The areas for which planning is l Zones recommended to assure that prompt i and effective actions can be l taken to protect the public in ( the event of an accident. The , two zones are the 10-mile radius > i plume exposure pathway zone and the 50-mile radius 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 t Exercise the licensee, state, and local *
* '# plans as is reasonably achievable without mandatory public ,
participation. o General EmerFency - 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 Of fices, Brattleboro, Vermont) is dedicated to the news media for the purpose of disseminating and coordinating information concerning accident conditions. All activities conducted within , this center will be the ; responsibility of the Vermont i Yankee Nuclear Information Director. I e
Rsv. O Page 1.3-6 () o Observer - A member of an exercise control group. Each Observer may be assigned to one or more activities or functions 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. i 1
o Protective Action - Those emergency measures taken to , effectively mitigate the ! consequences of an accident by j minimizing the radiological exposure that would likely occur if such actions were not undertaken. p_ o Protective Action - Projected radiological dose Guides J g-values to the public which warrant protective actions following an uncontrolled release of radioactive material. Protective actions would be warranted provided the reduction in the individual dose is not offset by excessive risks to individual safety in implementing such action. o Scenario - The hypothetical situation, from start to finish, in an exercise I which is the theme or basis upon l which the action or play of the l exercise unfolds, o Site - That property within the fenced boundary of Vermont Yankee which is owned by the Vermont Yankee Nuclear Power Corporation. I o Site Area Emergency - An emergency classification that indicates an event which involves l likely or actual major failures (~N of plant functions needed for the
\ protection of the public.
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R3v. O Page 1.3-7 () o Small-Scale Exercise - An exercise which tests as much of the licensee emergency plan and procedures without participation of state and local government agencies. o Technical Support - An emergency response facility Center (2nd floor. Administration Building) with the espability to assess and mitigate the accident using plant parameters and highly qualified technical personnel. Also, assists in accident recovery operations.. o Unusual Event - An emergency classification that indicates a potential degradation of plant safety margins which is not likely to affect personnel on-site or the public of f-site or renuit in radioactive releases requiring off-site monitoring. o Yankee Nuclear Services - A division of Yankee Atomic Division (YNSD) Electric Company. An Engineering ' ,b support organization which provides emergency response support to Vermont Yankee upon request. 2144e O
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 1.4 REEEEERCES O . l l l 2145e
R2v. O Page 1.4-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 1.4 REEERENCES
- 1. Vermont Yankee Nuclear Power Station Emergency Plan.
- 2. Vermont Yankee Nuclear Power Station Emergency Plan Implementing Procedures.
- 3. Vermont Yankee Nuclear Power Station Final Safety Analysis Report -
Vermont Yankee Nuclear Power Corporation.
- 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 - Technical Administrative Guideline l No. 12, Emergency Preparedness Responsibilities.
- 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.
- 9. Daily Weather Maps, National Weather Service, Climate Analysis Center, Washington, DC 20233.
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t i O i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE
. 1990 2.0 EXERCISE OBJECIIVES AND EXIENI OF PLAY - VERMQ U ANKEE _
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_ O l Rev. O Page 2.0-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDMESS EXERCISE 1990 2.0 EXERflSE_DALECIILES_AND_g.utnDLEIAY - VER50NLTANKEE Ex1 tent of Play A. Accident _Assmassent -
- 1. Demonstrate the ability of Control Room A.1 The scenario events initiated on the simulator personnel to recognize emergency initiating provides the operational and radiological data events and properly classify the condition which allows personnel to demonstrate this in accordance with pre-established objective by implementing Procedure A.P. 3125, emergency action levels. Emergency Plan Classification and Action Level Scheme.
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- 2. Demonstrate the ability of the Control Room A.2 The scenario will provide technical and TSC staff to coordinate the assessment information to players which will allow them of plant conditions and corrective actions to analyze plant conditions and propose to mitigate accident conditions. corrective actions.
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- 3. Demonstrate that information concerning A.3 Te1 9 one 5 commsunications links will be plant conditions can be disseminated established by communicators between the between the Control Room and TSC in a simulator Control Room and the TSC in order to timely menner. transmit key information and data.
Controllers / Observers will evaluate the timeliness of information. j . i a 2160e
(' r Rev. O Fage 2.0-2 ht. cat of Play
- 4. Demonstrate the ability of the TSC staff to A.4 De scenario provides events that will enable initiate and coordinate corrective actions the TSC to coordinate in-plant corrective la an efficient and timely manner. actions through the use of OSC personnel.
- 5. Demonstrate the ability of appropriate TSC A.5 h e scenario includes events which allow for staff to participate with Control Room and discussion between '5e Control Room, TSC, and the EOF /RC in emergency classification and EOF staff on classification.
EAL discussions. i
- 6. Demonstrate the ability to assess data from A.6 Scecario events will require Chemistry and appropriate chemistry samples in support of Radiation Frotection technicians located at accident assessment activities and plant the OSC to simulate taking reactor coolant, conditions. containment air, or plant vent stack samples to assess plant conditions. Sample results will be provided by Observers who accompany the technicians during their sampling activities. (Refer to Procedure OP-3530, "Fost-Accident Sampling.")
B. No_tification_and_Communicat_ ion
- 1. Demonstrate that messages are transmitted B.1 Various communications links will be in an accurate and timely manner and that B.3 established between the emergency response messages are properly logged and documented. B.4 facilities in order to transmit informatiott and data. Recordkeeping and documentation will be demonstrated in accordance with Frocedure OF-3504, " Emergency Commsunications."
i Communications and transfer of data between facilities will be evaluated for timeliness I and completeness. 2160e
Rev. O Fage 2.0-3 Ex1 cat _of Play Dersonstrate the capability to notify B.2 Vermont Yankee staff, NRC, and state 2. federal and state authorities of emergency authorities shall be notified in accordance classifications and significant changes in with established procedures. NRC will be plant status in accordance with established notified by utilizing the NRC ENS red phone. The State authcrities will be notified through procedures.* the Nuclear Alert System (Crange Phone).
- 3. Demonstrate that appropriate status boards are utilized to display pertinent accident information at the various emergency response facilities.
4 Demonstrate that adequate emergency commuunication systems are in place to facilitate transmittal of data between the emergency response facilities and federal and state authorities. C. Dir_estion_and_ContIp1
- 1. Demonstrate the capability of key emergency C.1 All emergency response facilities have response facility management personnel 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. Demonstrate appropriate coordination of C.2 The Control Room will initially contact the 2. activities with federal and state federal and state agencies, providing them government agencies. with appropriate information on plant conditions and emergency status. This function will pass to the TSC and EOF /RC after the facilities are activated. NRC Region I Incident Response Team (Base and Site) will be participating in the exercise. Commuunications and information flow with the NRC Region I
- Indicates NRC-identified improvement items from Incident Response Team will be demonstrated.
the 1989 exercise. 2160e
Rev. O Page 2.0-4 Extent of Play D. Energency Response Facilities
- 1. Demonstrate the ability of station and D.1 Scenario data and exercise events will allow corporate personnel to activate and staff D.2 activation and operation of Vermont Yankee the emergency response facilities in a emergency response facilities. The Simulator Control Room, Control Room (coamsunication timely manner.
functions only), -TSC, OSC, EOF /RC, News Media
- 2. Demonstrate and test the adequacy and Center and Engineering Support Center will be effectiveness of emergency response activated in accordance with established facilities, operations, and equipment.* procedures. Designated plant and corporate emergency response personnel will participate Radiolorical Exposure control in the exercise.
E.
- 1. Demonstrate the ability to provide adequate E.1 Scenario events will require OSC On-Site E.2 Assistance Teams to be dispatched to radiation protection controls for on-site emergency response personnel, such as investigate problems associated with plant appropriate personnel dosimetry, equiper,t, equipment. Investigation and repair activities in the plant will require and protective clothing.
- implementation of radiation protection Demonstrate the ability to monitor and controls which include monitoring and tracking 2. track radiation exposure of on-site of radiation exposure of OSC On-Site emergency response personnel. Assistance Teams. (Refer to Procedure OP-3507, " Emergency Radiation Exposure F. In-Elant Corrective and_Renair Act_iona Control.")
- 1. Demonstrate that on-site assistance teams can be dispatched and deployed in a timely manner.
F.1 Scenario events will require OSC on-site F.2 assistance teams to be dispatched
- 2. Demonstrate the ability of on-site F.3 to investigate problems associated with assistance teams to perform corrective plant equipment. Plant personnel will be actions on plant equipment during emergency given the opportunity to perform corrective actions associated with damaged plant conditions.
equipment. Equipment mockup of the postulated damaged plant equipment will be available for
- Indicates NRC-identified improvement items from plant personnel to perform corrective actions.
the 1989 exercise. 2160e
O O O Rev. O Page 2.0-5 Ext _ent_stf_Ilay
- 3. Demonstrate the ability to provide adequate administrative controls and documentation for necessary repairs of plant equipment and systems during an emergency situation.
G. RadiDiogiraL88.scsEment
- 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 radiological and meteorological data in a G.3 to players which will allow them to evaluate timely manner. G.4 potential off-site radiological consequences.
G.5 The scenario will postulate an off-site
- 2. Demonstrate that adequate dose assessment radiological release through the plant vent procedures can be performed to determine stack which will allow players to evaluate off-site radiological consequences. off-site radiological conditions. Players will implement appropriate sections of
- 3. Demons *. rate the ability to assess potential Procedures OP-3513, " Evaluation of Off-Site off-site radiological consequences based on- Radiological C,snditions" and OP-3511, plant conditions. "Of f-Site Protective Actions Recommsendations."
- 4. Demonstrate the ability to perform timely assessment of off-site radiological conditions to support the formulation of protective action recosmeendations for the plume exposure pathway.
- 5. Demonstrate the ability to project the plume trajectory and potentially affected downwind sectors utilizing the computer dose assessment model (METPAC).
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O O O Rev. O Page 2.0-6 Extent of Play
- 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 necessary) of off-site monitoring teams. sections of Procedure OP-3510. "Off-Site and ' Site Boundary Monitoring."
- 7. Demonstrate the use of appropriate equipment and procedures to perform '
off-site radiological sonitoring. H. Eroint.tive Actiutq_ Decision Jaking
- 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 say 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 recommendations concerning off-site Procedure OP-3511, "Off-Site Protective radiological consequences.* Actions Recommendations".
I. Earallel_and_91her Acti_ona
- 1. Test and evaluate the adequacy of methods I.1 Security activities will be implemented in to establish and maintain access control accordance with established procedures to and personnel accountability within the control access to the protected area. i protected area. Assembly of emergency response personnel and evacuation of contractor / visitors will be i implemented in order to test personnel accountability within the protected area.
However, after the plant evacuation accountability checks have been completed, contractors and visitors will be exempted from
- Indicates NRC-identified improvement items additional personnel accountability checks.
from the 1989 exercise. 2160e
Rev. O Page 2.0-7 E(tent of Play
- 2. Demonstrate the licensee's capability for I.2 Exercise critique will be conducted with self-critique and ability to identify areas exercise controllers, observers, and players, needing Improvement. Critique items will be compiled and doctamented by the Exercise Coordinator.
J. Bahlic_Inf9Imation . Demonstrate the ability to develop and J.1 The News Media Center will be fully activated. 1. disseminate timely accurate press release J.2 Information on the simulated events occurring to the public and the news media. J.3 at the plant will be gathered, verified, incorporated into a news release, and
- 2. Demonstrate the ability to provide disseminated to key players. Also, after briefings for and to interface with the approval this information will be discussed at public and news media.* the News Media Center.
- 3. Demonstrate the ability to commuunicate and coordinate news releases between the EOF and the News Media Center.
Demonstrate the ability to provide rumor J.4 A hot line will be established to provide 4. control. rumor control for questions concerning the simulated accident.
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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 actual sample collection and analysis of in-plant chemistry samples which includes the use of the Post-Accident Sampling System (PASS).
- Indicates NRC-identified improvement items from the 1989 exercise. 4 2160e
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1 'l ! I 1 l l I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 4 1990 I l 3.0 EKERCISE GUIDELINES AND SCOPE
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O i I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 3.1 EXERCISE CUIDELINES 1 O I l l l l l O
Rcv. O i Page 3.1-1 ! VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 ! 3.1 EXERCISE GUIDELINES f
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i This package provides guidance for conducting the 1990 VYNPS j Emergency Response-Preparedness Exercise. It provides the framework for demonstrating emergency response capabilities, conducting the , 9 exercise and evaluating response activities. l B. Concepta of Operations and control of the Exercise t An Exercise Coordinator has been appointed by plant management to
-. eversee all exercise activities. The Exercise Coordinator is O- > m ponsible for approving the objectives and developing the scenario time sequence. The Exercise Coordinator is also responsible for the selection and training of the Controllers / Observers required to conduct and evaluate the exercise.
Vermont Yankee will supply official Controllers and Observers for each location where an emergency response action is being demonstrated. Prior to the exercise, the Controllers and Observers 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 actions. I1 In each facility where an action takes place, the Controller will make judgment decisions to keep the action going in accordance with i 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 0-
... Facility Controller who will then contact the Exercise Coordinator i 2154e
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Rsv. O Page 3.1-2 i'
- for guidance or resolut. ion 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 scenarlo-related problems which may occur during the exercise.
i Observers for the exercise will obse'rve the players as they perform their assigned emergency response functions. Individual observers are responsible for being knowledgeable in the area of their assigned function.. The Observers will critique the ef fectiveness of the emergency response actions taken during the exercise and will also provide a written evaluation to their facility Controller. The exercise initial conditions will be provided to a Control Room ! operations crew.-located in the Simulator, by the Controllers. The plant and reactor system parameters for the exercise will be , f- s generated by running the accident. scenario on the simulator. k- s Additional exercise message cards and scenario parameters will be ! provided by Controllers / Observers at the times indicated in the , exercise sequence of events, or when requested by the players. As information is provided to the players, they should determine the nature of the emergency and implement appropriate emergency plan implementing procedures. These 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. 1 I The hypothesized emergency will continue to develop based on data. and information provided to the operators located in the simulator. Wherever possible, operators should complete activities as if they were actually responding to the plant events. Inconsistencies in the scenario may be. intentional and may be required to test the-I (-'g capabilities of the emergency response facilities to the maximum
\_ / extent possible in a limited period of time.
1 2154e
Rev. O Page 3.1-3 l D C. Gangral G21 dance for the Conduct of the Exercise i l
- 1. Simulatina Emeraency Response Actions l
Since the exercise is intended to demonstrate actual capabilities as realistically as possible, participants should act as they would during an actual emergency. Wherever j possible, simulation of response activities should be avoided. Emergency response actions should be simulated only when it is not feasible to perform an action or when the action has been I previously identified as being simulated during the exercise (refer to Section 3.2). When an emergency response is to be simulated, the Controller / Observer will provide verbal or written directions on which actions are to be simulated. Radiation Work Permits (RWPs) have nn.t-been issued for the conduct of the emergency response exercise. If scenario events direct players to areas that are actually RWP-controlled due to high radiation, surface contamination, or airborne-radioactivity, players will simulate response activities without actually entoring the RWP-controlled area sun if they are authorized on the RWP for some other duty. l
- 2. Avoidine Violations of Iaws Violation of laws is not justifiable during the exercise. To implement this guideline the following actions must be taken:
i
- a. All Controllers / Observers and potential exercise 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. V 2154e
Rev. 0 1 Page 3.1-4
- b. Exercise participants will not direct illegal actions to be taken by other participants or members of the general public.
- c. Exercise participants will not intentionally take illegal actions when responding to exercise events. Specifically, local traf fic laws (i.e., speed limits) will be observed.
- 3. Arniding Personnel and Pronerty Endannerment All participants will be instructed to avoid endangering property (public or private), other personnel responding to the.
exercise, members of the general public, animals and the environment.
- 4. Actions to Minimize Public Inconvenience
\s_- It is not the intent, nor is it desirable, to eE - .ely train or test the public response during the conduct or the exercise. Public inconvenience is'to be avoided. The conduct of an exercise could arouse public concern that an actual emergency is occurring. It is important that conversations that can be monitored by the public-(radio, loudspeakers, etc.) be pref aced and conclude with the words, "THIS IS A DRILL; THIS IS A DRILL." D. Engrgency Response Implementation and Operations
- 1. Initial and Follow-Up Notification
- Initial and follow-up notification of the emergency.
classification will be made by the plant staff in accordance- I f- g with existing emergency plan implementing procedures, unless (ms/ directed otherwise. q 2154e
Rev. O Page 3.1-5
- 2. Control Room Operations 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 data, will be provided to the Control Room emergency response crew as necessary. Communications links that duplicate the emergency communications capabilities available at the Control Room will be used to communicate between the Simulator-Control Room and other emergency response facilities. The actual Control Room communication system for transmission of emergency announcements and information 9 (e.g., Gaitronics) will also be utilized.-
- 3. Technical Support Center (TSC) OptJtdLtions The TSC emergency response organization will be activated during the exercise. TSC information will originate from the Simulator Ccatrol Room. Information that is normally accessible by TSC personnel from the plant computer will be provided by Controllers / Observers 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 {f 1 I
i Rsv. O Page 3.1-6
- 4. Optrationg_S.upport Center (OSC) Operations The OSC emergency response organization will be activated during the exercise. Operations Support Center response activities will be communicated 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 Controller / Observer.
- 5. Estrainsv Operations Facilitv/ Recovery Center-(EOF /RC)
Operationa The EOF /RC emergency response organization will be activated during the exercise. Information and data will be transmitted to the EOF /RC from the TSC and Control Room (Simulator). EOF O- Controllers / Observers will provide other data to EOF /RC players as necessary.
- 6. Off-site Monitoring Tearm l
Of f-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 Controllers / Observers.
- 7. News Media Center Operations The News Media Center will be activated and staffed during the exercise. News Media Center staff will obtain all the necessary information on current plant status through commanications channels with the EOF /RC. Press releases will 2154e
_ _ - -. __ _.. ._ _ _ . . . _ _ . . _ _ _ _ _ . . . _ _ . ~ _ _. Rsv. O Page 3.1-7 be generated and disseminated in accordance with the Vermont Yankee Consnunications Department Emergency Response Plan and ) Procedures. All press releases are to be clearly marked: THIS IS A DRILL.
- 8. Security Operations t All exercise-related security emergency response activities will be implemented in accordance with existing procedures.
1 Access control and personnel accountability within the protected area will be demonstrated. At no time will actual plant security procedures-be violated in support of the exercise.
- 9. Nucl.ar e Regulatory Committion (NRC) Operations The NRC Region I Incident Response Team will participate in the V exercise. The NRC Region I will play a full participation role with a NRC Base Team located at the regional' office in King of Prussia, Pennsylvania and the NRC Site Team at Vermont Yankee emergency response facilities. 'No NRC Public Affairs participation is planned.
E. Exercise Termination l 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 implemented to terminate the exercise:
- 1. The Exercise Coordinator will obtain information from the Facility Controllers regarding the status of player actions and the demonstration of the exercise objectives.
O O 2154e
Rsv. O Page 3.1-8
- 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 Coordinatar will inform the Site Recovery Manager and TSC Coordinator that all exercise observations have been completed and that the exercise can be terminated.
- 4. A coordinated decision to terminate the exercise will be made.
between the Site Recovery Manager.and the TSC Coordinator. The Site Recovery Manager will also receive concurrence from the States to terminate exercise activities.
- 5. The Site Recovery Manager or TSC Coordinator will terminate the exercise.
- w)
The exercise may also be terminated under the following circumstances: l
- 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: l l
- 1. The Shift Supervisor will contact the TSC Coordinator and inform him l of the plant status. The TSC Coordinator will, in turn, contact'the Site Recovery Manager and inform him of the plant stctus; 2154e
-i R2v. O.
Page 3.1-9 O 2. The Site Recovery Manager will inunediately inform any State representatives at the EOF of the nature of the emergency;
- 3. Concurrent with the notification in Step 2, the Contro1~ Room will announce the following statement over the plant paging systemi-
"The emergency plan exercise has been terminated. I repeat.
The emergency plan exercise has been terminated." This message may be immediately followed by the appropriate emergency announcements.
- 4. The Exercise Coordinator will be responsible for directing the actions of the Controllers / Observers and other exercise participants. .
In the event that Item 2 should occur, the following actions should be taken:
- 1. The State Police, having been notified of the emergency, should open direct communications with the Vermont Yankee Control Room using the Nuclear Alert System.
- 2. -The Shift Supervisor will notify the Control Room Controller who, in turn, will notify the Exercise Coordinator.
- 3. 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.
- 4. The Exercise Coordinator will be responsible for temporarily halting the exercise until such time a decision is made.
- 5. If the final decision is to cancel the exercise, the Exercise Coordinator will be respos ale for directing the activities of all exercise participants, a; well as for the notification of the NRC.
I 2154e l
l Rsv. O Page 3.1-10
- 6. If the final decision is to continue the exercise, the Exercise Coordinator is responsible for informing all Controllers / Observers i of any projected changes to the expected response action (s).
- 7. The Exercise Coordinator will direct the organization as to the I appropriate action required to restore the exercise sequence, i
l O I l l 1 1 l 2154e l l 1
_.-+.2.-- _.-u , _ . - - ..... .__.2 ._._. m. . _ ._ . - - _, .. - -_____ _ _ _ _ _ O I l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990-1 3.2 PLAYER INSTRUCTIONS AND GRQUND RULES l l' 2148e
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l Rov. O Page 3.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 3.2 PIAYER INSTRUCTIONS AND GROUND RULES The Vermont Yankee Emergency Response Preparedness Exercise will be conducted on July 18, 1990. All emergency response facilities will be i 1 fully activated, and the scenario will be driven by the simulator, as in past exercises. 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 l regarding the exercise. Department Heads are responsible for ensuring that personnel are trained on this information. I i l p A. General Guidelines l t
- 1. Exercise participants-include the Exercise Coordinator, Players (including the NRC Incident Response Team), Controllers.
Observers, and NRC Evaluators. Controllers will provide players with command and message cards to initiate emergency 1 1 response actions. Observers and the NRC Evaluators will' l evaluate and note player actions. Controllers, Observers, and l NRC Evaluators will be identified by badges. l l
- 2. Always identify yourself by name and function to the Controllers, Observers, and Evaluators. Wear a name tag if one is provided.
- 3. You may ask the Controller / Observer for information such as:
a.- Initial conditions of the plant and systems including: f I o operating history of.the core 2148e
Rev. O Page 3.2-2 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 _cf the plant and field survey teams after a sample has been appropriate?y taken.
d.- Counting efficiency of all counting equipment.
- e. Activity from nose swabs or skin contamination surveys.
- 4. You may not ask the following from the Controllers /Observerst
- a. Information contained ir procedures, drawings, or instructions.
- b. Judgments as to which procedures should be used.
- c. Data which will be made available later in.the exercise,
- d. Assistance in performing actions in this exercise.
?
- e. Assistance in performing calculations.
-5. Play _out all actions, as much as possible, in'accordance with your plan and procedures as if it were an actual. emergency. If an action or data is to be simulated, a Controller / Observer will provide appropriate direction.
- 6. Always identify and discuss your actions to the l Controllers / Observers and NRC Evaluators.
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1 l Rsv. O Page 3.2-3
- 7. Periodically speak out loud, identifying your key actions and decisions to the Controllers / Observers and NRC Evaluators.
This may seem artificial, but it will assist the evaluators and is to your benefit. S. When you are assigned to complete a response action, be sure to be accompanied by a Controlier/ Observer at all times.
- 9. If you are in doubt ! bout completing a response action, ask your Controller / Observer for clarification. The Controller / Observer will not prompt or coach you. Emergency.
response actions must nol place exercise participants in any potentially hazardous situations.
- 10. The Controller / Observer will periodically issue messages or instructions designed to initiate response actions. You muni accept these messages immediately. They are essential to the
( proper conduct of the exercise. 4
- 11. If the Controller intervenes.in your response actions and recommends you redirect or reconsider your pisy actions, it-is for a good reason. The Controller's direction may be essential to the overall success of the exercise for all participating groups.
- 12. If you disagree with your Controller / Observer, discuss your I conce rns. However,- the Controller's/ Observer's final decisions must be followed.
1
- 13. Respond to questions in a timely manner.
1
- 14. Do not accept any messages / instructions from NRC Evaluators..
They are required to work through your Controller / Observer if-fe'T they want to initiate additional emergency conditions. O 2148e l l l 1 i
1 R2v. O Page 3.2-4 1
\ However, you may answer questions directed to you by NRC Evaluators. If you do not know the answer, refer them to your lead player or Controller / Observer.
- 15. You must respond as if radiation levels are actually present in accordancs with the information you receive. This may require you to wear protective clothing, respirators, and additional dosimetry and adhere to radiation protection practices.
- 16. Controllers / Observers /NRC Evaluators are exempt from simulated ,
radiation levels and other emergency conditions. Do not let this confuse you or cause you to act unwisely. However, no one is exempt from normal station radiological practices and procedures.
- 17. . Utilize status boards and log books as much as possible to Q document and record your actions, l
t Q
- 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 follow the exercise.
l Provide any comments or-observations to your lead player or 1= '-- Controller / Observer af ter the exercise. Areas for improvement l or weaknesses when corrected will-improve the overall emergency response capability. I l l B. Player's Simulation List tP; , L The following describes those specific actions which do not have to q be performed and can be simulated by exercise participants. All' I\ G. 2148e -l 1 1
- . _ - - . - - . _ . _ . . -- . . - . . . . _ ~ . . -. - -
1 Rsv. 0 l Page 3.2-5 O (,,/ 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 not be programmed into the plant l process computer. This will be provided by Controllers / Observers utilizing telephone communications ]
between the Simulator and plant Computer Room.
- 2. ' A suf ficient number of individue.ls f rom the Vermont Yankee Emergency Response Organization will be prestaged at the Simulator.
- 3. Meteorological data will be simulated using a " test" file available to the Simulator Control Room Meteorological Computer System.
, 4. Af ter plant evacuation accountability has been completed, plant personnel and contractrrs/ visitors not directly involved in the exercise will be allowed to return to work, at the discretion of the TSC Coordinator. The distribution of potassium iodide (KI) will be simulated. 5.
- 6. Charcoal cartridges will-be used as silver zeolite cartridges during off-site monitoring activities.
I- 7. The YNSD Emergency Response Team will be prestaged in.the area. 1
- 8. No emergency response facility evacuation will be demonst' rated j during the exercise.
- 9. Off-site monitoring teams and. security boundary monitoring:
_p ersonnel will not wear protective clothing.and/or respirators. f~ Q i 2148e i ~
Rsv. O Page 3.2-6 O k-/ 10. The inner gate and electrically controlled doors will not be left in the open position during the exercise.
- 11. The plant Gaitronics is not available from the simulatort actual plant announcements will be made from the Vermont Yankee l plant; Control Room.
- 12. Controllers / Observers will not be ~1ssued dosimetry unless plant acces's is required prior to the exercise. Security will be notified of their assigned location.
- 13. All decontamination actions associated with the exercise may be simulated after discussion'and approval by the Controller / Observer.
- 14. The use of respiratory protection equipment may be simulated by f
r- plant personnel after discussion and approval by.the km Controller /Obse rver.
- 15. Radiation Work Permits (RWPs) have nat been issued for the I conduct of the exercise.
Simulator C.on. trol Room Information C. l l The following describes how the Simulator Control Room emergency response activities will be integrated with the plant Control Room functions during the exercise:
- 1. Players reporting to the plant Control Room will be directed to an area (SS office) that will have a Controller and i communications link with the simulator. All Control Room i
exercise communications should be directed to the Simulator Control. Room. 2148e y/N
Rov, O Page 3.2-7 O 2. All exercise-related Gaitronics calls to the Control Room and vice versa will be relayed or answered by the Control Room Controller. Channel 3 should be utilized for all exercise messages. 1
- 3. Gaitronics plant announcements will be coordinated by the I Simulator Controller. They will be made by the operating crew I in the plant Control Room.
- 4. TSC Communicators normally assigned to the Control Room and a i Radiation Protection Technician for transmitting initial radiological and meteorological data will be prestaged at.the ,
simulator.
- 5. Process computer ID data, normally accessible by TSC personnel; will be provided by a designated person in the simulator via personnel in the plant Computer Room.
O
- 6. Personnel movement in and out of the Simulator Control Room will be limited to the controllers / Observers.
- 7. Communications equipment in the Simulator Control Room is the same as the plant Control Room. The commercial phone extensions are different but auto ring down and speaker phones are operable. The orange State phone and red ENS-NRC phone will be operable. The orange phone extension is 613. The red ENS NRC phone will be initially operable until the TSC takes over this communication function.
D. Player's c---amanshio The following is a list of items that'should be followed to improve gamesmanship during the exercise: O 1. Make it known when significant events occur or when you are l about to perform a significant action.
. .-- _-- - .-- . . - - .. - . _ - . _ . - . - . ~ .
Rsv. O Page 3.2-8 1 l O 2. Keep all messages, status boards, and problem boards accurate, current, timed, and dated.
- 3. Hold briefings regularly, at a minimus svery 30 minutes.
- 4. Key players should wear badges which identify their role.
Bound log books should be used in all emerg ncy response facilities.
- 5. All announcements, including those on the Gaitronics, should state "THIS IS A DRILL."
- 6. Avoid simulation unissa.it has been specified. Use protective clothing where called for (e.g., step-off pads, etc.).
E. Personnel Accountability and Exercise Participation g IExampted Exercise Participants) Procedures require that all exercise participants be identified. Proper identification will not only help eliminate confusion, but is necessary for security and accountability. This requirement applies to all areas within the plant fence, ~ the Governor Hunt House, the EOF /RC, the simulator area, the News Media Center, and the Vermont Yankee Corporate Office in Brattleboro. l l Although it is 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. lie Department Heads should review their area of responsibility and I provide the. Exercise Coordinator with a list of names and positions for anyone that should be exempted from exercise participation.
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l Rev. O Page 3.2-9 O- This list 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 a list of exempt personnel for the exercise. All other personnel, not listed, are expected to participate as required by the Emergency Plan. The exempt list of plant personnel will include the On-Shift Security Crew, Operating { Crew, and Duty Chemistry and Health Physics Technician and the l individuals identified by the Department Heads. Security at the l Training Center entrance will also limit access through the doors,to exercise participants for the duration-of the exercise. F. Off-Site Participation This year, Vermont Yankee is conducting a small scale exercise which will involve the participation of the NRC Region I Incident Response O- Team. The NRC Region I will play a full participation role with a NRC base Team located at the regional office in King of Prussia, Pennsylvania and the NRC Site Team at the Vermont Yankee emergency response facilities. No NRC Public Affairs participation is 4
-planned. The States of Vermont, New Hampshire, Massachusetts, and the local communities within the plume exposure pathway will have-the opportunity to participate in the exercise.-
The capability to notify federal, state, and local authorities of emergency classifications in accordance with established procedures will be demonstrated as follows:
- a. NRC will be notified by utilizing the Emergency Notification System (ENS) red phone.
2148e
Rsv. O Page 3.2-10 O b. Vermont, New Hampshire, and Massachusetts State Police dispatchers and State Emergency Operations Centers (EOCs) will be notified through the Nuclear Alert System (NAS) orange phone. I
- c. ?!RC Region I Incident Response Team representatives and i 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 Yankea personnel. ;
If any state official tries to contact the plant Control Room REGARDING THE EXERCISE, the Vernon switchboard should- transfer the call to the Simulator Control Room in Brattleboro. The NAS orange phone extension in the Simulator Control. Room is 613. G. Exercise Critiquea The following is a brief description of the critique sessions that t 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. Emernancy Response Facility Critiones 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 heldt i
- 1. SRM and EOF
- 2. TSC and Simulator Control Room
("'T 3. Operations Support Center and Security
-- - 4. News Media Center 2148e
RSv. O Page 3.2-11 O Con 1Islier Debrlefing This session will be conducted by the Exercise Coordinator to compile all exercise consnents and findings. Participation is limited to Exercise Controllers. Exercise critiqua l This session will be conducted by the Exercise Coordinator to present to management a summary of all major findings and deficiencies identified curing the exercise. Participants include Vermont Yankee management, Exercise Controllers, key players, and the NRC. NRC Exit Imediately following the exercise critique, the NRC will present O-their preliminary findings. Participants will be-the same as in the exercise critique session. 2148e
O i I i VERMONT YANKEE NUCLEAR POWER STATION NIERGENCYRESPONSEPREPAREDNESSEXERCISE 1990 3.3 PROCEDURE EH CUTION LIST
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Rev. O Page 3.3-1 VERMONT YANKEE NUCLEAR POWER STATION I EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 3.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES EXECUTION LIST Procedure Nn=her Ii.tle l l AP 3125 " Emergency Plan Classification and Action Level Scheme" l OP 3500 " Unusual Event" l OP 3501 " Alert" OP 3502 " Site Area Emergency" OP 3503 " General Emergency" OP 3504 " Emergency Communications" OP 3507 " Emergency Radiation Exposure Control" OP 3510 "Off-Site and Site Boundary Monitoring" O P OP 3511 "Off-Site Protective Actions Recommendation" OP 3513 " Evaluation of Off-Site Radiological Conditions" OP 3524 " Emergency Actions to Ensure Accountability and Security Response" OP 3525 " Radiological Coordination" l OP 3530 " Post-Accident Sampling" l l l 1 i l l 1 l l
l O t VERMONT YANKEE NUCLEAR POWER STATION f MERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 4.0 CONTROLLER /0BSERVER INFORMATIoh , O f'1. O 2"2-
i 4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 4.1 CONTROLLER /0BSERVER ASSIGhMENTS O . f 2152e i 1
1 4 1 O' Controller-Observer Organization 1990 Graded Exercise July 18,1990 Exercise Coordinator Ed Porter . Simulator Control Room I Controller Al Chesley , Observer Mike Sontag Simulator Support Group Mark Krider John Hudachek i Dave Tuttle Al Thomas Vernon Overview Stan Jefferson Main Control Room O Controller Dick Slauenwhite
)
Observers None TSC Controller Jim Hawxhurst Observers Ed Tarnuzzer Cal Cameron OSC Controller Gary LeClair Observers Dave Stafford Tracy North ., Phil Howard Don Dyer ! Bob Leach Tom Childress Greg Duffy Bob Grippardi -i Harry LeFebrve Steve Naeck ' Ron Cardarelli-O -
1 2 s Brattleboro Overview Rocco Marcello EOF Controller Jon Arms Observers John Parillo Dan McDavitt John Babbitt SRM Controller Ed Salomon Observers Tom Burda Karen Jackson Security Controller None
. Observer Ed Wojnas NMC Controller Gordon Bristol Observer Ruth Zikaras Devin Starlanyl ESC (Bolton)
Controller Dorsey Holsinger i O l l l l 1 l l - - _ _ - _ _ _ _ . - _ _ __ _ _ _, , ,, _ _ , _
O VERMONT YANKEE NUCLEAR POWER STATION 2MERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 4.2 CONTR01.1 rn AND OBSERVER EKERCISE GUIDANCE O 4 9 O
Rsv. O Page 4.2-1 O' VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 4.2 CORIRQ118'D AND OBSERVER n n CIEE CUIDANCE ) Prior to the exercise, each Controller / Observer will be provided a scenario package and the plant emergency plan implementing procedures which correspond to their assignment. It is the responsibility of the Controller / Observer to read the contents of the package and review the procedure 6. A Controller / Observer briefing will be conducted prior to the exercise. Any questions regarding the scenario or the exercise assignments should be discussed at this , time. Each Controller / Observer should ensure that they are f amiliar with the location (s) required by their assignment. Emergency response facility tours are available af ter the Controller / Observer 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 comments, observations, and exercise documentation. Each Controller will be responsible for ensuring that the documentation is provided to the Exercise Coordinator at the conclusion of the exercise. Each Controller is also responsible for providing a brief summary of their facility comments during the player debriefing. () Controllers / Observers should identify themselves to the players and explain their role in the exercise. Players should be informed thet any actions which i deviate from standard plant or emergency procedures should be identified to the Controllers / Observers. Controllers / Observers 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. The primary role of Controllers / Observers is to evaluate the emergency responses activities of the players. In order to document the adequacy of emergency response actions during the exercise, Controllers / Observers are required to complete the Emergency Exercise / Drill Observers Evaluation Form. When completing this form Controllers / Observers should attempt to differentiate their comments into either adequate or potential deficiencies. For deficiencies of personnel, equipment, etc. provide recommendations for improvement which detail corrective actions, if possible. I f 2453e (
Rcv. O Pcg3 4.2-2 Controllers / Observers should unt allow their biases to be documented as
\ recognized weakness 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 1,ayout, Off-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Ccmments.
Facility Activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the f acility was activated; (3) when initial activities became well organized; (4) whether personnel perfomance followed the organized arrangements specified by plant procedures; and (5) the efficiency of methods of authority transfer. If a transfer of responsibility occurre'd, then the Observer should determine if all affected personnel were aware that the transfer had occurred. Communication comments should identify: (1) personnel familiarity with emergency communications use; (2) whether suf ficient communications were available to ensure a timely, efficient, and effective flow of information; (3) whether there were enough communications personnel to make use of all available equipment; (4) the adequacy of communications logs and the effectiveness of data transfer; (5) whether there were any problems in the design of the existing communications system (i.e., location relative to traffic flow); (6) whether there were any recognized difficulties in the use of computer systems; and (7) whether center status boards were effectively used. Observers should document their comments in this area very carefully,
/9 providing sufficient details to track any recognized deficiencies.
V Plans and Procedural consnents should identify: (1) whether personnel were familiar with the details of the overall concepts of applicable procedures; (2) whether situations developed which required deviation from the procedures or plan (3) whether personnel were overwhelmed with procedural requ,tements which distracted them from performing their required emergency response function, and (4) whether the procedures adequately described the actions required to complete an assigned function. Equipment capability connents 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 j assignment; (3) whether backup equipment was readily available when
- malfunctions were reported; (4) whether the available systems provided an l adequate service; and (5) whether equipment malfunctions impacted the expected emergency response.
Scenario related comments should address: (1) whether sufficient information was available to ensure appropriate player response (2) whether the scenario l details deviated from actual procedural requirements; and (3) whether the 2453e g) U
Rev. O Page 4.2-3 scenario detail provided any prompting to the player. The adequacy of the scenario in keeping the players active and interested throughout the exerciso shN!d also be addressed by the Controllers / Observers. Training comments should identify: (1) whether plant personnel have been provided sufficient training to handle "ad hoc" procedural deviationst and (2) whether training identified improper procedural requirements. Comments on f acility layout deficiencies /reconsnendations should identify: (1) whether the available work space was adequate; (2) whether traffic flow hindered the response ef forts; (3) whether the communications available in the work area were adequate; (4) whether the noise level hindered emergency response ef forts; and '5) whether suf ficient references were available to complete the job assic.iment. Off-site monitoring team observers should identify: (1) the adequacy of sampling methodst (2) the adequacy of contamination control measurest (3) the adequacy of reporting and documentation measurest 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 projectica 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 iodidel (3) the adequacy of established contamination control access points; (4) the adequacy of exposure planning measures afforded in plant activv ies t atJ (5) the adequacy of decontamination and posting techninues. The Contr,11er/Ubserver evaluation and documentation forms are found in Section 4.3. All such documentation must be provided to the Controller after the exercise and prict to the plant critique. 2453e
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 4.3 C.0HIRQ1 H R AND OBSERVER EVALUATION CRITERIA O 2149e
i R:v. 0 Page 4.3-1 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY. RESPONSE FREFAREDNESS EKERCISE j 1210 4.3 CORIR011 rIt AND OBSERVER EVALUATION CRITERIA As discussed in Sections 4.1 and 4.2, each Controller / Observer has been , assigned specific areas of response to evaluate. This section has been ! developed to assist the Controllers / Observers in recording and documenting their findings and observations. The completed material ! will be an of ficial record of the exercise observations. Attschment A consists of forms to be used in maintaining an event I
; chronology log.
l Attachment B contains evaluation checklists for each eniergency response facility. Each Controller / Observer should complete the appropriate checklist. l Attachment C contains an evaluation form which should be used to sunanarize major findings and observations. This form MUST BE completed I by each Controller / Observer. All three attachments should be completed and submitted to the facility g Controller. Each Controller will then submit the attachments to the Exercise Coordinator for documentation and record keeping. 1 1
\
l l J 1 l l 1 2149e v , l l l i
Rsv. O Page 4.3-A.1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCL RESPONSE _ PREPAREDNESS..EKERCI.SE 1910 ATIACEMENT.A Vermont Yankee Nucinar Power Station Emergengy_ARSPQDag Exereige/ Drill Evaluator's Obs3rvationa-Chronological Log Tim. Obatryation/c - ant O 1 Name: Area Evaluated: j Date: 2149e
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Rev. O Pa6e 4.3-A.2 O' VERM0EIJANKI;E_XUCLI;MLI.Qh[ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 11PD ATIACMMENT.A (Continued) _Iing Ohagrvation/C. t O - Name: Area Evaluatedt _Date: 2149e
i ! I i t i R:v. 0 l Page 4.3-B.1 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PPHAREIEESS.. EXERCISE , i 1210 ATIACHMENT B , Vermont Yankes ; fagygency Exerciae/ Drill Evaluation Check List [ i INSTRUCTIONS > The following evaluation check lists are provided to assist the Controllers / Observers with their evaluation of the drill / exercise. The Controllers / Observers 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 coments or suggestions for improvement, should be ! included on Attachment C, the Emergency Exercise / Drill Evaluation Form or on a separate piece of paper. ; Baling Systd C. -nta and Suggested.__ Improvements 1 Adequate A May be followed by coments and suggestions for improvements, especially if rating is marginal. Oi ; Inadequate I Must be followed by coments, ! together with suggestions for ; improvement. ! i Not Observed or N No coments or suggestions Not Applicable are required. ', I l ! I t I r (^}
'%J '
2149e d , 8
Rsv. O Page 4.3-B.2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE MEPAREDNESS. EXERCISE 1210 ATTACHMENT B (Continued) Section Im j I. Control Room (Simulator and Actual) 4.3-B.3 II. Technical Support Center 4.3-B.S III. Operations Support Center 4.3-B.8 IV. Emergency Operations Facility / Recovery Center 4.3-B.11 V. Site and Off-Site Monitoring 4.3-B.14 VI. Security 4.3-B.'15 VII. News Media Center 4.3-B.16 s O G 2149e
Rov. O Page 4.3-B.3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EKERCISE 1110 ATTACHMENT B (Continued)
- 1. CONTRQL_RQQM Ratine Campanta A. Accident Assesament/Emeraency Clannif* cation
- 1. Did the Control Room staff demonstrate Yes/No the ability to recognize emergency initiating conditions and classify the events in accordance with AP-3125.
- 2. Did the Control Room staff demonstrate Yes/No the ability to coordinate the assessment of plant conditions and corrective actions with the Technical Support Center?
() B. Notification and On-munication
- 1. Did the Control Room staff demonstrate the Yes/No ability to notify the plant staff of an emergency through the use of alarms and the pub)ic 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/No
-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 l the Control Room staff? 2
- 5. Wera adequate emergency communication systems Yes/No available in the Control Room to transmit data and information to other emergency response facilities?
2149e 4
.__._m._ _ _ . -
Rsv. O Page 4.3-B.4 VIRMONT. YANKEE NUCLEAR POWER STAT 10R EMERGENCY RESPONSE PREPAREDNESS RYRROISE 1910 ATTACHMENT E (Continued) I. CONTROL ROOM , Eating Comunania C. Activation and Responge
- 1. Did the Control Room staff demonstrate the Yes/No ability to approp-lately implement Emergency Plan Implementing Procedures and did they follow them?
- 2. Was the person in charge in the Control Room Yes/No clearly identifiable and was good command and control taken at the Control Room?
O Controller / Observer Name: () l 9
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Rov. O Page 4.3-B.! VIRMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EKERCISE 121Q AIIACHMENT..B (Continued) II. IEC5HICAL SUPPORT CENTER Rating Commania A. Accident Assesament/Emeraency Classification
- 1. Did the TSC staff den.snstrate 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 staff 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 coirdinate corrective actions in an efficient and timely manner?
- 4. Did the TSC staff oomonstrate the ability to Yes/No direct and coordinate the taking of appropriate chemittry samples to analyze plant conditions? i
- 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. Notification and ce==unication
- 1. Was information flow within the TSC and to Yes/No other appropriate emergency response N facilities timely, complete, and accurate?
l 2149e O
R:v. 0 . Page 4.3-B.6 I VERMONT YANKEE NUCLEAR POWER.. STATION DiERGENCY RESPONSE PREPAREDNESS EXERCISE , 199D l l I
, ATTACIDiENT B (Continued) l l
II. IECHNICAL EUPPORT. CENTER Rating ComuneALs ) 1
- 2. Was adequate record keeping of events, Yes/No )
actions, and communications documented and l logged by the TSC staff?
- 3. Were adequate emergency communications systems Yes/No available in the TSC to transmit data and 1 information to other emergency response facilities?
- 4. Was information concerning plant conditions Yes/No disseminated between the Control Room and TSC l performed in a timely manner?
7 I s
- 5. Were statua boards utilizad and maintained Yes/No to display pertinent accident information at the TSC? ,
C. ActivaU yp and Respgnas
- 1. Did the TSC staff demonstrate the ability Yes/No to activate and staff the TSC7 l
- 2. Did the TSC staff demonstrate the ability Yes/No to appropriately implement Emergency Plan i 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? l () 2109' 1 l e---- --
- . . . _ _ _ , _ , , . , . . , , , s,,.. ,,
R:v. O Page 4.3-B.7 YEgliQRT YANKEE NUCIEAR POWER STATION EMERCENCY REEPONSE PRFPAREDNEEE KYERCIEE 1110 ATTACHMENT B (Continued) J l II. IEC11NICAL SUPPORT CENIER Rating Cguments
- 5. Did the TSC Coordinator demonstrate the Yes/No ability to maintain command and control of TSC emergency response activities? ;
1
- 6. Did the TSC keep other emergency response _ Yes/No facilities advised of the status of their-activities and information which they had developed? l
- 7. Was the TSC organization and initiation Yes/No of activity efficient and well organized?
O ! 1 I I l l Controller / Observer Names 2149e 1
R:v. O Fage 4.3-B.8 yERMONT YANKEE NUC11AR POWER STATION 12ifAGENCY.RESPONSLIREPAREDNESS nnCISE 1210 ATIACEMENT.B (Continued) III. OfERATIONS_El!Z10RLCENIER Rating ConunantA A. Notification and can==unication
- 1. Was information flow within the OSC and to Yes/No other appropriate emergency response facilities timely, 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 communications systems Yes/Nc, available in the OSC to transmit data and information to other emergency response facilitles?
- 4. Were status boards utilized and maintained to Yes/No display pertinent accident information at the OSC?
B. Activation and Respongg
- 1. Did the OSC staff demonstrate the ability to Yes/No activate and staff the OSC7
- 2. Did the OSC staff demonstrate the ability to Yes/No-appropriately implement Emergency Pisn Implementing Procedures and did they follow them?
- 3. Were initial and continuous accountability Yes/No checks of OSC personnel performed?
2149e O
Rsv. O Page 4.3-B.9 VERMONT YANKEE NUCLEAR POWER STATION IMERGENCY RESPONSE PREPARRnNESS EYFRCISE i 1EEQ AIIACllMENI 3 ; (Continued) i III. OPERATIONS SUPPORT CENTER Rat he Comunenta
- 4. Did the OSC Coordinator and OSC Coordinator's . Yes/No Assistant demonstrate the ability to maintain command and control of OSC emergency response activities? I
- 5. Did the OSC keep other emergency response Yes/No !
facilities advised of the status of their activities and information which they had developed?
- 6. Was the OSC organization and the initiation Yes/No of activity efficient and well organized?
- 7. Did the OSC staff demonstrate the ability to Yes/No
[ provide adequate radiation pretection controls for on-site emergency response personnel? l l 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 c.s directed by the TSC?
- l. 10. Did the OSC staff demonstrate the ability Yes/No to initiate, brief, and dispatch On-Site Assistance Teams?
O 2149e
. . . . . . - ~ . . - . - - - . .- - _ - . -. _ _ _ _ - . . . _ _____
R2v. O Page 4.3-B.10 ; YERMONT. YANKEE E! CLEAR POWER stall 0N EMERGENCY RESPONSE PREPAREDNESS EKERCISE 1920 ATTACHMENT B (Continued) III. OFIRATIONS SUPPORT CENIER
- 11. Were on-site assistance teams able to trouble- Yes/No shoot'and evaluate problems with plant l equipment and systems?
- 12. Were their adequate administrative controls Yes/No and documentation taken to perform the necessary repairs of plant equipment and systems during an emergency situation?
i Controller / Observer Name , r [ 2149e l t i + l l
Rsv. 0
, Page 4.3-B.11 VERMONT YANKEE NUCLEAR. POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1HD ATTACHMENT B (Continued)
IV. EMERGENCY OPERATIONS FACILITY / RECOVERY CENTER l Rating Comments A. Notification and Cn-munication I
- 1. Was information flow within the EOF /RC and Yes/No '
to other appropriate emergency response facilities timely, complete, and accurate?
- 2. Were adequate emergency communications systems Yes/No l available in the EOF /RC to transmit data and information to other emergency response facilities?
- 3. Uas adequate record keeping of events, _ Yes/No I~h actions, and communications documented
\s / and logged by the EOF /RC staff?
- 4. Was information concerning plant conditions Yes/No disseminated between the TSC and EOF /RC performed in a timely manner?
- 5. Were status boards utilized and maintained Yos/No to display pertinent accident information at the EOF /RC?
I l B. Activation and RespQnER
- 1. Did the EOF /RC staff demonstrate the ability Yes/No to activate and staff the EOF /RC7
- 2. Did the EOF /RC staff demonstrate the ability Yes/No to appropriately implement Emergency Plan Implementing Procedures and did they follow the :':
I l i l ()
R;v. 0 l Page 4.3-B.12 i YER?iONT YANKEE NUCLEAR Pab[fJLSTATION EMERCENCY RESPONSE ParPAntnNESS EYrRCISE 1110 ATIACHMENT B (Continued) ; IV. DIERGENCLDEERAIIDNILIACILITY/ RECOVERY CENIER kmting CDpmanta
- 3. Did the Corporate Security Force establish Yes/No access control into the EOF /RCf Yes/No ;
- 4. Did the EOF Coordinator demonstrate the _
ability to maintain command and control of t EOF emergency response activities? l
- 5. Did the EOT/RC keep other emergency response _ Yes/No !
facilities advised of the status of their !' activities and information which they had developed? j O 6. Were the EOF /RC organization and the initiation of activity efficient and well organized? _ Yes/No
- 7. Did the Site Recovery Manager demonstrate the Yes/No [
ability to maintain the command and control of ! the overall emergency response effort and f organization? l
- 8. Did the Site Recovery Manager demonstrate the Yes/No l ability to de-escalate from the emergency 8 phase into the recovery phase? .
- 9. Were preliminary recovery plans established Yes/No :
and discussed between the Site Recovery { Manager and appropriate personnel? , C. Radiological Assessment. !
- 1. Was information concerning radiological and Yes/No i meteorological data obtained by appropriate i EOF personnel in a timely manner? ;
- 2. Did the EOF staff demonstrate the ability Yes/No r to perform off-site dose assessment in l
accordance with Procedure OP-35137 i 2149e r
*e
R:v. O Page 4.3-B.13 s - VERMONT YANKEE NUCLEAR POWER STATION EMIAGMCLESt0MLHEFAILEDtESS EKEACiliE 1110 AIIACHMENT.B (Continued) IV. EtifAGELY OPER4I1QNB FACILITY / RECOVERY CENTER Ratine Comments
- 3. Did the EOF staff demonstrate the ability to Yes/No effectively track and define the plume utilir.ing the computerized dose assessment model (METPAC)?
D. Protgetive Action Decision-Makins 1, Did the Radiological Assistant's staff Yes/No demonstrate the ability to perform timely assessment of off-site radiological conditions to support the formulation of protective action recommendations?
- 2. Did the EOF Coordinator obtain and provide Yes/No the necessary information to the Site Recovery Manager concerning protective action recommendations in accordance with -
Procedure ope 3511. l l
- 3. Did the Site Recovery Manager demonstrate . Yes/No the ability to make protective action recommendations to off-site authoritfee in accordance with Procedure OP-35117 Controller / Observer Namet ,
t _ _ .- __'e
R:v. O Page 4.3-B.14 YLILMONT YANKEE NUCLEAR POWER STATION DiERGENCL2ESTONSE_FAEFAREDNESS .EKERCISE 1120 ATTACHMENT..B (Continued) ; V. $1IE AND OFF-SITE _MONIIORING 141138 CQEneD18 A. Activation and ReA&QnAA
- 1. Did the site and off-site monitoring teams Yes/No demonstrate the ability to transmit t
' information over the radio utilizing proper units and terminology in accordance with Procedure 0?-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 O equipment, field monitoring procedures, and what was required of them?
- 4. Were off-site monitoring teams able to Yes/No determine and connunicate their location in the field using appropriate maps and .
sample points (landmarks)? I r l ! i l l Controller / Observer Names i 2149e
<< l
I R;v. O Page 4.3-B.15 YEMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1110 ATTACHMENT _) (Continued) K VI. SECURlII Rating Comments A. Activation and ResPQnat
- 1. Did the Security staff demonstrate the ability Yes/No !
to perform accountability of personnel within the Protected Area in accordance with Procedures OP-3524?
- 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 O to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
Controller / Observer Namet 2149e
Rov. O Page 4.3-B.16 O- VIBliONT YANKEE NUCLEAR POWER fLIATION Dif,RGENCY RMTONSE PREPAREDNESS EXERCISE 119.0 ATTACHMENT B (Continued) VII. Huis MEDIA CENTER Ealing Comments A. Ac11Yation_and_Rampanst I
- 1. Did the News Media staff demonstrate the Yes/No !
ability to activate and staff the News Media Center?
- 2. Was information flow between the News Media Yes/No Center and EOF /RC timely, complete, and accurate?
- 3. Were the News Media staff familiar with their Yes/No rians and procedures and do they follow them?
- 4. Did the News Media staff demonstrate the , . - Yes/No ability to provide accurate and timely information concerning the emergency to the public and the news media?
- 5. Did the News Media staff demonstrate the Yes/No !
ability to coordinate news releases with the state's public 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?
i Controller / Observer Name: 2149e e
R:v. O P0ge 4.3-C.1 VERMONT YANKEE NUCLEAR POWER STAT 1QN EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1DE ATTACHMENT C Emeraency Exerclae/ Drill Qhaarver's Evaluation Fogg Observer's Name ___ Exercise / Drill Date Exercise / Drill Title Observer's Location: Time Started: Time Ended _ _ _ _ Observed Plaver Function Overall Performance and Observations (include the proper and effective use of procedures, equipment and personnel): Recognized Deficiencies Comments and Recommendations (Specific): E0_IE Use additional pages as required. Signature Titlet VYOPF-3505.02 ! OP-3505. Rev. 14 Page 1 of 1 2149e
Rev. O Page 4.3-C.2 YISMONT YANKEE NUCLEAR POWER _SIAIl0S EMERGENCY RESPDERLEEEAILEDNESS EKERCISE 1110 ATTACHMENT..C (Continued) O . Continued on Additional Pages Yes No Signature:
Title:
Date: 2149e t
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i1 # t j j .- G VERMONT YANKEE NUCLEAR POWER STATION ENERGENCY RESPONSE PREPAREDNESS' EXERCISE
-1990
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!l Rev. C VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESFONSE PREPAREDNESS 1990 5.1 INITIAL CONDITIONS !
(This information will be provided to the players at the start of the exercise). ;
- 1. The Reactor is now at approximately 100% rated power. The reactor has been operating steady state for the past sixteen months with no recent l shutdowns.
- 2. Night orders for the operations crew are as follows:
- a. Containment de-inerting has commenced on the previous shift for a - fj scheduled power reduction and Drywell entry; Reactor Engineering staff
~
has determined that power reduction should not exceed 1% per 3 minutes,
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs) . RRUs 2'and 4 are showing abnormal amperage fluctuations. (
- c. The Auxiliary Operators are changing the suction' filters on the "B" Control Rod Drive (CRD) Pump.
- 3. All other power generating and safety system equipment is operable.
- 4. The following on-site meteorological conditions exist at 0700: ,
Wind Speed , mph (lower / upper) 2.0/5.6 Wind Direction , degrees (lower / upper) 10/348 Delta Temperature ,'F-(lower / upper) -0.7/-0.6 Ambient Temperature , 'F 53.4 Precipitation , inches 0.0
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- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than 10s. A high pressure system centered over Pennsylvania this morning will drif t to the southeast and slowly weak'en during the day. This system will dominate the weather today. O O
l l I Rev. O ; Page 5.1 3 Table 5.1-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 162 inches Reactor Pressure 1,00E psig Reactor Power APRM (average) 100% Core Plate Differential Pressure 20.0 psid Total Core Flow 46 mil lbs/hr Main Steam Line Flow - Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr Condenser Hotwell Level 56% Condenser Vacuum 2.6 indes Hg(/ts) Condensate Storage Tank Level 52%
-Reactor Coolant Temperature 527 'F Recirc' Drive Flow (average) 30,000 gpm Feedwater Flow 6.4 mil lbs/hr
\_
Reactor Building Differential Pressure -0.75 inches Hg Drywell Pressure 1.70 psig Drywell Temperature 140 'F Torus Water Level 1.16 ft Torus Temperature 72 'F Drywell/ Torus 0, Concentration 2.6% High Range Containment Monitors 2.7 R/hr ; Containment Gas / Particulate 600/60,000 cpm Reactor Building Vent Monitors Gas /Part 500/4,000 cpm > Reactor Building Vent Exhaust N/S- 1.5/1.5 mR/hr Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uCi/sec Stack Gas I/II 150/200 cpm High Range Noble Gas Monitor 0.1 mR/hr _v
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?g"' 32, ENERGENCY RESPONSE PREPAREDNESS 6 EXERCISE;
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Rev. O Page 5.2 1 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 5.2 NARRATIVE
SUMMARY
The scenario begins at 0700 vich the simulator reactor running at approximately 1004 power. The reactor has been in a steady state for the past sixteen months with no recent shutdowns. Night orders have instructed the operations crew that containment de-inerting _ has been started for a scheduled power reduction and drywell entry. The Reactor Engineering staff has determined that power reduction should not exceed 1% per 3 minutes. The drywell entry is needed to accomplish repairs to the Drywell Reactor Reci;culatico Units (RRUs) . RRUs 2 and 4 are showing abnormal cmperage fluctuations. The Auxiliary Operators have also been 9 directed to change the suction filters on the "B" Control Rod Drive (CRD) Pump, All other power generating and safety system equipment is operable. At 0730, an earthquake is sensed on-site and could be felt at various locations around the plant. Upon confirmation that an earthquake has been sensed on site, the Shif t Supervisor should_ declare an UNUSUAL EVENT. The UNUSUAL EVENT (approximately 0745) is based upon AP 3125, " Natural Phenomenon", due to any earthquake sensed on site as recognized-by either observation, detection or notification. The Shift Supervisor should initiate the appropriate notifications concerning the . declaration of the UNUSUAL EVENT. and changing plant. conditions. -The shift operations crew will initiate appropriate procedures to check plant instrumentation and to conduct visual inspections for an assessment of _ any potential damage caused by the earthquake. O 1
I I Rev. 0 Page 5.2 2
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v At 0800, a high turbine vibration alarm occurs. The turbine trips on a high vibration signal causing an automatic reactor SCRAM signal. When the reactor SCRAM signal occurs, the control rods fail to insert cauwing the reactor to remain critical and an Anticipated Transient Without Scram (ATWS) condition exists. This results in reactor power remaining above 2%. The Main Steam' Isolation Valves (MSIVs) are still open and pressure is being regulated by the Electric Pressure Regulator (EPR) and the turbine bypass valves to the Main Ccndenser. An ALERT should be declared (approximately 0815) based upon AP 3125, " Loss of Systems or Equipment", due to failure of Reactor Protection System (RPS) to initiate or accomplish a required SCRAM. gs Following the ALERT, the Technical Support Center (TSC), Operations Support
\ Center (OSC), and Emergency Operations Facility / Recovery Center (EOF /RC) will be activated and staffed. Notifications should Ebe made ' to the appropriate personnel including the state and federal authorities.
The Control Room staff will initiate actions to stabilize the plant, and the operators will attempt to individually drive control rods into the reactor core. The control rods will be allowed to be inserted f 1 successfully. Operators will insert the control rods in-accordance_with Reactor Engineering directions. l l By 0830, the "A" CRD Pump trips due to an electrical breaker problem. i Operators will not be able to continue to. insert control rods into the
-1 reactor core because both "A" and "B" CRD Pumps are'not available. Plant j personnel should be dispatched to investigate the problem on "A" CRD Pump or expedite the completion of the filter replacement on "B" CRD. Pump.
O
I Rev. O Page 5.2 3 B) 0925, Loss of Main Condenser vacuum occurs due to condenser air in. 3 leskage problems. Loss of condenser vacuum causes the closure of the MSIVs. The Main Condenser is no longer available as a heat sink. Control rods are still not fully inserted and reactor power is still above 2t ; By 0935, one of the CRD Pumps will be returned to service (depending upon plant corrective actions - and decisions) . Operators will be able to continue to individually drive - control rods into the reactor core, Reactor power will be reduced as the control rods are successfully inserted. A SITE AREA EMERGENCY should be declared (approximately 0945) based upon AP 3125, " Loss of Systems or Equipment", due to failure of Reactor Protection System (RPS) to initiate and accomplish a required SCRAM with the Main Condenser unavailable. Upon primary containment isolation, operators will continue control rod insertion and implement actions to stabilize the plant. This will include using the Safety Relief Valves (SRVs) HPCI or RCIC with the torus as the heat sink to control reactor pressure and cooldown. Operators will also start RHR in the torus cooling mode and monitor torus temperature and level. I Reactor power reduction and pressure control will continue. Once all control rods have been inserted' into the reactor core, ope rators will , commence a reactor cooldown. Plant conditions will be stabilizing and , remaining fairly constant for the next hour and thirty' minutes. Plant discussions may begin on the possibility of de-escalation from the emergency phase to a recovery mode of operation. I O 1
Rev. 0 Page 5.2 4 9 At 1130, the Simulator Operator will insert a casualty that causes a large ster- line break inside the primary containment. A rapid depressuri::ation of the reactor will occur with a rapid increase in containment pressure. The rapid reactor pressure decrease causes fuel cladding failures and releases fission product gases into the primary containment. The containment radiation monitors will have increased significantly. By 1135, a high drywell pressure _ alarm is received which initiates a Primary Containment Isolation of Groups 2, 3, and 4. The simulator control board will indicate that the' Torus Purge Supply Valve (V16 19 10) did not close on Group 3 isolation. Reactor operator efforts to isolate the Torus Purge Supply Valve (V161910) are unsuccessful. Area radiation monitors in the Reactor Building are increasing significantly. Plant Vent e Stack monitors are indicating a release- of radioactivity to the environment. The release pathway is associated with a flange being dislodged upstream of the Torus Purge Supply Valve - (V16-19 10) in the Reactor Building. A GENERAL EMERGENCY should be declared (approximately 1145) based upon AP 3125, " Fuel Damage ," due to the loss of two of three fission product barriers with the potential loss of third. By 1200, it is anticipated that on-site assistance teams should be dispatched to investigate the leak in the Reactor Building and the problem associated with the Torus Purge Supply Valve (V16-19-10). By 1300, the repairs associated with the Torus Purge Supply Valve (V16 19-10) have been completed. The leakage into the Reactor Building is isolated. 9
. - - - - - . - = , - , . . ., , . .
1 l Rev. 0 l Page 5.2 5 1 i By 1330, the plant is stabilized, and the Plant Vent Stack monitors have decreased. The source of the release into the Reactor Building has been controlled and isolated.- Therefore, the release of radioactivity to the environment will continue to decrease with time based upon the volume exchange rate of the Reactor Building through Standby Gas Treatment System. De-escalation from the emergency phase into the recovery mode is now feasible. At 1400, the exercise will be terminated. I 1 O
O VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 5,3 SCENARIO TIME LINE O O
Rev. O Page 5.3 1 i VERMONT YANKEE NUCLEAR POWER STATION
. EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 5.3 SCENARIO TIME LINE CLOCK SCENARIO TIME TIME DESCRIPTION 0700 0:00 .
< .' ' Initial conditions established.
0715 0:15 - 0730 0:30 <... Earthquake sensed'on site. 0745 0:45 -
<-- . UNUSUAL EVENT (AP 3125, NATURAL PHENOMENON) - Any Earthquake 3 sensed on site as recognized by-either observation, detection, or notification.
0800 1:00 .
< -- Turbine vibration alarm. Turbine trips. Rx SCRAM signal occurs with control rods not inserting. ATWS condition exists.
0815 1:15 -
<--- ALERT (AP 3125, LOSS OF SYSTEMS OR EQUIPMENT) - Failure'of Reactor Protection System (RPS) to initiete or' accomplish a required SCRAM.
0830 1:30 - <- - "A" CRD Pump trips. No CRD Pumps available to drive control rods. Plant personnel dispatch to investigate CRD Pump problems. 0845 1:45 . 0900 2:00 - 0915 2:15 - 0925 2:25 -
<... Loss of Main Condenser vacuum causes MSIV closure. Control rods still not inserted and Reactor power above 2%.
0930 2:30 . 0935 2:35 .
<--- CRD Pump returned to service. Operators continue to drive control rods.
1
Rev. O Page 5.3 2 5.3 SCENARIO TIME LINE (continued) OlhCK SCENARIO s/ TIME TIME DESCRIPTION , 0945 2:45 - <--- SITE AREA EMERGENCY (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. 1000 3:00 <-.- Operators to continue control rod insertion and implement actions to stabilize the plant. 1015 3:15 -
<.-- Reactor pressure and cooldown is being controlled. Plant conditions stabilizing and remaining fairly constant.
1030 3:30 - 1045 3:45 - 1100 4:00 . O
- I
( )1115 4:15
~
1130 4:30 <-.. Steam Li- Bretk Inside Primary Containment. Rapid depressurization occurs. 1135 4:35 <.-. PCIS occurs (Grtups 2,3,4). Problem-with Torus Purge Supply Valve V16-19 10. ARMS in Rx Bldg. increasing significantly. Plant Vent Stack release begins, 1145 4:45 <.-. GENERAL EMERGENCl (AP 3125, FUEL DAMAGE) . Loss of. 2 of 3 fission product carriers with the potential loss of thir.d. 1200 5:00 -
<--- Teams sent.to investigate Reactor Building leakage and problem with_the Torus Purge Supply Valve (V16 19 10).
~
l l 1215 5:15 . l 1 (3 x.;s
Rev. O I Page 5.3 3 5.3 SCENARIO TIME LINE (continued) i CLOCK SCENARIO 4 TIME TIME DESCRIPTION 1230 5:30 . 1245 5:45 . 1 1300 6:00 .
< . , . . Repairs to,the Torus Purge Supply Valve (V16 19 10) have been completed. Leak into Reactor Building is isolated.
1315 6:15 . 1330 6:30 .
<... Plant is stabilized. Release from Plant Vent Stack has been controlled. De-escalation from the emergency phase into the recovery mode is possible.
1345 6:45 l
~
9 1400 7:00 -
<--- EXERCISE IS TERMINATED.
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~i I-O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 i
5.4 DETAILED SEOUENCE OF EVENTS O 4 2498e
Rov. O Page 5.4-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 5.4 DETA11th SEQUENCE OF EVENTS Clock- Scenario Time Time Event / Action Messagg Ca==nd Prior to EXPECTED CONTROL ROOM (CR) ACTIONS 0700 00:00 WILL BE IMPLEMENTED BY AN EXERCISE OPERATIONS CREW (INCLUDING SUFFICIENT NUMBER OF PRESTAGED INDIVIDUALS FROM THE VERMONT YANKEE EMERGENCY ORGANIZATION) LOCATED IN THE SIMULATOR COMPLEX IN THE CORPORATE TRAINING CENTER. OPERATIONAL CONTROL ROOM DATA WILL BE PROVIDED BY THE SIMULATOR INSTRUMENTATION RESPONSES. IN CASES WHERE SPECIFIC INFORMATION NOT MONITORED BY THE SIMULATOR IS REQUIRED, IT WILL BE ISSUED BY CONTROLLERS /0BSERVERS ON MESSAGE CARDS. IN THE EVENT THAT A SIMULATOR MALFUNCTION OCCURS, THE EXERCISE WILL BE CONDUCTED USING INFORMATION DEVELOPED FROM SECTION 8.0 AND SECTION 9.0. 2498e
1 Rsv. O Page 5.4-2 Clock Scenario lime _, . lime . Event /ActiQD Message Connand Prior to The Simulator CR Controller issues SCR-M-1 SCR-C-1 0700 00:00 initial conditions to the simulator (Cont'd) CR players. Guidelines for use of Gaitronics and the plant evacuation alarm are provided to players. Initiating messages are also CR-M-1 provided to all emergency centers TSC-M-1 , and f acility staf f s upon subsequent TSC-N-2A activations. Operational and TSC-M-2B radiological data will be available OSC-M-1 to the TSC via TSC communicators SRM-M-1 who normally respond to EOF-M-1 the CR prestaged in the ESC-M-1 simulator. Security will be provided a list of Controllers / Observers and nonparticipants who will not have to be accounted for during the exercise. 0700 00:00 Simulator is put into operation. Reactor power is at 100 percent power. The reactor has been operating steady state for the past 16 months with no recent shutdowns. 2498e
1 Rev. O Page 5.4-3 Clock Scenario lime _ _ Time _ Event / Action tiessaac Coltmand 0700 00:00 Hight orders have instructed the (Cont'd) Operations crew that containment de-inerting has begun on the previous shift for a scheduled L, power reduction and drywell entry. The Reactor Engineering staff has determined that power reduction should not exceed 1% per three minutes. The drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs). RRUs 2 and 4 are showing abnormal amperage fluctuations. The Auxiliary
-Operators have been directed to O change the suction filters on the "B" Control Rod Drive (CRD) pump.
All other power generating and safety system equipment is operable. 0730 00:30 An earthquake is sensed on-site SCR-M-2 and can be felt at various locations around the plant. Control Room operators should SCR-M-3 initiate Procedure OP-3127,
" Natural Phenomena" which will instruct them to check plant instrumentation and to conduct visual inspections for an assessment of the potential O damage caused by the earthquake.
2498e
Rev. O Page 5.4-4 Clock Scenario Time. Time Event / Action Message Command 0730 00:30 This will include checking j (Cont'd) indications on the seismic accelerometer and contacting SCR-M-4 SCR-C-2 Vernon and Bellows Falls dams ; for an assessment of dam status. Approx. Approx. The Shift Supervisor should declare 0745 00:45 an UNUSUAL EVENT based upon the following EAL: AP-3125, " NATURAL PHENOMENON - Any earthquake sensed on-site as recognized by either observation, detection or notification." The SS/ PED should initiate. Procedure OP-3500, Unusual Event and refer to Appendix I, the SS/ PED checklist. Operators may dispatch other plant personnel (auxiliary operators or security force) to perform plant inspections / tours associated with the earthquake event and other plant activities. FOR EXERCISE PURPOSES, EARLY SCR-C-3 IN-STATION ACTIONS MAY BE CONTROLLED j AND PERFORMED BY THE SIMULATOR CONTROLLERS.
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R:;v, O Page 5.4-5 Clock Scenario ; Ilmt_. ._Ilme Ersat/ Action Meanage Command Approx. Approx. The SS/ PED should announce l 0745 00:45 the Unusual Event over (Cont'd) the Plant Paging System. This activity will be performed by players in the Simulator CR, and simultaneously performed
- by a Controller directed member =
of the operating shift crew in the actual Control Room. The SS/ PED should notify Vermont, New Hampshire, and Massachusetts State Police Agencies using the Nuclear Alert System-(orange phone) and provide the _\ appropriate message to each agency. The SS/ PED should notify the NRC on the red phone 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. 2498e a
Rsv. O Page 5.4-6 7 ( Clock Scenario lime _ _ Time Event / Action tiastagt CQmmand Approx. Approx. The Security Shif t Supervisor 0745 00:45 should notify Yankee Nuclear (Cont'd) Services Division (YNSD) Security and activate the YNSD Personnel Group Paging System.
' The Security Shif t Supervisor should also notify New England Hydro Power Station of the Unusual SEC-C-1 Event. THIS CALL WILL BE SIMULATED.
The Primary and Secondary Duty and Call Officers (DCOs) should report to the plant after notification of the Unusual Event 7-s > (,,/ Status. The DCOs should contact the SS/ PED to be advised of the situation. Responsibility for TSC and E0F Coordinator assignments would be discussed, as appropriate. The TSC Coordinator should assume the overall supervision and l l coordination of the on-site emergency response activities. This will include escalating the emergency classification as conditions warrant. (} v 2498e
l Rsv. O Page 5.4-7 j
! Clock Scenario limc_, Time Event / Action Message Command l
Activation of the Technical Support Center (TSC) is optional l at the Unusual Event. 0750 00:50 IF AN UNUSUAL EVENT HAS NOT BEEN SCR-C-4 DECLARED BY THE SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS TIME. Plant personnel sent to perform a OSC-M-2 visual inspection of the plant will find no damage from the earthquake. 0800 01:00 Simulator control board indicates high turbine
'q) vibration alarm.
Turbine trips on high vibration signal causing an automatic reactor SCRAM signal. When the reactor SCRAM signal occurs, the control rods fail to insert causing the reactor to remain critical. An Anticipated Transient Without Scram (Ah!S) condition exists. Reactor power is also above 2%.
/~ 2498e \
Rev. O Page 5.4-8 Clock Scenario Ii m Time Event / Action lienage Command 0800 01:00 The SS/ PED should notify the i3C (Cont'd) Coordinator of the changing plant conditions, and that a partial reactor SCRAM occurred. The TSC Coordinator and SS/ PED
' should start to review the plant conditions against Procedure AP-3125, " Emergency Plan Classification and Action Level Scheme."
The Control Room personnel will be working to stabilize plant conditions, and the operators will start to manually drive control rods that have not fully inserted into the core. Operators will insert the control rods in accordance with Reactor Engineering directions. The Main Steam Isolation Valves (MSIVs) are still open, and pressure is being regulated by the Electric Pressure Regulator (EPR) and the turbine bypass valves to the Main Condenser. 2498e
)
Rev. O Page 5.4-9 9 Clock limg_ Scenario Time Event / Action dettage Command Approx. Approx. The SS/ PED or TSC Coordinator 0815 01:15 should declare an ALERT based upon the following EAL: AP-3125,
" LOSS OF SYSTEMS OR EQUIPMENT -
Failure of the Reactor Protection System (RPS) to initiate or accomplish a required SCRAM." The SS/ PED directs the operations staff to initiate Procedure I OP-3501, " Alert." An Alert announcement should be
; made over the plant page instructing emergency personnel 2=- d,!,!,I to report to their assigned emergency response facilities,
___ and other personnel, contractors, and visitors return to the Governor Hunt House Information Center and wait for further E instructions. Y t L At this time, the Technical Support Center (TSC), Operations Support Center (OSC), and the Emergency Operations Facility / Recovery Center (EOF /RC) should be activated and staffed. 2498e n a
i Rsv. O Page 5.4-10 Clock Scenario Event / Action Time Time Message Command Approx. Approx. The SS/ PED should notify the Vermont, 0G15 01:15 New Hampshire, and Massachusetts (Cont'd) State Police Agencies of the escalation to the Alert emergency classification. The NRC should be notified of the escalation to the Alert. The Security Shift Supervisor should initiate the emergency call-in method for the Alert classification. The Security Shift Supervisor () should notify Yankee Nuclear Services Division (YNSD) Security of the escalation to the Alert status. Upon Alert notification, the YNSD Engineering Support Center (ESC) is activated. The Security Shif t Supervisor should notify the New England Hydro Power Station in Vernon of the escalation to the Alert status. THIS CALL WILL SEC-C-1 BE SIMULATED. , i I 2498e O l i i
Rev. O Page 5.4-11 lh Clock h Scenario
. Time Event / Action tit 18A&R CQIDoland Approx. Approx. The TSC Coordinator should 0815 01:15 notify REMVEC of the Alert status (Cont'd) and plant conditions.
0820 01:20 The Security Shift Supervisor should ensure that an accountability of personnel has been initiated in accordance with procedures SP-0906, " Emergency Procedures" and OP-3524,
" Emergency Actions to Ensure Accountability and Security Response."
The TSC Coordinator should respond, h activate, and staff the TSC in accordance with Appendix III of OP-3501, " Alert." TSC staff representing the following departments should assemble at the TSC following the declaration of an Alert:
- 1. Instrument and Control Supervisor
- 2. Radiation Protection Supervisor or designated '
alternate 2498e
- - - = = = = = = = =
Rav. O Page 5.4-12 Clock Scenario lime _ Time Event /Aetion lic11Att Comand . 0820 01:20 3. Reactor and Computer (Cont'd) 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.).
0825 01:25 The Emergency Operations Facility (EOF) Coordinator should activate and staff the EOF /RC in accordance with Appendix IV of OP-3501,
" Alert."
2498e
i Rsv. O Page 5.4-13 Clock Scenario O1 Time Time Event / Action Massage CDamAnd 1 0825 01:25 The emergency response staff that (Cont'd) reports to the EOF /RC includes the following:
- 1. Site Recovery Manager and designated corporate staff
- 2. EOF Coordinator 1
- 3. Purchasing Supervisor
- 4. Public Information Liaison
- 5. Additional trained plant -
staff members to assume the
) following tag board assignmencs: ,
EOF Coordinator's Assistant Radiological. Assistant Manpower and Planning Assistant i Communications Assistant 2498e O
, , , , , - ' . . . . . - i,,,.
.u. h .- ,
Rev. O Page 5.4-14 Clock Scenario Iig)L Time Event / Action litAAAge Command 0825 01:25 - Radiological Coordinator (Cont'd) i
- Personnel and Equipment Monitoring Team
- 6. Corporate Security Force The Operations Support Center (OSC)
Coordinator (assigned by the TSC Coordinator) should act.ivate and staff the OSC in accordance with Appendix VII of OP-3501,
" Alert."
The plant staff that reports to the OSC includes the following:
- 1. Radiation Protection and Chemistry Assistants and Technicians
- 2. Control Instrument Specialist
- 3. Maintenance Staff
- 4. Status Board Caretaker
- 5. Other personnel as required.
2498e l
Rev. O Page 5.4-15 [") Clock IlmL Scenario lime Ennt/Aet10D tiidiligt Command 0825 01:25 The Site Recovery Mansger (SRM) (Cont'd) and staff should report to the EOF /RC and implement the procedural steps listed in Appendix V:13 of OP 'J501,
" Alert."
Radiation Prots? tion Technicians from the 8 0 may be disp.atched to perform dose rate radiation surveys, air sampling, and contamination surveys of the plant. 0830 01:30 IF AN ALERT HAS NOT BEEN DECLARED SCR-C-5 BY THE SS/ PED, HE WILL BE DIRECTED - TO DO SO A7 IlilS TIME. Approx. Approx. Jimulator control board indicates 0830 01:30 th* "A' CRD pump has tripped. Operators will not be able to continue to insert control rods into the reactor core. The SS/ PED should immediately inform the TSr Coordinator and SRM concerning the unavailability of both "A" and "B" CRD pumps. 2498e (
.=
Rev. O Page 5.4-16 0) b Clock Time _ Scenaric _ Time Event / Action Message CamEAnd Approx. Approx. Plant personnel should be OSC-M-3 , 0830 01:30 dispatched to investigate the OSC-M-4 (Cont'd) problem on "A" CRD pump or expedite the completion of the filter replacement on "B" CRD pump (refer to Miniscenarin 7.2.1). Control Room staff vill implement actions necessary to keep the plant stabilized. 0845 01:45 News release on the details of NMC-M-1 the earthquake is broadcast over the local radio and , television network. 0 I Loss of Main Condenser vacuum occurs Approx. Approx. 0925 02:25 due to condenser air in-leakage problems. Loss of condenser vacuum i causes the closure of the Main Steam Isolation Valves (MSIVs) on containment Group 1 isolation. , [ The Main Condenser is no longer available as a heat sink. Reactor , power is still above 2%. Upon MSIV closure, the SS/ PED should notify the TSC Coordinator and SRM that a Group 1 isolation has occurred. (v') 2498e
l R v. O J Page 5.4-17 f () Clock lime _ Scenario _Ilme Eysnt/ Action Mtttage Command Approx. Approx. One of the CRD pumps will be OSC-M-5 0935 02:35 declared operable and returned - to service. Operators will be able to continue to individually drive control rods into the reactor core. 4 Reactor power will be reduced as the control rods are successfully inserted. 0935 02:35 The SRM, TSC Coordinator, and SS/ PED should evaluate plant conditions against Procedure AP-3125. " Emergency Plan g-~ Classification and Action Level V Scheme." The SRM with consultation from the TSC Coordinator and SS/ PED should recognize the need to escalate to a Site Area Emergency. Approx. Approx. The SRM should declare a SITE AREA 0945 02:45 EMERGENCY hased upon the f ollowing 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."
/~'N 2498c . Y ,)
R:v. O Fage 5.4-18 I Clock Scenario 4 Iirpe_. _Ilme EY_ent/Aetien llMA&&t CD Mand Approx. Approx. If present, the SRM should inform 0945 02:45 the NRC Site Team represent stives, - (Cont'd) the State representatives of Vermont, New Hampshire, and Massachusetts located at the EOF /RC and contact each State's E00s via the Nuclear Alert System to inform theu of the escalation to the Site Area Cmergency. The SS/ PED will also be directed to make the appropriate plant announcement concerning the escalation to the Site Area Emergency. l O Upgraded notifications should also be made to YNSD and the NRC. 09SO 02:50 Upon primary containment isolation, operators will continue control rod incertion and implement actions to stabilize the plant. This will include using the Safety Relief Valves (SRVs), HPCI, or RCIC with the torus as the heat sink to control reactor pressure and cooldown. 2498e
Rsv. O Page 5.4-19 ( Clock Scenario Ilmt._ Time Zyent/ Action tits sage Gn-and 0950 02:50 Operators will also start RER in (Cont'd) the torus cooling mode and monitor torus temperature and level. 1000 03:00 IF A SITE AREA EMERGENCY HAS NOT SRM-0-1 BEEN DECLARED BY THE SRM, HE WILL
' BE DIRECTED TO DO SO AT THIS TIME.
1030 03:30 Reactor power reduction and pressure control will continue. Plant condi* tons will be stabilizing , and remaining fairly constant. Plant discussions may.begin on the possibility of de-escalation from the emergency phase to a recovery mode of operation. 1040 03:40 The ESC should be providing ESC-M-2 technical and engineering support to the Vermont Yankee staff. The ESC meteorologist - should provide a specialized weather forecast for the Vermont Yankee site. 2498e (V~') l
Rcv. 0 Page 5.4-20 m () Clock Ilme_ Scenario _Ilme EYant/ Action des &> Command 1130 04:30 A casualty will be inserted by Simulator Operator that causes a large steam line break inside the primary containment. A rapid depressurization a' 'h: reactor occurs with a rapid increase in containment pressure. The rapid reactor pressure decrease causes fuel cladding failures and releases fission product gases into the primary containment. The containment radiation monitors will have increased significantly. 7-s 1135 04:35 A high drywell pressure alarm is received which initiates a l Primary Containment Isolation of Groups 2. 3. and 4. Simulator control board will indicate that the Torus Purge Supply Valve V16-19-10 did not close on Group 3 isolation. Area radiation monitors in the Reactor Building are increasing significantly. 2498e UN
----_--.-_-.___m_._-__-..._____m.
R:v. O rage 5.4-21 () Clock Ilme_ Scenario Ilme Eyent/Aetien titlingt Command 1135 04:35 Standby Cas Treatment System (SBGTS) initiated automatically on Group 3 isolation. Stack Gas Monitors I/II, and high-range plant vent stack monitor begin to increase as indicated by the simulator control board. The release pathway is associated , with a flange being dislodged upstream of the Torus Purge Supply , Valve V16-19-10 in the Reactor Building. (- U Reactor operator efforts to isolate the Torus Purge Supply Valve V16-19-10 are unsuccessful. Approx. Approx. The SRM, with consultation from 1145 04:45 the TSC Coordinator and SS/ PED, should recognize the need to escalate to a General Emergency. The SRM should declare a GENERAL EMERGENCY based upon the following EAL: AP-3125, " FUEL DAMAGE - Loss of 2 of 3 fission product barriers with potential loss of third." t' 2498e b]
R:v. O Page 5.4-22 Clock Scenario ML Time Event /Act1QD Message Cunnaad Approx. Approx. If present, the SRM should inform 1145 04:45 the NRC Site Team representatives, (Cont'd) the Stntc representatives of Vermont, New Hampshire, and Massachtteetts located at the EOF /RC, and contact each state's EOCs via the Nt. clear Alert System to inform them of the escalation to the General Emergency. l The SS/ PED will also be directed l to make the appropriate plant I announcement concerning the escalation to the General Emergency. Upgraded notifications of the General Emergency status should should be made to YNSD and the NRC. The SRM should implement Procedure OP-3511, "Off-Site Protective Action Recommendations," to formulate and recommend protective actions to State authorities based upon plant conditions. 2498e J .
l R v. O i Page 5.4-23 l l [ Clock Scenario \ EnntlAc.11on Command litoe_ _. Time MeJAase 1150 04:50 Stack gas monitors continue to escalate due to noble gases and lodines passing through the standby gas treatment charcoal filters. l l 1 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 I 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. The SS/ PED should inform the TSC Coordinator and SRM that the Torus Purge Supply Valve V16-19-10 did not close upon Group 3 isolation and attempts to isolate the valve were unsuccessful. 2498e t U c
R:v. O Page 5.4-24 Scenario O' Clock Ilme_ Time Event / Action MgAggge Command 1200 05:00 IF A GENERAL EMERGENCY HAS NOT BEEN SRM-C-2 DECLARED BY THE SRM. HE WILL BE DIRECTED TO DO SO AT THIS TIME. Approx. Approx. Team should be requested to take 1200 05:00 a plant vent stack sample (refer to Procedure OP-3530 " Post-Accident Sampling"). Plant personnel should be looking for the source of the leakage into the Reactor Building. On-site assistance teams may be dispatched to investigate the leak in the Reactor Building. Approx. Approx. TSC personnel should also be , 1200 05:00 investigating the problem associated with the Torus Purge Supply Valve V16-19-10 (refer to Miniscenario 7.2.2). Approx. Approx. The team sent to investigate the OSC-M-6 1215 05:15 problem with the Torus Purge OSC-M-7 Supply Valve V16-19-10 will find that the valve indication , is open. Corrective actions to close the valve will be expected to occur by the team. l 2498e
I Rev. O Page 5.4-25
) Clock Time _
Scenario T4me Event / Action Messane Command 1230 05:30 The ESC has reviewed the latest ESC-M-3 NWS forecast and has updated meteorological information for the site. An updated weather forecast is EOF-M-3
'available fror. NWS.
IF NOT ALREADY DONE, THE TSC TSC-C-1 COORDINATOR WILL BE DIRECTED TO DISPATCH AN ON-SITE ASSISTANCE TEAM TO INVESTIGATE PROBLEM WITH THE TORUS PURGE SUPPLY VALVE V16-19-10. 05:45 IF A NATIONAL WEATHER SERVICE EOF-C-1
- 1245
( UPDATE KAS NOT BEEN REQUESTED BY THE RA, HE WILL BE PROVIDED WITH ONE. Approx. Approx. Repairs associated with the Torus OSC-M-8 SCR-C-6 1300 06:00 Purge Supply Valve V16-19-10 OSC-M-9 have been completed. Simulator control board indications show that the Torus Purge Supply Valve V16-19-10 has closed. Leakage past the Torus Purge Supply Valve has stopped.
Rev. O Page 5.4-26 () Clock Ilme_ Scenario Time Event / Action tiessage Comand Approx. Approx. The leak into the Reactor 1300 06:00 Building is isolated. 1330 06:30 Control Room indications show that plant conditions are stabilizing and the plant vent
' stack monitors have decreased.
The source of the fission product release into the Reactor Building has been controlled and isolated. The release of radioactivity to the environment will continue to decrease with time based upon the volume exchange rate of the Reactor Building 7-~ ! through Standby Gas Treatment System. De-escalation from the emergency phase into the recovery mode is now possible, approx. Approx. Exercise is terminated. 1400 07:00 (N 2498e
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 6.0 EXERCISE MESSACES O 2499e
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 6.1 CO N D CARDS O O
. _ - -- - . - . . . . .. - _ . - . - . . . . - . - . - - ~ . .. _ . . . . - . - - . - . ..
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE k 1990 i SECTION 6.1 . SCENARIO COMMAND CARD CROSS REFERENCE INDEX i CARD ClhCK SCENARIO SECTION 6.1 SECTION 5.4 NUMBER TIME TIME PAGE NO. PAGE NO.
....... ............. ........ ............ ............. i SCR.C 1 PRIOR TO 0700 00:00 6.1 1 5.4 2 -l SCR.C.2 0730 00:30 6.1 2 5.4 4 ,
SCR.C.3 0745/AS NEEDED 00:45 6.1 3 5.4 4 SEC.C 1 0745/AS NEEDED 00:45 6.1 4 5.4 6/5.4 10 I SCR.C 4 0750 00:50 6.1 5- 5.4 7 ; SCR.C.5 0830 01:30 6.1 6 5.4 15 L SRM.C 1 1000 03:00 6.1 7 5.4 19 f SRM.C.2 1200 05:00 '6.1 8 5.4 24 4 TSC.C.1' 1230/AS NEEDED 05:30 6.1 9 5.4 25 ' EOF.C.1 1245 05:45 6.1 10 5.4 25 SCR.C.5 1300/AS NEEDED 06:00 6.1 11 5.4 25-i r w I ( ~
b I R3v. 0 , Page 6.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE , 1990 SCENARIO CQtMAND..C&RD FROM: Simulator CR Controller _ COPMAND NO. SCR-C-1 TO: Shift Supervisor CLOCK TIME: Prior to 0700 LOCATION: Simulator Conttg1 Room SCENARIO TIME: Prior to 00:00 PARTICIPANT MESSAGE IRIS _.IS_A_ DRILL Communications systems that are availabic in the Control Room have been duplicated in the Simulator Control Room Area EXCEPT for Gaitronics and the plant evacuation alarm. Please use the Gaitronics/ Plant Evacuation Alarm in the Simulator Control Room to complete the required PA announcements. An Exercise Controller will then direct a member of the shift operating crew at the plant to repeat the announcements from ths Main Control Room. i l l 2499e i
R:v. O Page 6.1-2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO COPMAND CARD TROM: Eimulator CR Controller COtMAND NO. 3.CR-C-2 TO: $hift Suoarvisor CLOCK TIME: 0730 LOCATION: Simulator Control Room SCENARIO TIME: 00:30 PARTICIPANT MESSAGE ; TilIS IS A DRILL For exercise purposes. Control Room communications with Vernon and l Bellows Falls Dams will be simulated. O 4 2499e O :
Rev. O Page 6.1-3 [ VERMONT YANKEE NUCLEAR POWER STATION. EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO CCfMAND CARD TROM: Simulator CR Controller COPMAND NO. SCR-C-3 TO: Shift Suoervisor CLOCK TIME: 0745 LOCATION: Simulator Control Room SCENARIO TIME: 00:45 PARTICIPANT MESSAGE THIS IS A DRILL Early in-station actions will be simulated and information " requested at this time will be provided by controllers. O i i I i i 2499e
R v. O Page 6.1-4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO C0fftAND CARD FROM: Security Controller COMMAND NO.: SEC-C-1 TO: Security Suoervisor CLOCK TIME: 0745 or when net.dgL _ LOCATION: Security Catehause SCENARIO TIME: 00:45 ! PARTICIPANT MESSAGE IRIS IS A DRILL FOR EXERCISE PURPOSES, communications with New England Hydro Power Station in Vernon will be simulated. O 1 I l ( 2499e ) l
Rev. O Page 6.1-5 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENMWLCOMMAND CARD FROMi Simulator CR Coatrollar C0tMAND NO.I SCR-C-4 TO: Shift Sungrvisor CLOCK TIME: 0750 LOCATION: Simulator Control Room SCENARIO TIME: 00:30 PARTICIPANT MESSAGE THIS IS A DRILL DECLARE AN UNUSUAL EVENT BASED UPON AP .'4125 NATURAL PHENOMENON, ANY EARTHQUAKE SENSED ON-SITE AS RECOG'lIZED BY EITHER OBSERVATION, DETECTION, OR NOTIFICATION. O : A 2499e
Rev. O Page 6.1-6 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO. COMMAND. CARD , FROM: Eimulator CR controller COMMAND NO. RCR-C-5 TO: Shif t Suggnigor/ Plant CLOCK TIME: 0830 Emeraenev Director LOCATION: Simulator Control Room SCENARIO TIME: 01 30
/
PARTICIPANT MESSAGE IRIS IS A DRILL DECLARE AN ALERT BASED UPON AP-3125, LOSS OF SYSTEMS OR EQUIPMENT - FAILURE OF THE REACTOR PROTECTION SYSTEM (RPS) TO INITIATE OR ACCOMPLISH A REQUIRED SCRAM. 4 0
R3v. O Page 6.1-7 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO _C0ffiAND CARD FROM: SEM_CCDtID11er COMMAND NO. SRM-C-1 TO: Sits _.Rarovery Mananar CLOCK TIME: 1000 LOCATION: EQF/R0 SCENARIO TIME: 03t00 PARTICIPANT MESSAGE TifIS IS A DRILL DECLARE A SITE _ARELLEMERGENCY 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 2499e O ,
R;v. O Page 6.1-8 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE t 1990 , SCENARIO COMMAND CARD FROM: SRM Controller COMMAND NO. SRM-C-2 ; i TO: Eite Reenygry Manneer CLOCK TIME: 1200 LOCATION: EOF /RC SCENARIO TIME: 05:00 [ t PARTICIPANT MESSAGE Ill1S IS A DMLL DECLARE A GENERAL EMERGENCY BASED UPON AP-3125, FUEL DAMAGE, DUE TO 1.0SS OF 'IVO OF THREE FISSION PRODUCT BARRIERS WITH THE POTENTIAL LOSS OF THE THIRD. l r i I f i 2499e
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Rsv. O < Pcgo 6.1-9 ; VERMONT YANKEE NUCLEAR POWER STATION ! EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 i SCENARIO COPEAND CARD FROMt ISC._ Cont rolle r COMMAND NO.t ISC-C-1 TO: TSC Coordinator CLOCK TIME: 1230 or as ne And __ LOCATION: ISC SCENARIO TIME: 05:30 PARTICIPANT MESSAGE TilIS IS A DRILL DISPATCH ON-SITE ASSISTANCE TEAM TO INVESTIGATE PROBLEM WITH THE TORUS PURGE SUPPLY VALVE V-16-19-10. O l l i 2499e O : i
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Rev. O Page 6.1-10 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO COPMWD CARD FROMt EOF Contro11gr 00MMAND NO.: EOF-C-1 TO: Radio 19sical Asalatant ,_ CLOCK TIME: 1245 LOCATION: EOF /RA-Done Asseamment Area SCENARIO TIME: 05:45 PARTICIPANT MESSAGE THIS IS A DRILL REQUEST A WEATHER FORECAST FROM ESC AT THIS TIME. O 2499e
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Rsv. 0 l Page 6.1-11 l l 1 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO CottiAND_ CARD > FROMt Simulator CR Controller COMMAND NO. : SCR-C-6 TO: Shift Supervisor CLOCK TIME: 1300 or ma needed LOCATION: Simulator control Room SCENARIO TIME: 06:00 PARTICIPANT MESSAGE THIS IS A DRILL REPAIRS TO THE TORUS PURGE SUPPLY VALVE V-16-19-10 HAVE BEEN COMPLETED. SIMULATOR CONTROL BOARD INDICATIONS SHOW THAT THE TORUS PURGE SUPPLY VALVE V16-19-10 HAS CLOSED. LEAKAGE INTO THE REACTOR BUILDING IS ISOLATED. MAKE SURE THIS INFORMATION IS TOLD TO THE SITE RF,00VERY MANAGER AND TSC COORDINATOR. O 2499e V
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VERMONT YANKEE NUCLEAR POWER STATION (f-')s EMERGENCY RESPONSE PREPAREDNESS EXERCISE
'- 1990 SECTION 6.2 SCENARIO MESSAGE CARD CROSS REFERENCP INDEX CARD CLOCK SCENARIO SECTION 6.2 SECTION 5.4 NUMBER TIME TIME PAGE NO. PAGE NO.
SCR M 1 PRIOR TO 0700 00:00 6.2 1 5.4 2 CR M 1 PRIOR TO 0700 00:00 6.2 2 5.4 2 TSC.M 1 *
- 6.2 3 5.4 2 TSC M 2A UPON ASSIGNMENT 6.2 4 5.4 2 TSC M 2B UPON ASSIGNMENT 6.2 5 5.4 2 OSC M 1 *
- 6.2 6 5.4 2 SRM M 1 *
- 6.2 7 5.4 2 EOF M 1 *
- 6.2 8 5.4 2 ESC.M 1 *
- 6.2 9 5.4 2 SCR M 2 0730 00:30 6.2 10 5.4 3
/ SCR M.3 0735 00:35 6.2 11 5.4 3 ~- SCR M 4 APPROX 0740 00:40 6.2 12 5.4-4 OSC M 2 APPROX 0750/AS NEEDED 00:50 6.2 13 5.4-7 OSC M 3 APPROX 0830/AS NEEDED 01:30 6.2 14 5.4-16 OSC M-4 APPROX 0830/AS NEEDED 01:30 6.2 15 5.4-16 NMC M 1 0845 01:45 6.2 16 5.4 16 l OSC M 5 APPROX 0935/AS NEEDED 02:35 6.2-17 5.4 17 ESC M 2 1040/AS REQUESTED 03:40 6.2 18 5.4 19 6.2 20 5.4 24 OSC M 6 APPROX 1215/AS NEEDED 05:15 OSC M 7 APPROX 1215/AS NEEDED .05:15 6.2 21 5.4 24 ESC M 3 1230/AS REQUESTED 05:30 6.2-22 5.4-25 EOF M 3 APPROX 1230/AS NEEDED 05:30 6.2 24 5.4-25 OSC M 8 APPROX 1300/AS NEEDED 06:00 6.2 25 5.4 25 l
OSC M 9 APPROX 1300/AS NEEDED 06:00 6.2 26 5.4 25
- UPON ACTIVATION OF RESPECTIVE FACILITY OR ARRIVAL (8
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Rev. O Page 6.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO. SCR-M-1 TO: Shift Supervisor CLOCK TIME: Prior to 0700 LOCATION: Simulator Control Room SCENARIO TIME: 00:00-PARTICIPANT MESSAGE. THIS IS A DRILL For initial conditions, see attached pages.
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THIS IS A DRILL
.2502e h
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Rev. 0 3 VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 INITIAL CONDITIONS (This information will be provided to the players at the start of the , l-i exercise),
- 1. The Reactor is'now at approximately 100% rated power. The reactor has .
been operating steady state for the past sixteen months with no recent shutdowns.
- 2. Night orders for the operations crew are as follows;
- a. Containment de iner;>ing has commenced on the previous shift for a scheduled power reduction and Drywell entry. Reactor Engineering staff
-i has determined that power reduction should not exceed it per 3 minutes. :
O.
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs) . RRUs 2 and 4 are showing abnormal amperage fluctuations.
- c. The Auxiliary Operators are changing the suction filters on the "B" Control Rod Dtive (CRD) Pump.
- 3. All other power generating and safety system. equipment is operable.
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed , uph (lower / upper) -2.8/5.6 Wind Direction , degrees (lower / upper) 10/348 Delta Temperature , 'F (lower / upper) -0.7/-0.6 Ambient Temperature , 'F ~53.4 Precipitation , inches 0.0
. .. ~
l
Rev. O Page 2 of 3 i
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late ; morning - High temperatures 75 to 80. Probability of precipitation less than ; 10%. j A high pressure syste.m centered over Pennsylvania this morning will drif t to the southeast and slowly weaken durin5 the day. This system will dominate the weather today. ! O i O ,
- . - - - ~
kov. O Page 3 of 3 V l P.itial Plant and Reactor Systen Values 1 Reactor Vessel Coolant Level 162 inches 1,006 psig -I Reactor Pressure Reactor Power APRM (average) 1004 Core Plate Differential Pressure 20.0 psid Total Core Flow 46 mil lbs/hr . Main Steam Line Flow - Total 6.2 mi1~lbs/hr Main Steam Line Radiation 194 mR/hr Condenser Hoewell Level 564 - Condenser Vacuum' 2.6 inches Hg(Abs) Condensate Storage Tank Level 52% Reactor Coolant Temperature 527 'F Recirc Drive Flow (average)- 30,000 gpm Feedwater Flow 6.4 mil lbs/hr ,
' Reactor Building Differential Pressure -0.75 inches Hg Drywell Pressure 1.70 psig.
Drywell Temperature 140 'F Torus Water Level 1.16 ft Torus Temperature 72.'F Drywell/ Torus Os Concentration 2.6% ! High Range Containment Monitors .2.7 R/hr containment Gas / Particulate : 600/60',000 cpm Reactor Building Vent Monitors Gas /Part 500/4,000 cpm. f' Reactor Building Vent Exhaust N/S -1.5/1.5 mR/hr
~
Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uCi/sec Stack Gas I/II .150/200 cpm High Range Noble Gas Monitor 0.1 mR/hr O
R2v. O Page 6.2-2 O- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ! 1990 l SCENARIO MESSAGE CARDS l FROM: Control Room Cnntroller MESSAGE NO.: CR-M-1 TO: Control Room Communicator CLOCK TIME: Prior to 0700 LOCATION: Control Room SCENARIO TIME: 00:00 PAR 7icIPANT MESSAGE "tHIS IS A DRILL i For initial conditions, see attached pages. ! i O i THIS IS A DRILL O 2502e
1 I' Rev. 0 Page 1 of 3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 INITIAL CONDITIONS (This information will be provided to the players at the start of . the exercise).
- 1. The Reactor is' now at approximately 100% rated power. The reactor has been operating steady state for the past sixteen months with no recent i
shutdowns,
- 2. Night orders for the operations crew are as follows:
- a. Containment de inerting has commenced on the previous shift for a scheduled power reduction and Drywell entry. . Reactor Engineering staff has determined that power reduction should not exceed 1% per -3 minutes,
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs) . RRUs 2 and 4 are showing abnormal amperage fluctuations.
- c. The Auxiliary Operators are changing the suction filters on the "B" Control Rod Drive (CRD) Pump.
- 3. All other power generating and safety system equipment is operable..
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed , sph (lower / upper) 2.8/5.6 Wind Direction , degrees (lower / upper) 10/348 Delta Temperature , 'F (lower / upper) -0.7/-0.6 Ambient Temperature , 'F 53.4
-Precipitation , inches 0.0 O
l Rev. O Page 2 of 3 O
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than lot. A high pressure system centered over Pennsylvania this morning will drift to the southeast and slowly weaken d: ring the day. This system will dominate the weather today. O l l L I-1 U
l Rev. O Page 3 of 3 I Initial Plat.t and Reactor System Values i Reactor Vessel Co0lant Level 162 inches Reactor Pressure 1,006 psig Reactor Power - APRM (a m age) 100% Core Plate Differential Pressure 20.0 paid l Total Core Flow 46 mil lbs/hr Main Steam Line Flow - Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr Condenser Hotwell Level 56% Condenser Vacuum 2.6 inches Hg(Abs) Condensate Storar, Tank Level 524 1 Reactor Coolant Temperaturo 527 'F Recire Drive Flow (average) 30,000 gpm Feedwater Flow 6.4 mil lbs/hr 0' - Reactor Building Differential Pressure -0.75 inches Hg Drywell Pressure 1.70 psig Drywell Temperature- 140 'F Torus Water Level 1.16 ft Torus Temperature 72 'F j Drywell/ Torus 02 Concentration- 2.6% High Range Containment Monitors 2.7 R/hr Containment Cas/ Particulate 600/60,000 cpm Reactor Building Vent Monitors Gas /Part. 500/4,000 cpm i Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr ! Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uCi/see Ste k Gas I/II 150/200 cpm High Range Noble Gas Monitor 0.1 mR/hr O 1
Rev. O Page 6.2-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: TSC Controller MESSAGE NO.: TSC-M-1 TO: TSC Coordinator CLOCK TIME: Upon TSC Activation LOCATION: TSC SCENARIO TIME: , i PARTICIPANT MESSAGE THIS IS A DRILL j For initial conditions, see attached pages, i i 1 THIS IS A DRILL O 2502e
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Rev. O VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1990 INITIAL CONDITIONS (This information will be provided to the players at the start of the_ . exercise).
- 1. The Reactor is"now at approximately 1004 rated power. The reactor has been operating steady state for the past sixteen months with no recent shutdowns.
- 2. Night orders for the-operations crew are as follows:
- a. - Containment de-inerting has commenced on the previous shift for a .
scheduled power reduction and Drywell entry. Reactor Engineering staff l has determined that power reduction should not exceed it per 3 minutes. l
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor
(' Recirculation Units (RRUs) . ,RRUs 2 and 4_ are showing abnormal amperage- 3 l fluctuations,
- c. The Auxiliary Operators are changing the suction filters on the "B" Control Rod Drive (CRD) Pump.
L l'
- 3. All other power generating _and safety system equipment is operable.
t l
- 4. The following on-site meteorological conditions exist at 0700:
l_ Wind Speed , mph (lower / upper)- 2.8/5.6 Wind Direction , degrees (lower / upper) 10/348. : Delta Temperature , 'F (lower / upper) 0.7/-0.6 Ambient Temperature , 'F 53.4 l' Precipitation , inches 0.0 J
l Rev. O Page 2 of 3
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable. winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than 104. A high pressure s stem centered over Pennsylvania this morning will drift to the southeast and slowly weaken during the day. This system will dominate the weather today. O O
Rev. 0 , Page 3 of 3 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 162 inches Reactor Pressure 1,006 psig j Reactor Power - APRM (average) 100% Core Plate Differential Pressure 20.0 psid Total Core Flow 46 mil lbs/hr Main Steam Line Flow - Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr Condenser Hotwell Level 56% Condenser Vacuum 2.6 inches Hg(Abs) Condensate Sturage Tank Level. 52% Reactor Coolant. Temperature 527 'F Recire Drive Flow (average) 30,000 gpm Feedwater Flow 6.4 mil lbs/hr
. . . Reactor Building-Differential Pressure -0.75 inches Hg Drywell Pressure 1.70 psig Drywell Temperature 140 'F Torus Water Level 1.16'ft Torus Temperature 7 2 'F Drywell/ Torus 0 Concentration 2 '. 6 %
High Range Containment Monitors 2.7 R/hr Containment Gas / Particulate 600/60,000 cpm Reactor Building Vent Monitors Cas/Part 500/4,000 cpm Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector. 270'mR/hr SJAE Discharge Rate 50,000 uCi/sec Stack Gas I/II 150/200 cpm High Range Noble Cas Monitor 0.1 mR/hr O
N Rev. 0 Page 6.2-4 O-VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 f.CENARIO MESSAGE CARDS FROM: TSC Controller MESSAGE NO.: TSC-M-2A TO ' TSC Coordinator CLOCK TIME: Upon Assignment of Data Recorder LOCATION: TSC SCENARIO TIME: PARTICIPANT MESSAGE THIS IS A DRILL 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 THIS IS A DRILL 2502e
n-- Rev. O Page 6.2-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSACE CARDS FROM: . TSC Controller MESSAGE NO.: TSC-M-2B TO: TSC Coordinator CLOCK TIME: Upon Assignment of Comunicators LOCATION: TSC SCENARIO 7IME: PARTICIPANT MESSAGE THIS IS A DRILL Af ter assigning your TSC Comunicators to the Control Room, the prestaged TSC Communicators at the Simulator Control Room will be made available. O THIS IS A DRILL 2502e I
l i Rev. 0 l Page 6.2-6 ) l (\
\w- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1990 SCENARIO MESSAGE CARDS ,
FROM: OSC Controller MESSAGE NO.: OSC-M-1 TO: OSC Coordinator CLOCK TIME: Upon OSC Activation LOCATION: OSC SCENARIO TIME: PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages. t L l' eg THIS IS A DRILL i V 2502e
l Rev. O Page 1 of 3 VERMONT YANKEE NUC1. EAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The Reactor is' now at approximately 1004 rated power. The reactor has been operating steady state for the past sixteen months with no recent shutdowns.
- 2. Night orders for the operations crew are as follows:
- a. Containment de-inerting has commenced on the previous shift for a scheduled power reduction and Drywell entry. Reactor Engineering staff A has determined that power reduction should not exceed 1% per 3 minutes. .
i \.j
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor l Recirculation Units (RRUs) . RRUs 2 and 4 are showing abnormal amperage fluctuations,
- c. The Auxiliary Operators are changing the suction filters on the "B" Control Rod Drive (CRD) Pump.
- 3. All other power generating and safety system equipment is operable.
L
- 4. The following on-site meteorological conditions exist at 0700:
Wind Speed , aph (lower / upper) 2.8/5.6 Wind Direction , degrees (lower / upper) 10/348 f l Delta Temperature , 'F (lower / upper) -0.7/ 0.6 Ambient Temperature , 'F 53.4 0.0 Q Precipitation , inches
-tj
I Rev. 0 , Page 2 of 3
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than 106. A high pressure s'ystem centered over Pennsylvania this morning will drift to the southeast and slowly weaken during the day. This system will dominate the weather today. O O
Rev. O Page 3 of 3 Initial Plant and Reactor System Valuel Reactor Vessel Coolant Level 162 inches Reactor Pressure 1,006 psig-Reactor Power - APRM (average) 100% Core Plate Differential Pressure 20.0 psid 46 mil lbs/hr Total Core Flow Main Steam Line Flow - Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr Condenser Hotwell Level 56% condenser vacuum 2.6 inches Hg(Abs) Condensate Storage Tank Level 52% Reactor Coolant Tempers.ture 527 'F Recire Drive Flow (average) 30,000 gpm Feedwater Flow 6.4 mil lbs/hr O. Reactor Building Differential Pressure -0.75 inches Hg Drywell Pressure 1,70 psig-Drywell Temperature ~ 140 'F Torus Water Level 1.16 ft Torus Temperature 7 2 'F Drywell/ Torus 0 Concentration- 2.6% High Range Containment Monitors 2.7 R/hr Containment Gas / Particulate 600/60,000 cpm Reactor Building Vent Monitors Gas /Part 500/4,000 cpm Reactor Building Vent Exhaust N/S 1.5/1.'5 mR/hr. Steam Jet Air Ejector 270 mR/hr~ SJAE Discharge Rate 50,000 uci/see Stack Gas I/II 150/200 cpm High Range Noble Gas Monitor 0.1 mR/hr O
Rev. O Page 6.2-7 O- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS , FROM SRM Controller MESSAGE NO. SRM-M-1 : TO: Site Recovery Manager CLOCK TIME: Upon Activation LOCATION: RC SCENARIO TIME: PARTICIPANT MESSAGE
'THIS IS A DRILL For initial conditions, see attached pages.
O THIS IS A DRILL 2502e l
Rev. O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The Reactor is now at approximately 1004 rated power. The reactor has been operating steady state for the past sixteen months with no recent shutdowns.
- 2. Night orders for the operations crew are as follows:
- a. Containment de-inerting has commenced on the previous shif t . for a .
scheduled power reduction and Drywell entry. Reactor Engineering staff has determined that power reduction should not exceed 14 per 3 minutes,
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs) . RRUs 2_and 4 are showing abnormal amperage fluctuations,
- c. The Auxiliary Operators are changing the suction filters on the "B" Control Rod Drive (CRD) Pump.
- 3. All other power generating and safety system equipment is operable.
- 4. The f4 1owing on site meteorological conditions exist at 0700:
Wind Speed , mph (lower / upper) 2.8/5.6 Wind Direction , degrees (lower / upper) 10/348 Delta Temperature , 'F (lower / upper) -0.7/ 0.6-Ambient Temperature , 'F 53.4. Precipitation , inches 0.0
Rev. O Page 2 of 3 ,
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than 10%. A high pressure sjstem centered over Pennsylvania this morning will drift to the southeaat and slowly veaken during the day. This system will dominate the weather today. O O
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Rev. O Page 3 of 3 Initial Plant and Reactor System Values l Reactor Vessel Coolant Level 162 inches Reactor Pressure 1,006 psig Reactor Power APRM (average) 100% Core Plate Differential Pressure 20.0 psid Total Core Flow -46 mil lbs/hr Main Steam Line Flow - Total 6.2 mil lbs/hr 3 Main Steam Line Radiation 194 mR/hr Condenser Hotwell Level 564 I Condenser Vacuum- 2.6 inchet Hg(Abs) Condensate Storage Tank Level 52% Reactor Coolant Temperature 527 'F Recire Drive Flow (average) 30,000 gpm 1 Feedwater Flow 6.4 mil lbs/hr Reactor Building Differential Pressure 0.75 inches Hg Drywell Pressure 1.70 psig DQwell Temperature 140 'F Torus Water Level- 1.16 ft -l Torus Temperature 72 'F Drywell/ Torus 0, Concentration 2.6% High Range Containment Monitors 2.7 R/hr i Containment Cas/ Particulate 600/60,000 cpm Reactor. Building Vent Monitors Cas/Part '500/4,000 cpm i Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 270 mR/hr~ SJAE Discharge Rate- 50,000.uci/sec Stack'Cas I/II 150/200 cpm High Range Noble Gas Monitor 0.1 mR/hr-O
t i Rsv. 0 Page 6.2-8 (D U VERMONT YANKEE NUCLEAR PO WR STATION EMERGENCY RESPONSE PREPAREDNESh' EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: EOF Controller MESSAGE ?40.: EOF-M-1 TO: EOF Coordinator CLOCK TIME: Upon Activation LOCATION: EOF SCENARIO TIME: PARTICIPANT MESSAGE THIS IS A DRILL ~ tor initial conditions, see attached pages. b\ V I' l 1 l l l l THIS IS A DRILL
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Rev. O Page 1 of 3 q
-VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 INITIAL CONDITIONS
_(This information will be provided to the players at the start of the exercise). .
- 1. The Reactor is' now at approximately 100% rated power. The reactor has l been operating steady state for the past sixteen months with no recent i shutdowns.
- 2. Hight orders for the operations crew are as follows:
- a. Containment de inerting has commenced on the previous shift for a scheduled power reduction and Drywell entry. Reactor Engineerin6 staff has determined that power reduction should not exceed 1% per 3 minutes.
O
- b. The Drywell entry is needed to acc. implish repairs to the Drywell Reactor Recirculation Units (RRUs) . RRUs 2 and 4 are showing abnormal amperage fluctuations,
- c. The Auxiliary Operators are changing the suction filters on the "B" Control Rod Drive (CRD) Pump.
- 3. All other power generating and safety system equipment is operable.
- 4. The following on-site meteorological conditions exist at 0700:
Wind Speed , aph (lower / upper) 2.8/5.6 Wind Direction.,. degrees (lower / upper) 10/348. Delta Temperature ,'F (lower / upper) -0.7/-0.6 Ambient Temperature , 'F 53.4 Precipitation , inches 0.0
I Rev. O Page 2 of ?, O' {
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than lot. A high pressure system centered over Pennsylvania this morning will drift to the southeast and slowly weaken during the day. This system will dominate the weather today. O O
I Rev. O Page 3 of 3 l Initial Plant and Reactor System Values Reactor Vessel Coolant Level 162 inches Reactor Pressure 1.006 psig Reactor Power - APRM (average) 100% Core Plate Differential Pressure 20.0 psid i Total Core Flow 46 mil lbs/hr j Main Steam Line Flow - Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr condenser Hotwell Level 56% Condenser Vacuum 2.6 inches Hg(Abs) ! Condensate Storage Tank Level 52% Reactor Coolant Temperature 527 'F Recire Drive Flow (average) 30,000 gpm , Feedwater Flow 6.4 mil lbs/hr Reactor Building Differential Pressure -0.75 inches Hg Drywell Pressure 1.70 psig Drywell Temperature 140 'F Torus Water Level 1.16 ft j Torus Temperaturo 7: 'F l Drywell/ Torus 0, Concentration 2.6% ; High Range Containment Monitors 2.7 R/hr Containment Cas/ Particulate 600/60,000 cpm Reactor Building Vent Monitors cas/Part 500/4,000 cpm Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uCi/see Stack Cas I/II 150/200 cpm High Range Noble cas Monitor 0.1 mR/hr j O l:
Rsv. O Page 6.2-9 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 s SCENARIO MESSACE CARDS i FROM: ESC Controller MESS /**, NO. ESC-M-1 TO: ESC Director CLOCK TIME: Upon Activation LOCATION: Engineering Support Center SCENARIO TIME: _ , i PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages.
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4 THIS IS A DRILL 2502e i
Rev. O j Page 1 of 3 i O-VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE , 1990 1Hr'IAL CONDITIONS (This information will be provided to the players at the start of the , 1 exercise). .; i
- 1. The Reactor is' now at approximately 1004 rated power. The reactor has been operating steady state for the past sixteen months with no .recent shutdowns. ;
- 2. Night orders for the operations crew are as follows:
- a. Containment de inerting has commenced on the previous shift for a 4 scheduled power reduction and Drywell entry. Reactor Engineering staff has determined that power reduction should not exceed 1% per 3 minutes.
I
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor i
Recirculation Units (RRUs) . RRUs 2 and 4 are showing abnormal amperage fluctuations. f
- c. The Auxiliary Operatore are changing the suction filters on the "B" Control Rod Drive (CRD) Pump.
- 3. All other power gensrating and safety system equipment.is operable. .
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed , sph (lower / upper) 2.8/5.6 Wind Direction , degrees (lower / upper) 10/348 ; Delta Temperature , 'F (lower / upper) . 0.7/-0.6 Ambient Temperature , 'F 53.4 Precipitation , inches 0.0 O 1
t Rev. O Page 2 of 3
- 5. Regional Meteorological Torecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than 104. A high pressure system centered over Pennsylvania this morning will drif t to the southeast and slowly weaken during the day. This system will dominate the weather today. I l I l t
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Page 3 of 3 j) 1 N~-l Initial Plant and Reactor System Values i
Reactor Vessel Coolant Level 162 inches Reactor Pressure 1,006 psig Reactor Power - APRM sverage) 1004 Core Plate Differential Pressure 20.0 psid Total core Flow 46 mil lbs/hr Main Steam Line lisv Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr condenser Hotwell Level 56% Condenser Vacuum 2.6 inches Hg(Abs) Condensate Storage Tank Level 52% Reactor Coolant Temperature 527 'F Recire Drive Flow (average) 30,000 gpm Feedwater Flow 6.4 mil lbs/hr
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Reactor Building Differential Pressure 0.75 inches Hg Drywell Pressure 1.70 psig Drywell 1emperature 140 'F Torus Water Level 1.16 ft Torus Temperature 72 'F I Drywell/ Toras 0, concentration 2.6% High Range Containment Monitors 2.7 R/hr
- Containment Cas/Patticulate 600/60,000 epm Reactor Building Vent Monitora Oss/Part 500/4,000 cpm Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejestor 270 mR/hr SJAE Discharge Rats _ 00,000 uCi/see Stack Cas I/II 150/200 cpm l High Range Noble Cas Monitor 0.1 mR/hr O
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i R:v. 0 )' Page 6.2-10 l l
\s / VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO.: SCR-M-2 TO: Shift Supervisor CLOCK TIME: 0730 LOCATION: Simulator CR SCENARIO TIME: 00:30 PARTICIPANT MESSAGE ,
THIS IS A DRILL Guard House called to report that they sensed the ground moving and that abnormal river motion was observed. A plant technician who was working in the South Warehouse called to report that he felt the floor moving and several items rattled on the storage racks. (3 V l THIS IS A DRILL 1
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Rsv. 0 l Page 6.2-11 VERMONT YANKEE NUCLEAR POWER STATION ; EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1990 SCENARIO MESSAGE CARDS FROM: l 1 stor CR Controller
$_Iy1 MESSAGE NO.: SCR-M-3 1
TO: f.hift Supervisor CLOCK TIME: 0735
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LOCATION: fipulator CR SCENARIO TIME: 00:35 ] l PARTICIPANT MESSAGE T_H_IC IS A DRILL Auxiliary Operator reports a positive indication on the seismic acerlerometer.
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l t O r THIS IS A DRILL' 2502e ,
R2v. O Page 6.2-12 O V VERMONT YANKEE NUCLEAR POWER STATION EKERGENCY RESPONSE PREPAREDNESS EXERCISE ; 1990 SCENARIO MESSAGE CARDS FROMt Simulator CR Controller MESSAGE NO. SCR-M-4 10: Shif t Supervisor CLOCK TIME: Approximately 0740 LOCATION: Simulator CR SCENARIO TIME: 00:40 PARTICIPANT MESSAGE i i THIS IS A DRILL Dam personnel from the Vernon and Bellows Falls Dams have been contacted and i report that they have observed abnormal river motion, but the dams are intact and exhibit no signs of damage or failure. (D \_ / ! i i i THIS IS A DRILL v 2502e
Rsv. O Page 6.2-13 r3
-- VERMONT YANKEE NUCLEAR POWER STATION j EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 i
3CENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-M-2 TO: A0 or Plant Personnel CLOCK TIME: Approximately 0750 Investinatina Earthquake Damage or as needed LOCATION: Plant Site' SCENARIO TIME: 00:50 1 PARTICIPANT MESSAGE I THIS IS A DRILL , Upon inspection for damages caused by the earthquake, you have noticed no ; visual damage to plant equipment. i (D
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- THIS IS A DRILL
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Rsv. O Page 6.2-14 , , - ~. t N. VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE , 1990 l I SCENARIO MESSAGE CARDS FROMt OSC Observer MESSAGE NO. OSC-M-3 701 On-Site Assistance Team CLOCK TIME: Approximately 0830 or as needed LOCATION: Reactor BuIllding SCENARIO TIME: 01:30 PARTICIPANT MESSAGE THIS IS A DRILL ! Team investigating problem with the "A" CRD pumps o Visual inspection of the "A" CRD pump breaker reveals the relay is burnt. o Estimated time to repair the breaker is approximately one hour.
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THIS IS A DRILL '( ) 2502e
i Rsv. O Page 6.2-15 1 s
'\j VERMONT YANKEE NL' CLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1090 SCENARIO MESSAGE CARDS j FROM OSC Observer MESSAGE NO. OfC-M-4 l TO: A0 or On-Site Assistance Team CLOCK TIME: Approximately 0830 or as needed LOCATION: Reactor Bu'ildina . El . 232 '-6" SCENARIO TIME: 01:30 PARTICIPANT MESSAGE THIS IS A DRiit Estimated time to complete the suction filter change on the "B" CRD pump is approximately one hour.
O L 1 i THIS IS A DRILL ( 2502e
Rev. O Page 6.2-16 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM:' News Media Center Observer MESSAGE NO.: NMC-M-1 TO: News Media Center Staff CLOCK TIME: 0845 LOCATION: News Medir Center SCENARIO TIME: 01:45 PARTICIPANT MESSAGE THIS IS A DRILL (The following information was heard on the local radio stations and local television network.) This morning an earthquake was felt in southern Vermont at around 7:30 a.m. The New England Seismic Network estimated the magnitude at 4.8 on the Richter scale. The epicenter was located near the town of Northfield, Massachusetts (latituda 43 degrees, 43 minutes and longitude 72 degrees, 28 minutes) , approximately 11 to 12 miles southeast of Brattleboro, Vermont. No casualties i or road and bridge damage have been reported, according to local Brattleboro officials. However, several chimneys have fallen and telephone service was i temporarily interrupted in the Greenfield, Massachusetts area. Scientists from the New England Seismic Network have also stated that after shocks may be i felt throughout the day, While it may be surprising to most people, an average of five earthquakes are felt somewhere in New England each year. The probabilities of a damaging earthquake occuring somewhere in New England are small by worldwide standards. The chances that a potentially damaging earthquake, of equal or greater value than the one that occurred today will repeat somewhere in New England, are 1 in 300 per year. THIS IS A DRILL () 2502e l
l Rsv. O Page 6.2-17 l (~ b VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO. OSC-M-5 . T0: On-Site Assistance Team CLOCK TIME: Approximately 0935 or as needed LOCATION: Reactor Building SCENARIO TIME: 02:35 PARTICIPANT MESSAGE THIS IS A DRILL Repairs to the CRD pump are completed. The CRD pump is operable and can be returned to service.
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- THIS IS A DRILL 2502e l
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Rav. O Page 6.2-18 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSACE CARDS FROM: ESC Controller MESSAGE NO.: ESC-M-2 __ TO: ESC Meteorologist CLOCK TIME: 1040 or as requested , LOCATION: ESC Yankee Atomic Electric Co. SCENARIO TIME: 03:40 PARTICIPANT MESSAGE THIS IS A DRILL Utilite the attached meteorological information to generate the weather forecast for the site. O THIS IS A DRILL 2502e-
Rsv. O Page 6.2-19 f WEATHER FORECAST ff0R SITE: VERMONT YANKEE __ Date of Forecast , Time of Forecast: 1000 , Current Site Meteorology (as of 0945 ): Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower 4.9 mph 10 deg from -1.5 0F 0 0.00 in/15 min Upper 5._4_ mph 345 deg from -1.5 0F D Forecast Site Meteorology: Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation : A. 1000- Lower 4 mph 350 deg from -- 0F C 0.00in/15 min 1100 Upper 8 mph 345 deg from -- 0F D B. 1100- Lower 6 mph _330 deg from _ _ - - 0F B 0.00in/15 min 1200 Upper 10 mph 335 deg from -- 0F C j C. 1200- Lower 5 mph 320 deg from -- 0F B 0.00in/15 min /] Q l',00 Upper 10 mph 315 deg from -- 0F C Nat'.onal Weather Service Forecast for site region: I Mo stly sunny today, with variable winds becoming northwest 5 to 10 mph by late merning. High temperatures will be 75'F to 80'F. Probability of precipitation less tt.an 10%. A high pressure system centered over Pennslyvania this morning will drift to the southeast and slowly weaken during the day. This system will dominate the weather today. Special Weather Statements: Winds predominantly from the north to north nori.nwest. Neutral to slightly unstable conditions should persist throughout the day. i 2502e i
i Rev. O ! Page 6.2-20 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM OSC Observer MESSAGE NO.t OSC-M-6 TO: On-Site Assistance Team CLOCK TIME: Approximately 1215 , or as needed LOCATION: Reactor Building. E1. 252' - SCENARIO TIME: 05:15 l' South Side PARTICIPANT MESSAGE THIS IS A DRILL Upon arrival at the south side to the Reactor Building, El. 252', you observe the followingt [ o You can hear a hissing sound coming f rom the south wall of the Reactor Building.
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o Upon looking up near the south wall, you see the bottom flange of Valve V16-19-9 dislodged. p-l THIS IS A DRILL 2502e
I R2v. O Page 6.2-21 (
\ - VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO. OSC-M-7 ,
CLOCK TIMEt Approxirately 1215 TO: On-Site Assistance Team , or as .teeded __, LOCATION: Torus Catwalk - Torus Purge SCENARIO TIME: 05:15 , Supply Valve (V16-19-10) PARTICIPANT MESSAGE THIS IS A DRILL Visual inspection of the valve reveals that the valve Indication is open. I i l I l t l l l r i l
/'~~T THIS TS A DRILL
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Rsv. O Page 6.2-22 (' VERMONT YANKEE NUCLIAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS , FROM: ESC Controller MESSAGE NO.: ESC-M-3 l ESC Meteorolonist CLOCK TIME: 1230 or as requested TO: LOCATION: ESC Yankee Atomic Electric Co. SCENARIO TIME: 05:30 PARTICIPANT MESSAGE THIS IS A DRILL , Utilize the attached meteorological information to generate the weather forecast for the site. I i l
,- THIS IS A DRILL l'.&g l
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Rev. O Page 6.2-23
')' WEATHER FORECAST FOR SITE: VERMONT YANKEE Date of Forecast *.
Time of Forecast: 1200 Current Site Meteorology (as of 1130 ): Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower 2.9 mph 309 deg from -2.1 0F A 0.00 in/15 min Upper .6.2 mph 310 __deg from -2.3 0F C Forecast Site Meteorology: Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation A. 1200 Lower 6 mph 310 deg from -- 0F B _ 0.00in/15 min 1300 Upper 12 mph 320 deg from -- 0F C B. 1300 Lower 6 mph 310 deg from -- 0F A 0.00in/15 min 1400 Upper 10 mph _320 deg from -- 0F B I 0.00in/15 min h L C. 1400 1500 Lover Uppsr 5 mph 10 mph 308 deg from 325 deg from 0F 0F B C National Weather Service Forecast for site region: Mostly sunny and warm this afternoon with a high near 80'F. Northwest winds 5 mph to 10 mph. Mostly clear tonight with a low around 55'F. *dinds becoming light and variable. Tomorrow, becoming cloudy with showers. Highs in the mid 70 2. Winds becoming south to southwest 10 mph to 15 mph. Special Weather Statements: (
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Rev. O Page 6.2-24 Tx I )
' VERMONT YANKEE NUCLEAR POWER STATION EMERGEN Y RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROMt EOF /RA Controller MESSAGE NO.: EOF-M-3 TO: Radiological Assistant CLOCK TIME: As Requested l (Approximately 1230)
LOCATION: EOF / Dose Assessment Area SCENARIO TIME: 05:30 PARTICIPANT MESSAGE l I THIS IS A DRILL 12:00-18:00 - General Area Forecast l l Mostly sunny and warm this afterno n with a high near 80'F. Northwest winds 1 5 mph to 10 mph. Mostly clear tonight with a low arennd 55'F. Winds becoming l light and variable, j Tomorrow, becoming cloudy with showers. Highs in the mid 70's. Winds ) (/')
\~ becoming south to southwest 10 mph to 15 mph.
THIS IS A DRILL
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i Rev. O Page 6.2-25 i (s - VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-M-8 TO: On-Site Assistance Team CLOCK TIME: Approximately 1300-or as needed , LOCATION: Torus Catwalk - Torus Purge SCENARIO TIh's 06:00 ' Supply Valve (V16-19-10) PARTICIPANT MESSAGE I THIS IS A DRILL Upon completing repair efforts on the torus purge supply valve (V16-19-10), you observe the following: l o You hear the air vent off from the valve and the valve will shut. 0 o Valve indication is showing closed position. t ,/ F i j i THIS IS A DRILL je s i N.~s! 2502e
i Rsv. 0 l Page 6.2-26 l (~~ s. VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-M-9 , TO: On-Site Assistance Team CLOCK TIME: Appr.oximately 1300 or as needed LOCATION: Reactor Bu'ilding .E1. 252' - SCENARIO TIME: 06:00 South Side , PARTICIPANT MESSAGE THIS IS A DRILL NOTE: (Message card should be given to team only if the team pr weeded to the south side of the Reactor Building. El. 252', oefore fixing the valve , and team is located near the south side of the Reactor Building.) l) ----------------------------~~--------------------------------------------~~-~~~
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You hear no more hissing sound from the south wall of the Reactor Building, El. 252'. t I { l 1 l
- .s TilIS IS A DRILL l ' ' . ,
2502e ' 1
a VERMONT YANKEE NUCLEAR POWER STATION ENERCENCY RESPONSE PREPAREDNESS EKERCISE 1990: 7.0 STATION EVENT DATA O I M ir O t
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. ENERGENCY RESPONSE PREPAREDNESS. EXERCISE' :,
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I 1 l l Rev. O ; Page 7.1 1 iO VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 7.1 EVENTS
SUMMARY
The following information and supplementary material are provided for the i controllers / Observers having in plant control assigreents to ensure the proper , development of the scenario. The information provided in this section assumes , that the " players," who are dispatched to perform repair, rescue, or other activities, will take certain actions in response to the scenario event. The Controller / Observer must be cognizant of the actions of the players 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 controller / Observer will be required to provide additional information to the players, i O i Approximate Miniscenario Time Event Location 7.2.1 0830 Plant Damage Assessment Reactor Bldg. o CRD Pumps and Switchgear i l Room 7.2.2 1200 Plant Damage Assessment Reactor Bldg.- o Toto's Purge Supply and Totus Catvalk Valve (V16 19 10) 4 Inspection and Repair L ; I m 1 1
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I Rev. O Page 7.2.1 1 ; I VERMONT YANKEE NUCLEAR POWER STATION : EMERCENCY RESPONSE PREPAREDNESS EXERCISE ; 1990 7.2.1 Miniscenario Control Rod Drive (CRD) Pumns I. General Descriotion f f The plant is in an Alert classification due to an ATWS condition. At 0830 while operators are driving in control rods, the "A" CRD Pump trips due i to a breaker problem. It is expected that plant personnel will be , dispatched to investigate the problem with the "A" CRD Pump or expedite I the completion of the suction filter replacement on "B" CRD Pump. II. Descriotion of Player Resoonses/ Observations / Corrective Actions The Shif t Supervisor should immediately inform the TSC Coordinator that t
' the both the "A" and "B" CRD Pumps are not available to drive in control rods. The TSC Coordinator should direct plant personnel to investigate the ;
problem with the "A" CRD Pump and to determine the status and completion of the suction filter replacement on the "B" CRD Pump. The plant personnel investigating the problem with the "A" CRD Pump will determine that the relay in the "A" CRD Pump breaker cubicle has been j burned out. e replacement of the relay will take approximately one hour l to complete the repairs (refer to Message Card OSC M 3). It will also be determined that the status of completing the suction filter change on the "B" CRD Pump is approximately one hour (refer to Message Card OSC M 4). i.. The TSC Coordinator may dispatch plant personnel to assist with the suction filter change or discuss alternative methods to allow for the "B" CRD Pump to be returned to service as soon as possible.
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l III, Event Closcout
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Due to the interactive nature of this event, the actions taken by plant j personnel will determine when the CRD Pumps are declared operable and , returned to service. The event will be completed upon returning one of ! the CRD Pumps back into operation (refer to Message Card OSC.M 5). ; s 4 l 9 i l t
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Rev. O O Page 7.2.2 1 i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 i 7.2.2 Miniscenario - Torus Purge Suvo1v Valve (V16 19 10)
- 1. General Descriotion t
At approximately 1135, the simulator control board will indicate that the Torus Purge supply Valve (V16 19 10) did not close on Group 3 isolation. Reactor operator attempts to isolate the Torus Purge Supply Valve are unsuccessful. It is also apparent that there is a leak in the Reactor . Building as indicated by significantly elevated Reactor Building ARMS and ; the Plant Vent Stack monitor readings increasing. It f s anticipated that on site assistance team (s) will be dispatched to investigate the leak in the Reactor Building and the problem associated with the Torus Purge Supply O Valve (V16 19 10). (V II. Descrintion of Player Responses / Observations / Corrective Actions ; i The Shift Supervisor should inform the TSC Coordinator and the Site Recovery Manager (SRM) that the Torus Purge Supply Valve (V16 19 10) did not close on Group 3 isolation and attempts to isolate the valve were unsuccessful. The TSC Coordinator, with consultation from the Shift , Supervisor and SRM, should dispatch on site assistance teams to investigate the leak into the Reactor Building and the problem associated with the Torus Purge Supply Valve (V16 19 10). Discussions on emergency exposure ; concerns, radiological exposure control, dose commitments, in plant radiological conditions and task assignments should occur prior to dispatching the team (s). It is expected that the on site assistance team will be directed to go to [ the Torus Purge Supply Valve (V16-19 10) located on the Torus Catwalk. , There are two possible ways of accessing the Torus Catwalk by entering the v f
)
4 Rev. O ! Page 7.2.2 ? Reactor Building EL 252 (ground floor) and proceeding to the tiorthwest access hatch or southeast access hatch. Upon entrance to the Reactor : Building, the team will encounter elevated radiation levels (refer to the appropriate Tables and Figures in Section 9.3). If the team initially utilizes the southeast access hatch to the Torus Catwalk or proceeds to the south side of the Reactor Building EL 252, the ' team will be told that they can hear a hissing sound coming from the south wall. The team will also be told upon looking up near the south wall, they can see the bottom flange of Valve V16 19 9 dislodged (refer to Message Card OSC M 6) . However, if the team initially utilizes the northwest access hatch to the Torus Catwalk and does not proceed to the south side of Reacter Building EL 252, the team will only encounter the elevated . radiation levels. ! [ Upon proceeding to the Torus Catwalk and locating the Torus Purge Supply Valve (V16 19 10), the team will find that the valve indication is open (refer to Message Card OSC M 7). Corrective actions to close the valve will be expected to occur by the team. When repair efforts are successfully i completed, the team will be told that they can hear the air vent off from the valve and the valve will shut. The tsem will also be told that the . valve indication is in the close position (refer to OSC M 8). If the team , exits the south side of the Reactor Building and initially entered the [ e uth side before closing the valve, the team will also be told that they ! cannot hear the hissing sound from the south wall (refer to Message Card OSC.M 9). ; III. Event Closeogt; The on site assistance team will have successfully shut the Torus Purge Supply Valve (V16 19-10). Simulator control board will also show that the Torus Purge Supply Valve (V16 19-10) has closed. The leakage into the Reactor Building has been isolated.
]V
1 O VERMONT YAN".EE NUCLE.AR POWER STATION EMERGENCY RESPONSE PP.EPAREDNESS EXERCISE 1990 8.0 OPERATIONAL DATA HOIEl The operational data is highly dependent on operator actions taken-in response to the conditions presented within the scenario. The l operational data reflects plant. conditions assuming certain basic ' O operator response actions being taken. The operational data was taken from the plant simulator. 1 i O
l VERMONT YANKEE NUCLEAR POWER STATION .REV. 2 EMERGENCY RESPONSE PREPAREDNESS EXERCISE PAGE 8.0 1 1990 8.0 OPERAfl0NAL DATA SCENARIO TIME 00:00 00:15 00:30 00:45 01:00 01:15 01:30 01:45 CLOCK TIME 07:00 07:15 07:30 07:45 08:00 08:15 06:30 08:45
' ITEM PANEL INST ID DESCRIPfl0N UNITS 1~93 FT 23 108 1 HPCI FLOW GPM 0 0 0 0 0 0 0 0 2 93 F1 10 139A RHR A FLOW GPM 0 0 0 0 0 0 0 0 3 93 FI 10 1399 iM B FLOW GPM 0 0 0 0 0 0 0 0 4 93 F1 14 50A CS A FLOW GPM 0 0 0 0- 0 0 0 0 5 93 FI 14 508 CS B FLOW GPM 0 0 0 0 0 0 0 0 6 93 PI 16 19 12A DRYWELL PRESSURE PSIA 17 17 17 17 16 16 16 16 7 93 FI 16 19 128- DRYWELL PRESSURE PSIA 17 1/- 17 17 16 16 _ 16 16 8 94 Fl*13 91 RCIC FLOW GPM 0 0 0 -0 0 0~ 0 0 ;
-9 94 FI 12 141A RWCU FLOW GPM 60 60 60 60 0 0 0 0 10 94 FI 12 1418 RWCU FLOW GPM 60 60 60 60 0 -0 0 0 11 94 2 165A RX COOLANT TEMP DEG F 527 527 527 527 532 517 524- 521 12 94 2 1658 RX COOLANT TEMP DEG F 527 527 527 527 532 517 524 521 13 94 2 159A REclRC A LOOP FLOW KGPM 30 30 30 30 30 0 0- 0 14 ' 94 2 1598 RECIRC B LOOP FLOW KGPM 30.1 $0.1 30.1 30.1 30.1, 0 0 0 i 15 95 7 46A APRM/lRM A % 100 100 100 100 65 13 13 13 it 9' 7 468 APRM/lRM B % 99 99 99 99 65 13 13 13 17 95 7 46C APRM/lRM C % 100 100 -100 100 65 13 13 13 18 95- 7 460 APRM/lRM D % 100 100 100 100 65 13 13 13 19 95 7 46E APRN/lRM E % 101 101 101 101 66 13 13 13 20 95 7 46F APRM/lRM F % 101 101 101 101 '66 13 13 13 21 95 7 43A SRM A CPS 352000 352C20 352000 352000- 132000 9730 9410 9410.
22 95 7 438 SRM B CPS 429000 429000 429000 428000 146000 10700 10300 10300 i 23 95 7 43C SRM C CPS 506000 506000 506000 505000 174000 11500 11500 11500-24 95 7 430 SRM D CPS 397000 397000 397000 396000 141000 9800 9800. 9800 25 95 2 3 95 CORE FLOW MLB/HR 47 47 47 47 54 8 2 2 26 95 2 3 95 CORE DP PSID 21 21 21 21 23 4 3 3 27 95 F1 3 310 C,tD FLOW GPM 45.9 45.9 45.9 45.9 120.6 45.9 0 0 28 95 - 6 96 WIDE RANGE PRESSURE PSIG 1006 1006 1006 1006 969 925 923 923 29 95 6 96 NARROW RANGE PRESS PSIG 1006 1006 1006 1006 969 DSL DSL DSL , 30 95 6 97 FEEDWATER FLOW MLB/HR 6.2 6.2 6.2 6.2 5.3 0.3 0.1 0.1 ! 31 :95 6 97 MAIN STEAM FLOW MLB/HR 6.2 6.2 6.2 6.2 4 0.3 0.1 0.1 32 95 6 98 NARROW RANCE LEVEL INCHES 162 162 162 162 152 164 168 162 33 9-5 6 98 WIDE RANGE LEVEL INCHES OSH OSH OSH OSH 155 164 168. 162 34 96 LI 107 5 CST LEVEL % 52 52 52 52 52 50 50 50
'35 96 LI 102 5A HOTWELL LEVEL N % 56 56 56 56- 55 62 66 65 i 36 96- LI 102 5B HOTWELL LEVEL S % 54 54 54 54 -52 53 54 54 37 97 Pl.101 29 CONDENSER VACUUM IN HG 2.6 2.6 2.6 2.6 - 3.1 1.6 1.3 1.2 38 98 D/G A BKR (T= CLOSED;F=0 PEN) F F F F F F F F 39 98 D/G B BKR (T= CLOSED;F80 PEN) F F F F F F F F 40 9 23 16 19 33A/C TORUS TEMPERATURE DEG F 72 72 72 72 72 72 72 72 41 9 25 L1 46A TORUS LEVEL FEET 1.16 1.16 1.16 1.16 1.15 1.15 1.15 1.15 42- 9-25 LI 468 TORUS LEVEL FEET 1.16 1.16 1.16 1.16 1.15 1.15 1.15 1.15 43 9 25 TR 16-19-44 TORUS PRESSURE PSIA 14.7 14.7 14.7 14.7 14.7- 14.7 14.7 14.7 44 9 25 TR-16 19-44 DRYWELL PRESSURE PSIA 17 17 17 17 16 16 16 16
- 45 9 25 PR 1 156 3 DW/ TORUS OP PSID 1.87 1.87 1.87 1.85 1,82 1.79 1.77 1.75 46 9 25 TR 16-19 45 DRYWELL TEMPERATURE DEG F 138 138 138 137 137 136 135 134 l 47 9 26 Pl*1 125-3A RX BUILDING OP IN H2O 0.75 0.75 -0.75 0.75 0.7 0.18 0.68 0.68
. <% 48 9 26 PI 1 125 38 RX EUILDING DP IN H2O 0.75 0.75 0.75 0.75 0.7 0.68 0.68 0.68 49 9-26 F1 1 125 1A SGTS FLOW CFM 78 78 78 11 0 0 0 0 50 9 26 F1 1 125 18 SGTS FLOW CFM 0 0 0 0 0 0 0 0 51 . CAD DW/ TORUS 02 00NC. % 2.58 2.58 2.58 2.58 2.58 2.58 2.58 2.58 52 DW HYDROGEN CONC. % 0 0 0 0 0 0 'O O i
s- 0
w i VERMONT YANKEE NUCLEAR POWER STATION REV. 2 EMERGENCY RESPONSE PREPAREDNESS EXERCISE PAGE 8.0 2 1990 8.0 OPERATIONAL DATA (CONT'D) SCENARIO TIME 02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 . CLOCK TlHE 09:00 09:15 09:30 09:45 10:00 10:15 10:30 10:45 ITEM PANEL INST ID DESCRIPfl0N
}
UN!TS ' 1 93 FT 23 108 1 HPCI FLOW GPM 0 0 2414 3029 3029 4131 4130 4130 2 93 Fl*10 139A RHR A FLOW GPM 0 0 0 0 0 0 0 0 e 3 93 FI 10 1398 RHR B FLOU GPM 0 0 5876 5976 5976 5976 $976 5976 4 v.3 FI 14 50A CS A FLOW GPM 0 0 0 0 0 0 0 0 5 93 F1 14 508 CS B FLOW GPM 0 0 0 0 0 0 0- 0 6 93 PI 16 19 12A DRYWELL PRESSURE PSIA 16 16 16 1F 14 ' 14 14' 15 i 7 93 PI 16 19 128 DRYWELL PRESSURE PSIA 16 16 .16 15 14 14 14 15 i 8 94 FI 13 91 RCIC FLOW GPM 0 0 0 0 0 0 0 0 9 94 F1 12 141A RWCU FLOW GPM 0 0 0 65 62- 65 65 65 ,l 10 94 F1 12 1418 RWCU FLOW GPM 0 '0 0 65 62 65 65 65 : 11 9-4 2 165A RX COOLANT TEMP DEG F 519 517 516 525 529 489 499 499 12 94 2 165B RF COOLANT TEMP DEG F 519 517 516 525 529 489 490 499 I 13 94 2 159A RECIRC A LOOP FLOW KGPM 0 0 0 0 0 0 0 0 14 94 2 1598 RECIRC B LOOP FLOW KGPM 0 0 0 0 0, 0 0 0 15 - 95 7 46A APRM/lRM A % 13 13 13 5 0 0 0 0 i 16 95 7 468 APRM/lRM B % 13 13 13 5 0 0 0 0 17 95 7 46C APRM/lRM C % 13 13 13 5 0 0 0 0 18 95 7 460 APRM/IRM D %. 13 13 13 5 0 0 0 0 19 95 7 46E APRM/lRM E % 13 13 13 5 0 0 0 0- i L 40 95 7 46F APRM/lRM F X 13 13 13 5 0 0 0 0 , 21 95 7 43A SRM A CPS 9410 9410 9410 30 28.1 32.2- 28.8 28.5 ; 22 95 7 438 SRM B CPS 10300 10300 10300 30 27.6 31.8 28.4 28 23 95 7 43C SRM C CPS 11500 11500 11500 30 27.8 31.9 28.5 28.1 ; 24 95 7 430 SRM D CPS 9800 9800 9800 30 27.8 31.9 28.5 28.2 + 25 95 2 3 95 CORE FLOW MLB/HR 1 1 1 1 1 1 1 1 26- 95 2 3 95 CORE DP PSID 3 '3 3 3 3 3 3 3 i k7 95 FI 3 310 CRD FLOW GPM 0 0 0 45.9 4' 9 46 45.9 45.9 28 95 6 96 WIDE RANGE PRESSURE PSIG 922 922 990 935 946 864 752 745 29 95 6-96 NARROW RANGE PRESS PSIG DSL DSL 990 DSL DSL DSL- DSL DSL 30 95 6 97 FEEDWATER FLOW MLB/HR 0.1 0.1 0.1 0 0 0 0 0 31 95 6 97 MAIN STEAM FLOW MLB/HR 0.1 0.1 0 0 0 0 0 0 32 95 6 98 NARROW RANGE LEVEL INCHES 162 164 170 tu 156 158 166 158 33 95 6 98 WIDE RANGE LEVEL INCHES 162 164 170 167 156 158 166 158 34 96 LI 107 5 CST LEVEL % 50 49 49 50 50 49 48 48 35 96 L1 102 5A HOTWELL LEVEL N % 65 65 65 56 55 57 58 58 36 96- L1 102 5B HOTWELL LEVEL $ % 54 54 54 55 55 54 54 54 37 97 PI 101 29 CONDENSER VACUUM IN HG 1.2 1.2 17.1 29.5 30 30 29.9 29.9 38 9-8 D/G A BKR (TsCLOSED;Fs0 PEN) F F F F F 'F F F i 39 D/G B BKR (T= CLOSED;Fs0 PEN) F F F F F F _F F 40 ' 9 23' 16 19 33A/C TORUS TEMPERATURE DEG F 72 72 72 75 77 79 81 82 41 9 25 LI 46A TORUS LEVEL FEET 1.15 1.14 1.14 1.01 1.03 1.06 1.08 1.1 42 9 25 LI 468 TORUS LEYEL FEET 1.15 1.14 1.14 1.01 1.03 1.06 1.08-- 1.1 43 9 25 TR 16 19 44 TORUS PRESSURE PSIA 14.7 14.7 14.7 14.4 14.4 14.4 14.4 14.4 44 9 25 TR 16 19-44 DRYWELL PRESSURE PSIA 16 16 16 15 14 14 14 15 45 - 9 25 'PR 1 156 3 DW/ TORUS DP PS!D 1.73 1.7 1.68 0.07 0.07 0.07 0.07. 0.07 46- 9-25 TR 16 19 45 DRYWELL TEMPERATURE DEG F 133 132 132 131 129 128 127 126 47 9 26 PI 1 125 3A RX Buli. DING DP IN H2O 0.68 0.68 -0.68 0.71 1 1 1 1
. l48 ' 9 2o PI 1 US 38 RX BUILDING DP IN H2O 0.68 0.68 0.68 0.71 1 1 -1 1 49 9 26 FI 1 125 1A SGTS FLOW CFM 0 0 0 1500 1500 1500 1500 1500
- 50. 9 26 F1-1 125 18 SGTS FLOW CFM 0 0 0 0 0 0 0 0 51' CAD DW/ TORUS 02 CONC. % 2.58 2.58 2.58 2.4 9.02 13.04 15.5 16.98 52 DW HTDROGEN CONC. % 0 0 0 0 0 0- 0' O l
u
VERMONT YANKEE NUCLEAR POWER STAfl0N REV. 2 EMERGENCY USPONSE PREPAREDNESS EXERCISE PACE 8.0 3 i 1990 i 8.0 OPERATIONAL DATA (CONT 80) _1 SCENAR10 TIME 04:00 04:15 04:30 04:45 05:00 05:15 05:30 05:45 CLOCK TIME 11:00 11:15 11:30 11:45 12:00 12:15 12:30 12:45 ITEM PANEL INST 10 DESCRIPTION UNITS 1 93 FT 23 108 1 MPCI FLOW GPM 4130 4129 4126 0 0 0 0 0 2 93 F1 10 139A RNR A FLOW GPM 0 7363 7363 6449 5897 5897 5897 5897 3 93 F1 10 139s RNR 5 FLOW GPM 5976 5976 5976 0 0 0 0 0 4 93 F1 14 50A CS A FLOW GPM 0- 0 0 0 0 0 0 0 j' 5 93 F1 14 500 CS B FLOW OPM 0 0 0 0 0 0 0 0 6 93 Pl*16 19 12A DAYWELL PRESSURE PSIA 14 15 15 17 17 17 17 17 - 7 93 PI 16 19 12s DRfWELL PRESSURE PSIA- 14 15 15 17 17 17 17 17 8 94 F1 13 91 RCIC FLOW GPM 0 0 0 0 0 0 0- 0
,1 9 94 F1-12 141A RWCU FLOW GPM 65 65 ' 65 65 65 60 60 60 10 94 F1 12 141B RWCU FLOW GPM 65 65 65 65 65 60 60 . 60 11 94 2 165A RX COOLANT TEMP DEG F 473 472 470 276 278 314 298 298 12 94 2 1658 RX COOLANT TEMP DEG F 473 4 72 470 276 278 314- 298 298 h 13 94 2 159A RECIRC A LOOP FLOW KGPM 0 -0 0 0 0 0 0 0 14 94 2 1599 RECIRC B LOOP FLOW KGPM 0 .0 0 0 0 0 0 0' 0-15 95 7 46A APRM/IRM A 1 0 0 0 0 0 0 0 ,
16 95 7 468 APRM/lRM B % 0 0 0 0 0 0 0 0 i 17 95 7 46C APRM/lRM C 1 0 0 0 0 0 0 0 0 18 95 7 460 APRM/lRM D 1 0 0 0 0 0 0 0 0 19 95 7 46E APRM/lRM E % 0 0 0 D- 0 0 0 O ; 20 95 7 46F APRM/lRM F % 0 0 0 0 0 0 0 0
.. 21 95 7 43A SAM A CPS 31.8 28.6 28 -- 39.1 38-7 34.7 38.7 38.7
- . 22 95 7 438 SRM B CPS 31.3 28.1 '27.5 38.6- 18.1 38.1 38.1 38.1 23 95 7 43C SRM C CPS 31.4 28.2 27.6 38.8 38.4 38.4 38.4 38.4 24 95 7 430 SAM D CPS 31.5 28.3 27.4 38.3 5t.3 38.3 38.3 38.3 25 95 2 3 95 CORE FLOW MLS/NR 1 1 1 1 2 2 1 1 i
26 95 2 3 95 CORE DP PSID 3 3 3 3 3 3 3 3 27 95 FI 3 310 CRD FLOW GPM 45.9 45.9 45 9 $9.8 P. 1 35.1 35.1 35.1 28 95 6 96 WIDE RANGE PRESSURE PSIG 690 582 56k 104 53 53 53 53 29 95 6 96 NARROW RANGE PRESS PSIG .DSL DSL DSL DSL DSL DSL DSL DSL 30 95 6 97 FEEDWATER FLOW MLB/HR 0.1 0' O.1 0 0 0 0 0 31 95 6 97 MAIN STEAM FLOW MLB/rt 0 0 0 0 0 0 0 0 32 95 6 98 NARROW RANGE LEVEL INCdES 158 164- 158 OSH OSH OSH OSH OSH 33 95 6 98 WIDE RANGE LEVEL INCHES. 158 164 158 03t OSH OSH OSH OSH 34 96 LI 107 5 CST LEVEL % 48 47 47 45 ~ 45 40 39 39 35 96 Ll+102 5A HOTWELL LEVEL M % 57 58 58 55 . 54 - 57 58 58 j 36 96 LI 102-58 NOTWELL LEVEL S X 54 54 54 .55 54= 54 54- 54 37 97 PI 101 29 CONDENSER VACUUM IN MG 29.9 29.9 29.? 30 30 30.3 30.3 30.3 38 98 D/G A BKR (TsCLOSED;FsOPEN) F F F F F F F F 39 98 D/G B BKR (Tscl0 SED;FsOPEN) F F F F F F F F !
, 40 9 23 16 19 33A/C TORUS TEMPERATURE DEC F 84 86 87 93 ~ 95 98 98 98 1 < 41 9 25 LI 46A TORUS LEVEL FEET 1.13 1.15 1.19 1.14 1.05 1.82 1.88 1.88
- j
. 42 9 25 LI 468 TORUS LEVEL FEET 1.13 1.15 1.19 1.14 1.05 1.82 1.88 1.88 43 9 25 TR 16 19 44 TORUS PRESSURE PSIA 14.4 14.4 14".4 14.7 14.7 14.7 14.7 14.7 44 9 25 TR 16 19-44 DRYWELL PRESSURE PSIA 14 15 15 17 17 17 17 17 45 9 25 PR 1 156 3 DW/ TORUS DP PSID 0.07 0.07 0.07 2.2 2.12 2.56 '2.62 2.62 46 9 25 TR 16 19 45- DAYWELL TEMPERATURE DEG F 125 125 124 224 236 .240 245 -245
[ 47 9 26 .PI 1 125 3A RX BUILDING DP IN N20 -1 -1 1 0.34 0.34 0.34 0.34 0.34 l .. 48 9 26 PI 1 125 38 RX 8UILDING DP IN H20 1 1- 1 0.34 0.34 0.34 0.34 0.34 49 9 26 FI 1 125 1A SGT$ FLOW CFM 1500 1500 1500 1500 1500 1500 1500 1500 50 9 26 F1 1 125 1B SGTS FLOW CFM 0 0 0 0 0 0 0 0 51 CAD DW/ TORUS 02 CONC. % 17.89 18.44 18.77 11.09 12.07 12.96 13.46 13.46 52 DW NYDR0 GEN CONC. % 0 0 0 0 0 0 0 0 , a
VERMONT YANKEE NUCLEAR POWER STATION REV. 2 EMERG'WCY RESPONSE PREPAREDNESS EXERCISE PAGE 8.0 4 1990 l 8.0 CPERAfl0NAL DATA (CONT 80)
................
- POST
. SCENARID TIME 06:00 06:15 06:30 06:45 07:00 ':7:00 CLOCK TIME 13:00 13:15 13:30 13:45 14:00 14r00 ITEM PANEL INST ID DESCRIPil0N UNITS 1 93 FT 23*108 1 MPCI FLOW OPM 0 0- 0 0 0 0 i 2.93 .F1 10 139A RNR A FLOW OPM 5897 5897 5897 5897 5897 5897 l 3 93 F1 10 1398 RNR e FLOW GPM 0 0 0 0 0 0 .i ~
4 93 .FI 14 50A CS A FLOW GPM 0 0 0 0 0 0 5 93 FI 14 505 CS B FLOW - GPM 0 0 0 0 0 0 6 93 Pl*16 19 12A DATWELL PAES$URE PSIA 17 17 17 - 17 17 - 17 7 93 PI 16 19 128 DRYWELL PRESSURE PSIA 17 17 17 17 17 17 8 94 FI 13 91 RCIC FLOW GPM 0 0 0 0 0 0 9 94 Fl*12 141A RWCU FLOW GPM 60 60 60 60 60 60 10 94 F1 12 1419 RWCU FLOW GPM 60 60 60 60 6C !.0 11 94- 2 165A RX C00LANT TEMP DEG > 298 298- 298- 298 298 298 12 94 2 1658 RX COOLANT TEMP DEC F 298 298 298 298 298 298
+ 13 94 '2 159A RECIRC A LOOP FLOW KGPM 0 0 0 0 0 0 14 94 2 1590 RECIRC B LOOP FLOW KGFM 0 0 0. -0 0 0 15 95 7 46A APRM/lRM A % 0 0 0 0 0 0 16 95 7 468 APRM/lRM S % 0 0 0 0 0 0 .!
17 95 7*46C APRM/lRM C % 0 0 0 0 0 0 18 95 7 460 APRM/IRM D % 0 0 0 0- 0 0 19 95 7 46E APRM/lRM E % 0 0 0 0 0- 0 20 95 7 46F AFRM/lRM F % 0 0 0' O O 0 21 95 7 43A SRM A CPS 38.7 38.7 38.7 38.7 38.7 38.7 , 22 95 7 438 SkM B CPS 38.1 38.1 38.1 38.1 38.1 38.1 23 95 7 43C SRM C CPS 38.4 38.4 38.4 38.4 38.4 38.4 24 95 7 430 SRM 0 CPS 38.3 38.3 38.3 .38.3 38.3- 38.3
.} 25 95 2 3 95 CORE FLOW MLI/HR 1- 1 1 1 1 1 I
26 95 2 3 95 CORE DP PSID 3 3 3 3 3 3 27 95 71 3 310 CRD FLOW GPM 35.1 35.1 35.1 35.1 35.1 35.1 ! 28 95 6*% WIDE RANGE PRESSURE PSIG 53 53 53 53 53 53 29 95 6 96 HARROW RANGE PRESS PSIG DSL DSL DSL DSL DSL DSL 30 95 6 97 FEEDWATER FLOW MLB/HR 0 0 -0 0 0 0 31 95 6-97 MAIN STEAM FLOW MLB/HR 0 0 0 0 0 0 32 95 6 98 NARROW RANGE LEVEL INCHES OSH OSH OSH OSH OSH OSH 33 95 6 98 WIDE RANGE LEVEL INCHES OSH OSH OSH OSH OSH OSH 34 9-6 LI 107 5 CST LEVEL 1 39 39 39 - 39' 39 39 35 96 LI 102 5A NOTWELL LEVEL N 1 58 58 58 58- 58 58
~.j ! 36 96 L1 102 5B NOTWELL LEVEL $ % 54 54 ~54 54 54 54 -
+
37 97 P! 101*29. CONDENSER VACUUM IN HG 30.3 30.3 30.3, 30.3 30.3 30.3- i
. 38 98 D/G A BKR (T CLOSED;Fa0 PEN) F F- F F F F~ ,
39 98 D/G B SKR (T= CLOSED;Fa0 PEN) F F F F F F l' j 40 ' 9 23 16 19 3A/C TORUS TEMPERATURE DEG F 98 98 98 98 98 98
, =1 9 25 LI 46A TORUS LEVEL FEET 1.88 1.88 1.88 1.88 1.88 1.88 1.j 42 9 25 LI 46b TORUS LEVEL FEET 1.88 1.88 1.88 1.88 1.88 1.88 < q 43 9 25 TR 16 19 44 TORUS PRESSURE PSIA 14.7 14.7
- 14.7 14.7 14.7 14.7 44- 9 25 TR 16 19 44 - DRYWELL PRE $huRE PSIA 17 17 17 17 . 17 17 45 9 25 PR-1 156 3 DW/ TORUS DP PSID 2.62 2.62 2.62 2.62 2.62- 2.62 44 9-25 TR 16-19 45 DATWELL TEMPERATURE DEG F 245 245- 4 245 245 245 245-47 9 26 PI 1 125 3A RX BUILDIN0 DP IN H2O 0.34 0.34 0.34 0.34 0.34 0.34 I 48 9 26 PI 1 125 38 RX BUILDING DP IN N20 0.34 0.34- 0.34 0.34 0.34 -0.34' 49 9 26 FT 1 125 1A SGTS FLOW CFM 1500. 1500 1500 1500 1500 1500-50 9 26 F1 1 125 18 SGTS FLOW CFM C 0 0 0 0 0 31 CAD DW/ TORUS 01 CONC. X 13.46 13.46 13.46 13.46 13.46- 13.46 52 DW HYDROGEM CONC. X 0 0 0 0 0 0
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e VERMONT YANKEE NUCLEAR POWER STATION- REY. 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE PAGE 9.1 1 1990 9.1 AREA RADIATION MONITORS-SCENARIO TIME 00:00 00:15 00:30 00:45 01:00 01:15 01:30 -01:45 CLOCK TIME 07:00 07:15 07:30 07:45 08:00 08:15 08:30 08:45 PANEL BLDG /ELV DESCRIPfl0N UNITS RMSil*1 9 11 RB/256 RX BLDG WI RADS N R/NR -<1 <1 <1 <1 <1 <1 <1 <1 RMSIl 2 9 11 RB/256 RX BLDG HI RADS . 5 R/HR <1 <1 <1 <1 <1 <1 <1 <1 RMSil 3 9 11 RS/256 TIP RM HI RAD R/HR <1 <1 <1 41 <1 <1 <1 <1 ' i 9 11 RB/232 SUPP CHANS RD EXT CW MR/HR 8 8 8 8 8 7 7 7 2 9 11 RS/256 N PERSONNEL RB ACCESS MR/NR 10 10 10 10 10 8 6 5 3 9 11 RB/256 S EQUIP RR RB ACCESS MR/NR 0.3 0.3 = 0.3- 0.3 0.3 0.3 0.3 0.3 4 9 11 RB/256 RB NEUTRON MON *TIP MR/HR- 5 5 5 5 5 5 5 5 5 9 11 kV256 PERSONNEL HATCH RB MR/HR 300 300 300 300 300 240 180 140 6 9 11 RB.'280 ELEV ENTR 280FT RB MR/HR' 8 8 8 8 8 8 7; 7 7 9 11 RB/3 6 CR0 REPAIR RB(CR0 RM) MR/HR 16 16 16 16 16 13 10 10 8 9 11 RB/303 ELEV ENTR 303FT RS MR/HR 3 3 3 3 3 2.5 2 :2 9 9 11 RS/303 k'?O CLEANUP (SAMPLE $ 4 )1R/HR 4 4 4 4 4 4 4 4 10 9 11 RS/318 EL'V ENTR 318FT RB MR/HR 5 5 5 5 5 4.5 4 '4 11 9 11 RO/318 H2O CLEANUP (PRE COAT) MR/NR 5 5 5. 5 5 4.5 . 4 4 12 9 11 RS/345 ELEY ENTR 348FT RB MR/HR 4 4 4 4 4 3 2.5 2 14 9 11 RB/345 WEST REFUEL RB MR/NR 3 3 3 3 3 2.5 2 2 15 9 11 RB/345 SPENT FUEL P0OL RB' MR/HR 8 8 8 8 8 8 8 8 16 9 11 RO/318 NEW FUEL VAULT RB MR/HR 0.65 0.65 0.65 0.65 0.65 0.58 0.52 0.48 17 9 11 RW/230 RECIRC PUMP RM RW MR/HR 1 .1 1 1_ 1 1 1 1 18 9 11 RW/255 RADW OPER AREA RW MR/HR 1 1 '1 .1 '1 1 1 'i 19 9 11 RW/255 PUMP / TANK AREA RW MR/HR 2 2 2 2 2 2 2- 2 20 9 11 TB/248 N ACCESS 248FT TB MR/NR 3 3 3- 3 3 3 2 2 21 9 11 TF248 MAIN STM VALVE'TB MA/HR 370 370 370 370 370 350 320' 270 22 9 11 TB/232 CONDENSATE DEMIN TB MR/HR 0.3 0.3 0.3 0.3 0.3 0.28 0.26 0.24 23 9 11 TB/252 DECONTAMINATION TB MR/HR 0.16 0.16 0.16 0.16 0.16 0.16 0.16 0.16 24 9 11 TB/272 TURB STM INLET T8 MR/HR 190 190 190 190 190 180 160 -140 25 9 11 AB/272 VIEW GALLERY CR MR/HR 0.12 0.12 0.12 0.12 0.12 0.12 0.12 0.12 26 9 11 TB/252 REAR GATE TURB WARENSE MR/HR 0.02 0.02 0.02 0.02 0.02- 0.02 0.02 0.02 13 9 11 TB/228 %IST SEP AREA TB MR/HR 150 150 150 150 150 140 130 110
I VfRMONT YANKEE NUCLEAR POWER STAfl0N ALV. 0
- EMERGENCY RESPONSE PREPAREDNESS EXERCISE PAGE 9.1 2 j 1990 9.1 AREA RADIATION MONITORS (CONT 80)
SCENARIO TIME 02:00 02:15 02:30 02:45- 03:00 03:15 03:30 03:45 CLOCK TIME 09:00 09:15 09:30 09:45 10:00 10:15 10:30 10:45 AR1 No. PANEL BLDG /ELV DESCRIPTION- UNITS RMSil'1 9*11 RS/256 RX BLDG HI RADS N R/HR <1 <1 <1 <1 <1 <1 <1 <1 RMSIl 2 9 11 RS/256 RX BLOG HI RADS S R/HR <1 <1 <1 <1 <1 <1 <1 <1 RMS!! 3 9 11 RB/256 TIP RM HI RAD R/HR <1 <i <1 si <1 <1 <1 <1 1- 9 11 RB/232 SUPP CHAMB RB EXT CW MR/HR 7 7 6 6 6 6 6 6 ! 2 9*11 RS/256 N PERSONNEL RB ACCESS MR/HR 4 3 3 2 1 1 0.7 0.6 3 9 11 RS/256 S EQUIP RR kB ACCESS MR/HR 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 4 9 11 RS/256 RB NEUTRON MON *TIP MR/HR 5 5 5 5 5 5 5 5 5 9 11 RB/256 PERSONNEL HATCH RB MR/NR 100 90 75 50 35 20 15 12 6 9 11 RB/280 ELEV ENTR 280FT RB MR/HR 6 6 6 6 5.5 5.5 5- 5 7 9 11 RB/256 CRD REPAIR RB(CRD RM) MR/HR 8- 7 7 6 5 4 4 4 8 9 11 RS/303 ELEV ENTR 303FT RB MR/HR 2 2 2 2 1 1 1 1
- 9. 9 11 RB/303 H2O CLEANUP (SAMPLE $1NK)MR/HR 4 4 4 4 4 4 4 4 i 10 9 11 RS/318 ELEY ENTR 318FT RB MR/HR 4 4 4 .3 3 3 3 3 11 9 11 RB/318 H2O CLEANUP (PRE COAT) MR/HR 3 3 3 3 3 2 2 2 i r
12 9 11 RS/345 ELEV ENTR 348FT RB MA/HR 2 2 2 2 1 1 1 1
- \
9 11 RB/345 14 WEST REFUEL RB MR/nR 2 2 2 1 1 1 1 1 15 9 11 RS/345 SPENT FUEL POOL RB MR/HR 8 8 8 8 8 8 8 8 16 9 11 RB/318 WEW FUEL VAULT RB MR/HR 0.45 0.4 0.4 0.4 0.4 0.35 0.35 0.35 17 9 11 RW/230 RECIRC PUMP RM RW MR/NR 1 1 1 1 1 1. 1 1
=
18 9 11 RW/255 RADW OPER AREA RW MR/HR 1 1 1- 1 1 1 1 1
- 19 9 11 RW/255 PUMP / TANK AREA RW MR/HR 2 2 2 2 2 2 2 2 20 9 11 TB/248 N ACCESS 248FT TB- MR/M 2 2 2 2 2 2 2 2 21 9 11 TB/248 MAIN STM VALVE TB MR/HR 230 190 160 140 120 110 100 90 22 9 11 TB/232. CONDENSATE DEMIN TB MR/HR 0.2 0.2 0.18 C.18 0.16 0.15 0.15 0.14 23 9 11 TB/252 DECONTAMINATION TB MR/HR 0.16 0.15 0.15 0.15 0.15 0.15 0.15 0.15 24 9 11 TB/272 TURB STM INLET TB MR/HR 110 95 80 70 60 55 50 45 25 9 11 AB/272 VIEW GALLERY CR MR/HR 0.12 0.1 0.1 0.1 0.1 0.1 0.1 0.1 M 26 9 11 TB/252 REAR CATE TURB WAREHSE MR/HR 0.02 0.01 0.01 0.01 0.01 0.01 0.01 0.01 13 9 11 TB/228 M0lST SEP AREA TB MR/HR 90 80 65 55 45 40 30 30 9
VERMONT TANKEE NUCLEAR POWER STATION REY. O A EMERGENCT RESPONSE PREPAREDNESS EXERCISE PAGE 9.1 3 9.1 AREA RADIAil0N MONITORS (CONT'0) 1 SCENAtto TIME 04:00 04:15 04:30 04:45 05:00 05:15 05:30 05:45 CLOCK TIME 11:00- 11:13 11:30 11:45 12:00 12:15 12:30- 12:45 ARM No. PANEL BLDG /ELV DESCRIPfl0N UNITS RMSl1 1. 9 11 RB/256 RX BLDG HI RADS N ~R/HR <1 <1 <1 2 10 16- 20 24 RMS!I 2' 9 11 k:,/256 RX BLDG HI RADS S R/HR <1 <1 <1 3 12 20 25 30
- RMSil 3 9 11 RB/256 TIP RM HI RAD R/HR <1 <1 <1 2 10 16 20 24 1 9 11 RB/232 BUPP CHAMS RB EXT CW MR/HR 6 6 6 3000 6000 9000 (OSH)>1E4 ~ (OSH) 2 9 11 RS/256 N PERSONNEL RB ACCESS MR/HR 0.5 0.4 0.4 (0$H)>1E3 (OSH) (OSH) (OSH) (OSH) 3 9 11 RB/256 S EQUIP RR RB ACCESS. MR/HR 0.3 0.3 0.3 (0$H)>1E3 (0$N) (OSH) (OSH) (CSH) 4 9 11 RS/256 RB WEUTRON MON TIP MR/HR 5 5 5 1800 10000 (0$N)>1E4- (OSH) -(OSM) 5 9 11 RB/256 PERSONNEL HATCH RB MR/NR 9 8 .7 6000 (0$N)>1E4 '(OSM) (OSH)' (05H) 6 9 11 RS/280 ELEY ENTR 280FT RB MR/HR 5 5 5 1700 5500 (OSP 1E4 (OSH) (OSH) 7 9 11 RB/256 CR0 REPA!R RB(CRD RM) MR/HR 4 4 4 200 630 200 2100 2500 8 9 11' RS/303 ELEV ENTR 303FT RB MR/HR 1 1 1 6000 (OSM)>1E4 tosh)' (OSH) (OSH) 9 9 11 RS/303 H2O CLEANUP (SAMPLE $1NK)MR/HR 4 4 4 6000 (0$H)>1E4 (OSH) : (OSH) (OSH) 10 9 11 RB/318 ELEY ENTR 318FT RB MR/HR 3 3 3 1700 5300 (OSM)>1E4 (OSH) (OSH) 11 9 11 RS/318 - H2O CLEANUP (PRE COAT) MR/HR 2 2 2 1700 5500 (OSM)>1E4 (OSH)' (OSH) 12 9 11 RB/345 ELEV ENTR 348FT RB MR/HR 1 1 1 600 1800 3900 5500 6600 14 9 11 RB/345 WEST REFUEL RB MR/HR 1 1 1 600 1800 3800 5400 6500 15 9 11. RS/345 SPENT FUEL POOL RB MR/HR 8 8 8 600 1800 3800 5300 6400 16 9 11 RB/318 NEW FUEL VAULT RB MR/HR 0.35 0.34 0.34 6.7 20 45 68 68
- 17 9 11 RW/230 RECIRC PUMP RM RW 'MR/HR 1 1 1 1 1 l' i 1 18 9 11 RW/255 RADW OPER AREA RW MR/HR 1 1 1 1 1 1 1 1 19 9 11 RW/255 PUMP / TANK AREA RW MR/HR 2 2 2 2 2 2 2' 2 20 9 11 TB/248 W ACCESS 248FT TB MR/HR 2 2 2 2 2 2 2 2 21 . 9 11 TB/248 MAIN STM VALVE TB MR/NR 80 70 65 60 55 55 50 - 50 22 9 11 TB/232 CONDENSAT8 DEMIN TB MR/HR 0.14 0.14 0.13 0.13 0.13 0.13 0.13 0.13 23 9 11 TB/252 DECONTAMINAfl0N TB MR/HR 0.15 0.15 0.15 0.15 0.15 0.15 0.15 0.15 24 9 11 TB/272 TURO STM INLET TB MR/HR 40 35 35 30 28 28 - 25 25 25 9 11 AS/272 VIEW GALLERT CR MR/HR 0.1 0.1 0.1 0.1 0.1 0.1 0.1L 0.1 26 9 11 TB/252 REAR GATE TURB WAREHSE MR/HR 0.01 0.01 0.01 0.01 0.01 0.01 0.01' O.01 13 9 11 TB/228 MolST SEP AREA TB MR/HR 23 19 16 16 16 16 16- 16 (OSH) 0FF SCALE HIGH
I REV. 0 [ VERMONT YANKEE NUCLEAR POWER STATION ( EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 PAGE 9.1 4 9.1 AREA RADIATION MONITORS (CONT'D)
, POST SCENARIO TIME 06:00 06:15 06:30 06:45 07:00 07:00
- CLOCK TIME 13:00 13:15 13:30 13:45 14:00 14:00 ARM No. PANEL BLDG /ELY DESCRIPfl0N UNITS f
....... ...... ............................... ............................................................ )
RMS!! 1 9 11 RS/256 RX BLDG HI RADS N R/HR 28 27 26 24 24 RMS!! 2 9 11 RS/256 RX BLDG HI RADS S R/HR 35 33 32 30 30 l
- I RMS!I 3 9 11 r.8/256 TIP RM H! RAD R/NR 28 27 26 24 24 1 9 11 RS/232 SUPP CHAMS RB EXT CW MR/NR (0$H)>1E4 (OSH) (OSH) (OSH) (OSH)
- l 2 9 11 RS/256 N PERSONNEL R$ ACCESS MR/HR (0$H)>1E3 .(OSN) (OSN) (OSN) (OSH) 3 9 11 RB/256 $ EQUIP RR RB ACCESS MR/HR (03H)>1E3 (OSM) (OSM) (OSH) (OSH) 4 9 11 'RB/256 RB NEUTRON MON TIP MR/HR (0$N)>1E4 (OSM) (OSH) (OSH) (OSH) 5 9 11 Rs/256 PERSONNEL HATCH RB MR/NR (0$H)>1E4 (OSN) (OSH) (OSH) (OSH) i 6 9 11 RB/280 ELEY ENTR 280FT RB MR/HR (0$H)>1E4 (OSN) (OSH) (OSH) (OSH) l 7 9 11 RS/256 CRD REPAIR RB(CRD RM) MR/HR 3000 2800 2700 2600 2500 8 9 11 RS/303 ELEY ENTR 303FT RB MR/HR (OSM)>1E4 (OSH) (OSH) (OSM) (OSH)
- l 9 9 11 R8/303 H2O CLEANUP (SAMPLE SINK)MR/HR (0$H)>1E4 (OSN) (OSM) (OSH) (OSH) 10 9 11 RS/318 ELEV ENTR 318FT RS MR/HR (0$H)>1E*. (OSH) (OSM) (OSH) (OSH) 11 9 11 Rs/318 H2O CLEANUP (PRE COAT) MR/HR (OSH)>1E4 (OSM) (OSH) (OSH) (OSH) 12 9 11 R8/345 ELEV UTR 348FT RB' MR/HR 7600 7300 7000 6700 6500 14 9 11 Rs/345 WFT' iiFUEL RB M/HR 7500 7200 6800 6600 6400 15 9 11 RS/345' :WT FUEL POOL RB MR/HR 7400 7000 6700 6500 6200 9 11 RB/318 a 'l FUEL VAULT R8 68 68 68 68 68 45 A 16 MR/HR 17 9 11 RW/230 '. CIRC PUMP RM RW MR/HR l' 1 1 1 1 1 18 9 11 RW/255 RADW OPER AREA RW - MR/HR 1 1 1 '1 1 1 19 9 11 RW/255 . PUMP / TANK AREA RW MR/HR 2. 2 2 2 2 2 20 9 11 TB/248 N ACCESS 248FT TB MR/HR 1.5 1.5 1.5 1.5 1.5 1.5 l 21 9 11 TB/248 MAIN STM VALVE TB MR/HR 50 50 50 50 50 54 22 9 11 T3/232 CONDENSATE DEMIN T8 MR/HR 0.13 .0.13 0.13. 0.13 0.13 0.13 l 23 9 11 TB/252 DECONTAMINATION TB MR/HR 0.15 0.15 0.15 0.15 0.15- 0.15 l 24 9 11 T8/272 TURB STM INLET TB MR/HR 25 25 .25 25 25' 27 i
- 25 9 11 AS/272 VIEW GALLERY CR MR/HR. 0.1 0.1 - 0.1 0.1 0.1 0.1 I 26 9 11 TB/252 REAR CATE TURB WARENSE MR/HR 0.01 0.01 0.01 0.01 0.01 0.01 13 9 11 ~ TB/228' MotST SEP AREA TB MR/HR ' 16 16 16 16 16 16 l
l ............................................................................................................. l (OSH) 0FF SCALE HIGH l
- MONITOR READINGS WILL DECREASE AS REACTOR BUILDING IS VENTED VIA $8GTS l
l l I l l I
m O VERMONT YANKEE NUCLEAR POWER STATION s EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 9 9.2 PROCESS MONITORS 9 9 1
-i
l VERMONT YANKEE NUCLEAR POWER STATIDN REY. 0 EMERGENCY RESPONSE PREPAREDNESS EXERCISE PAGE 9.2 1 1990
.2 PRDCESS MONITOR $
SCENARIO TIME 00:00 00:15 00:30 00:45 01:00 01:15 01:30 01:45 CLDCK TIME 07:00 07:15 07:30 07:45 08:00 08:15 08:30 08:45 ARM No. PANEL BLDC/ELY DESCRIPTION UNITS 92 STACK GAS MON GAS 1 CPM 150 150 150 150 150 150 150 150 92 STACK GAS MON GAS 2 CPM 200 200' 200 200 200 200 200 200 92 STACK HI RANGE MR/HR 0.1 0.1 0.1 0.1 0.1 0.1 . 0.1 0.1 92 CONTAINMENT MON GAS CPM 600 600 600 600 600 600 600 600 92 CONTAINMENT MON PART CPM 60000 60000 60000 60000 60000 60000- 60000 60000 92 DRYWELL CH A R/HR 3 3 3 3- 3 2 1 1 92 DRYWELL CH B R/HR 3 3 3 3 3~ 2 1 1. 92 RX BLDG VENT GAS CPM 500 500 500 500 500 500 500 500 9 2- RX BLDG VENT' PART CPM 4000 4D00 4000 4000 4000- 4000 4000 4000 31 9 10 RX BLDG VENT NORTH MR/HR 1 1 2 2 1 1 1 1
.32 9 10 RX BLDG VENT SOUTH MR/HR 1 1 2 2 1 1 1 1 453A 9 10 SPENT FUEL POOL A MR/HR 10 10 10 10 10 10 10 8 453B 9 10 SPENT FUEL POOL B MR/HR 10 10 10 10 10 10 10 8 9 10 MAIN STM LINE A MR/HR 200 200 200 '200 200 100 100 00 9 10 MAIN STM LINE B MR/HR 200 200 200 200 200 100 100 80 9 10 MAIN STM LINE C VA/HR 200 200 200 200 200 100 100 80 9 10 MAIN STM LINE D 4R/HR 200 200 200 200 200 100 100- 80 38 9 10 SJAE(AIR EJECTDR) MR/HR 270 270 270 270 270 260 -250 240 M
l 1
VERMONT YANKEE NUCLEAR POWER STAfl0N REV. O EMERGENCY RESPONSE PREPAREDNESS EXERCISE ' PACE 9.2 2 1990 V[ ) 2 PROCESS MON! TORS (CONT'D) SCENARIO TIME -02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 CLOCK TIME 09:00 09:15 09:30 09:45 10:00 10:15 10:30 10:45 PANEL INST 10 DESCRIPil0N UNITS ITEM ...... ............................... ............................................................................. 92 STACK GAS MON GAS 1 CPM 150 150 150 150 150 150 150 150 92 STACK GAS MON GAS 2 CPM 200 200' 200 200 200 200 200 200 92- STACK Mi RANGE MR/HR 0.1 0.1 0.1 0.1 0.1 -0.1 0.1 0.1
'92 CONTAINMENT MON GAS CPM 600 600 600 600 600 600 600 600 92 CONTAINMENT MON PART CPM 60000 60000 60000 60000 60000 60000 60000 60000 92 DATWELL CH A R/hR 1 1 1 1 1 1 1 1 92 DRYWELL CN $ R/NR 1 1 1 1 1 1 1 1 92- RX BLDG VENT GAS CPM 500 500 500 500 500 500 500 500 92 RX BLDG VENT PART CPM- 4000 4000 4000- 4000 4000 4000 4000 4000 31 9 10 RX BLDG VENT NORTH MR/HR 1 1 1 1- 1 1 1 1 32 9 10 RX BLDG VENT SOUTH MR/HR 1 1 1 1 1 1 1 1 453A 9 10 SPENT FUEL POOL A MR/HR 8 8 8 8 8 7 7 7 4538 9-10 SPENT FUEL POOL B MR/HR 8 8 8 8 8 7 7 7 9 10 MAIN STM LINE A MR/HR 60 55 0 0' 0 0 0 0 9 10 MAIN STM LINE B MR/HR 60 55 0 0 0 0 0 0 9 10 MAIN STM LINE C MR/HR 60 55 0 0 0 0 .0 0 9 10 MAlW STM LINE D MR/HR 60 55 0 0 0 0 0 0
~ 38 9 10 SJAE(A!R EJECTOR) MR/HR 230 225 0 0 0 0 0 0 O-g l
4
l l VERMONT YANKEE NUCLEAR POWER STATION REV. 0 l EMERGENCY RESPONSE PREPAREDNESS EXERCISE PAGE 9.2*3 1990 9.2 PROCESS MONITORS (CONT'D) SCENARIO TIME 04:00 04:15 04:30 04:45 05:00 05:15 05:30 05245 CLOCK TIME 11:00 11:15 11:30 11:45 12:00 12:15 12:30 12:45 ITEM PANEL ' INST ID DESCRIPfloh UNITS 92 STACK GAS MON GAS 1 CPM 150 150 150 OSH(>1E6) 0$H OSH OSH OSH 92 STACK GAS MON GAS 2 CPM 200 200 200 0$H(*1E6) OSH OSH OSH OSH j 92 STACK HI RANGE MR/HR 0.1 0.1 0.1 64 115 160 190 225 92 CONTAINMENT MON GAS CPM 600 600 600 OSH(>1E6) OSH OSH OSH OSH 92 CONTAINMENT MON *PART CPM 60000 60000 60000 OSH(>1E6) OSH OSH OSH OSH 92 DRYWELL CH A R/HR 1 1 1 1300 3000 2800 2700 2500 92 DRYWELL CH B R/HR 1 1 1 1300 3000 2600 2700 2500 92 RX BLDG VENT GAS CPM 500 500 500 OSH(>1E6) OSH OSH OSH OSH 92 RX BLDG VENT PART CPM 4000 4000 4000 0$H(>1E6) OSH OSH OSH OSH 31 9 10 RX BLDG VENT NORTH MR/HR 1 1 1 0$H(>1E3) OSH OSH OSH OSH 32 9 10 RX BLOG VENT SOUTH MR/HR 1 1 1 OSH(>1E3) OSH- OSH OSH OSH 453A 9 10 SPENT FUEL POOL A MR/HR 7 7 7 600 2000 4000 5000- 6000 4538 9 10 SPENT JUEL POOL B MR/HR 7 7 7 600 2000 4000 5000 6000 9 10 MAIN STM LINE A MR/HR 0 0 0 0 0 0 0 0 1
. 9 10 MAIN STM LINE B MR/HR 0 0 0 0 0 0 0 0 9 10 MAlW STM LINE C MR/HR '0 0 0 0 0 0 0 0 9 10 MAIN STM LINE D MR/HR 0 0 0 0 0 0 0 0 !
38 9 10 SJAE(AIR EJECTOR) MR/HR 0 0 0 0 0 0 0 0
'g, 3 ,
e
VIRMONT YAhKit NUCLEAR POWER STATION REV. 0 1 EMERGEhCT RESPON$t PktPAR10NES$ IXERCISE PAGE 9.2 4 i 1990 i 9.2 PROCES$ NON!f0R$ (CONT'0) !
$cthARio 11M8, 06:00 06:15 06:30 06:45 07:00 i CLOCK 11ME 13:00 13*15 13:30- 13:45 14:00 ITEM PeNil IN$1 10 0($CRIPfl0N UNIT $
..... ...... ............................... .............. .................................... i 92 STACK GAS MON GAS 1 CPM 0$ M(> 1E',) 0$N 0$N 0$N CSM 92 STACK CA$ MON GAS 2 CPM 0$M(*1F 6) 0$M OSM 0$N 0$N 92 STACK Mi RANGE MR/NR 230 230 210 200 200 92 CONIA!NMENT MON GA$' CPM 0$N(> E6) 0$N OSM OSM 0$N 92 CONTAINMENT MON PARI CPM ObM(*1E6) OSM OSM 0$M 0$N 92 DRYWELL CH A R/MR 2900 2200 2100 2000 1900 92 DRTWELL CM B R/NR 2900 2200 2100 - 2000 1900 92 RX BLOG VENT GAS CPM 0$N(>1t6) 0$M 0$N 0$N 0$N 92 RX BLOG VENT = PART CPM C$N(*1!6) OSM OSM 0$N OSM l 31 9 10 RX BLOG VENT NORTM MR/HR 0$N(>1E3) 0$M 0$M OSM 0$N !
32 9 10 RX BLOG VENT SOUTM MR/HR 0$M(>1E3) 0$N 0$N OSM 0$N 453A. 9 10 SPENT FUEL POOL A MR/MR 7000 7000 6000 6000 2400 ! 4538 9 10 SPENT FUEL POOL B MR/NR 7000 7000 6000 6000 2400 9 10 MAIN STM Llhi A MR/HR 0 0 0 0 0 9 10 MAIN STM LIht B MR/HR 0 0 0 0 0 9 10 MAIN $1M LlhE C MR/hR 0 0 0 0 0 9 10 MAIN $1M LlhE 0. MR/HR 0 0 0 0 0 38 9 10 SJA!(AIR EJECTOR) MR/NR 0 0 0 0 0 h01E Post 1400 values decline steadily with time. M
O ( VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.3 IN-PLANT RADIATION LEVELS l O . O
O O O TABLE 9.3-1 Rev. O Page 9.3-la Reactor Building Refuel Deck, Elevation 345' (mR/hr unless otherwise noted) Clock Scenario Zone III Zone IV Time Time ARM 12 ARM 14 ARM 15 453 A 453 B Zone I Zone II
------- -=_ - - - - - - - - - - - = _ - - - - - - - - - - - - - - - - - - - -
- - - - - - - - - - = - - -
0700 0 4 3 8 10 10 4 ' 10 10 10 0800 1:00 4 3 8 10 10 4 10 10 10 0815 1:15 3 3 8 9 9 4 10 10 9 1:30 3 3 8 9 9 4 9 9 9 0830 9 9 0845 1:45 2 2 8 8 8 3 9 2:00 2 2 8 8 8 3 8 8 9 0900 8 8 8 0915 2:15 2 2 8 -8 8 2 2:30 2 2 8 8 8 2 8 8 8 0930 8 8 8 0945 2:45 2 1 -8 7 7 2 3:00 1 1 8 7 7 2 7 7 8 1000 1 7 7 8 1015 3:15 1 1 8' -7 '7 1 1- 8 7 7 1 7 7 8 1030 3:30 1 7 7 8 1045 3:45 1 1 8 7 7. 4:00 .1 1 8- 7 7 1 7- 7 8 1100 7 7 8 1115 4:15 l' 1 8 7 7 1 4:30 1 ~1 8 7 7 1 7 7 -8 1130 600 600 600 1145' 4:45 600 600 600 600 600 600 5:00 1800 1800 1800 1700 1700 2000 1700 1700 2000 1200 4000 4000 1215 5:15 3900 3900 3800 3700 3700 4000 4000 5:30 5500 5400 5300 5200 5200 5500 5000 5000 5500 1230 6000 6000 6600 1245 5:45 6600 6500- 6400 6200 6200 6600 6:00 7600 -7500 7400 7200- 7200 7600 6950 6950 7600 1300 6600 6600 7300 1315 6:15 7200 7000 7000. 6900 6900 .7300 6:30 7000 6800 6700 6600 6600 7100- 6500 6500 7100 1330 6700 1345 6:45 6700 6600 udOO 6300 6300 6700 .6100 6100 1400 7:00 6500 6400 6200 6100 6100 6500 5900 5900 6500
=-
-== .=_ - - - = - . _ _ _
Notes: Zone readings are average dose rates throughout zone. General area contamination levels 2K-10K dpm/100 cm2 in all zones after 1130.
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I L O O O i l TABLE 9.3-2 Rev. O i i Reactor Building, Elevation 318' Page 9.3-2a j (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 5 5 1 5 5 3 ~ 5 4 1 1 ! 0800 1:00 5 5 1 5 5 3 5 4 1- 1 0815 1:15 4 4 1 5 5 3 5 4 1 1 i 0830 1:30 4 4 1 5 5 3 5 4 1 1 0845 1:45 4 4 1 4 4 3 4 3 1 1
' 0900 2:00 4 3 0.5 4 4 3 4 3 0.5 0.5 0915 2:15 4 3 0.5 4 4 3 4 3 0.5 0.5 0930 2:30 4 3 0.5 4 3 2. 3 2 0.5 0.5 -
0945 2:45 3 3 0.5 4 3 2 3 2 0.5 0.5 1000 3:00 3 3 0.5 4 3 2 3 2 0.5 0.5 1015 3:15 3 2 0.5 3 2 2 2 1 0.5 0.5 1030 3:30 3 2 0.5 3 2 2 2 1 0.5 0.5 1045 3:45 3 2 0.5 3 2 1 2 1 0.5 0.5 1 1100 4:00 3 2 0.5 3 2 1 2 1 0.5 0.5 1115 4:15 3 2 o0. 5 3 2 1 2 1 0.5 0.5 1130 4:30 3 2 0.5 3 2 1 2 1 0.5 0.5 1145 4:45 1700 1700 7 1700 1700 1000 1700 800 1400 1400
- 1200 5:00 5300 5500 20 5300 5500 4500 5500 .3600 4200 4200 l 1215 5:15 (OSH)>1E4-(OSH)>1E4 50 11000 12000 10000 12000 8000 8800 8800 i 1230 5:30 (OSH) (OSH). 70 17000 20000 15000 20000. 12000 14000 14000 1245 5:45 -(OSH) (OSH) 84 20000' 24000 20000 24000 16000 16000 16000 1300 6:00 (OSH) (OSH) 98- 23000 28000 22000 28000 18000 18000 18000 1315 6:15 (OSH) (OSH) 94 22000 .27000 21000 27000 17000 17000 17000 1330 6:30 (OSH) (OSH) 91 21000 26000- 21000 26000 17000_ 17000 17000 1345 6:45 (OSH)- (OSH) 85 20000 24000 20000 24000 16000 16000 16000 1400 7:00 (OSH). (OSH) 82 19000 23000 20000 24000 16000 15000 15000
__-___===_ _----------------- ____ ------------------__-- ___- _ _ _ _ _ - - 1 Notes: Zone readings are average dose rates throughout zone. 1 General area contamination levels 10K-50K dpm/100 cm2 in all zones after 1130. (OSH) OFF SCALF HIGH
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O O O 1 TABLE 9.3-3 Rev. O Reactor Building, Elevation 303' Page 9.3-3a (mR/hr unless otherwise noted) Clock Scenario TiEe Time ARM 8 ARM 9 Zone I Zone II Zone III Zone IV Zone V Zone VI Zone VII i
-. - = - - - - - - - - - - - - . . . - - - - - - - - - = = - - - - - - - - - --- - - - - -
- 0700 0 3 4 4 3 _ - - - - - - - - - - - - - - - - - - , - - - - - - - - -
0800 1:00 3 4 4 3 6 3 6 5 5 0815 1:15 2 4 4 3 6 3 6 5 5 ; 0830 1:30 2 4 4 3 6 3 6 5 5 0845 1:45 2 4 4 3 6 3 6- 5 5 0900 2:00 2 4 4 3 6 3 6 5 5 0915 2:15 2 4 4 4 6 4 6 5 5 0930 2:30 2 4 4 4 6 4 6 5 5 0945 2:45 2 4 4 4 6 4- 6 5 5 i 1000 3:00 1 4 4 4 6 4 6 6 6 1015 3:15 1 4 4 4 7. 4 7 6 6 ' 1030 3:30 1 4 4~ 4 7 4 7 6 6 1045 3:45 1 4 4 4 7 4 7 6 6
-1100 4:00 1 4 4 4 7 4 7 6 6
- 1115 4
- 15 1 4 4 4 7 4 7 6 6 i 1 7 7 6 1130 4:30 4 4- 4 4 6-1145 4:45 1000 1600 1400 1400 900 1400 1400. 1100 1400 1200 5:00 4000 5600 4200 4200 3000 4200 4200 3400 4200 ;
i 1215 5:15 7800 9600 8800 8800 6000 8800 8800 7000 8800 1230 5:30 (OSH)>1E4.(OSH)>1E4 14000 14000 9000 14000 14000 11000 14000 1245 5:45 (OSH) (OSH) 16000 16000 10000 16000 16000 13000 16000 1300 6:00 (OSH) . (OSH) - '18000 18000 11000- 18000 18000 14000 18000 i 1315 6:15 .(OSH) -(OSH)~ 17000 17000 11000 17000 17000 14000 17000 1330 6:30 (OSH) (OSH) 17000 17000 11000 17000- 17000 14000 17000 1345 6:45 (OSH) (OSH) 16000 16000 10000 16000 16000 13000 16000 + s 1400 '7:00 (OSH) :(OSH) 15000 15000 9600 15000 15000 12000 15000 , Notes: Zone readings are average dose rates throughout zone. General area contamination levels 10K-50K dpm/100 cm2 in all zones after 1130. j . (OSH) OFF SCALE HIGH
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O O O TABLE 9.3-4 Rev. O Page 9.3-4a Reactor Building, Elevation 280' (mR/hr unless otherwise noted) RB Vent -RB Vent Clock Scenario North South ARM 31 ARM 32 Zone I Zone II Zone III Zone-IV Zone V. Zone VI Zone VII Time Time ARM 6 - - - - - - - - - - - - _ - - - -
=_
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1 1 10 12 10 8 10 12 1 0700 ~ 0 8 12 1 1:00 8 1 1 10 12 10 8 10 0800 8 7 8 12 1 0815 1:15 7 1 1 8 12 1 8 12 8 7 8 12 1 0830 1:30 7 1 1 7 1 1 8 10 8 7 8 10 0845 1:45 6 8 10 1 2:00 6 1 1 8 10 8 0900 7 6 7- 10 1 0915 2:15 6 1 1 7- 10 1 1 7 10 7 6 7 10 1 0930 2:30 6 1 2:45 6 1 1 7 10 7 6 7 10 0945 6 7 9 -1 1000 3:00 6 1 1 7 9 7 1 1 ~7 9 7 5 7 9 1 1015 3:15 5 1 5 1 1 7' 9 7 5 7 9 1030 3:30 5 7 9 1 1045 3:45 5 1 1 7 9 7. 1 -1 7 9- 7 5 7 9 1 1100 4:00 5 9 1 5 1 1 7 9 7 5 7 1115 4:15 8 1 4:30 5 1 1 7 8 7 5 7' 1130 2000 1700 2000 2200 2000 1145 4:45 1700 OSH(>1E3)OSH(>1E3) 2000 2200 OSH OSH 5500 5800 5500 5500 5500 5800 '6000 1200 5:00 5500- 10000
.OSH- OSH 12000 15000 '12000 11800 12000 15000 1215 5:15 OSH(>1E4) 20000 17000 20000 24000 15000
'1230 5:30 OSH OSH 'OSH 20000 -24000 OSH OSH OSH .24000 29000 240C0 21000 24000 .29000 18000 1245 5:45 24000 28000 34000 20000 1300 6:00 OSH OSH OSH' 28000 34000 28000 OSH OSH 27000 32000 27000 23000 270C0 32000 20000 1315 6:15 OSH 20000 OSH .OSH OSH 26000 31000 26000 22000 26000 31000 1330 6:30 29000 24000 21000 25000 29000 20000 1345 6:45 OSH OSH OSH 24000 OSH OSH 24000 28000 24000 20000 24000 28000 20000 1400 7:00 OSH
=_ _ - _ _ - . - _ _ - - - - - = = - -------------
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Notes: Zone readings.are average dose-rates throughout zone. General area contamination levels 20K-100K dpm/100 cm2 in all zones after 1130. Zone VIII same as Zone VI
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l l TABLE 9.3-5 Rev. O Reactor Building,' Elevation 252' Page 9.3-Sa.1 (mR/hr unless otherwise noted) Clock Scenario RM- Zone Zone Zone Zone Zone Zone Zone Time Time ARM 2 ARM 3 ARM 4 ARMS ~ ARM 7 14-29* I II III - IV V VI VII
-------- _ _= ---- - ------------------------- - -
0700 0 10 1 5 300 20 100 5 12 1 300 1 20 28 0800 1:00 10 'l 5 300 .20 100 5 12 1 300 1 20 24 0815 1:15 8 1 5 240 10 100 5 12 l' 240 1 10 20 i 0830 1:30 6 1 5 180 10 100 5 10 1 180 1 10 18 j 0845 1:45 5 1 5 140 10 100 5 8 1 140 1 10 15 0900 2:00 4 1 5 100 '10 100 5 7 1 100 1 10 13. 0915 2:15 3 1 5 90 10 100 5 5 1 90 1 10 10
'0930 2:30 3 1- 5 70 10 100 5 5 1 70 1 10 10 ,
0945 2:45 2 1 5 50 5 100 5 3 1 50 1 5 10 1000 3:00 1 1 5 30 5 100 5 2 1 30 1 5 10 1015 3:15 1 1 5 20 5 100 5 1 1 20 1 5 10 1030 3:30 1 1 5 20 5 -100 5 1 1 20 1 5 10 ! 1045 3:45 1 1 5 10 5 100 5 1 1 10 1 5 10 1100 '4:00 1 1. 5 10 5 100 5 1- 1 10 1 5 10 'l 1115 4:15 1 1 5 10 5 100 5 1 1 10 1 5 9 1130 4:30 1 1 5 10 5 100 5 1 1 10 1* 5 8 1145 4:45- >1E3 >1E3 1800 6000 200 >500 2000 2000 3000 6000 3000 200 250 1200 5:00 (OSH) (OSH) 10000 >1E4 600 >500 10000.10000 12000 19500 12000 600 700 1215 5:15 (OSH) -(OSH) >1E4 (OSH) 1400 >500 16000 16000 20000 41000-20000 1400 1800 1230 5:30 (oSH) (OSH) (OSH) (OSH) 2100 >500 20000 20000 25000 53500 25000 2100 2900 1245 5:45 (OSH) (OSH) (OSH)- (OSH) 2500 >500 24000 24000 30000. 64000 30000 2500 3500 1300 6:00 (OSH) (OSH) (OSH)- (OSH) 13000 >500 28000 28000 35000 74000 35000- 3000 4000 , 1315 6:15 (OSH) (OSH) (OSH)' (OSH) 2800 >500 27000 27000 33000 71000 33000 2800 3800 6:30 (OSH) (OSH) (OSH)- (OSH) 2700 >500 26000 26000 32000 68000 32000 2700- 3700 1345 6:45 (OSH) (OSH)'(OSH) (OSH) 2500- >500 24000.24000 30000 65000 30000 2500 3500 1400 7:00 (OSH). (CSH) (OSH) (OSH) 2500 >500 24000.24000 30000 63000 30000 2500 3400 . . - - - - - - - - - - - - - - - - - - _ _ - = _ _ - . - _ ____ =_ ------- =_----- . Notes: Zone readings are average dose rates.throughout zone. t General area contamination levels 20K-100K dpm/100 cm2 in all. zones after 1130. _ - - - - _ _ . . - - - - - _ _ _ _ - - - _ _ _ _ . _ _ . . + .- _ __ _ -_
L O O O Rev. O Page 9.3-Sa.2 TABLE 9.3 (Continued) Clock Scenario NORTH SOUTH TIP Time Time RMS II- 1*
- RMS II-2** RMS II--3 *
- 0700 0 <1.0 <1.0 <1.0
- 0800- 1
- 00 <1.0 :
<1.0 <1.0 0815 1:15 <1.0 <1.0 <1.0
! 0830 1:30 <1.0 <1.0 <1.0 l' 0845 1:45 <1.0 <1.0 <1.0 l 0900 2:00 <1.O <1.O <1.O- , 0915 2:15 <1.0 <1.0 <1.0 l 0930 2:30 <1.0 <1.0 <1.0 0945 2:45 <1.0 <1 . 0 <1.0-1000- 3:00 <1.0 <1.0 <1.0 i 1015 3:15 <1.0 <1.0 <1.0 1030 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 t 1115 4:15 <1.0 <1.0 <1.0 1130 4:30 <1.0 - <1.0 <1.0
- 1145 4
- 45 2 :3 2 1200 5:00 10 12 10 1215 5:15L 16 20 '16 i
1230 5:45 20 25 20 1245 5:45 24 30 24 1300 6:00' 28 35 28 1315 6:15 27 33 27 1330 6:30 26 32 26 1345 6:45- 24 30 24 1400 7:00 24 30 24 + Notes:
**- RMS II readings in R/hr. (high-range accident ARMS - 1 R/hr to 10,000 R/hr) 1 l
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TABLE 9.3-5 Rev. 0 Turbine Deck, Elevation 272' Page 9.3-6a (mR/hr unless otherwise noted) Turbine Deck Scenario- CAM (cpm) Clock NG Particulate Time Time- ARM 24 Zone I Zone II Zone III
--=- ___ = -=- -=-- - ------- -- -- ---------
_=___-=------ . 0700 0 190 100 150 190 250 900 1:00 190 100 150 190 250 900 0800 250 900 0815 1:15 180 80 140 180 160 75 120 160 250 900 0830 1:30 250 900 0845 1:45 140 75 120 -140 2:00 110 75 90 110 250 900 0900 250 900 0915 2:15 100 50 80 100 80 50 70 80 250 900 0930 2:30 0945 2:45 70 40 60 70 250 900 3:00 60 40 50 60 250 900 1000 250 900 1015 3:15 50 30 50' 50 3:30 50 30 40 50 250 900 - 1030 250 900 1045 3:45 40 20 35 u4'O 4:00 40 20 35' 40 250 900 1100 250 900 1115 4:15 40 16 30 40 4:30 30 16 22 30 250 900 1130 250 900 1145- 4:45 30 16 22 30 5:00 30 11 22 30 250 900 1200 250 900 1213 5:15 30 11 22 30 5:30 25 11 22 25 250 900 1230 250 900 1245 r:45 25 10 20 25 25 10 20 25 250 900 1300 6:00 250 900
-1315 6:15 25 10 20 25 6:30 25 10 20 25 250 900 1330 250 900 1345 6:45 25 10 20 25 25 10_ 20 25 250 900 1400 -7:00 Notes: Zone readings are average dose rates th oug'iout zone.
General area contamination-levels <1K dpm/100 cm2.
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. n O O O TABLE 9.3-7 Rev. O Turbine Building Truck Bay, Make-Up Demineralization Cond. Page 9.3-7a Demineralization Areas, Elevation 252' (mR/hr unless otherwise noted)
Clock Scenario RM-14-23A RM-14-36 Time Time (cpm) ARM 26 (cpm) Zone I Zone II o Z~ne III Zone IV 0 150 0.02 150 0.2 0.2 0.1 0.2 0700 0.2 0.2 0800 1:00 150 0.02 150 0.4 0.3 1:15 150 0.02 150 0.5 0.3 0.2 0.2 0815 0.2 0.2 0830 1:30 150 0.02 150 0.5 0.3 1:45 150 0.0/ 150 0.5 0.3 0.2 3.2 0845 0.2 0900 2:00 150 0.02 150 0.5 0.3 0.2 2:15 150 0.01 150 0.5- 0.3 0.2 0.2 0915 0.2 0930 2:30 150 0.01 150 0.5 0.3 0.2 2:45 150 0.01 150 0.5 0.3 0.2 0.2 0945 0.2 1000 3:00 150 0.01 150 0.6 0.3 0.2 3:15 150 0.01 150 0.6 0.3 0.2 0.2 1015 0.2 0.2 1030 3:30 150 0.01 150 0.6 0.3 3:45 150 0.01 150 0.6 0.3 0.2 0.2 1045 0.2 0.2 1100 4:00 150 0.01 150 0.6 0.3 4:15 150 0.01 150 0.7 0.3 0.2 0.2 1115 0.2 0.2 1130 4:30 150 0.01 150 0.7 0.3 4:45 150 0.01 150 0.7 0.3 0.2 0.2 1145 C.2 0.2 1200 5:00 150 0.01 150 0.7 0.3 5:15 150 0.01 150 0.7 0.3 0.2 0.2 1215 0.2 1230 5:30 1EO 0.01 150 0.7 0.3 0.2 5:45 150 0.01 150 0.7 0.3 0.2 0.2 - 1245 0.2 1300 6:00 150 0.01 150 0.7 0.3 0.2 6:15 150 0.01 150 0.7 0.3 0.2 0.2 1315 0.2 0.2 1330 6:'0 4 150 0.01 150 0.7 0.3 6:45 150 0.01 150 0.7 0.3 0.2 0.2 1345 0.2 0.2 1400 7:00 150 0.01 150 0.7 0.3 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2. _ . _- m_...m., __--- .e.,. . _ . _ -
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O O ELEVATION 252' O . ge PRETREATMENT ROOM, BOILER R6OM, TURBINE LOADING BAY, MUDS, DIESELS. COND. DEMIN. HATCH
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O O O TABLE 9.3-8 Rev. O Turbine Building Cend. Bay, Elevation 248' Page 9.3-8a (mR/hr unler otherwise noted) Clock Scenario ~ Time Time ARM 20 ARM 21 Zone III Zo'ne IV Zo*te V Zone VI Zone VII Zone VII __ --_ _ _ _ _ - - = - - 0700 0 3 370 2 2 4 8 300 3 0800 1:00 3 370 2 2 4 8 300 3 0815 1:15 3 350 2 2 4 8 390 3 0830 1:30 2 320 2 2 4 8 'j 00 2 0645 1:45 2 270 2 2 4 4 300 2 0900 2:00 2 230 2 2 3 4 200- 2 0915 2:15 2 190 2 2 3 4 150 2 0930 2:30 2 160 2 2 3 4 150 2 0945 2:45 2 140 2 2 3 4 150 2 1000 3:00 2 120 2 2 3 4 100 2 1015 3:15 2 110 2 2 3 3 100 2 1030 3:30 2 100 2 1 3 3 90 2 1045 3:45 2 90 2 1 3 3 80 2 1100 4:00 2 80 1 l' 3 3 80 2 1115 4:15 2 70 1 1 2 3 60 2 1130 4:30 2 65 1 1 2 3 60 2 1145 4:45 2 60 1 1 2 2 50 2 , 1200 5:00 2 55 1 1 2 2 50 2 1215 5:15 2 55 '1 1 1 1 50 1 1230 5:30 2 50 1 1 1 1 50 1 4 { 1245 5:45 2 50 1 1 1 1 50 1 1300 6:00 2 50 1 1 1 1 50 1 1315 6:15 2 50 1 1 1 1 50 1 1330 6:30 2 50 1 1 1 1 50 1 1345 6:45 2 50 1 1 1 1 50 1 1400 7:00 2 50 1 1 1 1 50 1 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2. i 4
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O O O Rev. O TABLE 9.3-9 Page 9.3-9a Turbine Building, Demineralization /OG Areas, Elevation 232' i (mR/hr unless otherwise noted) Clock Scenario ! Time Time ARM 22 ARM 38 Zone I Zone II Zone III 0700 0 0.3 70 0.2 0.5 0.2 0800 1:00 0.3 70 0.2 0.5 0.2 0815 1:15 0.28 60 0.2 0.5 0.2 0830 1:30 0.26 50 0.2 0.5 0.2 0845 1:45 0.24 40 0.2 0.5 0.2 0900 2:00 0.20 30 0.2 0.5 0.2 0915 2:15 0.20 25 0.2 0.5 0.2 0930 2:30 0.18 D/S 0.2 0.5 0.2 0945 2:45 0.18 D/S 0.2 0.5 0.2 1000 3:00 0.16 D/S 0.2 0.5 0.2 1015 3:15 0.15 D/S 0.2 0.5 0.2 i 1030 3:30 0.15 D/S 0.2 0.5 0.2 1045 3:45 0.14 D/S 0.2 0.5 0.2 1100 4:00 0.14 D/S 0.2 0.5 0.2 1115 4:15 0.14 D/S 0.2 0.5 0.2 1130 4:30 0.13 D/S 0.2 0.5 0.2 1145 4:45 0.13 D/S 0.2 0.5 0.2 1200 5:00 0.13 D/S 0.2 0.5 0.2 1215 5:15 0.13 D/S 0.2 0.5 0.2 1230 5:30 0.13 D/S 0.2 0.5 0.2 1245 5:45 0.13 D/S 0.2 0.5 0.2 1300 6:00 0.13 D/S. O.2 0.5 0.2 1315 6:15 0.13 D/S 0.2 0.5 0.2 1330 6:30 0.13 D/S 0.2 0.5 0.2 ' 1345 6:45 0.13 D/S 0.2 0.5 0.2 1400 7:00 0.13 D/S 0.2 0.5 0.2 Notes: Zone readings are average dose rates throughout zone. i General area contamination levels <1K dpm/100 cm2. ' D/S = Downscale reading.
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O O O ' TABLE 9.3-10 Rev. O Turbine Building Cond. Bay, Elevation 222'6" & 228'6" (mR/hr unless otherwise noted) Clock Scenario - Time Time ARM 13 Zone I Zone II Zone III Zone IV Zone V Zone VI < 0700 0 150 3 1 50 150 2 75 , . 0800 1:00 150 3 1 50 150 2 75 i 0815 1:15 140 3 1 45 140 2 70 0830 1:30 130 3 1 45 130 2 70 0845 1:45 110 3 1 35 110 2 55 , 0900 2:00 90 3 1 30 90 2 45 t 0915 2:15 80 3 1 25 80 2 40 0930 2:30 70 3 1 20 70 2 35 0945 2:45 60 1 1 20 60 2 30 1000 3:00 50 1 1 15 50 2 25 ; 1015 3:15 40 1 1 10 40 2 20 1030 3:30 30 1 1 10 30 2 15 1045 3:45 30 1 1 10 30 2 15 1100 4:00 20 1 1 5 20 2 10 1115 4:15 20 1 1 5 20 2 10 1130 4:30 15 1 1 5 15 2 7 1145 4:45 15 1 1 5 15 2 7 1200 5:00 15 1 1 5 15 2 7 1215 5:15 15 1 1 5 15 2 7 1230 5:30 15 1 1 5 15 2 7 1245 5:45 15 1 1 5 15 2 7 . 1300 6:00 15 1 1 5 15 2 7 1315 6:15 15 1 1 5 15 2 7 1330 6:30 15 , 1 1 5 15 2 7 ) 1345 6:45 15 1 1 5 15 2 7 i 1400 7:00 15 1 1 5 15 2 7 Notes: Zone readings are averacye dose rates throughout zone. General area contamination levels <1K dpm/100 cm2.
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. 9.4 PLANT CHEMISTRY DATA I
i SECTION . ZAGI i f . U 9.4.1 Reactor Coolant Activity Data........................ 9.4.1 1
- 9.4.2 Primary Containment Air Activity Data................ 9.4.2 1 9.4.3 Reactor Building Air Activity Data................... 9.4.3-1 i
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i I I' Rev. 0 Page 9.4.1 1 VERMONT YANKEE NUCLEAR poi /ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uci/al) . Timo Isotope Prior to 1130 1130 1145 1145 1200 I.131 2.5E.03 1.1E+02 1.0E+02 1 132 2.8E 03 1.1E+02 1.0E+02 I.133 5.2E 03 2.0E+02 2.0E+02 1 134 4.1E 03 9.3E+01 7.5E+01 I.135 4.5E.03 1.8E+02 1.7E+02 Total Iodine 1.9E.02 6.9E+02 6.5E+02 1 131 Dose 4.5E.03 1.8E+02 1.8E+02 Equivalent Kr.83m 1.2E.03 6.1E 01 1.3E+00 Kr-85m 2.5E-02 4.3E.01 4.1E.01 Kr 85 4.8E.03 2.4E.02 2.4E.02
- Kr.87 2.9E 03 5.0E.01 4.3E.01 Kr.88 ?t.0E.03 9.9E.01 9.1E.01 Xe 133 5.3E-03 4.4E+00 4.6E+00 Xe.135m 5.8E.03 8.2E+00 1.7E+01 Xe.135 2.2E.03 2.6E+00 5.5E+00 Total Noble 4.8E 02 1.8E+01 3.0E4 01 Gas Note: Reactor coolant sataple dose rates are provided in Section 9.5.1. l O
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Rev. 0 'd Page 9.4.1 2 VEPJiONT YAl C UNLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCi/ml) Time Isotope 1200 1215 1215 1230 1230 1245
....... e........ ......... .........
I.131 1.0E+02 1.0E+02 9.9E+01 I.132 9.2E+01 8.4E+01 7.6E+01 1 133 1.9E+02 1.9E+02 1.8E+02 1 134 6.1E+01 4.9E+01 4.0E+01 1 135 1.6E+02 1.5E+02 1.5E+02 l Total Iodine 6.1E+02 5.8E+02 5.5E+02 1 131 Dose 1.7E+02 1.7E+02 1.6E+02 Equivalent Kr.83m 1.8E+00 2.2E+00 2.5E+00 Kr.85m 3.8E 01 3.6E.01 3.4E.01 ; Kr.85 2.3E.02 2.3E.02 2.2E.02 Kr 87 3.7E.01 3.2E.01 2.7E.01 Kr.88 8.4E.01 7.8E.01 7.2E.01 Xe.133 4.8E+00 5.0E+00 5.1E+00 i Xe.135m 2.1E+01 2.2E+01 2.2E+01 Xe.135 8.3E+00 1.1E+01 1.3E+01 Total Noble 3.7E+01 4.2E+01 4.5E+01 Cas Note: Reactor coolant sample dose rates are provided in Section 9.5.1. ,b U
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,m Rev. O (V) Page 9.4.1 3 ;
VERMONT YANKEE NUCLEAR POWER STATION ' EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCi/ml) Time Isotope 1245 1300 1300 1315 1315 1330 I.131 9.7E+01 9.5E+01 9.4E+01 I.132 7.0E+01 6.3E+01 5.8E+01 1 133 1.8E+02 1.8E+02 1.7E+02 1 134 3.2E+01 2.6E+01 2.1E+01 > I.135 1.4E+02 1. 41:.tv 2 1.3E+02
- O rotal Iodine 5.2E+02 5.0E+02 4.7E+02 V ,
I.131 Dose 1.6E+02 1.6E+02 1.5E+02 . Equivalent Kr.83m 2.8E+00 2.9E+00 3.0E+00 - Kr.85m 3.3E.01 3.1E.01 2.9E.01 Kr.85 2.2E 02 2.2E.02 2.1E.02 Kr 87 2.3E 01 2.0E.01 1.7E.01 ' Kr.88 6.7E.01 6.2E 01 5.7E.01 Xe.133 5.3E+00 5.4E+00 5.5E+00 Xe.135m 2.2E+01 2.1E+01 2.1E+01 Xe.135 1.6E+01 1.8E+01 1.9E+01 Total Noble 4.7E+01 4.8E+01 5.0E+01 Gas , i Note: Reactor coolant sample dose rates are provided in Section 9.5.1. I h, ( w) . l l l
Rsv. O Pag? 9.4.1 4 VERMONT YANKEE NUC1. EAR POWER STATION l O EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 i i i 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uC1/ml) l Time Isotope 1330 1345 1345 1400 )
. ......... i l
1 131 9.2E+01 9.0E+01 ' I.132 5.3E+01 4.8E+01 1 133 1.7E+02 1.6E+02 l 1 134 1.7E+01 1.4E+01 l I.135 1.2E402 1,2E402 Total Iodine 4.5E+02 4.3E+02 I.131 Dose 1.5E+02 1.5E+02 Equivalent O) \-- Kr.83m 3.1E+00 3.1E+00 Kr.85m 2.8E.01 2.6E.01 j Kr.85 2.1E.02 2.1E.02 i Kr.87 1.5E.01 1.3E.01 ) Kr.88 5.3E.01 4.9E.01 Xe.133 5.7E+00 5.6E+00 i Xe.135m 2.0E+01 1.9E+01 1 Xe.135 2.1E+01 2.3E+01 l Total Noble 5.1E+01 5.2E+01 1 Cas l i l Note: Reactor coolant sample dose rates are provided in Section 9.5.1. Post 1400 values continue to decline steadily with time, i O
i 6 t 1 1 4 i i 4 . i, i e VERMONT YANKEE NUCLEAR POWER STATION j 5 EMERGENCY RESPONSE PREPAREDNESS EXERCISE .:
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Rev. O Page 9.4.2 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uci/cc)
............ 4..........................................
Time Isotope Prior to 1130 1130 1145 1145 1200 I.131
- 3.1E.01 3.0E.01 1 132
- 3.2E.01 2.9E.01 1 133
- 6.0E.01 5.8E.01 1 134
- 2.7E.01 2.2E.01 1 135
- 5.1E.01 4.9E.01 Total Iodine
- 2.0E+00 1.9E+00 1 131 Dose
- 5.3E.01 5.2E.01 Equivalent Kr 83m 2 1.3E+01 1.2E+01 Kr.85m
- 2.5E+01 2.4E+01 Kr.85
- 1.4E+00 1.4E+00 Kr.87
- 2.9E+01 2.5E+01 Kr.88
- 5.8E+01 5.3E+01 Xe.133
- 2.5E+02 2.5E+02 Xe.135m
- 3.4E+01 3.2E+01 -
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- 6.9E+01 7.1E+01 Total Noble
- 4.8E+02 4.7E+02 Gas
- Below MDA at specified time.
Note: Primary containment sample dose rate provided in Section 9.5.2.
l l I l Rev. 0 l O-s- Page 9.4.2 2 I VERMONT YANKEE NUCLEAR POWER STATION , i EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 ] 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA-
..................................... I i
A. Primary Containment Air Activity Concentrations (uCi/cc) I Time , Isotope 1200 1215 1215 1230 1230 1245 ' I.131 3.0E.01 2.9E.01 2.9E.01 1 132 2.7E.01 2.4E 01 2.2E.01 1 133 5.7E.01 5.6E 01 5.4E.01 1 134 1.8E.01 1.4E 01 1.2C 01 1 1 135 4.7E.01 4.5E 01 4.3E.01 l
..... ....... ....... ....... ) /~ i Total Iodine 1.8E+00 1.7E+00 1.6E+00 k/
m I I 131 Dose 5.1E.01 4.9E.01 4.8E.01 , Equivalent ) Kr 83m 1.2E+01 1.1E+01 1.1E+01 Kr.85m 2.2E+01 2.1E+01 2.0E+01 Kr.85 1.4E+00 1.3E+00 1.3E+00 - Kr.87 2.2E+01 1.9E+01 1.6E+01 Kr.88 4.9E+01 4.6E+01 4.2E+01 . Xe.133 2.4E+02 2.4E+02 2.4E+02 Xe.135m 3.1E+01 3.0E+01 2.9E+01 Xe.135 7.2E+01 7.3E+01 7.4E+01 , Total Noble 4.5E+02 4.4E+02 4.3E+02 ! Cas i i Note: Primary containment sample dose rate provided in Section 9.5.2. L ie I
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i l l l 1 Rev. O ( Page 9.4.2 3 VERMONT YANKEE NUC1. EAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 l 9.4.2 J PRIMARY CONTAINMENT AIR ACTIVITY DATA I A. Primary Containment Air Activity Concentrations (uci/cc) Time 1 Isotope 1245 1300 1300-1315 1315 1330 I I.131 2.8E.01 2.8E.01 2.7E.01 I.132 2.0E.01 1.9E.01 1.7E 01 1 133 5.3E.01 5.2E.01 5.0E 01 1 134 9.4E.02 7.6E.02 6.1E.02 I.135 4.1E 01 4.0E 01 3.8E.01 i Total Iodine 1.5E+00 1.5E+00 1.4E400
}
I.131 Dose 4.7E.01 4.6E.01 4.5E 01 l Equivalent j i J Kr.83m 1.0E+01 9.9E+00 9.4E+00 Kr.85m 1.9E+01 1.8E+01 1.7E+01 Kr.85 1.3E+00 1.3E+00 1.2E+00 i Kr 87 1.4E+01 1.2E+01 1~.0E+01 ) Kr.88 3.9E+01 3.6E+01 3.4E+01 ; Xe.133 2.3E+02 2.3E+02 2.2E+02 i Xe 135m 2.8E+01 2.8E+01 2.7E+01 j Xe.135 7.5E+01 7.6E+01 7.6E+01 ; J Total Noble 4.2E+02 4.1E+02 3.9E+02 Cas ; I
.............. -)
Note: Primary containment sample dose rate provided in Section 9.5.2. [ \ N -] ,
R3v. O Pags 9.4.2 4 VERMONT YANKEE NUCLEAR POUEh % ATION EMERCENCY RESPONSE PREPAREDhiciS EXERCISE 1990 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uCi/cc) Time Isotope 1330 1345 1345 1400 1 131 2.7E.01 2.7E.01 1 132 1.5E.01 1.4E.01 1 133 4.9E.01 4.8E 01 1 134 4.9E 02 4.0E 02 1 135 3.6E.01 3.5E.01 Total Iodine 1.3E+00 1.3E+00 1 131 Dose 4.4E 01 4.3E.01 Equivalent Kr 83m 8.9E+00 8.5E+00 Kr.85m 1.6E+01 1.5E+01 Kr.85 1.2E+00 1.2E+00 Kr.87 8.6E+00 7.4E+00 Kr.88 3.1E+01 2.9E+01 Xe.133 2.2E+02 2.2E+02 Xe.135m 2.6E+01 2.6E+01 Xe 135 7.7E+01 7.7E+01 Total Noble 3.9E+02 3.8E+02 Cas l 6 Note: Primary containment sample dose rate _provided in Section 9.5.2. Post 1400 values continue to decline steadily with time.
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R:v. O Pego 9.4.3 1 VERMONT YANKEE NUCLEAR POWER STATION rN EMERGENCY RESPONSE PREPAREDNESS EXERCISE ( ) 1990 > x_/ 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA , A. Reactor Building Air Activity Concentrations (uci/cc). , Elevations 252' and 280' . See Notes Below* , Time Isotope Prior to 1130 1130 1145 1145 1200 , 1 131 ** 1.6E.04 4.6E 04 1 132 ** 1.6E.04 4.5E.04 1 133 ** 3.0E.04 8.9E.04 1 134 ** 1. 4 E. 04 3.4E.04 1 135 ** 2.6E.04 7.5E.04 Total Iodine ** 1.0E.03 2.9E 03 I 131 Dose ** 2.7E.04 7.9E 04 Equivalent Kr.83m ** 6.4E.03 1.8E.02 Kr.85m ** 1.3E.02 3.6E.02 7- Kr 85 ** 7.1E.04 2.1E 03 Kr 87 ** 1.5E.02 3.8E.02
- Kr.8L ** 2.9E.02 8.1E.02 Xe.133 ** 1.3E.01 3.4E 01 Xe.135m ** 1.5E.02 3.1E.02 Xe.135 ** 3.5E-02 1.0E.01 Xe 133m ** 3.7E-03 1.1E.02 Total Noble ** 2.5E.01 6.6E.01 Gas
- Notes:
- 1. Reactor Building Elevations 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 are provided in Section 9.5.3.
** Activity is below the MDA of the plant gamma ray spectrometer at this time, l
i f N ,l l 1 l I I
Rav. O Pcge 9.4.3 2 { VERMONT YANKEE NUCLEAR PO'.'ER STATION Q EMERGENCY RESPONSE PREPAREDNESS EXERCISE Q' 1990 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA A. Reactor Building Air Activity Concentrations (uCi/cc). Elevations 252' and 280' . See Notes Belov* ' Time Isotope 12 A ): . i m 1230 1230 1245 1245 1300 1 131 7.6: Oc ' 9 tA ' 1.3E.03 1.6E 03 1 132 6,8E. '4 h 1.0E.03 1.1E 03 1 133 1.4E.(' e M 's 2.5E 03 2.9E.03 I.134 4.5E.04 *" ,4 5.3E.04 5.2E.04 1 135 1.2E.03 .4E.u3 2.0E.03 2.3E 03 Total Iodine 4.5E.03 6.0E.03 7.3E 03 8.4E 03 1 131 Dose 1.3E.03 1.7E 03 2.2E 03 2.6E.03 Equivalent n Kr 83m 2.8E 02 3.6E.02 4.3E.02 4.8E.02 Kr.85m 5.7E.02 7.5E.02 9.1E 02 1.1E.01 /) 's/ Kr.85 .3.4E.03 4.7E.03 6.0E.03 7.2E.03 Kr.87 5.5E 02 6.5E.02 7.2E.02 7.5E.02 Kr.88 1.3E 01 1.6E.01 1.9E.01 2.2E 01 Xe.133 6.1E.01 8.4E.01 1.1E+00 1.3E+00 Xe.135m 3.9E 02 4.2E.02 4.2E.02 4.2E 02 Xe.135 1.7E.01 2.4E.01 3.0E.01 3.7E.01 Xe.133m 1.8E.02 2.5E.02 3.1E.02 3.7E 02 Total Noble 1.1E+00 1.5E+00 1.9E+00 2.2E+00 Cas
- Notes:
- 1. Reactor Building Elevation 303' and 318' . divide concentrations by a factor of 2.
- 2. Reactor Building Elevation 345' . divide concentrations by a tactor of 5.
- 3. Reactor Building air sample dose rates provided in Section 9.S.3.
O
a
-m Rev. O Page 9.4.3 3 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.4.3 REACTOR BUILDINC AIR ACTIVITY DATA A. Reactor Building Air Activity Concentrations (uct/ce). 1 Elevation 252' and 280' . See Notes Below*
Time Isotope 1300 1315 1315 1330 1330 1345 1345 1400 1 131 1.7E 03 1.7E.03 1.6E.03 1.5E 03 1 132 1.2E.03 1.1E 03 8.4E.04 7.6E.04 1 133 3.2E 03 3.1E.03 2.8E.03 2.8E.03 1 134 5.1E 04 4.6E 04 2.4E 04 1.9E.04 I 135 2.4E 03 2.4E.03 2.1E.03 2.0E.03 n ....... ....... ....... ....... ( Total Iodine 9.0E.03 8.7E.03 7.6E 03 7.2E.03 1 131 Dose 2.8E.03 2.8E.03 2.6E 03 2.5E.03 Equivalent Kr 83m 5.1E.02 4.8E.02 3.4E 02 3.0E.03 Kr.85m 1.1E.01 1.1E 01 9.1E.02 8.6E.02 Kr.85 7.7E.03 7.7E 03 7.2E.03 7.0E.03 Kr 87 7.6E 02 7.0E.02 4.4E.02 3.8E.02 i Kr.88 2.3E 01 2.2E.01 1.7E.01 1.6E 01 Xe.133 1.4E+00 1.4E+00 1.3E+00 1.2E+00 Xe.135m 4.2E 02 3.0E.02 3.9E.03 2.1E.03 Xe.135 4.0E.01 3.9E.01 3.5E.01 3.3E.01 Xe.133m 4.0E.02 4.0E.02 3.7E.03 3.6E.02 Total Noble 2.4E+00 2.3E+00 2.0E+00 1.9E+00 Cas
- Notes:
- 1. Reactor Building Elevation 303' and 318' . divide concentrations by a factor of 2.
- 2. Reactor Building Elevation 345' . divide concentrations by a
! factor of 5. O 3. Reactor Building air sample dose rates provided in Section 9.5.3. [ d 4. Post 1400 values continue to decline steadily with time.
-1 i
i 1 i ( ! i G l a i-VERMONT YANKEE NUCLEAR POWER STATION l 1 EMERCENCY RESPONSE PREPAREDNESS EXERCISE j3 i i 1990 -. ,l 1 i
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I l Rev. O Page 9.5.1 1 VERMONY YANKEE NUCLEAR POWER STATION 3 EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1990 9.5.1 Reactor Coolant Sample Dose Rates A. Gas Samples Unshielded (mR/hr per cc)* Shielded (1 in. lead in mR/hr per cc)* ;- Time Contact 1 ft Contact 1 ft Prior to 1130 1.4E.02 9.6E.05 1.7E.04 1.2E-06 3
.'130 1145 5.2E+00 3.6E.02 6.4E.02 4.5E.04 5 1
1.45 1200 f5.7E+00 6.0E.02 1.1E.01 7.5E-04 1:00-1215 1.1E+01 7.4E.02 1.3E.01 9.3E.04
./
1'!15 1230 1.2E+01 8.4E.02 1.5E.01 1.1E.03 1230 1245 1.3E+01 9.0E.02 1.6E.01 1.1E 03 ! 1245 1300 1.4E+01. 9.4E-02 1.7E.01 1.2E-03 / 1300-1315 1.4E+01- 9.6E-02 1.7E.01 1 2E.03 o 1315 1330 1.5E+01 1.0E.01 1.8E.01 1.3E.03 1330 1345 1.5E+01 1.0E.01 1.8E-01 1.3E.03 1345-1400 1.SE+01 1.0E.01 1.8E.01' 1.3E.03 Post 1400 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. ;
i 1
I Rev. O Page 9.5.1 2 VERMONY YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 t 9.5.1 Reactor Coolant Sample Dose Rates , B. Liquid _(Icdine) Unshielded'(mR/hr per cc)* Shielded (1 in- lead in mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 1130 1.5E-02 1.0E 04 1.9E.04 1.3E.06 1130 1145 5.4E+02 3.7E+00 6.7E+00 4.6E.02 1145-1200 5.1E+02 3.5E+00 6.3E+00 4.3E 02 1200 1215 4.8E+02 3.3E+00 5.9E+00 4.0E.02 1215 1230 4.5E+02 3.1E+00 5.7E+00 3.8E.02 l 1230 1245 4.3E+02 3.0E+00 5.4E+00 3.6E 02 1245 1300 4.1E+02 2.8E+00 5.1E4 90 3.4E.02 1300 1315 3.9E+02 2.7E+00 4.9E+00 3.3E.02 1315 1330 3.7E+02 2,5E+00 4.6E+00 3.1E.02 1330 1345 3.5E+02 2.4E+00 '4.4E+00 3.0E.02 1345 1400 3.4E+02 2.3E+00 4.2E+00 2.8E.02 Post 1400 Values. continue to decline steadily with time. f i
- Notes: Values must be multiplied by the sample volume in milliliters for liquid samples to cbtain the sample dose rate in mR/hr.
4 i,
Rev. 0
-Page 9.5.2 1.
VERMONY YANKEE NUCLEAR Pok'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.5.2 Primary Containment Sample Dose Rates A. Cas Samples Unchielded (mR/hr per cc)* Shielded (1 in. lead in mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 1130 As Read . As Read As Read As Read 1130 1145 1.4E+02 9.6E.01 1.7E+00 1.2E.02 1145 1200 1.4E+02 9.4E.01 1.7E+00 1.2E.02 1200 1215. 1.3F+02 9.0E.01 1.6E+00 1.1E-02 1215 1230 1.3E+02 8.8E.01 1.6E+00 1.1E.02 1230 1245 1 2E+02 8.6E.01 1.5E+00 1.1E.02 1245 1'300 1.2E+02 8.4E.01 1.5E+00- 1.1E.02 1300 1315 1.2E+02 8.2E.01 1.5E+00 1.0E.02 1315.'1330 1.1E+02 7.6E.01- 1.4E+00 9.8E.03 1330 1345 1.1E+02 7.8E.01 1.4E+00 9.8E.03 1345 1400 1.1E+02 7.6E.01 1.4E+00 9.5E.03 Post 1400 values continue to dechne steadily with time.
- Notes: Values trust be multiplied by_ the sample volume in cubic centimeters for gas samples to obtain the sample dose rate in mR/hr.
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1 Rsv. 0-Pass 9.5.3 1 l VERMONY YANKEE NUCLEAR PuVER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.5.3 Reactor Building Air Sample Dose Rates (Iodine Cartridge only) Elevation 252' and 280' . See Notes Below Unshielded (mR/hr per cc)* Shielded (1 in lead in mR/hr pu c c)* < Time Contact i ft Contact 1 ft Prior to 1130 As Read- As Read As Read As Read 1130 1145 7.8E.04 5.4E.06 9.7E.06 6.8E.08 1145 1200 2.3E.03 1.6E.05 2.8E.05 2.0E.07 1200 1215 3.5E.03 2.4E.05 4.4E.05 3.0E.07 ' 1215 1230 4.7E.03 3.2E.05 5.8E.05 4.1E.07 1230 1245 5.7E.03 3.9E 05 7.1E.05 4.9E.07 1245 1300 6.5E.03 4.5E.05 8.2E.05 5.7E.07 i 1300 1315 7.0E.03 4.8E.05 8.7E.05 6.1E.07 1315 1330 6.8E.03 4.7E.05 8.5E.05 5.9E.07 1330 1345 5.9E.03 4.1E.05 7.4E.05 5.1E.07 1345 1400 5.6E.03 3.9E 05 7.0E.05 4.9E-07 Post 1400 values continue to decline' steadily with time.
- Notes: 1. Values must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rate in mR/hr.
- 2. Reactor Building Elevations 303' and 318' . divide dose rates by a factor of 2.
- 3. Reactor Building Elevation 345' . divide dose rates by a factor of 5.
% =
1 l R2v. O Pegs 9.5.4 1 i VERMONY YANKEE F" CLEAR POWER STATION EMERGENCY RESPONSE.iREPAREDNESS EXERCISE 1990 f 9.5.4 Plant Vent Stack Sample Dose Rates A. Gas (Crab Sample)
................. j Unshielded (mR/hr per cc)* Shielded (1 in. 1 : mR/hr per cc)* !
Time Contact- 1 ft Contact 1 ft , Prior to 1135- As Read As Read As Read As Read 1135-1145 2.0E.03 1.4E.05 2.4E.05 1.7E.07 ; 1145 1200 5.7E.03 4.0E.05 7.0E.05 5.0E.07 1200 1215 9.1E.03 6.4E.05 1.1E.04 8.1E.07 1215 1230 1.2E.02 8.6E.05 1.5E.04 1.1E.06 1230 1245 1.5E.02 1.0E.04 1.8E.04 1.3E.06 1245 1300 1.8E.02 1.2E.04 2.2E-04 1.6E-06 1300-1315 1.8E-02 1.3E 04 2.3E.04 1.6E.06 h 1315 1330 1.8E.02 1.3E.04 2.3E.04 1.6E.06 1330 1345 1.6E.02 1.1E.04 2.0E.04 1.4E.06 1345 1400 1.5E.02 1.0E.04 1.8E.04 1.3E.06 Post 1400 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. 1
** Plant vent stack sample dose rates remain constant from 0700 1130 given the same sample volume.
Rev. O Pcg2 9.5.4 2 VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.5.4 Plant Vent Stack Sample Dose Rates B. Air Sample (Iodine Cartridge) Unshielded (mR/hr per ec)* Shielded (1 in lead in mR/hr per cc)* Time Contact. 1 ft Contact 1 ft Prior to 1135 As Read As Read As Read As Read 1135 1145- 1.2E.06 8.0E 09 1.4E.08 1.0E.10 1145 1200 3.2E.06 2.3E.08 4.0E.08 2.8E.10 1200 1215 5.0E.06 3.5F.08 6.2E.08 4.4E.10 17.15 1230 6.6E.06 4.6E.08 8.2E.08 5.8E-10 1230 1245 7.7E.06 5.4E.08 9.6E.08 6.7E.10 1245 1300 9.2E.06 6.4E-08 1.2E.07 8.1E-10 1300 1315 1.0E.05 7.0E.08 1.2E.07 8.8E.10 1315 1330 1.0E.05 7.0E.08 1.2E.07 8.8E.10 1330 1345 8.4E 06 5.9E.08 1.1E.07 7.4E.10 1345 1400 7.7E-06 5.4E.08 9.6E.08 6.7E.10 Post 1400 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 re.tes remain constant from 0700 1130 given the same sample volume..
-I i
Rev. O i Page 9.5.4 3 . i i VERMONY YANKEE NUCLEAR POWER STATION
- EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.5.4 Plant Vent Stack Sample Dose Rates 1
C. General Area Exposure Rates at Stack (mR/hr) { b Time . At Stack Door Inside Prior to 1135 As read
- As Read
- 1135 1145 10 10 1145 1200 20 20 1200 1215 35 35 1215 1230 45 45 1230 1245 50 50
~
1245 1300 60 60-1300 1315 60 60 1315 1330 55 55 1330 1345 50 50 1345 1400 45 45 Post.1400- Dose Rates Continue to Decline
- Background as read on survey meter.
l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 i 9.6 PLANT VENT STACK RELEASE DATA
?
EQIE: If the stack filter paper is analyzed, it will be assumed that the , gamma isotopic results will show all radionuclides below the MDA of the multi-channel analyzer. An RM-14/HP-210 survey of filter will show no counts above background. 0
_ - = _ . . .- . - .. .. l l Rev. O Page 9.6 1 VERMONT YANKEE NUCLEAR POWER STATION- 'l EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1990 l l 1 9.6 P! ANT VENT STACK RELEASE DATA - A. Plant Vent Stack Activity Release Concentrations (uci/cc) Time Isotope Prio'r to 1135 1135 1145 1145 1200 I.131- 3.3E.13 2.3E.07. 6.7E.07 1 132 4.8E.13 2.4E-07 -6.5E.07 I-133 7.5E.13 4.4E.07 1.3E-06 1 134 6.6E.13 2.0E.07 4.8E.07 I.135 6.3E.13- 3.8E.07 .1.1E.06 Total Iodine 2.9E-12 1.5E.06 4.2E-06 I-131 Dose 6.1E.13 3.9E.07 1.1E.06-l p Equivalent l' - Kr.83m ** 1.9E.04 5.2E.04 Kr-85m ** 3.7E.04 1.0E.03 Kr-85 ** 2.1E.05 6.1E.05 Kr.37 ** 4.3E.04 1.1E.03 Kr-88 ** 8.5E.04' 2.3E.03 Xe-133 ** 3.7E.03 1.1E.02 Xe-135m ** 4.2E.04 9.1E.04 Xe.135 ** 1.0E.03 3.0E.03. Total Noble ** 6.9E.03 2.0E.02 Gac I
- Activity concentrations (in uCi/ce) may be converted to activity release rates (uci/sec) by multiplying by the assumed stack flow l rate of.4.9E7 cc/sec. l l
. - *
- Noble gas release rates are minimal at this time and below MDA of ;
the multi. channel analyzer. l Note: Plant vent stack sample dose rates provided in Section 9.5.4.
/~N v ) \
l l
l l
.O \j Rev. 0 Page 9.6 2 .
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1 1990 l l 9.6: PLANT VENT STACK RELEASE DATA 1 I
^1 A. Plant Vent Stack Activity Releace Concentrations (uCi/cc) ]
Time Isa; ope 1200 1215 1215 1230 1230 1245 1245 1300 1 I 131 1.1E 1.5E.06 1.9E.06 2.3E.06 1.3E.06 1.5E 06 1.6E.06 I I.132 9.8E.07 I-133 2.1E.06 2.8E.06 3.5E 06 4.2E.06 l I.134 6.5E.07 7.3E.07 7.6E.07 7.5E.07- l I.135 1.7E.06 2.3E.06 2.8E 06. 3.3E.06 l
..... ....... ....... ....... ....... i l l l Total Iodine 6.5E-06 8.6E-06 1,0E.05 1.2E-05 I I.131 Dose 1.8E-06 2.5E.06 3.25 06 3.8E-06 i
l l)T (-, Equivalent ! l l l Kr.83m 8.0E.04 1.0E.03 '1.2E.03 1.4E.03 l l Kr.85m 1.6E-03 2.2E.03 2.6E.03 3.0E.03 ' l Kr-85 9.9E.05 1.4E.04 .l.7E 04 2.1E.04' l Kr-87 1.6E-03 1.9E.03 2.1E.03 . 2. 2 E.~0 3 . , Kr.88 3.6E.03 4.7E.03 5.- 5 E- 03 6.3E.03 l Xe.133 1.8E-02 2.5E-02 3.1E-02 .3.7E.02 1
- Xe.135m 1.1E-03 1,2E.03 1.2E 03 1.2E-03 l l Xe-135 4.9E.03 6.8E-03 8.7E.03 1.1E.02 I
\
l Total Noble 3.2E.02 '4.3E-02 '5.2E.02 6.2E.02 . Cas I l I l l
- Activity concentrations (in uCi/cc may be converted to activity l- release rates (uci/sec) by multiplying by the assumed stack flow ,
l' rate of 4.9E7 cc/sec. 'l
** Noble gas release rates are minimal at this tina and below MDA of the multi-channel analyzer.
Note: Plant vent stack sample dose rates provided in Section 9.5.4. r l I l l l l l' ~ . ,, , .,. ,
i l l Rev. O Page 9.6-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 l , t i 9.6 PIANT VENT STACK RELEASE DATA i A. Plant Vent Stack Activity Release Concentrations (uC1/cc) i' Time Isotope '1300-1315 1315 1330 1330 1345 1345 1400 1-131 2.4E.06 2.4E.06 2.3E.05 2.2E.06 i 1 132 1.7E.06 1.6E.00 1.2E.06 1.1E.06 I.133 4.5E.06 4.5E.06. 4.1E.06 4.0E.06 -i 1 134 7.3E.07 6.6E.07 3.4E.07 2.7E.07. I.135 3.5E.06 3.4E.06 3.0E.06 2.9E.06 Total Iodine 1,3E.05 1.3E.05 1.1E.05 1.0E.05 l l I.131 Dose 4.0E.06 4.0E.06 3.7E.06 3.6E.06 Equivalent Kr.83m 1.5E-03 1.4E.03 9.7E.04 8.7E.04 Kr 85m 3.2E 03 3.lE.03 2.6E.03 2.5E.03 j Kr 85 2.2E.04 2.2E.04 2.1E.04 2.0E.04 i Kr.87 2.2E.03 2.0E.03 1.3E.03 1.1E.03 Kr-88 6.6E.03 6.3E.03 4.9E.03 4.5E.03 Xe.133 4.0E.02 3.9E.02 3.7E.02 3.6E.02 Xe 135m 1.2E.03 8.8E.04 1.5E.04 1.1E.04 Xe 135 9.3E-03 1.1E.02 1.0E.02 7.0E.03 Total Noble 6.4E-02 6.4E.02 5.7E-02 5.2E.02 Cas Pc st 1400 values continue to decline steadily with time.
.............. -e
- 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 mir.imal at this time and below KDA of the multi. channel analyzer.
Note: Plant vent stack sample dose rates provided in Section 9.5.4. O
l O i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 . 9.7 0FF-SIJE 510NITORING MAPS AND. DATA O 4 9 i v s _ J
l l Rsv. O i 4/6/90 l Page 9.7-1 O VERMONT YANKEE NUCLEAR POWER STATION ; l EMERGENCY RESPONSE PREPAREDNESS EXERCISE-1990 , 1 9.7 0FF-SITE MONITORIhlt MAPS AND DATA-Off-site plume centerline whole body dose rates and radioiodine concentrations have been estimated as a function of time and distance from the site using a variable trajectory dose ass 6ssment model. Geographical representations of the plume are provided in this. package for each 15 minute average of meteorological conditions, ! starting at 1135. During the exercise, off-site monitoring team ; observers will use the information contained in this package tr e provide field monitoring teams with radiological data for various times and locations. During the exercise, the Survey Team Coordinator (s) will direct off-site monitoring teams to monitor locations relative to the meteorological conditions postulated for the exercise scenario. Use Figures 9.7-1 through 9.7-11 to provide survey results to the off-site monitoring teams. Figures 9.7-1 through 9.7-11 depict the plume conditions at various times throughout the exercise. Tbsse figur'es represent a plume width which is equivalent to a 3-sigma value of the centerline conditions. Since the figures show a plume width relative to the centerline, gamma dose rates can be estimated using the color coded maps and off-centerline value provided. Radiological data for other locations within the plume can be calculated as a function of the centerline vad outer edge values at a given segment / distance. Radiological data has been provided for each particular segment at centerline.. Dose and count rates for locations between two segments can be estimated as a function of the values at those segments. 2501e
Rsv. 0 4/6/90 Page 9.7-2 O Prior to the exercise, training will be provided to the off-site I monitoring team controller / observers on the use of this package. The following are specific instructions which off-site monitoring team l controller / observers should use during the exercise:- l l 1. As off-site monitoring teams are designated, check that Procedure Number OP-3510 is followed by team members. This will include the l initial equipment r. heck. t i
- 2. While enroute.to the assigned moni bring location, or while traversing the plume, use the attached figures and tables to issue appropriate radiological ~ data.-
- 3. Attempt to estimate the team's accrued exposure as a function of their continual job assignment. Do not issue pocket dosimeter j results to team members, unless they actually simulate checking their dosimeter reading. The pocket desimeters in tLe kits have a range of -
0-500 mR, which are subdivided into 20 mR intervals. ~ Attempt to provide realistic values! 0-5 R dosimeters may be provided. Always check to ask them the range.
- 4. Ask the off-site monitoring teams what equipment they have available 1
- or their use. Ask them the scales associated with the equipment;-
l log these answers to ensure that you do not provide them with data; that exceeds the range of their equipment. If, at any point during - the exercise, a situation occurs where the upper range of their equipment is exceeded, then issue them an "off-scale high" value.
- 5. If the off-site monitoring team stops to take an air =aample: l
- a. Report the appropriate whole body dose levels at.that location.
l g 2501e f 4
+ -* . _ . . . , . < . - -
w Rsv. 0 4/6/90 Page 9.7-3
]\-'# If an RM-14/HP-210 is left on to track the plume while driving b.
the meter count rate can be estimated using the following relationships: (1) 3,500 cpm on the RM-14/HP-210 is equivalent to approximately 1.0 mR/hr. Therefore, 14 mR/hr will cause the RM-14/HP-210 ; to read "off-scale high." (2) The upper range of RM-14/HP-210 = 50,000 cpm.
- 6. Whenever a team takes a " ground level" survey, the results should be the same as the we.i:t-high survey..
- 7. The Vtrmont Yankee off-site monitoring teams will substitute a charcoal sample instead of a silver zeolite sample for the purposes of this e.terc#.se. All data will be given from-the tasks provided as-though silver zeolite samples were being utilized.
- 8. Cer.tain 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 (see maps), assume the open window reading.is three times the. gamma (closed. window) line dose rate reading given on the map.
- 9. Air sample assumptions used to calculate the count rates (net cpm) l
! for the silver zeolite cartridges with the RM-14 instrument. Formula: Cone I-131 in uCi/cc = (net epm) (4.5 E-10 uCi-1/dpm-cc) (E)(V)(T) 2501e bu
, t
. - . . - . -- - - . . . . . .. . ~ - ....
Rsv. 0 4/6/90 Page 9.7-4
- (d where - 1 l
E = efficiency (0.025 for RM VY). l V = flow rate in liters per minute (VY flow rate - 10 1pm). T = sample collection time in minutes'(VY sample time - 10 minutes). l l therefore i l Cone I-131 in uci/cc = (^et epm) (1.8 E-10) l t or (Cone I-131 in uC1/cc) (5.6 E+09) = net cpm
*** Remember this assumes a sample volume of 100 liters and a RM-14 efficiency of 0.025.*** .A EDIE: THE PLUME PLOT FIGURES ARE GRAPHIC REPRESENTATIONS OF ATMOSPHERIC -U DISPERSION. THE THREE-DIMENSIONAL PLUMES VARY IN TIME AND SPACE. A SIMIIAR VERSION OF THE FIGURES OVERLAYED ON A LARGER FIELD SURVEY MAP WILL BE USED TO ASSIST CONTROLLERS IN INTERPRETATING DATA.
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, VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 10.0 METEOROLOGICAL DATA l
l O
, 2156e
- . . -.=, , . . - - - . . - . - - , , ., --
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Rsv. 1 Page 10.1-1 VERMONT YAhKc,E NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 10.1 ON-SITE METEOROLOGICAL DATA , ,, 06:15-0711Q Iisc Q1115 06:30 06:45 07:00 07:15 07:30 LOWSAV AVG LOWER SPEED MPH 5.8 5.4 4.4 2.8 2.5 3.1 UPWSAV AVG UPPER SPEED MPH 6.2 6.0 6.4 5.6 6.2 6.4 LOWDAV AVG LOWER DIR DEGS 360 4 15 10 355 350 LOWDSD AVG LOWER DIR SIGMA 12 20 20 59- 41 27 UPWDAV AVG UPPER DIR DEGS 345 350 349 348 328 330 UPWDSD AVG UPPER DIR SIGMA 17 24 22 18 40 37 LOTTAV AVG LOWER TEMP DEGS (F) 51.5 51.8 52.4 53.4 55.0 55.3 LODTAV AVG LOWER DELTA T DEGS (F)* 0.0 0.1 -0.2 -0.7 -1.4 -1.1 UPDTAV AVG UPPER DELTA T DEGS (F)* 0.1 0.1 -0.3 -0.6 -1.4 -1.2 SOLRAV AVG SOLAR RAD LANGS 0.16 0.25 0.19 0.36 0.45 0.51 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00
) 07:45-09:15 Ilme 1
07:45 08:00 08115 08110 08:45 09:00 09:15 LOWSAV AVG LOWER SPEED MPH 2.2 2.7 3.2 2.7 2.7 3.1 3.6 UPWSAV AVG UPPER SPEED MPH 5.6 6.0 5.8 5.4 5.4 6.0 5.1 LOWDAV AVG LOWER DIR DEGS 330 345 340 350 355 350 2 LOWDSD AVG LOWER DIR SIGMA 39 49- 31 70 47 -35 32 UPWDAV AVG UPPER DIR DEGS 325 323 339 341 '47 355 340 UPWDSD AVG ~ UPPER DIR SIGMA 28- .38 24 31 31 30 22 LOTTAV AVG LOWER TEMP DEGS (F) 55.6 57.7 60.0 61.5 63.4 65.4 66.6 LODTAV AVG LOWER DELTA T DEGS (F)* -1.1 -1.5 -1.7 -1.4 -1.5 -1.7 -1.4 UPDTAV AVG UPPER DELTA T DEGS (F)* -0.8 -1.5 -1.9 -1.4 -1.5 -1.6 -1.2 SOLRAV AVG SOLAR RAD LANGS 0.57 0.64 0.71 0.78 0.84 0.90 0.95 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CNOTES:
- 1. The height differential (Ah) for the lower delta temperature on the primary tower is-165 feet.
- 2. The height differential (Ah) for the upper delta temperature on the primary tower is 262 feet.-
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Rsv. 1 Page 10.1-2 Q'
\ - VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE
. 1990 .
10.1 ON-SITE METEQROLOGICAL DATA 09:30-1113h IlmA 09:30 09:45 10:00 10:15 10:30 1Q1p5 11:00 11:15 11:30 LOWSAV AVG LOWER SPEED MPH 4.9 4.0 3.0 4.6 5.3 6.6 3.8 2.9 UPWSAV AVG UPPER SPEED MPH - 545 5.4 4.6 3.7 5.7 8.1 8.7 6.9 6.2 LOWDAV AVG LOWER DIR DEGS 5 10 9 12 15 16 13 306 309 17 19 19 20 20 29 2) 39 24
*LOWDSD AVG LOWER DIR SICMA UPWDAV AVC UPPER DIR DEGS 350 345 340 342 330 332 326 319 310 UPWDSD AVG UPPER DIR SIGMA 17 15 14 16 17 14 21- 25 13 LOTTAV AVG LOWER TEMP DEGS (F) 67.2 68.4 69.3 71.0 72.5 73.8 74.4 74.9 75.6 LODTAV AVG LOWER DELTA T DEGS (F)* -1.2 -1.5 -1.6 -1.8 -1.7 -1.7 -1.9- -1.7 -2.1 UPDTAV AVG UPPER DELTA T DECS (F)* -1.1 -1.5 -1.7 -1.9 -1.7 -1.9 -2.1 -1.9 -2.3 SOLRAV AVG SOLAR RAD LANGS 1.00 1.05 1.09 1.13 1.17 1.05 1.09 1.8 1.31 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00- 0.00 0.00 t oO Ilms i
t, / 11:45-13:30 1LA5 12:00 12115 12:30 121h5 13100 13:15 13:30 LOWSAV AVG LOWER SPEED MPH 3.1 2.8 3.0 3.6 2.9 3.2 3.9 3.7 UPWSAV AVG UPPER SPEED MPH 6.0 6.1' 6.3 5.7 6.6 6.4 6.2 6.5 LOWDAV AVG LOWER DIR DEGS 322 308 322 308 312 309 304 339 l LOWDSD AVG LOWER DIR SIGMA 34 30 34 l0 24 34 43 24 UPWDAV AVG UPPER DIR DEGS 324 315 320 317 322 305 316 324 UPWDSD AVG UPPER DIR SIGMA 19 17 18 26 18 22 27 17 LOTTAV AVG LOWER TEMP DEGS (F) 75.7 76.5 76.4 76.9 77.2 77.3 77.9 77.5 LODTAV. AVG LOWER DELTA T DEGS (F)* -1.8 -1.6 -1.5 -1.8 -1.9 -1.6 -1.8 -1.7 ,- UPDTAV AVG UPPER DELTA T DEGS (F)* -2.2 -2.3 -2.3 -2.4 -2.2 -2.3 -2.2 -2.2 l SOLRAV AVG SOLAR RAD LANGS 1.27 1.29 1.21 1.21 1.18 1.05 1.19 0.92 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 CH01ES:
- 1. The height differential (Ah) for the lower delta temperature on the primary tower is 165 feet.
- 2. The height differential (Ah) for the upper delta temperature on the primary tower is 262 feet.
e e
Rsv. 1 Page 10.1-3 O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE j 1990 10.1 ON-SITE METEOROLOGICAL DATA 4 13:45-15:00 Ilma 13:45 1h;DD 14:15 14:30 14:45 15:00 . LOWSAV AVG LOWER SPEED MPH 6.2 7.2 7.8 8 .'0 7.5 7.2 UPWSAV AVG UPPER SPEED MPH , 8.3 9.4 9.5 10.0 9.5 10.0 ; LOWDAV AVG LOWER DIR DEGS 313 330 302 306 333 302 LOWDSD AVG LOWER DIR SIGMA 33 28 20 33 24 11 UPWDAV AVG UPPER DIR DEGS 317 325 315 304 320 311 UPWDSD AVG UPPER DIR SIGMA 23 15 11 25 17 11
-LOTTAV AVG LOWER TEMP.DEGS (F) 78.1 78.3 77.9 79.1 78.7 78.0 LODTAV AVG LOWER DELTA T DEGS (F)* -1.5 -1.8 -1.3 -1.9 -1.7 -1.6 UPDTAV AVG UPPER DELTA T DEGS (F)* -2.3 -2.2 -2.2 -2.3 -2.3 -2.4 SOLRAV AVG SOLAR RAD LANGS 1.13 0.96 0.89 1.09 0.99 0.79 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 CNQIES:
( The height differential (Ah) for the lower delta temperature on the primary tower is 165 feet.
- 2. The height differential (Ah) for the upper delta temperature on the primary tower is 262 feet.
)
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' VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 10.2 GENERAL AREA NWS FORECASTS O
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1 Rev. O Page 10.2-1 n\- ' THIS IS A DRILL 10.2 CENERAL AREA NWS FORECASTS 6:00-12:00 - Gantral Area Forecast Mostly sunny today, with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75'F to 80*F. Probability of precipitation less than 10%. A high pressure system centered over Pennsylvania will drift southeastward and slowly weaken during the day. This system will dominate the weather today. ( THIS IS A DRILL 1. l 6e
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Rav. O Page 10.2-2 O- THIS IS A DRII4 i 10.2 GENERAL AREA NWS FORECASTS 12:00-18:00 - General Area Foreeggi Mostly sunny and warm this af ternoon with a high near 80'F. Northwest winds 5 to 10 mph. Mostly clear tonight with a low around 55'F. Winds becoming light and variable. Tomorrow, becoming cloudy with showers. Highs in the mid 70's. Winds becoming south to southwest 10 to 15 mph. O THIS IS A DRILL
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