ML20237C367
| ML20237C367 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 11/20/1987 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| References | |
| NUDOCS 8712210280 | |
| Download: ML20237C367 (314) | |
Text
{{#Wiki_filter:_ _ _ _ O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ; 1987 EXERCISE MANUAL O' l l 1453eno.86 [g ennaih> F
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 TABLE OF CONTENTS Section Page
1.0 INTRODUCTION
l 1.1 Exercise Schedule............................................ 1.1-1 I 1.2 Participating Centers / Agencies............................... 1.2-1 j 1.3 Definitions.................................................. 1.3-1 l 1.4 References................................................... 1.4-1 l 2.0 EXERCISE OBJECTIVES............................................... 2.0-1 , 3.0 EXERCISE GUIDELINES AND SCOPE 3.1 Guidelines................................................... 3.1-1 3.2 Extent of P1ay............................................... 3.2-1 3.3 Simulation List.............................................. 3.3-1 3.4 Player Instructions.......................................... 3.4-1 ()
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3.5 Procedure Execution List..................................... 3.6 Exercise Termination criteria................................ 3.5-1 3.6-1 4.0 CONTROLLER /0BSERVER INFORMATION 4.0-1 4.1 Controller /0bserver Assignments.............................. 4.1-1 4.2 Controller / Observer Exercise Guidance........................ 4.2-1 4.3 Controller /0bserver Comments.................................. 4.3-1 5.0 EXERCISE SCENARIO 5.0-1 5.1 Initial Conditions........................................... 5.1-1 5.2 Narrative Summary............................................ 5.2-1 5.3 Scenario outline............................................. 5.3-1 5.4 Scenario Time Line........................................... 5.4-1 5.5 Detailed Sequence of Events.................................. 5.5-1 6.0 EXERCISE MESSAGES 6.0-1 l 6.1 Command Cards................................................ 6.1-1 6.2 Message Cards................................................ 6.2-1 i 7.0 STATION EVENT DATA 7.1 Events Summary............................................... 7.1-1 g-~g 7.2 Event Mini-Scenarios......................................... 7.2-1
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Rev. 2 9/18/87 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 TABLE OF CONTENTS (Continued) 8.0 OPERATIONAL DATA.................................................. 8.0-1 9.0 RADIOLOGICAL DATA 9.1 Area Radiation Monitors...................................... 9.1-1 9.2 Process Radiation Monitors................................... 9.2-1 9.3 In-Plant Radiation Leve1s.................................... 9.3-1 9.4 Plant Chemistry Data......................................... 9.4-1 9.5 Plant Vent Stack Release Data................................ 9.5-1 9.6 Radiological Sample Dose Rates............................... 9.6-1 9.7 Off-Site Monitoring Team 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 l
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0 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987
1.0 INTRODUCTION
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O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 1.1 EXERCISE SCHEDULE O O 1454e/2.33
Rev. 1 9/18/87 [ Page 1.1-1 V VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 1.1 EXERCISE SCHEDULE A. Controller / Observer Briefing Date: November 24, 1987 Time: 10:00 a.m. Location: Vermont Yankee Information Center
Purpose:
Controller / Observer Briefing on Scenario and b Assignments Attendees: Vermont Yankee and Yankee Atomic Controllers / Observers B. Controller / Observer Plant Tour i Date: Week prior to exercise l Time: As necessary (contact lead controller) Location: Emergency Resprese Facilities and In-Station Areas
Purpose:
Familiarize Controllers / Observers with Affected Areas Attendees: Controllers / Observers (' 1454e/2.33
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t C. NRC Briefing , f, ( Date: s) Time-
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( Location: Vermont Yankee Information Center
Purpose:
NRC Briefing and Review of Exercise Scenario Attendees: NRC Evaluators j D. Exercise Date: Week of November 29, 1987
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Time: Location: Vermont Yankee Emergency Response Centers l
Purpose:
Emergency Response Preparedness Exercise i Attendees: Vermont Yankee Emergency Response Organization, i Controllers / Observers NRC Evaluators, and Yankee I Atomic Engineering Support Center Staff { E. Exercise Debriefing Date: Morning after Exercise Time: To be Announced During or Immediately Following Exercise f ( 1454e/2.33 t
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Purpose:
Exercia,t Del riefing , i l/ } t Attendees: Exercise Coordinator and Controllers N
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1 4 Location: Vermont Yanki? Informaticy Center i i i 3
Purpose:
Utility Self-Critique /NRC Preliminary Findings
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, VERMONT YANKEE NUCLEAR POWER STATION
. EMERGENCY RESPONSE PREPAR"DiiESS EXERCISE 1987 1-
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, 1.2 PARTICIPATING QENTERS/ AGENCIES
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 1.2 PARTICIPATING CENTERS / AGENCIES VERMONT YANKEE NUCLEAR POWER CORPORATION Vermont Yankee Nuclear Power Station: o Control Room (notification and communication functions only) o Technical Support Center (2nd floor of Administration Building) p-s o Operations Support Center (1st floor of Administration Building) o Energy Information Center (Governor Hunt house) Vermont Yankee Training Center: o Simulator Room (Control Room functions - 1st floor of Training Center) o Emergency Operations facility / Recovery Center (1st floo" of Training Center) News Media Center (Dalem's Chalet - Located in West Brattleboro, Vermont) ,m
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1 Rev. 1 10/9/87 Page 1.2-2 YANKEE ATOMIC ELECTRIC COMPANY L Yankee Atomic Corporate Headquarters: h o Engineering Support Center (Framingham, Massachusetts) STATE OF VERMONT _ Vermont Emergency Management Agency (State Response Agencies): o Emergency Operation Center-(Waterbury, Vermont) o Incident Field Office (Dummerston, Vermont) o Department of Health Lab (Burlington, Vermont) Local Emergency Operations Centers (Local Response): o Brattleboro - Brattleboro Town Hall Vernon - Town of Vernon Fire Station
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o o Dummerston - Dummerston Town Office Building
.o Gilford - Gilford Town Fire Department STATE OF NEW HAMPSHIRE New Hampshire Emergency Management Agency (State Response Agencies):
o Emergency Operation Center (Concord, New Iampshire) 1455e/2.32 l t ) $i
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%J o DPHS Radiological Units (Concord, New Hampshire) o Southwestern Fire Mutual Aid Dispatch Center (Keene, New Hampshire) o Incident Field Office (Keene, New Hampshire) l o State Police Communications Center (Concord, New Hampshire)
Local Emergency Operations Centers (Local Response): o Hinsdale - Hinsdale Fire Stat 4.on o Chesterfield - Chesterfield Town Office o Richmond - Richmond Civil Defense. Building o Winchester - Winchester Emergency Service Building o Swanzey - Swanzey Center Fire Station o Keene - Keene Fire Station STATE OF MASSACHUSETTS Massachusetts Civil Defense Agency (State Response Agencie.;: o Emergency Operation Center (Framingham, Massachusetts) o Area IV Emergency Operation Center (Belchertown, Massachusetts) o Massachusetts Department of Public Health (EOF (Brattleboro, Vermont)) r 1455e/2.32 f I i
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' f Page 1.2-4 j ( Local Emergency Operations Center (s) (Local Response): i o Greenfield - Fire Station i o Leyden - Town Hall { o Bernardson - Fire Station o Gill - Fire Station o Northfield - Fire Station o Warwick - Fire Station
& STATE OF NEW YORK O To perform alert and notification to appropriate State and locals.
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O 1 I I l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 1.3 DEFINITIONS O O 1134e/20.101
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\s / 1 VERMONT YANKEE NUCLEAR POWER STATION !
EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1987 ABBREVIATIONS, DEFINITIONS, AND TERMIN0 LOGY ;
)j 1.3 DEFINITIONS q A. Abbreviations o A -
Alert o ACR0 - Alternate Control Room Operator o A0 - Auxiliary Operator o A0G - Advanced Off-Gas o APRM - Average Power Range Monitor o ARM - Area Radiation Monitor O ( ,) o Cond - Condensate o CR - Control Room o CRP - Control Room Panel o CS - Core Spray o DC0 - Duty and Call Officer o DW - Drywell o EAL - Emergency Action Level o ECCS - Emergency Ccre Cooling System o ENS - Emergency Notification System o EOF - Emergency Operations Facility o EPZ - Emergency Planning Zone
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o ESC - Engineering Support Center o FEMA - Federal Emergency Management Agency o FW - Feedwater o HPCI - High Pressure Coolant Injection o HRNG - High Range Noble Gas o LPCI -- Low Pressure Coolant Injection o Mn Con Bk Pres ' - Main Condenser Back Pressure o MPA - Manpower and Planning Assistant o MSIV - Main Steam Isolation Valve o MSL - Main Steam Line o NAS - Nuclear Alert System ( ( o NG - Noble Gases o NRC - Nuclear Regulatory Commission o OP - Operating Procedure o OSC - Operations Support Center o PASS - Post-Accident Sample System o PED - Plant Emergency Director o P0D - Pocket Dosimeter o PVS - Plant Vent Stack o RA - Radiological Assistant o RCS - Reactor Coolant System o RCIC - Reactor Core Isolation Cooling n U 1134e/20.101
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o RERP - Radiological Emergency Response Plan o RHR - Residual Heat Removal ! o RR - Reactor Recirculation o RTF - Reactor Transfer Fan o RV - Relief Valve o RWCU - Reactor Water Clean-Up o' Rx - Reactor o SAE - Site Area Emergency o SBGTS - Stand-By Gas Treatment System o SJAE - Steam Jet Air Ejector o SRM - Site Recovery Manager o SRV - Safety Relief Valve g-o SRM - Source Range Monitor o SU Trans - Start-Up Transformer o TAG - Technical Administrative Guideline o TS - Technical Specification o TSC - Technical Support Center 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
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B. Terminology o Alert - An emergency classification which is defined as an actual or potential substantial degradation of the level of safety of the plant, o Controller - A member of an exercise control group. Each Controller may be assigned to one of more activities or functions for the purpose of keeping the action going according to a scenario, resolving differences (acting as an umpire), supervising and otherwise assisting as needed. o Critique - A meeting of key participants in an exercise, usually held shortly after its conclusion, to identify weaknesses and deficiencies in emergency response capabilities .
,s o Emergency Action -
Specific instrument readings, system (
\-) Levels or event observation and/or radiological levels which initiate event classification, notification procedures, protective actions, and/or the mobilization of the emergency response organization.
These are specific threshold readings or observations indicating system failures or abnormalities, o Emergency Assistance - General term used to refer to the Personnel radiation monitoring teams, sample analysis team, and in-plant search, and rescue teams. o Emergency Operations - 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. [)
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,() Page 1.3-5 o- -Emergency Planning - The areas for which planning is Zones recommended to assure that prompt and effective actions can be taken.to protect the public in the event of an accident. The two zones are the 10-mile radius plume exposure pathway zone and the 50-mile radius ingestion exposure pathway zone.
o Engineering Support - A YNSD emergency response facility Center (YNSD communication area, Room 341, 1671 Worcester Road, Framingham, Massachusetts) established to provide additional l engineering support to the i 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 Q;f 5% equipment. o Full Participation - An exercise which tests as much of Exercise the licensee, state, and local plans as is reasonably achievable without mandatory public participation. o General Emergency - An emergency classification which is defined as actual or imminent substantial core degradation or melting with potential for loss of containment integrity. o News Media Center - An emergency response facility (Dalem's Chalet. West 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 Yankee Nuclear Information Director. 1134e/20.101 1 _ _ _ _ _ _
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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, I and reporting the strengths and weaknesses, and making recommendations for improvement. o Operations Support - An emergency response facility Center (1st floor, Administration Building) established to muster ; skilled emergency response personnel to perform activities in the plant. o Protective Action - Those emergency measures taken to effectively mitigate the consequences of an accident by minimizing the radiological exposure that would likely occur if such actions were not undertaken. 7-s
-- o Protective Action -
Projected radiological dose Guides values to the public which warrant protective actions following an uncontrolled release of radioactive material. Protective actions would be warranted provided the reduction in the individual dose is not offset by excessive risks to individual safety in implementing such action. o Scenario - The hypothetical situation, from start to finish, in an exercise which is the theme or basis upon which the action or play of the exercise unfolds. o Site - That property within the fenced boundary of Vermont Yankee which is owned by the Vermont Yankee Nuclear Power Corporation. t,,,/ 1134e/20.101
Rev. 1 9/18/87 Page 1.3-7 o Site Area Emergency - An emergency classification that indicates an event which involves likely or actual major failures of plant functions needed for the protection of the public. o Technical Support - An emergency response facility Center (2nd floor, Administration Building) with the capability to assess and mitigate the accident using plant parameters and highly qualified technical personnel. Also, assists in accident recovery operations. o Unusual Event - An emergency classification that indicates a potential degradation of plant safety margins which is not likely to affect personnel on-site or the public off-site or result in radioactive releases requiring off-site monitoring, o Yankee Nuclear Services - A division of Yankee Atomic Division (YNSD) Electric Company. An Engineering support organization which provides emergency response support to Vermont Yankee upon request. l 0 ll34e/20.101
1 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987
1.4 REFERENCES
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()! VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987
1.4 REFERENCES
- 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.
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- 5. Vermont Yankee Nuclear Power Station Emergency Operating Procedures.
- 6. Yankee Atomic Electric Company - Technical Administrative Guideline No. 12, Emergency Preparedness Responsibilities.
- 7. Martin, G. 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.
- 8. Daily Weather Maps, National Weather Service, Climate Analysis Center, Washington, DC 20233.
- 9. Letter dated 9/25/87 from Mr. D. A. DeVito to G. L. Lowe (See Section 2.?)
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O I I I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987
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2.0 EXERCISE OBJECTIVES O 1395e/12.43
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( Page 2.0-1 (} VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 2.0 EXERCISE OBJECTIVES - VERMONT YANKEE In order to demonstrate the radiological emergency response preparedness of the Vermont Yankee Nuclear Power Station, an emergency response preparedness exercise will be conducted during the week of November 29, 1987. The exercise being conducted is a full-scale, off-hours exercise which will involve the participation of Vermont Yankee station and corporate personnel. The exercise is also unannounced for the State of Vermont, State of New Hampshire, Commonwealth of Massachusetts, and the local communities within the plume exposure pathway who plan to
,.s participate in the exercise.
A set of exercise objectives for the exercise was developed to evaluate and test certain elements of the Vermont Yankee emergency preparedness program. The selected exercise objectives were based upon previous open items identified by the NRC and corrective actfons taken in regard to follow-up action items identified by Vermont Yankee personnel. These exercise objectives will be used to ascertain the required input to the exercise scenario sequence of events and to establish the evaluation criteria to be used by the exercise controllers and observers. The specific exercise objectives to be demonstrated are as follows: A. Accident Assessment
- 1. Demonstrate the ability of Centrol Room personnel to recognize emergency initiating events and properly classify the condition in accordance with pre-established emergency action levels.
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-( y) 2. Demonstrate the ability of the Control Room and TSC staff to coordinate the assessment of plant conditions and corrective actions to mitigate accident conditions.*
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- 3. Demonstrate that information'concerning plant conditions can be disseminated between the' Control Room and TSC in~a timely.
manner.*
- 4. Demonstrate the ability of the TSC staff to initiate and coordinate corrective actions in an efficient and timely' manner.*
5.. Demonstrate the ability of appropriate TSC staff to participate l, . with the. Control Room and the EOF /RC in emergency classification. and EAL discussions.*
- 6. Demonstrate the ability to obtain appropriate chemistry samples in support of accident assessment activities which may include the.use of the post-accident sampling system as necessary.
L( B. Notification'and Communication 1.' Demonstrate that messages are transmitted in an accurate and timely manner and that messages are properly logged and documented.
- 2. Demonstrate the capability to notify federal and state authorities of emergency classifications in accordance with established procedures.
- 3. Demonstrate that appropriate status boards are utilized to display pertinent accident information at the various emergency response facilities.
- 4. Demonstrate that adequate emergency communication systems are in place to facilitate transmittal of data between the emergency response facilities and federal and state authorities.
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- 5. ' Demonstrate that off-site monitoring teams can use appropriate maps and sample points (landmarks) for determining and communicating their location in the field.*
C. Direction and Control-
- 1. Demonstrate the capability of key emergency response facility' management personnel to direct and coordinate their respective emergency response activities in an efficient and timely manner.*
- 2. Demonstrate appropriate coordination of activities with federal and state government agencies.
D. Emergency Response Facilities
- 1. Demonstrate the ability of station and corporate personrel to activate and staf f the emergency response f acilities in a ti:nely manner.
- 2. Demonstrate and test the adequacy and effectiveness of emergency response facilities, operations, and equipment.
1 E. Radiological Exposure Control l
- 1. Demonstrate the ability to provide adequate radiation protection controls for on-site emergency response personnel, such as I
appropriate personnel dosimetry, equipment, and protective clothing.
- 2. Demonstrate the ability to monitor and track radiation exposure of on-site emergency response personnel.
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I ' l (1 Rev. 1 g_ 7/10/87 Page 2.0-44 F.- Radiological Assessment l' . . Demonstrate that adequate dose assessment procedures.can be a- performed to determine off-site. radiological consequences. l . p 2. Demonstrate that radiological assessment personnel at the EOF can obtain radiological and meteorological data in a timely manner.
- 3. Demonstrate the ability to perform timely assessment of off-site radiological conditions to support the formulation of protective action recommendations for the plume exposure pathway.
4'. Demonstrate that off-site monitoring teams can be dispatched and' deployed in a timely manner. t .
- 5. Demonstrate the use of appropriate equipment and procedures to perform off-site radiological monitoring.
- 6. Demonstrate the ability to effectively track and define the plume during a radiological release by utilizing the computerized dose assessment model (METPAC).
G. Protective Action Recommendations
- 1. Demonstrate the ability to implement appropriate on-site protective action measures for emergency response personnel.
- 2. Demonstrate the adequacy of the protective action decision making process to make appropriate recommendations _concerning off-site radiological consequences.
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) Page 2.0-5 H. Parallel and Other Actions
- 1. Test and evaluate the adequacy of methods to establish and maintain access control and personnel accountability within the ,
protected area.
- 2. Demonstrate the licensee's capability for self-c~ritique and ability to identify areas needing improvement.
I. Public Information
- 1. Demonstrate the ability to develop and disseminate timely accurate press releases to the public and the news media.
,s 2. Demonstrate the ability to provide briefings for and to I i
( ,) interface with the public and news media.
- 3. Demonstrate the ability to communicate and coordinate news releaser, between the EOF and the News Media Center.
- 4. Demonstrate the ability to coordinate news releases with the state's public information representatives.
- 5. Demonstrate the ability to provide rumor control.
The annual Radiological monitoring drill and semi-annual Health Physics drill will be included as part of this exercise. A separate Health Physics drill was held to demonstrate the actual sample collection and analysis of the Post-Accident Sampling System (PASS). I U
- Indicates NRC identified improvement items from the 1986 exercise.
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Rev. 1 9/21/87 Page 2.0-6 v 2.0 EXERCISE OBJECTIVES - STATE OF VERMONT Group A State of Vermont Local Jurisdiction
- 1. Demonstrate the ability to mobilize yes yes and activate facilities promptly.
(This is to include: State EOC, EOF, IF0, JIC, and all local EOCs: Brattleboro, Vernon, Dummerston, Guilford)
- 2. Demonstrate the ability to make yes yes decisions and to coordinate emergency activities.
- 3. Demonstrate the adequacy of yes yes facilitiesand displays to support emergency operations.
- 4. Demonstrate the ability to yes yes communicate with all appropriate gg g ') locations, organizations, and field personnel.
- 5. Demonstrate the ability to project yes no field data and to determine appropriate protective measures, based on PAG's available shelter, evacuation time estimates, and all other appropriate factors.
- 6. Demonstrate ability to implement yes yes protective actions for plume pathways hazards.
(This is to include: . simulated sheltering and evacuation of total town jurisdictions.)
- 7. Demonstrate the ability to alert yes yes j
the public within the 10-mile EPZ ! and disseminate an initial instructional message within 15 minutes. f (
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Group A (continued) State of Vermont Local Jurisdiction
- 8. Demonstrate the ability to formulate yes no ,
and distribute appropriate instructions to the public in ! a timely fashion.
- 9. Demonstrate the organizational yes yes ability and resources necessary to deal with impediments to evacuation, including weather or traffic obstructions. !
- 10. Demonstrate the ability to yes yes continuously monitor and control emergency worker exposure.
- 11. Demonstrate the ability to brief yes no the media in a clear, accurate and timely manner.
- 12. Demonstrate the ability to provide yes no
/~' advance coordination of
(_)S information released.
- 13. Demonstrate the ability to make yes no the decision, based on predetermined criteria, to supply and administer KI to emergency workers, l
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' Group B State of Vermont Local Jurisdiction
- 14. . Demonstrate the' ability.to make the yes .no decision, based on predetermined partial criteria, whether'to issue KI to the general population, and supply and administer-KI'once the decision has been made to do so.
Vermont will not issue KI to the b public. . Vermont will demonstrate. the decision making,' identify L sources, and methods of supplying. l
'15. Demonstrate _th'e ability to supply no no and administer KI once the decision has been made to do so.
- 16. Demonstrate the ability to- yes no
' . establish and operate rumor.
control in a coordinated fashion.
- 17. Demonstrate the ability to yes yes fully staff facilities and amintain staffing around the clock.
(All staffed facilities will demonstrate rosters for two-shift capabilities.)
- 18. Demonstrate the ability to yes no mobilize and deploy field monitoring teams in a timely fashion. Two DPHS field teams will be mobilized (additional in reserve).
- 19. Demonstrate appropriate equipment yes no
.and procedures for determining
< ambient radiation levels.
;20.- Demonstrate appropriate equipment yes no and procedures for measurement
-of airborne radioiodine concentrations as low as 10-7-uCi/cc in the presence of O- noble gases.
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1. l., Rev. 1 l.. 9/21/87 ' iQ- ; Page 2.0-9 V Group B (continued) State of Vermont Local Jurisdiction
, 21.* Demonstrate appropriate equipment yes no and procedures for collection,
-transport, and analysis of' samples of soil, vegetation, snow, water, l.
and milk.
.The State of' Vermont will demonstrate the collection, transportation, and testing, as part of the ingestion objective, by an actual one-time demonstration.
22.* Demonstrate appropriate lab yes no operation functions for measuring and analyzing all types of
- l. samples.
The Vermont testing will include analysis:of soil, water, vegetation, milk, snow (as appropriate) during
- the Ingestion Drill.
23.* Demonstrate the ability to project yes no dosage to the public via ingestion pathway. exposure, based on plant and field data, and to determine appropriate protective measures, based on PAGs and other relevant factors as part of the Ingestion [ Exercise] Drill. l Vermont determinations of PAGs based primarily on Vermont Laboratory test results. 24.* Demonstrate the ability to implement yes no protective actions for ingestion pathway hazards.
- 25. Demonstrate the organizational no no }
ability and resources necessary to control access to an evacuated area.
- Indicates the objectives that will be demonstrated on Day 2, the ingestion pathway part of the exercise.
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Group B (continued). State of' Vermont -Local Jurisdiction
- 26. Demonstrate the organizational no no ,
ability and resources necessary to effect an orderly evacuation within the plume EPZ of these groups: transit-dependent, special needs, and institutionalized.
- 27. . Demonstrate the organizational no no c ability and resources necessary to effect an orderly evacuation of schools within the plume EPZ.
- 28. Demonstrate adequacy of procedures no no for the registration and radiological monitoring of evacuees.
- 29. Demonstrate adequacy of facilitics no no for mass care of evacuees.
m 30. Demonstrate adequate equipment and no no ( ,) procedures for decontamination of emergency workers, equipment, and vehicles.
- 31. Demonstrate adequacy of ambulance no no
' facilities and procedures for handling contaminated, injured, and exposed individuals.
- 32. Demonstrate adequacy of hospital no no facilities and procedures for handling contaminated, injured, and exposed individuals.
- 33. Demonstrate the ability to identify yes no need for, request, and obtain Federal assistance.
I I O 1570e/20.137
/.
Rev. 1 i
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[ I Page 2.0-11 l i> s z Group B (continued) State of Vermont Local Jurisdiction 34.* Demonstrate the ability to estimate yes no total population exposure.
- 35. Demonstrate the ability to no no determine and implement appropriate measures for controlled recovery and re-entry.
In' addition, the State of Vermont local jurisdictions will participate in an unannounced, off-hour exercise, as part of the test exercise. l
,~
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- Indicates the objectives that will be demonstrated on Day 2, the ingestion pathway part of the exercise.
1 1 1570e/20.137 t
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b hid'.EXERCISEOBJECTIVES-STATEOFNEWHAMPSHIRE l i A! r "The state of New' Hampshire objectives for'the Vermont Yankee reise are In addition,.to the stated gs)A based on the. draft FEMA Guidance Memorandum EX-3. objectives, this exercise will: satisfy the NUREG-0654, ibTA-REP-1, Revision 1,
, .p
.requirementLfor an off-hours exercise (6'p.m. .to 4 a.m.).
fw[h ,y T, J. Q. fi , L I. _ , St,hek t Local f *NFEMA' Objective %nd Extent of Play (New Hampshi M Jurisdictions a a .+" l '. , _ .x ( N '" . Group A Obiectives, 4q ,
+. .p f,. !
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- 1. Demonstrate ab.11ty to mobilize staff Yes Yes f .,,
p 1] anddenivate facilities promptly. ,
.'2 N
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'Th s ewi}1mobilizestateand localeem mency response personnel -
I [ \ and facil ties) The state EOC, the f k
- EOF,.the IF0, the Media Center, and (
. 4
^
all Tocal EOCs will be activated j' p ace 'ing to existing procedures. ( I q 3 p
- 2. Demonstrate ability to make decisionJ Yes Yes i
-}' . end to coordinate emergency activities.
e m
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- 3. : Demonstrate adequacy of facilities and Yes Yes I >
displays to support emergency ,
9 '
operations. /' ,+ 3 6 4
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1564e/3.26 .
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,, 1 State Local
, FEMA Objective and Extent of Play '
[New Hampshire) Jurisdictions i
'4a Demonstrate ability to communicate with Yes Yes all appropriate locations, organizations, b,' .
and field personnel.
- 5. Demonstrate ability to alert the public Partial isrtial within the 10-mile EPZ, and dissemirsate (simulated) (simulated) an initial instructional message'sithin J '.' . 15 ninutes.
i The state will demonstrate decisions and i procedures l'or activating sirens and EBS. j i e The EBS rar,flo station will be contacted (()' and provided vith IAe appropriate sessage. The radio statLon will only be asked to y demonstrate receipt and acknowledgement t' 'af the message. No actual radio messages will be broadcast. Activation times will be coordina c3 v'.h local EOCs. The audible alert and EBS systees will , be tested separately from exercisv. i i
\
'6. P.psonstrate ability to fonnulate and Yes N/A distribute appropriate instructions to s o,
% the pdblic in a timely fashion.
F( U 1564e/3.26 I
r _ _ __ Rev. 1 9/21/87 . fe3 Page 2.0-14 l t, l s - l State Local FEMA Objective and Extent of Play (New Hampshire) Jurisdictions The state will formulate appropriate messages. The radio station will not be contacted. Broadcast of messages will be simulated.
- 7. Demonstrate the organizational ability Yes Yes and resources necessary to deal with impediments to evacuation, including weather or traffic obstructions.
Demonstration of the ability will involve
,s dispatch of a special purpose vehicle to a
(,,,) simulated traffic impediment area. The vehicle dispatched may be either a local or a state vehicle.
- 8. Demonstrate ability to continuously monitor Yes Yes and control emergency worker exposure.
Dosimetry will be issued to emergency workers at both the state and local levels. Ability to issue, monitor, and control emergency worker exposures will be tested.
- 9. Demonstrate ability to brief the media in a Yes N/A clear, accurate, and timely manner.
( 1564e/3.26 l
'iv Rev. 1 9/21/87.
Page 2.0-15 State Local i FEMA Objective and Extent of Play (New Hampshire) Jurisdictions-Group B Objectives
- 10. Demonstrate ability to provide advance Yes N/A coordination of information released.
LA. state representative will be present in the Media Center to coordinate with state personnel in other locations and with utility personnel. r
- 11. Demonstrate the ability to make the decision, Yes N/A based on predetermined criteria, to supply and administer KI to emergency workers.
(
- 12. Demonstrate the ability to make the decision, No N/A I based on predetermined criteria, whether to i
issue KI to the general population, and 1' supply and administer KI once the decision has been made to do so. 1 The State of New Hampshire does not intend to issue KI to the general population.
- 13. Demonstrate the ability to supply and Yes Yes administer KI once the decision har been made to do so.
'. N 1564e/3.26
-_a_-_-____
Rev. 1 tT 9/21/87 i ( ,) Page 2.0-16 State Local FEMA Obiective and Extent of Play (New Hampshire) Jurisdictions KI will be available for emergency teams at local EOCs and the IFO. New Hampshire does < l I not intend to administer KI to the general public.
- 14. Demonstrate ability to establish and operate Yes N/A rumor control in a coordinated fashion.
- 15. Demonstrate ability to fully staff Yes Yes facilities and maintain staffing around the clock.
,a k_-) Key state and local personnel will be mobilized for emergency facilities. Second shift capability will be demonstrated by roster.
- 16. Demonstrate ability to mobilize and deploy Yes N/A field monitoring teams in a timely fashion.
Two DPHS field teams will be mobilized.
- 17. Demonstrate appropriate equipment and Yes N/A procedures for determining ambient radiation levels.
\
t' - N-. 1564e/3.26 l l i
7 1 i Rev. 1
... 9/21/87 /i Page 2.0-17 ' Q)
State Local
' FEMA Obiective and Extent of Play- (New Hampshire) Jurisdictions
- 18. Demonstrate. appropriate equipment and Yes 'N/A-procedures for measurement of airborne radioiodine concentrations as low as
~
'10 uCi/CC in the presence of noble gases.
** 19. Demonstrate appropriate equipment and Yes N/A
-procedures for collection, transport, and analysis of samples of soil, vegetation, snow, water, and milk.
This will be demonstrated as part of the Ingestion Pathway Drill the day after the () exercise. Actual samples collected will depend on weather conditions at the time'of the drill. Capabilities for samples not collected will be demonstrated through discussions..
** 20. Demonstrate appropriate lab operation Yes N/A functions for measuring and analyzing all types of samples.
I
** Indicates the objectives that will be demonstrated on Day 2, the ingestion pathway part of the exercise.
1564e/3.26
l l Rev. 1
. ,.m 9/21/87 Page 2.0-18
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State Local FEMA Objective and Extent.of Play (NewHampshirej Jurisdictions l
- 21. Demonstrate the organizational ability and No No resources necessary to effect an orderly evacuation within the plume EPZ of these groups: transit-dependent, special needs, and institutionalized.
This capability has been adequately demonstrated at Vermont Yankee in the past. (This will be demonstrated at the next Seabrook exercise.)
- 22. Demonstrate the organizational ability and No No resources necessary to effect an orderly t
(j evacuation of schools within the plume EPZ. Due to the off-hours nature of this exercise, the objective will not be demonstrated this year.
- 23. Demonstrate adequacy of procedures for No No registration and radiological monitoring of I evacuees.
- 24. Demonstrate adequacy of facilities for mass No No l care of evacuees.
1 1564e/3.26 )
1 Rev. 1 9/21/87 Page'2.0-19
) 1 i
State Local FEMA' Objective and Extent of Play' (New Hampshire) Jurisdictions
' 25' . Demonstrate adequate equipment and procedures No No for decontamination of emergency workers,
. equipment, and vehicles.
- 26. . Demonstrate adequacy of ambulance of facilities No No and procedures for handling contaminated.
injured, and exposed individuals.
- 27. Demonstrate. adequacy of hospital facilities No No and procedures for handling contaminated, injured, and~ exposed individuals.
) 28. Demonstrate ability to identify need for, Yes N/A request, and obtain federal assistance.
** 29.- Demonstrate. ability to estimate total Yes N/A population exposure.
i
- 30. Demonstrate ability to determine and No No implement appropriate measures for controlled recovery and re-entry.
TOTALS 26/35 10/18
** Indicates the objectives that will be demonstrated on Day 2, the ingestion pathway part of the exercise.
O 1564e/3.26
Rev. 1 9/21/87 ['] x_ - Page 2.0-20 2.0 EXERCISE OBJECTIVES - STATE OF MASSACHUSETTS
- 1. Demonstrate ability to mobilize and activate facilities promptly.
f
- 2. Demonstrate ability to make decisions and to coordinate emergency !
i activities.
- 3. Demonstrate adequacy of facilities and displays to support emergency operations.
- 4. Demonstrate ability to communicate with all appropriate locations, organizations, and field personnel.
- 5. Demonstrate ability to project field data and to determine appropriate protective measures, based on PAGs, available shelter, rN
.: evacuation time estimates, and all other appropriate factors.
)
- 6. Demonstrate ability to implement protective actions for plume pathway hazards.
- 7. Demonstrate ability to alert the public within the ten-mile EPZ and disseminate an initial instructional message within 15 minutes.
- 8. Demonstrate ability to formulate and distribute appropriate instructions to the public in a timely fashion.
- 9. Demonstrate the organizational ability and resources necessary to deal with impediments to evacuation, including weather or traffic obstructions.
- 10. Demonstrate ability to continuously monitor and control emergency worker exposure.
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1595e/4.95
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i Rev. 1 i/k1 9/21/87 Page 2.0-21 O 111. Demonstrate ability to brief the media in a clear, accurate, and . timely manner.
.'12. . Demonstrate' ability to provide advance coordination of information 1 released.
- 13. Demonstrate the ability to make the decision, based on predetermined criteria, to supply and administer KI to emergency workers. !
- 14. Demonstrate the ability to make the decision, based on predetermined criteria, whether to issue KI to the general population, and supply and administer KI, once the decision has been made to do so.
L 15.- Demonstrate the ability to supply and administer KI, once the decision has been made to do so. 16'. Demonstrate ability to establish and operate rumor control in a coordinated fashion.
- 17. Demonstrate ability to mobilize and deploy field monitoring teams in a timely fashion.
- 18. Demonstrate appropriate equipment and procedures for determining ambient radiation levels. ;
- 19. Demonstrate appropriate equipment and procedures for the measurement of airborne radiciodine concentrations as low as 10~ uCi/cc in the presence of noble gases.
O 1595e/4.95 l
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Rev. 1 g 2 0-22 1
** 20. Demonstrate appropriate equipment and procedures for collection and '
transport of: samples of soil, vegetation, snow, water, and milk.
** 21. Demonstrate appropriate lab' operation functions for measuring and analyzing all types of samples.
** 22. ~ Demonstrate ability to project dosage to the public via ingestion pathway exposure, based on plant and field data, and to determine appropriate protective measures, based on PAGs and other relevant factors..
** 23. Demonstrate ability to implement protective actions for ingestion pathway hazards.
.'** 24. Demonstrate ability to identify need for, request, and obtain Federal assistance.
** 25. Demonstrate ability to estimate total population exposure.
i I
** Indicates the objectives that will be demonstrated on Day 2, the ingestion I
pathway part of the exercise. t 1595e/4.95 I
- .---------,r -,-- - -.----,-.,,---r,,--- - - . - - . - - - , . , - - -
2.0 EXERCISE OBJECTIVES - STATE OF NEW YORK 9 : I l l l
y D) N l u .... STATE OF NEw YORK DIVISION oF MILITARY AND NAVAL AFFAIRS STATE EMERGENCY MANAGEMENT OFFICE ] Pusuc SECUR BUILDWG Mao M. cuouo p c d 'nTc , AtaANv. New YoRM 122a 5000 Cwe w s
"^
bne September 25, 1987 George L. Lowe, Director Division of Emergency Management Department of Public Safety 103 South Main Street Waterbury, VT 05676-0850 Dear Mrllwp4 Than o'u fpr your correspondence pertaining to the Radiological Eme gency Preparedness (REP) Exercise to be conducted for the Vermont
. Yankee Nuclear Power Station during the' week of November 29, 1987.
I C I have shared your letter with representatives from the New York State Department of Health and the Radiological Emergency Preparedness Group which,'along with this office, have responsibility for REP program and operational activities. I will also advise my appropriate field staff and the Emergency Managers for Washington, Rensselaer and Columbia Counties, which are within the 50 mile ingestion exposure emergency planning zone for Vermont Yankee. It is our intent to monitor your November 29, 1987 exercise and to perform alert and notification to appropriate State and ' tal officials. We do not plan to deploy field monitoring (should the senaario winds affect New York), radiological assessment or operational response and recovery procedures. For this exercise, or in the event of an emergency affecting our respec-tive borders, during business hours, please contact myself at (518) 457-2222 or Mr. Anthony Germano, SEMO Chief-of-Staff at (518) 457-9994. During non-business hours, you should call the State Warning Point at (518) 457-22005 They will, in turn, notify key New York State staff. ) If you require any additional information, lease contact Mr. Germano of say s taff. He will assist you in any way h can. .' l_ Sincer,iy, l Donald'A -OeVito Dire'ctor s
8 O I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.0 EXERCISE GUIDELINES AND SCOPE O 1553e/12.81
l O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.1 EXERCISE GUIDELINES O O 1553e/12.81
Rev. 1
- - . 9/18/87. 'P .
Page 3.1-1 I' VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.1 EXERCISE GUIDELINES l A. Purpose
-This package provides guidance for conducting the 1987 VYNPS Emergency Response Preparedness Exercise. It provides the framework for demonstrating emergency response capability, conducting the
. exercise and evaluating the results.
l B. Concepts of Operations and Control of 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 appropriate maps, materials, and evaluation forms. An Exercise Coordinator was appointed by plant management for the ! purpose of developing the accident time sequence and to be in overall charge of conducting the exercise. The Exercise Coordinator will be responsible for approving the objectives, the accident time sequence, and the selection and training of the Controllers / Observers required to evaluate the effectiveness of the Vermont Yankee Emergency Preparedness Program. Controllers for the exercise will distribute information to players on message cards, and in each facility a Lead Controller will make judgement decisions to keep the action going in accordance with the scenario outline. The Lead Controllers will also provide advice to Observers and resolve problems in their assigned emergency response 1553e/12.81
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y Rev. 1 9/18/87 J' -Page 3.1-2 ln N facility. If a crisis situation arises, a Controller will first contact the Facility Lead Controller who will then contact the-Exercise Coordinator for advice or resolution of the problem. All F major requests for scenario modifications or holding periods must be cleared through the Exercise Coordinator. Observers for the exercise will observe the players as they work in l their assigned emergency response functions. Individua1Eobservers -l are responsible for being knowledgeable in the area of their assigned function. The Observers will critique the effectiveness of the emergency response actions during the exercise and also provide a written evaluation to the Lead Controller for the assigned facility. 7s %y The exercise initial conditions will be provided tu a Control Room
~
operations crew, located in the simulator area, by the Control Room
-b Simulator Controllers. The plant and reactor system parameters for ,
the' exercise will be generated by running the accident scenario on the simulator. The remaining exercise message' cards and additional scenario parameters will be provided by Controllers / Observers at the times' indicated by the exercise sequence of events, or when requested by the players. Other message cards mayLbe issued to players at times' required by player actions during the exercise. 4 As the initiating events are provided to the plant staff, they will q I determine the nature of the emergency and the implementation of appropriate emergency plan implementing procedures. These procedures are expected to include a determination of the emergency classification in accordance with the Vermont Yankee Emergency Plan. Notifications will be made to the appropriate federal and state authorities. ; 1553e/12.81
i Rev. 1 9/18/87 l [ Page 3.1-3 C The hypothesized emergency will continue to develop based on data and information provided to the operators located in the. Simulator Room. Wherever possible, operators wii.1 complete responses as if they were actually responding to the plant events. Inconsistencies in the scenario may be intentional and required to provide a basis which tests capabilities of emergency centers to the maximum extent feasible in a limited time. Controllers have the authority to resolve or explain problems that may occur with the scenario during the exercise. C. General Guidance for the Conduct of the Exercise
- 1. . Simulating Emergency Response Actions Since exercises are intended to demonstrate actual capabilities O'
,O as realistically as possible, participants should act as they would during a real emergency. Wherever possible, actions should be carried out. Emergency response actions should be simulated when it is not feasible to perform an action or when the action has been previously identified as being simulated during the exercise (refer to Section 3.3). When an emergency response is to be simulated, the Controller /0bserver will provide verbal or written directions on which actions are to be simulated.
Radiation Work Permits (RWPs) have ng 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 the activities they would have performed without actually entering the RWP-controlled area even if they are authorized on the RWP for some other duty. fD 1553e/12.81 l _ _ - _ _ _ b
Rev. 1 9/18/87.
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2.s Avoiding Violations of Laws
' Intentional violation of laws is not justifiable during any.
exercise. To implement this guideline the'following actions must be taken: a.- All Controllers / Observers and potential exercise participants must be specifically informed of the need to. avoid intentional violation of all federal, state and local laws, regulations, ordinances, statutes and other legal restrictions. The orders of all police, sheriffs or other authorities should be followed as would_normally be the case.
- b. Exercise participants will not direct illegal actions to be taken by other exercise participants or members of the-(D) general public.
- c. Exercise participants will not intentionally take illegal actions when being called out to participate in an exercise. Specifically, local traffic laws such as speed laws will be observed.
- 3. Avoiding Personnel and Property Endangerment
'i Participants and Evaluators will be instructed to avoid endangering property (public or private), other personnel 1 responding to the exercise, members of the general public, i l
animals and the environment. 1 0 1553e/12.81
I Rev. 1 ' 9/18/87 Page 3.1-5
- 4. Actions to Minimize Public Inconvenience
' ~
t It is-not the intent, nor.is it desirable or feasible, to effectively train or test the public response during the cond'uct of radiological emergency exercises. Public inconvenience is to be minimized. i. The actions.of federal, state and local-agencies and nuclear power plant operators receive continuous public notice and scrutiny;~therefore, the conduct of an exercise could arouse public concern that an actual emergency is occurring. It'is important'that conversations that-can be monitored by the public (radio, loudspeakers, etc.) be pref aced and conclude with the words, "THIS IS A DRILL; THIS IS A DRILL." () D. Emergency Response Implementation and Operations
- 1. Initial and Follow-Up Notification Initial and follow-up notification of the emergency classification will be nade by the plant staff in accordance with existing emergency plan implementing procedures, unless directed otherwise.
I
- 2. Control Room Operations A Control Room emergency response crew will be positioned in the Simulator Room which is located at the Vermont Yankee Training Center in Brattleboro, Vermont. The remaining support staff normally on duty will initially be simulated until later supplemented after the ALERT by the emergency response organization. The plant and reactor system parameters will be provided to the Control Room Simulator players by the simulator f( ) control board and by Control Room Simulator Controllers in the 1553e/12.81
1 i Rev. 1 .I
,, 9/18/87 f -
Page 3.1-6 L T form of message or command cards when required. Other [
'information, such as radiological data and meteorological data, will be provided to Control Room players as necessary.
Communications between the Simulator Control Room and other-i emergency response facilities will utilize communications links that duplicate the emergency communications capabilities available at the. Control Room or by utilizing the actual I Control Room communication system for transmission (e.g., Gaitronics - PA System at the plant to make Control Room emergency announcements).
- 3. Technical Support' Center (TSC) Operations The TSC emergency response organization will be activated during this exercise. TSC information will come from the Control Room, located in the Simulator Area. Information that is normally accessible by TSC personnel from the plant computer will be.provided by Controllers /0bservers 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 Area.
- 4. Operations Support Center (OSC) Operations The OSC emergency response organization will be activated during this exercise. Operations Support Center responses, direction and information will be communicated with the Technical Support Center. OSC Observers will accompany all OSC teams dispatched during the exercise and will have appropriate operational and radiological data for the players. No team participating in the exercise should leave the Staging Area without an Observer / Controller.
1553e/12.81
Rev. 1 9/18/87 Page 3.1-7 f
- 5. Emergency Operations Facility / Recovery Center (EOF /RC)
Operations i The EOF /RC emergency response organization will be activated during this exercise. Information and data will be transmitted to the EOF /RC from the TSC and Control Room (Simulator). EOF Controllers and Observers will provide other data to EOF /RC players as necessary.
- 6. Off-Site Monitoring Teams Off-site monitoring teams will be fully activated and dispatched in accordance with existing procedures. Simulated data will be provided to off-site monitoring teams by the Off-Site Monitoring Team Observers / Controllers.
( v 7. News Media Center Operations The News Media Center will be activated and staffed during the exercise. The News Media activities are an integral part of the exercise objectives. Press releases to the general public and news media will be generated. News Media Center staff will obtain all necessary information on current status of the exercise through communications channels with the EOF /RC. Simulated press releases will be compiled and disseminated in accordance with the Vermont Yankee Communications Department ) Emergency Response Plan and Procedures. All press releases are to be clearly marked: THIS IS A DRILL. l 8. Security Operations l l All security emergency responses appropriate to the exercise : scenario will be implemented in accordance with existing l procedures. Access control and personnel accountability within 1553e/12.81
Rev. 1
,m 9/18/87 Page 3.1-8 s )
(_, the protected area will be demonstrated. At no time will actual plant security procedures be violated in support of the l exercise. E. Exercise Termination 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 objectives. I O (_ i
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\ 1553e/12.81
1 I O l i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.2 EXERCISE OBJECTIVES AND EXTENT OF PLAY O 1 1407e/12.85 i
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1 l ,. l O I \ l l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.3 SIMULATION LIST O l l l 1406e/4.69
Rev. 1 9/18/87 m Page 3.3-1
't VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987
'3.3 SIMULATION LIST
.1. Scenario specific data will not be programmed into the plant process computer. This will be provided by Controllers / Observers utilizing telephone communications between the Simulator Area and plant Computer Room.
- 2. Sufficient number of individuals from the Vermont Yankee Emergency L Organization wil1~be prestaged at the Simulator Area.
l' 3. Meteorological data will be simulated using a " test" file available to the Simulator Control Room Meteorological Computer System.
- 4. After plant evacuation accountability has been completed, plant personnel and contractors / visitors not directly involved in the exercise will be I l
allowed to return to.. work, at the discretion of the TSC Coordinator.
- 5. The distribution of potassium iodide (KI) will be simulated.
- 6. Charcoal cartridges will be used as silver zeolite cartridges during
! ON - off-site monitoring activities.
- 7. The YNSD Emergency Response Team will be prestaged in the area.
l
- 8. No emergency center evacuation will be demonstrated during the exercise.
- 9. Off-site monitoring teams and security boundary monitoring personnel will not wear protective clothing and/or respirators.
- 10. . The inner gate and electrically controlled doors will not be left in the open position during this exercise.
- 11. Initial on-shift Chemistry and Health Physics Technicians actually in the plant will be simulated.
- 12. The plant Gaitronics is not available from the simulator; actual plant notifications will be made, through the Vermont Yankee plant Control Room.
1406e/4.69
i Rev. 1 9/18/87 (~~ Page 3.3-2 A._.)) -
- 13. Controllers / Observers will not be issued dosimetry unless plant access is required prior to the exercise. Security will be notified of their assigned location.
- 14. All decontamination actions associated with the exercise will be simulated.
- 15. The use of respiratory protection equipment will be simulated by plant personnel.
- 16. Radiation Work Permits (RWPs) have not been issued for the conduct of the emergency response exercise.
,m m
s/ 1406e/4.69 l l l
._______-_-__-________-_______a
~
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.4 PLAYER INSTRUCTIONS O 1409e/12.86
Rev. 1 ys 9/18/87 (,) Page 3.4-1 i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.4 PLAYER INSTRUCTIONS The Vermont Yankee Emergency Response Preparedness Exercise will be conducted during the week of November 29, 1987. The successful demonstration of emergency response capabilities will depend on player response and protocol. General guidelines for the exercise are as follows:
- 1. Exercise participants include Players (including NRC Incident f-s.
Response Team), Controllers, Observers, NRC and FEMA Evaluators, and s, ) an Exercise Coordinator. Controllers will provide players with command and message cards to initiate emergency response actions. They will be identified by badges, and Observers will also be evaluating Player actions.
- 2. a. Always identify yourself by name and function to the Controllers, Observers, and Evaluators. Wear a name tag if one in provided.
- b. You may be expected to support and interact with members of the NRC Incident Response Team. Keep in mind that their purpose is to assist the utility and NOT to evaluate their performance.
- 3. You may ask the Controller / Observer for information such as:
f-
- a. Initial conditions of the plant and systems including:
t ( o operating history of the core 1409e/12.86
Rev. 1 , fN 9/18/87 LIQ- Page 3.4 o initial coolant activity o general weather conditions o availability of systems according to the scenario
- b. . Area radiation data at the location of emergency _ teams.
- c. Airborne data at the location of the plant and field survey teams after a sample has been appropriately 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 / Observers:
- a. Information contained in procedures, drawings, or instructions.
- b. Judgements as to which procedures.should be used.
- c. Data which will be made available later in the day.
- d. What the Controller /0bserver would do if he were a player.
- e. Assistance in performing actions in this exercise.
- f. Assistance in carrying out calculations.
- 5. Play out all actions, as much as possible, in accordance with your Emergency Plan and Procedures as if it were a real emergency. If an action or data is to be simulated, an Exercise Controller or Ok Observer will provide Players with appropriate direction.
1409e/12.86
Rev. 1 9/18/87 Page 3.4-3 l f'^') v
- 6. Always identify and discuss your actions to the Controllers and Observers. State your data out loud as you are recording it. For your own benefit, it is recommended that you play out your actions as much as possible, as if it were a real emergency. It is to your advantage to exercise as many appropriate response actions as I
possible.
- 7. Periodically speak out loud, identifying your key actions and decisions to the Controllers / Observers. This may seem artificial, but it will assist the evaluators and is to your benefit.
- 8. When you are assigned to complete a response action, be sure to be accompanied by an Exercise Controller or Observer at all times.
- 9. If you are in doubt about completing a response action, ask your n
Controller or Observer for clarification. The Controller /0bserver (} will not prompt or coach you. Emergency response actions must not place exercise participants in any potentially hazardous situations.
- 10. The Controller / Observer will periodically issue messages or instructions designed to initiate response actions. You must accept these messages immediately. They are essential to the proper conduct of the exercise.
- 11. If the Controller intervenes in your response actions and recommends you redirect or reconsider your play actions, it is for a good reason. His direction may be essential to the overall success of the exercise for all participating groups.
- 12. If you disagree with your Controller or Observer, discuss your problem with him. However, Controllers / Observers final decisions (
1 must be followed. I) N-l l
- 13. Respond to questions in a timely manner.
I l 1409e/12.86
Rev. 1 3
,q
, 9/18/87 Page 3.4-4 l
'14. Do not accept any messages / instructions from NRC Evaluators. They are required to work through your Controller /0bserver if they want to initiate additional emergency conditions. However, you may answer questions directed at you by NRC Evaluators. If you do not know the answer, refer them to your lead player or Controller /
Observcr.
- 15. You must play as if radiation levels are actually present in accordance with the information you receive. This may require you
'to wear additional dosimeters, observe emergency radiation protection practices, wd to be aware of and minimize your radiation exposures.
- 16. Controllers / Observers / Evaluators are exempt from simulated radiation levels and other emergency conditions. Do not let this confuse you or cause you to act unwisely. However, no one is exempt from normal station radiological practices and procedures.
- 17. Utilize status boards and log books as much as possible to document and record your actions.
- 18. Always begin and end all communications with the words "THIS IS A DRILL," during the exercise 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. Provide your input to your lead player or ;
Controller / Observer immediately after the exercise. A critique will follow the exercise. Areas for improvement or weaknesses when corrected will improve the overall emergency response capability. 1409e/12.86
' (Q \ i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 i 3.5 PROCEDURE EXECUTION LIST O l O 1411e/12.87
4 Rev. 1
,s 9/18/87 Page 3.5-1 l [
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.5 EMERGENCY PLAN IMPLEMENTING PROCEDURES EXECUTION LIST ]
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Procedure Number Title AP 3125 " Emergency Plan Classification and Action Level Scheme" j AP 3512 " Release of Public Information" OP 3500 " Unusual Event" OP 3501 " Alert" OP 3502 " Site Area Emergency" OP 3503 " General Emergency" 0F 3504 " Emergency Communications"
%J OP 3507 " Emergency Radiation Exposure Control" OP 3510 "Of f-Site and Site Beitadary Monitoring" 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" OP 3530 " Post-Accident Sampling" 1411e/12.87
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i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.6 EXERCISE TERMINATION CRITERIA i
) .O 1412e/12.88 l
Rev. 1 9/18/87
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Page 3.6-1 V VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 3.6 EXERCISE TERMINATION CRITERIA The exercise may be terminated under the following circumstances:
- 1. .If all emergency response actions have'been completed in accordance with'the exercise time sequence; 1
- 2. If an actual plant emergency condition develops coincident with the exercise; and
- 3. If an actual off-site emergency impacts the response actions of p' Vermont Yankee exercise participants.
J . In the event that Item 2 should occur, the following actions will be 1 ,' taken: p.
- 1. The Shift Supervisor will contact the TSC Coordinator of the plant status. The TSC Coordinator will, in turn, contact the Site Recovery Manager and inform him of the plant status;
- 2. The Site Recovery Manager will immediately inform any State representatives at the EOF of the nature of the emergency;
- 3. Concurrent with the notification in Step 2, the Control Room will announce over the plant paging system the following statement:
"The emergency plan exercise has been terminated. I repeat.
The emergency plan exercise has been terminated." 14t2e/12.88
Rev. 1 9/18/87 Page 3.6-2 (~') - Q,) This message may be immediately followed by the appropriate emergency class announcement (if appropriate);
- 4. The Exercise Coordinator would be responsible for directing the actions of the Controllers /0bservers; and
- 5. The emergency plan / procedures and notifications applicable to the event would be implemented in accordance with the nature of the emergency (if appropriate).
In the event that Item 3 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 lA)
't.J 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 would 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 would be responsible for temporarily halting the exercise until such time a decision could be made;
- 5. If the final decision were to cancel the exercise, then the Exercise Coordinator would be responsible for directing the activities of the evaluation team as well as for the notification of NRC;
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Rev. 1 es 9/18/87 Page 3.6-3 l l l
- 6. If the final decision were to continue the exercise, then the Exercise Coordinator would be responsible for informing all ]
Controllers / Observers of the projected change to the expected response action (s); and
- 7. The Exercise Coordinator would direct his organization as to the j appropriate action required to restore the exercise sequence. >
D C t% (_) 1412e/12.88
D C i l 4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 l 4.0 CONTROLLER /0BSERVER INFORMATION lO 1 l O 1634e/1.166
l i VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 4.1 CONTROLLER /0BSERVER ASSIGNMENTS O O 1563e/26.79
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i Rev. 2 11/17/87 f-ssz Page 4.1 .t
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VERMONT YANKEE NUCLEAR POWER STATION
' EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 4.1 CONTROLLER /0BSERVER ASSIGNMENT LIST i Exercise Coordinator: S.. Jefferson Center: Simulator Control Room Controller: A. Chesley, VY Observers: J. McArdle, YNSD - Notification / Classification D.ETuttle, VY - General / Communications M. Krider,.VY - Simulator Operator H J. Hudacheck - Simulator Data Center: Control Room' Controller: 'D. Slauenwhite - VY Center: Technical Support Center Controller: P. Klaski, VY ' [ ) - P. Anderson, YNSD - Direction and Control U Observers:
C. Cameron, VY - Accident Assessment Center: Operations Support Center Controller: F. Deal, VY Observers: D. McDavitt, YNSD - On-Site Assistance Team R. Cardarelli, YNSD - Gn-Site Assistance Team D. Ervin, YNSD - PASS S. Racz, VY - Survey Teams and Governor Hunt House Monitoring Team G. Stratton, YNSD - Off-Site Monitoring Team E. Cumming, YNSD - Off-Site Monitoring Team S. Spanas,'oED- Site Monitoring Team J. Babbitt, VY - General Center: Emergency Operations Facility i Controller: J. Hawxhurst, YNSD l Observers: D. Pergola, YNSD - Radiation Assessment Area l l E. Salomon, YNSD - EOF Coordinator N. Panzarino, YNSD - Off-Site Monitoring / Chemistry R. Meyers, YNSD - Communications /Information Flow l \ Controller: E. Porter, VY (Site Recovery Manager) l Observers: W. Riethle, YNSD - Organization, Command, and Control T. Fuller, YNSD - State Interface O 1634e/1.166 l
I Rev. 2-11/17/87 f s Page 4.1-2 Center: ~ Security. Controller: E. Wojnas, YNSD - General Observation 1 Center: ~ News Media Center Controller: R. Zikaras, YNSD Observer: H. Lefebvre, VY - General Observation 1 Center: Engineering Support Center Controller: K. Traegde, YNSD B. Off-Site Organization 2 State of New Hampshire
. Center: Emergency Operations Center Controller: S. McCandless, HMM
- Observer:
Center: IFO (Keene,.NH) Controller: M. O' Hare, HMM Observers: . J. Spead, Seabrook (Consultant)
, Seabrook (Consultant)
\' Center: EOF (Brattleboro, VT)/ Media Center Observer: T. Casella, HMM - NH Interface Local E00s Center: Chesterfield EOC Observer: B. Hobbs, HMM Center: Hindsdale EOC Observer: J. Lischinsky, HMM Center: Richmond EOC Observer: G. Reynolds, HMM Center: Swanzey EOC Observer: J. Rainey, HMM
' Center: Winchester EOC Observer: M. Vigliani, HMM 1 The Controller assigned to the EOF /RC will be responsible for coordinating the comments from the observers located at Security and News Media Center.
,/) 2 The Exercise Debriefings off-site are at the discretion of the Senior v Management available (Player) in the off-site facility.
-1634e/1.166
(- Rev. 2
- j"- 11/17/87 l . -( 'Page 4.1-3 State of Massachusetts Center
- Emergency Operations Center (Framingham)
Controller: T. Matthews, MA/DPH Observer: J. Robinson, YNSD i Center: IFO-Greenfield (Greenfield Fire House) Controller: M. Gilmore YNSD Observer: D. Newman , YNSD State of Vermont Center: . Emergency Operations Center (Waterbury) Controller: R. Quinlan, VEM
~0bserver: , VY Center: IF0'Dummerston (State Highway Garage)
Controller: E. Tarnuzzer, YNSD Observer: .E. May, YNSD D. Rice, YNSD O i l l 1634e/1.166 i i _m_ _ . - _ _ _ _ _ _ _ _ _
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l ) _t f^ ' VERMONT YANKEE NUCLEAR POWER STATION f EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1987 l l 4.2 CONTROLLER AND OBSERVER EXERCISE GUIDANCE l 1 1566e/20.129
Rev. 1 f-~3 9/18/87 l ( j' Page 4.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1987 4.2 CONTROLLER AND OBSERVER EXERCISE GUIDANCE Prior to the exercise, each Controller /0bserver will be provided a package and a set of plant emergency plan implementing procedures which correspond to their assigned evaluation area. It is the responsibility of the Controller / Observer to read the contents of the package, review the procedures associated with the assignment, and then, develop a checklist of important concepts associated with the designated procedure which can be used as a reference during the exercise. In developing this checklist, an attempt should be made to categorize the concepts under the following general headings: Detection and Classification; Notification and Communication; Information Flow; Emergency Organization; Accident Assessment; Dose Assessment; and Protective Action Decision Making. Prior to the exercise, each Controller / Observer will be requested to attend a Controllers / Observers Briefing Meeting. During this meeting, each Controller /0bserver should identify any questions he/she has with the package ((. content and/or their assignment. It is the responsibility of each Controller / Observer to ensure that he/she is familiar with the various plant locations where their assignment will require their presence. Tours will be provided as a portion of the briefing; however, these tours will be limited in their duration. It may be advisable to plan an additional tour. Observers should familiarize themselves with their assigned Center and Lead Controller prior to the exercise. The Lead Controller will be responsible for directing observer activities throughout the course of the exercise. At exercise termination, each Lead Controller is responsible for meeting with their Observers and directing their critique and documentation of their exercise comments. Each Lead Controller will be responsible for ensuring that this documentation is provided to the Exercise Coordinator at the conclusion of the critique session. Each Lead Controller is also responsible for providing a brief summary of their facility comments during the formal critique. Controllers / Observers should identify themselves to players and explain their role in the exercise. Controllers / Observers should inform players that if
. their actions are going to deviate from standard plant or emergency procedures they should tell the Observer why. Controllers / Observers should keep a detailed time log throughout the exercise, listing all transferred data and players responses. This log and related comments should provide the time, place, and names of involved personnel.
7-~g Section 4.3 contains log sheets and evaluation forms to be used for documentation of observations. !b The primary role of exercise Controllers /0bservers is to evaluate the emergency responses of the players. In order to document the adequacy of 1566e/20.129 i
Rev. 1 9/18/87 /9 Page 4.2-2 \ _/ 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 recognized deficiencies of personnel, equipment, etc. provide recommendations for improvement detailing corrective actions, if possible. Controllers / Observers should not allow their biases to be documented as recognized weakness or deficiencies. Comments and recommendations should be further subdivided under the general. headings according to the following minor headings: Facility Activation / Organizational Control, Communications, Adherence to Plans and Procedures, Equipment Capabilities, Scenario, Training, Facility Layout, Off-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Comments. Facility Activation comments should identify: (1) the time that emergency response personnel were notified; (2) when the facility was activated; (3) when initial activities become well organized; (4) whether personnel performance follows the organized arrangements specified by plant procedures; and (5) the efficiency of methods of authority transfer. If a transfer of responsibility occurs, then the Observer should determine if all affected personnel are aware that the transfer has occurred. p) i Communication comments should identify: (1) personnel familiarity with emergency communications use; (2) whether sufficient communications were available to ensure a timely, efficient, and effective flow of information; (3) whether there were enough communications personnel to make use of all available equipment; (4) the adequacy of communications logs and describe the effectiv' e ness of data transfer; (5) whether there were any problems in the design of the 3xisting communications system (i.e., location relative to traffic flow); (6) whether there were any recognized difficulties in use of computer systems; and whether center status boards are effectively used. Observers should document their comments in this area very carefully, providing sufficient details to track any recognized deficiencies. Plans and Procedural comments should identify: (1) whether personnel were familiar with the details of overall concepts of applicable procedures; (2) whether situations developed which required deviation from the procedure or plan; (3) whether personnel were overwhelmed with procedural requirements distracting them from performing their required emergency response function, and (4) whether the procedures adequately described the actions required to { complete an assigned function. I i Equipment capability comments should identify: (1) whether all necessary materials and equipment were available and functional; (2) whether emergency i I response personnel checked operability of equipment prior to conducting their assignment; (3) whether backup equipment was readily available when malfunctions were reported; (4) whether the available systems provide an h) adequate service; and (5) whether equipment malfunctions impacted the expected U emergency response. 1566e/20.129
Rev. 1 f 9/18/87 ! Page 4.2-3 Scenario related comments should address: (1) whether sufficient information was available.to ensure appropriate player response; (2) whether the scenario details deviated from actual procedural requirements; and (3) whether the scenario detail provided any prompt to the player. An additional question should be answered by Controllers /0bservers concerning the adequacy of the scenario-in keeping the players active and interested throughout the exercise. Training comments should identify: (1) whether plant personnel have been provided sufficient training to handle "ad hoc" procedural deviations; and (2) whether training identifies improper procedural requirements. Comments on facility layout deficiencies / recommendations should identify: (1)
'whether the available work space provided was adequate; (2) whether. traffic flow hindered the response efforts; (3) whether the communications available in the work area were adequate; (4) whether the noise level hindered emergency response efforts; and (5) whether sufficient references were available to complete the job assignment.
Off-site monitoring team observers should identify: (1) the adequacy of sampling methods; (2) the adequacy of contamination control measures; (3) the adequacy of reporting and documentation measures; and (4) the effectiveness of the team in defining the plume condition and sample locations. Dose projection techniques should be evaluated in conjunction with this general ( category. Consideration of dose projection technique should identify: (1) the effectiveness of the system in allowing the correct interpretation of off-site conditions, and (2) the effectiveness of using the projection technique in positioning off-site teams. Evaluation of Personnel Dosimetry / Exposure Control activities should identify: (1) the timeliness and effectiveness of dosimetry distribution; (2) the effectiveness of protective measures, such as administration of potassium iodide; (3) the adequacy of established contamination control access points; (4) the adequacy of exposure planning measures afforded in plant activities; and (5) the adequacy of decontamination and posting techniques.
.The Controllers / Observers will be provided a supply of the Evaluation Forms found in the following section. All such documentation must be provided to the Lead Controller after the exercise and prior to the plant critique.
1566e/20.129
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i Revision 0 11/9/87
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1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ] 1987 l 4.3 CONTROLLER AND OBSERVER COMMENTS As discussed in Sections 4.1 and 4.2, each Observer / Controller has been assigned specific areas of the response effort to evaluate. These observations shall be documented and discussed after the completion of the exercise. This section has been developed to assist the Observer / Controller to maintain a detailed log of events as they occur, recall their observations as they pertain to specific exercise objectives, and finally, to provide an official record of the observations for inclusion into the final exercise report. Attachment A consists of blank pages formatted for use as a chronological log. This should assist each controller / observer in completing their respective evaluation check lists (Attachment B). Attachment B is a check list to be used to assist in evaluating their assigned facility / area. This check list shall be submitted with Attachment C to the Lead Controller for each location. b("~h Attachment C is enclosed for summarizing major observations and comments. This form MUST BE submitted by each Observer / Controller to their respective Lead Controller. Each Lead Controller will subsequently submit these forms to the Exercise Coordinator for inclusion into the final exercise report. , U-
Revision 0 11/9/87 Page 4.3-A.1 ()') VERMONT YANKEE NUCLEAR POWER STATION t* EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 o ATTACHMENT A Vermont Yankee Nuclear Power Station Emergency Response Exercise / Drill Evaluator's Observations-Chronological Log g) Time Observation / Comment
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1 i VDJ10NT YANKEE NUCLEAR POWER STATION e . emf 3GENCY RESPONSE PREPAPIDNESS EXERCISE l) 115i7 T
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O I L i l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 5.1 INITIAL CONDITIONS l O l l O 1574e/12.127
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;fL Revision 2-9/18/87 Page 5.1-1 VERMONT YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 5.1 INITIAL CONDITIONS-1.
(This-information will be provided to the players at the start of the-
; exercise).
- 1. The Reactor is operating at approximately 100 percent rated power.
The reactor has been operating steady state for the past six months with no recent shutdowns. c
- 2. a. A slight increase in reactor coolant iodine concentration has been observed for the past two weeks.
- b. The setpoints for the main steam line radiation monitors have been raised to 300 mR/hr due to high background.
- c. The night orders state: "If you reach the alarm setpoint for the
. main steam line radiation monitors; DO NOT decrease power at a L rate greater than 1% per minute; also, DO NOT SCRAM the reactor unless an isolation is imminent."
3-
- 3. The Standby Gas Treatment System Train "A" is out of service for changing the charcoal filters.
- 4. All other power generating equipment is operating, and all safety system equipment is operable.
- 5. The initial plant and Reactor System parameters associated with the start of the exercise are shown in Table 5.1-1.
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\s d , 1574e/12.127
I I Revision 2 9/18/87 jq Page 5.1-2
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- 6. The following on-site meteorological conditions exist at 1630:
1 Wind Speed, mph (upper / lower) 2.6/2.4 j Wind Direction, degrees (upper / lower) 189/218 l Delta Temperature, F (upper / lower) -0.87/-0.58 Ambient Temperature,' F 18.6 j Precipitation, inches 0.0
- 7. Synoptic (regional) meteorological conditions: l l
A typical winter day in Vermont; a cold front passed through the area ; l a day ago. Today the high temperatures during the day reached into i the mid-20's. Lows expected tonight in the teens. Winds light and variable. l h o 1574e/12.127 l I
- b. . _ _ _ _ - _ . _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _
g .; je a , Revision 2 9/18/87-I Page 5.1-3 TABLE 5.1-1
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Initial Plant and Reactor System Values Reactor Vessel. Coolant Level 158 inches. L Reactor' Pressure' 1,000 psig Reactor Power - APRM (average) 100% Core Plate Differential Pressure 20 psid L Total Core Flow 48 mil lbs/hr Main Steam Line Flow - Total 6.4 mil lbs/hr Main Steam Line Radiation 250 mR/hr
-Condenser Hotwell Level 59%
' Condenser' Vacuum 2.5 inches.Hg-Condensate Storage Tank Level 75 %
Reactor Coolant Temperature 5270F RR Drive Flow (average) 30,000 gpm Feedwater Flow 6.42 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.7 psig Drywell Temperature 1350F Torus Water Level. 1.15 ft Torus Temperature 760F Drywell/ Torus 0 2. Concentration 2.8% O HR. Containment Monitors Containment Gas /Part 1.0 R/hr 4,000/3,000 cpm Reactor Building Vent Monitors Gas /Part 150/1,500 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Jet Air Ejector 100 mR/hr Stack Gas I/II 20/30 cpm-High Range Noble Gas <0.1 mR/hr 1 1574e/12.127
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 5.2 NARRATIVE
SUMMARY
O O 1552e/4.68 _ - _ _ = _
.g VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 5.3 SCENARIO OUTLINE i
[D U . l l i l \ > 1 I 1417e/12.115 1 1 I
u i i Rev. 3 1
. - 10/9/87. l 'f,Qk Page 5.3-1 I VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE AUGUST 1987 5.3 SCENARIO OUTLINE ClockT Scenario l Time Time. Events 1630 00:00 Initial Conditions
- Reactor is at 100% power and has been operating steady state, 100% power, for the past six months. All systems are operating normally and are available for service with the exception'of the "A" train of the Standby Gas Treatment System which is out of service for changing of charcoal filters. . Chemistry has reported a
( ! slight increase in reactor coolant activity over
.the past two weeks. (This has caused the main steam line radiation monitors to read approximately 250 mR/hr.)
- The reactor operations crew becomes familiar with the operating conditions.
1635. 00:05
- An earthquake is sensed on-site and can be felt {
1 to to at various locations around the plant. 1700 00:25 l
*** UNUSUAL EVENT SHOULD BE DECLARED ***
(AP-3125, " Natural Phenomenon:" Any earthquake l sensed on-site.) l 1417e/12.115
Rev. 3 10/9/87 7- s Page 5.3-2 (v) Clock Scenario Time Time Events (Continued)
- Shift Supervisor will initiate inspections to 1635 00:05 determine the extent of damage caused by the to to earthquake. An auxiliary operator will be 1700 00:25 dispatched to investigate seismic sensing equipment.
1755 01:25
- A second, more severe earthquake is experienced to to on-site. Subsequent investigations by shift 1805 01:35 personnel reveal that several plant systems have sustained noticeable damage. Included is the "A" train of the Standby Gas Treatment System.
o Simulator Operator inserts a casualty which simulates' increasing failed fuel. () 1810 01:40 *** ALERT SHOULD BE DECLARED *** (AP-3125, Natural Phenomenon: Earthquake which damages plant systems or structures.)
- Shift Supervisor may commence a controlled power reduction, a controlled plant shutdown, or a manual scram. (The Load Dispatcher, when informed of the event, will request that the o
Shift Supervisor keep the plant on-line as long as possible as power demand is unusually high.) If the Shift Supervisor elects to initiate a manual scram, such action will be controlled at this time. l l
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(/ 1417e/12.115 l l _ _ - _ - _ _ _ _ _ _ _ _ -
Rev. 3 10/9/87 g ~g Page 5.3-3 k%- ) I l Clock Scenario Time Time Events 1930 03:00 o Simulator Operator inserts a casualty which simulates a partial reactor SCRAM. (SCRAM is initiated due to main steam line radiation levels at three times normal.) o Simulator Operator inserts a casualty which simulates several stuck control rods.
- Group 1 isolation occurs as a result of high main steam line radiation levels.
o Simulator Operator inserts a casualty which simulates that the inboard MSIV on Main Steam ('~N Line B indicates open.
- Drywell radiation levels are increasing slightly.,
- Plant personnel may be dispatched to investigate reason for partial scram.
1945 03:15 *** SITE AREA EMERGENCY SHOULD BE DECLARED *** (AP-3125. " Loss of Systems or Equipment:" Failure of the Reactor Protection System to accomplish a required SCRAM with the main condenser unavailable.)
- Plant Operator may attempt to reset the scram (control board), or personnel may be dispatched to shut Valve CRD-56 in order to attempt to drive rods.
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Clock Scenario Time Time Events 2045 04:15 o Simulator Operator inserts a casualty which simulates a break between the inboard MSIV and the outboard MSIV on Main Steam Line B.
- Steam tunnel temperatures and radiation levels increase significantly.
- Reactor Building Area radiation monitors increase significantly.
- Standby Gas Treatment Train "B" trouble alarm occurs.
[) 2050 04:20 o Simulator Operator inserts a casualty which s_/ causes the stack gas monitors on the plant vent stack to indicate a release of radioactivity to the environment. 2100 04:30 *** GENERAL EMERGENCY MAY BE DECLARED *** (AP-3125, " Loss of Two of Three Fission Product Barrierr With a Potential Loss of the Third") However, gross incore fuel damage may not be detected at this time. 2105 04:35
- The activity released from concentrations of iodine and noble gases is measurable off-site at two miles downwind.
- Plant personnel attempt to investigate problem with "B" inboard MSIV.
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Rev. 3 10/9/87
;,-f Page 5.3-5 x.s Clock Scenario Time Time Events 2150 05:20 *** GENERAL EMERGENCY SHOULD BE DECLARED ***
(AP-312 " Plant Conditions Producing Projected or Actual Site Boundary Whole Body Dose Rates Greater Than 1 R/hr"). 2250 06:20 o Simulator Operator inserts corrective actions on inboard MSIV "B."
- Control board indicates inboard MSIV "B" has closed.
- Plant is stabilized and release of radioactivity has decreased significantly.
(V) 2315 06:45 Exercise is terminated. I O V 1417e/12.115 l l ._ - - - - - _ - - - - - - _ _ - -
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O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 5.5 DETAILED SEQUENCE OF EVENTS O O 1567e/20.133 l
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() Page 5.5-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987' 5.5 DETAILED SEQUENCE OF EVENTS Clock. Scenario L Time Time Event Message Command 1600-1630 00:00 EXPECTED CONTROL ROOM (CR) ACTIONS 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. j ) 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. 3 O 1567e/20.133 ,m.- , . . -
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Clock ' Scenario Time Time Event Message- Command 1 1600-1630 00:00 The Simulator CR Controller-issues CR-M-1 CR-C-1
'(Cont'd) initial conditions to the simulator CR players. Guidelines for use of Gaitronics and'the' plant evacuation alarm are provided to players.
Initiating messages are also CR-M-1A provided.to all' emergency centers TSC-M-1 and facility staffs upon subsequent TSC-M-2A activations. Operational'and TSC-M-2B radiological data will be available OSC-M-1 to the TSC via TSC communicators EOF /RC-M-1
-> who normally respond to ESC-M-1 the CR prestaged in the VTREP-M-1 simulator. Data will be available MAREP-M-1 to the EOF over normal telephone NHREP-M-1 links. Security will be provided a list of Controllers / Observers and nonparticipant who will not have to be accounted for during the exercise.
'1630 00:00 Simulator is put into operation.
Reactor power is at 100 percent power. The reactor has been operating steady state for the past six months with no recent shutdowns. The Standby Gas O 1567e/20.133 l
( 4-Rev. 2 10/9/87 Page 5.5-3 ?(}. \ \.) ' Clock Scenario. Time -Time Event Message Command 1630 00:00 Treatment System (SBGTS) Train "A"
~
(Cont'd) is-out of service for changing of .; I the charcoal filters. All other power generation and safety system equipment is available and operable. Chemistry reported that.a slight increase in reactor coolant iodine concentrations have been observed for the past two weeks. This has caused the main steam line radiation monitor readings to be elevated.
.1635- 00:05 An earthquake is sensed on-site CR-M-2
( and can be felt at various locations around the plant.
'1640 00:10' Control Room operators should CR-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 damage caused by the earthquake.
This will include checking . indications on the seismic accelerometer and contacting t s 1567e/20.133
Rev. 2 10/9/87 1 ) Page 5.5-4 N,.) Clock Scenario Time Time Event Message Command 1640' 00:10 Vernon and Bellows Falls dams CR-M-4 CR-C-1A (Cont'd) for an assessment of dam status. The Shift Supervisor / Plant Emergency Director (SS/ PED) should declare an Unusual Event based upon the following EAL: AP-3125
" Natural Phenomenon": Any earthquake sensed on-site.
Operators may dispatch other plant personnel (auxiliary operators or ( (,) security force) to perform plant c inspections / tours associated with the earthquake event and other plant activities. FOR EXERCISE CR-C-2 PURPOSES, EARLY IN-STATION ACTIONS WILL BE SIMULATED AND PERFORMED BY CONTROLLERS. The SS/ PED should initiate Procedure 0.P.-3500, Unusual Event and refer to Appendix I, the SS/ PED checklist. O (O 1567e/20.133
Rev. 2 10/9/87
,,_7 Page 5.5-5 .(3_,4)
Clock. ' Scenario Time Time Event Message Command l 11640 00:10 The SS/ PED should announce (Cont'd) the Unusual Event over the Plant Paging System.. This activity will be performed by players in the Simulator CR, and simultaneously performed' I by a Controller 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 Security Shift Supervisor to start
-the emergency call-in method.
The SS/ PED should notify the NRC on the red phone and maintain communications until relieved by the TSC. The Security Shift Supervisor should notify New England Hydro Power Station of the Unusual Event. A 1567e/20.133
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Page 5.5-6 1
' Clock- Scenario-Time- Time Event Message Command
- 1640 00:10 The Primary and Secondary Duty-
- (Cont'd)- and Call Officers (DCOs) should report to the plant after notification of the Unusual Event Status.
The DCOs should contact the SS/ PED to be advised of the situation. Responsibility for TSC and-EOF Coordinator assignments would be discussed, as appropriate. The TSC Coordinator should assume O: the overall supervision and
.] +
coordination of the on-site emergency response activities. This will include escalating the emergency classification as conditions warrant. Activation of the Technical Support Center (TSC) is optional at the Unusual Event. 1700 00:30 IF AN UNUSUAL EVENT HAS NOT BEEN CR-C-3 DECLARED BY THE SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS TIME. ] 1567e/20.133
I Rev. 2 10/9/87 j
, Page 5.5-7 H Clock Scenario Time' Time- Event Message Command- I 1
1745' 01:15- The SS/ PED may request that a reactor coolant sample be taken to determine the fuel integrity of the reactor Core. 1755 01:25 A second earthquake occur'. on-site
. CR-M-5 that is more intense than the CR-M-6 first' earthquake.
The SS/ PED or TSC Coordinator will reinitiate visual inspections of the plant to determine the extent of the damage from the second~ earthquake. 1805 01:35 Plant personnel sent to. investigate OSC-M-2 the plant will discover that OSC-M-3 'l several plant systems have been OSC-M-4' l damaged. Controller / Observers acting as one CR-M-7 of the technicians who were , changing the charcoal filters , in the SBGTS Train "A," will I l i O 1567e/20.133
i Rev. 2 10/9/87 (T Page 5.5-8 l Clock Scenario Time Time Event Message Command. 1805 01:35 call the Simulator CR to report (Cont'd) that the SBGTS Train "A" has been damaged by the earthquake, and that reassembly of the unit is not possible. The SS/ PED or TSC Coordinator should start to review the plant conditions against criteria stated in Procedure AP-3125
" Emergency Plan Classification and Action Level Scheme."
[~'I 1810 01:40 The SS/ PED or TSC Coordinator should declare an ALERT based upon the following EAL: AP-3125,
" Natural ' Phenomenon": Earthquake which damages plant systems or structures.
Operators may begin a controlled power reduction, a controlled plant shutdown, or a manual SCRAM. NOTES l l
- 1. MANUAL SCRAM OF THE REACTOR CR-C-4 WILL BE CONTROLLED AT THIS TIME.
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{ Rev. 2 10/9/87 (4
) Page 5.5-9 %J Clock Scenario Time Time Event Message Command 1810 01:40 2. LOAD DISPATCHER WILL REQUEST CR-M-8 CR-C-4A (Cont'd) THAT THE PLANT BE KEPT ON-LINE AS LONG AS POSSIBLE BECAUSE OF HIGH DEMAND FOR POWER AT THIS TIME.
The SS/ PED directs the operations staff to initiate Procedure OP-3501, " Alert." An Alert announcement should be made over the plant page instructing emergency personnel (,] to report to their assigned emergency response facilities, and other personnel, contractors, and visitors return to the Governor Hunt House Information Center and wait for further information. At this time, the Technical Support Center (TSC), Operations Support Center (OSC), and the Emergency Operations Facility / , Recovery Center (E0F/RC) should be activated and staffed. O 1567e/20.133
i Rev. 2 f~t 10/9/87 i Page:5.5-10 Clock Scenario Time Time Event Message Command l 1810 01:40 The SS/ PED should notify the Vermont, (Cont'd) New Hampshire, and Massachusetts State Police' Agencies of the
,i- 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 and activate YNSD personnel group' paging system. Upon YNSD notification, the Engineering Support Center (ESC) is activated. The Security Shift Supervisor should notify the New England Hydro Power Station in Vernon of the escalation to the Alert status. O 1567e/20.133
l i i i Rev. 2 10/9/87 IT ' Page 5.5-11 i NI l 1 Clock. Scenario. l Time Time Event Message Command 1810 01:40 The Security Shift Supervisor (Cont'd) should ensure that an accountability of personnel i has been completed in accordance with procedures SP-0906 " Emergency Procedures" and OP-3524
" Emergency Actions to Ensure Accountability and Security Response."
The TSC Coordinator should respond, activate, and staff the TSC in accordance with Appendix III of r3 OP-3501, " Alert." (x 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
- 3. Reactor and Computer Supervisor (N-1567e/20.133
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Clock Scenario. . 3 ' Time Time- Event . Message Command %, 1810 01:40 4. : Operations Supervisor
-(Cont'd)-
- 5. Maintenance Supervisor.
- 6. Engineering Support Supervisor
- f. -.
- 7. GE' Resident Engineer (aslnecessary)
- 8. Plant Services Supervisor
- 9. Other staff personnel to -
fulfill the functions of the TSC (i.e., Status Board Keepers, Communicators, Switchboard Operators, etc.). The Emergency Operations Facility (EOF) Coordinator should activate and staff the EOF /RC in accordance with Appendix IV of OP-3501,
" Alert."
The emergency response staff that
' reports to the EOF /RC includes the l- following: ,
- 1. Site Recovery Manager and I_
designated corporate staff , !- 1 p 1 1567e/20.133
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fJ Rev. 2 l n 10/9/87 ti ' , Page 5.5-13 l d' T , 1 i ', Clock Scenario [ j Time Time f, Event Message Command ) 1810 01:40 2. EOF Cochdinator ' (Cont'd) / i .- Y '- 3. Purchasing Supervisor
, ,j
't Public Information Liaison
- 4. h a
- 5. Additional trained plant staff members to assume the following tag board assignments:
EOF Coordinator's Assistant
/'- g' i
.N
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- Radiological Assi 9 ant i i i
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Manpower and Planning Assiutant ,. Communications Assistant
- i Gr.ilC ogical Coordinator
- Personnel and Equipment
' Monitoring Team
.'1',
j'
- 6. Corporate Security Force
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1810 01:40' 1he10perations Support Center (OSC) (Cont'd) Coordinator (assigned by the TSC 3 Coordinator) should activate 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. Chemistry and Eealth Physics Technicians and Assistants im
- 2. Control Instrument Specialist
- 3. Lead Plant Mechanics
- 4. Status Board Caretaker
- 5. Other personnel as required.
The Site Recovery Manager (SRM) and staff should report to the EOF /RC and implement the pro edural steps listed in Append 1x VIII of OP-3501, "ulert." .f ( 1567e/20.133
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' Clock Scenario Time Time Event Message Command 1820 01:50' On-site' Assistance Teams (s) h may.be dispatched from OSC to determine the total extent of the damage from the earthquake.
n Chemistry / Health Physics l l' Technicians from the OSC may be dispatched to perform dose. rate radiation surveys, air sampling, and contamination surveys of the plant. 1825 01:55 IF AN ALERT HAS NOT BEEN DECLARED CR-C-5 BY THE SS/ PED, HE WILL BE DIRECTED TO DO SO AT THIS TIME. 1830 02:00 Main steam line radiation monitor j alarm for high radiation level. 1900 02:30 Main steam line radiation monitors EOF-1 continued to increase due to fuel ESC-1
. failure problems.
Operators continued to bring the plant down in power for a controlled plar.t shutdown. 1930 03:00 High main steam line radiation alarm annunciated which initiates a containment Group 1 isolation. 1567e/20.133 j
Rev. 2 10/9/87 Page 5.5-16 .(}v Clock Scenario Time Time Event Message Command 1930 03:00 When reactor SCRAMS automatically (Cont'd) on closure of the MSIVs, simulator control board indicates that only a partial reactor SCRAM occurred and not all control rods are fully inserted. Coincident with the closure of the MSIVs, the inboard MSIV on Main Steam Line B indicates open position, while the outboard MSIV indicates closed position.
/ -~s 4 \,._ /
Drywell radiation levels are starting to increase slightly. Operators will attempt to reset the OSC-M-5 SCRAM from the simulator control board, but are not successful. Operators may then dispatch an Auxiliary Operator to shut Valve CRD-56 in order for them to start manually inserting control rods. Operators will also attempt to close the inboard MSIV on Main Steam Line B. The inboard MSIV on Main Steam Line B indication ()
! remains in the open position.
I 1567e/20.133
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( ] l Clock Scenario Time Time Event Message Command I Approx Approx The SS/ PED should notify the ; 1935 03:05 TSC Coordinator and SRM that a partial reactor SCRAM occurred )
\
and attempts to close inboard MSIV on Main Steam Line B have been unsuccessful. The SRM, TSC Coordinator, and SS/ PED should evaluate plant conditions against Procedare AP-3125. " Emergency Plan Classification and Action tQ Level Scheme."
. ( ,/
The SRM with consultation from l the TSC Coordinator and SS/ PED should recognize the need to escalate to a Site Area Emergency. Approx Approx The Site Recovery Manager should 1945 03:15 declare a Site Area Emergency based upon the following EAL: AP-3125, " Loss of Systems or Equipment": Failure of the Reactor Protection System to accomplish a required SCRAM with the main condenser unavailable. 1567e/20.133 > > _ _ _ _ .__ ___D
Rev. 2 10/9/87 Page 5.5 Clock' Scenario Time' Time Event' Message Command
. Approx Approx If present, the SRM should inform 1945 03:15 the State representatives of Vermont, (Cont'd) New Hampshire, and Massachusetts located at the EOF /RC and contact each State's E0Cs via the Nuclear Alert System to inform them of the escalation to the Site Area Emergency.
The SS/ PED will also be directed to make the appropriate plant announcement concerning the escalation to the Site Area Energency. (} Upgraded notifications should also be made to YNSD and the NRC. Approx. Approx Operators are following procedures 1950 03:20 to place the plant in a cold shutdown condition. Operators are continuing to manually insert control rods that have not fully inserted. TSC personnel should be requested to investigate the reason why the inboard MSIV on Main Steam Line B is remaining.in the open position. 1567e/20.133 _____._m_._________________
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- - o .e Page 5.5-19 Clock. ' Scenario-
- Time ' Time Event Message Command i 2000' 03:30 .IF A SITE AREA EMERGENCY HAS NOT ' EOF /
BEEN DECLARED BY THE SRM, HE WILL -RC-C 3E DIRECTED TO DO SO AT THIS TIME. 2045- 04:15 Simulator'0perator' inserts a ESC-2 casualty that simulates a break between the inboard MSIV and the
~ outboard MSIV on Main Steam Line B outside the primary containment in the steam tunnel.
Within five seconds, simulator control board shows annunciator g "high" alarms for main steam tunnel temperature and main steam line 1 flow. The ARM in the vicinity of the control rod drive repair (Elevation 252, Rx Building) increases significantly. The Reactor Building vent. ARM alarms and trips the Reactor Building Ventilation System on high radiation. The Standby Gas Treatment System (SBGTS) is initiated automatically on Reactor Building isolation. O V 1567e/20.133
Rev. 2 ,. s . 10/9/87 Page 5.5-20 () Clock Scenario Time Time Event Message Command 2045 04:15 SBGTS Train "B" trouble alarm occurs. (Cont'd) Reactor Building area radiation monitors at various elevations are j ritarting to increase significantly. Operators will reattempt to close the inboard MSIV on Main Steam Line B. The inboard MSIV on Main Steam Line B indication remains open. In order to reduce the release of (_,) radioactive material outside of primary containment, the operators may use relief valves to manually depressurize the reactor coolant system. By reducing the reactor pressure, the leak rate in the steam tunnel decreases. 2050 04:20 The Stack Gas Monitors I/II, and hi-range monitor begin to increase as indicated by the simulator control board. A release of radioactivity to the environment begins. O 1567e/20.133
.a Rev. 2-10/9/87-Page 5.5-21 Clock ~ Scenario
' Time Time Event Message Command 2050; 04:20' Stack gas monitors continue to 1(Cont'd)' escalate,due to noble gases and iodines passing.through'the standby gas treatment charcoal filters.
The appropriate EOF staff should initiate Procedure OP-3513
" Evaluation of Off-Site
' Radiological Conditions" to determine off-site dose projections.
Off-site Monitoring Teams should be dispatched to monitor the plume in the downwind direction. The E0F Coordinator and Radiological Assistant should initiate Procedure OP-3511 "Off-Site Protective Action Recommendations" to formulate protective actions recommendations. Approx Approx The SRM, TSC Coordinator, and j 2050 04:20 SS/ PED should evaluate plant i conditions against criteria in Procedure AP-3125, " Emergency Plan Classification and Action Level Scheme." 1567e/20.133
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, Clock Scenario l Time Time Event Message Command Approx Approx The SRM, with consultation from 2050 04:20 the TSC Coordinator and SS/ PED, (Cont'd) should recognize the need to escalate to a General Emergency. Approx Approx The Site Recovery Manager may 2100 04:30 declare a General Eraergency based upon " loss of two of three fission product barriers with potential loss of the third." If present, the SRM should inform the State representatives of i Vermont, New Hampshire, and N-Massachusetts located at the EOF /RC and contact each State's EOCs via the Nuclear Alert System to inform them of the escalation to the General Emergency. t
- The SS/ PED will also be directed .
to make the appropriate plant announcement concerning the l escalation to the General Emergency. Upgraded notification of the General Emergency status should be made to YNSD and the NRC. I
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1567e/20.133
Rev. 2 10/9/87 ('"} (s_,/ Page 5.5-23 i Clock Scenario Time Event Message Command Time 2100 04:30 Team should be requested to take a plant vent stack sample especially for iodine (refer to Procedure OP-3530, " Post-Accident Sampling"). OSC teams may be dispatched to OSC-M-6 investigate the leak in the OSC-M-7 Reactor Building and problems associated with the inboard MSIV on Main Steam Line B. 2110 04:40 Releases to the environment (,,/ through the plant vent stack have exceeded 1 R/hr whole body. 2150 05:20 The SRM should declare a General Emergency based upon plant conditions producing projected l or actual site boundary whole body dose rates >l R/hr. 05:30 IF A GENERAL EMERGENDY HAS NOT EOF / 2200 BEEN DECLARED BY THE SRM, HE WILL RC-C-2 BE DIRECTED TO DO S0 AT THIS TIME. IF A NATIONAL WEATHER SERVICE EOF / UPDATE HAS NOT BEEN REQUESTED BY RC-C-3 THE RA, HE WILL BE PROVIDED WITH 1 ONE. l
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Page 5.5-24 Clock Scenario Time __ Time Event Message Command 2250 06:20 Simulator control board indications show that the inboard MSIV on Main Steam Line B has closed. Steam leakage past the inboard MSIV on Main Steam Line B has stopped. Steam tunnel temperature and radiation levels are decreasing. Area radiation monitors in the Reactor Building are decreasing. f t 2300 06:30 Plant conditions are stabilizing N and the releases to the environment have decreased significantly. 2315 06:45 Exercise is terminated. I
\ 1567e/20.133
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O I l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS, EXERCISE 1987 6.0 EXERCISE MESSAGES O 1571e/20.138
l l i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 6.1 COMMAND CARDS I l l i O 1571e/20.138
t i V-VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS DRILL 1987 SCENARIO COMMAND CARD INDEX l Card Number Clock Time Page (6.1) Page'(5.5) CR-C-1 1600 6.1-1 5. 5-2 ' CR-C-1A 1640 6.1-1A 5.5-4
'CR-C-2 1640 6.1-2 5.5-4 CR-C-3 1700 6.1-3 5.5-6 CR-C-4 1810 6.1-4 5.5-8 CR-C-4A 1810 6.1-5 5.5-9 CR-C-5 1825 6.1-6 5.5-15 EOF /RC-C-1 2000 6.1-7 5.5-19 EOF /RC-C-2 2200 6.1-8 5.5-23 a
['N . ' EOF /RC-C-3 2200 6.1-9 5.5-23 NMC-C-1 After G.E. 6.1-10 l k j.
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, Rev. 1 l~ 9/18/87 l l O
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Page 6.1-1 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO.: CR-C-1 T0: Shift Supervisor CLOCK TIME: 1600-1630 LOCATION: Simulator Control Room SCENARIO TIME: 0 min. PARTICIPANT MESSAGE THIS IS A DRILL Communications systems that are available in the Control Room have been duplicated in the Simulator Control Room Area EXCEPT for Gaitronics and the plant evacuation alarm. SIMULATE the use of the Gaitronics/ Plant Evacuation Alarm and an Exercise Controller will complete the required PA announcements from the actual Control Room. THIS IS A DRILL 1571e/20.138 LJ 1 1 ___.________-___-_O
1[ Rev. 1 9/18/87 Page.6.1-1A l VERMONT YANKEE NUCLEAR POWER STATION, l EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1987~ SCENARI0' COMMAND CARD I~ FROM: Simulator CR Controller COMMAND NO.: CR-C-1A
'TO:
Shift Supervisor ~ CLOCK TIME: 1640 or when needed LOCATION: Simulator Control Room -SCENARIO TIME: 10 min. PARTICIPANT MESSAGE. THIS IS A DRILL FOR EXERCISE PURPOSES, Control' Room communications with Vernon and Bellows Falls Dams will be simulated. . SEE MESSAGE CR-M-4.
.i THIS IS A DRILL 1571e/20.138 4
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Rev. 1 9/18/87 (~~T Page 6.1-2 l C/ I VERMONT YANKEE NUCLEAR POWER STATION , EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1987 l SCENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO.: CR-C-2 i TO: Shift Supervisor CLOCK TIME: 1640 LOCATION: Simulator Control Room SCENARIO TIME: 10 min. PARTICIPANT MESSAGE THIS IS A DRILL Early in-station actions will be simulated and information requested at this time will be provided by controllers.
.PN
'%]
THIS IS A DRILL 1571e/20.138 O
Rev. 1 e- 9/18/87 ( Page 6.1-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 KENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO.: CR-C-3 TO: Shift Supervisor CLOCK TIME: 1700 LOCATION: Simulator Control Room SCENARIO TIME: 30 min. PARTICIPANT MESSAGE THIS IS A DRILL DECLARE AN UNUSUAL EVENT DUE TO INDICATION OF AN EARTHQUAKE SENSED ON-SITE (AP-3125, Natural Phenomenon). . %s THIS IS A DRILL 1 1571e/20.138 l 1
Rev. 1 9/18/87 i Page 6.1-4 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO.: CR-C-4 TO: Shift Supervisor CLOCK TIME: 1810 or when needed l LOCATION: Simulator Control Room SCENARIO TIME: 1:40 i PARTICIPANT MESSAGE THIS IS A DRILL FOR EXERCISE PURPOSES, DO NOT MANUAL SCRAM THE REACTOR AT THIS TIME. v) l THIS IS A DRILL l l 1571e/20.138
Rev. 1 9/18/87 1 Page 6.1-5 VERMONT. YANKEE NUCLEAR POWER STATION
-EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO COMMAND CARD l
[ FROM: Simulator CR Controller COMMAND NO.: CR-C-4A ! TO: Shift Supervisor / Plant. CLOCK TIME: 1810 or when needed Emergency Director LOCATION: Simulator Control Room' SCENARIO TIME: 1:40 PARTICIPANT MESSAGE THIS IS A DRILL FOR EXERCISE PURPOSES, Control Room communications with the Load Dispatcher will be simulated. . SEE MESSAGE CR-M-8. THIS IS A DRILL 1 I { 1571e/20.138 o i
J { Rev. 1 9/18/87 () 7s Page 6.1-6 ) VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO.: CR-C-5 TO: Shift Supervisor / Plant CLOCK TIME: 1825 Emergency Director LOCATION: Simulator Control Room SCENARIO TIME: 1:55 PARTICIPANT MESSAGE THIS IS A DRILL DECLARE AN ALERT BASED UPON AN EARTHQUAKE SENSED ON-SITE WHICH DAMAGES PLANT SYSTEMS OR STRUCTURES (AP-3125, Natural Phenomenon). g-k> m THIS IS A DRILL 1 l
, 1571e/20.138 1
l l 1 Rev. 1 9/18/87 Page 6.1-7 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO COMMAND CARD FROM: EOF /RC Controller COMMAND NO.: EOF /RC-C-1 TO: Site Recovery Manager CLOCK TIME: 2000 LOCATION: EOF /RC SCENARIO TIME: 3:30 PARTICIPANT MESSAGE THIS IS A DRILL DECLARE A SITE AREA EMERGENCY DUE TO FAILURE OF THE REACTOR PROTECTION SYSTEM TO ACCOMPLISH A REQUIRED SCRAM WITH THE MAIN CONDENSER UNAVAILABLE (AP-3125, Loss of Systems or Equipment):
- 1. Group 1 isolation.
- 2. Reactor power greater than five percent after SCRAM.
THIS IS A DRILL 1571e/20.138 l
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Page 6.1-8 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO COMMAND CARD i FROM: EOF /RC Controller COMMAND NO.: EOF /RC-C-2 TO: Site Recovery Manager- CLOCK TIME: 2200 t . LOCATION: EOF /RC SCENARIO TIME: 05:30 l-PARTICIPANT MESSAGE THIS IS A DRILL DECLARE A GENERAL EMERGENCY DUE TO PROJECTED OR ACTUAL SITE BOUNDARY WHOLE BODY DOSE RATES >l R/HR. O THIS IS A DRILL 1571e/20.138 I
Rev. 1
- c. 9/18/87 s ,) Page 6.1-9 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO COMMAND CARD FROM: EOF /RC Controller COMMAND NO.: EOF /RC-C-2 TO: Radiological Assistant CLOCK TIME: 2200 t LOCATION: EOF /RA-Dose Assessment Area SCENARIO TIME: 05:30 PARTICIPANT MESSAGE THIS IS A DRILL REQUEST A NATIONAL WEATHER SERVICE FORECAST UPDATE AT THIS TIME (OP-3513) (SEE MESSAGE CARD EOF-2).
(~n
/
THIS IS A DRILL 1571e/20.138 4
/
Rev. 1 9/23/87 Page 6.1-10 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY. RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: News Media Center Controller MESSAGE NO.: NMC-C-1 TO: Manager of Communications CLOCK TIME: After G.E. LOCATION: News Media Center SCENARIO TIME:. After G.E. PARTICIPANT MESSAGE THIS IS A DRILL The News Media Center Controller will initiate several calls to the News Media
. Center. The phone calls,.made after the declaration of the GENERAL EMERGENCY, will' test the adequacy of rumor control and the ability of the News Media Center personnel to clarify and disseminate nuclear power plant accident-related information.
( ). One or two calls will be made directly to the plant emergency organization staff to' evaluate the ability to recognize and redirect News Media Center related calls. I
/T )
k~sI THIS IS A DRILL I 1606e/23.59 l J
I' O i i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 6.2 MESSAGE CARDS O i, [ ' 1572e/3.31
l l
. y~m
( )
.'V VERMONT Y ANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS DRILL 1987 SECTION 6.2 SCENARIO MESSAGE CARD INDEX Clock Time Page (5.5) Page (6.2)
Card Number. 1600 5.5-2 6.2-1 CR-M-1
*
- 6.2-5 CR-M-1A
*
- 6.2-9 TSC-M-1
*
- 6.2-13 TSC-M-2A
*
- 6.2-14 TSC-M-2B
*
- 6.2-15 OSC-M-1
*
- 6.2-19 EOF /RC-M-1
*
- 6.2-23 ESC-M-1
*
- 6.2-27 VT-REP-M-1
*
- 6.2-31 MA-REP-M-1
*
- 6.2-35 NH-REP-M-1 1635 5.5-3 6.2-39 CR-M-2 1640 5.5-3 6.2-40 CR-M-3 1640 5.5-4 6.2-41 CR-M-4 CR-M-5 1755 5.5-7 6.2-42 1755 5.5-7 6.2-43 CR-M-6 1805 5.5-7 6.2-46 OSC-M-2 1805 5.5-7 6.2-47 OSC-M-3 1805 5.5-7 6.2-48 OSC-M-4 1805 5.5-7 6.2-44 CR-M-7 1810 5.5-9 6.2-45 l CR-M-8 1900* 5.5-15 6.2-52 EOF-1 2200* ** 6.2-53 EOF-2 1900* 5.5-15 6.2-54 f ESC-1 1930 5.5-16 6.2-49 OSC-M-5 2045 5.5-19 6.2-55 ESC-2 2100 5.5-23 6.2-50 OSC-M-6 2100 5.5-23 6.2-51 OSC-M-7
i Rev. 2
< 9/18/87 j Page 6.2-1
( l~'J't
\-- \
VERMONT YANKEE NUCLEAR POWER STATION (
) -
EMERGENCY RESPONSE PREPAREDNESS EXERCISE l l 1 f SCENARIO MESSa,GE CARDS j
' t i
> (.~ FROM: Simulator CR Controller MESSAGE NO.: CR-M-1 4 TO: Shif t Supervisor CLOCK TIME: 1600 - 1630 LOCATION: Simulator Control Room SCENARIO TIME: 00:00 PARTICIPANT MESSAGE h'
THIS IS A DRILL For initial conditions, see attached pages.
'l i
i
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f
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7 t i
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f t I l l j (N, - THIS IS A DRILL I l 1572e/3.31 ) l i
i i Rev. 2 9/18/87
. /T
! 4 Page 6.2-2 N)
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 6.2 INITIAL CONDITIONS i I (This information will be provided to the players at the start of the exercise).
? ., The reactor is operating at approximately 100 percent rated power.
The reactor has been operating steady state for the past six months with no recent shutdowns. 2a. A slight increase in reactor coolant iodine concentration has been observed for the past two weeks. (j
\
D 2b. The setpoint on the main steam line monitors have been raised to 300 mR/hr due to high background. 2c. The night orders state: "If you reach the alarm setpcint for the main steam line radiation monitors, DO NOT decrease power at a rate not greater than 1% per minute; also, DO NOT SCRAM the reactor unless isolation is imminent."
- 3. The Standby Gas Treatment System Train "A" is out of service for !
charcoal filter replacement.
- 4. All other power generating equipment is operating, and all safety system equipment is operable.
l 1
- 5. The initial plant and Reactor System parameters associated with the
]
j start of the erarcise are shown in Table 6.2-1. I 1572e/3.31 4
l
'1 Rev. 2 9/18/87 Page 6.2-3 -~)
Q ,l
- 6. The following on-site meteorological conditions exist at 1630: !
Wind Speed, mph (upper / lower) 2.6/2.4 Wind Direction, degrees (ups.er/ lower) 189/218 ] l Delta Temperature, F (upper / lower) -0.87/-0.58 l Ambient Temperature, F 18.6 ! Precipitation, inches 0.0
- 7. Synoptic (regional) meteorological conditions:
A typical winter day in Vermont; a cold front passed through the area a day ago. Today the high temperatures during the day reached into the mid-20's. Lows expected tonight in the teens. Winds light and variable. I
\
9 (_,) 1572e/3.31
Rev. 2 9/18/87 (-
\
Page 6.2-4 TABLE 6.2-1 l
' Initial Plant and Reactor System Values Reactor Vessel Coolant Level 158 inches Reactor Pressure 1,000 psig Reactor Power - APRM (average) 100%
Core Plate Differential Pressure 20 psid Total Core Flow 48 mil lbs/hr Main Steam Line Flow - Total 6.2 mil lbs/hr Main Steam Line Radiation 250 mR/hr Condenser Hotwell Level 59% Condenser Vacuum 2.5 inches Hg Condensate Storage Tank Level 75% Reactor Coolant Temperature 5270F RR Drive Flow (average) 30,000 gpm Feedwater Flow 6.42 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.7 psig Drywell Temperature 1350F Torus Water Level 1.15 ft Torus Temperature 760F f-w Drywell/ Torus 02 Concentration 2.8% (,) HR Containment Monitors 1.0 R/hr Containment Gas /Part 4,000/3,000 epm Reactor Building Vent Monitors Gas /Part 150/1,500 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Jet Air Ejector 100 mR/hr Stack Gas I/II 20/30 cpm High Range Noble Gas <0.1 mR/hr
,m \ 1572e/3.31 ,
t i
W Rev. 2 9/18/87 !
') Page 6.2-5
'( V j VERMONT YANKEE NUCLEAR PGWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE i
SCENARIO MESSAGE CARDS FROM: Control Room Controller MESSAGE NO.: CR-M-1A TO: Control Room Supervisor CLOCK TIME: 1600 - 1630 l l LOCATION: Control Room SCENARIO TIME: 00:00 PARTICIPANT MESSAGE I THIS IS A DRILL For initial conditions, see attached pages. I i
.f% ^
(> O THIS IS A DRILL L) 1572e/3.31 1 l
1 a i, Rev. 2 9/18/87 !: Page 6.2-6 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1987 ) I 1 i 1 6.2 INITIAL CONDITIONS j (This.information will be provided to the players at the start of the exercise).
- 1. The' reactor'is operating at approximately 100 percent rated power.
The reactor has.been operating steady state for the past six months with no recent shutdowns. 2a.'A slight increase;in reactor coolant iodine concentration has been observed for the past two weeks. 2b. The setpoint'on the main steam line monitors have been raised to. 300 mR/hr due to high background. l
-2c. The night orders state: "If you reach the alarm setpoint for the i main steam line radiation monitors, DO NOT decrease power at a rate not greater than 1% per minute; also, DO NOT SCRAM the reactor unless isolation is imminent."
- 3. The Standby Gas Treatment System Train "A" is out of service for charcoal filter replacement.
- 4. All other power generating equipment is operating, and all safety i system equipment is operable.
- 5. The initial plant and Reactor System parameters associated with the start of the exercise are shown in Table 6.2-1.
O\ . 1572e/3.31 A
Rev. 2 ! 9/18/87 l
; ,.s) Page 6.2-7
\_/
- 6. The following on-site meteorological conditions exist at 1630:
Wind Speed, mph (upper / lower) 2.6/2.4 Wind Direction, degrees (upper / lower) 189/218 ! Delta Temperature, F (upper / lower) -0.87/-0.58 l Ambient Temperature, F 18.6 1 Precipitation, inches 0.0 j
- 7. Synoptic (regional) meteorological conditions:
A typical winter day in Vermont; a cold front passed through the area j a day ago. Today the high temperatures during the day reached into 1 the mid-20's. Lows expected tonight in the teens. Winds light and variable. f~%;
'% )
e!
+
n
! I
\- ' 1572e/3.31 :
i
)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ l
Rev. 2 L 9/18/87 Page 6.2 ' TABLE 6.2-1 Initial Plant and Reactor System Values
, Reactor Vessel Coolant Level 158 inches )
Reactor Pressure 1,000 psig Reactor Power - APRM (average) .100% Core Plate Differential Pressure 20 psid Total Core Flow 48 mil lbs/hr Main Steam Line Flow - Total 6.4 mil lbs/hr Main Steam Line Radiation 250 mR/hr Condenser Hotwell Level 59%
. Condenser Vacuum 2.5 inches Hg Condensate Storage Tank Level 75%
Reactor Coolant Temperature 5270F
-RR Drive Flow (average) 30,000 gpm Feedwater Flow 6.42 mil lbs/hr y' Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.7 psig
.Drywell Temperature 1350F Torus Water Level 1.15 ft Torus Temperature 760F Drywell/ Torus 02 Concentration 2.8%
v HR Containment Monitors 1.0 R/hr Y Containment Gas /Part 4,000/3,000 cpm Reactor Building Vent Monitors Gas /Part 150/1,500 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Je_t Air Ejector 100 mR/hr Stack Gas I/II . 20/30 cpm High Range Noble Gas <0.1 mR/hr i 1572e/3.31
! I Rev. 2
- f. 9/18/87 Page 6.2-9 l /'-]
(..) VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l l SCENARIO MESSAGE CARDS FROM: TSC Controller MESSAGE NO.: TSC-M-1 TO: TSC Coordinator CLOCK TIME: Upon TSC Activation LOCATION: TSC SCENARIO TIME: PARTICIPANT MESSAGE , THIS IS A DRILL For initial conditions, see attached pages.
't%,
g
^ THIS IS A DRILL
( - p 1572e/3.31 i
Rev. 2 9/18/87 (} V Page 6.2-10 "JERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 6.2 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The reactor is operating at approximately 100 percent rated power.
The reactor has been operating steady state for the past six months with no recent shutdowns, i 2a. A slight increase in reactor coolant iodine concentration has been
,-s observed for the past two weeks.
N_ / i 2b. The setpoint on the main steam line monitors have been raised to 300 mR/hr'due to high background. 2c. The night orders state: "If you reach the alarm setpoint for the main steam line radiation monitors, DO NOT decrease power at a rate not greater than 1% per minute; also, DO NOT SCRAM the reactor unless isolation is imminent."
- 3. The Standby Gas Treatment System Train "A" is out of service for charcoal filter replacement.
- 4. All other power generating equipment is operating, and all safety system equipment is operable.
- 5. The initial plant and Reactor System parameters associated with the
,-s start of the exercise are shown in Table 6.2-1.
\- 1572e/3.31
Rev. 2 9/18/87 e-~s Page 6.2-11 i t ! x -)
- 6. The following on-site meteorological conditions exist at 1630:
Wind Speed, mph (upper / lower) 2.6/2.4 Wind Direction, degrees (upper / lower) 189/218 Delta Temperature, F (upper / lower) -0.87/-0.58 Ambient Temperature, F 18.6 Precipitation, inches 0.0
- 7. Synoptic (regional) meteorological conditions:
A typical winter day in Vermont; a cold front passed through the area a day ago. Today the high temperatures during the day reached into the mid-20's. Lows expected tonight in the teens. Winds light and variable. 4 l 1 I 1 l
/
f 1572e/3.31 I l l
I Rev. 2 9/18/87
--) Page 6.2-12 TABLE 6.2-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 158 inches Reactor Pressure 1,000 psig Reactor Power - APRM (average) 100%
Core l'iate Differential Pressure 20 psid Total Core Flow 48 mil lbs/hr Main Steam Line Flow - Total 6.4 mil lbs/hr ; Main Steam Line Radiation 250 mR/hr Condenser Hotwell Level 59% Condenser Vacuum 2.5 inches Hg Condensate Storage Tank Level 75% Reactor Coolant Temperature 5270F RR Drive Flow (average) 30,000 gpm Feedwater Flow 6.42 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.7 psig Drywell Temperature 1350F Torus Water Level 1.15 ft Torus Temperature 760F Drywell/ Torus 02 Concentration 2.8% f')
\- '
HR Containment Monitors Containment Gas /Part 1.0 R/hr 4,000/3,000 cpm Reactor Building Vent Monitors Gas /Part 150/1,500 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Jet Air Ejector 100 mR/hr Stack Gas I/II 20/30 cpm High Range Noble Gas <0.1 mR/hr 4
)
(3 ( ,) 1572e/3.31 l l l _ _ _ _ _ _ _ _ _ _ _ _ _______ _ _ _ -
1' Rev. 2 9/18/87 L /]- Page 6.2-13 N.} VERMONT YANKEE NUCLEAR POWER STATION j EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987. SCENARIO MESSAGE CARDS FROM: TSC Controller MESSAGE NO.: TSC-M-2A TO: TSC Coordinator CLOCK TIME: Upon assignment of data recorder l LOCATION: TSC SCENARIO TIME: PARTICIPANT MESSAGE THIS IS A DRILL To obtain plant computer information that is normally accessible by TSC personnel, utilize the Controller / Observer telephone communication that is available in the Plant Computer Room. o /O THIS IS A DRILL V 1572e/3.31
. _ _ _ __________L
Rev. 2 } 9/18/87 [)
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Page 6.2-14 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: TSC Controller MESSAGE NO.: TSC-M-2B T0: TSC Coordinator CLOCK TIME: Upon assignment of communicators LOCATION: TSC SCENARIO TIME: PARTICIPANT MESSAGE l0 THIS IS A DRILL (s ) When assigning your TSC Communicators to the Control Room, simulate tbis action and the prestaged TSC Communicators at the Simulator Control Room will be activated and utilized. 3 THIS IS A DRILL 1572e/3.31
Rev. 2 9/18/87 Page 6.2-15 ll\m) VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 l l S_CENARIO MESSAGE CARDS FROM: OSC Controller MESSAGE NO.: OSC-M-1 , TO: OSC Coordinator CLOCK TIME: Upon OSC Activation LOCATION: OSC SCENARIO TIME: PARTICIPANT MESSAGE g~s THIS IS A DRILL NJ For initial conditions, see attached pages. l s I l THIS IS A DRILL 1572e/3.31
I l l l Rev. 2 9/18/87 Page 6.2-16 (} x_.- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 6.2 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The reactor is operating at approximately 100 percent rated power.
The reactor has been operating steady state for the past six months with no recent shutdowns. 2a. A slight increase in reactor coolant iodine concentration has been
, -~s observed for the past two weeks. $vl 2b. The setpoint on the main steam line monitors have been raised to 300 mR/hr due to high background.
S 2c. The night orders state: "If you reach the alarm setpoint for the main steam line radiation monitors, DO NOT decrease power at a rate not greater than 1% per minute; also, DO NOT SCRAM the reactor unless isolation is imminent."
- 3. The Standby Gas Treatment System Train "A" is out of service for charcoal filter replacement.
- 4. All other power generating equipment is operating, and all safety system equipment is operable. .
1
- 5. The initial plant and Reactor System parameters associated with the start of the exercise are shown in Table 6.2-1.
i,-~)
1572e/3.31 l
. Rev. 2 9/18/87
('"3 Page 6.2-17
\~-)
- 6. The following on-site meteorological conditions exist at 1630:
Wind Speed, mph (upper / lower) 2.6/2.4 Wind Direction, degrees (upper / lower) 189/218 Delta Temperature, F (upper / lower) -0.87/-0.58 Ambient Temperature, F 18.6 Precipitatfen, inches 0.0
- 7. Synaptic (regional) meteorological conditions:
A typical winter day in Vermont; a cold front passed through the area a day ago. Today the high temperatures during the day reached into the mid-20's. Lows expected tonight in the teens. Winds light and l variable. fN (_) e
% i i
I 1 l 1 O (m l 1572e/3.31 L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
Rev. 2 9/18/87 ('~3 Page 6.2-18
%)
TABLE 6.2-1 Initial Plant and Reactor System Values
' Reactor Vessel Coolant Level 158 inches Reactor Pressure 1,000 psig Reactor Power - APRM (average) 100%
Core Plate Differential Pressure 20 psid Total Core Flow 48 mil lbs/hr ; Main Steam Line Flow - Total 6.4 mil lbs/hr i Main Steam Line Radiation 250 mR/hr Condenser Hotwell Level 59% Condenser Vacuum 2.5 inches Hg Condensate Storage Tank Level 75% Reactor Coolant Temperature 5270F RR Drive Flow (average) 30,000 gpm Feedwater Flow 6.15 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H O 2 Drywell Pressure 1.7 psig Drywell Temperature 1350F Torus Water Level 1.15 ft Torus Temperature 760F J's Drywell/ Torus 02 Concentration 2.8% i) s~~ HR Containment Monitors 1.0 R/hr Containment Gas /Part 4,000/3,000 cpm ; Reactor Building Vent Monitors Gas /Part 150/1,500 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Jet Air Ejector 100 mR/hr Stack Gas I/II 20/30 cpm High Range Noble Gas <0.1 mR/hr I l l ~ o
- 1572e/3.31
Rev. 2 9/18/87 Page 6.2-19 j ()T VERMONT YANKEE NULLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1987 I SCENARIO MESSAGE CARDS FROM: EOF /RC Controller MESSAGE NO.: EOF /RC-M-1 Site Recovery Manager / CLOCK TIME: Upon Activation TO: EOF Coordinator LOCATION: EOF /RC SCENARIO TIME: PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages. Ns l l THIS IS A DRILL (} 1572e/3.31
l 1 l l Rev. 2 l 9/18/87 Page 6.2-20 l . [~ hl G: VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987
\
l 6.2 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The reactor is operating at approximately 100 percent rated power.
The reactor has been operating steady state for the past six months with no recent shutdowns. I 2a. A slight increase in reactor coolant iodine concentration has been observed for the past two weeks. f-~s 2b. The setpoint on the main steam line monitors have been raised to 300 mR/hr due to high background. 2c. The night orders state: "If you reach the alarm setpoint for the main steam line' radiation monitors, DO NOT decrease power at a rate not greater than 1% per minute; also, DO NOT SCRAM the reactor unless isolation is imminent." .
- 3. The Standby Gas Treatment System Train "A" is out of service for charcoal filter replacement.
- 4. All other power generating equipment is operating, and all safety system equipment is operable.
- 5. The initial plant and Reactor System parameters associated with the start of the exercise are shown in Table 6.2-1.
1572e/3.31
Rev. 2 9/18/87 (
\_)/
Page 6.2-21
- 6. The following on-site meteorological conditions exist at 1630:
Wind Speed, mph (upper / lower) 2.6/2.4 Wind Direction, degrees (upper / lower) 189/218 > Delta Temperature, F (upper / lower) -0.87/-0.58 Ambient Temperature, F 18.6 Precipitation, inches 0.0
- 7. Synoptic (regional) meteorological conditions:
A typical winter day in Vermont; a cold front passed through the area a day ago. Today the high temperatures during the day reached into the mid-20's. Lows expected tonight in the teens. Winds light and variable. O l l i l 1
'-' 1572e/3.31 l
l 1
Rev. 2 9/18/87 1 Page 6.2-22 A) TABLE 6.2-1 Initial Plant and Reactor System Values Reactor' Vessel Coolant Level 158 inches Reactor Pressure 1,000 psig
-Reactor Power - APRM (average) 100%
Core' Plate Differential Pressure 20 psid Total Core Flow 48 mil lbs/hr Main Steam Line Flow - Total 6.4 mil lbs/hr Main ~ Steam Line Radiation 250 mR/hr Condenser Hotwell Level 59% Condenser Vacuum 2.5 inches Hg Condensate Storage Tank Level 75*
' Reactor Coolant Temperature 5270F RR Drive-Flow (average) 30,000 gpm Feedwater Flow 6.42 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.7 psig Drywell Temperature 1350F Torus Water Level 1.15 ft Torus Temperature 760F Drywell/ Torus 02 Concentration 2.8%
- HR Containment Monitors 1.0 R/hr
-' Containment Gas /Part 4,000/3,000 cpm Reactor Building Vent Monitors Gas /Part 150/1,500 cpm Reactor Building. Vent Exhaust N/S 1.0/1.0 mR/hr u Steam Jet Air Ejector 100 mR/hr Stack Gas I/II 20/30 cpm High Range Noble Gas <0.1 mR/hr
) 1572e/3.31
Rev. 2 9/18/87 Page 6.2-23 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: ESC Contro11er MESSAGE NO.: ESC-M-1 TO: ESC Director CLOCK TIME: Upon Activation LOCATION: SCENARIO TIME: PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages. l l l D THIS IS A DRILL 1572e/3.31
t' I
~t:
Rev. 2 9/18/87
' /N - Page 6.2-24 Q.
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1987 6.2 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise). i
- 1. 'The reactor is operating at approximately 100 percent rated power.
The reactor has been operating steady state for the past six months with no recent shutdowns. l 2a. A slight increase in reactor coolant iodine concentration has been observed for the past two weeks. 2b. The setpoint on the main steam line monitors have been raised to 300 mR/hr due to high background. 2c. The-night orders state: "If you reach the alarm setpoint for the main steam line radiation monitors, DO NOT decrease power at a rate
.not greater than 1% per minute; also, DO NOT SCRAM the reactor unless isolation is imminent."
- 3. The Standby Gas Treatment System Train "A" is out of service for :
charcoal filter replacement. l 1
- 4. All other power generating equipment is operating, and all safety system equipment is operable.
l 5. The initial plant and Reactor System parameters associated with the
,. start of the exercise are shown in Table 6.2-1.
\~ -
1572e/3.31 l C
. - - - - - - - - ---__-_-__-___D
I- Rev. 2 9/18/87 O I Page 6.2-25 I
%)
- 6. The following on-site meteorological conditions exist at 1630:
Wind Speed, mph (upper / lower) 2.6/2.4 Wind Direction, degrees (upper / lower) 189/218 Delta Temperature, F (upper / lower) -0.87/-0.58 Ambient Temperature, F 18.6 Precipitation, inches 0.0
- 7. Synoptic (regional) meteorological conditions:
4 A typical winter day in Vermont; a cold front par ed through the area a day ago. Today the high temperatures during the day reached into the mid-20's. Lows expected tonight in the teens. Winds light and variable. (~%, G r i 1572e/3.31
4 Rev. 2 9/18/87
) Page 6.2-26 x /
TABLE 6.2-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 158 inches Reacter Pressure 1,000 psig ; Reactor Power - APRM (average) 100% Core Plate Differential Pressure 20 psid ; Total Core Flow 48 mil lbs/hr Main Steam Line Flow - Total 6.4 mil lbs/hr Main Steam Line Radiation 250 mR/hr Condenser Hotwell Level 59% l 2.5 inches Hg Condenser Vacuum Condensate Storage Tank Level 75% Reactor Coolant Temperature 5270F RR Drive Flow (averagn) 30,000 gpm Feedwater Finw 6.42 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.7 psig Drywell Temperature 1350F Torus Water Level 1.15 ft Torus Temperature 760F Drywell/ Torus 02 Concentration 2.8% t'
- HR Containment Monitors 1.0 R/hr Containment Gas /Part 4,000/3,000 epm ,
Reactor Building Vent Monitors Gas /Part 150/1,500 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Jet Air Ejector 100 mR/hr Stack Gas I/II 20/30 cpm High Range Noble Gas (0.1 mR/hr I i ') 1572e/3.31 u_ __
Rev. 2 9/18/87 Page 6.2-27
/~~'T qf VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: EOF State Observer MESSAGE NO.: VT-REP-M-1 TO: Vermont State Representative CLOCK TIME: Upon Arrival at EOF /RC LOCATION: EOF /RC SCENARIO TIME: ,
PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages. I l l l l f~'% THIS IS A DRILL
\m- )
1572e/3.31 l 1
i i 1 j Rev. 2 9/18/87 O Page 6.2-28 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 6.2 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The reactor is operating at approximately 100 percent rated power.
The reactor has been operating steady state for the past six months with no recent shutdowns. 2a. A slight increase in reactor coolant iodine concentration has been observed for the past two weeks. 2b. The setpoint on the main steam line monitors have been raised to 300 mR/hr due to high background. 2c. The night orders state: "If you reach the alarm setpoint for the main steam line radiation monitors, DO NOT decrease power at a rate not greater than 1% per minute; also, DO NOT SCRAM the reactor unless isolation is imminent." l 3. The Standby Gas Treatment System Train "A" is out of service for charcoal filter replacement.
- 4. All other power generating equipment is operating, and all safety system equipment is operable.
S. The initial plant and Reactor System parameters associated with the start of the exercise are shown in Table 6.2-1. 1572e/3.31
Rev. 2 9/18/87 - I' Page 6.2-29 N_))
- 6. The following on-site meteorological conditions exist at 1630:
Wind Speed, mph (upper / lower) 2.6/2.4 Wind Direction, degrees (upper / lower) 189/218 Delta Temperature. F (upper / lower) -0.87/-0.58 Ambient Temperature, F 18.6 Precipitation, inches 0.0
- 7. Synoptic (regional) meteorological conditions:
A typical winter day in Vermont; a cold front passed through the area a day ago. Today the high temperatures during the day reached into the mid-20's. Lows expected tonight in the teens. Winds light and variable. O l l l l l I i 1 i i O 1572e/3.31
1 1 Rev. 2 j 9/18/87 I
-~ Page 6.2-30
'" TABLE 6.2-1 Initial Plant and Reactor System Values l Reactor Vessel Coolant Level 158 inches ! Reactor Pressure 1.000 psig Reactor Power - APRM (average) 100% Core Plate Differential Pressure 20 psid Total Core Flow 48 mil lbs/hr Main Steam Line Flow - Total 6.4 mil lbs/hr Main Steam Line Radiation 250 mR/hr Condenser Hotwell Level 59% Condenser Vacuum 2.5 inches Hg Condensate Storage Tank Level 75% Reactor Coolant Temperature 5270F RR Drive Flow (average) 30.000 gpm Feedwater Flow 6.42 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.7 psig Drywell Temperature 1350F Torus Water Level 1.15 ft Torus Temperature 760F Drywell/ Torus 02 Concentration 2.8% O N-HR Containment Monitors Containment Gas /Part Reactor Building Vent Monitors Gas /Part 1.0 R/hr 3.000/4.000 cpm 150/1,500 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Jet Air Ejector 100 mR/hr Stack Gas I/II 20/30 cpm High Range Noble Gas <0.1 mR/hr () 1572e/3.3.
Rev. 2 9/18/87 Page 6.2-31
/) %)
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: EOF State Observer MESSAGE NO.: MA-REP-M-1 TO: Massachusetts State CLOCK TIME: Upon Arrival at Representative EOF /RC LOCATION: EOF /RC SCENARIO TIME: PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages.
/' N N
i THIS IS A DRILL ( 1572e/3.31 ! 1 l
i Rev. 2 9/18/87 p Page 6.2-32 U VERMONT YANKEE NUCLEAR POWER STATION ; i EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1987 6.2 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise),
- 1. The reactor is operating at approximately 100 percent rated power.
The reactor has been operating steady state for the past six months with no recent shutdowns. , 2a. A slight increase in reactor coolant iodine concentration has been observed for the past two weeks. O V 2b. The setpoint on the main steam line monitors have been raised to 300 mR/hr due to high background. 2c. The night orders state: "If you reach the alarm setpoint for the main steam line radiation monitors, DO NOT decrease power at a rate not greater than 1% per minute; also, DO NOT SCRAM the reactor unless isolation is imminent."
- 3. The Standby Gas Treatment System Train "A" is out of service for charcoal filter replacement.
- 4. All other power generating equipment is operating, and all safety system equipment is operable.
- 5. The initial plant and Reactor System parameters associated with the start of the exercise are shown in Table 6.2-1.
1572e/3.31
Rev. 2 9/18/87 f s Page 6.2-33 ( 6. The following on-site meteorological conditions exist at 1630: Wind Speed, mph (upper / lower) 2.6/2.4 Wind Direction, degrees (upper / lower) 189/218 Delta Temperature, F (upper / lower) -0.87/-0.58 Ambient Temperature, F 18.6 Precipitation, inches 0.0
- 7. Synoptic (regional) meteorological conditions:
A typical winter day in Vermont; a cold front passed through the area a day ago. Today the high temperatures during the day reached into the mid-20's. Lows expected tonight in the teens. Winds light and variable. l l l 1572e/3.31 l
Rev. 2 9/18/87 (] Page 6.2-34 V TABLE 6.2-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 158 inches Reactor Pressure 1,000 psig Reactor Power - APRM faverage) 100% Core Plate Differential Pressure 20 psid Total Core Flow 48 mil lbs/hr Main Steam Line Flow - Total 6.4 mil lbs/hr Main Steam Line Radiation 250 mR/hr Condenser Hotwell Level 59% Condenser Vacuum 2.5 inches Hg Condensate Storage Tank Level 75%
- Reactor Coolant Temperature 5270F RR Drive Flow (average) 30,000 gpm Feedwater Flow 6.42 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H O2 Drywell Pressure 1.7 psig Drywell Temperature 1350F Torus Water Level 1.15 ft Torus Temperature 760F
,- g Drywell/ Torus 02 Concentration 2.8%
(') HR Containment Monitors Containment Gas /Part 1.0 R/hr 4,000/3,000 cpm Reactor Building Vent Monitors Gas /Part 150/1,500 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Jet Air Ejector 100 mR/hr Stack Gas I/II 20/30 cpm High Range Noble Gas <0.1 mR/hr 4 ("
- k
\ 1572e/3.31
Rev. 2 9/18/87 Page 6.2-35 (^"'} ' N~J VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: EOF State Observer MESSAGE NO.: NH-REP-M-1 TO: New Hampshire State CLOCK TIME: Upon Arrival at Representative EOF /RC LOCATION: EOF /RC SCENARIO TIME: PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages.
/*
i L 1 THIS IS A DRILL 1572e/3.31 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l
Rev. 2 9/18/87
<s Page 6.2-36 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 6.2 INITIAL CONDITIONS (This information will be provided to the players at the start of the l exercise).
- 1. The reactor is operating at approximately 100 percent rated power.
The reactor has been operating steady state for the past six months with no recent shutdowns. 2a. A slight increase in reactor coolant iodine concentration has been observed for the past two weeks. i
%d 2b. The setpoint on the main steam line monitorc have been raised to 300 mR/hr due to high background.
l 2c. The night orders state: "If you reach the alarm setpoint for the main steam line radiation monitors, DO NOT decrease power at a rate not greater than 1% per minute; also, DO NOT SCRAM the reactor unless isolation is imminent."
- 3. The Standby Gas Treatment System Train "A" is out of service for charcoal filter replacement.
- 4. All other power generating equipment is operating, and all safety system equipment is operable, f
- 5. The initial plant and Reactor System parameters associated with the start of the exercise are shown in Table 6.2-I. j O 1572e/3.31
Rev. 2 9/18/87 . Page 6.2-37
- 6. The following on-site meteorological conditions exist at 1630:
Wind Speed, mph (upper / lower) 2.6/2.4 Wind Direction, degrees (upper / lower) 189/218 Delta Temperature, F (upper / lower) -0.87/-0.58 Ambient Temperature, F 18.6 Precipitation, inches 0.0
- 7. Synoptic (regional) meteorological conditions:
A typical winter day in Vermont; a cold front passed through the area a day ago. Today the high temperatures during the day reached into the mid-20's. Lows expected tonight in the teens. Winds light and variable. ; O O 1572e/3.31 _ _ _ _ _ _ _ _ _ _ _ a
t Rev. 2 l 9/18/87 , ,m Page 6.2-38 I TABLE 6.2-1 Initial Plant and Reactor System Values l Reactor Vessel Coolant Level 158 inches Reactor Pressure 1.000 psig Reactor Power - APRM (average) 100% Core Plate Differential Pressure 20 psid Total Core Flow 48 mil lbs/hr Main Steam Line Flow - Total 6.4 mil lbs/hr Main Steam Line Radiation 250 mR/hr Condenser Hotwell Level 75% Condenser Vacuum 2.5 inches Hg Condensate Storage Tank Level 13.4 feet Reactor Coolant Temperature 5270F RR Drive Flow (average) 30,000 gpm Feedwater Flow 6.42 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.7 psig Drywell Temperature 1350F Torus Water Level 1.15 ft Torus Temperature 760F Drywell/ Torus 02 Concentration 2.8%
/O HR Containment Monitors 1.0 R/hr k Containment Gas /Part 4,000/3,000 cpm Reactor Building Vent Monitors Gas /Part 150/1.500 cpm Reactor Building Vent Exhaust N/S 1.0/1.0 mR/hr Steam Jet Air Ejector 100 mR/hr Stack Gas I/II 20/30 cpm High Range Noble Gas <0.1 mR/hr i
I l t 1572e/3.31
l Rev. 2 9/18/87 f' ~N Page 6.2-39 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 l SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO.: CR-M-2 T0: Shift Supervisor CLOCK TIME: 1635 - 1640 LOCATION: Simulator CR SCENARIO TIME: 00:05 - 00:10 PARTICIPANT MESSAGE THIS IS A DRILL I Guard House called to report that they sensed the ground move and that abnormal river motion is being observed. S o g-lh kla ce b o h t A plant technician who was working in G m.~ ~ - ri i called to report that he felt the floor moving and several items were dislodged from their storage racks uae to the abnormal building motion. v / THIS IS A DRILL 1572e/3.31
Rev. 2 9/18/87 p Page 6.2-40
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 l SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO : CR-M-3 T0: Shift Supervisor CLOCK TIME: 1640 LOCATION: SCENARIO TIME: 00:10-PARTICIPANT MESSAGE THIS IS A DRILL Auxiliary operator reports a positive indication on the seismic accelerometer. l l l
/]
ud THIS IS A DRILL 1572e/3.31
7 l Rev. 2 9/18/87
- ~ .
Page 6.2-41 ! VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 i SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO.: CR-M-4 i TO: Shift Supervisor CLOCK TIME: 1640 (Approximate) LOCATION: Simulator CR SCENARIO TIME: 00:10 PARTICIPANT MESSAGE THIS IS A DRILL i Dam personnel from the Vernon and Bellows Falls Dams have been contacted and report that they have observed abnormal river motion, but that the dams are still intact and exhibit no signs of failure. m ( ) L/
< THIS IS A DRILL
( 1572e/3.31
Rev. 2
,, 9/18/87 Page 6.2-42
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO.: CR-M-5 T0: Shift Supervisor CLOCK TIME: 1755 LOCATION: Simulator CR SCENARIO TI!!E: 01:25 ' PARTICIPANT MESSAGE THIS IS A DRILL A second tremor is felt in the Control Room. More intense than the first shake. Liquid spills out of some full coffee cups. 1 i 1 . l
)
THIS IS A DRILL L) 1572e/3.31 i
1 1 4. Rev. 2 9/18/87 Page 6.2-43 VERMONT YANKEE NUCLEAR POWER STATION j EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 l SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO.: CR-M-6 TO: Shift Supervisor CLOCK TIME: 1755 LOCATION: Simulator CR SCENARIO TIME: 01:25 PARTICIPANT MESSAGE THIS IS A DRILL Security calls to let SS know motion sensor on fence went off. Gilt some ground motion prior to alarm. O l i THIS IS A DRILL 1572e/3.31
l I Rev. 2 9/18/87 A Page 6.2-44 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO.: CR-M-7 TO: Shift Supervisor CLOCK TIME: 1815 (Approximate) LOCATION: Simulator CR SCENARIO TIME: 01:45 PARTICIPANT MESSAGE i THIS IS A DRILL ! One of the maintenance technicians who was replacing the charcoal in Standby Gas Treatment Unit A reported that, due to severe structural distortion of the unit's housing, they cannot reassemble the unit. Two access covers cannot be installed as required. Repairs are estimated to take at least 48 hours. O I i THIS IS A DRILL 1572e/3.31
Rev. 2 9/18/87 Page 6.2-45 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO.: CR-M-8 T0: Shift Supervisor CLOCK TIME: 1810 (Approximate) , l LOCATION: Simulator CR SCENARIO TIME: 01:40 PARTICIPANT MESSAGE THIS IS A DRILL When notified of the plant status, the Load Dispatcher requests that the plant be kept on-line as long as possible because of an unusually high power demand. i
~
7 THIS IS A DRILL ( 1572e/3.31 I '
Rev. 2 9/18/87 ] Page 6.2-46
]
V l VERMONT YANKEE NUCLEAR POWER STATION J EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1 1987 i
}
SCENARIO MESSAGE CARDS j FROM: OSC Observer MESSAGE NO.: OSC-M-2 TO: Auxiliary Operator CLOCK TIME: 1805 (Approximate) LOCATION: Switchgear Room, El. 252' SCENARIO TIME: 01:35 PARTICIPANT MESSAGE THIS IS A DRILL You obst.tve positive indication of an earthquake on the seismic event accelerometer. l
/7 THIS IS A DRILL l
t O 1572e/3.31
I l Rev. 2 9/18/87 j es Page 6.2-47
i
( VERMONT YANKEE NUCLEAR POWER STATION I l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 I i L i SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-M-3 TO: Auxiliary Operator CLOCK TIME: 1810 (Approximate) LOCATION: Turbine Building, E1. 232'-6" SCENARIO TIME: 01:40 PARTICIPANT MESSAGE 1 1 THIS IS A DRILL You are observing a moderate leak from the flanged connection below TI-104-17B l on the service water return line from the stator liquid cooling unit heat
- l. exchanger.
The leak has not worsened since you arrived. The leak appears to be coming from a separation at the flange faces. [ ~)
- O 1
4 i
-~ THIS IS A DRILL 1572e/3.31 1
____ __ a
Rev. 2 9/18/87 Page 6.2-48 (}-
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-M-4 TO: Auxiliary Operator CLOCK TIME: 1810 (Approximate) LOCATION: Turbine Building, E1. 228'-6" SCENARIO TIME: 01:40 PARTICIPANT MESSAGE THIS IS A DRILL Upon inspection for damages caused by the earthquake, you have noticed several pipe hangers and supports which have become partially dislodged from the building structure. Several systems are affected (Service Water, Condensate, Fire Protection) but the piping hangers and supports associated with these systems show some minor signs of stress. Several pieces of concrete and grouting are laying on the floor but the piping itself is still intact. l l ( THIS IS A DRILL k. 1572e/3.31
Rev. 2 9/18/87 l jN Page 6.2-49 l
; i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-M-5 TO: Auxiliary Operator CLOCK TIME: 1930 (Approximate)
LOCATION: Valve CRD-56 SCENARIO TIME: 03:00 PARTICIPANT MESSAGE THIS IS A DRILL Report to the Simulator Control Room that you have just shut Valve CRD-56. bv l l l l THIS IS A DRILL
\
1572e/3.31
i Rev. 2 ! l 9/18/87
,CT Page 6.2-50
%)
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-N-6 TO: A0 Investigating Steam Leak CLOCK TIME: 2050 (Approximate) LOCATION: CRD Repair Room Door SCENARIO TIME: 04:20 PARTICIPANT MESSAGE THIS IS A DRILL The door leading into the CRD Repair Room is very warm, radiation levels are available from controller. Steam vapor is weeping from around the door perimeter. THIS IS A DRILL 1572e/3.31
l Rev. 2 9/18/87 ! (j) f- s Page 6.2-51 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-M-7 TO: A0 Investigating Steam Leak CLOCK TIME: 2055 LOCATION: Steam Tunnel /CRD Repair Room SCENARIO TIME: 04:20 PARTICIPANT MESSAGE THIS IS A DRILL You observe so much steam that visibility is drastically impaired, you can hear the steam leak, but cannot locate it. Radiation levels are available from controller. l l l l l 1 1 THIS IS A DRILL 1572e/3.31
Rev. 2 9/18/87 f ~s Page 6.2-52 b) VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: EOF /RA Controller MESSAGE NO.: EOF-1 TO: Radiological Assistant CLOCK TIME: 1900 or as Requested LOCATION: EOF / Dose Assessment Area SCENARIO TIME: 02:30 PARTICIPANT MESSAGE THIS IS A DRILL 12:00-18:00 - General Area Forecast i Party cloudy with light and variable winds expected this afternoon. High temperatures in the mid-20's, with a 10% chance of precipitation. As a strong high pressure system moves further east along the central eastern seaboard, a low prersure system is expected to deepen in the Great Lakes region g bringing colder Canadian air to the northeast in two days. Winds expected from A/ the southwest between 4-8 mph tonight, low temperatures in the teens. Also, 50% chance of flurries late tonight. THIS IS A DRILL O 1572e/3.31 ! l 1 1 l
Rev. 2 9/18/87 [N Page 6.2-53 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: EOF /RA Controller MESSAGE NO,: EOF-2 TO: Radiological Assistant CLOCK TIME: 2200 or as Requested LOCATION: EOF / Dose Assessment Area SCENARIO TIME: 05:30 PARTICIPANT MESSAGE THIS IS A DRILL 18:00-02:00 - General Area Forecast Light snow expected with little accumulation, changing to rain by early morning. Low around 140F tonight, winds four to eight mph from the southwest. A strong low pressure system is moving northeast from the Great Lakes region. Chance of snow, changing over to rain, as the system moves into our area. Accumulation of up to an inch may be expected in low-lying areas and ( j two to three inches in the mountains, before changing back to rain by morning. Late tomorrow, light rain clearing overnight. Hazardous driving conditions may be expected tomorrow. [ THIS IS A DRILL 1572e/3.31 t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Rev. 2 9/18/87 Page 6.2-54 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1967 SCENARIO MESSAGE CARDS i FROM: ESC Controller MESSAGE NO.: ESC-1 TO: ESC Meteorologist CLOCK TIME: 1900 or as Requested LOCATION: ESC Framingham, Massachusetts SCENARIO TIME: 02:30 PARTICIPANT MESSAGE THIS IS A DRILL For the data form, see attached page. O l I l s
'I l
THIS IS A DRILL i ' 1572e/3.31 6 (
l Rev. 2 9/18/87 O Page 6.2-54B (,,)i WEATHER FORECAST FOR SITE: VERMONT YANKEE Date of Forecast: 12/1/87 Time of Forecast: 1900 Current Site Meteorology (as of 1830 ): Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower 5.1 mph 125 deg from -0.52 0F D 0.00 in/15 min Upper 10.9 mph 239 deg from -0.80 0F D Forecast Site Meteorology: Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation A. 1830- Lower 5 mph 180 deg from -- 0F E 0.00in/15 min 1930 Upper 10 mph 180 deg from -- 0F E B. 1930- Lower 3 mph 180 deg from -- 0F E 0.00in/15 min 2030 Upper 6 mph 180 deg from -- 0F E (( ,j C . 2030- Lower 2 mph 180 deg from -- 0F E 0.01in/15 min , 2130 Upper 6 mph 180 deg from -- 0F E National Weather Service Forecast for site region: Partly cloudy with light and variable winds expected this afternoon. High temperatures in the mid-20's, with a 10% chance of precipitation. As a strong high pressure system moves further east along the central eastern i seaboard, a low pressure system is expected to deepen in the Great Lakes region l bringing colder Canadian air to the northeast in two days. Winds expected from the southwest between 4-8 mph tonight, low temperatures in the teens. Also, 50% chance of flurries late tonight. Special Weather Statements: Chance of precipitation after midnight. Unseasonably cold for this time of year. Winds will tend to go up valley this evening at approximately S mph. l'
\~ ' 1572e/3.31
l l Rev. 2 l
,- 9/18/87 Page 6.2-55 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 SCENARIO MESSAGE CARDS FROM: ESC Controller MESSAGE NO.: ESC-2 TO: ESC Meteorologist CLOCK TIME: 2045 LOCATION: ESC Framingham, Massachusetts SCENARIO TIME: 04:15 or as Requested PARTICIPANT MESSAGE THIS IS A DRILL
'For the data form, see attached page.
O
\,_/
[ THIS IS A DRILL 1572e/3.31 l
-- _ _ - - ___________________a
Rev. 2 9/18/87 Page 6.2-55B WEATHER FORECAST FOR SITE: VERMONT YANKEE Date of Forecast: 12/1/87 Time of Forecast: 2048- _ Current Site. Meteorology (as of 2015 ): l Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower 1.2 mph 274 deg from -0.45 0F D 0.00 in/15 min Upper 8.2 mph 133 deg from -0.72 0F D Forecast Site Meteorology: Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation A. 2015- Lower 2 mph 180 deg from -- F E 0.011n/15 min 2115 Upper 6 mph 180 deg from -- 0F E B. 2115- Lower 2 mph 180 deg from -- 0F E 0.011n/15 min 2215 Upper 5 mph 180 deg from -- 0F E C. 2215- Lower 2 mph 180 deg from. - 0F E 0.0lin/15 min 2314 Upper 5 mph 180 deg from -- 0F E National Weather Service Forecast for site region: Light snow expected with little accumulation, changing to rain by early morning. Low around 140F tonight, winds four to eight mph from the southwest. A strong low pressure system is moving northeast from the Great Lakes region. . Chance of snow, changing over to rain, as the system moves into our area. Accumulation of up to an inch may be expected in low-lying areas and two to three inches in the mountains, before changing back to rain by morning. Late tomorrow, light rain clearing overnight. Hazardous driving conditions may be expected tomorrow. Special Weather Statements: The area in the vicinity of the plant (up to ten miles) should get mostly rain. Winds will continue'from the south at 8 mph up the valley until mid-morning tomorrow when they will come from the west at 5 mph. The total rainfall should be approximately 0.4 inches by the end of tomorrow. 1572e/3.31
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 I 7.0 PLANT EVENT DATA l O l l l [ O 1573e/1.161 1 1 i
i O ; VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987
'7 .1 EVENTS SUIT 1ARY O
O 1573e/1.161
Rev. 2 9/18/87 Page 7.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 7.1 EVENTS
SUMMARY
The following information and supplementary material are provided for those controllers having in-plant control assignments so as to further ensure the proper development of the scenario. The information provided in this section assumes that the " players," who are dispatched to perform repair, rescue, or other activities, will take certain actions in rSaponse to the scenario. The controller / observer must be cognizant { of the actions of those players to which assignment is given and provide information regarding the results of the players actions as appropriate. The information provided in this section does not preclude l the possibility that the controller will be required to provide additional information to the players. Approximate Miniscenario Time Event Location 7.2.1 1805 Verification of Seismic SWGR Room Event Turbine Bldg. El. 252' Plant Damage Assessment Turbine Bldg. I 7.2.2 1810 o Stator Liquid Cooling E1. 232'-6" Unit Plant Damage Assessment Turbine Bldg. l 7.2.3 1815 o Feedwater Piping El. 228'-6" Penetrations 7.2.4 1815 Damaged SBGTS Unit Reactor Bldg. El. 280' 1573e/1.161
1 Rev. 2 j 9/18/87 1 Page 7.1-2 g 7.1 EVENTS
SUMMARY
(Cont'd) Approximate l Location Miniscenario Time Event 7.2.5 1930 Operation of Valve Reactor Bldg. CRD-56 El. 252' I 7.2.6 2050 Entry into CRD Repair Reactor Bldg. Room El. 252' i l 1573e/1.161 1
v VERMONT YANKEE NUC1. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 7.2 EVENT MINISCENARIOS O O 1573e/1.161
i
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l Rev. 2 9/18/87 Page 7.2.1-1 ('~}1 Q, i J VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1 Miniscenario 7.2.1 i l I. General Description At 1755, a second earthquake is sensed on-site. II. Description of Player Responses / Observations / Corrective Actions The SS/ PED may dispatch an A0 to the seismic event accelerometer located in the Switchgear Room (Turbine Building, El. 252'). Upon reaching the seismic event accelerometer, the controller will inform the A0 that the indicator is sticking out indicating that a seismic event has occurred. The A0 shall report this information to the CR (refer to message Card CR-M-3). III. Event Closecut Event is terminated after the A0 reports his findings to the CR. l b) L 1573e/1.161
Rev. 2
~~s 9/18/87
(,) Page 7.2.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE Miniscenario 7.2.2 I. General Description After notification from various sources that an apparent earthquake has occurred, the SS/ PED should dispatch available personnel to inspect plant equipment for damage. II. Description of Player Responses / Observations / Corrective Actions While inspecting plant equipment for damage, an A0 discovers that a flanged connection on the service water return lines from the stator liquid cooling unit Heat Exchanger B has partially separated. A (,) moderate leak is observed. The efficiency of the heat exchanger does not appear to be compromised, and the leak has not worsened since first discovered. No other damage to the unit is apparent. Corrective actions taken may include attempts to " remake" the connection which will reduce the leakage by approximately half its original amount; they may simply attempt to collect leakage by using whatever means are immediately available; or they may isolate one heat exchanger, in which case, the leak will be eliminated. III. Event Closecut When corrective actions as directed by the CR/TSC are completed. In addition, the CR (simulator) is notified of the corrective actions. O 1573e/1.161
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VERMONT YANKEE NUCLEAR POWER STATION , EMERGENCY RESPONSE PREPAREDNESS EXERCISE l l Miniscenario 7.2.3 General Descript!on ! I. I After notification from various sources that an apparent earthquake has occurred, the SS/ PED should dispatch available personnel to inspect plant equipment for damage. II. Description of Player Responses / Observations / Corrective Actions While inspecting plant equipment for damage caused by the seismic event, an A0 notices several pipe hangers partially dislodged from the building structure. The lines affected are reactor feedwater pump suction lines r (Turbine Building El. 228'-6"). There is no apparent damage to the pipe (x itself, but a small amount of concrete has been damaged due to the lateral movements. III. Event Closeout This event is closed out when the A0 makes his report to the SS/ PED. 1 There are no actions which can be taken by station staff to correct this problem, with the exception of attempting to temporarily support the affected lines. l 1573e/1.161 1 I
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Rev. 2 j 9/18/87 Page 7.2.4-1 (~T Q VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE Miniscenario 7.2.4 I. General Description Prior to the earthquakes, a maintenance crew was performing a scheduled maintenance procedure on the "A" Standby Gas Treatment System (SBGTS). The second earthquake has caused significant damage to the unit such that reassembly is not possible. II. Description of Player Responses / Observations / Corrective Actions While attempting to reassemble the unit, the maintenance crew realizes that the access covers which had been removed for maintenance cannot be reinstalled due to severe structural distortion of the unit's housing. Without these covers in place, the unit is inoperable. (This information will be passed on to the CR from a Controller identifying himself as one of the maintenance technicians.) If requested to provide an estimated repair time, he shall respond stating that, due to the severity of structural distortion, extensive modifications would be required, and the unit would be out of service for at least 48 hours as a minimum. III. Event Closecut The event is terminated when all the information above is transmitted to the CR/TSC. O O 1573e/1.161
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l Rev. 2 9/18/87 Page 7.2.5-1 [~ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE Miniscenario 7.2.5 l l I. General Description l l l After the partial SCRAM, a number of control rods fail to insert as l required. Shift Supervisor will follow OE-3101, " Reactivity Control l Emergevey Procedure." Operators will attempt to reset the SCRAM and drive rods. Resetting of the SCRAM will not be possible due to the initiating condition (main steam line high radiation) still being present. In order to drise rods individually, Valve CRD-56 has to be I manually shut by an operator. II. Description of Player Responses / Observations / Corrective Actions
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N~J An A0 should be dispatched to shut Valve CRD-56. When he reaches the valve location, the Controller will tell him to simulate any actions he would take regarding valve repositioning (Simulator Operator will insert this action into the simulator), and report to the CR/TSC that CRD-56 has been shut. III. Event Closecut Event is terminated when A0 reports his actions to the CR/TSC that CRD-56 is shut. 1573e/1.161
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Rev. 2 9/18/87 f-~3 Page 7.2.6-1 i', } VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE Miniscenario 7.2.6 I. General Description Entry into CRD Repair Room to investigate steam leak. II. Description of Player Responses / Observations / Corrective Actions The SS/ PED may request that the steam leak be investigated. An operator would be requested to enter the CRD Repair Room. Necessary protective clothing / equipment would be required. If the person feels the door at the CRD Repair Room entrance, it is extremely warm and steam vapor is weeping from the door perimeter, radiation levels will be provided by ( the Controller (per Section 9.3-5, Figure 9.3-5). If the person N ventures inside the door, he experiences poor visibility due to steam, extreme noise due to the leak, and high radiation. No assessment of damage can be safely made until the leak is isolated. III. Event Closeout The event is closed out when the operator either determines that entry is impossible or, if entry is made, the conditions above are reported to the SS/ PED. , 1 l l m 1573e/1.161
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 8.0 OPERATIONAL DATA O NOTE: The operational data is highly dependent on operator actions taken in response to the conditions presented within the scenario. The data reflects plant conditions assuming certain basic operator response actions being taken. l 0
i i i l Rev.- 2 9/25/87 Page 8.0-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 8.0 OPERATIONAL DATA Scenario Tine (hr: min) 00:00- 00:15 00:30 00:45 Clock Time 16:30 16:45 17:00- 17:15 l Item Panel Inst ID Description _ Units i 1 9-5 6-97 WR Press psig 1000 1000 1000 1000 3 9- 6-98 P 10b8 10b8- 10b8 10b j 4 9-5 6-98 WR Level inches- 160 160 160 160
- 5. 9 CR Position In/Out Out Out Out Out 6 9-6 LI-111-1 HW Level N % 59 59 59 .59 9-6 LI-111-2 HW Level S % 59 58 58 58 7
8 9-7 PI-101-29' Cond. Vac in_Hg 2.5 2.5 2.5 2.5 9 9--21 TE-2-126A Steam Tun. Temp. OF 114 114 114 115 10 9-21 TE-13-77A Steam Tun. Temp. O. 113 113 114 113 11 9-21 TE-23-105A Steam Tun. Temp.- 01 115 113 114 115 12 9-25 -(2)TR 149-1 DW Area Temp. OF 135 135 135 135 13 (4) DW Area Temp. OF 134 134 134 134 14 9-25 LI-46A/B Torus Level ft. 1.15 1.15 1.15 1.15 t 15 9-25 PR-1-156-3 DW Torus AP psid 1.84 1.84 1.84 1.84 16 9-26 PI-1-125-3A Rx Bldg. AP in H 2O .75 .75 .75 .75 or B 17 9-47 16-19-40 Torus Temp. OF 75.5 75.5 75.5 75.5 18 9-26 SBGT Flow cfm 0 0 0 0 19 CAD DW/ Torus 02 Cone % 2.8 2.8 2.8 2.8 20 9-3 SRVs SRV Position Open/Close Closed Closed Closed Closed 21 9-3 FI-14-50A CS "A" Flow gpm x 0 0 0 0 103 22 9-3 F2-14-50B CS "B" Flow gpm x 0 0 0 0 103 23 9-3 FI-23-108-1 HPCI Flow gpm x 0 0 0 0 103 9-3 LI-23-73 CST Level - 75 75 75 75 24 25 9-3 FI-10-139A RHR "A" Flow g"pm x 0 0 0 0 103 26 9-3 FI-10-139B RER "B" Flow gpm x 0 0 0 0 103 27 9-4 FI-12-141A RWCU Flow gpm 120 120 120 120 and B Total 28 9-4 FR-20-528 DW EQ Sump gpm 0 0 0 0 ' 29 9-4 FR-20-528 DW Floor Sump gpm 0 0 0 0 30 9-4 FI-13-91 RCIC Flow gpm 0 0 0 0 31 9-4 Recire Rx Cool. Temp. OF 526 527 527 527 Recorder 1568e/26.84 - - - - - - _ - - - _ J
l Rev. 2 9/25/87 (~S Page 8.0-2 x Scenario Time (hr: min) 00:00 00:15 00:30 00:45 Clock Time 16:30 16:45 17:00 17:15 Item Panel Inst ID Description Units 9-4 2.-3-9 2A RR Drive A gpm x 28 31 31 30 32 103 RR Drive B gpm x 28 31 31 31 33 9-4 2-3-92B 103 7-46A APRM/IRM A % 100 100 100 99 34 9-5 9-5 7-46A APRM/IRM B % 99 98 99 100 l 35 7-46B APRM/IRM C % 99 99 99 99 36 9-5 7-46B APRM/IRM D % 98 98 99 100 37 9-5
% 99 99 99 99 38 9-5 7-46C APRM/IRM E APRM/IRM F % 100 98 99 99 39 9-5 7-46C 40 9-5 7-43 A SRM A cps 5x105 5x105 5x105 5x105 41 9-5 7-43 B SRM B cps 5x105 5x105 5x105 5x10f 42 9-5 7-43 C SRM C cps 5x105 5x105 5x105 5x105 9-5 7-43 D SRM D cps 5x105 5x105 5x105 5x105 43 FI-3-310 CRD Flow gpm 49 49 49 49 44 9-5 45 9-5 6-96 FW Flow mlb/hr 6.42 6.42 6.42 6.42 46 9-5 6-96 NR Level inches 158.9 158.9 158.9 158.9 47 9-5 6-3-95 Core Flow mlb/hr 46.7 47 47.5 47
('; 48 9-5 6-3-95 Core AP psid 21 21 21 21 G/ j J 1568e/26.84 l 1 _ . . _ _ . . ________________i
l l l Rev. 2 ! 9/25/87 l Page 8.0-3 l r~'s lO 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 8.0 OPERATIONAL DATA. Scenario Time (hr: min) 01:00 01:15 01:30 01:45 17:30 17:45 18:00 18:15 Clock Time Item Panel Inst ID Description Units psig 1000 1000 1000 1000 1 9-5 6-97 WR Press MSL Flow mlb/hr 6.4 6.4 6.4 6.4 2 9-5 6-97 I psig 1006 1006 1006 1006 3 9-5 6-98 NR Press inches 160 160 160 160 4 9-5 6-98 WR Level In/Out Out Out Out Out 5 9-5 CR Position
% 59 59 59 59 6 9-6 LI-111-1 HW Level N
% 59 58 58 58 7 9-6 LI-111-2 HW Level S Cond. Vac in Hg 2.5 2.5 2.5 2.5 8 9-7 PI-101-29 115 Steam Tun. Temp. OF 115 114 115 9 9-21 TE-2-126A 115 Steam Tun. Temp. OF 114 115 113 10 9-21 TE-13-77A 115 TE-23-105A Steam Tun. Temp. OF 115 115 114 11 9-21 135 (2)TR 149-1 DW Area Temp. OF 135 135 135 12 9-25 134 135 DW Area Temp. OF 135 134 13 (4) 1.15 1.15 LI-46A/B Torus Level ft. 1.15 1.15 14 9-25 1.8 psid 1.8 1.8 1.8
(y 15 16 9-25 9-26 PR-1-156-3 DW Torus oF FI-1-125-3A Rx Bldg. AP in H 2O .75 .75 .75 .75 or B 75.5 Torus Temp. OF 75.5 75.5 75.5 17 9-47 16-19-40 0 cfm 0 0 0 18 9-26 SBGT Flow
% 2.8 2.8 2.8 2.8 19 CAD' DW/ Torus 02 Conc 20 9-3 SRVs SRV Position Open/Close Closed Closed Closed Closed gpm x 0 0 0 0 21 9-3 FI-14-50A CS "A" Flow 103 gpm x 0 0 0 0 22 9-3 FI-14-50B CS "B" Flow 103 gpm x 0 0 0 0 23 9-3 FI-23-108-1 HPCI Flow 103 75 75 75 75 24 9-3 LI-23-73 CST Level %
0 0 gpm x 0 0 25 9-3 FI-10-139A RHR "A" Flow 103 gpm x 0 0 0 0 26 9-3 FI-10-139B RHR "B" Flow 103 gpm 120 120 120 120 27 9-4 FI-12-141A RWCU Flow and B Total *
- DW EQ Sump gpm 0 0 28 9-4 FR-20-528 0 DU Floor Sump gpm 0 0 0 29 9-4 FR-20-528 0 gpm 0 0 0 30 9-4 FI-13-91 RCIC Flow OF 527 527 527 527 31 9-4 Recire Rx Cool. Temp.
Recorder () 1568e/26.84
Rev. 2 9/25/87 O Page 8.0 Scenario Time (hr: min) 01:00 01:15' 01:30 01:45 Clock Time 17:30 17:45 18:00 --18:15 Item Panel Inst ID Description Units 9-4 2-3-92A RR Drive A gpm x 30 30 30 28 32 103
'33 9-4 2-3-92B RR Drive B gpm x 30 '30 30 28 103 9-5 7-46A APRM/IRM A % 99 99 100 100 34
% 98 99 99 99 35 .9-5 7-46A APRM/IRM B '
9-5 7-46B APRM/IRM C % 99 100- 99 100 36
% 99 99 98 98 37 9-5 7-46B APRM/IRM D APRM/IRM E % 99 99 100 100 38" 9-5 7-46C 7-46C APRM/IRM F % 99 99 100. 100 39 9-5 9-5 7-43 A SRM A cps 5x105 5x105 .5x105 5x105 40 41 9-5 7-43 B SRM B cps 5x105 '5x105 5x105 5x105 7-43 C SRM C cps 5x105 3xio5 5x105 5x105 42 ~9-5 7-43 D SRM D cps 5x105 5x105 5x105 5x105 43 9-5 49 49 '49 49 44' 9-5 FI-3-310 CRD Flow gpm
~45- 9-5 6-96 FW Flow- mlb/hr 6.4 6.4 6.4- 6.4 9-5 6-96 NR Level inches 158.9 159.8 158.9 158.9 46 47 9-5 6-3-95 Core Flow mlb/hr 47.2- 47.2 47.2 47.2 9-5 6-3-95 Core AP psid 21 21 21 20.9 48
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Rev. 2 9/25/87 Page 8.0-5 (D
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 8.0 OPERATIONAL DATA Scenario Time (hr: min) 02:00 02:15 02:30 02:45 Clock Time 18:30 18:45 19:00 19:15 Panel Inst ID Description Units
. Item .
WR Press psig 1000 990 970 960 1 9-5 6-97 6-97 MSL Flow mlb/hr 5.9 5.5 4.3 3.5 2 9-5 957 6-98 NR Press psig 997 991 969 3 9-5 WR Level inches 160 160 160 160 4 9-5 6-98 CR Position In/Out Out Out Out Out 5 9-5 59 59 59 59 6 9-6 LI-111-1 HW Level N % 58 58 58 56 7 9-6 LI-111-2 HW Level S % PI-101-29 Cond. Vac in Hg 2.4 2.28 1.9 1.7 8 9-7 Steam Tun. Temp. OF 115 114 115 115 9 9-21 TE-2-126A Steam Tun. Temp. OF 114 114 113 114 10 9-21 TE-13-77A TE-23-105A Steam Tun. Temp. OF 115 115 114 115 11 9-21 (2)TR 149-1 DW Area Temp. OF 135 134 134 135 12 9-25 DW Area Temp. OF 135 134 134 134 13 (4) 1.15 Torus Level 1.15 1.15 1.15 () (,,/ 14 15 9-25 9-25 LI-46A/B PR-1-156-3 DW Torus AP ft. psid 1.8 1.8 1.8 1.8 FI-1-125-3A Rx Bldg. AP in H 2O .75 .75 .75 .75 16 9-26 or B 16-19-40 Torus Temp. OF 75.5 75.5 75.5 75.5 17 9-47 cfm 0 0 0 0 18 9-26 SBGT Flow
% 2.8 2.8 2.8 2.8 19 CAD DW/ Torus 02 Conc 20 9-3 SRVs SRV Position Open/Close Closed Closed Closed Closed Flow gpm x 0 0 0 0 21 9-3 FI-14-50A CS "A" 103 "B" Flow gpm x 0 0 0 0 22 9-3 FI-14-50B CS 103 gpm x 0 0 0 0 23 9-3 FI-22-108-1 HPCI Flow ;
103 75 75 75 75 l 24 9-3 LI-23-73 CST Level T.
"A" Flow gpm x 0 0 0 0 !
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- 28 9-4 FR-20-528 DW EQ Sump gpm DW Floor Sump gpm 0 0 0 0 29 9-4 FR-20-528 gpm 0 0 0 0 30 9-4 FI-13-91 RCIC Flow Recire Rx Cool. Temp. OF 525 524 517 512 31 9-4
,-s Recorder k- / 1568e/26.84
3 Rev. 2 9/25/87 3 q Page 8.0-6 ig Scenario Time (hr: min) 02:00 02:15 02:30 02:45 i Clock Time 18:30 18:45 19:00 19:15 Item Panel Inst ID Description Units gpm x 28 25 18 13 32 9-4 2-3-92A RR Drive A 103 gpm x 27 25 19 13 33 9-4 2-3-92B RR Drive B 103
% 93 88 70 58 34 9-5 7-46A APRM/IRM A
% 94 87 69 58 35 9-5 7-46A APRM/IRM B
% 93 88 70 57 36 9-5 7-46B APRM/IRM C
% 93 88 70 57 37 9-5 7-46B APRM/IRM D
% 94 87 69 58 38 9-5 7-46C APRM/IRM E
% 94 87 69 57 39 9-5 7-46C APRM/IRM F cps 5x105 5x105 3x105 105 40 9-5 7-43 A SRM A 7-43 B SRM B cps 5x105 5x105 4xio5 105 41 9-5 105 7-43 C SRM C cps 5x105 5x105 3x105 l 42 9-5 105 7-43 9 SRM D cps 5x105 5x105 3x105 43 9-5 49 gpm 49 49 49 l 44 9-5 FI-3-310 CRD Flow 6-96 FW Flow mlb/hr 5.94 5.59 4.37 3.56 45 9-5 158 6-96 NR Level inches 158 159 158 4 46 9-5 22.3 9-5 6-3-95 WT Core Flow mlb/hr 43.5 40.7 29.3 47 Core AP psid 18.4 16.6 10.4 7.4 48 9-5 6-3-95 l
- DW Equipment Sump Flow - may be cycling between 0 and 50 gpm.
t 1568e/26.84 i
Rev. 2 9/25/87 ( Page 8.0-7 C ! VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 8.0 OPERATIONAL DATA Scenario Time (hr: min) 03:00 03:15 03:30 03:45 Clock Time 19:30 19:45 20:00 20:15 Item Panel Inst ID Description Units WR Press psig 930 820 880 840 1 9-5 6-97 mlb/hr 1.25 0 0 0 2 9-5 6-97 MSL Flow NR Press psig 930 821 887 835 3 9-5 6-98 WR Level inches 150 150 150 170 4 9-5 6-98 CR Position In/Out In In In In 5 9-5 LI-111-1 HW Level N % 59 59 58 SS 6 9-6 HW Level S 58 58 58 56 7 9-6 LI-111-2 % PI-101-29 Cond. Vac in Hg 1.7 11 16.5 20.5 8 9-7 OF 115 114 114 115 9 9-21 TE-2-126A Steam Tun. 16np. Steam Tun. Temp. OF 114 113 113 115 10 9-21 TE-13-77A 114 114 115 114 11 9 -21 TE-23-105A Steam 'Iun. Te-n. OF (2)TR 149-1 DW Area Tem, OF 135 135 135 135 12 9-25 DW Area Temp. OF 135 135 135 135 13 (4) 1.4 Torus Level 1.15 1.29 1.42 (' 14 9-25 9-25 LI-46A/B PR-1-156-3 DW Torus AP ft. psid 1.79 1.55 1.25 1.71 ( 15 PI-1-125-3A Rx Bldg. AP in H 2O .74 .74 .35 .35 16 9-26 or B 16-19-40 Terus Temp. OF 75 108 112 114 17 9-47 SBGT Flow cfm 0 0 1450 1450 18 9-26
% 2.8 2.8 2.8 2.8 19 CAD DW/ Torus 02 Conc ** ** ** **
20 9-3 SRVs SRV Position Open/Close CS "A" Flow gpm x 0 0 0 0 21 9-3 FI-14-50A 103 FI-14-50B "B" Flow gpm x 0 0 0 0 22 9-3 CS 103 gpm x 0 0 0 0 23 9-3 FI-23-108-1 HPCI Flow 103 CST Level 75 75 7) i5 24 9-3 LI-23-73 5l, 9-3 FI-10-139A RER "A" Flow gpm x 5.5 5.5 5.5 5.5 25 103 FI-10-139B RHR "B" Flow gpm x 6.5 6.5 6.5 6.5 26 9-3 103 gpm 120 120 120 120 27 9-4 FI-12-141A RWCU Flow and B Total *
- gpm *
- 28 9-4 FR-20-528 DW EQ Sump DW Floor Sump gpm 0 0 0 0 29 9-4 FR-20-528 gpm 0 0 0 0 30 9-4 FI-13-91 RCIC Flow Recirc Rx Cool. Temp. OF 501 520 525 491 31 9-4 1568e/26.84 i
l l l _ _ _ _ _ _ _ _ - _ - \
Rev. 2 9/25/87 O Page 8.0-8 1 l Scenario Time (hr: min) 03:00 03:15 03:30 03:45 Clock Time 19:30 19:45 20:00 20:15 Item Panel Inst ID Description Units 32 9-4 2-3-92A RR Drive A gpm x 0 0 0 0 103 33 9-4 2-3-92B RR Drive B gpm x 0 0 0 0 103 34 9-5 7-46A APRM/IRM A % 17 0 0 0 35 9-5 7-46A APRM/IRM B % 16 0 1 0 36 9-5 7-46B APRM/IRM C % 17 1 0 0 37 9-5 7-46B APRM/IRM D % 15 2 1 0 38 9-5 7-46C APRM/IRM E % 16 0 0 0 39 9-5 7-46C APRM/IRM F % 16 0 0 0 40 9-5 7-43 A SRM A cps 8x104 9x104 8x103 2 41 9-5 7-43 B SRM B cps 9x104 7x104 6x103 3 42 9-5 7-43 C SRM C cps 2x105 9xio4 7xio3 3 43 9-5 7-43 D SRM D cps 1x105 6x104 5x103 2 44 9-5 FI-3-310 CRD Flow gpm 70 49 49 49 45 9-5 6-96 FW Flow mlb/hr 1.5 .26 0 0 46 9-5 6-96 NR Level inches 150 149 153 170 47 9-5 6-3-95 Core Flow mlb/hr 17 2 1 1 48 9-5 6-3-95 Core AP psid 5 3 3 3
- DW Equipment Sump Flow - may be cycling between 0 and 50.
*n SRVs may be open or closed - depending on operator action.
1568e/26.84
' Rev. 2 on2 0.,
9/25/87 Page 8.0-9
'r 'T 's h 3,
( ! i q ~ s
, VEfJdONT YANKEE NUCLEAR POWER STATION
[ , N 'EMM.GENCY RESPONSE PREPAREDNESS EXERCISE 3<, 8.0 OPERATIONAL DATA Scenario Ijpg (hr: min) 04:00 04:15 04: 30 04:45 20:30 20:45- 21:00 21:15 Clock Timc t Item Panel Inst ID Descr[o3in, Units psig 900 750 250 190 1 9-5 6-97 WR Press 0 0 0 2 9-5 6-97 _MSL Flow n1b/hr 0 psitt 930 733 234 194 3 9-5 6-98 IIR Press inches 180 190 160 180 4 9-5 6-98 WR Level' CR PosLejon in/Out In In In In 5 9-5 58 58 LI-111-1 HW Level'N % 59 59 6 9-6 60 60 LI-111-2 HW Level S % 58 58 7 9 -6 27.5 PI-101-29 Cond. Vac in Hg 24.5 26 27.5 8 9-7 215 225 Steam Tun. Temp. OF 114 115 9 C-21 TE-2-126A 226 Steam Tun. Tsap. OF 113 115 214 f 10 9-?1 TE-13-77A 226 TE-23-105A Steam Tun. Temp. OF 115 114 216 il 9-2 i ' 134 135 (2)TR 149-1 DW Area Temp. OF 134 135 12 9-25 134 134 DW Area Temp. OF 135 135 33 (4) 1.44 1.46 1.47 14 9-25 II-46p/!3 Torus Level ft. 1.42 psid 1.51 1.47 1.38 1.27 (g- g) 15 16 9-25 9-26 PR-1-J$6-3 DW Iorus AP f!-1+125-3A Rx Bldg. AP in H 2O .35 .35 .35 .35 or 3 16-19-40, 113 114 122 124 17 9-47 < Torus Torp. OF cfm 1450 1450 1450 1450 18 9-26 J SEGI Flow
% 2.8 2.8 2.8 2.8 19 C/W DW/ Torus 02 Cone ** ** ** **
20 9-3 SRVs SRV Position Open/Close gpm x 0 0 0 0 21 9-3 FI-14-50A CS "A" Flow 103 gpm x 0 0 0 0
', 22 9-3 FI-14-50B CS "B" T. low 103 gpm x 0 0 0 0 23 9-3 F1-23-108-1 HPCI Flow 103 g 60 80 80 60 24~ 9-3 LI-2R-73 CST Level gpm x 5.5 5.5 5.5 5.5 23' 9 -3 ' FI 139A RHR "A" Flow i 103 gpm x 6 6 6 6 26 9-3 FI-10-1598 BHR "B" Flow 103 gpm 120 120 120 120 27 9-4 FI-12-141A RWCU Flow and B Total 0 DW EQ Sump gpm 0 0 0 l
28 9-4 FR-20-528 0 DW Floor Sump gpm 0 0 0 29 9-4 FR-20-528 0 gpm 0 0 0 33 9-4 FI-13-91 RCIC Flow Rx Cool. Temp. OF 497 501 411 344 31 9 -4 Recirc Racorder N 1568e/26.84 l s. I
Rev. 2 9/25/87 Page 8.0-10
/)s
(,. Scenario Time (hr: min) 04:00 04:15 04: 30 06:45 Clock Time 20:30 20:45 21:00 21:15 Item Panel Inst ID Description Units RR Drive A gpm x 0 0 0 0 32 9-4 2-3-92A 103 RR Drive B gpm x 0 0 0 0 33 9-4 2-3+92B 1 103
% 0 0 0 0 34 9-5 7-46A APRM/lRM A
% 0 0 0 0 35 9-5 7-46A APRM/IRM B
% 0 0 0 0 36 9-5 7-46B APRM/IRM C
% 0 0 0 0 37 9-5 7-46B APRM/IRM D
% 0 0 0 0 38 9-5 7-46C APRM/IRM E
% 0 0 0 0 39 9-5 7-46C APRM/IRM F cps 1 2 2 40 9-5 7-43 A SRM A 1 cps 2 2 2 2 41 9-5 7-43 B SRM B 7-43 C SRM C cps 2 2 1 1 42 9-5 cps 2 3 2 2 43 9-5 7-43 D SRM D 44 9-5 FI-3-310 CRD Flow gpm FW Flow mlb/hr 0 0 0 0 45 9-5 6-96 NR Level inches 180 185 164 166 46 9-5 6-96 6-3-95 Core Flow mlb/hr .86 .56 .57 .60 47 9-5
() 48 9-5 6-3-95 Core AP psid 3.26 3.27 3.26 3.26
- DW Equipment Sump Flow - may be cycling between 0 and 50.
** SRVs may be open or closed depending on operator action.
f
*** CRD Flow - dependent upon operator action.
us 1568e/26.84 l
R l ;
-I Rev. 2 9/25/87
' Page 8.0-11 tO VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE- ,,
1
)
8.0 OPERATIONAL DATA
'Seenario Time (hr: min) 05:00 05:15 -05:30 05:45
_ Clock Time 21:30 21:45 22:00 22:15 Item Panel Inst ID Description Units 1 9-5 6-97 WR Press psig 200 200 190 190 l 2 9-5 6-97 MSL Flow mlb/hr 0 0 0 0 3 9-5 6-98 NR Press psig 196 200 193 199 l 4 9-5 6-98 WR Level inches 170 180 180 180 5 9-5 CR Position In/Out In In .In In 6 ~ 9-6 LI-111-1 HW Level N % 61 61 61 61' 7 '9-6 LI-111-2 HW Level S % 61 62 62 61 8 9-7 PI-101-29 Cond. Vac in Hg< 30 30 30 30 9 9-21 TE-2-126A Steam Tun. Temp. CF 225 225 225 226 9-21' ~TE-13-77A Steam Tun. Temp 0F 226 225 225 225 l 10 11 9-21 TE-23-105A' Steam Tun. Temp. OF 225 226 _225 226 12 9-25 (2)TR 149-1 DW Area Temp. OF 136 136 136 136 13 (4) DW Area Temp. OF 135 135 135 135 14 25 LI-46A/B Torus Level ft. 1.47 1.47 1.47 1.47 15 9-25 PR-1-156-3. DW Torus SP psid 1.14 1.14 1.14 1.14 5 16 9-26 PI-1-125-3A Rx Bldg.'AP in H 2O .35 .35 .35 .35 or B 17 9-47 16-19-40 Torus Temp. OF 119 121 120 120 18 9-26 SBGT Flow cfm 1450 1450 1450 1450 19 CAD DW/ Torus 02 Cone % 2.8 2.8 2.8 2.8 Open/Close ** ** ** ** 20 9-3 SRVs SRV Position 9-3 FI-14-50A CS "A" Flow gpm x 0 0 0 0 21 103 9-3 FI-14-50B CS "B" Flow gpm x 0 0 0 0 22 103 23 9-3 FI-23-108-1 HPCI Flow gpm x 0 0 0 0 103 60 80 60 6C 24 9-3 LI-23-73 CST Level g 25 9-3 FI-10-139A RHR "A" Flow gpm x 5.5 5.5 5.5 5.5 103 FI-10-139B RER "B" Flow gpm x 6 6 6 6 26 9-3 103 27 9-4 FI-12-141A RWCU Flow gpm 120 120 120 120 and B Total gpm * * *
- 28 9-4 FR-20-528 DW EQ Sump 9-4 FR-20-528 DW 11oor Sump gpm 0 0 0 0 29 9-4 F;-13-91 RCIC Flov ;pm 0 0 0 0 30 31 9-4 Recire Rx Cool. Temp. OF 334 349 348 340 Recorder
() 1568e/26.84
i Rev. 2 9/25/87 1 Page 8.0-12 l Scenario Time (hr: min) 05:00 05:15 05:30 05:45 i Clock Time 21:30 21:45 22:00 21:15 1 Item Panel Inst ID Description Units j 32 9-4 2-3-92A. RR Drive A gpm x 0 0 0 0 i 103 ' 33 9-4 .- 2-3-92B RR Drive B gpm x 0 0 0 0 ! 103 34 9-5 7-46A- APRM/IRM A. .% 0 0 0 0 35 9-5 7-46A APRM/IRM B % 0 0 0 0 36 9-5 7-46B APRM/IRM C % 0 0 0 0 37 9-5 7-46B- APRM/IRM D % 0 0 0 0 9-5 7-46C APRM/IRM E % 0 0 0 0 ; 38 ' 39 9-5 7-46C APRM/IRM F %' O O O O 40 9-5 7-43 A SRM A cps 2 1 1 l' 41 9-5 7-43 B SRM B cps 1 1 2 1 42 9-5 7-43 C SRM C cps 1 1 2 2 43 9-5 7-43 D SRM D cps 1 2 1 1
.44 9-5 FI-3-310 CRD Flow gpm 45 9-5 6-96 FW Flow mlb/hr 0 .0 0 0 46 9-5 6-96 NR Level inches 170 183 183 182 47 9-5 '6-3-95 Core Flow mlb/hr .5 .5 .5 .5 48 9-5 6-3-95 Core AP paid 3.26 3.26 3.26 .3.26 l
- DW Equipment Sump Flow - may be cycling between 0 and 50.
** SRVs may be open or closed depending on operator action.
*** CRD Flow - dependent upon operator action.
1568e/26.84
Rev. 2 9/25/87 Page 8.0-13 , (% -) 1 VERM0'G fANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 8.0 OPERATIONAL DATA Scenario Time (hr: min) 06:00 06:15 06:30 06:45 Clock Time 22:30 22:45 23:00 23:15 Item Panel Inst ID Description Units 6-97 WR Press psig 180 170 180 190 1 9-5 MSL Flow mlb/hr 0 0 0 0 2 9-5 6-97 6-98 NR Press psig 185 173 182 192 3 9-5 6-98 WR Level inches 170 170 170 170 4 9-5 9-5 CR Position In/Out In In In In 5 HW Level N 61 61 62 62 6 9-6 LI-111-1 % 7 9-6 LI-111-2 HW Level S % 61 62 62 62 9-7 PI-101-29 Cond. Vac in Hg 30 30 30 30 8 Steam Tun. Temp. OF 225 225 202 125 9 9-21 TE-2-126A TE-13-77A Steam Tun. Temp. OF 226 225 200 126 10 9-21 TE-23-105A Steam Tun. Temp. OF 226 225 198 126 11 9-21 (2)TR 149-1 DW Area Temp. OF 135 135 135 135 12 9-25 DW Area Temp. 134 135 134 134 13 (4) OF 9-25 LI-46A/B Torus Level ft. 1.47 1.47 1.4 1.4 y'~ 14
.9 .85 psid .95 .9
(' 15 16 9-25 9-26 PR-1-156-3 DW Torus AP PI-1-125-3A Rx Bldg. AP in H 2O .35 .35 .35 .35 or B 16-19-40 Torus Temp. OF 120 119 118 118 17 9-47 l 9-26 SBGT Flow cfm 1450 1450 1450 1450 l 18
% 2.8 2.8 2.8 2.8 l 19 CAD DW/ Torus 02 Conc ** ** ** **
20 9-3 SRVs SRV Position Open/Close FI-14-50A CS "A" Flow gpm x 0 0 0 0 21 9-3 103 "B" Flow gpm x 0 0 0 0 22 9-3 FI-14-50B CS 103 gpm x 0 0 0 0 23 9-3 FI-23-108-1 HPCI Flow 103 9-3 LI-23-73 CST Level % 80 60 80 EC 24 25 9-3 FI-10-139A RHR "A" Flow gpm x 5.5 5.5 5.5 5.5 103 gpm x 6 6 26 9-3 FI-10-139B RER "B" Flow 6 6 103 FI-12-141A RWCU Flow gpm 120 120 120 120 27 9-4 and B Total gpm * * *
- 28 9-4 FR-20-528 DW EQ Sump DW Floor Sump gpm 0 0 0 0 29 9-4 FR-20-528 RCIC Flow gpm 0 0 0 0 30 9-4 FI-13-91 Recire Rx Cool. Temp. OF 335 338 340 340 31 9-4 1568e/26.84
i) Rev. 2 9/25/87 Page 8.0-14 Scenario Time (hr: min) , 06:00 06:15 06:30 06:45 Clock Time 22:30 22:45 23:00 23:15 Item Panel Inst'ID Description Units 9-4 2-3-92A RR Drive A gpm x 0 0 0 0 32 103 33 9-4 2-3-92B RR Drive B gpm x. 0 0 0 0 103 34 9-5 7-46A APRM/IRM A % 0 0 0 0 35 9-5 7-46A APRM/IRM B % 0 0 0 0 36 5 '7-46B APRM/IRM C % 0 '0 0 0-37- 9-5 7-46B APRM/IRM D % 0 0 0 0 38 9-5 7-46C APRM/IRM E % 0 0 0 0 39 9 7-46C APRM/IRM F % 0 0 0 0 7-43 A cps 1 1 1 2 40- 9-5 SRM A 7-43 B cps- 1 1 1 2 41 9-5 SRM B
.7-43 C cps. 2 1 2 2 42 9-5 SRM C 43 9-5 7-43 D SRM D cps 1 1 1 2-44 9-5 FI-3-310 'CRD Flow gpm 9-5 6-96 FW Flow mlb/hr 0 0 0 0 45-46 .9-5 6-96 NR Level inches 172 173 168 170 47 9-5 6-3-95 WT Core Flow mlb/hr .5 .5 .5 .5
. 48 9-5 6-3-95 Core AP -psid 3.26 3.26 3.26 3.26 i
- DW Equipment Sump Flow - may be cycling between 0 and 50.
** SRVs may be open or closed depending on operator action.
*** CRD Flow - dependent upon operator action. i 1568e/26.84
O 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9.0 RADIOLOGICAL DATA O 1547e/23.33
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9.1 AREA RADIATION MONITORS O . f 1547e/23.33 O
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O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9.2 PROCESS MONITORS O j I l 4 r 1550e/23.34
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I f l ' Rev. 3 10/7/87 Page 9.3-11a TABLE 9.3-11 Drywell, Elevation 252' (R/hr unless otherwise noted) Clock Scenario Time Time ARM 27 ARM 28 1630 0 3.0 3.0 1730 60 3.0 3.0 j 1745 75 4.0 4.0 l 1800 90 4.0 4.0 1815 105 4.0 4.0 1830 120 5.0 5.0 6.0 6.0 1845 135 1900 150 6.0 6.0 1915 165 6.0 6.0 1930 180 10.0 10.0 1945 195 10.0 10.0 2000 210 150.0 150.0 2015 225 150.0 150.0 2030 240 150.0 150.0 2045 255 150.0 150.0
. 2100 270 150.0 150.0 , . 2115 285 150.0 150.0 I ' 2130 300 150.0 150.0 2145 315 150.0 150.0 2200 330 150.0 150.0 2215 345 150.0 150.0 2.230 360 150.0 150.0 2245 375 150.0 150.0 2300 390 150.0 150.0 i
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Rev. 2 11/20/87 Page 9.3-12a [A TABLE 9.3-12 Torus Catwalk (mR/hr unless otherwise noted) Clock Scenario Time Time ARM 1 Zone I Zone II 1630 0 10 50 10 1730 60 10 50 10 1745 75 10 50 10 i 1800 90 10 50 10 1815 105 10 50 10 1830 120 10 50 12 1845 135 10 55 15 1900 150 10 55 15 1915 165 10 55 15 1930 180 100 55 15 1945 195 450 550 150 2000 210 500 550 150 2015 225 550 550 250 2030 240 600 550 250 2045 255 700 550 400
/ 'i 2100 270 800 800 700
(, 2115 285 1000 1000 900 2130 300 1000 1000 900 2145 315 1000 1200 1000 2200 330 1000 1400 1200 2215 345 1500 1500 1200 2230 360 1500 1300 1200 2245 375 1500 1500 1200 2300 390 1500 2000 1600 Notes: Zone readings are average dose rates throughout zone. General area contamination levels >10 K 6 dpm/100 cm2, 1545e/18.66 l i
I~ FIGURE 9.3-12 Rev. 0 8/31/87 TORUS CAT <7ALK Page 9.3-12b l-h Rea. Bldg. Suppression Chamber Ext. Catwalk
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O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 l 9.4 PLANT CHEMISTRY DATA O O 1548e/18.68 i
1 i l Rev. 0 7/30/87 j Page 9.4-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9.4 PLANT CHEMISTRY DATA Section Page 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 O l
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l 1 \'- 1548e/18.68
-______-_-_a
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE-1987 l 9.4.1 REACTOR COOLANT ACTIVITY DATA 1 O l l 1 0 1546e/4.62
Rev. 1 9/16/87 [%J'T 3 Page 9.4.1-1 VERMONT YANKEE NUCLEAR POWER STATION j l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uCi/cc) Isotope Prior to 1645 I-131 4.5E-3 I-132 6.5E-3 I-133 9.4E-3 I-134 1.0E-2 I-135 8.7E-3 Total Iodine: 3.9E-2 I-131 Dose Equivalent 7x10~ Kr-85m 2.1E-3 Kr-87 3.6E-3 Kr-88 5.3E-3 Xe-133 1.8E-2 Xe-135m 3.3E-3 l Xe-135 4.1E-3 Total NG: 3.6E-2 Note: Reactor coolant activity sample dose rates are provided in Section 9.6. O 1546e/4.62
( Rev. 1 9/16/87 Page 9.4.1-2 A. Reactor Coolant Activity Concentrations (uCi/cc) Isotope 1645-1815 1815-1830 1830-1930 1930-2300 I-131 1.0E-1 1.0E0 7.3E0 7.3E1 I-132 1.5E-1 1.5E0 1.1El 1.1E2 I-133 2.1E-1 2.1E0 1.5El 1.5E2 I-134 2.2E-2 2.2E-1 1.6E0 1.6El I-135 1.9E-1 1.9E0 1.4E1 1.4E2 Total Iodine: 6.lE-1 6.7E0 4.9El 4.9E2 I-131 Dose Equivalent: 1.5E-1 1.5E0 1.1El 1.1E2 O Kr-85m 1.1E0 1.1El 8.4E1 8.4E2 Kr-87 2.2E0 2.2E1 1.6E2 1.6E3 Kr-88 3.0E0 3.0E1 2.2E2 2.2E3 Xe-133 8.2E0 8.2E1 6.0E2 6.0E3 Xe-135m 1.6E0 1.6El 1.2E2 1.2E3 Xe-135 2.5E0 2.5El 1.8E2 1.8E3 Total NG: 1.9El 1.9E2 1.4E3 1.4E4 O 1546e/4.62 ) l i l
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I l 1 l l l l VERMONT YANKEE NUCLEAR POWER STATION ENERGEBCT RESPONSE PREPAREDNESS EXERCISE 1987 l 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA O 1 O l
i I I Rev. O
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. 7/30/87
'( Page 9.4.2-1 VERMONT YANKEE NUCLEAR POWER STATION j EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uCi/ce) l f
Prior to Time Isotope 1645 1645-1815 1815-1930 1930-2300 I-131
- 9E-9 SE-8 SE-7 I-132
- 2E-7 1E-6 9E-6 I-133
- 3E-8 2E-7 2E-6 I-134
- SE-7 3E-6 3E-5 O I-135
- 1E-7 SE-7 SE-6 Total Iodine:
- 8E-7 SE-6 SE-5 Kr-85m
- 6E-6 3E-5 3E-4 Kr-87
- 1E-6 SE-6 SE-5 Kr-88
- 1E-6 SE-6 SE-5 Xe-133
- 1E-5 SE-5 5E-4 Xe-135m
- 1E-5 SE-5 SE-4 Xe-135
- 4E-6 2E-5 2E-4 Total NG:
- 3E-5 2E-4 2E-3 l
- At this time, iodine and noble gases will not be detectable above the MDA of the plant gamma spectrometer.
Note: Primary containment sample dose rates are provided for both gas and l iodine cartridge samples in Section 9.6.
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY PREPAREDNESS EXERCISE 1987 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA O . O 1540e/18.103
l l Rev. 1 9 /16 /P (T (,,) Page 9.4.3-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA A. Reactor Building Air Activity Concentrations (uCi/cc) - Elevation 252', Zones I, II, III, IV - See Notes Below* Isotope Prior to 1815 1815-2050 2050-2250 2250-2300 I-131 ** 1.0E-10 1.0E-2 1.0E-2 I-132 ** 2.0E-10 2.0E-2 2.0E-2 I-133 ** 2.0E-10 2.0E-2 2.0E-2 I-134 ** 3.0E-10 3.0E-2 3.0E-2 I-135 ** 2.0E-10 2.0E-2 2.0E-2 f r'% ks- Total Iodine: <1.0E-10 1.0E-9 1.0E-1 1.0E-1 Kr-85m ** 2.3E-5 7.8E+0 7.8E-1 Kr-87 ** 3.9E-5 1.3E+1 1.3E+0 Kr-88 ** 7.8E-5 2.6E+1 2.6E+0 Xe-133 ** 1.6E-4 5.2E+1 5.2E+0 Xe-135m ** 3.5E-5 1.2E+1 1.2E+0 Xe-135 ** 3.9E-5 1.3E+1 1.3E+0 Total NG: <1.0E-10 3.7E-4 1.2E+2 1.2E+1
- Notes:
- 1. Refer to Reactor Building Elevation 252' floor figure in Section 9.3 for location of zone designation.
2.. Reactor Building sample dose rates are provided in Section 9.6
- 3. Reactor Building Elevation 252', Zones V, VI, VII, concentrations are 95%
of those given above.
- 4. All other Reactor Building elevation air samples are 50% of those given I above, except for Elevation 280' which is 80%.
** Activity is below the MDA of the plant gamma ray spectrometer at this time.
1540e/18.103
(3 t Ams) .! VERMONT YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9.5 PLANT VENT STACK RELEASE DATA Note: 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 p( ,), of the filter will show no counts above background. 1
I a 4 d i b Rev. 2 y (,-)'- 11/30/87 Page 9.5-1~ h I I L t VERMONT YANKEE NUCLEAR POWER STATION i
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EMERGENCY RESPONSE PREPAREDNESS EXERCISE j 1987 l d 9.5 PLANT VENT STACK RELEASE DATA A. Plant Vent Stack Activity Release Rates (uCi/sec)* Isotope Prior to 1645 1645-1815 1815-1130 i Kr-8 5tn ** 2.7El 6.0E1 Kr-87 ** 4.7El 1.2E2 I Kr-88 ** 6.0E1 1.7E9 Xe-133 ** 1.4E2 4.0E2 ) Xe-135m ** 3.2E1 9.0E1 (} Xe-135 ** 4.6El 1.3E2 l Total NG: <100 uCi/sec 3.5E' 9.7E2 I-131 2.2E-5 2.9E-1 8.1E-1 I-132 3.2E-5 4.2E-1 1.2E0 l I-133 4.8E-5 6.5E-1 1.8E0 1-134 5.2E-5 7.0E-1 1.9E0 I-135 4 4E-5 5.9E-1 1.6E0 Total lodine 2.0E-4 2.7E0 7.3E0
- Activity release rates (in uCi/sec) may be converted to activity concentrations (in uCi/cc) by dividing by the stack flow rate of 7.0E7 cc/sec. -- until 1930 ONLY!
** Noble gas release rates are minimal at this time.
1541e/12.116 - _ _ - _ _ _ _ _ - _ _ _ _ _ -
Rev. 2
- 9/28/87
( Page 9.5-2 A. Plant Vent Stack Activity Release Rate (uCi/sec)* Isotope 1930-2050 2050-2100 2100-2115 2115-2130 2130-2145 Kr-85m 1.2E2 2.3E5 4.7E7 3.3E7 3.9E6 Kr-87 2.4E2 4.9E5 6.2E7 4.4E7 4.5E6 Kr-88 3.4E2 6.8E5 1.2E8 8.6E7 8.5E6 Xe-133 8.0E2 1.6E6 3.7E8 2.5E8 3.3E7 Xe-135m 1.8E2 3.4E5 5.5E7 3.8E7 3.9E6 Xe-135 2.6E2 5.3E5 1.3E8 9.4E7 1.2E7 Total NG: 1.9E3 3.8E6 7.8E8 5.5E8 6.5E7 I-131 1.6E0 2.4E3 2.6E4 4.4E4 5.2E4 I-132 2.3E0 3.5E3 3.8E4 6.5E4 7.8E4 O ( ,/ I-133 3.5EG 5.5E3 6.4E4 9.7E4 1.2E5 I-134 3.8E0 5.9E3 8.4E4 1.0E5 1.3E5 I-135 3.2E0 5.1E3 7.5E4 8.9E4 1.1E5 Total Iodine 1.4E1 2.2E4 2.9E5 4.0E5 4.9E5
- Activity release rates (in uCi/sec) may be converted to activity concentrations (in uCi/cc) by dividing by the stack flow rate of 4.9E7 cc/sec. -- after 1930.
.)
1 l l 1541e/12.114
h Rev. 2 9/28/87 Page 9.5-3 A. Plant Vent Stack Activity Release Rate (uCi/sec)* ,F I' Isotope 2145-2200 2200-2215 2215-2230 2230-2245 2245-230 ,,,, >
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Kr-85m 3.6E6 2.2E6 1.3E6 7.2E5 9.0E4 Kr-87 4.2E6 2.5E6 1.5E6 8.4E5 l 1.5E5 Kr-88 7.7E6 4.7E6 2.9E6 1.6E6 3.5E5 Xe-133 3.0E7 1.8E7 1.1E7 6.1E6 1.6E6 Xe-135m 3.6E6 2.2E6 1.3E6 7.2E5 2.1ES Xe-135 1.1E7 6.5E6 4.0E6 2.2E6 6.UES ( i Total NG: 6.0E7 3.6E7 2.2E7 1.2E7 3.0E6 , [ I
! I I-131 3.8E4 2.3E4 1.4E4 7.6E3 1.9E3 '\' '
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE b 1987
\_
Rev. 3.0 9/26/87 Page 9.6.1-1 9.6.1 Rgastor Coolant Sample Dose Rates , s. Upsielded[Qrf4/hr per cc)* Shielded (1 in. Lead in mR/hr per cc)* L ! h, T.jm,Le Cot 1ty+ p. 1 Ft . Contact 1 Ft.
-I Prior to 1645 2.0F-2 2.0E-4 5.0E-3 3.6E-5 1645-1815 2.2E+1 ' 1.5E-1 6.5E+0 4.5E-2 1815-1830 2.2E+2 1.5E+0 6.5E+1 4.5E-1 1830-1930 1.6E+3 1.1E+1 4.8E+2 3.3E+0 1930-2300 1.6E+4- 1.1E+R 4.8E+3 3.3E+1
) L-l
- Note: Numbers must be'anitiplied by the sample volume in ec's to derive dose rates.
L 4 O (V 1549e/16.84 i
l 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE (N 1987
)
(_ > ! Rev. 3.0 l 9/26/87 , Page 9.6.2-1 i l 9.6.2 Primary Containment Air Sample Dose Rates Gas Unshielded (mR/hr per cc)* Shielded (1 in. Lead in mR/hr per ec) Time Contact 1 Ft. Contact 1 Ft. Prior to 1645 No Measurable Dose Rates 1645-1815 1.9E-5 1.3E-7 4.7E-6 3.3E-8 1815-1930 1.2E-4 8.6E-7 3.1E-5 2.2E-7 1930-2300 1.2E-3 8.6E-6 3.1E-4 2.2E-6 Iodine Unshielded (mR/hr per cc)* Shielded (1 in. Lead in mR/hr per cc) Time Contact 1 Ft. Contact 1 Ft. Prior to 1645 No Measurable Dose Rates 1645-1815 1.2E-6 8.4E-9 3.0E-7 2.1E-9 1815-1930 7.6E-6 5.3E-8 1.9E-6 1.3E-8 1930-2315 7.6E-5 5.3E-7 1.9E-5 1.3E-7 I
- Note: Numbers must be multiplied by the sample volume in ec's to derive dose rates.
1549e/16.84
I i VERMONT YANKEE NUCLEAR POWER STATION (O EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 1 ( l 1 Rev. 3.0 ] 9/26/87 ' Page 9.6.3-1 9.6.3 R_ tactor Building Sample Dose Rates (mR/hr) 252' Elevation Shielded (1 in. Lead in Unshielded (mR/hr per ec)* mR/hr per ec)* Iodine Cartridge Time Contact 1 Ft. Contact 1 Ft. Prior to 1815 <1.0E-10 <1.0E-12 <3.0E-11 <3.0E-13 ( 1815-2050 1.5E-9 1.1E-11 4.0E-10 2.8E-12 2050-2300 1.6E-1 1.1E-3 4.0E-2 2.8E-4
- Notes: ,
- 1. Numbers must be multiplied by the sample volume in cc's to obtain the dose rate.
- 2. All other Reactor Building elevation sample dose rates are a fraction of these. See Section 9.4.3.
1549e/16.84
VERMONT YANKEE NUCLEAR POWER STATION () (/ EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9 Rev. 3.0 9/26/87 Page 9.6.3-2 9.6.3 Reactor Building Sample Dose Rates (mR/hr) 252' Elevation Shielded (1 in. Lead in Unshielded (mR/hr per cc)* mR/hr pcr cc)* Gas Sample Time Contact 1 Ft. Contact 1 Ft. Prior to 1815 <6.2E-11 <4.0E-13 <1.5E-11 <1.0E-13 1.6E-6 5.7E-5 4.0E-7 A) ( 1815-2050 2.2E-4 7.4E+3 5.2E+1 1.9E+3 1.3E+1 2050-2250 2250-2300 7.4E+0 5.2E-2 1.9E+0 1.3E-2 i i
- Notes
- 1. Numbers must be multiplied by the sample volume in ec's to obtain the dose rate.
- 2. All other Reactor Building elevation sample dose rates are a fraction of
( these. See Section 9.4.3. ( 1549e/16.84
VERMONT YANKEE NUCLEAR POWER STATION e EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 Rev. 3.0 9/26/87 Page 9.6.4-1 1 9.6.4 Plant Vent Stack Sample Dose Rates Gas Unshielded (mR/hr per cc)** Shielded (1 in. Lead in mR/hr per cc)** Time Contact 1 Ft. Contact 1 Ft. Prior to 1645 1.3E-6 8.8E-9 3.2E-7 2.2E-9 1645-1815 4.5E-6 3.1E-8 1.1E-6 7.8E-9 [) 1815-1930 1.2E-5 8.5E-8 3.1E-6 2.1E-8
\_/ 4.3E-8 1930-2050 2.4E-5 1.7E-7 6.1E-6 2050-2100 1.1E-1 7.8E-2 2.8E 0 2.0E-2 2100-2115 9.8E 0 6.9E-2 2.5E+2 1.7E-2 2115-2130 6.9E O 4.8E-2 1.7E O 1.2E-2 2130-2145 8.5E-1 5.8E-3 2.1E-1 1.5E-3 2145-2200 7.6E-1 5.3E-3 1.9E-1 1.3E-3 -
2200-2215 4.5E-1 3.2E-? 1.1E-1 7.8E-4 2215-2230 2.8E-1 1.9E-3 7.0E-2 4.8E-4 2230-2245 1.5E-1 1.1E-3 3.8E-2 2.6E-4 2245-2300 3.8E-2 2.6E-4 9.5E-3 6.6E-5
** Note: Numbers must be multiplied by the sample volume in ec's to l
derive dose rates. 1
- 1549e/16.84
VERMONT YANKEE NUCLEAR POWER STATION lO
%.)
EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1987 Rev. 3.0 9/26/87 Page 9.6.4-2 9.6.4 Plant Vent Stack Sample Dose Rates General Area Exposure Rates at Stack (mR/hr) Time At Stack Door Inside Prior to 2050 *
- 2050-2100 1.0E-1 1.0E-0 2100-2115 5.0E O 1.0E+2 2115-2130 2.0E+0 5.0E+1 2130-2300 2.0E-0 1.0E+1
- Note: Background as read on survey meter.
i 1549e/16.84
l VERMONT YANKEE NUCLEAR POWER STATION
~. EMERGENCY RESPONSE PREPAREDNESS EXERCISE ' 1987 Rev. 3.0 9/26/87 Page 9.6.4-3 9.6.4 Plant Vent Stack Sample Dose Rates Iodine Unshielded (mR/hr per cc)** Shielded (1 in. Lead in mR/hr per cc)**
l Time Contact 1 Ft. Contact 1 Ft. l Prior to 1645 6.2E-12 4.3E-14 1.5E-12 1.1E-14 1645-1815 8.4E-8 5.8E-10 2.1E-8 1.5E-10 1815-1930 2.3E-7 1.6E-9 5.7E-8 3.9E-10 i
) 1930-2050 4.3E-7 3.0E-9 1.1E-7 7.5E-10 2050-2100 6.8E-4 4.7E-6 1.7E-4 1.2E-6 2100-2115 8.9E-3 6.2E-5 2.2E-3 1.6E-5 2115-2130 1.2E-2 8.6E-5 3.1E-3 2.1E-5 2130-2145 1.5E-2 1.1E-4 3.8E-3 2.6E-5 2145-2200 1.1E-2 7.5E-5 2.7E-3 1.9E-5 2200-2215 6.5E-3 4.5E-5 1.6E-3 1.1E-5 2215-2230 4.0E-3 2.8E-5 1.0E-3 7.0E-6 1
2230-2245 2.1E-3 1.5E-5 5.3E-4 3.7E-6 2245-2300 5.2E-4 3.6E-6 1.3E-4 9.1E-7 O
\- / 1549e/16.84 l
r -m--,---,,,,-,v--,- - - - - - - , - , - - , - 0 1 i i 1 VERMONT YANKEE NUCLEAR POWER STATION , I EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987
'l 1
9.7 0FF-SITE MONITORING TEAM OBSERVER INSTRUCTIONS / DATA O 1 1 i 1542e/16.137
Rev. 1 9/15/87 Page 9.7-1 v NOTE: THE PLUME PLOT FIGURES ARE GRAPHIC REPRESENTATIVES OF ATMOSPHERIC DISPERSION. THE THREE-DIMENSIONAL PLUMES VARY IN TIME AND SPACE. A SIMILAR VERSION OF THE FIGURES OVERLAYED ON A LARGER FIELD SURVEY MAP WILL BE USED TO ASSIST CONTROLLERS IN INTERPRETING DATA.
*THE TRfJISITION FROM NEUTRAL TO STABLE ATMOSPHERIC CONDITIONS, TYPICAL OF A WINTER EVENING, IS FIRST EVIDENT IN FIGURE 9.7-3. l l
10 l '%) i [ l l i i ( 1542e/16.137
Rev. I 11/18/87 e Page 9.7-2 (
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 9.7 MONITORING TEAM OBSERVER INSTRUCTIONS / DATA Off-site plume centerline whole body dose rates have been estimated as a function of time and distance from the site using a variable trajectory dose assessment model. Geographical representations of the plume are provided in this package for each 15 minute average of meteorological conditions, starting at 20:45. During the exercise, off-site monitoring team observers will use the information contained in this package to provide field monitoring teams with radiological data for various times and locations.
, (/\) During the exercise, the Survey Team Coordinator (s) will direct off-site monitoring teams to monitor locations relative to the meteorological conditions postulated for the exercise scenario. Use Figures 9.7-1 through 9.7-9 to provide survey results to the off-site monitoring teams.
Figures 9.7-1 through 9.7-9 depict the plume conditions at various times throughout the exercise. These figures represent a plume width which is equivalent to a 3-sigma value of the centerline conditions. Since the 4 1 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 and outer edge values at a f l 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. l () O 1542e/16.137
Rev. 1 9/15/87 f-%. Page 9.7-3 g l 1 Prior to the exercise, training will be provided to the off-site monitoring team controller / observers on the use of this package. The following are specific actions which off-site monitoring team controller / observers should take during the exercise: ;
- 1. As off-site monitoring teams are designated, check that Procedure l Number OP-3510 is followed by team members. This will include the initial equipment check.
- 2. While enroute to the assigned monitoring location, or while I traversing the plume, use the attached figures and tables to issue l appropriate radiological data.
- 3. Attempt to estimate the team's accrued exposure as a function of their continual job assignment. Do not issue pocket dosimeter
\ results to team members, unless they actually simulate checl" g their dosimeter reading. The pocket dosimeters in the kits have a range of 0-500 mR, which are subdivided into 20 mR intervals. Attempt to provide realistic values! 0-5 R dosimeters may be provided. Always check to ask them the range.
- 4. Ask the off-site monitoring teams what equipment they have available for their use. Ask them the scales associated with the equipment; log these answers to ensure that you do not provide them with data that exceeds the range of their equipment. If, at any point during the exercise, a situation occurs where the upper range of their equipment is exceeded, then issue them an "off-scale high" value.
- 5. If the off-site monitoring team stops to take an air sample: ;
- a. Report the appropriate whole body dose levels at that location.
( 1542e/16.137 (
1 Rev. 1 11/20/87 s Page 9.7-4 , l 1 NJ
- b. If an RM-14/HP-210 is left on to track the plume while driving !
the meter count rate can be estimated using the following relationships: (1) 5,000 cpm on the RM-14/HP-210 is equivalent to approximately 1.0 mR/hr. Therefore, 10 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 waist-high survey.
I
- 7. The Vermont Yankee off-site monitoring teams will substitute a charcoal sample instead of a silver zeolite sample for the purposes p,,
( ,1 of this exercise. All data will be given from the tasks provided as though silver zeolite samples were being utilized. !
- 8. Certain field monitoring teams may take open window end closed window readings with their dose rate survey meters. If a team is located in the centerline (blue area) of 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. If a team is off-centerline (yellow or green areas) of the plume (as shown on the maps), assume that the open window reading is the same as the gamma (closed window) dose rate given for that area on the map.
l NOTE: THE PLUME PLOT FIGURES ARE GRAPHIC REPRESENTATIONS OF ATMOSPHERIC DISPERSION. THE THREE-DIMENSIONAL PLUMES VARY IN TIME AND SPACE. A SIMILAR VERSION OF THE FIGURES OVERLAYED ON A LARGER FIELD SURVEY MAP WILL BE USED TO ASSIST CONTROLLERS IN INTERPRETATING DATA. O 4
.\,j
*THE TRANSITION FROM NEUTRAL TO STABLE ATMOSPHERIC CONDITIONS, TYPICAL OF A WINTER EVENING IS FIRST EVIDENT IN FIGURE 9.7-3.
1542e/16.137
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Figure 9.7.1 Offsite Radiological Conditions At Clock Time 20:50-21:00 BLUE AREA (CENTERLINE) YELLOW AREA GREEN AREA PLUME DISTANCE CONO. GAMMA RM-14 SAM-II GAMMA RM-14 SAM-11 GAMMA RM-14 SAM-II NO MILES I-131 DOSE RATE 100 LITERS DOSE RATE 100 LITERS DOSE RATE 100 LITERS uCi/cc SILVER ZEOLITE SILVER ZEOLITE SILVER ZEOLITE X 10E-6 mR/HR CPM CPM mR/HR CPM CPM mR/HR CPM CPM
- 4. ::::::::::::::====== :::== ::::::::::::: ::== :::::::::::= ::::::::== :::::::::==::::::::::::: 0 0.06
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- = ::::::::::::::::== ::: =uss== ::::::::::= ::::========
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- =
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0.35 0.000::::::::::::::=== 1080 :::::::= 0 :::=== 0 :::::::::::::= 100 0 :::===0::::::::::11==:::::0 0 4.95 0.006 4 44 445 0 4 44 0 0 4 5 8173 6e 82 817 7 8 82 4 3.55 0.147 675 817 54 539 3 1.67 0.970 2210 5393 53932 221 539 5393 22 345 3447 158 34 345 16 3 34 2 1.07 0.062 1580 0 0 1 .06 0.000 1040 0 0 104 0 0 10
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[ L H2 I fe t (Irifor ) ," N _ '. TP. - , N 3 MILES w E Figure 9.7.4 Offsite Radiological Conditions at Clock Time 21:30-21:45 [ BLUE AREA (CENTERLINE) YELLOW AREA GREEN AREA PLUME DIETANCE CONC. GAMMA RM-14 SAM-II GAMMA RM-14 SAM-II GAMMA RM-14 SAM-II l NO MILES I-131 DOSE RATE 100 LITERS DOSE RATE 100 LITERS DOSE RATE 100 LITERS l uCi/cc SILVER ZEOLITE BILVER ZEOLITE SILVER ~EOLITE X 10E-6 mR/HR CPM CPM mR/HR CPM CPM mR/HR CPM CPM
- ===:::::::::======= :::::::===::::::::::::::::::::::::::: ======= :::::::::= :::==::::::::::::::::::=
SB .35 0.000 204 0 0 20 0 0 2 0 0 0 6.24 0.007 3 39 389 0 4 39 0 0 4 5 4.85 0.129 544 717 7172 54 72 717 5 7 72 4 2.97 0.398 1260 2213 22129 126 221 2213 13 22 221 3 2.97 0.123 1230 EB4 6839 123 68 084 12 7 08 2 1.30 0.034 270 189 1890 27 19 189 3 2 19 1 .06 0.000 196 0 0 20 0 0 2 0 0
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PLUME DISTINCE CONC, GAMMA RM-14 SAM-11 GAMMA RM-14 SAM-II GAMMA RM-14 SAM-II NO MILES 1-131 DOSE RATE 100 LITERS DOEE RATE 100 LITERS DOSE RATE 100 LITERS uC1/cc SILVER ZEOLITE SILVER ZEOLITE SILVER ZEOLITE
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O SB 9 7 8 0.35 9.65 8.25 6.38 0.000 0.004 0.073 0.128 46 332 549 2 22 406 712 0 222 4059 7117 0 33 55 5 0 41 71 0 2 400 712 22 0 0 0 5 3 0 0 7 4 41 71 0 2 6 6.44 0.107 654 595 5949 65 59 595 7 6 59 5 4.77 0.163 145 906 9063 15 91 906 1 9 91 4 3.47 0.139 113 773 7728 11 77 773 1 0 77 3 2.17 0.067 113 373 3725 11 37 373 1 4 37 2 1.17 0.007 75 39 389 8 4 39 1 0 4 1 0.06 0.000 45 0 0 5 0 0 0 0 0
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==
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8 10.59 8.71 8.26 0.051 0.077 0.084 256 384 477 284 428 467 2B36 4281 4670 26 38 48 28 43 47 284 420 467 4 3 5 3 4 5 2B 43 47 7 7.05 0.134 100 745 7450 10 75 745 1 7 75 6 5.86 0.131 73 720 7284 7 73 72P 1 7 73 4.57 0.095 71 528 5282 7 53 528 1 5 53 5 4 3.57 0.059 52 328 3280 5 33 328 1 3 33 3 2.40 0.024 31 133 1334 3 13 133 0 1 13 2 1.15 0.001 3 6 56 0 1 6 0 0 1 0.06 0.000 2 0 0 0 0 0 0 0 0 1 t ::::::::::::::::::::::::====== ress ::::== ::::::::::::::::====:::::::::= :::::::::::::::::::=====:::::::::
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 10.0 METEOROLOGICAL DATA O 1569e/20.136 l
. _- _ - _ __ _ _-_____ _ _ __ l
1 I
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Rev. 3 10/9/87 Page 10.1-1
.I J
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE I
-1987 110.1 ON-SITE METEOROLOGICAL DATA l
'16:30-18:00 Time 16:30 16:45 17:00 17:15 17:30 17:45 18:00 LOWSAV AVG LOWER SPEED MPH 2.4 2.7 2.8 2.8 2.4 0.8 1.2 UPWSAV AVG UPPER. SPEED MPH- 2.6 3.6 6.5 5.6 5.0 4.7 5.2 LOWDAV AVG LOWER DIR DEGS 218 161 217. 150 111 243 263 LOWDSD AVG LOWER DIR SIGMA- 26 38 14 59 17 17 25
~UPWDAV AVG UPPER'DIR DEGS 189 186 156 176 231 255 263 1 18 38 8 21 25 7 9 UPWDSD AVG: UPPER DIR SIGMA
'LOTTAV AVG LOWER TEMP DEGS (F) 18.6- 17.4 17.1 17.1 15.9- 16.0 16.6 LODTAV AVG LOWER' DELTA T DEGS (F) -0.58 -0.56 -0.55 -0.54 -0.53 -1.52 -0.53
-0.79
~
g UPDTAV AVG UPPER DELTA T DEGS (F) -0.87 -0.86 -0.84 -0.82 -0.81' -0.80
,.SOLRAV AVG SOLAR RAD LANGS 0.00- 0.00 0.00 0.00 0.00 0.00 0.00 RAINTO 15' MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 ,
18:15-19:45' Time 1 18:15 18:30 18:45 19:00 19:15 19:30 19:45 LOWSAV AVG LOWER SPEED MPH 3.6 5.1 3.1 2.9 1.7 1.3 3.1 UPWSAV AVG UPPER SPEED MPH 8.8 10.9 5.8 4.0- 4.4 6.7 6.3 LOWDAV AVG LOWER DIR DEGS 176 125 33 297 205 328 234 LOWDSD AVG LOWER DIR SIGMA 66 63 26 30 52 64 20 UPWDAV AVG UPPER DIR DEGS 244 239 296 251 157 135 146 UPWDSD AVG UPPER DIR SIGMA 7 29 42 25 57 7 9 LOTTAV AVG LOWER TEMP DEGS (F) 16.6 16.5 17.0 16.5 16.1 16.0 16.5 LODTAV AVG LOWER DELTA T DEGS (F) -0.53 -0.52 -0.51 -0.53 -0.53 -0.51 -0.51 UPDTAV AVG UPPER DELTA T DEGS (F) -0.80 -0.80 -0.79 -0.80 -0.79 -0.78 -0.77 SOLRAV AVG SOLAR RAD LANGS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.'00 0.00 0.00 1 0 1569e/20.136
'r ,'
Rev. 3
'11/20/87 Page 10.1-2 O-x) VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1987 10.1 ON-SITE METEOROLOGICAL DATA 20:00-22:00 Time 20:00 20:15 20:30 20:45 21:00 21:15 21:30 21:45 22:00.
LOWSAV AVG LOWER SPEED MPH 2.6 1.7 1.7 1.7 1.9 2.0 '0. 9 1.4 1.4-UPWSAV AVG UPPER SPEED MPH 5.4 7.0 9.5 9.5 8.4 7.5 6.7 5.2 5.2 LOWDAV AVG LOWER DIR DEGS 204 113 '305 305 335 249 347 .312 312 52 53 43 43 38 20 47 i S4 54 LOWDSD AVG LOWER DIR SIGMA.
.UPWDAV AVG UPPER DIR DEGS 155 146 136 136 132 135 135' l 140 140 12 8 6 6 7 7 6 10 10 -
UPWDSD AVG UPPER DIR SIGMA LOTTAV AVG LOWER TI29 DEGS (F)' 15.7 15.1 14.5 14.5 15.6 15.2 14.5 14.1 -14.1 LODTAV. AVG LOWER DELTA T DEGS (F) -0.50 -0.49 -0.49 -0.49 -0.49 -0.46 -0.44 -0 . 4 .* -0.42 UPDTAV AVG UPPER DELTA T DEGS (F) -0.76 -0.75 -0.75 -0.75 -0.76 -0.72' -0.71 '- 0.70 -0.70 SOLRAV AVG SOLAR RAD LANGS 0.00- 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 RAINTO~15 MIN RAINFALL INCHES 0.00 0.00- 0.00 0.00 0.00 0.00 0.00 0.00- 0.00 t k.s[% Time 22:15- 00:1s 22:15 22:30 22:45 23:00 23:15 23:30 23:45 24:00 0:15 LOWSAV AVG LOWER SPEED MPH 2.3 3.0 1.8 1.1 1.0 2.0 3.0 3.0 4.0 UPWSAV AVG UPPER SPEED MPH 4.0 4.7 5.0 4.6 4.6 7.0 5.0 5.0 6.0 231 213 148 48 227 166 170 180 180 LOWDAV AVG LOWER DIR DEGS LOWDSD AVG LOWER DIR SIGMA 39 19 46 45 42 39 115 131 152 145 146 150 195 200 700 UPWDAV AVG UPPER DIR DEGS UPWDSD AVG UPPER DIR SIGMA 12 8 11 12 10 8 j LOTTAV AVG LOWER TEMP DEGS (F) 13.6 14.2 14.8 13.7 14.2 14.3 l
-LODTAV AVG LOWER DELTA T DEGS (F) -0.40 -0.39 -0.40 -0.40 -0.41 -0.41 -0.42 -0.42 -0.42 UPDTAV' AVG UPPER DELTA T DEGS (F) -0.68 -0.69 -0.70 -0.68 -0.67 -0.67 -0.67 -0.67 -0.67 SOLRAV AVG SOLAR RAD LANGS 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.7 0.11 0.26 RAINTO 15 MIN RAINFALL INCHES 49e/20.136
l 1 Rev. 2 I 9/23/87 [
, -) Page 10.2-1 l
i s/ 1 l 10.2 GENERAL AREA NWS FORECASTS l J 12:00-18:00 - General Area Forecast Party cloudy with light and variable winds expected this afternoon. High temperatures in the mid-20's, with a 10% chance of precipitation. As a strong high pressure system moves further east along the central eastern seaboard, a low pressure system is expected to deepen in the Great Lakes region bringing colder Canadian air to the northeast in two days. Winds expected from the southwest between 4-8 mph tonight, low temperatures in the teens. Also, 50% chance of flurries late tonight. O 1569e/20.136
l Rev. 2 9/23/87 Page 10.2-2 (~' ( 10.2 GENERAL AREA NWS FORECASTS l 18:00-02:00 - General Area Forecast l Light snow expected with little accumulation, changing to rain by early morning. Low around 14 F tonight, winds four to eight mph from the southwest. A strong low pressure system is moving. northeast from the Great Lakes region. Chance of snow, changing over to rain, as the system moves into our area. Accumulation of up to an inch may be expected in low-lying areas and two to three inches in the mountains, before changing back to rain by morning. Late tomorrow, light rain clearing overnight. Hazardous driving conditions may be expected tomorrow. O O 1569e/20.136
t l i' 1 Rev. 2 , O ' 9/18/87 Page 10.2-3
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^
WEATHER FORECAST FOR SITE: VERM9NT YANKEE Date of Forecast: 12/1/87 Time of Forecast: 1900 Current Site Meteorology (as of 1830 ): v Delta-Wind Speed Wind Direction Temperature Stabilly P_ precipitation 5.1 mph 125 deg from -0.52 0F D? \l,02 00 in/15 min Lower i Upper 10.9 mph 239 deg from -0.80 0F - P i 3
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Forecast Site Meteorology: ' h
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Delte-Time Wind Speed Wind Direction Temperature S.ay.11ty t Piacipitation Lower 5 mph 180 deg from -- of E- 0.00in/1fmin A. 1830-Upper 10 mph 180 deg f rom -- 0F E / 1930 y
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1930- Lower 3 mph 180 deg from -- of E 0.00iu/15imin B. 180 deg from E 2030 Upper 6__ mph _O F 2030- Lower 2 _ mph 180 deg from -- 0F '( 0.0' in/ M min l' C. ' ? Upper __ 6 mph 180 deg from -- 0F t 2130
\
l' National Weather Service Forecast for site region: Partly cloudy with light and variable winds expected this afternoon. High j~ temperatures in the mid-20's, with a 10% chance of precipitation. As a strong high pressure system moves further east along the central eastern j J seaboard, a low pressure system is expected to deepen in the Great I.ake.; region bringing colder Canadian air to the northeast in two days. Winds expected d om the southwest between 4-8 mph tonight, low temperatures in the teena. Also. 50% chance of flurries late tonight. ; Special Weather Statements: Chance of precipitation after midnight. Unseasonably cold for this time of year. Winds will tend to go up valley this evening at approximately 8 mph. , ;. O 1572e/3.31 e s l
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p I WEATHER FORECAST FOR Sili.:'V4PMO;;T ~ ' ' ~ YANKEE Date of Forecast: 12/1/87 ! s Time of Forecast: 2048 i i jC":l.ntSiteMeteorology(asof 2015 ): Delta-
,. c ( Wind Speed Wind Dire g;79 Temperature Stability Precipitation i
1.2 'aph ') 7 4 deg -f ro.n -0.45 0F D G 00 in/15 r1tn
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t :/pper 8.2 mph 133 deg I mn -0.72 0F D L ! 4; . )!' dv;: cast Site Meteorology:
- Ltitt-
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_ . , Time Wind Speed.7 Wind Direction Temperature Stability Precipitation i A. 2015- Lower 2 mph _)SO deg from -- 0F E 0.01in/15 min 3 2115 Upper 6 mph f80 deg from -- of C
/ B. ' 2115- Lower _ , L mih 180 deg from _ -- 0F E 'd.01in/15 min 2215 Upper .i mph 180 deg from _ - - 0F E C. 2215- Lower 2 mph 180 deg f2am -- 0F E 0.01in/15 min 5 mpb 180 deg froni 0F, E 2314 Upper --
National Weather Service Forecast for site region: s Light snow expected witn little accumulation, charging,to rain by early morning. Low around 140F tonight, wirds four to elght mph from the southwest. A strong low Chance of snt;w, pressure system is moving r artheast from *.he Great Lakes region. changing over to rain, as he system moves into our aren. Accumulation of up tc an , inch may be expected in.:o -lying areas and two to three inches in the mountains, before changing back to ra a by morning. Late tomorrow, light rain clearing l overnight. Hazarde. , driv: ig canditions may be expected tomorrow. l (- \\ ll l' (: Special Weather Statements: b The area in the vicinity of the plan. (up to ten miles) should get mostly rain. Winds will contin w frem the p uch at 8 mph up the valley until mid-morning :omor r w when they will come f rota che wll<: at a mph. The totel rainfall should be j approximately 0.4 ircnes h r the e.o o' t u.; /T rw l 1 1572e/3.31 i b
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