ML20154C763
| ML20154C763 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 08/31/1988 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| References | |
| NUDOCS 8809150009 | |
| Download: ML20154C763 (295) | |
Text
{{#Wiki_filter:VEU10NT YANKEE hTCLEAR PC'WER STATION UtERGENCY RESFCNSE PREFAREENESS EXERCISE 1988 EXERCISE MAhTAL O e-IS92e/3.19? 91 00 00 g F b
Rev. : 8/11/88
'~) VERMONT YANKEE NL' CLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE .
t 1983 TABLE OF CONTENTS Section [agt
1.0 INTRODUCTION
1.1 Exercise Schedule......................................... . 1.1-1 1.2 Participating Centers / Agencies............................... 1.2-1 1.3 Definitions.................................................. 1.3-1 1.4 References................................................... 1.4-1 l l l 2.0 EXERCISE 0BJFCTIVES............................................... 2.0-1 l 3.0 EXERCISE CUIDELINES AND SCOPE 3.1 Guidelines................................................... 3.1-1 3.2 Ex t e n t o f P 1 a y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.2-1 , 3.3 Player Instructions.......................................... 3.3-1 l 3.4 P r o c e d u r e Ex e c u t i o n L i s t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4-1 l l 3.5 Exercise Termination Criteria................................ 3.5-1 4.0 CONTROLLER /0! SERVER INFORMATION
- 4.1 Con t ro l l e r / Ob s e rv e r A s s i g nme n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.1-1 4.2 Controller /0tserver Exercise Guidance........................ 4.2-1 4.3 Controller / Observer Comnents................................. 4.3-1 5.0 EXERCISE SCENAR10 5.1 Initiki conditions........................................... 5.1-1 5.2 N a r r a t i v e S ansa r y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.2-1 5.3 Scenario Time Line........................................... 5.3-1 5.4 De ta iled se que nc e o f Event s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.4-1 6.0 EXERCISE MESSACES 6.1 Command Cards................................................ 6.1-1 6.2 Message Cards................................................ 6 . 2 'a 7.0 STATION EVENT DATA 7.1 Events Summary............................................... 7.1-1 7.2 Event Mini-Scenarios......................................... 7.2.1-1 s-
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X1 8/11/88 I VEhMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 l TABLE OF CONTENTS (Continued) 8.0 OPERATIONAL DATA.................................................. 8.0 I 1 ! 9.0 RADIOLOGICAL DATA i ' i l 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 Radiological Sample Dose Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.5.1-1 i 9.6 Plant Vent Stack Release Data................................ 9.6-1
) i 10.0 METEOROLOGICAL DATA j 10.1 On-Site Meteorological Data.................................. 10.1-1
- 10. 2 General Area Nat :onal Weather Se rvice Forecas t s. . . . . . . . . . . . . . 10.2-1
; 10.3 National Weather Se rvice Surf a:e Maps . . . . . . . . . . . . . . . . . . . . . . . . 10.3-1 !
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l VERMONT YANKEE NUCLEAR POWER STATION f EMERGENCY RESTONSE PREPAREDNESS EXERCISE 1988 ; a L I
1.0 INTRODUCTION
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f 6 VERMONT YANKEE NUCLEAR POWER STATION ; EMERGENCY RESPONSE PREPAREDNESS EXERCISE , 1988 ; 1 < l 1.1 EXERCISE SCHEDULE i k I i 1 f i i i } t i 1091e/3.196 L-_...----_-. . , _ _ . - ,.. - . - _ _ -.__ .,-. _ - - _ - - ..- _ _- _
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. -7 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ;
l 1988 I l H 1.1 EXERCISE SCHEDULE x A. Controller / Observer Briefing Date: August 30, 1988 , i I Time 9:00 a.m. Location: Vermont Yankee Energy Information Center
Purpose:
Controller / Observer Briefing on Scenario and Assignments i Attendees: Vermont Yankee and Yankee Atomic Controllers / Observers l B. Controller / Observer Plant Tour j Dates August 30, 1988 l i ! Time: As necessary (contact Lead Controller) j i l { Location: Emergency Response Facilities and In-Station Areas i j i Purposes Familiarize Controllers / Observers with Affected Areas j i, < j Attendeest Controllers / Observers ! i ) 1891e/3.196 I I 4
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6/21/88 Page 1.1 j O. NRC Briefina r
!.. Date: To be announced .,
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Location: Vermont Yankee Energy Information Center f
Purpose:
NRC Briefing and Review of Exercise Scenario '
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l i , uttendees: NRC Evaluators , i t f D. Exercise , Date: August 31 -1988 , i l l Time: 0600 hours , Location: Vermont Yankee Emergs,cy Response Centers ! j Purposr: Emergency Response Preparedness Exercise Attendees: Vermont Yankee Emergency Response Organization, , j Controllers / Observers, Nr.C Evaluators, and Yankee j Atomic Engineering Support Center Staff ' I ! E. Exercise Debriefinz ' 1 4 I j Dates Day of Exercise I { Time: To be announced during or immediately following i t j exercise c l d 1891e/3.196 l ] t 4
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. Location: Location to be designated by the Emergency Response i ,
Facility Controller i
Purpose:
Players and Controller / Observer Debriefing . Attendees: Controllers / Observers. Fey Participants
; F. Controller Debriefing ,
f Date: After, Exercise Player Debriefing ; 1 1 l , Time: To be announced ; i Location: Vermont Yankee Information Center i
Purpose:
Exercise Debriefing Attendees: Exercise Coordinator and Controllers
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G. Exercise Crit (que ! i ! Date: September 1, 1988 r l Time: To be announced " l Location: Vermont Yankee Infrumation Center i .1 ]
Purpose:
Utility Self-Critique /NRC Preliminary Findings i Attendees: Vermont Yankee Management, NRC Evaluators, Exercise s ]
- Controllers (Observers need not attend), and Vermont i Yanket Key Participants
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I; !- l l@ L l! i ! i i 4 , i . 8 I l l l l ' t ! VERMONT YANKEE NUCLEAR POWER STATION I P EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1 1988 ; i
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-i 1.2 PARTICIPATING CE)TERS/ AGENCIES ,
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4 I Rev. 1 f-- . 8 6/21/88 \ Page 1.2-1 VERMONT YANKEE FUCLEAR POWER STATION T EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 i 1.2 PARTICIPATING CENTERS / AGENCIES 1 s VERMONT YANKEE NUCLEAR POWER CORPORATION ; Vermont Yankee Nuclear Power Station: l o Control Room (notification and communication functiops unty) o Technical Support Center (2nd floor of Administration Building) r () o Operations Support Center (1st floor of Administration Building) o Energy Information Center 0 Governor Hunt House) Vermont Yankee Training Center: 4 o Simulator Room (Control Room functions - 1st floor of Training l ' Center) l o Emergency Operations Facility / Recovery Center (1st floor of Training Center) l 1 News Media Center (Vermont Yankee Nuclear Power Corporation Offices - Brattleboro, Vermont) 1 4
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I \ Rev. 1 . 6/21/88 l Page 1.2-2 O .[ t L YANKEE ATOMIC ELECTRIC COMPANY i Yankee Atomic Corporate Headquarters: i j i o Engineering Support Center l t
' STATE OF VERMONT (Notifica'tinn and Communication Only) l
- . l Vermont Emergency Management Agency
- o Emergency Operations Facility / Recovery Center (state representatives f j located in the State Room) l 1
o Emergency Operating Center'(Waterbury Vermont) l
, STATE OF NEW HAMPSHIRE (Notification and Comunication Only)
I New Hampshire Emergency Management Agency: i o Emergency Operations Facility / Recovery Center (state representatives located in the State Room) - ( a l
- o Emergency Operating Center (Concord, New Hampshire) l i
STATE OF MASSACHUSETTS (Notification and Comunicatig Only) ) Massachusetts Civil Defense Agency, Massachusetts Department of Public l j Health! , I j o Emergency Operations Facility /Kecovery Center (state representatives l located in the State Room) 1 l o Emergency Operating Center (Framingham Massachusetts) s
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l l l s l l l l i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPARodNESS EXERCISE 1988 i 1.3 DEFINITIONS l l
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1 Rev. 2 ; 6/21/88 Page 1.3-1 {)% s, VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 ABBREVIATIONS, DEFINITIONS AND'TERMIN0 LOGY i , t 1.3 DEFINITIONS. ,
'A. Abbreviations ,
I o ACR0 - Alternate Control Room Operator o AO - Auxiliary Operator 1
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o A0G - Advanced Of f-Gas System o APRM - Average Power Range Monitor o ARM - Area Radiation Monitor o C/HP - Chem / Health Physics o CR - Control Room / Control Rod , o CRP - Control Room Panel f o CS - Core Spray o CTP - Core Thermal Power o DC0 - Duty and Call Officer o DW - Drywell i o EAL - Emergency Action Level o ECCS - Emergency Core Cooling System o ENS - Emergency Notffication System o EOF - Emergency Operations Facility - o EPZ - Emergency Planning Zone i j o ESC - Engineering Support Center \ o FEMA - Federal Emergency Management Agency ( l o FW - Feedwater 1889e/3.194
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'- t Page 1.3 2 o 'HPCI . High Pressure Coolant Injection o HRNG - High Range Noble Gas o I&C - Instrumentation and Control' ,
o LPCI - Low Prossure Coolant Injection o MCC - Motor Control Center o Mn Con Bk Pres - Main Condenser Back Pressure o MPR - Mechanical Pressure Regulator s o ' SIV - Main Steam Isolation Valve o MSL - Main Steam Line o NAS - Nuclear Alert System o NG - Noble Cases o NRC - Nuclear Regulatory Commission o OP - Operating Procedure o OSC - Operations Support Center o OT - Operational Transient o PASS - Post-Accident Sampling System o PCIS - Primary Containment Isolation System o PED - Plant Emergency Director o POD - Pocket Dosimeter o PVS - Plant Vent Stack o RA - Radiological Assistant o RCS - Reactor Coolant System
, o RCIC - Reactor Core Isolation Cooling o REMVEC - Rhode Island Eastern Massachusetts, and Vermont Energy Control.
o RERP - Radiological Emergency Response Plan 1889e/3.194
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Page 1.3-3' J 4 o RHR - Residual Heat Removal o RP - Reactor Recirculation System j o RTF - Reactor Transfer Fan , o RV -- Relief Valve o RWCU - Reactor Water Clear.-Up i o Rx - Reactor o SAE - Site Area Emergency . I o SBGTS - Standby Gas Treatment System , o SJAE - Steam Jet Air Ejector o SRM - Site Recovery Manager / Source Range Monitor o SRV - Safety Relief Valve ; t 1 o SU Trans - Start-Up Transformer l o TAG - Technical Administrative Guideline o TS - Technical Sper.ification ; i o TSC - Technical Support Center l 4 o VY - Vermont Yankee ; i i j o VYNPC - Vermont Yankee Nuclear Power Corporation ( j o VYNPS - Vermont Yankee Nuclear Power Station o WSI - Weather Services International i I l j o YNSD - Yankee Nuclear Services Division 1 i i I iO ) 1889e/3.194 i i
Rev. 2 ( 6/21/88 Page 1.3-4 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 i keeping the action going according l to a scenario, resolving differences ( (acting as an umpire), supervising i 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 . j 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 mobilisation of the emergency response organisation. l These are specific threshold readings or observations indicating , system failures or abnormalities. f o Emergency Assistance - General term used to refer to the Personnel radiation monitoring teams, sample i analysis team, and in-plant search, and rescue teams. l o Emergency Operations - An emergency response facility f Facility / Recovery (Vermont Yankee Training Center, j Center Brattleboro, Vermont) which i evaluates off-site accident consequences and coordinates emergency response and assistance with all off-site agencies. l 0 1889e/3.194
Rev. 2 6/21/88 A Page 1.3-5 Q o Emergency Planning - The areas for which planning is Zones ;reconsnendeo to assure that prompt . j and effective actions can be taken to protect the public in [ the event of an accident. The '! two nones 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 , j Center (Yankee Atomic Electric Corporate
- Headquarters) established to 1
j provide additional engineering ; j support to the affected site in plant assessment and recovery operations. 4
- o Exercise - A demonstration of the adequacy i of timing and content of emergency implementing procedures, methods, and equipment.
j o Full Participation . An exercise which tests as much of j Exercise the licensee, state, and local plans as is reasonably achievable l ' without mandatory public participation. o General Emergency - An emergency classification which ,
- is defined as actual or iu inent i i substantial core degradation or ,
i melting with potential for loss l of containment integrity. l J o News Media Center - An emergency response facility ;
- (VYNPC Corporate Offices, )
i Brattleboro, Vermont) is ' i I dedicated to the news media for i the purpose of disseminating and j l coordinating information ! j I concerning accident conditions. ! ! All activities conducted within l l this center will be the l ) responsibility of the Vermont i i Yankee Nuclear Information l Director. ( i \ 1889e/3.194 1 I i a
Rev. 2 6/21/88 ( ' Page 1.3-6 o Observer - A member of an exercise control group. Each Observer may be assigned to one or more activities or functions for the purpose of evaluating, recording, and reporting the strengths and 1 weaknesses, and making recommendations for improvement. i o Operations Support - An emergency response facility Center (1st floor, Administration 4 Building) established to muster i skilled emergency response t 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 l exposure that would likely occur
! - 'f such actions were not i undertaken. ;
i o Protective Action . Projected radiological dose f Guides values to the public which ! warrant protective actions following an uncontrolled release i of radioactive material. i Protective actions would be ) warranted provided the reduction in the individual dose is not L offset by excessive risks to , individual safety in implementing j
; such action. [
l o Scenario - The hypothetical situation, from start to finish, in an exercise ! which is the theme or basis upon i 4 which the action or play of the i ! exercise unfolds. l ) o Site - That property within the fenced boundary of Vermont Yankee which 1 is owned by the Vermont Yankee
! Nuclear Power Corporation.
l l N o Site Area Emergency - An emergency classification that ] s indicates an event which involves J likely or actual major failurew l j of plant functions needed for the (
; protection of the public.
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s Rev. 2 $ 'O 6/21/88 < V Page 1.3-7 o Small-Scale Exercise - An exercise which tests as much of the licensee emergency plan and procedures without participation of state and local t J government agencies. o Technical Support - An emergency response facility i Center (2nd floor, Administration i Building) with the capability to assess and saitigate the accident using plant parameters and highly : qualified technical personnel. Also, assists in accident j j 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 9 requiring off-site monitoring. o Yankee Nuclear Services - A division of Yankee Atomic I Division (YNSD) . Electric Company. An Engineering support organization which provides emergency response ;
- support tr Vermont Yankee upon 1 request.
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1.4 REFERENCES
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1.4 REFERENCES
- 1. Vermont Yankee Nuclear Power Station Eroergency Plan. l
- 2. Vermont Yankee Nuclear Power Station Emergency Plan Implementing Procedures.
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- 3. Vermont Yankee Nuclear Power Station Final Safety Analysis Report -
Vermont Yankee Nu;1 ear Power Corporation.
- 4. Vermont Yankee Nuclear Power Corporation - Comunications Department Emergency Response Plan and Procedures.
- 5. Vermont Yankee Nuclear Power Station Emergency Operating Procedures.
- 6. Vermont Yankee Nuclear Power Station Core Damage Assessment Methodology.
- 7. Yankee Atomic Electric Company - Technical Administrative Guideline No. 12, Emergency Preparedness Responsibilities.
- 8. 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.
- 9. Daily Weather Maps. National Weather Service. Climate Analysis Center. Washington, DC 20233.
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i VERMONT YANKEE NUC1. EAR F0WER STATION f i EMERGENCY RESPONSE PREPAREDNESS EXERCISE 4 1988 L l 1 t i ; i t s 2.0 EXERCISE OBJECTIVES i ( I l 1 i t i le ) .1 1 1 ) l I
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I t ' Rev. 3 6/21/88 Page 2.0-1 4 6 VERMONT YANKEE NUC1. EAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE I a l 1988 i j 2.0 FXERCISE OBJECTIVES - VERMONT YANKEE i a i In order to demonstrate the radiological emergency response preparedness of the Vermont Yankee Nuclear Power Station, an amergency response ;
- preparedness exercise will be conducted on Wednesday, August 31, 1988. j
. The exercise being conducted is a small-scale exercise which will involve f 1
J the participation of Vermont Yankee station and corporate personnel. The ! l State of Vermont, State of New Hampshire, Conunonwealth o'f Massachur.etts, . ] and the local cormunities within the plume exposure pathway have the ] j opportunity to participate in the exercise, if they so desire. l i A set of exercise objectives for the exercise was w veloped to evaluate ( l and test certain elements of the Vermont Yankee emergency preparedness ; i program. The selected exercise objectives were based upon previous open ! items identified by the NRC and corrective actions taken in regard to
- follow-up action items identified by Vermont Yankee personnel. The exercise objectives will be used to ascertain the required input to the ,
l exercise scenario sequence of events and to establish the evaluation f ! criteria to be used by the exercise controllers and observers. The f 1 i specific exercise objectives to be demonstrated are as follows: l 4 I j A. Accident Assessment
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- 1. Demonstrate the ability of Control Room personnel to recognise l emergency initiating events and properly classify the condition l in accordance with pre-established emergency action levels.
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- Indicates NRC identified improvement items from the 1987 exercise. l 1887e/3.192 '
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- 2. Demonstrate the ability of the Control Room and TSC staff to coordinate the assessment of plcut conditious and ccrrective 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.*
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- 4. Demonstrate the ability of the TSC staff to initiate and ;
coordinate corrective actions'in an efficient and timely manner.* ; r
- 5. Demonstrate the ability of appropriate TSC staff to participate j with the Control Room and the EOF /RC in omdrgency classification
- and EAL discussions. ,
i. I 6. Demonstrate the ability to access data from appropriate ] chemistry samples in support of accident assessment activities j and plant conditions. B. Notification and Comunication .
- 1. Demonstrate that messages are transmitted in an accurate and l timely manner and that messages are properly logged and l documented.* l i
j 2. Demonstrate the capability to notify federal and state j authorities of emergency classifications in accordance with j t j established procedures. [ \ l 3. Demonstrate that appropriate status boards are utilized to i i display pertinent accident information at the various emergency response facilities.
- Indicates NRC identified improvement items from the 1987 exercise.
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J-6/21/88 , Page.2.0-3 b 1 Demonstrate that adequate emergency communication' systems are in j
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^ place to facilitate transmittal of data between the emergency , i l response facilities and federal and state authorities. l ! C. Direction and Control i 4 t i
- 1. Demonstrate the capability of key emergency response facility j' management personnel to direct and coordinate their respective ;
emergency response activities in an efficient and timely manner. .i I J 1 D. Emerzency Response Facilities . I i 1. Demonstrate the ability of station and corporate personnel to 1 activate and staff the emergency response facilities in a timely l i manner. I
- 2. Demonstrate and test the adequacy and effectiveness of emergency j I response facilities, operations, and equipmer.t.
f l E. Radiological Exposure Control I i t
- 1. Demonstrate the ability to provide adequate radiation protection l !
I, controls for on-site emergency response personnel, such as I appropriate personnel dosimetry, equipment, and pro *.ective ' } clothing. l l l i 4 l 2. Demonstrate the ability to monitor and track radiation exposure l of on-site emergency response personnel. l l 1 ' I i' i iO i
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- Indicates NRC identified improvement items from the 1987 exercise.
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F. In-Plant Corrective and Repair Actions
- 1. Demonstrate that on-site assistance teams can be dispatched and deployed in a timely manner.
- 2. Demonstrate the ability of on-site assistance teams to perform corrective maintenance on damaged plant equipment during emergency conditions.
- 3. Demonstrate the ability of plant personnel to trouble-shoot and evaluate problems associated with plant equipment and systems.
- 4. Demonstrate the ability to provide adequate administrative controls and documentation for necessary repairs of plant equipment and systems during an emergency situation.
G. Radiological Assessment
- 1. Demonstrate that radiological assessment pe*sonnel at the EOF can obtain radiological and meteorological data in a timely manner.
- 2. Demonstrate the ability to assess potential off-site radiological consequences based on plant conditions.
- 3. Demonstrate adequate staf fing, equipment readiness check, and deployment (if necessary) of off-site monitoring teams.
- 4. Demonstrate the ability to project the plume trajectory and potentially affected downwind sectors utilizing the computer dose assessment model (METPAC).
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- Indicates h7C identified improvement items from the 1987 exercise.
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Rev. 3 ' 6/21/88 p) y Page 2.0-5 - H. Protective Action Decision-Making a I 1. Demonstrate the ability to implement appropriate on-site 1 protective action measures for emergency response personnel. I i J" ' 1
- 2. Demonstrate the r* m of the protective action decision i awking proce s-t< . _repriate recossmendations concerning I
of f-site radiolot . uences. i L Parallel t I. Ot, J ;
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l 1. Test and , i idequacy of methods to establish and : saintain ac. ntrol and personnel accountability within the , l protected area. f J j 2. Demonstrate the licensee's capability for self-critique and j ability to identif y areas needing improvement. 1 J. Public Information [ 1 r I
- 1. Demonstrate the ability to develop and disseminate timely ;
! accurate press releases to the public and the news media. ; ' i 1
- 2. Demonstrate the ability to provide briefings for and to l L
' interface with the public and news media. (
t i j 3. Demonstrate the ability to cosinunicate and coordinate news [ i 4 releases between the EOF and the News Media Center. ; J 1 I 1 4. Demonstrate the ability to provide rumor control. {
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- Indicates NRC identified improvement items from the 1987 exercise.
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4 Rev. 3 6/21/88 l l Page 2.0-6 - } ' t 1 ; 1 ' 4 1 The annual Radiological monitoring drill and semi-annual Health l 1 Physics drill will be included as part of this exercise. A separate' j l i { Health Physics drill will be held to demonstrate the actual sample f a 1
. collection and analysis of in-plant chemistry samples which includes :
i the use of the Post-Accident Sampling System (PASS). [ I ! i i 1 ! I r i 4 i 1 i l i ! l i !O 1 4 i l l, i ! i l + l i r l l 1 l i i f
- Indicates NRC identit i improvement items frem the 1987 exercise.
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EMERGENCY RESPONSE PREPAREDNESS EXERCISE , ] j 1988 i 1 1 < 3.0 EXERCISE GUIDE!.INES AND SCOPE
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I f - i 1 1 l l 1 i t l i j VERMONT YANKEE NL' CLEAR POWER STATION g I EMERGENCY RESPOSSE PREPAREDNESS EXERCISE I l 1988 l I t e l b < I !, 3.1 EXERCISE GLIDELINES (
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() VE*LMONT (ANKEE N1) CLEAR POWER STATION EMERLEMCt RESPONSE PREPAREDNESS EXERCISE 1988 3.1 EXERCISE CUIDELINES A. Purpose This package proviJcs guidance for conducting the 1988 VYNPS Emergency Responst Preparedness Exercise. It provides the framework for demonstrating emergency response capabili. e, conducting the exercise and evaluating the results. I B. Concepts of Operations and Control of the Exercise p) ( Vermont Yankee will supply of ficial Controllers and Obsers ars for Lach 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. i i An Exercise Coordinator was appointed by plant management for the purpose of developink the acc' dent time sequence and. to be in l overall charge of conducting the exercise. The Exercise Coordinator vill 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. I Controllers for the exercise will distribute information to play >rs i on message carde, and in each facility a Controller will make I judgement decisions to keep the action going in accordance with the ( scenario t>atline. The Controllers will also provide advice to
- Observers and resolve probisms in their assigned emergency response 1885e/3.191 i
Rev. 1 6/21/88 r-'s Page 3.1-2 (x.s) facility. If a crisis situation arises, in Observer will first contact the Facility Controller who will then contact the Exercise Coordinator for advice or resolution of the problem. All nsjor 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 i their assigned emergency response functions. Individual observers are responsible for being knowledgeable in the area of their assigned function. The Observers will critique the ef fectiveness of the emergency response actions during the exercise and also provide a written evaluation to the Controller for the assigned facility. The e'tercise initial conditions will be provided to a Control Room j operations crew, located in the simulator area, by the Control Room j () Simulator Controllers. The plant and reactor system parameters for the exercise will be gencrated by running the accident scenario on the simulator. The remaining exercise message cards and aaditional i scenario parameters will be provided by Controllers / Observers at the times indicated by the exercise sequence of events, or when I requested by the players. Other message cards may be issued to l players at times required by player actions during the exercise. l l As the initiatin] events are provided to the plant staff, they will l 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 i Plan. Notifications will be made to the appropriate federal and state authorities. The hypothesired emergency will continue to develop based on data () O and information provided to the uperators located in the Simulator Room. Wherever possible, operators will complete responses as if 1885e/3.191
Rev. 1 'f i 6/21/88 Page 3.1-3 . they were actually responding to the plant events. Inconsistencies j in the scenario may be intentional and required to provide a basis j which tests capabilities of emergency centers to the maxiews extent j f 2 feasible in a limited time. Controllers have the authority to ]
- resolve or explain problems that may occur with the scenario during j j the r.xercise. ;
, f 4
C. General Guidance for the Conduct of the Exercise r l I ! I 1. Simulating Emergency Response Actions : i i : W Since exercises are intended to' demonstrate actual capabilities I as realistically as possible, participants should act as they l j would during a real emergency. Wherever possible, actions l' l should be carrie2 out. Emergency response actions shot;1d be simulated when it is not feasible to perform an action or when { l j the action has been previously identified as being simulated l ) during the exercise (refer to Section 3.3). When an emergency i 1 4 response is to be simulated, the Controller / Observer will i j ;
- provide verbal or written directions on which actions are to be i simulated, i 1 ,
I I Radiation Work Permits (RWPs) have got been is6ued for the l .J : conduct of the emergency response exercise. If scenario events ' direct players to areas that are actually RWP-controlled due to
]
1 high radiation, surface contamination, or airborne j radioactivity, players will simulate the activities they would l l have performed without actually entering the RWP-controlled l . area even if they are authorised on the RWP for some other duty. ) ) ! l J l 1 1 ; 4 l 1835e/3.191 1 l 1 j 1
Rev. 1 6/21/88 Page 3.1-4 (J)
- 2. Avoiding Violations of Laws Intentional violation of laws is not justiftable 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 he the case, l
- b. Exercise participants will not direct illegal actions to be taken by other exercise participants or members of the general public.
- c. Exercise participants will not intentionally take illegal l 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 4
Participants and Evaluators will be instructod to avoid i il endangering property (public or private), other personnel ' i responding to the exercise, members of the general public, animals and the environment. i.
' 1SS5e/3.191 i j
Rev. 1 6/21/88 (} (_ ,/ Page 3.1-5
- 4. Actions to Minimize Public Inconvenience It is not the intent, nor is it desirable or feasible, to effectively train or test the public response during the 1
conduct of radiological emergency exercises. Public inconvenience is to be minimized. The actions of federal, state and local agencies and nuclear power plant operators receive continuous public notice and scrutiny; therefore, the conduct of an exercise could arouse public concern that an actual emergency is occurring. It is important that conversations that can be monitored by the public (radio, loudspeakers, etc.) be prefaced and conclude 3 with the words, "THIS IS A DRILL; THIS IS A DRILL."
/ D. Emergency Response Implementation and Operations i
- 1. Initial and Follow-Up Notification Initial and follow-up notification of the emergency l
i classification will be made by tha plant staff in accordance a with existing emergency plan implementing procedures, unless directed otherwise. I
- 2. Control Roem Operations i
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 l supplemented af ter the ALERT by the emergency response '
-g organization. The plant and reactor system parametets will be
] 1 ( ,) provided to the Control Room Simulator players by the simulator i control board and by Control Room Simulator Controllers in the ISS5e/3.191
.______________-_-____--___i
Rev. 1 , 6/21/88 Page 3.1-6 ]! form of message or command cards when required. Other 4 information, such as radiological data and meteorological data, will be provided to Control Room players as necessary. Comunications between the Simulator Control Room and other l emergency response facilities will utilize communications links i J , that duplicate the emergency communications capabilities t i available at the Control Room or by utilising the actual - 1 Control Room communication system for transmission (e.g., l Gaitronics - PA System at the plant to make Control Room emergency announcements). ;
! I 1 3. Technical _ Support Center (TSC) Operations l 1 l 1 i
! The TSC emergency response organization will be activated ! I l during this exercise. TSC information will come from the i Control Room located in the Simulater Area. Information that j is normally accessible by TSC personnel froes the plant computer j l will be provided by Contro11ecs/Cbservers utilizing telephone f j comunications between the simniator area and plant computer . room. In addition. TSC Communicators, who would normally be [ . t ] assigned to the Control Room to provide TSC requested plant ' data, will be staged at the Simulator Area. :, l 1 ) 4. Operations Support Center (OSC) Operations l 1 ! j I
! The OSC emergency response organization will be activate during this exercise. Operations Support Center responses, direction and information will be comununicated with the ,
4 Technical Support Center. OSC Observers will accompany all OSC l 1 J-teams dispatched during the exercise and will have appropriate operational and radiological data for the players. No team , j participating in the exercise should leave the Staging Atoa without an Observer / Controller. l j s 1 1885e/3.191 i
Rev. 1 l 6/21/88 Page 3.1-7
- 5. Emergency Operations Facility / Recovery Center (EOF /RCJ, Operations The EOF /RC emergency response organization will be activated during this exercise. Information and data will be tre.nsmitted '
r to the EOF /RC from the TSC and Control Room (Simulator). EOF l f Controllers and Observers will provide other data to E07/RC
; players as necessary. , ,
3
- 6. Off-Site Monitoring Teams ,
I s Off-site monitoring teams will be fully activated and dispatched in accordance with existing procedures. Simulated ( data will be provided te off-site monitoring teams by the i
- Off-Site Monitoring Team Observers / Controllers. ,
- 7. News Meola Center Operations
. I i The News Media Center will be act.ivated and staffed n ring the ! exercise. Press releases to the general public and news media i j will be generated. News Media Center staff will obtain all [
j necessary information on current status of the' exercise through l consnunications channels with the EOF /RC. Simulated press f f releases will be compiled and disserhated in accordance with f
} the Vermont Yankee Consnunications Department Emergency Response j Plan and Procedures. All press releases are to be clearly l marked: THIS IS A DRILL. f i
l 8. Security Operations I
)i
- All security emergency responses appropriate to the exercise j scenario will be implemented in accordance with existing j procedures. Access control and personnel accountability within j the protected acea will be demonstrated. At no time will j
] 18S5e/3.191
W, ,- 7 l' L , Rev. 1 i 6/21/88 Page 3.1-8 l P actual plant security procedures be violated in support of the ; exercise. [ \ l E. Exercise Terminatly l I l l The exercise will be terminated by the Exercise Coordinator when all I emergency response actions have been completed in accordance with the exercise time sequence and exercise objectives. . The following steps will be implemented'to terminate the exerciset_ f
- 1. The Exercise Coordinator will receive ini.rmation from the j Facility Controllers concerning the status of player actions I
( and whether the stated facility emergency responrr actions and [ objectives have been demonstrated. !
- 2. The Facility Controllers will be responsible to inform the ,
Exercise Coordinator of their facility status and whether their ; facility emergency response actions and objectives have been satisfactorily observed.
- 3. Upon receiving all of the Facility Controllers status, the l Exercise Coordinator will inform the Site Recovery Manager and j TSC Coordinator that the Controller / Observer organization has !
completed their exercise observations and is ready to terminate f the exercise. [ t i
- 4. A coordinated decision to terminate the exercise would be made' between the Site Recovery Manager and the TSC Coordinater.
I
- 5. The Site Recovery Manager or TSC Coordinator will terminate the exercise.
O 1885e/3.191
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i \ i i i 4 i i <
! VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE
- 1988 l i 1
4 l 3.2 EXERCISE OBJECTIVES AND EXTEITI OF PLAY
! t
.l } i l , . j t I l l . 1 l l i l j 1 1 1 l l l I i 2 I l 1902e/23.258 1 1 I j 1 i
. - - ~ - - - - - _ _ - - - - - - - - - - - - . _ - - . _ . _ _ -
l O 6 Rev. 1 6/21/88 Page 3.2-1 VERMONT YANKEE NUCI. EAR POWER STATION j EMERCENCY, RESPONSE PREPAREDNESS EXERCISE 1988 i 3.2 EXERCISE OBJECTIVES AND EXTENT OF PLAY Extent of Play . A. Accident Assessment
- 1. Demonstrate the ability of Control Room A.1 The scenario events initiated on the simulator personnel to recognize emergency initiating provides the operational and radiological data j events and properly classify the condition which allows personnel to des.Onstrate this in accordance with pre-established objective by implementing Procedure A.P. 3125, ^
1 energency action levels. Emergency Plan Classification and Action Level Scheme. i Demonstrate the ability of the Control Room A.2 The scerefio will provide technical 2. and TSC staff to coordinate the assessment Information to players which.will allow them of plant conditions and corrective actions to analyze plant conditions and propose to mitigate accident conditions. corrective actions. 1 i 3. Demonstrate that information concerning A.3 Telephone commmunications links will be established by e-micators between the ) plant conditions can be disseminated between the Control Room and TSC in a simulator Control Room and the TSC in order to I transmit key information and data. Exercise l timely manner.* controllers / observers will evaluate the timeliness of information.
- 4. Demonstrate the ability of the TSC staff to A.4 The scenario provides events that will enable l the TSC to coordinate in-plant corrective i Initiate and coordinate corrective actions actions through the use of OSC personnel.
l in an efficient and timely manner.* i j i -
- Indicates NRC-identified improvement items from i the 1987 exercise.
1 1902e/23.258 , i i
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[\. Rev. 1 - l 6/21/88 Page 3.2-2 Extent of Play
- 5. Demonstrate the ability of appropriate TSC A.5 The scenario includes events which allow for staff to participate with Control Room and discussion between the Control Room. TSC, and the EOF /RC in emergency classification and EOF staff on classification.
l EAL discussions. l
- 6. Demonstrate the ability to access data from A.6 Scenario events will require Chemistry and l appropriate chemistry samples in support of Health Physics technicians located at the OSC accident assessment activities and plant to simulate taking reactor coolant or conditions. containment air samples to assess plant conditions. Sample results will be provided by the Exercise Observers who accompany the t2chnicians during their sampling activities.
(Refer to Procedure OP-3530, "Post-Accident Sampling.") B. Notification and Commuunication
- 1. Demonstrate that messages are transmitted B.1 Various communications links will be in an accurate and timely manner and that B.3 established between the emergency response messages are properly logged and B.4 facilities in order to transmit information documented.* and data. Recordkeeping and documentation will be demonstrated in accordance with Procedure OP-3504 "Emergency Cosamunications."
Commuunications and transfer of data between facilities will be evaluated for timeliness and completeness.
- 2. Demonstrate the capability to notify B.2 Vermont Yankee staff, NRC, and state federal and state authorities of emergency authorities shalL he notified in accordance classifications in accordance with with established procedures. NRC will be established procedures. notified by utilizing the NRC EMS red phone.
The State authorities will be notified through the Nuclear Alert System (Orange Phone).
- Indicates NRC-identified improvement items from the 1987 exercise.
1902e/23.258
N./ Rev. 1 6/21/88 Page 3.2-3 Extent of Play l l
- 3. Demonstrate that appropriate status boards~
are utilized to display pertinent accident information at the various emergency response facilities. l
- 4. Demonstrate that adequate emergency communication systems are in place to l
facilitate transmittal of data between the emergency response facilities and federal and state authorities. C. Direction and Control Demonstrate the capability of key emergency C.1 All emergency response facilities have
- 1. designated coordinators who will direct and response facility management personnel to coordinate emergency response activities in direct and coordinate their respective emergency response activities in an
- their particular area of responsibility.
efficient and timely manner. I D. Emergency Response Facilities
- 1. Demonstrate tne ability of station and D.1 Scenario data r.ad exercise events will allow corporate personnel to activate and staf f D.2 activation and operation of Vermont Yankee 4
the emergency response facilities in a emergency response facilities. The Simulator timely manner. Control Room. Control Room (cn==nnication functions only). TSC. OSC EOF /RC, News Media i Demonstrate and test the adequacy and Center and Engineering Support Center will be 2. effectiveness of emergency response activated in accordance with established facilitics, operations, and equipment. procedures. Designated plant and corporate emergency response personnel will participate in the exercise.
- Indicates NRC-identified improvement items from -
i the 1987 exercise. l 1902e/23.258 l
, - g s ( x.-) Rev. I 6/21/88 Page 3.2-4 Extent of Play l E. Radiolor,1 cal Exposure Control Demonstrate the ability to provide edequate E.1 Scenario events will require OSC On-Site
- 1. E.2 A5sistance Teams to be dispatched to radiation protection controls for on-site arvestigate problems associated with plant emergency response personnel, such as Investigation and repair appropriate personnel dosimetry, equipment. equ.'? ment.
activities in the plant will require and protective clothing. implementation of radiation protection Demonstrate the ability to monitor and contro s which include monitoring and tracking i 2. track radiation exposure of on-site of radiation exposure of OSC On-Site emergency response personnel. Assistance Teams. (Refer to Procedure OP-3507. "Emergency Radiation Exposure F. In-Plant Corrective and Repair Actions Control.") F.1 Scenario events will require OSC On-Site
- 1. Demonstrate that On-Site Assistance Teams Assistance Teams to be dispatched can be dispatched and deployed in a timely F.2 manner.
F23 to insestigate problems associated with F.4 plant equipment. Equipment mockup of the
- 2. Demonstrate the ability of On-Site postulated damaged plant equipment will be available for pisnt personnel to perform Assistance Teams to perform corrective corrective maintenanca. Plant personnel will maintenance on damaged plant equipment during emergency conditions. also be given the opportunity to trouble-shoot and evaluate the problems associated with the Demonstrate the ability of plant personnel damaged plant equipment.
3. to trouble-shoot and evaluate prob 1 cms associated with plant equipment and systems.
- 4. Demonstrate the ability to provide adequate administrative controls and documentation for necessary repairs of plant equipment and systems during an emergency situation.
# Indicates NRC-identified 'mprovement items from the 1987 exercise.
1902e/23.258
i ( \v Rev. 1 6/21/88 Page 3.2-5 Extent of Play C. Radiological Assessment
- 1. Demonstrate that radiological assessment C.1 Scenario events will postulate off-normal personnel at the EOF can obtain C.2 radiological levels in the drywell and radiological and meteorological data in a C.4 increased area radiation levels in the plant.
timely manner. The scenaria will provide information on plant conditions and in-plant radiological
- 2. Demonstrate the ability to assess potential conditions to players which will allow them to off-site radiological consequences based on evaluate potential off-site radiological plant conditions. consequences. Players will implement appropriate sections of Procedures OP-3513,
- 3. Demonstrate ad quate staffing, equipment "Evaluation of Off-Site Radiological readiness check, and deployment (11 Conditions" and OP-3511. "Off-Site Protective necessary) of Of f-Site Monitoring Teams. Actions Recommendations."
- 4. Demonstrate the ability to protect the C.3 off-Site Monitoring Teams will be assigned at plume trajectory and potentially affected the OSC. Players will implement appropriate downwind sectors utilizing the computer sections of Procedure OP-3510. "Off-Site and dose assessment model (METPAC). Site Boundary Monitoring."
H. Protective Action Decision Making
- 1. Demonstrate the ability to implement H.1 On-site protective action measures will appropriate on-site protective measures for include radiation exposure control and plant emergency response personnel. evacuation of nonessential personnel. After plant evacuation and accountability has been completed, all plant personnel and contractors not directly involved in the exercise may be allowed to return to work.
- Indicates NRC-identified improvement items from the 1987 exercise.
1902c/23.258
p , i I )
\s \_ /
Rev. I 6/21/88 Page 3.2-6 Extent of Play
- 2. Demonstrate the adequacy of the protective 11 . 2 Protective action decision making will be action decision making process to make demonstrated in accordance with recommendations concerning off-site Procedure OP-3511. "Off-Site Protective radiological consequences. Actions Recommendations".
I. Parallel and Other Actions
- 1. Test and evaluate the adequacy of methods I.1 Security activities will be implemented in to establish and meintain access control accordance with established procedures to and personnel accountability within the control access to the protected area.
protected area. Assembly of emergency response personnel and evacuation of contractor / visitors will be implemented in order to test pe rsonnel accountability within the protected area. Ilowever, af ter the plant evacuation accountability checks have been completed, contractors and visitors will be exempted from additional personnel accountability checks.
- 2. Demonstrate the licensee's capability for 1.2 Exercise critique will be conducted with self-critique and ability to identify areas exercise controllers, observers, and players.
needing improvement. Critique items will be compiled and documented by the Exercise Coordinator. J. Public Information
- 1. Demonstrate the ability to develop and J.1 The News M'e dia Center will be fully activated.
disseminate timely, accurate press releases J.2 Inf ormation on the simulated events occurring to the public and the news media. J.3 at the plant will be gathered, verified, incorporated into a press release, and
- 2. Demonstrate the ability to provide disseminated to key players. Also, after briefings for and to interface with the approval this information will be discussed at public and news media. the News Media Center.
- Indicates NRC-identified improvement items from the 1987 exercise.
140?c/23.?58
- - - - - - - _ - ~ . - . . .__.- __. - . . - _ _ _ - . - - _ - _ _ _ _ - _ _ - . . _ _ . _ _ _ - - _ . - _ _ - - . _ . _ ._
O Rev. I 6/21/88 Page 3.2-7 Extent of Play i 1 3. Demonstrate the capability to connunicate and coordinate press releases between the EOF and the News Media Center.
- 4. Demonstrate the ability to provide rumor J.4 A hot line w111 be established to provide control. rumor control for questions concerning the simulate.d accident.
i l a i I I i a i l. ) l l ( i
- Indicates NRC-identified improvement items from the 1987 exercise.
r 1902c/23.258 2
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1 i i 1 I i 4 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE { 1988 l i l l l 3.3 PLAYER INSTRUCTIONS l l i )
- i i
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i I 1 i 1 ! l 1 i t 1883e/3.189
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i i h i Rev. 2 } 8/15/88 i Page 3.3-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1988 , i t I l 3.3 PLAYER INSTRUCTIONS c ; The Versoont Yankee Emergency Response Preparedness Exercise will be conducted during the week of August 29, 1988. The successful r demonstration of emergency response capabilities will depend on player response and protocol. The following information is provided for players on the details of the exercise and instructions that players should j follow during the exercise. Department heads are responsible for l ensuring that personnel are trained on this information. [ A. General Guidelines i
- 1. Exercise participants include Players, Controllers Observers, NRC Evaluators, and an Exercise Coordinator. Centro 11ers will f provide players with consnand and message cards to initiate i emergency response actions. Observers will evaluate actions i along with the NRC. Controllers. Observers, and NRC Evaluators I
will be identified by badges.
- 2. Alvays identify yourself by name and function to the l Controllers, Observers, and Evaluators. Wear a name tag if ct.e j is provided. .
f
- 3. You may ask the Controller / Observer for information auch ass
- a. Initial conditions of the plant and systeas including o ope.ating history of the core 1883e/3.189
Rev. 2 O (, 8/15/88 Page 3.3-2 o initial coolant activity o general weather conditions o availability of systems according to the scenario
- b. Area radiation data at the location of emergency teams.
I l c. Airborne data at the location of the plant and field survey teams after a sample has been appropriately taken. I
- c. Counting etficiency of all counting equipment,
- e. Activity from nose swabs or skin contamination surveys.
, ,Q r U 4. You may ng ask the following from the Controllers /Observerst
- 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.
1
- f. Assistance in carrying out calculations.
i
- 5. Play out all actions, as much as possible, in accordance with your Emergency Plan and Procedures as if it were a real l k- emergency. If an action or data is to be simulated, an Exercise Controller or Observer will provide Players with appropriate direction.
l Rev. 2 : 8/15/88 i O ' Page 3.3-3 j i
- 6. Always identify and discuss your actions to the Controllers and j t Observers. State your data cut loud as you are recording it. ;
yor your own benefit, it is recosamended thatlyou play out your oj 4. actions as much as possible, as if it were a real emergency. ! t It is to your advantage to exercise as many appropriate ; response actions as poscible.
- 7. Periodically speak out loud, identifying your key actions and i i
decisions to the Controllers / Observers. This may seem j artificial, but it will assist the evaluators and is to your .j benefit. [ l
- 8. When you are assigned to complete a response action, be sure to j be accompanied by an Exercise Controller or Observer at all l times.
O 9. If you are in doubt about completing a response action, ask f i your Controller or Observer for clarification. The Controller / Observer yill not prompt or coach you. Emergen:y i I response actions must not place exercise rsrticipants in any i t potentially hasardous situations. L i
- 10. The Controller / Observer will periodically issue messages or j instructions designed to initiate response actions. You must l accept these messages isusediately. They are essential to tho !
proper conduct of the exercise. ; I
- 11. If the Controller intervenes in your response actions and [
recommends you redirect or reconsider your play actions, it is f 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 must be followed. 1
- )
l Rev. 2 8/15/88 l n Page 3.3-4 l i (v)
- 13. Respond to questions in a timely manner.
- 14. Do not accept any w asages/ instructions from NRC Evaluators.
They are required to work through your Controller / Observer if l they want to initiato additional emergency conditions. However, you may answer questions directed at you by NRC : l Evaluators. If you do not know the answer, refer them to your lead player or Controller / Observer. i
- 15. You must play as if radiation levels are actually present in accordance with the information you receive. This may require you to wear protective clothing, respirators, additional dosimeters, observe emergency radiation protection practices, .
and to be aware of and minimize your radiation exposures. O
\ 16. Controllers / Observers / Evaluators are exempt from simulated
\
1 radiation levels and other emergency conditions. Do not let ' this confuse you or cause you to act unwisely. Hewever, no one is exempt from normal station radiological practices and procedures.
- 17. Utilize status boards and log books as much as possible to ,
decument and record your actions. i
- 18. Always begin and end all consnunications 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 l Controller / Observer iernediately af ter the exercise. A critique l l
will follow the exercise. Areas for improvement or weaknesses I when corrected will improve the overall emergency response I capability. ; i l i t l l 1883e/3.189 1
Rev. 2 8/15/88
' [']
w/ Page 3.3-5 B. Player's Simulation List The following describes those specific actions which do not have to be performed and can be simulated by exercise participants. All other actions are to be performed in accordance with our operating procedures. No action will be allowed which alters or affects the ongoing operation of the piant. The simulation list is as follows:
- 1. Scenario specific data will not be programed into the plant I
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 Organization will be prestaged at the Simulator Area.
4 N
- 3. Meteorological data will be simulated using a "test" file available to the Simulator Control Room Meteorological Computer '
System. I f 4. After plant evacuation accountability has been completed, plant
- personnel and contractors / visitors not directly involved in the l exercise will be allowed to return to work, at the discretion I
.l of the TSC Coordinator. i
- 5. The distribution of potassium iodide (KI) will be simulated.
) 6. Charcoal cartridges will be used as silver neolite cartridges j during 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, i J 1883e/3.189
k Rev. 2 l 8/15/88 1 Page 3.3-6 [ I l 9. Off-site monitoring teams and security boundary monitoring j personnel will not wear protective clothing and/or respirators. i i i i i j 10. The inner gate and electrically controlled doors will not be left in the open position during this exercise. i I 1 11. Initial on-shift chemistry and Health Physics Technicians l actually in the plant will be simulated. l 1 { } 12. The plant Caitronics is not available from the simulatort ! actual plant notifications will be made, through the Vermont i j Yankee plant Control Room. i l
- 13. Controllers / Observers will not be issued dosimetry unless plant ;
access is required prior to the exercise. Security will be i notified of their assigned location. l 1 l l 14. All decontamination actions associated with the exercise may be j q simulated after discussion and approval by the ( l controller / observer. I 1 l t i i t
- 15. The use of respiratory protection equipment may be simulated by plant ;
l
- personnel after discussion and approval by the controller / observer. !
I i
- 16. Radiation Work Permits (RWPs) have not been issued for the 6 I conduct of the emergency response exercise.
I 1 h j C. Simulator Control Room Information f I ! J ! l The following describes how the Simulator Control Room emergency ! 1 response activities will be integrated with the plant Control Room f functions during the exercise I l i O 1883e/3.189
- i i !
i Rev. 2 ; 8/15/88 ! Page 3.3-7 i O. I 1. Players reporting to the Main Control Room will be directed to ) 3 an area (SS office) that will have a Controller and [ coeurunications link with the simulator. All Control Room f , exercise conuounications should be directed to the Simulator j I Control Room. ; I 2. All exercise Caitronics calls to the Control Room and vice [ ] versa will be relayed or answered by the Control Room exercise
- f i controller. Channel 3 should be uti11
- ed for all exercise ;
} ! j messages. j 1 6
- 3. Gaitronies plant announcements will be coordinated by the [
Starulator Controller. They will be made by the operating crew j in the plant Control Room. l ]2 t 4 TSC status and information consnunicators normally assigned to. 1 the Control Room, and a chemistry Health Physics Technician for
- l ;
i initial radiological and meteorological data, will be prestaged [ j at the simulator. l i t q i l
- 5. Process computer ID data, normally accessible by TSC personnel, (
j will be provided by a designated person in the simulator area l { via personnel in the plant Computer Room. ! I ! i 6. Personnel movement in and out of the Simulator Control Roon
- l will be limited to the exercise Controllers / Observers. l
( !
- 7. Cosuounications equipment in the Simulator Control Room is the l
- i. ,
same as the plant Control Room. Commercial phone extensions I {
,; are different, but auto ring down and speaker phones are operab:e. The orange state phone and red INS-NRC phone will be
] operable. The orange phone extension is 613. jO
- 1883e/3.189
-I i ,-w - _- - , - , , _ , , , - . . . ,,.m_~__,_,-,.,y,q,,_p p_. _. m .
__,,g ,,. __m._ y
Rev. 2 8/15/88 (~;) l x, Page 3.3-8 D. Player's Camesmanship This section contains a listing of items to improve our gamesmanship during the exercise. The listing of items applicable to all in the gamesmanship area are as follows:
- 1. When significant events occur or when you are about to perform a significant action, make it known. j i
- 2. Keep all messages, status boards, and problem boards accurate, up to date, timed, and dated.
- 3. Briefings need to be held regularly, at a minimum every 30 minutes.
Ch (_j 4. Key players should wear badges identifying their role. Sound log books should be used in all emergency centers. ; i
- 5. All announcements, including those on the Caitronics should state "THIS IS A DRILL."
r
- 6. Avoid simulation unless it has been specified. L'se protective clothing where called for, step-off pads, etc.
E. Personnel Accountability and Participation Plant Security will be provided with a itst of exempt personnel for the exercise. All other personnel, not listed, are expected to l participate as required by the Emergency Plan. The exempt list of plant personnel will include the On-Shift Security Crew. Operating Crew, and Duty Chemistry and Health Physics Technician. Security at the Training Center ent.rance will also limit access through the O doors to exercise participants for the duration of the exercise. I 1883e/3.189
Rev. 2 l 8/15/88 Page 3.3-9 i l (J) . l T. Exercise Critiques The followir.g is a brief description of the critique sessions that will be held after the exercise. TLe critique sessions are held to determine whether the stated exercise objectives were met, verify I the effectiveness of our emergency plan and procedures, and identify areas for future improvement. The specific schedule for the 1 critique sessions will be announced at the conclusion cf the l exercise. Center Critiques This meeting will be conducted by the Controller with participants I to debrief them on findings for the particular emergency center. Three critique sessions will be heldt r O 1. SRM. EOF. and NMC 1
- 2. TSC and Simulator Control Koom ,
- 3. Operations Support Center and Security t
Controller Debrief T1is r4eting will be conducted by the Exercise Coordinator to ec pile all exercise conm nts and problems. Partidpation is imited to Exercise Controllers. i Exercise Critique i This meeting will be conducted by the Exercice Coordinator to l present to management a suxury of all major probless and I l deficiencies identified during the exerciso. Participants include Vermont Yankee management. Exercise Controllers, key players, and NRC. l l l 1883e/3.189 l c
l I I l ) Rev. 2 ! j 8/15/88 ! Page 3.3-10 j l 1 I i 2 NRC Exit ! A j Issnediately fc11 ewing the exercise critique, the NRC will present f j their findings. Participants will be the same as in the exercise f l eritique. j t i i I I l !' l i ; ! I i ( ) i l ' ? i l , l l i l I h } l i 18S3e/3.189 l i
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( l ! VERMONT YAM:EE hTCLEAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCl$E ! l I l 1988 i I 3.4 PROCEDVRE EXECUTION LIST I 1 i i O i I i l 1 l I i l j 1882e/3.185 i
- ~ ~ , . .v,----- ~ -n- ._,,,nn_ .
e 4 .A Rev. 1 5/23/88-() Page 3.4-1 VERMONT YANKEE NLCLEAR POWER STATION 4 EMERGENCY RE3?0NSE PREPAREDNESS EXERCISE . 1983 3.4 EhiRGF ' .MPLEMENTING PROCEDURES EXECUTION LIST I Procedure ;mbe r Title . AP 3125 "Emergency ?lan Classification and Action i Level Scheme" AP 3512 "Release of Public Information" 4 OP 3500 "Unusual Event" OP 3501 "Alert" c OP 3502 "Site Area Emergency" j OP 3503 "General Emergency" OP 3504 "Emergency Communications" OP 3507 "Emergency Radiation Exposure Control" 4 OP 3510 "off-Site and Site Boundary 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 kesponse" OP 3525 "Radiological Coordination" OP 3530 "PosteAccident Scmpling" 1 J i J i 1882e/3.188 I 1
l O i l i i VERMONT YANKEE NUCLEAR POWER STATION
\
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 O l 3.5 EXERCISE TERMINATION CRITERIA i O . ! 1881e/3.187 t l
Rev. 2 6/21/88 :
. Page 3.5-1
] _ VERMONT YANKEE NUCLEAR POWER STATION ', EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 4 ! 3.5 EXERCISE TERMINATION CRITERIA , I l j The exercise may be terminated under the following circumstances: l ! ?
- 1. If all emergency response actions have been completed in accordance ,
in3 Pr i 2. If an actual plant emergency condition develops coincident with the } exercise; and i
- 3. If an actual off-site emergency impacts the response actions of 1 Vermont Yankee exercise participants. i I !
In the event that Item 2 should occur, the followir.g actions will be I taken I i !
- 1. The Shift Supervisor will contact the TSC Coordinator and inform him j of the plant status. The TSC Coordinator wili, in turn, contact the i Site Recovery Manager and inform him of the plant status;
! l ]
- 2. The Site Recovery Manager will imediately inform any State
- representativos at the EOF of the nature of the emergency;
! 3. Concurrent with the notification in Step 2, the Control Room w.t' announce over the plant paging system the following statement: 1 "The emergency plan exercise has been terminated. I repeat. The emergency plan exercise has been terminated." l t 4 1881e/3.187 l i-1
L 4 Rev. 1 6/21/88 . j Page 3.5-2 This message may be imrnediately followed by the appropriate j emergency class announcement (if appropriate); l 4 The Exercise Coordinator would be responsible for directing the ; actions of the Controllers / Observers; and ] , 1 S. The emergenc'j plan / procedures and notifications applicable to the l I event would be implemented in accordance with the nature of the emergency (if appropriate). l ! J In the event that Item 3 should occur, the following actions should be i taken i 3
- 1. The State Police, having been notified of the emergency, should open i j direct communications with the Vermont Yankee Control Room using the l Nuclear Alert System; {
i
- 2. The Shift Supervisor will notify the Control Room Controller who, in ,
l turn, will notify the Exercise Coordinator; ;
- I 4
- 3. A coordinated decision would be made in conjunction with the Site {
Recovery Manager and/or the TSC and EOF Coordinators concerning the f completion of the exercise; ! I l l 4. The Exercise Coordinator would be responsible for temporarily l l halting the exercise until such time a decision could be'made; i i ] 5. If the final decision were to cat.:e1 the exercise, then the Exercise j Coordinator would be responsible for directing the activities of the l evaluation team as well as for the notification of NRC; l l l .i \ ) 1881e/3.187 1 1 0 i l
l i I 1 4 ! t i i Rev. 2 ; i' 6/21/88 ' Page 3.5-3 } t
- 6. If the final decision were to continue the exercise, then the j i
Exercise Coordinator would be responsible for informing all < : l Controllers / Observers $f the projected change to the expected i i j response action (s); 'and -
~
j i j 7. The Exercise Coordinator woul'd direct'his organisation as to the ' "" l: 4
- appropriate action required to restore the exercise sequence. !
I , i I J P l e I 1 6 f t I l 1 l 1 , j 1 . j I I
- i
. i l l' l,
1 1 i 6 I i i i 4 j 1 a ( 1 1 I ! 1881e/3.187 I 1 i f I
1 O , VERMONT YANKEE NUCLEAR P0h'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 4.0 CONTROLLER /0BSERVER INFORMATION l l O 1
'I i
1 O 1880e/3.186 i
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 4.1 CONTROLLER /0BSERVER ASSIGNMENTS NOTE: Assignment list will be provided at the exercise briefing. l
\
O 1880e/3.186 i I
- n - - - -- a - -- w l
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VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 6 E 4.2 CONTROLLER AND OBSERVER EXERCISE GUIDANCE i O ! I l 1 I 1893e/3.198 I l
Rev. 0 5/6/88 Page 4.2-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE , 1988 4.2 CORIROLLER AND OBSERVER EXERCISE GUIDANCE Prior to the exercise, each Controller / Observer 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 l 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 / Observer should identify any questions he/she has with the package , content and/or their assignment. It is the responsibility of each O 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 theraselves with their assigned Center and 4 Controller prior to the exercise. The Controller will be responsible for
- directing observer activities throughout the course of the exercise. At
! exercise termination, each Controller is responsible for meeting with their Observers and directing their critique and documentation of their exercise i comments. Each Controller will be responsible for ensuring that this documentation is provided to the Exercise Coordinator at the conclusion of the critique session. Each Controller is also responsible for providing a brief ; sumary of their facility comments during the formal critique. i Controllers / Observers shculd identify themselves to players and explain their role in the exercise. Controllers / Observers should inform players that if their actions are going to deviate f rom standard plant or emergency procedures i 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 coments should provide the time, place, and names of involved personnel.
Section 4.3 contains log sheets and evaluation forms to be used for documentatfun of observations. The primary role of exercise Controllers / Observers is to evaluate the j, emergency responses of the players. In order to document the adequacy of l 1893e/3.198 1 4 ,
Rev. 0
-5/6/88 p Page 4.2-2 emergency response actions during the exercise, Controllers / Observers art 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 recomendations for improvement detailing corrective actions, if possible. Controllers / Observers should not allow their biases to be documented as recognized weakness or deficiencies. Coments and recomendations 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, Sce.nario, Training, Facility 1.ayout. Off-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Comments. i Facility Activation coments should identifyr (1) the time that emergency response personnel were notified; (2) when the facility we 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. O Communication comments should identify: (1) personnel familiarity with emergency comunications use; (2) whether auf ficient comunications 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 effectiveness of data transfer; (5) whether there were any problems in the design of the existing communications system (i.e., locatian relative to traffic flow); (6) whether there were any recognized difficulties in use of computer systems; and whether center status boards are ef fectively und. Observers should document their coments in this area very carefully, providing sufficient details to track any recognized deficiencies. Plans and Procedural coments should identify: (1) whether personnel were familiar with the details of overall concepts of applicable procedures; (2) whether situations developed which required dev stion from the procedure or , plant (3) whether personnel were overwhelmed wit + 1 ',cedural requirements ' distracting them from performing their required e .tgency response function, and (4) whether the procedures adequately described the actions required to complete an assigned function. Equipment capability coments should identify: (1) whether all necessary materials and equipment were available and functional; (2) whether emergency response personnel checked operabilit.y of equipment prior to conducting their assignment; (3) whether backup equipinent was readily available when < malfunctions were reported; (4) whether the available systems provide an j adequate service; and (5) whether equipment malfunctions impacted the expected emergency response. 1893e/3.198
s Rev. 0 5/6/88 l
~' Page 4.2-3
\s / 1 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 Contco11ers/ Observers 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 ef fectiveness of i the team in defining the plume condition and samplo locations. Dose projection techniques should be evaluated in conjunction with this general O cate >ry. Consideration of dose projection technique should identify: the effectiveness of the system in allowing the correct interpretation of off-site conditions, and (2) the effectiveness of using the projection (1) 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 Controller after the exercise and prior to the plant critique. 1 F l b i 1893e/3.198 l N
I 1 1 l l l l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1988 1 1 l 4.3 CONTROLLER AND OBSERVER CO.TTENTS , i l l i l 1898e/18.334
l ; Rev. 0 - 5/19/88 Page 4.3-1 ; fg (,,) VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1988 4.3 CONTROLLER AND OBSERVER COMMENTS f 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 (Attschment 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 Controller for each location. , O Attachment C is enclosed for summarizing major observations and comments. This form MUST BE submitted by each Observer / Controller to their respective Controller. Each Controller will subsequently submit these forms to the Exercise Coordinator for inclusion into the final exercise report. I l i B l l l i ( 1898e/18.334 1 i l
Rev. 0 5/19/88
-~s Page 4.3-A.1 i
N )> VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 ATTACHMENT A Vermont Yankee Nuclear Power Station Emergency Response Exercise / Drill Evaluator's Observations-Chronological Log Time Observation / Comment O l l l l rg Name Area Evaluated . (s) Date: 1898e/18.334 i l
l l l Rev. 0 5/19/88 Page 4.3-A.2 VERMONT YANKEE NUCLEAR F0WER STATION EMERGENC'.' EESPONSE PREPAREDNESS EXERCISE 1988 l ATTACHMENT A l (Continued) Time Observation / Comment I i O j l l l I k i l 1 l Name! Area Evaluated: Date: 1898e/18.334 i _- _ _ _ - - . . . _ _ _ _ _ _ _ _ . - - _ - - _ _ _ _ . .
Rev. 0 5/19/88 Page 4.3-B.1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERC,1,SE S 1988 ATTACMMENT B ! Vermont Yankee Ernergency Exercise / Drill Evaluation Check List i INSTRUCTIONS , The following evaluation check list is provided to assist the i Controllers / Observers with their evaluation of the exercise / drill. The Controllers and Observers should complete the check lists for the location or emergency responses which pertain to areas which they were responsible for observing or controlling during the exercise / drill. The evaluation check list will u.l.lize a rating set :e based upon three (3) types of ratings .followed by coments and suggestions as indicated below: Rating Symbol Coments and Suggested Iroprovements O Adequate A May be followed by coments and suggestions for improvements, especially if rating is marginal. Inadequate I Must be followed by coments, together with suggestions for i improvement. ; Not Observed or N No coments or suggestions j Not Applicable are required. l l If your evaluation indicates inadequate performances, please provide a description of the problem area and suggested solution for improvement as ' indicated on the Emergency Exercise / Drill Evaluation Form or on a separate piece of paper. f i l i 1898e/18.334 l
,[s r Rev. 0 ' 5/19/88 Page 4.3-B.2 , j VERMONT YANKEE NUCLEAR POWER STATION ) EMERGENCY RESPONSE PREPAREDNESS EXERCISE ; 1988 2
+ :
ATTACHMENT B l (Continued) i Check lists have been provided for the following facilities / areas: ]: Section Page [ d I. Control Room (Simulator and Actual) 4.3-B.3 ! II. Technical Support Center 4.3-B.6 l III. Operations Support Center 4.3-B.10 j IV. Emergency Operations Facility / Recovery Center 4.3-B.14 _j V. Site and Off-Site Monitoring 4.3-B.13 i VI. Security 4.3-B. 20 L VII. News Media Center 4.3-B.22 [ I L l l l l 1 i I i 1 1898e/18.334
y .._ .-- .- h Rev. 0 5/19/88 Page 4.3-B.3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 i ATTACHMENT B ! (Centinued) l [ I. CONTROL ROOM 1 INSTRUCTIONS 4 l The following evaluation check list is'provided to assist the [
~
Controllers / Observers with their evaluation of the exercise / drill. The Controllers and Observers should complete the check lists for the location or [ emergency responses which pertain to areas which they were responsible for observing or controlling during the exercise / drill. The evaluation check list !
< will utilize a rating scale based upon three (3) types of ratings followed by ,
comments and suggestions as indicated below: , I Rating Symbol Comments and Suggested Improvements ! i Adequate A May be followed by comments and 1 s'uggestions for improvements, especially if rating is marginal. , t Inadequate I Must be followed by comments, ' together with suggestions for improvement. l [ Not Observed or N No coments or suggestionn i Not Applicable are required. If your evaluation indicates inadequate performances, please provide a ; description of the problem area and suggested solution for improvement as i indicated on the Emergency Exercise / Drill Evaluation Form or on a separate I piece of paper. Check list comences on the following page. O 189Se/18.334 l
b Rev. O ; 5/19/88 ! S Page 4.3-B.4 , VERMONT YANKEE NUCLEAR POWER STATION , EMERGENCY RESPONSE PREPAREDNESS EXERCISE
- 1988 ,
l ATTACHMENT B ; (Continued) , k I. CONTROL ROOM
; I
! Rating Coment s , A. Accident Assessment / Emergency Classification
- 1. Did the Control Room staff demonstrate Yes/No
, the ability to recognize emergency j initiating conditions and classify the events in accordance with AP-3125. *
- 2. Did the Control Roon staff demonstrate Yes/No the ability to coordinate the assessment of plant conditions and corrective actions with the Technical Support Center?
j B. Notification and Communication i , 1. Did the Control Room staff demonstrate the Yes/No j ability to notify the plant staff of an (
- emergency through the use of alarms and the ;
public address system? 1
; 2. Did the Control Room staff demonstrate the Yes/No ,
j ability to notify federal and state l j authorities of emergency classifications in > ; j accordance with established procedures? l Was information flow within the Control Room Yes/No I ) 3. and to other appropriate emergency response ; j facilities timely, complete, and accurate? .
- 4. Was adequate record keeping of events, actions Yes/No and comunications documented and logged by the Control Room staff? l
) 5. Were adequate emergency comunication systems Yes/No available in the Control Room to transmit , data and information to other emergency j response facilities? j O 1898e/18.334
Rev.' 0 5/19/88 Page 4.3-B.5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 , ATTACHMENT B (Continued) Rating Consnent s C. Activation and Response
- 1. Did the Control Room staff demonstrate the Yes/No ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
- 2. Was the person in charge in the Control Room Yes/No clearly identifiabic and was good conunand and control taken at the Control Room?
O 0 Controller / Observer Name 1898e/18.334
i
' i Rev. 0 5/19/88 Page 4.3-B.6 l 1
j VERMONT YANKEE NUCLEAR POWER STATION. EMERGENCY RESPONSE PREPAREDNESS EXERCISE .D 5 1988 , l l ATTACHMENT B <! (Continued) l II. TECHNICAL SUPPORT CENTER i 1 l ! INSTRUCTIONS [ 1 i 2 The following evaluation check list is provided to assist the ! Controllers / Observers with their evaluation of the exercise / drill. The Controllers and Observers should complete the check lists for the' location or i emergency responses which pertain to areas which you were responsible for l observing or controlling during the exercise / drill. The evaluation check list ! will utilize a rating scale based upon three (3) types of ratings followed by ( coments and suggestions as indicated below L j Rating Symbol . Comments and Suzzested Improvements f O Adequate A May be followed by coments and suggestions for improvements, especially if rating is marginal. f l Inadequate I Must be followed by comments, !
, together with suggestions for j j improvement, j
.l
- Not Observed or N No coments or suggestions l
! Not Applicable are required. !
i , If your evaluation indicates inadequate performances, please provide a ; description of the problem area and suggested solution for improvement as { f indicated on the Emergency Exercise / Drill Evaluation Form or on a separate piece of paper. t 1 Check list comences on the following page. j i
)
i l i i l 1 1898e/18.334 4 4
Rev. O S/19/88 . j
- Page 4.3-B.7 4
VERMONT YANKEE NUCLEAR POWER STATION
- i. EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 i r J- ATTACHMENT B i i 1 (Continued)
! i 4 II, TECHNICAL SUPPORT CENTER ! ! I l Rating Comments ! l A. Accident Assessment / Emergency Classification l l 1. Did the TSC staff demonstrate the ability to Yes/No i support the Control Room staff in identifying , the cause of the incident, mitigating the i consequences of that incident, and placing l
~
l the plant in a stable condition? i j
- 2. Did the TSC staff demonstrate the ability to Yes/No ,
- coordinate the assessment of plant conditions i and corrective actions with the Control Room?
l 3. Did the TSC staff demonstrate the ability to Yes/No to initiate and coordinate corrective actions in an efficient and timely manner? l i I 4
- 4. Did the TSC staff demonstrate the ability to Yes/No !
j direct and coordinate the taking of l a appropriate chemistry samples to analyze l 1 plant conditions? : ! 5. Did the TSC staff demonstrate the ability to Yes/No ! a participate with the Control Roorn and EOF /RC ] J in emergency classification and LAL l l discussion. j l 6 i B. Notification and Consnunication- i I 1 } 1. Was information flow within the TSC and to Yes/No j other appropriate emergency response l j l facilities timely, complete, and accurate? < t )
- y 1
1898c/18.334 i l i )
Rev. 0 5/19/88 - Page'4.3-B.8 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1931 ATTACHMENT B (Continued) Rating Comments , 2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the TSC staff?
- 3. Were adequate emergency coninunications systems Yes/No available in the TSC to transmit data and information to other emergency response facilities?
- 4. Was information concerning plant conditions Yes/No disseminated between the Control Room and TSC performed in a timely manner?
- 5. Were status boards utilized and maintained Yes/No to display pertinent accident information at the TSC7 C. Activation and Response
- 1. Did the TSC staff demonstrate the ability Yes/No to activate and staff the TSC7
- 2. Did the TSC staff demonstrate the ability Yes/No to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
- 3. Were initial and continuous accountability Yes/No checks of TSC and CR personnel performed?
- 4. Did the TSC Coordinator establish and Yes/No coordinate access control into the Protected Area and Control Room? ,
l 1898e/18.334 ;
)
i o
Rev. 0 5/19/88 (T Page 4.3-B.9 (sl VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 ATTACHMENT B (Continued) Rating Comments
- 5. Did the TSC Coordinator demonstrate the Yes/No ability to maintain command and control of j TSC emergency response activities?
i
- 6. Did the TSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had developed?
- 7. Was the TSC organization and initiation Yes/No of activity efficient and well organized?
d a I Controller / Observer Name: (3
, (_s/ 1898e/18.334 j
2 l i
Rev. 0 5/19/88 . q Page 4.3-B.10 O VERMONT YANKEE NUC1. EAR POWER STATION i
- EMERGENCY RESPONSE PREPAREDNESS EXERCISE j 1988 ;
i i ATTACHMENT B t ) (Continued) { ! l III. OPERATIONS SUPPORT CENTER 1 l j INSTRUCTIONS f i . l l The following evaluation check list is provided to assist the ! Controllers / Observers with their evaluation of the exercise / drill. The ! l Controllers and Observers should complete the check lists for the location or l j emergency responses which pertain to areas which you were responsible for i i observing or controlling during the exercise / drill. The evaluation check list {
- will utilize a rating scale based upon three (3) types of ratings followed by ;
coments and suggestions as indicated below: I j Ratina Symbol Coments and Suggested Improvements . l Adequate A May be followed by coments and (
- suggestions for improvements, ,
especially if rating is marginal, t
; Inadequate I Must be followed by coments, y
together with suggestions for {
- improvement.
}
] Not Observed or N No coments or suggestions ! Not Applicable are required. ] l If your evaluation indicates inadequate performances, please provio. a [ description of the problem area and suggested solution for impovement as '
- indicated on the Emergency Exercise / Drill Evaluation yorm or on a separate j i piece of paper. ;
I t J ! j Check list comences on the following page. ! I i i 4 i l j 1898e/18.334 a 1 i I
Rev. 0 5/19/88 Page 4.3-B.11 Li VERMONT YANKEE NLCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 ATTACHMENT B (Continued) l 1 III. OPERATIONS SUPPORT CENTER Rating Comments A. Notification and Communication I 1. Was information flow within the OSC and to Yes/No i other appropriate emergency response facilities timely, complete, and accurate?
- 2. Was adequate record keeping of events, actions, Yes/No and communications documented and logged by the OSC staff?
(D s- /
- 3. Were adequate emergency communications systems available in the OSC to transmit data and Yes/No information to other emergency response facilities?
- 4. Were status boards utilized and maintained to Yes/No display pertinent accident information at the OSC7 B. Activation and Response
- 1. Did the OSC staff demonstrate the ability to Yes/No activate and staff the OSc?
a
- 2. Did the OSC staff demonstrate the ability to Yes/No ,
appropriately implement Energency Plan l
- Implementing Procedures and did they follow l J them?
l
- 3. Were initial and continuous accountability Yes/No checks of OSC personnel performed? l l
l l l I 1898e/18.334 4 1 a
i Rev. 0 , 5/19/88 ; Puge 4.3-8.12 ' VERMONT YANKEE NUC1. EAR POWER STATION (
- EMERGENCY RESPONSE PPEPAREDNESS EXERCISE j 1988 4
i ATTACHMENT B l l (Continued) l } $ i ! Ratina Conenent s i i 4 Did the O!I Coordinator and OSC Coordinator's Yes/No , j Assistant demonstrate the ability to maintain i coasnand and control of OSC emergency response l activities? l I l
- 5. Did the OSC keep other emergency response Yes/No
}
facilities advised of the status of their i -I activities and'information which they had ! j developed? ! 1- 6. Was the OSC organizat! m and the initiation Yes/No f
- of activity efficient and well organized?
j 7. Did the OSC staff demonstrate the ability to Yes/No { provide adequate radiation protection ! a controls for on-site emergency response . l personnel? ! i I j 8. Did the OSC staff demonstrate the ability to Yes/No ! 4 monitor and track radiation exposure of on-site emergency response personnel? . 1 I
- 9. Did the OSC staff demonstrate the ability Yes/No f L to obtain and analyze appropriate chemistry !
samples as directed by the TSC7 l 10. Did the OSC staff demonstrate the ability Yes/No f to initiate, brief, and dispatch On-Site i Assistance Teame? ! i
- 11. Did the on-site assistance teams demonstrate Yes/No {
the ability to perform corrective maintenance l 4 on damaged plant equipment during emergency i 1 conditions? ) r ) i 1898e/18.334 l L ! l
Rev. 0 5/19/88
Page 4.3-3.13 v
VERMONT YANKEE NL' CLEAR POWER STATION , EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 ATTACHMENT B (Continued) j 12. Were on-site assistance teams able to trouble- Yes/No i shoot and evaluate problems with plant ' equipment and sys tems'.'
- 13. Were their adequate administrative controls Yes/No ;
and documentation taken to perform the necessary repairs of plant equipment and systems during an emergency situation? i s_-) i i i l I i Controller / Observer Naret f
~
1898e/18.334
Rev. 0 5/19/88 f~'j Page 4.3-B.14 V VERMONT YANKEE NU REAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1988 ATTACHMENT B (Continued) IV. EMERGENCY OPERATIONS FACILITY / RECOVERY CENTER INSTRUCTION 9 The following evaluation check list is trovided to assist the Contro11ers/00 servers with their evaluation of the exercise / drill. The Controllers and Observers should complete the check lists for the location or emergency responses which pertain to areas which you were responsible for observing or controlling during the exercise / drill. The evaluation check list will utilize a rating scale based upon three (3) types of ratings follow (d by comments and suggestions as indicated below Rating Symbol Comments and Suggested Improvements 1 () Adequate A May be followed by comments and suggestions for improvements, especially if rating is marginal. Inadeqcate I Must be followed by comments, together with suggestions for inprovement. Not Observed or N No comments or suggestions Not Applicable are required. If yout evaluation indicates inadequate performances, please provide a description of the problem ares and suggested solution for improvement as , indicated on the Emergency Exercise / Drill Evalvstion Form or on a separate piece of paper. Check list commences on the following page. 1
\~-) 1898e/18.334 ,
- _. . .. -_ . _. . .- . -. . - _ =
i f Rev. 0 : 5/19/88 Page 4.3-5.15
- VERMONT YAhTEE NUC1. EAR POWER STATIO_N ;
F.MERGENCY RESPCNSE PREPAREDNESS EXERCISE ~ 1988 ! i ! ATTACHMENT B a (Continued) l
! IV. EMERGENCY OPERATIONS FACII,ITY/ RECOVERY CENTER i 1
l Ratina Coments L l4 A. Notification and Comunication i \ j 1. Was information flow within the EOF /RC and Yes/No - ! j to other appropriate emergency response , ) facilities timely, complete, and accuratet f i t i 2. Were adequate emergency communications systems Yes/No i 4 available in the FOT/RC to transmit data and I ! information to other cmergency response f
, facilities? 6 1' l
- 3. Was adequate record keeping of events, _
Yes/No I actions, and communications documented i and logged by the EOFIRC stafff l [ ]; 4. Was information concerning plant conditions Yos/No I i disseminated between the TSC and ECF/RC f j performed in a timely mannert f a ! l 5. Wert status boards utilized and maintained Yes/No q to display pertinent accident information j at the EOF /RCf l ' B. Activation and Response f i 1. Did the EOF /RC staff demonstrate the ability Yes/No j ) to activate and staff the EOT/RCf ; 1 2. Did the EOF /RC staff demonstrate the ability Yes/No l j to appropriately implement Emergency Plan j
! Implementing Procedures and did they follow !
them? ! )- 1 1 j j 1898e/18.334 l l ! i ! i !
Dev. 0 5/19/88 Page 4.5-B.16 s i
+O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE
- 1988 ATTACHMENT _B, (Continued) 4 Rating Comments
- 3. Did the Corporate Security Force establish Yes/No access control into the EOF /RC7 4 Did the EOF Coordinator demonstrate the , , , __
Yes/No ) ability to maintain command and control of
- EOF emergency response activities?
- 5. Did the E0P/RC keep other emergency response Yes/No [
facilities advised of the status of their activities and information which they had developed?
- b. Were the EOF /RC organisation and the initiation Yes/No of activity efficient and well organized?
7
- 7. Did the Site Recovery Manager demonstrate the ___
Yes/No ability to maintain the command and control of the overall emergency response ef fort and ' organization? '
- 8. Did the Site Recovery Manager demonstrate the Yos/No ability to de-escalate from the emergency phase into the recove.y phase? ,
- 9. Were preliminary recovery plans established Yes/No !
and discussed between the Site Recovery { Manager and appropriate personnel? ! l C. Radiologieel Assessment i 1
- 1. Was information concerning radiological and Yes/No l meteorological data obtained by appropriate EOF personnel in a timely mannert
- 2. Did the EOF staff demons'. rate the ability Yes/No to perform of f-site dose assessment in accordance with Procedure OP-35137
() 189Se/18.334 1 i
Rev. 0 5/19/88 Page 4.3-B.17 (N VERMONT YANKEE NUCLEAR POWER STATION l' EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 ATTACHMENT B (Continued) ! Rating Comments
- 3. Did the EOF staff demonstrate the ability to Yes/No effectively track and define the plume utilizing the computerised dose assessment model (METPAC)?
D. Protective Action Decision-Making j 1. Did the Radiological Assistant's staff Yes/No demonstrate the ability to perform timely assessment of off-site radiologicol I' conditions to support the formulation of protective action recommendations?
- 2. Did the EOF Coordinator obtain and provide Yes/No ,
the necessary information to the Site ; tecovery Manager concerning protective action recommendations in accordance with Procedure OP-3511.
- 3. Did the Site Recovery Manager demonstrate Yes/No 1
the ability to make protective action recommendations to off-site authorities in accordance with Procedure OP-35117 1 i q
]
l l I Controller / Observer Names I . x 189Se/18.334
)
l
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _______________l
i s P Rev. O ;
- 5/19/88 i
- Page 4.3-B.18 VERMONT YANKEE NUCLEAR POWER STATION !
) EMERGENCY RESPONSE PREPAREDNESS EXERCISE i ! 1988 ] ! a ! ATTACHMENT B l (Continued) 5 g V. SITE AND OFF-S!TE MONITORING 1
l INSTRUCTIONS , i The following evaluation check list is provided to assist the ! f I i Controllers / Observers with their evaluation of the exercise / drill. The I Controllers and Observers should complete the check lists for the location or ! 1 emergency responses which pertain to areas which you were responsible for ! observing < controlling during the exercise / drill. The evaluation check list , l will utilise a rating scale based upon three (3) types of .tatings followed by l coments and suggestions as indicated below: } l' 1 Ratina Symbol Coments and Suagested Improvements l 1 e 1 Adequate A May be followed by comments and l suggestions for improvements,
. i j especially if rating is marginal.
l Inadequate I Must be followed by coments, i j together with suggestions for !
; improvement. l l
Not Observed or N No coments or suggestions Not Applicable are required. 4 j If your evaluation indicates inadequate performances, please provide a 4
! description of the problem area and suggested solution for improvement as !
J indicated on the Emergency Exercise / Drill Evaluation Form or on a separate j l piece of paper. , i 1 1 1 l 1 1898e/18.334 1 a 1
Rev. O i i 5/19/88
N Page 4.3-B.19
[b i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 ; 1 ATTACHMENT B t l (Continued) ; I l V. SITE AND OFF-SITE MONITORING 1 Rating Comments I A. Activation and Response L
- 1. Did the site and off-site monitoring teams Yes/No demonstrate the ability to transmit information over the radio utilizing proper units and terminology in accordance with Procedure OP-35107
- 2. Were site and off-site monitoring teams __
Yes/No
-' dispatched and deployed in a timely manner?
l l 3. Were team members familiar with the use of Yes/No 1 equipment, field monitoring procedures, and what was required of them?
- 4. Were off-site monitoring teams able to Yes/No l
i determine and communicate their location ; l in the field using appropriate maps and sample points (landmarks)? l l l l t l Controller / Observer Names \ l l 189Se/18.334 , l (
Rev. 0 5/19/88 Page 4.3-B.20 [/)
\s_
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 ATTACHMENT B (Continued) VI. SECURITY INSTRUCTIONS The following evaluation check list is provided to assist the Controllers / Observers with their evaluation cf the exercise / drill. The Controllers and Observers should complete the check lists for the location or emergency responses which pertain to areas which you were responsible for i d observing or controlling during the exercise / drill. The evaluation check list will utilize a rating scale based upon three (3) types of ratings followed by J comments and suggestions as indicated belows Rating Symbol Comments and Suggested Improvements i O) Adequate A May be followed by carpents awl ( suggestions for improvements, especially if rating is marginal. Inadequate i Must be followed by comments, together with suggestions for improvement. a Not Observed or N No comments or suggestions Not Applicable are required. If your evaluation indicates inadequate performances, please provide a description of the problem area and suggested solution for improvement as indicated on the Emergency Exercise / Drill Evaluation Form or on a separate piece of paper. i i l l 1 189Se/18.334 L
Rov. 0 5/19/88
, Page 4.3-B.21 VERMONT YANKEE NUCI. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE
,?. 98 6 ATTACHMENT B (Continued) l VI. SECURITY Rating Comments A, Activation and Response j 1. Did the Security staff demonstrate the ability Yes/No to perform accountability of personnel within L the Protected Area in accordance with i Procedures OF-35247 l l
- 2. Were access control points established and Yes/No maintained to control access at the site and the Protected Areat f O)
(,, 3 Did the Security staff demonstrate the ability to appropriately implen.ent Fmergency Plan Yes/No l Implementing Procedures and did they follow them? I I i ! l i l i
]
Controller / Observer Namet ; 4 189Se/18.334 l l
s i i: j Rev. 0 , 5/19/88 g Page 4.3-B.22 i l e. $s VERMONT YANKEE NUCI. EAR POWER STATION ! EMERGENCY RESPONSE PREPAREDNESS EXERCISE ! 1988 } l . ATTACHMENT P (Continued) 6 ( ' VII. NEWS MEDIA GNTER j l INSTRUCTIONS [ 4 The following evaluation check list is provided to assist the i i Controllers / Observers with their evaluation of the exercise / drill. The j i Controllers and Observers should complete the check lists for the location or j emergency responses which pertain to areas which you were responsible for l j observing or controlling during the exercise / drill. The evaluation check list !
- will utilize a rating scale based upon three (3) types of ratings followed by !
coaments and suggestions as indicated below Rating Symbol Comments and Suggested Improvements Adequate A May be followed by comments and {' suggestions for improvements. } especially if rating is marginal. f Inadequate I Must be followed by comments. , j together with suggestions for [ ] improvement. ! I I J Not Observed or N No comments or suggestions * ] Not Applicable are required. i
- If your evaluation indicates inadequato performances, please provide a j description of the problem area and sust.ested solution for improvement as i 1 indicated on the Emergency Exercise / Drill Evaluation Form or on a separate l
! piece of paper. 1 I I ! ) b 1 I i a 4 O 1 ee/1e.3>- i l
Rev. 0 5/19/88 Page 4.3-B.23 (} VERMONT YANKEE NUCI. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 l ATTACHMENT B (Continued) , i l VII. NEWS MEDIA CENTER Rating Comments A. Activation and Response
- 1. Did the News Media staff demonstrate the Yes/No ability to activate and staff the News Media Center?
I
- 2. Was information flow between the News Media Yes/No Center and EOF /RC timely, complete, and accurate?
)
- 3. Were the News Media staff familiar with their Yes/No 4 plans and procedures and do they follow them?
ll 4. Did the News Mecia staff demonstrate the Yes/No { ability to provide accurate and timely t information concerning the emergency to the public and the news media? 1 l j i l 1 i l l l l Controller / Observer Naces i 1 l 189Se/18.334 l l
R:v. 0 5/19/88 Page 4.3-C.1
-~
' h VERMONT YANKEE NUCLEAR POWER STATION
' EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988
, ATTACHMENT C Emergency Exercise / Drill Observer's Evaluation Form Observer's Nr.me Exercise / Drill Date Exercise / Drill Title Observer's Location:
Time Started: Time Ended: Observed: Player Function l
}
/
Overall Performance and Observations: (include the proper and effective use of procedures, equipment and personnel): _ I Recognized Deficiencies: ; 1 I Comments and Recommendations (Specific): I t NOTE: l Use additional pages as required. l
....................... i l
Eignature: Titles l VYOPF-3505.02
' OP-3505 Rev. 13 l Page 1 of 1 l 1898e/18.334 l
l 1 I ; ! Rev. 0 l l 5/19/88 l
' Page 4.3-C.2 i
' i VERMONT YANKEE NL' CLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l l 1988 l l l i ! i ATTACHMENT C I l (Continued) l l I I l 1
- I 1
I j , I i i [ l ; I I I I l ?
! l
! i I l ( t Continued on Additional Pages Yes No Signature
Title:
Datet 189Se/18.334 i
= . _ _ _ _ . . _ _ . . _ _ _ .- - _. . .
i i { l l 1 c I ! I t i l ! i.
! i 1 !
i i e i i 1 VERMONT YANKEE NUCLEAR POWER STATION i 1 ' j EMERGENCY RESPONSE PREPAREDNESS EXERCISE t 4 1983 I ! l
\ t
! l
- 5.0 EXERCISE SCENARIO i
1 1 i l' I i ! ! ) I t i @ 4 4 a i ! I t i } r I f i i !
\
\
1899e/12.493 1
- i. !
i I l l I '1 l i ! { l I i I i VERMONT YANKEE NL' CLEAR POWER STATION l i I ! EMERGENCY kESPONSE PREPAREDNESS EXERCISE I I 1988
- r l
5.1 INITIAL CONDITIONS , I I I i 1 l l i [ ( t 9 4 1 1899e/12.493 1
.___m,, -
Rev. 3 8/10/88 OLJ Page 5.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 5.1 INITIAL CONDITIONS (This infermation will be provided to the players at the start of the exercise). i
- 1. The Reactor is now at approximately 907. rated power. Tht. reactor has been operating steady state for the past eight months with no recent shutdowns.
- 2. Power was reduc *d for a rod sequence exchange which has been l completec.
I
- 3. The SJAE discharge release rate has been trending up for the past montn. Last SJAE discharge release rate for previous day. {
25.000 uC1/sec. The most recent sample taken (0750. yesterday) of l the Reactor Coolant System total iodine concentration was 2.0E-3 uCi/ml. 4 Drywell floor drain sump flow as of 0000 midnight was 2.0 gpm and has slowly been increasing. Drywell equipment drain sump flow as of 0000, midnight was 1.0 spm and is steady.
- 5. Shift order instructions:
- a. Closely monitor drywell leakage. Surveillance should be completed as soon as practical.
- b. Consult with the Reactor Engineering Supervisor for any control
\ rod pattern changes or reactor powe.r reductions because of suspected fuel leak.
1899e/12.493
Rev. 3 8/10/88 Page 5.1-2
- c. Power reduction rate of <1%. CTP/ minute is recommended, if necessary.
- 6. All other power generating equipment is operating, and all safety system equipment is operable.
- 7. The following on-site meteorological conditions exist at 0600: ,
Wind Speed, mph (upper / lower) 9.1/5.2 Wind Direction, degrees (upper / lover) 359/356 7 Delta Tenperature. F (upper / lower) -1.1/-0.8 ! Ambient Temperature. F 60.3 Precipitation, inches 0.0 t S. Synoptic (regional) meteorological conditions: , l () Mostly sunny with northerly winds today. High temperatures in the mid 70's, with a slight chance of some afternoon showers. ' As a strong high pressure system moves further east, strong winds . will give way to light variable conditions. i i i I i i I i O 1899e/12.493 l I i
i Rev. 3 ' 8/10/88 ! Page 5.1-3 O TABLE 5.1-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 159 inches t Reactor Pressure 992 psig I Reactor Power - APRM (average) 881 l Core Plate Differential Pressure 17.7 paid Total Core Flow 44 mil lbs/hr - Main Steam Line Flow - Total 5.6 mil 1bs/hr [
~
Main Steam Line Radiation 150 mR/hr Condenser Hotwell Level 52% ; Condenser Vacuun 2.2 inches Ng l Condensate Storage Tank Level 651 . Reactor Coolant Temperature 5k50F i Recire Drive Flow (average) 27.000 spm l Feedwater Flow 5.5 mil 1bs/hr ' Reactor Building Differential Pressure -0.75 inches Hg0 [ Dryvell Pressure 1.83 psis Drywell Temperature 1360F ; Torus Water Level 1.16 ft : Torus Temperature 880F l Drywell/ Torus 02 Concentration 2.751 l O HR Containment Monitors Containment Gas /Part Reactor Building Vent Monitors Gas /Part 2.0 R/hr 2,000/1.500 cpm 150/1.500 cpm
}
l Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr ! Steam Jet Air Ejector 140 mR/hr ! Stack Cas I/II 20/20 cpm l High Range Noble cas <0.1 mR/hr l l l l I [ l ! t I I : I l l r ! i l l l 1899e/12.493
O VERMONT YANKEE NUCI. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 5.2 NARRATIVE
SUMMARY
O 1879e/18.321
'j i L
Rev. 5 s/26/88 ! Page 5.2-1 VEMONT YANKEE l EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1984 l k i 5.2 Narrative Summarr ; i The scenario begins at 0600 with the simulator reactor running at I approximately 901 power. The reactor has been operating in a steady f state for the past eight months with no recent shutdowns. The reactor is operating at 901 power because of a rod sequence exchange and a fuel { pin leak as evidenced by elevated Steam Jet Air Ejector ($JAE) l discharge release rates. A slight increase in drywell leakage has been observed over the past few days. Shift orders have instructed the operations crew to closely monitor the drywell leakage. The operations j crew has also been advised to check with the Reactor Engineering staff I before performing any control rod pattern changes or reactor power reductions because of the suspected fuel leak.
?
At 0615, simulator control Room indications show increased drive 11 { floor drain sump leakage. An alare is received in the Control loom for i t the drywell floor drain sump. Operators checking the drywell floor [ drain sump integrators will find that the drywell leakage has increased to approulantely 6 spa. The Shitt Supervisor should declare (approminately 0630) an UNUSUAL EVENT based upon AP-3125 (C001 ANT INVENTORY) due to reactor coolant toeperature above 212'T a4 unidentified sump leakage greater than 5 spa. The Shitt Supervisor may I begin a controlled power reduction at this time. At 0745, a failure of the main turbine Mechanical Pressure Regulator ! (MPR) occurs. This causes the turbine bypass valves to open fully which rapidly increases vessel steam flow. With the high steam l outflow, the reactor vessel pressure decreases which results in a l reactor vessel water level swell. The reactor vessel water level swell l 1879e/18.321 i
\
Rev. 5 8/26/88 [m} Page 5.2-2 w/ reaches the high water level setpoint. The turbine trips on high reactor level causing the reactor to scram. The feed pumps, HPCI, and RCIC also trip. With the turbine bypass valves fully open, reactor pressure continues to decrease until low steam line pressure or high steam line flow initiates MSIV closure and Group 1 isolation. The closure of the MSIVs causes a pressure increase and attendant level shrink. Reactor low water level will initiate Group 2, 3, 4 and 5 isolation. At this time, it is postulated that additional fuel cladding perforations occur due to the pressure transient and thermal stress. The Shift Supervisor should initiate the appropriate notifications concerning the reactor scram and plant conditions. The Control Room staff will also initiate actions to stabilize the plant. This will O) include controlling pressure by cycling the relief valves or by operating the HPCI and RCIC Systems resetting the group isolations; and cloling down the plant. Plant personnel may also investigate the reason for the MPR failure. Near 0800, an area radiation monitor annunciator alarm is received in the Control Room. The containment gas / particulate monitors are indicating increased radioactivity in the drywell. By 0830, the torus catwalk area radiation monitor is alarming. The containment gas / particulate monitors are also alarming, and the contaitvaent high-range monitors arc slightly elevated. An "ALERT" should be declared (approxinstely 0900) based upon AP-3125, , (RM)l0 LOGICAL CONDITIONS) due to unexpected area radiation levels 1,000 tines normal which could require off-site impact assessment. yollowing the ALERT TSC, OSC, and E0T/RC wi?' *a t iva t e d '.'id O l staffed. Notifications should be made to tt y RC. ac t Yankee Nucloar Servicec Division.
; l 1879e/18.321 I
Rev. 5 8/26/88
/'N Page 5.2-3 b
At 1015 a significant packing leak from a valve located in the drywell occurs. A high dryvell pressure alarm is received which initiates a Primary Containment Isolation System (PCIS) of Groups 2. 3. and 4 isolation. The containment high-range radiation monitors have increased to *. 500 R/hr. Annunciator "high" area radiation monitors are also being received in the Control Room. Coincident with the high drywell pressure signal, not all of the automatic plant systems and equipment actuate. One of the RER pumps of the ECCS does not start due to a 4 kV breaker problem. One of the diesel generators also does not start due to a clogged starting air filter. A SITE AREA EMERGENCY should be declared (approximately 1030) based upon AP-3125. (FL'EL DAMAGE) due to the containment radiation monitors reading greater than 1.000 R/hr. By 1100, plant personnel will be looking for the source of the dryvell leakage. It is anticipated that personnel will be dispatched to electrically backseat valves in accordance with plant procedures. On-site assistance teams should also be requested to investigate the problems associated with the RER pump and diesel generator. Equipment mockup ot a 4 kV breaker and an electrical relay used for backseating will be available for plant personnel to work with and to perform the necessary repairs. By 1215. teams should be in the process of electrically backseating the l 1 appropriate valves. The other teams investigating the RRR pump and diesel generator will discover the problems associated with the 4 kV breaker and starting air filter, respectively. 1 By 1345, the faulty valve has been successfully backseated, and the leakage into the dryvell has been stopped. The problems associated l with the RHR pump and diesel generator have also been repaired by the ! on-site assistance teams. 1879e/18.321
I Rev. 5 ; s/26/88 Page 5.2-4 i By 1400, Control Room indications show that plant conditions are ! i stabilising, and drywell pressure and temperature are decreasing. l 1 At 1415 the exercise will be terminated. i l l I I i 1 1 I I \, O l 2 i i l 1 1879e/18.321
l VERMONT YANKEE hTCLEAR Pok'ER STATION ENERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 5.3 SCENARIO TIME LINE l i i
)
1897e/18.333 L i
-.- . - . . ._ .--~ __-- - - . - - - _ _ - -.. - -.- -
l l i O i i I i 1 I l l ' l l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 198S l 5.4 DETAILED SEQUENCE OF EVENTS I l 9 l , 1 1 l 4 I l i 1 i i i 1 1900e/23.256
Rev. 3 8/10/88 Page 5.4-1 VERMONT YANKEE hl.' CLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1988 i 5.4 DETAILED SEQUENCE OF EVENTS Clock Scenario Time Time Event /Actio3 Message Comand i Prior to 00:00 EXPECTED CONTROL R00?! (CR) ACTIONS 0600 WILL BE IMPLEMENTED BY AN EXERCISE OPERATIONS CREW (INCLUDING SUTTICIEh7 l NLH3ER OF PRESTAGED INDIVIDUALS TROM THE VERMONT YANKEE EMERGENCY l ORGAN!1ATION) LOCATED IN THE SIMULATOR COMPLEX IN THE CORPORATE TRAINING CENTER. OPERATIONAL CONTROL ROOM DATA WILL d BE PROVIDED BY THE SIMULATOR INSTRt,MENTAT!0N RESPONSES. IN CASES WHERE SPECITIC INFORMATION NOT MONITORED BY THE $1MUI.4 TOR l IS REQUIRED, IT WILL BE ISSUED BY CohTROLLERS/0BSERVERS ON MESSAGE CARDS. IN THE EVEh". THAT A SIMULATOR
, MALTt?.'CTICN CCCURS. THE EXERCISE WILL BE CONDUCTED USING INTORMATION i DEVELOPED TROM SECTION 8.0 AND l
SECTION 9.0. 1 1900e/23.256 4 l
i Rev. 3 ; 8/10/88 Page 5.4-2 !
\ I Clock Scenario Time Time Event / Action Message Command !
Prior to 00:00 The Simulator CR Controller issues SCR-M-1 SCR-C-1 0600 initial conditions to the simulator ! (Cont'd) CR pidyers. Cuidelines for use of Gaitronics and the plant I evacuation alarm are provided : to players. [ Initiating messages are also CR-M-1A provided to all emergency centers TSC-M-1 j and facility staffs upon subsequent TSC-M-2A l activations. Operational and TSC-M-2B radiological data vill be available OSC-M-1 l to the TSC via TSC comunicators EOF /RC-M-1 ! who normally respond to O the CR prestaged in the ESC-M-1 STATE-M-1 simulator. Security will be provided a list of Controllers / ; Observers and nonparticipants who l will not have to be accounted for [ during the exercise. 0600 00:00 Simulator is put into operation, f Reactor power is at 90 percent ! power. The reactor has been operating steady state for the past eight months with no recent shutdowns. I O 1,0ee<>>.2se l l l
I key. 3 j 8/10/88 i Page 5.4-3 1 . Clock Scenario i Time _ Time Event / Action Messan Conrnand i 0600 00:00 The reactor is operating at J i (Cont'd) 90 percent power because a rod , 3 j 3 sequence exchange and fuel pin leak. Elevated Steam Jet Ejector ($JAE) discharge [ release rates were provided ] , j as initial conditions. > l J Also, a slight increase in drywell SCR-M-2 f l 1eakage has been observed for the I I past few days. The dryvv11 floor i
! I drain leakage was calculated at j midnight to be at 2.0 spm and has -
slowly been increasing. I i Shift orders have instructed the r operations crew to closely monitor the dryvell leakage. } i The operations crew has also been SCR-M-3 ;' j advised to check with the Reactor ' Engineering staff before performing : any control rod pattern changes or reactor power reductions because
- of the suspected fuel leak. ;
I ; 0605 00:05 Control Room indications show increased dryvell floor drain sump leakage. l ) , 1900e/23.256 ! 1 l
Rev. 3 8/10/88 Page 5.4-4 I i Clock Scenario Time . Time Event / Action Message Conmand j 0615 00:15 The floor drain pumping alarm is ] J receivad on the Control Room panel. } Operators may wait until floor drain ;
- punp stops before implementing procedure on. "Drywell T1oor Drain Sump Surveillance." !
0620 00:20 Operators checking the drywell sep i integrators and completing the i l procedure will find that the l I j drywell floor drain leakage has l ] increased to approximately 6 gpm. j 0630 00:30 The Shift Supervisor should declare ' I an tlM;SUAL EVENT based upon the I ] 1 following EAL: AP-3125. "C001AVT
}
, thYENTORY - Reacto coolant l teeperature above 212*T and ) unidentified surp leakage greater i 1 j than 5 gpm." l I i the SS/ PED should initiate l Procedure OP-3500. Unusual Event !
; and refer to Appendix ! the !
4 SS/ PED checklist. l t I i j The plant is in 24-hour Limiting i Condition of Operation (LCO). J Operators z.ny dispatch other plant personnel (auxiliary operators or j l security force) to perform plant ! 1 1900e/23.256 I __. _ __ ._________ -__________ _ _____ _ _ _ _ _ a
i Rev. 3 8/10/88 m Page 5.4-5 Clock Scenario t Time _ _ Time Event / Action Message _ Command l 0630 00:30 inspections / tours associated with (Cent'd) the drywell leakage and other plant activities. FOR EXERCISE PURPOSEE, EARLY SCR-C-2 i IN-STATION ACTIONS WILL BE' SIMULATED l AND PERF0RMED BY CONTROLLERS. The SS/ PED may call Reactor Engineer at home ( 'mulated) to verify rate j at which power would be decreased. .: Operato.s may begin a controlled
! power reduction, a controlled i t plant shutdown, or a manual scram.
A MANUAL SCRAM WILL BE CONTROLLED AT THIS TIME. SCR-C-3 l Load Dispatcher w ll be informed of the change in reactor power. l l The SS/ PED should announce j the Unusual Event over the Plant Paging System. This activity will be performed by l ) players in the Simulator CR, and simultaneously performed j by a Controller directed evmber of the operating shift crew in the ac*ual Control Room. i 1 1900e/23.256
- 1 i
J w *.
}
b Rev. 3 8/10/88 r Page 5.4-6 e Clock Scenario Time Time Event / Action Message Command 0630 00:30 The SS/ PED should notify Vermont, (C d) New Hampshire, and Massachusetts [ t
) State Police Agencies using the Nuclear Alert System
] (orange phone) and provide the [ appropriate message to each l agency.
- The SS/ PED should notify the ,
t Security Shift Supervisor to start, l I the emergency call-in method. i 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 I Power Station of the Unusual SEC-C-1 , Event. THIS CALL WILL BE SIMULATED.
)
d The Primary and Secondary Duty ! and Call Officers (DCOs) should report to the plant after l j notification of the Unusual Event ) Status. l l 1 i The DCOs should contact the SS/ PED to be advised of the situation. () Responsibility for TSC and ! 1900e/23.256 4 w
Rev. 3 l 8/10/88 , Page 5.4-7 l
- Clock Scenario .
i ! Time Time Event / Action Message Command l 0630 00:30 EOF Coordinator assignments would. i j (Cont'd) be discussed, as appropriate. : 2 1 j The TSC Coordinator should assume f i the overall supervision and j 9 l coordination ot the on-site 4-emergency response activities, i t j This will include cscalating l the emergency classification l l as conditions warrant. ; Activation of the Technical ,
! Support Center (TSC) is optional '
) at the Unusual Event. ! v l f , 0645 00:45 IF AN UNUSUAL EVENT HAS NOT BEEN SCR-C-4 l DECLARED BY THE SS/ PED, HE WILL BE l , DIRECTED TO DO SO AT THIS TIME. I 0700 01:00 The SS/ PEP mey request RHR SCR-M-4 chemistry sample and a drywell air f ! sample be taken for shutdown cooling. I 0745 01:45 Failure of the main turbine . Mechanical Pressure Regulator (MPR)
]
occurs. This causes the turbine bypass valves to open fully which ( rapidly increases vessel steam i flow. ! 1900e/23.256 3 9
l Rev. 3 8/10/88 ;
'Page 5.4-8 O
i Clock Scanario , Time Time Event / Action Message Command r I i 0745 01:45 With the high steam outflow, the i l (Cont'd) reactor vessel pressure decreases j which results in a reactor vessel water level swell. , The reactor vessel water level f swell reaches the high water level {' setpoint. l I The turbine trips on high reactor l 1 level, causing the reactor to scram. i The feed pumps HPCI, and RCIC also l i 1 (::) l Operators will inir.iate SCRAM procedure. Reactor low water level will 1 initiate Group 2, 3, 4, and 5 isolation. At this time, l l additional fuel cladding
- perforations occur due to the i pressure transient and thermal l i stress.
i ~ 0800 02:00 The SS/ PED should initiate ! notifications concerning the reactor scram and plant conditions. 1900e/23.256 i i l 4
i Rev. 3 8/10/88 l' Page 5.4-9 l t Clock . Scenario Time Time Event / Action Message Command
- 0800 02:00 An area radiation monitor ..
(Cont'd) annunciator alarm is received on the Control Room panel. The containment gas particulate
- monitors are indicating increased ,
radioactivity in the drywell. The SS/ PED may evaluate EALs on radiological condition due to some higher radiation monitor readings and more potential fuel , perforations. 0815 0',:15 The Control Room personnel shou *i have reactor pressure under control and will be working to stabilize all plant conditions. i The SS/ PED may request additional chemistry drywell samples. i l Control Room Personnel may send OSC-M-2 l an A0 or request I&C to investigate the MPR failure. ! The SS/ PED may consider activation of TSC and OSC to l support necessary in-plant actions. l 1900e/23.256 i
,sv. 3 8/10/88 Page 5.4-10 L0 Clock > Scenario
! Time Time Event / Action Message Command l 0830 02:30 The torus catwalk area radiation i f monitor is alarming. i i The SS/ PED may evacuate the. Reactor Building. l L By this time, the gas / particulate monitors are also alarming and the containment high-range monitors are slightly elevated. l l 0845 02:45 Chemistry samples have been analyzed and indicate high drywell activity (if requested). l The torus catwalk area radiation l monitor is off-scale high. l 0900 03:00 The SS/ PED or TSC Coordinator i should declare an ALERT based upon the following EAL: AP-3125, "RADIOLOGICAL CONDITIONS - Unexpected area radiation levels 1,000 times normal which could *equire off-site impact assessment." The SS/ PED directs the operations staff to initiate Procedure OP-3501, "Alort." l 1900e/23.256 1 I l
\
s Rev. 3 k' 8/10/88 , Page 5.4-11 O Clock Scenario Time Time Event / Action Message Connand 0900 03:00 An Alert announcement should be (Cont'd) 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 (EOF /RC) should be activated and staffed. The SS/ PED should notify the Vermont, New Hampshire, and Massachusetts State Police Agencios of the escalation to the Alert emergency classification. The NRC should be notified of the escalation to the Alert. The Security Shift Supervisor should initiate the emergency es11-in method for the Alert classification. 1900e/23.256
3 i Rev. 3 8/10/88 Page 5.4-12 L. I r O > N 3 Clock Scenario i Time _ Time Event / Action Message' Command 1 l 0900 03:00 The Security Shift Supervisor (Cont'd) should' notify Yankee Nuclear Services Division (YNSD) Security , J f and activate YNSD personnel ; 1 group paging system. I 1 Upon YNSD notification, the Enginedring Support Center (ESC) is activated. t l The Security Shift Supervisor ! I should notify the New England f 1 i
< Hydro Power Station in Vernon of the escaintion to the !
Alert status. This call will be simulated. l The TSC Coordinator should , i j notify REMVEC of the Alert status ; 4 i and plant conditions. ! 1 j 0905 03:05 The Security Shif t Supervisor j should ensure that an I accountability of personnel .f has been completed in i accordance with procedures SP-0906, "Emergency Procedures" and OP-3524, "Emergency Actions to Ensure Accountability and Security Response." 1900e/23.256 1 l u- . _ . . . _ _ . _ _ _ _ . . ~ . .__ _ _ _ _ _ _ _ _ _ _ , _ . . . , _ _ _ _ _ . _ _ _ _ , _ . , _ . . . . _ _ _ _ _ . _ , . . _ _ , _ _
, .t A . Rev.I i 8/10/88, i Page 5.4-13. ;
- - Clock Scenario .
4 f ! Tiw- Time Event / Action Message- Conunand 0905 03:05 The TSC Coordinator should respond. l ] (Cont'd) activate, and staff the TSC in l j accordance with Appendix III of l 1 t 4 OP-3501. "Alert." : 1 [ 4 i
- TSC staff representing the (
i i following departments should assemble at the TSC following f the declaration of'an Alerts. t 1
- 1. Instrument and Control (
j Supervisor i i i : 4
- 2. Radiation Protection l
I Supervisor or designated l l alternate i . i
! 3. Reactor and Computer ,
l Supervisor l l i I , 4. Operations Supervisor j I l 1 l
- 5. Maintenance Supervisor q 1
I I J j
- 6. Engineering Support
! Supervisor :
i i 1 7. GE Resident Engineer
.. I j (as necessary) {
! i 1
l 1 1 I 1900e/23.256 l' i I 4 l i I 'i 1 :
Rev. 3 8/10/88 Page 5.4-14 [sL) Clock Scenario Time Time Event / Action Message Command 0905 03:05 8. Plant Services (Cont'd) Supervisor
- 9. Other staff personnel to fulfill the functions of the TSC (i.e., Status Board Keepers, Communicators.
Switchboard Operators, etc.). 0910 03:10 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 following: l
- 1. Site Recovery Manager and designated corporate staff ;
l l
- 2. EOF Coordinator j
- 3. Purchasing Supervisor i 4. Public Information liaison
- 5. Additional trained plant staff members to assume the following tag board assignments:
1900e/23.256 l
Rev. 3 8/10/88
,S Page 5.4-15 Y
Clock Scenario Time Time Event / Action Message Comrrand 0910 03:10 - EOF Coordinator's (Cont'd) Assistant
- Radiological Assistant
- Manpower and Planning Assistant Communications Assistant
- Radiological Coordinator N -
Personnel and Equipment Monitoring Team
- 6. Corporate Security Force The Operations Support Center (OSC)
Coordinator (assigned by the TSC Coordinator) should activate and staff the OSC in accordance with Appendix VII of OP-3501, "Alert." The plant staff that reports to the OSC includes the following:
- 1. Radiation Protection and Chemistry Assistants and O Technicians 1900e/23.256
I , t Rev. 4 8/26/88 ' Page 5.4-16 Clock Scenario Time Time Event / Action Message Command 0910 03:10 2. Control Instrument Specialist (Cont'd) ; i
- 3. Maintenance Staff l
- 4. Status Board Caretaker l
- 5. Other personnel as :
- required. '
l The Site Recovery Manager (SRM) j and staff should report to the ! EOF /RC and implement the 3 procedural steps listed in ,
- Appendix VIII of OP-3501 "Alert."
l Chemistry / Health Physics i Technicians from the OSC may ; be dispatched to perform dose l t rate radiation surveys, air ! ! sampling, and contamination ! i I surveys of the plant. i a i 0920 03:20 IF AN ALERT HAS NOT BEEN DECLARED SCR-C-5 ; BY THE SS/ PED, HE WILL BE DIRECTED l j TO DO SO AT THIS TIME. j i ! I The Reactor Building vent exhaust 1000 04:00 l l l monitor has been increasing and l l may be exceeding 140 mR/hr, from l ehine. 1 1900e/23.256
) -
4
Rev. 4 s 8/26/88 i Page 5.4-17 Clock Scenario Time Time Event /Actinn Message Command 1000 04:00 The SRM or TSC Coordinator may (Cont'd) declare a SITE AREA EMERGENCY based upon the following EAL: AP-3125, "FUEL DAMAGE - Reactor Building ! ventilation radiation monitor I 1 reading greater than 140 mR/hr." 1015 04:15 A significant packing leak from a valve located in the drywell occurs (simulator operator inserts casualty). , I A high drywell pressure alarm is () received which initiates a Primary Containment Isolation System (PCIS) of Groups 2. 3, and 4. The B diesel generator did not start ! as a result of the high drywell pressure signal due to a clogged starting air filter. i The containment high-range radiation monitors have increased to 1,500 R/hr. Annunciator high area radiation monitor indication in Control Room. l The D RHR pump of the ECCS did not i start as a result of the high
- drywell pressure signal due to a I
() 4 kV breaker problem. J 1900e/23.256 1
Rev. 4 8/26/88 Fase 5.4-18 O* Clock Scenario Time Time Event / Action Message Command 1015 04:15 The Control Room Personnel should OSC-M-3
- (Cont'd) have notified the TSC. The TSC ,
Coordinator should send an A0 to ] investigate the pump problem. i 1 1030 04:30 The SRM should declare a SITE AREA EMERGENCY based upon the following EAL: AP-3125. "FUEL DAMAGE - Containment radiation monitors l reading greater than 1,000 R/hr." If present, the SRM should inform 1 the State representatives of Vermont, New Hampshire, and Massachusetts located at the EOF /RC and contact each State's EOCs via the Nuclear l Alert System to inform them of L the escalation to the Site Area ; Emergency. I l The SS/ PED will also be directed to make the appropriate plant announcement concerning the escalation to the Site Area Emergency. 4 J l Upgraded notifications should also be made to YNSD and the NRC. 1 i C\ 1900e/23.256 4 1
Rev. 4 ! 8/26/88 Page 5.4-19 Clock Scenario Time Time Event / Action Message Conunand 1030 04:30 The Control Room personnel should OSC-M-4A, 4B ; (Cont'd) have notified the TSC of problems with the B diesel generator. The t TSC Coordinator should send a l maintenance person to investigate the diesel generator problem. i On-site assistance teams, under i TSC Coordinator's direction, should electrically backseat the appropriate valves in accordance with the High Drywell Pressure Procedure OT 3111. . O v 1045 04:45 IF A SITE ARC.A EMERGENCY HAS NOT EOF-C-1 l BEEN DECLARED BY THE SRM, HE WILL ; PE DIRECTED TO DO SO AT THIS TIME. i On-site assistance team reporting OSC-M-5 l to Diesel Generator Room will be I able to troubleshoot, discuss l problem, and discuss repair method I for replacement of the air filter. i L l 1105 05:05 IF NOT ALREADY DONE, THE TSC TSC-C-1 1 COORDINATOR WILL BE DIRECTED TO TSC-C-2A ( DISPATCH ON-SITE ASSISTANCE TEAMS TSC-C-28
. TO B DIESEL CENERATOR, D RHR PUMP, AND 4 KV PUMP BREAKER IN SWITCHGEAR ROOM.
1900e/23.256
Rev. 4 8/26/88 3 Page 5.4-20 l l Clock Scenario , Time Time Event / Action Message Conunand 1115 05:15 On-Site assistance team reports to OSC-M-6 Switchgear Room. Equipment mockup : of a 4 kV breaker will be available { for plant personnel to work on ! and perform the necessary rept. irs. I The ESC should be assisting at this ESC-M-1 I time in technical problem solving. ( Also, the ESC meteorologist should . be providing a specialized weather 4
; forecast. l
[ IF NOT ALREADY DONE. THE TSC
- COORDINATOR WILL BE DIRECTED TO .
t IMPLEMENT THE STEP IN HIGH DRYWELL l PRESSURE PROCEDURE CALLING FOR BACKSEATING VALVES. TSC-C-3 i i I 1130 05:30 The Control Room personnel will be l q trying to control drywell pressure. . j The packing leak will remain a function of Reactor Coolant System
- pressure until either the correct l drywell valve is backseated or
) pressure is drastically reduced. 4 I,O 1900e/23.256 1 3
Rev. 4 8/26/88 Page 5.4-21 Clock Scenario Time Time Event / Action Message Command 1200* 06:00 After replacement of air f11ter on B diesel generator and initiation of post maintenance operability test, the diesel is declared operable. 1215 06:15 The EOF Dose Assessment Personnel EOF-M-1 should be doing radiological off-site consequence assessments, based upon potential containment failure. A weather forecast is available. The on-site assistance teams should be in the process of electrically backseating the drywell valves. 1300 07:00 The ESC has reviewed the latest ESC-M-2 hVS forecast and has updated meteorological information for ' the site. An updated weather forecast is EOF-M-2 available from hNS. l
- NOTE: Due to the interactive nature of the exercise, the occurrence and i duration of the event is approximate.
I O 1900e/23.256 l
Rev. 4 8/26/88 ' Page 5.4-22 t I Clock Scenario ! Time Time Event / Action Message Consnand 1335* 07:35 The affected RHR pump has been tested and declared operable. : i REQUEST A WEATHER FORECAST EOF-C-2 ! UPDATE FROM ESC AT THIS TIME. t l 1345* 07:45 The faulty valve has been i successfully backseated and the ! I j leakage into the drywell has been stopped. ; l 1400 08:00 Control Room indications show that l 1 i plant conditions are stabilizing : I and drywell pressure and temperature are decreasing. l $ I 1415 08:15 The exercise can be terminated at ' 4 l t I this time. i l 1 I l i l I
)
- NOTE: Due to the interactive nature of the exercise, the occurrence and
- duration of the event is approximate. 1 l
l l j 1900e/23.256 l 1 1
- , . . . - - - . . ~ . - . - - - , - - - . - . . - - - . . . - - - - - - - - - - - - - - - - - . , -- , - - ~ ~ - - - - - - - - - - , ~ - - - - - - ~ - - - -
i e i ! f i I . I l l .i I ! i l l i VERMONT YANKEE N1) CLEAR POWER STATION l j EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1 1988 ! 1
' 6.0 EXERCISE MESSACES l
l l l
- O i a
l I i i 4 1 i
'l 1
l I I. O j i i I i !O 1911e/23.260 i
l t I l ^ .
/ V t i i; i
l l 1 f i t ', f ', VERMONT YANKEE NUCLEAR POWER STATION l EM?RGENCY RESPONSE PREPAREDNESS EXERCISE l i 1988 1 j 6.1 COMMAND CARDS . 1 I I I l l h I i 1 .I I 1 j j l l 1911e/23.260 1 f
I Rev. 4 - 8/26/88 Page 6.1-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO COMMAND CARD , l FROM: Simulator CR Controller COMAND NO.: SCR-C-1 i ) TO: Shift Supervisor CLOCK TIME: Prior to 0600 1 : LOCATION: Simulator Control Room SCENARIO TIi4E: O minute PARTICIPANT MESSAGE THIS IS A DRILL 1 Communications systems that are available in the Control Room have ! been duplicated in the Simulator Control Room Area EXCEPT for i Gaitronics and the plant evacuation alarm. Please use the Gaitronics/ Plant Evacuation Alarm in the liimulator 7 Control Room to complete the required PA announcements. An , j Exercise Controller will then direct a member of the shift i V operating crew at the plant to repeat the announcements from the Main Control Room. c I
- 1
(
)
) i I t I 3 i l I 4 THIS IS A DRILL i
}
} 1911e/03.260 f .I :
I 1 l I l Rev. 4 l 8/26/88 () Page 6.1-2 i ! VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO.: SCR-C-2 $ TO: Shift Supervisor CLOCK TIME: 0630 i LOCATION: Simulator control Room SCENARIO TIMEt 30 minutes t PARTICIPANT MESSAGE THIS IS A DRILL , l Early in-station actions will be simulated and information i requested at this time will be provided by controllers. l f i i l l
! l ! l ! l ! i J l' l
a l l I i 1 , I l i 1 i 4 i () THIS IS A DRILL I J 1911e/23.260 1 i
1 Rev. 4 8/26/88 Page 6.1-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO CO N VD CARD FROM: Simulator CR Controller C0ft1AND NO. SCR-C-3 TO: Shift Supervisor CLOCK TIME: 0630 or when needed LOCATION: Simulator Control Room SCENARIO TIME: 30 minutes PARTICIPANT MESSAGE THIS IS A DRILL POR EXERCISE PURPOSES, DQ,NnJ PJ.NUALLY SCRAM THE REACTOR AT THIS TIME. O O TN!S IS A DRILL 1911e/23.260
r-. i Rev. 4 8/26/88 O Page 6.1-4 i , VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY RESPCNSE PREPAREDNESS EXERCISE : 1988 , I j SCENARIO COMMAND CARD { i FROM: Security Controller __ COMMAND NO. SEC-C-1 TO: Security Supervisor CLOCK TIME: 0630 or when needed,__ LOCATION: Security Catehouse SCENARIO TIME: 30 minutes 1 l 4 PARTICIPANT MESSAGE -
- THIS IS A DRILL I I FOR EXERCISE PURPOSES, companications with New England Hydro Power ,
Station in Vernon will be simulated. ! l ' 1 , F 1 L l< l l l l i i i 4 I I 1 l
- l l
l 1 J j THIS IS A DRILL 1911e/23.260 i
j Rev. 4 8/26/88 1 O Page 6.1-5 l l , i VERMONT YANKEE NUCLEAR POWER STATION : 5 EMERGENCY RESPONSE PREPAREDNESS EXERCISE
- 1988
! SCENARIO COMMAND CARD i i f i FROM: Simulator CR Controller C0K4AND NO.! SCR-C-4 ! a TO: Shitt Supervisor CLOCK TIME: 0645 ! j LOCATION: Simulator Control Room SCENARIO TIME: 45 minutes ! i l 1 PARTICIPANT MESSAGE ! 1 THIS IS A DRILL DECLARE AN UNUSUAL EVENT BASED UPON AP-3125, C001 ANT INVENTORY, DUE : 1 TO REACTOR COOLANT TEMPERATURE ABOVE 2120F AND UNIDENTIFIED SUMP j LEAKAGE GREATER THAN 5 GPM. l t i t d I j l
\
.\ i i i i ; l 1 I i i j I i THIS IS A_ DRILL j 1911e/23.260 1 1 1 l
Rev. 4 i 8/26/88 Page 6.1-6 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 i SCENARIO COMMAND CARD FROM Simulator CR Controller COMMAND NO. SCR-C-5 TO: Shift Supervisor / Plant CLOCK TIME: 0920 ! Emeraency Director [ I LOCATION: Simulator Control Room SCENARIO TIME: 3:20 PARTICIPANT MESSAGE I THIS IS A DRILL DECLARE AN ALERT BASED UPON AP-3125, RADIOLOGICAL CONDITIONS, DUE l TO UNEXPECTED AREA RADIATION LEVELS 1,000 TIMES NORMAL WHICH COULD REQUIRE OFT-SITE IMPACT ASSESSMENT. I O i I l l l l l l l i e O THIS IS A DRILL 1911e/23.260
Rev. 4 8/26/88 Page 6.1-7 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO COPfiAND CARD FROM EOF /RC Controller COPHAND NO. I EOF-C-1 70: Site Recovery Manager CLOCK TIME: 1045 LOCATION: EOF /RC SCENARIO TIME: 04:45 PARTICIPANT MESSAGE THIS IS A DRILL DECLARE A SITE AREA EMERGENCY BASED UPON AP-3125 FUEL DAMAGE, DUE TO CONTAINMENT RADIATION MONITORS READING GREATER TRAN 1,000 R/HR. O O THIS IS A DRILL 1911e/23.260
i Rev. 4 f 8/26/88 Page 6.1-8 ( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 l SCENARIO COPMAND CARD FROM: TSC Controller COMMAND NO. TSC-C-1 TO: TSC Coordinator CLOCK TIME: 1105 LOCATION: TSC SCENARIO TIME: 05:05 PARTICIPANT MESSAGE T11S IS A DRILL -l t The B diesel generator did iso, start as a result of the high drywell pressure signal. Investigate the problem! ! t I l I i f I i i i i J l l I O THIS IS A DR!LL l 1911e/23.260
\
,_ ~ -, . . . - . . . . . ~. - -
I l 1 a Rev. A c 8/26/88 f Page 6.1-9A VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE : l 1988 l 1 l SCENARIO COMMAND CdtD
- FROMr TSC Controller COMMAND NO.
- TSC-C-1A i
j TO: TSC Coordinator CLOCK TIME: 1105 ,_, j j LOCATION: TSC SCENARIO TIME: 05:05 l
! +
- PARTICIPANT MESSAGE l THIS IS A DRILL :
j The D-RHR pump of the ECCS did not start with the high drywell ; j pressure signal. Investigate the probita! ' l l i 4 l j i a ? 1 . .i l 4 i i 4 1 i f i- L 1 ! l I i ! d i 1 ) I I. f I ! l l I l THIS IS A DRILL ; 4 l 1911e/21.260 l 1 I
l l t a Rev. 4 < 8/26/88
!' Page 6.1-9B ;
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPARE.NISS EXERCISE ' 1988 SCEN/AIO CO.*NAND CARD l FROM: TSC Controller COMMAND NO.: TSC-C-2B ' TO: TSC Coordinator CLOCK TIM 5 1105 or as necessary l r LOCATION: TSC SCENARIO TIME: 05:05 j I PARTICIPANT MISSAGE THIS IS A DRILL l l Results of visual inspection of the affected pump (D-RRR pump) ! appear normal. Investigate the 4 kV breaker in the Switchgear Room. ll 1 [ l i J ll i i l ) l
) :
l 1 : J i I i ! l i i l i :
) i i {
t i i ! J i l THIS IS A DRILL ) 1911e/23.260 i
< i N
2
- . - = . .
Rev. 4 8/26/88 l
< Page 6.1-10 j VERMONT YANKEE NUCLEAR POWER STATION LMERGENCY RESPONS1 PREPAREDNESS EXERCISE j 1988 1 r l
SCENARIO COMMAND CARD ) FROM: TSC Controller COPMAND NO.: TSC-C-3 . TO: TSC Coordinator CLOCK TIME: 1115 ) LOCATION: TSC SCENARIO TIME: 05:15 ! PARTICIPANT MESSAGE THIS IS A DRILL i i Implement Procedure 07-3111. "High Drywell Pressure " by i coordinating the electrical backseat of the appropriate valves. ' 1 1 !O J } i J i i l
- l L
.I j I i i i i 1 !
- )
i I 1 \ 4 : i i 2 i I i i THIS IS A DRILL ! 1911e/23.260 {
! i i !
i,
Rev. 4 8/26/88 Page 6.1-11 g VERMONT YANKEE NUCLEAR POWER STATION , EMERGENCY RESPONSE PREPAREDNESS EXERCISE le*8 : i i
. SCENARIO Cot 9RND CARD !
I
- TROM
- EOF /RC Controller CotetAND NO.: EOF-C-2 l 4 TO: Radiolonical Assistant CLOCK TIME: 1335 LOCATION: EOF /RA-Dose Assessment Area SCENARIO TIME: 07:35 :
W r. i PARTICIPANT MESSAGE ; 1 y THIS IS A DRILL REQUEST A WEATHER FORECAST FROM ESC AT THIS TIME. ) l i 4 l r 1 i I i 1 i i 2 1 I t f l I I i I I l ! r 2 l THIS IS A DRILL l 1911e/23.260 I 1 1
l l ! l l 1 1 I a I l I i l I ! l l l . i l 1 i VERMONT YANKEE .'iTCL5!/ POWER STATION j a . 1 I i J EMERGENCY AESPONSE PREPAREDNESS EXERCISE l i 1988 l l 6.2 MESSAGE CARDS e ! I l I I i ' i 1 i 1903e/23.259 1
Rev. 3 8/10/88 Page 6.2-1
}
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 , SCENARIO MESSAGE CARDS TROM Simulator CR Controller MESSAGE NO. SCR-M-1 To Shift Supervisor CLOCK TIME: Prior to 0600 1 l LOCATION: Simulator Control Room SCENARIO TIME: 00:00 PARTICIPANT MESSAGE THIS IS A DPILL l 4 For initial conditions, see attached pages. l I d j l ) l I i t i i j O THIS IS A DRILL
'90;c/20.159
i l Rev. 3 l 8/10/88 l p) t v Page 6.2-2 f VERMONT YANKEE hTCLEAR POWER STATION EMERCENCY RF.SPONSE PREPAREDNESS EXERCISE 1988 l l l 1 6.2 INITIAL CONDITIONS l (This information will be provided to the players at the start of the exercise).
- 1. The Reactor is now at approximately 907. rated power. The reactor has ;
been operating steady state for the past eight months with no recent 1 shutdowns. l
- 2. Power was reduced for a rod sequence exchange which has been completed.
- 3. The SJAE discharge release rate has been trending up for the past month. Last SJAF discharge release rate for previous day, l 25,000 uCi/sec. The most recent sample taken (0750, yesterday) of ,
the Reactor Coolant System total iodine concentration was 2.0E-3 uCi/ml. l
- 4. Dryvell floor drain su:rp flow a) of 0000 midnight was 2.0 gpm and has l slowly been increasing. Drywell equipment drain sump flow as of 0000, midnight was 1.0 gpm and is steady. l I
- 5. Shift order instructions: I
- a. Closely monitor dryvell leakage. Surveillance should be completed as soon as practical.
l 1 O 1903e/23.259
\
l l i
Rev. 3 I 8/10/88 (~'N; Page 6.2-3 y/
- b. Consult with the Reactor Engineering Supervisor for any control rod pattern changes or reactor power reductions, because of suspected fuel leak.
- c. Power reduction rate of (1%. CTP/ minute is recommended, if necessary.
- 6. All other power generating equipment is operating, and all safety I
system equipment is operable. , 7. The following on-site meteorological conditions exist at 0600: Wind Speed, mph (upper / lower) 9.1/5.2 Wind Direction, degrees (upper / lower) 359/356 Delta Temperature. F (upper / lower) -1.1/-0.8 ] Ambient Temperature, F 60.3 Precipitation, inches 0.0 l
- 8. Synoptic (regional) meteorological conditionst i
J Mostly sunny with northerly winds today. High temperatures in the j mid 70's, with a slight chance of some afternoon showers. As a strong high pressure system moves further east, strong winds ! will give way to light variable conditiens. t J l l l I 1 i 1903e/23.259
l l Rev. 3 8/10/88 Page 6.2-4 (] TABLE 6.2-1 l Initial Plant and Reactor System Vai.ues Reactor Vessel Coolant Level 159 inches Reactor Pressure 992 psig Reactor Power - APRM (average) 88% Core Plate Differential Pressure 17.7 psid Total Cora Flow 44 mil 1bs/br , Main Steam Line Flow - Total 5.6 mil lbs/hr Main Steam Line Radiation 150 mR/hr Condenser Hotwell Level 52% Condenser Vacuum 2.2 inches Hg Condensate Storage Tank Level 65% Reactor Coolant Temperature 5250F Recire Drive Flev (average) 27.000 gpm Feedwater Flow 5.5 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.83 psig Drywell Temperature 1360F i Torus Water Level 1.16 ft Torus Temperature 880F Drywell/ Torus 02 Concentration 2.75% l p] t HR Containment Monitors Containcent Cas/Part 2.0 R/hr 2.000/1 J00 epm Reactor Building Vent Monitors Cas/Part 150/1.500 epm Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 140 mR/hr Stack Gas I/II 20/20 epm ! High Range Noble Gas <0.1 mR/hr l l l l l i l l l I O l (v)
\
190k/23.259 j l l i l l
Rev. 3 8/10/SB QJ Page 6.2-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPON3E PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS I FROMt Control Room Controller MESSAGE NO. CR-M-1A i TO: Control Room Comunicator CLOCK TIME: Prior to 0600 4 LOCATION: Control Room SCENARIO TIME: 00:00 , PARTICIPANT MESSAGE 1 THIS IS A TRILL
! For initial conditions, see attached pages.
l j 1 .i J l 1 l 1 l l l l THIS IS A DRILL I 1903e/23.259
r j Rev. 3 a 8/10/88 Page 6.2-6 VERMONT YANKEE NUCLEAR POWER STATION l J EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 : l l 6.2 INITIAL CONDITIONS f I ! i (This information will be pro ided to the players at the start of the i t exercise). ' 4 l I
- 1. The Reactor is now at approximately 90% rated power. The reactor has l been operating steady state for the past eight months with no recent shutdowns.
i l 2. Power was reduced for a rod sequence exchange which has been i l completed. l
- 3. The SJAE discharge releasu rate has been trending up for the past [
t j month. Last SJAE discharge release rate for previous day. ! i 25,000 uci/sec. The most recent sample taken (0750. yesterday) of the neactor Coolant System total iodine concentration was i
- 2.0E-3 uCi/ml. !
I i ! 4. Drywell floor drain sump flow as of 0000 midnight was 2.0 spm and has slowly been increasing. Drywell equipment drain sump flow as of ; 0000, midnight was 1.0 spm and is steady. l j l 5. Shift order instructions ] a. Closely monitor drywell leakage. Surveillance should be completed as soon as practical. l 1903e/23.259
Rev. 3 8/10/88 p Page 6.2-/ bl
- b. Consult with the Reactor Engineering Supervisor for any control rod pattern changes or reactor power reductions, because of suspected fuel leak.
1
- c. Power reduction rate of <17.. CTP/ minute is recomended, if necessary.
l l 6. All other power generating equipment is operating, and all safety l system equipeent is operable.
- 7. The following on-site meteorological conditions exist at 0600:
Wind Speed. eph (upper / lower) 9.1/5.2 l Wind Direction, degrees (upper / lower) 359/356 Delta Temperature. F (upper / lower) -1.1/-0.S Ambient Temperature, F 60.3 i Precipitation, inches 0.0 l S. Synoptic (regional) meteorological conditions: Mostly sunny with northerly winds today. High temperatares in the mid 70's. with a slight chance of some afternoon showers. As a strong high pressure system moves further east. strong winds will give way to light variable conditions. O 1903e/23.259
Rev. 3 8/10/88 Page 6.2-8 (~']
'xm/
TABLE 6.2-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 159 inches Leactor Pressure 992 psig Reactor Power - APRM (average) 8S% Core Plate Differential Pressure 17.7 psid Total Core Flow 44 mil lbs/hr Main Steam Line Flow - Total 5.6 mil ibs/hr Main Steam Line Radiation 150 mR/hr Condenser Hotwell Level 52% Condenser Vacuum 2.2 inches Hg Condensate Storage Tank Level 65% Reactor Coolant Temperature 5250F Recire Drive Flow (average) 27.000 gpm i Feedwater Flow 5.5 mil lbs/hr ' Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.83 psig Drywell Temperature 1360F Torus Water Level 1.16 ft Torus Temperature 880F Drywell/ Torus 02 Concentration 2.75% J -\ HR Containment Monitors 2.0 R/hr j Containment Cas/Part 2.000/1.500 cpm
; Reactor Building Vent Monitors Cas/Part 150/1.500 epm i Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 140 mR/hr Stack Cas I/II 20/20 cpm High Range Noble Gas <0.1 mR/hr i
I i, l i 1903e/23.259
1 1 4 Rev. 3 .
~'
8/10/88 ! Page 6.2-9 , l(a} VERMONT YANKEE NUCLEAR POWER STATION '
- EMERGENCY RESPONSE PREPAREDNESS EXERCISE ,
j 1988 , 9 SCENARIO MESSAGE CARDS i FROM: TSC Controller MESSAGE NO.: TSC-M-1 ; TO: TSC Coordinator CLOCK TIME: Upon TSC Activation j LOCATION: TSC SCENARIO TIME: PARTICIPANT MESSAGE i THIS IS A DRILL I For initial conditions, see attached pages. I i ( ; 1 , .i i 1 ) / l a (_% / . i 1 l
- e l
I i l l i i i l l i i i l i I (") s-' THIS IS A DRILL 1903e/23.259
Rev. 3 8/10/88 Page 6.2-10 V VERMONT YANKEE NUCLEAR POWER STATION E.V RGENCY RESPONSF. PREPAREDNESS EXERCISE 1988 6.2 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The Reactor is now at approximately 907. rated power. The reactor has been operating steady state for the past eight months with no recent shutdowns.
l
- 2. Power was reduced for a rod sequence exchange which has been l completed.
j 3. The SJAE uischarge release rate has been trending up for the past month. Last SJAE discharge release rate f or previous day, l l 25,000 uCi/sec. The most recent sample taken (0750, yesterday) of the Reactor Coolant System total iodine concentration was 2.0E-3 uCi/ml. 4 Dryvell floor drain sump flow as of 0000 midnight was 2.0 spm and has slowly been increasing. Drywell equipment drain sump flow as of 0000, midnight was 1.0 spm and is steady.
- 5. Shift order instructions:
- a. Closely monitor dryvell leakage. Surveillance should be completed as soon as practical.
O 1903e/23.259 l l l I a
Rev. 3 8/10/SS
,O Page 6.2-11 N.]
l b. Consult with the Reactor Engineering Supervisor for any control l rod pattern changes or reactor power reductions, because of suspected fuel leak.
- c. Fower reduction rate of <11. CTP/ minute is recommended, if l necessary.
- 6. All other power generating equipment is operating, and all safety system equipment is operable.
- 7. The following on-site meteorological conditions exist at 0600:
Wind Speed, mph (upper / lower) 9.1/5.2 Wind Direction, degrees (upper / lower) 359/356 l Delta Temperature. F (upper / lower) -1.1/-0.S f Ambient Temperature, #F 60.3 d Precipitation, inches 0.0
- 8. Synoptic (regional) meteorological conditions: i Mostly sunny with northerly winds today. High temperatures in the mid 70's, with a slight chance of some afternoon showers.
As a strong high pressure system moves further east, strong winds will gi.ve way to light variable conditions. l l l 1903e/23.259
Rev. 3 8/10/88 () Page 6.2-12 () TABLE 6.2-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 159 inches Reactor Pressure 992 psig Reactor Power - APRM (average) 88% Core Plate Differential Pressure 17.7 psid Total Core Flow 44 mil lbs/hr Main Steam Line Flow - Total 5.6 mil 1bs/hr Main Steam Line Radiation 150 mR/hr Condenser Hotwell Level 52% Condenser Vacuum 2.2 inches Hg Condensate Storage Tank Level 65% Reactor Coolant Temperature 5250F l Recire Drive Flow (average) 27.000 gpm Feedwater Flow 5.5 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.83 psig Drywell Temperature 1360F Torus Water Level 1.16 ft Torus Temperature 880F l f ~s Drywell/ Torus 02 Concentration 2.75% HR Containment Monitors 2.0 R/hr (' ') l Containment Cas/Part 2.000/1.500 cpm l Reactor Building Vent Monitors Cas/Part 150/1,500 epm Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 140 mR/hr Stack Gas I/II 20/20 cpm l High Range Noble cas <0.1 mR/hr I n k_,) 1903e/23.259
I Rev. 3 8/10/88 Page 6.2-13 O VERMONT YANKEE NL' CLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 i SCENARIO MESSAGE CARDS 1 1 TROMt TSC Controller MESSAGE NO. TSC-M-2A l Tot TSC Coordinator CLOCK TIME Upon Assianment of
! Data Recorder LOCATION: TSC SCENARIO TIMEt PARTICIPANT MESSAGE (
l r 4 THIS !$ A DRILL l l l To obtain plant computer parameters that are normally available to TSC staff, use the Controller / Observer telephone in the Plant Computer Room to request i the information from the Simulator Computer Room. ! I l f t ]L I i 1 1 1 1
; i i
l i l ( i i i !
\
1 !
) i l
4 THIS IS A DRILL 1903e/23.259 i . l l
i Rev. 3 8/10/88 ; Page 6.2-14 VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 : SCENARIO MESSACE CARDS i 1 FROM: TSC Controller MESSAGE NO. TSC-M-2B Tot TSC Coordinator CLOCK TIMEt Upon Assignment of Comunica tors I LOCATION: TSC SCENARIO TIME 1 2 FARTICIPANT MESSAGE l }
- THIS IS A DRILL l After assigning your TSC Communicators to the Control Room, the prestaged TSC !
] Comunicators at the Simulator Control Room will be made available. ; 1 , i l i I i
?
4 1 a i ; 1 ; I l 2 l THIS IS A DRILL 1903e/23.259 1
Rev. 3 , 8/10/88 Page 6.2-15 l l VERMONT YANKEE NUCLEAR PO'a*ER STATION ; EMERGENCY RESPONSE PREPAREDNISS EXERCISE ' ) 1988 i SCENARIO MESSAGE CARDS ; TROM: OSC Controller MESSAGE NO. OSC-M-1 i TO: OSC Coordinator CLOCK TIME: Upon OSC Activation ; LOCATION: OSC SCENARIO TIME: PARTICIPANT MESSAGE . i THIS IS A DRILL l ! I )) For initial conditions, see attached pages. l i 4 s 1 r ( .
' f, e
i - I J l ) i ) l I j i
; i i
l t l i i THIS IS A DRILL J 1 j ! 1 1903e/23.259 ! i i
Rev. 3 8/10/88 Page 6.2-16 VERMONT YANKEE hTCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 1 1988 1 i 1 6.2 INITIAL CONDITIONS [ i (this information will be provided to the players at the start of the [ exercise). , 1
- 1. The Reactor is now at approximately 90% rated power. The reseter has been operating steady state for the past eight months with no recent [
shutdowns. ,
- 2. Power was reduced for a rod sequence exchange which has been
) j l completed. j 3. The SJAE discharge release rate has been trending up for the past i i month. Last SJAE discharge release rate for previous day, j 25,000 uCi/sec. The most recent sample taken (0750, yesterday) of ; l the Reactor Coolant System total iodine concentration was l
; L
- 2.0E-3 uCi/ml.
I I I 4 Dryvell floor drain sump flow as of 0000 midnight was 2.0 spm and has slowly been increasing. Drywell equipment drain sump flow as of l 0000, midnight was 1.0 gpm and is steady. I
- 5. Shift order instructions:
1 ] a. Closely monitor drywell leakage. Surveillance should be completed as soon as practical. 1 i l 1903e/23.259 j T d
Rev. 3 8/10/88 () Page 6.2-17 Consult with the Reactor Engineering Supervisor f or any control b. rod pattern changet. or reactor power reductions, because of suspected fuel leak. I J
- c. Power reduction rate of <1%. CTP/ minute is recommended, if l necessary.
1
; 6. All other power generating equipment is operating, and all safety 3
system equipment is operable. 9 i 7 The following on-site meteorological conditions exist at 0600: 1 r Wind Speed, mph (upper / lower) 9.1/5.2 I Wind Direction, degrees (upper / lower) 359/356 i Celta Temperature. F (upper / lower) -1.1/-0.8 I Ambient Temperature. F 60.3 j Precipitation, inches 0.0 S. Synoptic (regional) meteorological conditionst .I i i Mostly sunny with northerly winds today. High temperatures in the mid 70's. with a slight chance of some afternoon showers. ; As a strong high pressure system moves further east, strong winds , will give way to light variable conditions. f i i I i i l l; [ d
- 1903e/23.259 4 I
l l Rev. 3 8/10/85 Page 6.2-16 l () (~'/ TABLE 6.2-1 Initial Plant and Reactor System Values i l l Reactor Vessel Coolant Level 159 inches Reactor Pressure 992 psig Reactor Power - APRM (average) 89% Core Plate Differential Pressure 17.7 psid Total Core Flow 44 mil lbs/hr Main Steam Line Flow - Total 5.6 mil lbs/hr Main Steam Line Radiation 150 mR/hr Condenser Hotwell Level 52% Condenser Vacuum 2.2 inches Hg Condensate Storage Tank Level 65% Reactor Coolant Temperature 5250F Rectre Drive Flow (average) 27.000 gpm Feedwater Flow 5.5 mil 1bs/hr Reactor Building Differential Pressure -0.75 inches H 2O Drywell Pressure 1.83 psig Drywell Temperature 1360F Torus Water Level 1.16 ft Torus Tcmperature 8 SOT Drysell/ Torus 02 Concentration 2.75% O HR Containment Monitors Containment Gas /Part Reactor Building Vent Monitors Cas/Part 2.0 R/hr 2.000/1.500 cpm 150/1.500 epm l j Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 140 mR/hr Stack Gas I/II 20/20 cpm High Range Noble Gas (0.1 mR/hr l l l l C (, 1903e/23.259 i I
I I Rev. 3 I l 8/10/88 g Page 6.2-19 {/ s_. VERMONT YANKEE NUCLEAR PO'4ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ; 1988 l { l SCENARIO MESSACE CARDS i FROM E0T/RC Controller MESSAGE NO. EOF /RC-M-1 ! { TO: Site Recovery Manager / CLOCK TIME Upon Activation [ ! EOF Coordinator l i LOCATION: EOF /RC SCENARIO TIME: l i i l PARTICIPANT MESSAGE l l 1 THIS IS A CRILL I l For initial conditions, see attached pages. I t I r l i i t i i ! I i THIS IS A DRILL 1903e/23.259 l
~ ~ - ~. - _ _ ~ . . . . . _ _ _____ -_ _ _ _ - _
i
l Rev. 3 8/10/SS Page 6.2-20 VERMONT YANKEE NL' CLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1983 1 { 6.2 INIT!AL CONDITIONS 1 (This information will be provided to the players at the start of the exercise). ;
- 1. The Reactor is now at approximately 907. rated power. The reactor has been operating steady state for the past eight months with no recent shutdowns.
2 Power was reduced for a rod sequence exchange which has been i completed. I
- 3. The SJAE discharge release rate has been trending up for the past I month. Last SJAE discharge release rate for previous day. l 25.000 utilsec. The most recent sample taken (0750, yesterday) of the Reactor Coolant System total iodine concentration was 2.CE-3 uCi/ml.
4 Drysell floor drain sump flow as of 00-00 midnight was 2.0 spm and has i slowly been increasing. Drywell equipment drain sump flow as of ; 0000, midnight was 1.0 spm and is steady.
- 5. Shift order instructions
- a. Closely monitor drywell leakage. Surveillance should be completed as soon as practical.
O 1903e/23.259 i
l Rev. 3 l 8/10/88 ! Page 6.2-21
- b. Consult dth '.he Reactor Engineering Supervisor for any control rod pattern changes or reactor power reductions because of ;
suspected fuel leak,
- c. Power reduction rate of <1%. CTP/ minute is recorcended, if necessary. l l !
- 6. All other power generating equipment is operating, and all safety l
system equipment is operable. l
- 7. The following on-site meteorol:gical conditions exist at 0600:
Wind Speed. mph (upper / lower) 9.1/5.2 i Wind Direction, degrees (upper / lower) 359/356 l Delta Temperature. F (upper / lower) -1.1/-0.8 ! Ambient Temperature. T 60.3 Precipitation, inches 0.0
- 8. Synoptic (regional) meteorological conditions:
Mostly sunny with northerly winds today. High temperatures in the mid 70's with a slight chance of some aftornoon showers. As a strong high pressure system moves further east, strong winds ' will give way to light variable conditions. [ i l l l 1903e/23.259 l
i Rev. 3 8/10/88 0 TABLE 6.2-1 Page 6.2-22 Initial Plant and Reactor System Values ! l Reactor Vessel Coolant Level 159 inches Reactor Pressure $92 psig Reactor Pcwer - APRM laverage) 85% Core Plate Differential Pressure 17.7 psid Total Core T1ow 44 mil lbs/hr , Main Steam Line Tlev - Total 5.6 mil 1bs/hr
- Main Steam Line Radiation 150 mR/hr
] Condenser Hotwell Level 52% J Condenser Vacuum 2.2 inches Hg 4 Condensate Storage Tank Level 65%
- Reactor Coolant Temperature 5250T ,
i Recite Drive Flow (average) 27,000 gpm l Teedwater Flow 5.5 mil lbs/hr Reactor Building Differential Pressure -0.75 inches Mgo i Drywell Pressure 1.83 psig l l Drywell Temperature 1360T , i Torus Water Level 1.16 ft Torus Temperature S$0F ; { 1 Drywell/ Torus 02 concentration 2.75% i 1 . HR Containment Monitors 2.0 R/ht i Containment Gas /Part 2,000/1,500 epm Reactor Building Vent Monitors Gas / Fart 150/1,500 cpm i Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr i Steam Jet Air Ejector 140 mR/hr ; j Stack Gas I/II 20/20 epm i High Range Noble Gas <0.1 el/hr i I. l i a .I c i i l n [ i i f 1903e/23.259 : l 1 i i i
. _ _ _ ._____. _ _ - . - _ - _ - - - _ . _ _ -- - ~_ - _ _
I ! L
- Rev. 3 ;
' 8/10/SS ; Page 6.2-23 j l i , i VERMONT YANKEE Ntl CLEAR PO'4ER STATION ! ! EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 4 1988 l I l i , ECENARIO MESSAGE CARDS t t ESC Centro 11er MESSAGE NO. ESC-M-1 l l TROMt i
- l. To ESC Direct.or CLOCK TIMIt tlpon Activatten ;
i LOCATION: indneering Support Center St;ENARIO TIME: _,_ l PARTICIPANT MESSAGE f I 1' i THIS IS A CR!!d
! For initial conditions, see attached pages. l I
1 i I 1 l i l f ) i l l l l l i i l l i THIS IS A DRILL 1903e/23.059
4 r Rev. 3 i 8/10/88 j Page 6.2-24 VERMONT-YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 4 1988 6.2 INITIAL CONDITIONS (This information will be provided to the players at the start of the' t exerciae).
- 1. The Reactor is now at approximately 90% rated power. 'The reactor has I been operating steady state for the past eight months with no recent shutdowns. ,
- 2. Power was reduced for a rod sequence exchange which has been completed i
- 3. The SJAE discharge release rate has been trending up for the past month. Last SJAE discharge release rate for previous day, !
1 25,000 uC1/sec. The most recent sample taken (0750, yesterday) of j the Reactor Coolant System total iodine concentration was i 2.0E-3 uCi/ml. .i
, 4. Drywell floor drain sump flow as of 0000 midnight was 2.0 gpm and has <
slowly been increasing. Drywell equipment drain sump flow as of ;
.r j 0000, midnight was 1.0 gpm and is steady. ;
- 5. Sh!.ft order instructions l i !'
1
- a. Closely monitor drywell leakage. Surveillance should be '
I completed as soon as practical. !, ? ,1 l 1903e/23.259 , I i i
Rev. 3 8/10/88 [s) w/ Page 6.2-25
- b. Consult with the Reactor Engineering Supervisor for any control rod pattern changes or reactor power reductions, because of suspected fuel leak,
- c. Power reduction rate of (1%. CTP/ minute is recommended, if necessary.
- 6. All other power generating equipment is operating, and all safety system equipment is operable.
- 7. The following on-site meteorological conditions exist at 0600:
Wind Speed, mph (upper / lower) 9.1/5.2 Wind Direction, degrees (upper / lower) 359/356 Delta Temperature, F (upper / lower) -1.1/-0.8 s Ambient Temperature, F 60.3 A Precipitation, inches 0.0
- 8. Synoptic (regional) meteorological conditions:
Mostly sunny with northerly winds today. High temperatures in the mid 70's, with a slight chance of some afternoon showers. l As a strong high pressure system moves further east, strong winds I will give way to light variable conditions. l l i i A 1903e/23.259 l
)
r Rev. 3 8/10/88 Page 6.2-26 9 O TABLE 6.2-1 i Initial Plant and Reactor System Values i Reactor Vessel Coolant Level 159 inches Reactor Pressure 992 psig Reactor Power - APRM (average) 88% Core, Plate Differential Pressure 17.7 paid Total Core Flow 44 mil lbs/hr Main Steam Line Flow - Total 5.6 mil 1bs/hr I Main Steam Line Radiation 150 mR/hr Condinser Hotwell Level 52% Condenser Vacuum 2.2 inches Hg
- Condensate Storage Tank Level 65%
j Reactor Coolant Temperature 5250F Recire Drive r' low (average) 27,000 gpm Feedwater Flow 5.5 mil lbs/hr l i Reactor Building Differential Pressure -0.75 inches'H 2O Drywell Pressure 1.83 psig q Drywell Temperature 1360F i
, Torus Water Level 1.16 ft l Torus Temperature '880F !
Drywell/ Torus 02 Concentce' on 2.75% HR Containment Monitors 2.0 R/hr Containment Gas /Part 2,000/1,500 cpm Reactor Building Vent Monitors Gas /Part 150/1,500 cpm ! Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 140 mR/hr Stack Gas I/II 20/20 cpm High Range Noble Gas <0.1 mR/hr I l I o i l 1 l J l
- 1 i 1903e/23.259 s
1 __ --- ., ,, , --. . . . _ .., , ~ . __,. --- . ... .,_.._ _. _ .. . - . . . _ _ _ _ . . _ _ _ _ - . . _ _ , . - . . _ . _ . - - - . _ _ , . _ ,
Rev. 3 8/10/88 Page 6.2-27 [O~') VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS FROM: E0F State Observer MESSAGE NO.: STATE-M-; TO: 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. O O l l l l l l i I l /N THIS IS A DRILL N ,) l l 1903e/23.259
Rev. 3 8/10/88 (} Page 6.2-28 V VERMONT YANKEE NL' CLEAR POWER STATION EMEhGENCY RESPONSE PREPAREDNESS EXERCISE 1988 6.2 INITIAL CONDITIONS (This information will be previded to the players at the start of the exercise).
- 1. The Reactor is now at apptoximately 90% rated power. The reactor has been operating steady state for the past eight months with no recent shutdowns. ,
- 2. Power was reduced for a :od sequence exchange which has been
-~ co=pleted.
v
- 3. The SJAE discharge release rate has been trending up for the past month. Last SJAE discharge release rate for previous day, 25,000 uCi/sec. The most recent sample taken (0750, yesterday) of the Reactor Coolant System total iodine concentration was 2.0E-3 uCi/ml.
I i I
- 4. Drywell floor drain sump flow as of 0000 midnight was 2.0 gpm and has slowly been increasing. Drywell equipment drain sump flow as of 0000, midnight was 1.0 gpm and is steady. l l
- 5. Shift order instructions:
- a. Closely monitor drywell leakage. Surveillance should be completed as soon as practical.
1 l 1903e/23.259 l a
Rev. 3 8/10/88 ,x Page 6.2-29 , n L)
- b. Consult with the Reactor Engineering Supervisor for any control rod pattern changes or reactor power reductions, because of suspected fuel leak.
- c. Power reduction rate of (1%. CTP/ minute is recommended, if necessary.
- 6. \11 other power generating equipment is operating, and all safety system equipment is operable.
- 7. The following on-site meteorological conditions exist at 0600:
Wind Speed, mph (upper / lower) 9.1/5.2 Wind Direction, degrees (upper / lower) 359/356 Delta Temperature, #F (upper / lower) -1.1/-0.8 Ambient Temperature, F 60.3
/~N
() Precipitation, inches 0.0 S. Synoptic (regional) ceteorological conditions: Mostly sunny with northerly winds today. High temperatures in the mid 70's, with a slight chance of some af ternoon showers. As a strong high pressure system moves further east, strong winds l will give way to light variable conditions. j i l I I I l I /T ! U 1903e/23.259 i I
Rev. 3 8/10/88 ( Q ,)I Page 6.2-30 TABLE 6.2-1 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 159 inches Reactor Pressure 992 psig Reactor Power - APRM (average) 88?. Core Plate Differential Pressure 17.7 psid Total Core Flow 44 mil lbs/hr Main Steam Line Flow - Total 5.6 mil lbs/hr Main Steam Line Radiation 150 mR/hr Condenser Hotwell Level 52% Condenser Vacuum 2.2 inches Hg Concensate Storage Tank Level 65% Reactor Coolant Temperature 5'50F 2 Recire Drive Flow (average) 27,000 gpm Feedwater Flow 5.5 mil lbs/hr Reactor Building Differential Pressure -0.75 inches H 2O D'ywell Pressure 1.83 psig T.ywell Temperature 1360F Torus Water Level 1.16 ft Torus Temperature 8SOF y- 3 Drywell/ Torus 02 Concentration 2.75% (
) HR Containment Monitors 2.0 R/hr Containment Gas /Part 2,000/1,500 cpm Reactor Building Vent Monitors Gas /Part 150/1,500 epm Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 140 mR/hr Stack Gas I/II 20/20 cpm High Range Noble Gas <0.1 mR/hr i
l 1903e/23.259 1
h/88
) Page 6.2-31 (J
\ VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS , FROM: Simulator Controller MESSAGE NO.: SCR-M-2 T0: Operator CLOCK TIME: Completion of Initial Briefing LOCATION: Simulator Control Room SCENARIO TIME: Prior to 0600 PARTICIPANT MESSAGE THIS IS A DRILL For initial drywell leakage conditions, see attached pages. O l I l l l l l 1 l l O THIS IS A DRILL 1903e/23.259
l Rev. 3
8/10/88 ,
Page 6.2-32 ATTACHMENT 1 DATE;
,Cf.YWEL L FLOOR CG AIN 9R P SURVEI <. L ANCE t 0800 - 1600 1600 - 2400 (000 - 0900 TIE INTECFATOR TIM INTEGRATOP 1DC INTECRATOR t r
Current _ Previous Cnanm com Rate gyn , , _ nom CRYWELL ECCIPENT CRAIN SJM) SRVEILLANCE i I i 0800 - 1600 1600 2400 0000 - 0800 TIE INTEW ATOR TIW INTEGATOR TIE IN1Em ATOR Current Previous 1 Chancy 3 Rate / gyn M gyn i RO I - 3S I ACTIONS: i
- l. Notify the Shift Supervisor of leakt ge from 31ther sump increases by 2 i
gpm above normal in any 8 hour period. Shift Supervisor take action ' i to determine cause.
< 2. Initiate an orderly shutdown ard be in tha cold shutdown condition within 24 hours if either of the following occure Drywell floor drain leakage excecos 5gpm.
a.
- b. Total drywell sump leakage exceeds 25 gpr..
q VYOPF 4152.05 OP 4152 Re , 15 Page 1 of 1
i b' Rev.- 3 , 8/10/88 Page 6.2-33 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE. PREPAREDNESS EXERCISE ~ 1988 SCENARIO MESSAGE CARDE i FROM: Simulator CR Controller MESSAGE NO : SCR-il-3 70: Shift Supervisor CLOCK Tn4E: Prior to 0600
- LOCATION
- Simulator ,
SCENARIO TIME: 00:00
- l PARTICIPANT MESSAGE j THIS IS A DRILL Please be advised that Reactor Engineering is concerned with fuel integrity.
They suspect a fuel leak. The operation crews have been requested to notify l Reactor Engineering before performing any control rod pattern changes or reactor power reductions.
- l, i
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d . ! i i I ! i L r 4 I
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d 1 i () THIS IS A DRILL 1903e/23.259 1
Rev. 4 8/26/88 Page 6.2-34 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS FROM: Simulator CR Controller lESSAGE NO.: SCR-M-4 TO: SS/ Plant Emergency Director CLOCK TIME: Upon Request of Chemistry Air Sample Approximately 0700 LOCATION: Simulator Control Room __ SCENARIO TIME: 1:00 PARTICIPANT MESSAGE THIS IS A DRILL A routine RCS chemistry sample and a RER System chemistry sample can be taken and a gross analysis completed in approximately one hour and two hours, respectively. O THIS IS A DRILL 1903e/23.259
1 P Rev. 4 7-s 8/26/88 ( ) Page 6.2-35 N/ VERIONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS FROM: OSC Team Controller ._ MESSAGE NO. OSC-M-2 TO: A0 or I&C Investigatina . ,, CLOCK TIME: 0815 or as needed MPR Failure LOCATION: Turbine Buildina SCENARIO TIME: 02:15 , PARTICIPANT MESSAGE i THIS IS A DRILL ! l The technician performing troubleshooting o Physical verificacion of the front standard reveals that the rotating bushing is not moving. o Actual research of spare parts for a replacement is expected. o All paper work should be completed, not simulated! l () THIS IS A DRILL 1903e/23.259 i
Rev. 4 8/26/88 i Page 6.2-36 j VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ; 1988 l SCENARIO MESSAGE CARDS i FROM: OSC Team Controller MESSAGE NO.: OSC-M-3 TO: A0 or On-Site Assistance Team CLOCK TIME: 1015 or as needed ' LOCATION: RHR Pump Corner Room SCENARIO TIME: 04:15 PARTICIPANT MESSAGE THIS IS A DRILL l The A0 checks / inspects the affected RHR pump. Nothing unusual is observed. l . 1 i O ' i l 3 j i l 1 l
. i l I I
i l l THIS IS A DRILL O l
- 1903e/23.259 l l
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!I Rev. 4 8/26/88 Page 6.2-37A VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS i
FROM: OSC Team Controller MESSAGE NO.: OSC-M-4A ; i TO: A0 or On-Site Assistance Team CLOCK TIME: 1030 LOCATION: Diesel Generator Room SCENARIO TIME: 04:30 PARTICIPANT MESSAGE THIS IS A DRILL i ! The diesel generator is turning over very slowly. i A ! t l , I d i l ) i i 1 I i i THIS IS A DRILL 2 I 1903e/23.259 .) 1 1
-_, - - - . - - - - - , _ , . - - - , , . . - - . _ . - . . , , , , _ . - . - _ , , . . , , . _ , _ . _ _ , , , . , ~ . , _ . _ _ . - - , - . . , . - - . . . - . - _ . . , - - _ , . , . . - . - .
Rev. 4 8/26/88 Page 6.2-375 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS T FROM: OSC Team Controller MESSAGE NO.: OSC-M-4B TO: A0 or Mechanic CLOCK TIME: 1030 LOCATION: Diesel Generator Room SCENARIO TIME: 04: 30 PARTICIPANT MESSAGE THIS IS A DRILL Visual inspection of diesel generator as observed. NOTE: Differential pressure of 120 pounds of the P1-3-1B gauge monitoring I Dallinger air filter. O L l l l l I 1 l l l l l O THIS IS A DRILL 1903e/23.259 i
Rev. 4 8/26/88 f) v Page 6.2-38 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS FROM: OSC Team Controller MESSAGE NO.: OSC-M-5 TO: On-Site Assistance Team CLOCK TIME: 1045 or as Needed LOCATION: Diesel Generator Room SCENARIO TIME: 04:45 PARTICIPANT MESSAGE 4 THIS IS A DRILL l i Get the appropriate tools from your shop and parts from stores, etc. Discuss the repair effort with Controller. ) 4 THIS IS A DRILL 4 V 1903e/23.259 1 t
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Rev. 4 , 8/26/88 Page 6.2-39 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS l FROM: OSC Team Controller MESSAGE NO.; OSC-M-6 TO: On-Site Assistance Team CLOCK TIME: 1115 (DRHR Pump) LOCATION: Switchaear Room SCENARIO TIME: 05:15 PARTICIPANT MESSAGE THIS IS A DRILL The breaker repair team: o Use 4 kV magna blast breaker, located in the southeast corner, marked: "FOR TRAINING ONLY." The breal.er will be plugged into the breaker test source. o Troubleshoot and report findings. THIS IS A DRILL 1903e/23.259
Rev. 4 8/26/88 () VERMONT YANKEE NUCLEAR POWER STATION Page 6.2-40 F.MERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS FROM: ESC Controller MESSAGE NO. ESC-M-1 TO: ESC Meteorolonist CLOCK TIME: 1115 or As Requested LOCATION: ESC Yankee Atomic Electric Co. SCENARIO TIME: 05:15 PARTICIPANT MESSAGE THIS IS A DRILL For the data form, see attached page. O t l 1 ( THIS IS A DRILL 1903e/23.259 __._.___.a
Rev. 4 8/26/88 ( ), Page 6.2-41 WEATHER FORECAST FOR SITE: VERMONT YANKEE Date of Forecast: Time of Forecast: 1000 Current Site Meteorology (as of 0930 ): Delta-Wind Speed Wind Direction Temperature Stability Precipitation I Lower 10.7 mph 360 _ des from -1.8 0F A 0.00 in/15 mip i Upper 14.6 mph 3 deg from -2.2 0F C Forecast Site Meteorology: Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation A. 1000- Lower 9 mph 360 deg from -- CF , A 0.00in/15 min 1100 Upper 14 mph 360 deg from -- 0F C B. 1100- Lower 9 mph 360 __deg from -- 0F _, A 0.00in/15 min , 1200 Upper 14 mph 360 deg from -- 0F __ C C. 1200- Lower 7 mph 25 deg from -- 0F __, A 0.011n/15 min 1300 Upper 10 mph 25 deg from -- 0F C National Weather Service Forecast for site region: Mostly sunny with northerly winds today. High temperatures in the mid 70's, with a slight chance for an afternoon shower. As a strong high pressure moves further east, otrong winds will give way to light variable conditions. i Special Weather Statements: 2 Winds predominantly from the north. Very unstable conditions due to thermal buoyancy close to surface. Ground level release will be well mixed. Elevated i releases may be fumigated down to ground. Chance for an afternoon light shower. i i i .I 1903e/23.259 I l
i Rev. 4 8/26/88 ' Page 6.2-42 ()N
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VERMONT YANKEE NUCLEAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS FROM: EOF /RA Controller MESSAGE NO.: EOF-M-1 - TO: Radioloalcal Assistant CLOCK TIME: As Requested (Approximately 1215) ; i LOCATION: EOF / Dose Assessment Ares SCENARIO TIME: 06:15 l 4 PARTICIPANT MESSAGE l THIS IS A DRILL , 1 06:00-12:00 - General Area Forecast i Mostly sunny with northerly winds today. High temperatures in the mid 70's, i with a slight chance for an afternoon shower. l As a strong high prcssure moves further east, strong winds will give way to ' O light variable conditions. o I i t i i ' i I J l 1 , I l I THIS IS A DRILL ! (} 1903e/23.259 { d 4 l 4 {
Rev. 4 8/26/88 Page 6.2-43 ( VERMONT YANKEE NUCLEAR POWER STATION . EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 l I , SCENARIO MESSAGE CARDS
, TROM: ESC Controller MESSAGE NO.: ESC-M-2 TO: ESC Meteoroloalst CLOCK TIME: 1300 or As Requested
, I LOCATION: ESC Yankee Atomic Electric Co. SCENARIO TIME: 07:00 j 1 i j PARTICIPANT MESSAGE 1 THIS IS A DRILL , i For the data form, see attached page. I i I 4 1 4 f i ! a I 1 l l .i I THIS IS A DRILL ( l 1903e/23.259 1 1 1 i i
I Rev. 4 8/26/88 Page 6.2-44 WEATHER FORECAST FOR SITEt VERMONT YANKEE ! Date of Forecast ! Time of Forecastt 1200 l Current Site Meteorology (as of _ 1130 ): 1 Delta-Wind Speed Wind Direction Temperature Stability Precipitation l j Lower 7.0 mph _ 7 deg from -2.1 0F A 0.00 in/15 min ' Upper 8.8 mph 9 deg from -2.4 0F C ] Forecast Site Meteorology: 4 Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation A. 1200 Lower 7 mph 20 deg from - CF A 0.011n/15 min , 1300 Upper 9 mph 20 deg from - 0F A B. 1300 Lower 7 mph 25 deg from - 0F A 0.011n/15 min 1400 Upper 9 mph 25 des from - 0F A C. 1400 Lower 7 mph 25 deg from - 0F A 0.011n/15 min , 1500 Upper 9 mph 25 des from - 0F A I ) National Weather Service Forecast for site regions a Mostly sunny with northerly winds today. High temperatures in the mid 70's, with a slight chance for an af ternoon shower. As a strong high pressure moves further east, strong winds will give way to light variable conditions. l 4 Special Weather Statements: Winds shifting towards NNE, strong incoming solar radiation resulting in very } unstable conditions near surface. Chance for a liaht shower. 1 3 , i 1 l 5 1903e/23.259 4 l 1 i ,
Rev. 4 8/26/88 Page 6.2-45 a VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 SCENARIO MESSAGE CARDS FROM: EOF /RA controller MESSAGE NO. EOF-M-2 To: Radioloaical Assistant CLOCK TIME: As Requested (Approximately 1300) LOCATION: EOF / Dose Assessment Area SCENARIO TIME: 07:00 i PARTICIPANT MESSAGE j THIS IS A DRILL 12:00-18:00 - Ceneral Area Forecast , Mostly clear this afternoon and tonight. Low temperature this evening in the high 50's, winds northerly 5-10 mph. Tomorrow sunny, clear, high near 80. ; O I I t 1 ! i l I, t 1 i THIS IS A DRILL 1 1903e/23.259 b
O VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 4 1 7.0 STATION EVENT DATA i l J i
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I 1 I 1 , 1894e/20.592 l l
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- VERMONT YANKEE NUCLEAR POWER STATION r I
l EMERGENCY RESPONSE PREFAREDNESS EXERCISE a. I 1988
, i ! i I !
7.1 EVENTS SUM 1ARY l 4 t i i 1 e I l l .
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- O 1894e/20.592 4
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Rev. 3 8/26/88 :
/ Page 7.1-1 b
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 7.1 EVENTS
SUMMARY
i The following information and supplementary traterial are provided for those observers 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 perfom repair, rescue, or other activities, will take certain actions in response to the scenario. The controller / observer must be cognizant of the actions of those players to which assignment is given and provide - information regarding the results of the players actions as ; appropriate. The information provided in this section does not preclude [ the possibility that the observer will be required to provide additional information to the players. L Approximate Miniscenario Time Event Location 7.2.1 0745 Plant Damage Assessment Turbine Bldg. o Mechanical Pressure 1 Regulator (MPR) Failure i i 1.2.2 1015 High Dryvell Pressure Reactor Bldg. 5 Control Lower Level o Electrically Backseat i Drywell Valves J
- 7.2.3 1015 Plant Damage Assessment RHR Pump j o RER Pump Inspection Corner Room j and Breaker Repair and 4 kV l Switchgear Room i
- 1894e/20.592 i .
Rev. 3 8/26/88 Page 7.1-2 1 t 7.1 EVENTS SW91ARY (Cont'd) i Approximate j Miniscenario Time Event 14eation ; i 7.2.4 1015 Plant Damage Assessment Diesel Room l f o Diesel Generator B l Investigation i o i i i l i l I l l l O 1894e/20.592 i I i l l
-% - -.9M9F'MW w y
- . - . _ - - - - - - ~ - _ . - . . . . . . . . ~ . . - . . . . . . .
i 2 4 I !o t } t 9 i VERMONT YANKEE NUCLEAR /0WER STATION EMERGENCY RESPONSE PREFAREDNESS EXERCISE 1988 i li; 7.2 EVENT MINISCENARIOS l 1 1 O I l ] 1 i 1 l I l 1 i O 1895e/20.593
Rev. 3 8/26/88 () Page 7.2.1-1 VERMONT YANKEE NUCI. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 7.2.1 Miniscenario - Mechanical Pressure Reaulator (MPR) Failure I. General Description I The MPR fails downscale causing all of the bypass valves to rasp open. 3 Reactor pressure drops, level swells and trips the feed pumps, HPCI, l RCIC, and the turbine, resulting in a reactor scram. II. Descriptions of Player Responses / Observations / Corrective Actions > 1' The Con:tol Room may send an A0 or request I&C to investigate the 1 l problem with the MPR. The MPR valve is located in the Turbine Building () on the main turbine frcnt standard. The technicians will perform troubleshootir.g research to narrow down potential causes and make recommendations to department supervisors. If actual physical verification of the front standard is performed and the rotating bushing is inspected. it will be found to be not moving.
- i The technicians will then have to research spare parts for a replacement .
and perform the repairs (refer to Messake Card OSC-M-2). III. 7 gent _ Closeout : i l After the technicians diagnose the problem, replace the rotating bushing j and appropriate surveillance has been completed along with all paperwork ' has been completed Control Room personnel wil t then be able to operate the turbine. l i j NOTE: If an investigation is initiated prior to TSC or OSC activation, a controller will simulate action in Message Card OSC-M-2. I 1895e/20.593 l
Rev. 3 (* 8/26/88 ! Page 7.2.2-1 ( l l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE i 7.2.2 Miniscenario - Electrically Backseat Drywell Valves (OT 3111) l I j I. General Description At approximately LO15, significant packing leakage occurs. A high drywell pressure alarm is received, ins a result of the high dryvell ! j pressure signal. An automatic actuation signal fails to start the , l affected RHR Pump and Emergency Diesel Generator B. The high drywell pressure will also cause primary containment isolation of Groups II, f , III, and IV. The drywell pressure response is indicative of a loss of ! coolant inside of primary containment. l l II. Descriptions of Player Responses / Observations / Corrective Actions i < Upon receipt of the high drywell pressure signal, Control Room penonnel will verify the validity and implement the appropriate procedures
- including OT 3111. "High Drywell Pressure." Step 7 of *,he follow-up i actions will require Control Room personnel, via the TSC/OSC, to have a !
] team of ma ktenance elettrician. <iirpatched to electrically backseat the , l valves listed. Due to the increased area radiation level in the Reactor 5 t I
; Building, a C/HP technician may be dispatched to ascertain radiological I conditions in the areas of the MCCs that house the breakers for the l valves specified in Step 7.
i l a. It is expected that the OSC team will enter the Reactor Building via ! the north Reactor Building entrance. The team will not actually
; electrically backseat the valves outlinedt however, they should go to all the appropriate breaker locations and verbally describe all '
{ ; the actions that would be required to accomplish the requirements of l OT 3111. I 1895e/20.593 l
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i i 1 Rev. 3 - 8/26/88 ' ( Page 7.2.2-2 l b. In addition, opposite MCC 89A, the limitorque test stand will be set i up and functional. The repair team will demonstrate how they would j electrically backseat the valve in an emergency situation. ! 1
- c. Once the OSC team has completed the backseating, the simulator I
- operator will stop the drywell leakage in containment.
l I!!. Event Closeout l
; i j When the OSC tear tas backseated all the valves required and the simul? tor oper- e has stopped the leak, Control Room personnel will see l drywell pressure, temperatures, and possibly radiation 2,evels begin to '
' rend downward.
] l l The OSC observer she ald notify the 0$0 facility controller when the () leaking valve, determined by the controller, has been backseated. ' 1 I l 1 f \ > J i I 5 i i i l I r i ! } : i l ( )
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1895e/20.593 I l
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Rev. 3 8/26/88 (Lj ) Page 7.2.3-1 VERMONT YASTEE N1101. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 7.2.3 Miniscenario - RHR Pump Inspection and Breaker Repair I. General Description Upon receipt of the high drywell pressure signal, Control Room operators receive indication that the RRR pump has tripped (panel alarm and amber l breaker light on the RHR pump). Any attempts to restart the affected l pump are unsuccessful. II. Descriptions of Player Responses / Observations / Corrective Actions Since the simulator control panel shows indication that the RHR pump has l m I ) tripped, an OSC team will probably be requested to investigate the RHR
~
pump breaker located in the 4 kV Switchgear Room. In addition, an A0 may be dispatched to the affected RER pump Corner Room to perform a l visual inspection of the affected pump. Since there are elevated radiation levels in the Reactor Building, a C/HP technician may be dispatched with the /.0.
- a. When the A0 reaches the RHR pump Corner Room to perform a visual !
inspection, he finds nothing out of the ordinary (refer to Message i Card OSC-M-3) and will report his findings to the OSC. l l
- b. When the breaser repair teaa. inspects the RBR pump breaker in the Switchgear Room, they will encounter the 4 kV magn. blast breaker, '
located in the southeast corner, marked "FOR TRAINING ONLY." The ! breaker will be plugged into the breaker test source, its closing springs discharged, and its spring charging motor internally i disabled. The breaker repair team will troubleshoot the charging ' f) U circuit and report their findings (refer to Message Card OSC-M-6). 1895e/20.593 1 I J
Rev. 3 8/26/88 Page 7.2.3-2 The team will probably be directed to obtain the needed parts from stores and effect the needed repairs. Approximately 1335, the MC ceam should haver repaired the failed motor and concluded that the RER pump breaker has been repaired. III. Event Closecut When the TSC is infortmed of the completion of the repairs on the RHR pump breaker, they will relay this information to the Control Room. Operators in the Control Room may decide to start the RER pump without further incident relative to the breaker closing circuit. The OSC observer should notify the OSC facility controller as soon as practical after the pump breaker has been repaired. O \ t
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Rev. 3 8/26/88 O Page 7.2.4-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 7.2.4 Miniscenario - Diesel Generator B Investination - l i ! I. General Description 1 , ) 4 When the drywell high pressure signal is received Control Room operators receive indications that the B diesel generator failed to e* art as it should have. Any subsequent attempts to start the diesel r i
- will be unsuccessful. , j II. b eriptions of Player Resp--ses/ Observations / Corrective Actions i
t The Control Room may request (via the OSC and/or TSC) that en A0 or i electrician be dispatched to tne B Diesel Room to investigate the cause ] of the failure to start. ; i [
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! a. In addition to a visual inspection, the investiga*.or may be requested to attempt to start the diesel locally. If at any time, f
j he perfotas an action that would normally initiate a diesel start. { j he will be made aware that there seems to be no source of starting j air (refer to Message Card OSC-M-4A and 45). 4
- b. When the A0 reports his findings, which is a differential pressure j of 120 pounds of the Pl.3-1B gauge monitoring the Dollinger air j j filter, o taan of maintenance mechenics may be dispatched to the B Diesel Room. They will ascertain the cause of the failure to
] j start is a clogged filter in the air start line (refer to W ssage Card OSC-M-5). The mechanics will have to get the appropriate tools from their shop and parts from stores, etc. and complete ahe repair effort. 'O 1895e/20.593 a
I Rev. 3 :
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Page 7.2.4-2 g i 1 III. Event Closeout
- Af ter the mechanics fix the filter and report it, the simu*.ator operator !
- t
. will remove the malfunction and make the B diesel operable. Control !
l Room personnel will then be able to operate that diesel, j l - The OSC observer should notify the OSC facility controller as soon as i pructical after the filter has been fixed. i i , j k i I ! t a c i l 1 : 1 l i l I a i l i i i ! i l 4 4 l l 1 1 l 1895e/20.593 i i
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i VERMONT YANKEE NUCLEAR POWER STATION ! EMERGENCY RESPONSE PREPAREDNESS EXERCISE ! 1988 l f I I 8.0 OPERATIONAL DATA l l i b ' i
- NOTE: The operational data is highly Jependent on operator actions i taken in response to the conditions presented within the j j
} scenario. The data reflects plant condit!ons assuming !'
certain basic operator response actions be!ng taken. The operational data was taken from the plant slaulator. i l e i i j i I 4 i 1 !,o l i
i r n Vit40NT TANtit NUCLEAR POWit STAflON tev. 3 EMttCt%CY tisPCNst PitPAttDNtst ExttCist 8/26/88 1988 Page 8.0 1 8.0 OPitafl0NAL DATA scenario flee (hrsmin) 00:00 00:15 00:30 00:Cl 01:00 01:15 01:30 01:45 02:00 Clock flee (hrsmin) 06:00 06:15 06:30 06:45 07:00 07:15 07:30 07:45 08:00 a item Panel Inst 10 Description Units 1 I 1 93 FT 23 108 1 MPCI Flow kepm 0 0 0 0 0 0 0 0 0 i 2 9 .'t F1 10 139A RMR A Flow kg;sa 0 0 0 0 0 0 6 6 6 ] 3 93 F1 10 1398 RMt O Flow kgpa 0 0 0 0 0 0 0 0 0 i i 4 93 Fl.10 50A Cs A Flow kape 0 0 0 0 0 0 0 0 0 [ j 5 93 F1 10 500 Cs E Flow kepm 0 0 0 0 0 0 0 0 0 i pela 6 93 PI 161912A/S Drywlt Pressure il 15 15 15 15 15 15 15 15 , l 7 94 F1 13 91 ACic Flow sm 0 0 0 0 0 0 0 0 0 l ) 8 94 Fl*12 141A+8 adCU Flow opt 120 120 120 120 120 120 120 120 120 !
- 1 94 CW Equip s e p sui get * ;9 29 29 59 59 59 59 59 l 10 94 DW Floor sep sun get
- 32 32 65 65 98 98 65 65 l 11 94 2 165A/B Ra coolant Two deg 7 525 525 525 520 515 515 510 515 545 i 12 94 2 3 92A Recire A crive Flow kepm 27 27 25.5 21 17 14 11.5 7 7.5 13 94 2 3 928 Rectre B Drive Flow ag;n
( i 27 27 25.5 21 17 14 11.5 7 7.5 ' 14 95 7 46A APRM/ltM A 1 88 88 80 70 60 55 50 44 0 l i 15 95 7 468 APRM/ltm B 1 88 88 80 70 60 55 50 44 0 16 95 7 4tc APLM/leM C 1 88 88 80 70 60 55 50 44 0 f ! 17 95 7 460 APRM/ttM 0 4 88 88 80 70 60 55 50 44 0 18 95 7 468 APAM/lRM E 1 88 88 l 80 70 60 55 50 44 0 j 19 95 7 46F A iM/Itm F % 88 88 to 70 60 55 50 44 0 ; 1 20 95 7 434 se t A cps 3.4t+05 3.4t+05 3.4t+05 2.M+05 1.0t+05 1.0t+05 8.0t+04 7.M+04 1.2t+01 i d 21 b5 7 438 seM a eps 3.4t*05 3.4t+05 3.4t+C5 2.0E+05 1.M+05 1.0t+05 8.0t+04 7.0E*04 1.2t+01 I i 22 95 7 43C sem C cps 3.4t+05 3.4t+05 3.4t+05 2.M+05 1.M+05 1.M+05 8.0t+04 7.0t+04 1.2t+01 ( ] 23 95 7 430 sum o eps 3.4t+05 3.4t+05 3.4t+05 2.0t+05 1.0t+05 1.0t+05 8.0t+04 7.M+04 1.2t+01 ; a 24 95 6 3 95 Core Flow alb/hr 44 44 41.5 34 28 25 22 18 5 f 1 25 95 6 3 95 Core DP paid 17.7 17.7 16.6 12.3 9.4 8 6.9 6.5 3.3 t j 26 9-5 F1 3 310 CR0 Flow one 47 47 47 47 47 47 47 47 24 !
- 27 95 CR Position in/out out out out out out out out out in f
28 95 6 96 Feedwater Flow alb/hr 5.5 5.5 5 4.4 3.8 3.4 2.9 2.6 0 ! 29 95 6 96 marrow tange Lent inches 159 159 159 160 1H 160 160 160 181 l 30 95 6 97 Main steam FLN s!b/hr 5.6 5.6 5.1 4.5 3.9 3.5 3 2.6 0 ; 31 95 6 97 Wide tange Press. pois 990 990 990 988 982 980 978 976 1000 :
- 32 95 6 98 Wide tones Levet inches 150 150 151 152 152 152 152 152 173 l
- 33 95 6 98 barrow nonee Press, pois 992 992 980 972 962 956 950 950 1010 j 34 96 LI 107 5 Csf Level % 65 65 65 63 63 63 63 63 63
)
s 35 96 Lt 111 1 Motwett Levet u 1 53 53 57 60 60 60 60 60 64 26 96 Lt.111 2 Motwell Leset s 1 51 51 55 58 58 58 58 58 62
} 37 97 PI 101 M condenser vacuun in up 2.2 2.* 2.2 2.1 2.8 2.8 3 3.2 12 3'
38 98 D/G A Skr Light gr/ red green gre . green green green green green g . en V een 39 .8 , 0/G 8 Skr Lleht gr/ red ge m v een grm er m tr e green te m gi *n grm 40 9 25 Tis 16 19 46 Torus Toep, des F 88 88 88 M 88 48 89 89 90 41 9 25 41 46A/8 Torus Levet feet 1.16 1.16 1.16 1.16 1.16 1.16 1.15 1.15 0.97 ] 42 9 25 14 16 19 44 Terus Pressure pale 13.7 13.7 13.7 13.7 13.7 13.7 13.7 13.7 13.7 43 9 25 f t 1619 44 Orywlt Pressure pela 16 16 16 16 16 16 16 16 16 44 9 25 PR 1 156 3 Dw/ focus OP paid 1.83 1.83 1.83 1.83 1.83 1.83 1.79 1.79 1.79 45 9 25 f t 1619 45 Drywll Tesp. deg F 134 134 136 136 1M 136 134 136 154 , 46 b 25 PR 1 156 3 Orywll Pressure psig 1.83 1.83 1.83 1.83 1.83 1.83 1.8 1.8 1.8 ) 47 9 26 PI 1125 34/s em Blde DP in 90 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.75 0.7 1 48 926 F1 1 125 1A+B SGTs Flow cfm 0 0 0 0 0 0 0 0 2900 j 49 CAD DV/ focus 02 Conc. t 2.75 2.75 2.75 2.75 2.75 2.75 2.75 2.75 2.88 ] 1
- Legend Os downscale UP toscate PTL palt to lock l
}
- Yatue will be provided at the start of the esercise.
1 l a 1
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t i i 4 ' I vitse0MT TANKit NUCLEAR POWER STAfl0M Rev. 3 ) EMtnGENCT RESPONSE PetPAAEDNtss Extacist 8/26/88 , l } 1988 Page 8.0 2 1 I 8.0 CPIRATIONAL DAfA (Cont'd) f scenerlo Time (hrsmin) 02415 02:30 02:45 03:00 03:15 03:30 03:45 04:00 j Clock Time thr: min) 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 Ites Penet Inst 10 Description Units , ..................................................................................................................... .. l i a f l 1 93 FT.23 108 1 MPCI Flow kapa 4.2
- 4.2 4.2 4.2 4.2 4.2 0 ~0 l 1 2 93 Fl.10 1394 ana A Flow kape 6 6 6 6 6 6 6 6 !
3 93 71 10 139s aMe e Flow kepm 0 0 0 6 6 6 6 4 ( 4 9*3 F1 10 504 CS A Flow kapa 0 0 0 0 0 0 0 0 , f 5 93 F1 10 50s Cs a Flev kapa 0 0 0 0 0 0 0 0 f 6 93 Pl.16 19 12A/s Drywett Pressure pela 15 15 f 15 il 15 15 15 15 l' 1 7 94 F1 13 91 acic Flow spa 0 0 440 400 400 400 400 400 ) . 8 94 Ft.12 141A+B kWCU Flow spa 120 130 130 130 130 130 130 130 f 9 94 DW Equip.sw p sun set 59 59 59 59 59 59 59 59 e 10 94 DW Floor sump Sei gal 45 65 65 65 65 65 65 65 j 11 94 2 1654/B Ra Cootent Temp des F 535 520 500 480 440 430 400 425 i i 12 94 2 3 92A sectre A Crive Flow kapa 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 1 13 94 2 3 92: Recirc's Drive Flow kape - 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 ! 4 14 95 7 46A APaM/IRM A 1 0 0 0 0 0 0 0 0 ! ! 15 95 7 46s APaM/leM B 1 0 0 0 0 0 0 0 0 ! i 16 95 7 46C APam/ am C 1 0 0 0 0 0 0 0 0 l
] 17 95 7 460 ApaM/InM 0 1 0 0 0 0 0 0 0 0 I 18 95 7 46E APem/ lam E 1 0 0 0 0 0 0 0 0 ,
19 95 7 467 APam/laN 7 1 0 0 0 0 0 0 0 0 j , 20 95 7 434 stM A cps 5.0t+00 4.0t+00 4.0t+00 4.0t+00 4.0t+00 4.0t+00 4.0t+00 4.0t+00 i i 21 95 7 435 SAM 8 cps 5.0t+00 4.0t+00 4.0t+00 4.0t+00 4.0t+00 4.M+00 4.0t+00 4.0t+00 ! ] 22 95 7 43C stM C cps 5.0t+00 4.0t+00 4.0t+00 4.0t+00 4.0t+00 4.M+00 4.M*00 4.0t+00 23 95 7 430 SAM 0 cps ( 5.0t+00 4.0t+00 4.0t+00 4.0E+00 4.0t+00 4.0t+00 4.0t+00 4.0t+00 i i 24 95 6 3 95 Core Flow alb/hr 6 6 6 5.5 5.5 5.5 5.5 5.5 t i 13 95 6 3 95 Core DP paid 3.3 3.3 3.3 3.4 3.4 3.3 3.3 3.3 ~l } 26 95 71 3 310 CtD Flow spa 49 49 50 50 50 50 50 50 ' ] 27 95 Ca Position In/out in in in in in in in in ! q 48 95 6 96 feedseter Flow alb/hr 0 0 0 0 0 0 0 0 j 29 95 6 96 Marrow tonee Levet Inches l 157 15 7 152 161 163 in 1M 166 l l 30 95 6 97 Main steen Flow alb/hr 0 0 0 0 0 0 0 0 !' 31 95 6 97 Wide sense Press. pels 980 860 700 580 480 355 350 32 95 6 98 340 l Wide tonee Levet Irwhos 150 150 155 155 157 158 170 164 i j 33 9-5 6 98 marrow aanse Press, pois 952 Os DS 08 Os es 0s Os J 34 96 t!.107 5 Csf Level 1 63 63 63 62 62 60 60 60 l
- 35 96 LI 111 1 Witwelt Levet u 1 60 60 60 58 58 60 64 60 26 96 t!.111 2 setwett Levet S X 62 62 62 57 f
57 58 53 53 l j 37 97 Pl.101 29 Condenser vac u n in #g 17 22 23 27 27.5 28 24 29 l 38 98 D/G A Skr Light er/ red green green steen green green green green green l 39 98 0/G B Bhr Light l er/ red steen treen green green green ereen green green l ! l 40 9 25 7Is 16 19 48 f orua Temp. des F 94 97 94 101 104 105 105 104 j $ 41 9 25 LI 464/5 Torus Levet feet 0.94 1 1.03 1.M 1.00 1.11 1.42 1.39 i 42 9 25 T4 16 19 44 Terus Pressure pale 14 to 14 14 14.2 14.5 16 17 ! 43 9 25 ft.16 19 44 Drywell Pressure pela 16 16 16 16 16 16 , 18 19 44 9 25 PR 1 156 3 DW/ Torus OP paid 1.79 1.M 1.79 1.79 1.79 1.79 1.79 1.M i 4? 9 25 f t 1619 45 Orywett Temp. des 7 135 135 135 135 133 132 133 133 ) 46 9 25 PR 1 156 3 Drywell Pressure pels 1.8 1.8 1.8 1.8 1.8 1.8 1.8 1.8 , J 47 9 26 Pl.1 125 3A/s ta stes 2P in M20 0.7 t 0.7 0.7 0.7 0.7 0.7 0.7 j 48 9 26 71 1 125 1A+B SGTS Flow cfm 2900 kwo 2900 2900 2900- 2900 2900 2900 49 CAD OW/ Torus 02 cone. 1 2.88 2.M 2.88 2.M 2.88 2.98 2.59 2.5 i i Legends Os downscete UP watste PTL pull to Lock 1 l l.
YttMONI Yhdh WUCLEAR POWit STAfl0N tev. 3 EMERGEhCY ttS A '( PitPAtt04tl$ EXERCISE 8/26/88
!444 Page 8.0 3 8.0 CPERATIONAL DATA (Cont'd) !
Scenerlo Time (hrsmin) 04:15 04:30 04:45 05:00 05:15 05:30 05:45 06:00 06:15 Clock Time (brialn) 10:15 10:30 10:45 11:00 11:15 11:30 11:45 12:00 12:15 ; Item Panet Inst 10 Description Units i 1 93 FT 23 108 1 WPCI Flow kapa 0 0 0 0 0 0 0 0 0 {, 2 93 71 10 139A RNt A Flow kepa 6 6 6 6 6 6 6 6 6 3 93 71 10 139s RNR 8 Flow kepe 6 6 6 6 6 6 6 6 6 4 93 F1 10 50A C$ A Flow kgpe PTL PTL PTL PTL PfL PIL PIL PTL PIL 5 93 Ft.10 508 CS S Flow kepe PfL PTL PTL PTL Pil PfL PTL PfL PfL , f 6 93 PI 16 19 12A/B Dr m tt Pressure pois 20 21 21 21 21 21 21 21 21 g' 7 94 F1 13 91 Pcic Flow spe 400 400 400 400 400 400 400 400 400 ; 8 94 F1 12 141A+8 RWCU Flow spe 1?0 130 130 130 130 130 130 130 130 9 94 DW Egulp sg sua gat 59 59 59 59 59 59 59 59 59 10 94 DW Floor Su'p Sun. sat 65 65 65 65 65 65 65 65 65 11 94 2 165A/$ ta Cootant forp des F 430 420 410 400 390 380 370 360 350 l 12 94 2 3 92A tecirc A Orive Flow kope 0 0 0 0 0 0 0 0 0 1 13 94 2 3 92s tectre B Drive Flos kape 0 0 0 0 0 0 0 0 0 i 14 95 7 46A APRM/lRM A 1 0 0 0 0 0 0 0 0 0 15 95 7 468 APRM/IRM 8 1 0 0 0 0 0 0 0 0 0 16 95 7 46C APRM/ItM C 1 0 0 0 0 0 0 0 0 0 L , 17 95 7 460 APRM/lRM l' 1 0 0 0 0 0 0 0 0 0 18 95 7 461 APaM/IRM E 1 0 0 0 0 0 0 0 0 0 19 95 7 46F APRM/ItM F 1 0 0 0 0 0 0 0 0 0 20 95 7 43A Stw A cps 4.0000 4.0t+00 4.0000 4.0D00 4.0t+00 4.0D00 4.0D00 4.Ct+00 4.0!*00 21 95 7 438 stN B cps 4.0E+00 4.0t+00 4.0t+00 4.M+00 4.0t+00 4.0D00 4.0t+00 4.0t+00 4.0t+00 22 95 7 43C StM C cps 4.0t+00 4.00 00 4.0t+00 4.0D 00 4.0t+00 4.0t+00 4.CE+00 4 Ct+00 4.0t+00 23 95 7 430 seM 0 cps 4.0E+00 4.0000 4.0t+00 4.0D00 4.000C 4.0t+00 4.0E+00 4.0D00 4.0t*00 24 95 6 3 95 Core Flow alb/hr 0 0 0 0 0 0 0 0 0 25 95 6 3 95 Core DP paid 0.6 0.6 0.6 0.6 0.6 0.6 0.6 0.6 0.6 I 26 95 ft.3 310 CAD TLow spo 0 0 0 0 0 0 0 0 0 27 95 CR Position In/out in in in in in in in in in ' 23 95 6 96 Feedwater flow alb/hr 0 0 0 0 0 0 0 0 0 29 95 6 96 barrow Range Levet inches 185 178 165 167 163 161 161 161 161 i 30 95 6 97 hein steen Flow mLb/hr 0 0 0 0 0 0 0 0 0 ! 31 95 6 97 Wid,tanee Pre +s. pois 355 325 290 260 235 210 190 ' L5 150 32 95 6 93 Wide Range Levet inches 165 163 161 159 157 155 155 155 155 33 95 6 98 Warrow Range Press. pelg 05 08 05 05 05 05 05 08 05 34 96 Lt*107 5 Csf Levet 1 60 60 60 60 60 60 60 60 60 35 96 LI 111*1 Notwett Levet N 1 60 60 60 60 60 60 60 60 60 26 96 LI 111 2 Notwett Levet 5 1 53 53 53 53 53 52 52 52 52 i 37 97 PI 101 29 Condenser vacuJe in Ng 29 30 30 30 30 30 30 30 30 , 33 98, 0/G A Skr Light gr/ red green green green ar m grm green green gran prem l 39 98 D/G B Ikr Light gr/ red red red red red red red red green green 40 9 25 TIS 16 19 48 Torus Toep. des F 104 106 107 109 til 111 110 110 109 41 9 25 LI 46A/S forus Levet feet 1,43 1.47 1.49 1.53 1.54 1.53 1.52 1.51 1.5 I 42 9 25 ft 16 19 44 Tocus Pressure pale 18.5 19 19 19 19.2 19.2 19.2 19.2 19.0 43 9 25 ft 16 19 44 Dry w lt Pressure paio 21.5 22 22 22 22.2 22.2 22.2 22.4 22.4 44 9 25 PR 1 156 3 DV/ Torus OP psid 2.25 2.3 2.35 2.34 2.38 2.38 ?.38 2.38 2 . ',8 45 9 25 1t 16 19 45 Drywett Teep. des F 200 203 205 205 206 204 206 206 206 46 9 25 pt 1 156 3 s.,wett Pressure pais UP UP UP UP UP UP UP UP UP 47 9 26 PI 1 125 3A/S ta slog CP in M20 0.7 0.7 0.7 0.7 J.7 0.7 0.7 0.7 0.7 48 9 26 F1 1+125-1A+B SGTS plow cfm 2900 2900 2900 2900 2900 2900 2900 2900 2900 49 CAD DW/ Torus 02 Conc. 1 2.42 2.41 2.42 2.42 2.43 2.0 2.43 2.43 2.43 1 l i
A YtRMONT TAhK!! WUCLtAt POWtt $7ATION tev. 3 tuttathCY atsroust PREPAttDatst tutstist 3/26/88 1988 Page 8.0 4 8.0 OrttAttouAL DATA (Cont'd) 86enerlo itse therein) M:30 06:45 07:00 08:00 08:15 Clock Time (htrein) 12:30 12:45 13:00 14:00 14:15 Itos Penet Inst ID Description Units 1 93 FT 231081 NPCI Flow kepe 0 0' 0 0 0 2 93 71 10 1394 the A Flow kepe 6 6 6 6 6 3 93 FI 10 1396 RMt B Flow kape a 6 6 6 6 4 93 F! 10 504 Cs A Flow kepe PTL PTL PTL PTL PTL j 5 9-3 71 10 50s Cs t Flow kepe PfL PTL PIL PfL PIL 6 93 P! 161912A/S Drywlt Pressure pele 21 21 21 20 19 7 94 71 13 91 acic Flow spa 400 400 400 400 400 , 8 94 71 12 141A+B twCu Flow son 130 130 130 130 130 ! ] 9 94 DW tcNip SW San set 59 59 59 59 59 [ 1 10 94 DW Floor Se p sus set 65 65 45 65 65 11 v4 2 165A/B tu Cootent tecp deg 7 340 330 320 280 280 12 94 2 3 92A tectre A Orive Flow kepe 0 0 0 0 0 13 94 2 3 928 tectre B Drive Flow kaps 0 0 0 0 0 14 95 7 46A APRM/lRM A % 0 0 0 0 0 15 95 7 464 APRM/ttM t 1 0 0 0 0 0 16 95 7 46C APRM/lRM C 1 0 0 0 0 0 l 17 95 7 460 AveM/leM 0 1 0 0 0 0 0 l 18 95 7 46E ArtM!!tM t 1 0 0 0 0 0 i 19 95 7 46F APeM/leM F 1 0 0 0 0 0 20 95 7 434 sem a eps 4.0t+00 4.M +00 4. M +00 4.0E+00 4.0t+00 21 95 7 43B sem B ces 4.M+00 4.M+00 4.0t+00 6.0t+00 4.0t+00 1 22 95 7 43C stM C cpa 4.0t+00 4.0t+00 4.0t+00 4.0t+00 4.0t+00 1 23 95 7 430 stM 0 cps 4.M+00 4.0t+00 4.0t+00 4.M+00 4.0t+00 f
! 24 95 6 3 95 Core flow alb/hr 0 0 0 0 0 !
25 95 6 3 95 Core DP peld 0.6 0.6 0.6 0.6 0.6 I 26 95 71 3 310 CtD Flow spe 0 0 0 50 50 27 95 Ct Position f ri/out in in in in in 28 95 6 76 fee & eter flow alb/hr 0 0 0 0 0 29 95 6 96 horrow tense Levet inches 161 161 161 161 let 30 95 6 97 Mein stone FLcre otb/hr 0 0 0 0 0 4 31 95 6 97 Wide tange Press. pois 130 120 105 90 90 1 ] 32 95 6 98 Wide tense Levet Inches 155 155 155 155 155 l . 33 95 6 98 horrow tense Press. pals 08 05 05 05 Os
! 34 96 L1 107 5 Csf Levet t 60 60 60 60 60 )
! 35 96 LI 111 1 Notwell Levet u 1 60 60 60 60 60 ' 26 96 LI 111 2 totwett Level 5 5 52 52 52 52 52 37 97 PI 101 29 Cmdenser vacu.si in pg j 30 30 30 30 30 38 98 0/G A Skr Light gr/ red green grwn grwn grwn smo 39 98 D/G B Skr Light gr/ red green green green green green 40 9 25 115 16 19 48 Terus Temp. de9 F 109 104 104 107 107 41 9 25 LI 4M/B Tocus Levet feet 1,49 1.48 1.48 1.29 1.1 i 42 9 25 it 16 19 44 Terus Pressure pela 19.2 19.2 19.5 19 19 43 9 25 ft 16 19 44 Drywlt Pressure His 22.4 22.5 22.5 21.5 20 44 9 25 FA 1 156 3 OW/ Torus OP paid 2.38 2.38 2.35 1.2 0.2 45 9 25 ft 16 19 45 Orywlt Temp. deg 7 206 206 206 202 197 46 9 25 PR 1 156 3 Drywlt Pressure pais UP UP LP UP te 47 9 26 P! 1 125 3A/s ta stde DP in M20 0.7 0.7 0.7 0.7 0.7 il l 48 9 26 F1 1 125 1A+B 54T8 Flow cfm 2900 2900 2900 2900 2900 1 49 CAD OW/ Torus C2 Cone. 1 2.43 2.43 2.43 2.43 2.43 Legend 0$ cb nscete UP Wscale PTL patt to lock 1 l c
l l l , l I i VERMONT YANKEE WCLEAk POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE I ' 1988 e 9.0 RADIOLOGICAL DATA O l 1
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; 9.1 AREA RADIATION MONITORS !
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RB Control RB Elevator RB Elevator RB Reactor Clock Scenario Rod Drive Entrance Entrance Water Cleanup Time Time Repair (252') (280') (303') (303') 0600 0 15 8 2.2 3 0615 15 15 8 f.5 4 0630 30 15 8 2.5 4 06 4'., 45 15 8 2.5 4 C700 1:00 15 8 2.5 4 0715 1:15 15 8 2.5 4 0730 1:30 15 7 2.5 4 0745 1:45 15 7 2.5 4 0800 2:00 40 120 $ 4 0815 2:15 200 500 25 5 0830 2:30 600 1500 70 10 0845 2:45 1000 1800 100 15 0900 3:00 1500 2500 150 25 0915 3:15 2000 3000 200 30 0930 3:30 2000 3000 250 35 0945 3:45 2000 3000 300 35 1000 4:00 2500 3000 350 40 1015 4:15 3200 3000 400 50 1030 4:30 3200 3000 400 50 1045 4:45 3200 3000 400 55 1100 5:00 3200 3000 400 55 1115 5:15 3500 3000 400 55 1130 5:30 3500 3000 400 60 1145 5:45 3500 3000 400 60 1215 6:15 3500 3000 400 60 1245 6:45 3500 3000 400 60 1315 7:15 3500 3000 400 60 1345 7:45 3500 3000 400 60 1400 8:00 3500 3000 400 65 1415 8:15 3500 3000 400 65 1904e/4.386
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J 'v' 8/25788 Page 9.1-3 ! 9.1 AREA RADIATION MONITDRS (mR/hr unless noted otherwise) RB Elevator RB Reactor RB Spent Fuel RB Elevator RB Refueling Clock Scenario Entrance Water Cleanup Storage Pool Entrance Area West Time Time (318') (318') (345') (345') (345') 0600 0 4 5 10 3 4 0615 15 4.5 5 10 3.5 4 0630 30 4.5 5 10 3.5 4 0645 45 4.5 5 10 3.5 4 C700 1:00 4.5 4.5 10 3 4 0715 1:15 4.5 4.5 10 3 4 C730 1:30 4 4 10 2.5 4 C745 1:45 4 3.5 10 2.5 4 0800 2:00 6 110 10 8 6 0815 2:15 30 800 10 50 30 0830 2:30 90 1500 10 150 80 0845 2:45 120 2000 15 200 100 0900 3:00 180 2500 15 250 200 0915 ':15 J 220 3000 20 400 250 0930 3:30 240 3500 20 400 300 0945 3:45 270 4500 25 450 350 1000 4:00 300 5500 25 500 400 1015 4:15 350 5500 30 600 500 1030 5:15 375 2500 30 650 500 1045 4:45 400 500 30 650 400 1100 5:00 450 250 30 700 600 1115 5:15 450 150 30 700 600 1130 5:30 500 100 35 700 600 1145 5:45 500 90 35 700 600 1215 6:15 500 90 35 700 600 1245 6:45 500 90 35 700 600 1230 5:30 500 90 35 700 600 1345 7:45 500 80 35 700 600 1400 8:00 500 6000 35 700 600 1415 8:15 500 6000 35 700 600 1904e/4.386
l ,- _- w] ] g Page 9.1-4 9.1 AREA KADIATION MONITORS (mR/hr unless noted otherwise) RB New Fuel Fuel Fool F.onitor TB Moisture TB Condensate clock Scenario Storage Vault (345') Separator Area Demineralizer Area Time Time (318') k'est East (228') (232') 0600 0 1 10 10 150 0.3 0615 15 1 10 10 150 0.3 0630 30 1 10 10 150 0.3 0645 45 1 10 10 150 0.3 C700 1:00 1 10 10 150 0.3 C715 1:15 1 10 10 150 0.3 C730 1:30 1 10 10 120 0.25 0745 1:45 1 5 5 120 0.25 0800 2:00 25 6 6 100 0.25 0815 2:15 20 25 20 80 0.25 0830 2:30 60 60 60 60 0.2 0845 2:45 OSH (>102 ) 100 100 60 0.2 0900 3:00 USH 120 150 50 0.18 0915 3:15 OSH 150 200 40 0.18 0930 3:30 OSH 150 200 35 0.15 0945 3:45 OSH 160 220 30 0.15 1000 4:00 OSH 180 250 25 0.15 1015 4:15 OSH 250 300 25 0.15 1030 4:30 OSH 300 300 25 0.15 1045 4:45 OSH 320 300 18 0.15 1100 5.00 OSH 350 400 15 0.15 1115 5:15 OSH 400 400 12 0.15 1130 5:30 OSH 400 400 10 0.15 1145 5:45 OSH 400 400 10 0.15 1215 6:15 OSH 400 400 10 0.15 1245 6:45 OSH 400 400 10 0.15 1315 7:15 OSH 400 400 10 0.15 1345 7:45 OSH 450 400 10 c.15 1400 8:00 OSH 450 350 10 G.15 1415 8:15 OSH 450 350 10 0.15 OSH = Offscale High 1904e/4.386
=- . ._ _ _. - _ . - - - - _ - _ - - - _ - _ _ - _ _ ._ . . -- . - . _ _ ._ _ _
l 8 Pcg2 9.1-5 l l 9.1 AREA RADI ATION MONITORS (mR/hr unless noted otherwise) TB North TB Main Steam TB Steam TB Railroad TB Clock Scen~,rio Personnel Access Stop Valve Area Inlet (272') Rear Cate (252') Decontamination Time Time (248') (248') 400 200 0.02 0.2 l 0600 0 3 0.02 0.2 2.5 4C0 200 0615 15 0.2 400 200 0.02 0630 30 2.5 0.2 2.5 400 2.00 0.02 0645 45 0.2 400 200 0.02 0700 1:00 2.5 2.5 350 180 0.01 0.2 0715 1:15 0.01 0.2 2.5 300 150 0730 1:30 0.01 0.2 2.5 280 150 07's5 1:45 0.01 0.2 2.5 280 150 0800 2:00 0.01 0.18 2.5 220 100 0815 2:15 0.01 0.18 2 180 100 0830 2:30 0.01 0.18 2 170 90 0845 2:45 0.01 0.18 2 150 80 0900 3:00 0.01 0.18 1.8 150 70 0915 3:15 0.01 0.15 1.8 140 60 0930 3:30 0.01 0.15 1.8 130 55 0945 3:45 0.01 0.15 4:00 1.8 120 50 1000 0.01 0.15 1.8 100 45 1015 4:15 0.01 0.15 1.8 100 40 1030 4:30 0.01 0.15 1.5 90 40 1045 4:45 0.01 0.15 5:00 1.5 70 35 1100 0.15 1.5 70 35 0.01 1115 5:15 0.01 0.15 1.5 65 30 1130 5:30 0.01 0.15 1.5 60 30 1145 5:45 0.01 0.15 1.5 60 30 1215 6:15 0.01 0.15 6:45 1.5 60 30 1245 0.01 0.15 1.5 60 30 1315 7:15 0.01 0.15 7:45 1.5 55 30 1345 0.01 0.15 1.5 55 25 1400 3:00 0.01 0.15 1.5 55 25 1415 8:15 l 1904e/4.386
.-_. . ._ _ _ - _ . _-. ._. ._ _ - - _ _ ~ -. . - . .. - . . .-_ - - -. _ _ _ _ _
A
)I L. 2/88
" ge 9.1-6 9.1 AREA RADIATION MONITORS (mR/hr unless noted otherwise)
Radwaste Pump Radwaste Recirculation and Tank Area Pump Room Radwaste (155') Control Room Clock Scenario Viewing Callery Time (230*) (255') Operating Area Time _. 1.5 1 1.5 0.15 0600 0 1.5 1 1.5 0.15 0615 15 1.5 1 1.5 0.15 0630 30 45 1.5 1 1.5 0.15 0645 . 0.15 1:00 1.5 1 1.5 0700 0.15 0715 1:15 1.5 1 1.5 1.5 1 1.2 0.15 0730 1:30 0.15 1.5 1.2 0745 1:45 1 0.15 0800 2:00 1.5 1 1.2 1.5 1.2 0.15 0815 2:15 1 1.5 1.2 0.15 0830 2:30 1 1.5 1.2 0.12 0845 2:45 1 0.12 3:00 1.5 1 1.2 0900 0915 3:15 1.5 1 1.2 0.12 0930 3:30 1.5 1 1.2 0.12 1.5 1 1.2 0.12 0945 3:45 1000 4:00 1.5 1 1.2 0.12 1015 4:15 1.5 1 1.2 0.12 1030 4:30 1.5 1 1.2 0.12 1.5 1 1.2 0.12 1045 4:45 5:00 1.5 1 1.2 0.12 1100 1 1.2 0.12 1115 5:15 1.5 0.12 1.5 1 1.2 1130 5:30 1145 5:45 1.5 1 1.2 0.12 6:15 1.5 1 1.2 0.12 1215 1245 6:45 1.5 1 1.2 0.12 1.5 1 1.2 0.12 1315 7:15 0.12 1345 7:45 1.5 1 1.2 1.5 1.2 0.12 1400 8:00 1 1415 8:15 1.5 1 1.2 0.12 1904e/4.386
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i O O O Rev. 2 8/26/88 Page 9.2-2 j 9.2 PROCESS MONITORS (Continued) Clock Scenario RB Vent Exhaust Plenuss SJAE Stack Cas Nigh-Range Noble Cas Time Tisme North (smR/hr) South (nR/hr) Monitor (udt/hr) I (epse) II (cysm) Stack Cas (mR/hr) , 0600 0 1.5 1.5 140 20 20 <.1 0615 0:15 1.5 1.5 160 20 20 <.1 0630 0:30 1.5 1.5 160 20 20 <.1 0645 0:45 1.5 1.5 160 20 20 <.1 l 0700 1:00 1.5 1.5 160 20 20 '
<.1 l 0715 1:15 1.5 1.5 140 20 20 <.1 l C730 1:30 1.5 1.5 120 20 30 <.1
, C745 1:45 6 6 100 20 20 <.1 0800 2:00 20 20 D/S 20 20 <.1 0815 2:15 80 60 D/S 20 20 <.1 ! 0830 2:30 80 80 D/S 20 20 <.1 l 0845 2:45 100 100 D/S 20 20 <.1 0900 3:00 100 100 D/S 20 20 <.1 - 0915 3:15 100 100 D/S 20 20 <.1 l 0930 3:30 100 100 D/S 20 20 <.1 0945 3:45 125 125 D/S 20 - 20 c.1 1000 4:00 150 150 D/S 20 20 <.1 1C15 4:15 150 150 D/S 20 20 <.1 l 1030 4:30 150 150 D/S 20 20 <.1 , 1045 4:45 100 100 D/S 20 20 <.1 l 1100 5:00 100 100 D/S 20 20 <.1 1115 5:15 90 90 D/S 20 20 <.1 1130 5:30 90 90 D/S 20 20 <.1 l 1145 5:45 90 90 D/S 20 20 <.1 1215 6:15 90 90 D/S 20 20 <.1 l 1245 6:45 90 90 D/S 20 20 <.1
- 1315 7
- 15 90 9u D/S 20 20 <.1 l 1345 7:45 90 90 D/S 20 20 <.1 1400 8:00 80 70 D/S 20 20 <.1 1415 8:15 200 200 D/S 20 20 <.1 D/S = Downscale reading 1906e/20.600
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' Rev. 1 8/26/88 Pcge 9.3-3a TABLE 9.3-3 Reactor Building. Elevation 303' (mR/hr unless otherwise noted) C1cck Scena rio Time Time ARM 8 ARM 9 Zone I Zone II Zone III Zone Ij[ 0600 0 2 3 40 2 2 1 0700 1:00 2.5 4 40 2 2 1 0715 1:15 2.5 4 40 2 2 1 0730 1:30 2.5 4 40 2 2 1 0745 1:45 2 4 40 2 2 1 0800 2:00 5 4 40 4 8 6 0815 2:15 25 4 60 30 40 15 0830 2:30 70 10 80 55 100 20 OR45 2:45 100 15 100 80 140 30 0900 3:00 150 15 100 115 200 40 0915 3:15 200 30 150 140 280 50 0930 3:30 250 35 150 140 300 50 0945 3'.< 3 300 35 200 140 300 50 1000 4:00 350 40 200 140 300 50 1015 4:15 400 50 300 200 380 70 - 1030 4:30 400 50 350 230 400 80 1045 4:45 400 55 350 230 400 80 1100 5:00 400 55 350 230. 400 80 1130 5:30 400 60 350 230 400 80 1200 6:00 400 60 350 230 400 80 1230 6:30 400 60 350 230 400 80 f 1300 7:00 400 60 350 230 400 80 l 1315 7:15 400 60 350 230 400 80 j 1330 7:30 400 60 350 230 400 80 j 1400 8:00 400 65 350 230 400 80 , 1415 8:15 400 65 350 230 400 80 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2 is,all zones. IC10e/20.601
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O O O key. 1 8/26/88 Page 9.3-4a TABLE 9.3-4 Reactor Buildina, Elevation 280' (mR/hr unless otherwise noted) RB Vent RB Vent Clock Scenario North South Time Time ARM 6 ARM 31 ARM 12 Zone I Zone II Zone III Zone IV Zone V Zone VI Zone VII 0600 0 8 ' .5 1.5 1 2 2 1 75 8 1 0700 1:00 8 1.5 1.5 1 2 2 1 75 8 1 0715 1:15 8 1.5 1.5 1 2 3 2 75 8 2 0730 1:30 7 1.5 1.5 1 2 3 2 75 8 2 0745 1:45 7 6 6 5 4 5 4 80 10 4 0800 2:00 120 20 20 15 10 30 10 240 100 70 0815 2:15 500 80 60 60 40 100 50 800 400 300 0830 2:30 1500 80 80 70 80 300 150 2500 1200 800 0845 2:45 1800 100 100 80 120 360 180 3200 1600 900 0900 3:00 2500 100 100 90 170 360 250 4000 2200 1200 0915 3:15 3000 100 100 90 230 360 300 4000 2200 1200 0930 3:30 3000 100 100 90 2.30 400 320 4000 2200 1200 0945 3:45 3000 125 125 100 230 500 340 4000 2200 1200 1000 4:00 3000 150 150 120 280 600 340 5000 2800 1200 1015 4:15 3000 150 150 120 320 600 340 5500 3000 1550 1030 4:30 3000 150 150 120 370 600 340 6000 3000 1550 1045 4:45 3000 100 100 120 370 600 340 6000 3000 1550 1100 5:00 2000 100 100 120 370 600 340 6000 3000 1550 1130 5:30 3000 90 90 120 370 600 340 6000 3000' 1550 1200 6:00 3000 90 90 120 370 600 340 6000 3000 1550
, 1230 6:30 3000 90 90 120 370 600 340 6000 3000 1550 l 1300 7:00 3000 90 90 120 370 600 340 6000 3000 1550 1315 7:15 3000 80 70 120 370 600 340 6000 3000 1500 1330 7:30 3000 90 90 120 370 600 340 6000 3000 1550 1400 8:00 ?000 80 70 120 370 600 340 6000 3000 1550 1415 8:15 3000 200 200 120 370 600 340 6000 3000 1550 l Notcs: Zone readings are aversge dose rates throughout zone.
General area contamination levels <1K dpe/100 cm2 in all zones. 1910e/20.601
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O O O Rev. 1 8/25/88 Page 9.3-Sa.1 TABLE 9.3-5 Resctor "nilding, Elevation 252' (rK/h. ..less otherwise noted) (North) Clock Scenario (South) Zone II & l ARM 3 ARM 4 ARM S ARM 7 RM-;4-29* RM-14-30* Zone I 2one II Zone III Zone IV Zone V Zone VII Zone VI Time Time ARM 2 0600 0 10 0.2 5 300 15 100 200 15 14 2 1 2 2 2 0700 1:00 10 0.3 5 250 15 100 200 15 14 3 2 3 3 2 0715 1:15 10 0.3 5 250 15 150 200 15 14 6 3 6 6 3 , 0730 1:30 10 0.3 5 25G 15 150 200 15 14 6 3 6 6 3 l C745 1:45 10 0.6 6 250 15 150 200 15 14 6 3 6 6 3 0800 2:00 60 4 40 1000 40 >500 420 30 20 15 10 10 60 30 0815 2:15 150 3 35 4000 200 >500 450 150 130 60 30 20 60 200 d 0830 2:30 400 4 20 8000 600 >500 450 550 530 200 80 40 60 500 0845 2:45 800 6 20 8000 1000 >$00 450 ,950 900 300 100 75 80 900 0900 3:00 >103 8 25 8000 1500 >500 >500 1400 1300 500 200 150 100 900 0915 3:15 >103 10 30 8000 2000 >500 >500 1800 1500 900 350 300 100 900 l 0930 3:30 >103 10 30 8000 2000 >500 >500 1800 1500 900 350 300 500 1200 0945 3:45 >103 15 40 8000 2000 >500 >500 1800 1500 900 400 300 500 1200 1000 4:00 >103 20 50 9000 2500 >500 >500 2000 1800 1000 450 400 1000 2000 1015 4:15 >103 600 2000 >104 3200 >500 >500 2800 2500 1500 1200 800 i0 3000 1030 4:30 >103 700 2000 >104 3200 >500 >500 2800 2500 69 1200 800 1300 3000 1045 4:45 >103 800 2000 >104 3200 >500 >500 2800 2500 1506 '200 800 1500 3000 l 1100 5:00 >103 3103 2000 >104 3200 >500 >500 2800 2500 1500 1200 800 1500 3000 1130 5:30 >103 3103 2000 >104 3500 >500 >500 2800 2500 1500 1200 800 1500 3000 1200 6:00 >103 >103 2000 >104 3500 >500 >500 2800 2500 1500 1200 800 .1500 3000 1230 6:30 >103 >103 2000 >104 3500 >500 >500 2800 2500 1500 1200 800 15GJ 3000 l 1300 7:00 >103 >103 2000 >104 3500 >500 >500 2800 2500 1500 1200 800 1500 3000 1315 7:15 >103 >103 2000 >104 3500 >500 >500 2800 2500 1500 1200 800 1500 3000 1330 7:30 >103 >103 2000 >104 3500 >500 >500 2800 2500 1500 1200 800 1500 3000 1415 8:15 >103 3103 2000 >104 3500 >500 >500 2800 2500 1500 1200 800 1500 3000 Notes: Zone readings are average dose rates throughout zone. . General area contemination Icvels <1K dpm/100 cm 2 in all zones.
- RM-14 readings in cps and the RM-14 on X1 s.: ale goes off-scale at >500 cpm.
1910e/20.601 l L_______________________ _ ________________ _ ___ _ _ __ _
Rev. 1 8/25/88 O Page 9.3-Sa.2 O- TABLE 9.3-5 (Continued) Clock Scenario Time Time RMS II-1** RMS II-2** RMS II-3** 0600 0 <1.0 <1.0 <1.0 . 0700 1:00 <1.0 <1.0 <1.0 l . 0715 1:15 <1.0 ,<1.0 <1.0 0730 1:30 (1.0 <1.0 (1.0 0745 1:45 <1.0 <1.0 <1.0 , 0800 2:00 <1.0 <1.0 <1.0 0815 2:15 <1.0 (1.0 <1.0 j 0830 2:30 <1.0 <1.0 (1.0 0845 2:45 1.0 1.0 <1.0 : 0900 3:00 1.5 1.5 <1.0 0915 3:15 1.5 2.0 1.0 . 0930 3:30 1.5 2.0 1.0 , 0945 3:45 2.0 2.5 1.0 4:00 2.0 2.5 1.0 1000 1015 4:15 2.0 2.5 1.0 1030 4:30 2.0 2.5 1.0 ! 1045 4:45 2.0 2.5 1.0 i 1100 5:00 2.0 2.5 1.0 i 1130 5:30 2.0 2.5 1.0 O 1200 1230 6:00 6:30 2.0 2.0 2.5 2.5 1.0 1.0
- 1300 7
- 00 2.0 2.5 1.0 1315 7:15 2.0 2.5 1.0 1330 7:30 2.0 2.5 1.0 i 1415 8:15 2.0 2.5 1.0 Notes: l
** RMS II readings in R/hr (high-range accident ARMS - 1 R/hr to 10.000 R/hr) 1 l 1910e/20.601 4
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O O O TABI.E 9.3-6 Rev. 1 8/26/88 Turbine Deck, Elevation 272' Page 9.3-6a (mR/hr unless otherwise noted) Turbine Deck Clock Scenario CAM (cpe) Time Time ARM 24 Zone I Zone II Zone III NG Particulate 0600 0 200 100 25 2 250 900 0700 1:00 200 100 25 2 250 900 l 0715 1:15 180 80 20 2 250 900 0730 1:30 150 75 20 2 250 900 0745 1:45 150 75 15 2 250 900 0800 2:00 150 75 15' 2 250 900 0815 2:15 100 50 10 2 275 900 0830 2:30 100 50 10 1 300 900 0845 2:45 90 40 10 1 300 50? 0900 3:00 30 40 8 0.8 300 90( 0915 3:15 70 30 7 0.8 300 900 l 0930 3:3G 60 30 6 0.7 300 900 0945 3:45 55 25 5 0.7 300 900 1000 4:00 50 25 5 0.7 300 900 1015 4:15 45 20 5 0.7 300 900 1030 4:30 40 20 4 0.4 300 900 l 1045 4:45 40 20 4 0.4 - 300 900 35 4 1100 5:00 15 0.4 300 900 1130 5:30 30 15 4 0.4 300 900 1200 6:00 30 15 4 0.4 300 900 1230 6:30 30 15 4 0.4 300 900 1300 7:00 30 15 4 0.4 300 900 1315 7:15 30 15 4 0.4 300 900 1330 7:30 30 15 4 0.4 300 900 1415 8:15 - 25 15 4 0.4 300 900 Notcs: Zone readings are average dose rates throughout zone. 1910e/20.601
- ~ _ ,_. - - Ea-.- l n.S Pcge 9.3-6b l l (
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l- O O O TABLE 9.3-7 Rev.-1' 8/26/88 Turbine Building Truck Bay, Make-Up Demineral_ization Cond. Demineralization Areas. Page'9.3-7a' Elevation 252' (mR/'r 2nless otherwise noted) Clock Scenario Time Time RM-14-23A (cpm) ARM 26 RM-14-36 (cpm) RM-14-37 (cpm) Zone I Zone II Zone III Zone IV 0600 0 150 0.02 150 150 0.2 0.2 0.1 0.2 0700 1:00 150 0.02 150 150 0.4 0.3 0.2 0.2 0715 1:15 150 0.02 150 150 0.5 0.3 0.2 0.2 0730 1:30 150 0.02 150 150 0.5 0.3 0.2- 0.2 0745 1:45 150 0.02 150 150 0.5 0.3 0.2 0.2 j 0800 2:00 150 0.02 150 150 0.5 0.3 0.2 0.2 0815 2:15 150 0.02 150 150 0.5 0.3 0.2 0.2 0830 2:30 150 0.02 150 150 0.5 0.3 0.2 0.2 0845 2:45 150 0.02 150 150 0.5 0.3 0.2 0.2 0900 3:00 150 0.01 150 150 0.6 0.3 0.2 0.2 0915 3:15 150 0.01 150 150 0.6 0.3 0.2 0.2 0930 3:30 150 0.01 150 150 0.6 0.3 O.2 0.2 _ 0945 3:45 150 0.01 150 150 0.6 0.3 0.2 0.2 1000 4:00 150 0.01 150 150 0.6 0.3 0.2 0.2 1015 4:15 150 0.01 150 150 0.7 0.3 0.2 0.2 1030 4:30 150 0.01 150 150 0.7 0.3 0.2 0.2 l 1045 4:45 150 0.01 150 150 0.7 0.3 0.2 0.2 ! 1100 5:00 150 0.01 150 150 0.7 0.3 0.2 0.2 1130 5:30 150 0.01 150 150 0.7 0.3 0.2 0.2 1200 6:00 150 0.01 150 150 0.7 0.3 0.2 0.2 1230 6:30 150 0.01 150 150 0.7 0.3 0.2 0.2 1300 7:00 150 0.01 150 150 0.7 0.3 0.2 0.2 1315 7:15 150 0.01 150 150 0.7 0.3 0.2 0.2 1330 7:30 150 0.01 150 150 0.7 0.3 0.2 0.2 l 1415 8:15 150 0.01 150 150 0.7 0.3 0.2 0.2 Notec: Zone readings are average dose rates throughout zone. l 1910e/20.601
(G (G '.)~. PRETREATMENT ROOM, BOILER RdONI, TURBINE LOADING BAY, MUDS, DIESELS, COND. DEMIN. HATCH
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O O O Rev. 1 8/26/88 ' -Page 9.3-8a TABLE 9.3-8 , Turbine Building Cond. Bay. Elevation 248' (mR/hr unless otherwise noted) 1 Clock Scenario Time Time ARM 20 ARM 21 Zone I Zone II Zone III Zone IV 0600 0 3 400 70 300 400 2 0700 1:00 2.5 400 80 300 400 3
, 0715 1:15 2.5 350 70 250 350 3 0730 1:30 2.5 300 60 200 300 3 0745 1:45 2.5 280 50 180 280 3
- 0800 2
- 00 2.5 280 0.5 180 280 3 0815 2:15 2.5 220 0.5 120 220 2.5 j 0830 2:30 2 180 0.5 80 180 2.5 i 0845 2:45 2 170 0.5 70 170 2.5 C900 3:00 2 150 0.5 50 150 2 0915 3:15 1.8 150 0.5 30 150 2 1
0930 3:30 1.8 140 0.5 30 100 2 9 0945 3:45 1.8 130 0.5 30 100 2 1000 4:00 1.8 120 0.5 20 90 1.8 1015 4:15 1.8 100 0.5 20 70 1.8 1030 4:30 1.8 100 0.5 20 60 1.8 1045 4:45 1.5 90 0.5 20 60 1.5 1100 5:00 1.5 70 0.5 20 60 1.5 1130 5:30 1.5 65 0.5 20 60 _ 1.5 1200 6:00 1.5 60 0.5 20 50 1.5 1230 6:30 1.5 60 0.5 20 50 1.5 1300 7:00 1.5 55 0.5 20 _ 50 1.5 1315 7:15 1.5 55 0.5 20 50 1.5 1330 7:30 1.5 55 0.5 20 50 1.5 1415 8:15 1.5 55 0.5 20 50 1.5 Notes: Zone readings are average dose rates throughout zone. General area contamination levels <1K dpe/100 cm 2, 1910e/20.601
O s_e (nv) E TURBINE BUILDING EL. 248' m n 2 - I : m @- c , , 0111111
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l l O O O Rev. 1 8/26/88 Page 9.3-9a-TABLE 9.3-9 Turbine Building, Demineralization /OG Areas. Elevation 232' (mR/hr unless otherwise na.ted) Clock Scenario Time Time ARM 22 ARM 38 Zone I Zone II Zone III 0600 0 0.3 140 10 0.5 3 0700 1:00 0.3 160 10 0.5 3 0715 1:15 0.25 140 'O 0.5 3 0730 1:30 0.25 120 10 0.5 3 0745 1:45 0. 25 100 10 0.5 3 0800 2:00 0.25 D/S 10 0.5 1 0815 2:15 0.25 D/S 10 0.5 1 0830 2:30 0.2 D/S 10 0.5 1 0845 2:45 0.2 D/S 5 0.5 1 0900 3:00 0.18 D/S 5 0.5 1 0915 3:15 0.18 D/S 5 0.5 1 0930 3:30 0.15 D/S 5 0.5 1 0945 3:45 0.15 D/S S 0.5 1 l 1000 4:00 0.15 D/S 5 0.5 1 l 1015 4:15 0.15 D/S 5 0.5 1 1030 4:30 0.15 D/S 5 0.5 1 1045 4:45 0.15 D/S 5 0.5 1 1100 5:00 0.15 D/S 5 0.5 1 ! 1130 5:30 0.15 D/S 5 0.5 - 1 l 1200 6:00 0.15 D/S 5 0;5 1 ! 1230 6:30 0.15 D/S 5 0.5 1 1300 7:00 0.15 D/S 3 0.5 1 1315 7:15 0.15 D/S 5 0.5 1 1330 7:30 0.15 D/S 5 0.5 1 ! 1415 8:15 0.15 D/S S 0.5 1 Notco: Zone readings are average dose rates throughout zone. General area contamination levels (1K dpe/100 cm 2, D/S = Downscale reading. l 1910e/20.601 _ _ _ _ _ _ _ - _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ = _ _ . ._ - - . _ - .--
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Rev. 1 0/26/88 Page 9.3-10a TABLE 9.3-10 Turbine Building Cond. Bay. Elevation 222'6" & 228'6" (mR/hr unless otherwise noted) Clock Scenario Time Time ARM 13 Zone I Zone II Zone III Zone IV Zone V 0600 0 150 3 150 70 2 2 0700 1:00 150 3 150 70 2 3 0715 1:15 150 3 150 70 2 3 0730 1:30 120 3 120 60 2 3 0745 1:45 120 3 120 60 2 3 0800 2:00 100 2 100 60 2 3-0815 2:15 80 2 80 55 2 3 0830 2:30 60 2 60 50 2 3 0845 2:45 60 2 60 50 2 2.5 0900 3:00 50 2 50 50 1.5 2.5 0915 3:15 40 2 40 50 1.5 2.5 0930 3:30 35 2 25 45 1.5 2.5 0945 3:45 30 2 20 45 1.5 2.5 1000 4:00 25 2. 20 40 1.5 2.5 1015 4:15 25 2 15 40 1.5 2.5 1030 _ 4:30 20 2 10 40 1.5 2.5 l 1045 4:45 18 2 8 2. 1.5 2.5-1100 5:00 15 1.5 8 2 1.5 2.5 1130 5:30 10 1.5 8 2 1.5 2.5 1200 6:00 10 1.5 8 2 1.5 2.5 1230 6:30 10 1.5 8 2 1.5 2.5 1300 7:00 10 1.5 8 2 1.5 2.5 1315 7:15 10 1.5 8 2 1.5 2.5 1330 7:30 10 1.5 8 2 1.5 2.5 1415 8:15 10 1.5 8 2 1.5 2.5 l Notes: Zone readings are average dose rates throughout zone. General arer. contamination levels <1K dpsa/100 cm2, 1910e/20.601
s p V ( U , TURBINE BUILDING EL.222'6"&228'6' h Turbine Bldg. Moisture Separator Area ta ca r. i AEd mccw == E ) e u 55'p"t: 00 'P
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Rev. 0 5/31/88 Page 9.3-11a TABLE 9.3-11 ; Dryve11. Elevation 252' , (R/hr unless otherwise noted) , ~ Clock Scenario . Time Time ARM 27 ARM 28 l l : j 0600 0 2.0 2.0 0700 1:00 2.0 2.0 . 0715 1:15 2.0 2.0 { 0730 1:30 3.0 3.0 0745 1:45 3.0 3.0 j 0800 2:00 30 30 ; 3 0815 2:15 100 100 ; 0830 2:30 100 100 0845 2:45 300 300 l 0900 3:00 400 400 ., 0915 3:15 400 400 0930 3:30 450 470 ( 0945 3:45 520 550 i 1000 4:00 620 600 ' 1015 4:15 1500 1500 i 1030 4:30 1500 1500 l l O 1045 1100 4:45 5:00 1500 1500 1500 1500 l 1130 5:30 1500 1500 ; 7 1200 6:00 1500 1500 1230 6:30 1500 1500 4 1300 7:00 1500 1500
- 1315 7:15 1500 1500 7:30 1330 1500 1500 ;
} 1415 8:15 1500 1500 1 1 l i i l j i k i l 1910e/20.601 i i U ______.-__._.___m___________.____._4
l Page ga,11b q FIGU'c.E 9.3_11. O . DR Y'dFLL EL.252,5
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Rev. 1 8/25/88 ' Page 9.3-12a TAB 1.E 9.3-12
/
Torus Catwalk 4 (mR/hr unless otherwise noted) I Clock Scenario Time Time ARM 1 Zone I Zone II 0600 0 10 30 10 0700 1:00 10 30 10-0715 1:15 10 30 10 i 0730 1:30 10 30 10 .1 0745 1:45 10 30 10 0800 2:00 100 300 100 , 0815 2:15 450 1300 450 0830 2:30 3000 9000 3000 0845 2:45 >104 30000 12000 0900 3:00 >104 40000 15000 , 0915 3:15 >104 40000 15000 0930 3:30 >104 40000 15000 0945 3:45 >104 40000 15000 1000 4:00 >104 40000 15000 1015 4:15 >104 50000 25000 1030 4:30 >104 50CM 25000 1045 4:45 >104 50000 25000 1100 5:00 >104 50000 25000 1130 5:30 >104 50000 25000 1200 6:00 >104 50000 25000 5 1230 0:30 >104 50000 25000 4 1300 7:00 >104 50000 2.5000 4 1315 7:15 >104 50000 25000 1330 7:30 >104 50000 25000 j 1415 8:15 >104 50000 25000 Notes Zone readings are average dose rates throughout zone. General ares contamination levels <1K dpm/100 cm2, i i' i 1910e/20.601
l flGURE AS12 TRUS CAT WAL.K__ , Page 9.312b h F.ca, Bldg. Suppression Chamber Ext. Catvalk H , I
$ TO NW ACCESS HATCH l
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, l I l VERMONT YANKEE NUCLEAR POWER STATION l l l4. E'ERGENCY RESPONSE PREPAREDNtSS EXERCISE I
! 1988 l i i ; I l !
i ; i 1 { 9.4.1 R_EACTOR COOLANT ACTIVITY DATA 1 } t 4 , , t i l t L i
?
O 1908e/26.307 i .
I l Rev. 2 8/26/88 Page 9.4.1-1 . o , VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT ACTIVITY DATA i Reactor Coolant Activity Concentrations (uci/ml) I A. i
; Time Isotope Prior to 0615 0615 - 0630 0630 - 0645 l
I-131 2.3E-4 9.5E-3 1.1E-2 I a I-132 3.4E-4 1.4E-2 1.6E-2 j I-133 5.3E-4 2.2E-2 2.6E-2 I-134 4.6E-4 1.9E-2 2.3E-2
- ) - i l I-135 4.4E-4 1.8E-2 2.2E-2 Total Iodine
- 2.0E-3 8.3E-2 9.8E-2 I-131 Dose Equivalentt 4.4E-4 1.8E-2 2.2E-2 Kr-85m 7.5E-5 3.2E-3 3.7E-3 Kr-85 9.5E-6 4.0E-4 4.7E-4 Kr-87 9.9E-5 4.2E-3 4.9E-3 Kr-88 1.8E-4 7.6E-3 8.8E-3 Xe-133 4.3E-4 1.8E-2 2.1E-2 Xe-135m 1.1E-4 4.6E-3 5.4E-3 Xe-135 9.1E-5 3.8E-3 4.5E-3 Total Noble Cas 1.0E-3 4.2E-2 4.9E-2 O Notes Reactor coolant sample dose rates are provided in Section 9.5.
1908e/26.307
\
I i Rev. 2 I 8/26/88 ' Page 9.4.1-2 l VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT ACTIVITY DATA 4 l A. Reactor Coolant Activity Concentrations (uCi/ml) i
, um Isotope 0645-0700 0700-0745 I-131 2.3E 5.9E-2 I-132 3.4E-2 8.6E-2 I-133 5.3E-2 1.3E-1 I-134 4.6E-2 1.2E-1 !
I-135 4.4E-2 1.1E-1 Total Iodine: 2.0E-1 5.1E-1 i I-131 Dose ! l Equivalent: 4.4E-2 1.1E-1 Kr-85m 7.5E-3 2.0E-2 Kr-85 9.5E-4 2.5E-3 t i i Kr-87 9.9F-3 2.6E-2 , 1 Kr-88 1.8E-2 4.7E-2 i Xe-133 4.3E-2 1.1E-1
; Xe-135m 1.1E-2 2.9E-2
- Xe-135 9.1E-3 2.4E-2
- I Total 1 Noble Cas: 1.0E-1 2.6E-1
] Note Reactor coolant sample dose rates are provided in Section 9.5. ; i '
! f I
i 1908e/26.307 i i . l
l i Rev. 2 8/26/88 Page 9.4.1-3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR C001 ANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uC, al) ( Time 4 Isotope 0745 - 0800 0800 - 0815 I-131 3.2E+1 2.9E+1 I-132 4.7E+1 4.2E+1 I-133 7.4E+1 6.6E+1 i I-134 6.5E+1 5.8E+1 I-135 6.2E+1 5.5E+1 i r Total Iodine: 2.8E+2 2.5E+2 - , I-131 Dose 4 Equivalent 6.2E+1 5.5E+1 ! 1 Kr-85m 2.2E+3 2.1E+3 l j Kr-85 2.8E+2 2.7E+2 : Kr-87 2.9E+3 2.8E+3 l Kr-88 5.2E+3 5.0E+3 j i Xe-133 1.2E+4 1.2E+4 l l Xe-135m 3.2E+3 3.1E+3 Xe-135 2.6E+3 2.5E+3 l Total Noble Gas: 2.9E+4 2.8E+4 iO i Note Reactor coolant sample dose rates are provided in Section 9.5. J i 1908e/25.307
. Rev. 2 8/26/88 Page 9.4.1-4 t
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT ACTIVITY DATA A. Reactor Coolant Activity Concentrations (uci/ml) Time Isotope 0815 - 0830 0830 - 0845 0845 - 0900 t 1 I-131 2.6E+1 2.4E+1 2.3E+1
- I-132 3.9E+1 3.5E+1 3.4E+1 ,
I-133 6.1E+1 5.5E+1 5.3E+1 ! l I-134 5.3E+1 4.9E+1 4.6E+1 1-135 5.1E+1 4.6E+1 4.4E+1 i Total Iodine 2.3E+2 2.1E+2 2.0E+2 1-131 Dose Equivalent: 5.1E+1 4.6E+1 4.4E+1 ' Kr-85m 2.0E+3 2.0E+3 1.9E+3 I Kr-85 2.6E+2 2.5E+2 2.4E+2
; Kr-87 2.7E+3 2.6E+3 2.5E+3 '
l Kr-88 4.9E+3 4.7E+3 4.5E+3 ! J Xe-133 1.2E+4 1.1E+4 1.1E+4 l i Xe-135m 3.0E+3 2.9E+3 2.8E+3 : l Xe-135 2.5E+3 2.4E+3 2.3E+3 1 l Total l Noble Gast 2.7E+4 2.6E+4 2.5E+4 l Notes Reactor coolant sample dose rates are provided in Section 9.5. J
; 1908e/26.307 i
i
J i Rev. 2 S/26/88
/ Page 9.4.1-5 I
( VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 9.4.1 REACTOR C001AVT ACTIVITY DATA P A. Reactor Coolant Activity Concentrations (uci/ml) r J Time Isotong 0900 - 0915 0915 - 0930 0930 - 1000 1 I-131 2.2E+1 2.1E+1 1.3E+1 I-132 3.2E+1 3.0E+1 1.9E+1 I-133 5.0E+1 4.8E+1 3.1E+1 ' I-134 4.4E+1 4.2E+1 2.7E+1 I-135 4.2E+1 4.0E+1 2.6E+1
}
1 Total Iodine: 1.9E+2 1.8E+2 1.2e+2 ! i I-131 Dose ; i Equivalent: 4.2E+1 4.0E+1 2.4E+1 ; i Kr-85m 1.7E+3 1.6E+3 7.5E+2 l Kr-85 2.2E+2 2.0E+2 9.5E+1 Kr-87 2.3E+3 2.1E+3 9.9E+2 i Kr-88 4.1E+3 3.8E+3 1.8E+3 l Xe-133 9.9E+3 9.0E+3 4.3E+3 l Xe-135m 2.5E+3 2.3E+3 1.1E+3 Xe-135 2.1E+3 1.9E+3 9.1E+2 l 4 Total Noble Gast 2.3E+4 2.1E+4 1.0F+4 1-0 Notes Reactor coolant sample dose rates are provided in Section 9.5. 1908e/26.307 1
i Rev. 2 8/26/88 Q Page 9.4.1-6 b VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREP /JtEDNESS EXERCISE 1988 9.4.1 REACTOR COOLANT ACTIVITY DATA j A. Reactor Coolant Activity Concentrations (uCi/al) l Time l Isotope 1000 - 1015 1015 - 1030 1030 - 1415 9 ,
\
I-131 1.3E+1 1.1E+1 1.1E+1 1 I-132 1.8E+1 1.6E+1 1.6E+1 j I-133 2.9E+1 2.6E+1 2.5E+1 ! I-134 2.5E+1 2.3E+1 2.2E+1 I-135 2.4E+1 2.2E+1 2.1E+1 l Total Iodine 1.1E+2 9.8E+1 9.5E+1 I-131 Dose Equivalent 2.4EC 2.2E+1 2.1E+1 1 Kr-85m 7.1E+2 9.0E-1 3.9E-2 Kr-85 9.0E+1 1.1E-1 4. . 3 f Kr-87 9.4E+2 1.2E'O ' ' [ ] Kr-88 1.7E+3 2.2E+0 9.4E-2 ! j Xe-133 4.1E+3 5.2Et0 2.2E-1 l Xe-135m 1.0E+3 1.3E*0 5.7E-2 l i Xe-135 8.6E+2 1.1E*0 4.7E-2 ' Total Noble Gas 9.5E+3 1.2E+1 5.2E-1 l i' ! Notes Reactor coolant sample dose rates are provided in Section 9.5. 1 I : 1 j 1908e/26.307 l l 1
4-kb e
, VERMONT YANKEE NUCLEAR POWER STi. TION +
EMERGENCY RESPONSE PREPAREDNESS EXERCISE
** 1988 p.
, 9.4.2 . PRIMARY CONTAINMENT AIR ACTIVITY DAT..
l
- o.
.g l k I e .
Ai s
,.. k b ?? ' iH 1905;/20.595
___._.______s- - - - _ - __ . _ _ _ _ _ _ . _ _ _ . _
! Rev. 2 8/26/88 ' i Page 9.4.2-1 I i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY ITSPONSE PREPAREDNESS EXERCISE i 1988 i ! 9.4.2 PRIMARY CONTAINMENT AIR ACTI%ITY DATA 1 j A. Primary Containment Air _Aetivity Concentri.tions (uci/ce) i Time Isotope Prior to (M15 0615-0630 0630-0645 I-131
- 2.9E-8 4.0E-8 i I-132
- 4.2E-8 5.9E-8 I-133
- 6.6E-8 9.2E-R ,
! I-134
- 5.8E-8 6.14-8 !
1 I-135
- 5.5E-8 7.7E-8 l j !
J Total Iodine
- 2.5E-7 3.5F-7 l
j I-131 Dose
- 5.5E-8 7.7E-8 -
4 Equivalent k 1 Kr.85m
- 3.8E-6 5.3E-G
* {
3 Kr-85 4.8E-7 6.7E-7 r 1 Kr-87
- 5.0E-6 6.9E-6
'l Kr-88
- 9.0E-6 1.?E-5
(
):e-133
- 2.2E-5 3.0E-5 i
- Xe-135m *
- 5. .i E-6 7.7E-6 !
} Xe-135
- 4.6E-6 6.4E-6 j l
! Total Noble
- 5.0E-5 7.0E-5 i Gas '
I a r i l 3 l l i } i l
- Below MDA at specified time.
1 l Note Primary containment sample dose rates pruvided in Section 9.5. , 1905e/20.598 4 1 I e L.. - ~ - . _ . ___; _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _
Rev. 2 i 8/26/88
; Page 9.4.2-2 i
A VERMONT YANKEE NUdLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE j 1988 i } i 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA [ A. Primary Containment Air Activity Concentrations (uci/cc) l
] Time ,
Isotope 0645-0700 0700-0715 0715-0730 l. 9.5E-8 ' 1 I-131 5.4E-8 7.4E-8 I I-132 7.9E-8 1.1E-7 1.4E-7 :
, I-133 1.2E-7 1. '/ E-7 2.2E-7 l t I-134 1.1E-7 1.5E-7 1.9E-7 i I-135 1.0E-7 1.4E-{ _t.8E-7 j 1 Total Todine 4.7E-7 6.4E-7 8.3E-7 ;
1 i I I-131 Dose 1.0E-7 1.4E-7 1.8E-7 ! Equivaleet i i Kr-85m 7.1E-6 9.8E-6 1.3E-5 i 1 Kr-85 8.9E-? 1.2E-6 1.6E-6 I Kr-87 9.3E-6 1.3E-5 1.7E-5 l j Kr-89 1.7E-5 2.3E-5 3.1L-5 l Xe-133 4.0E-5 5.6E-5 7.3E-5 ! Xe-135m 1.0E-5 1.4E-5 1.9E-5 ,
)
Xe-135 8.6E-6 1.2E-5 1.5E-5 : Total Noble 9.4E-5 1.3E-4 1.7E-4 i j Gas i ; 5 l V Note: Primary contalement sample dose rates provided in Section 9.5. i i 1 j 1905e/20.598 l a l 1 .
. = _ _ . ._ _ _ __
s. Rev. 2 ; 8/26/88 Page 9.4.2-3 ' f VERMONT YANKEE NUC1. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1988 l l L r 9.4.2 *RIMARY CONTAINMENT AIR ACTIVITY DATA ! i A. Primary Containment Air Activity Conecntrations (uci/cc), . j r Time i j Isotope 0730-0745 0745-0800 0800-0815 , i i 1 I-131 1.5E 1.03-4 1.0E-3 i
- I-132 2.2E-7 1.5E-4 1.5E-3 , (
; I-133 3.4E-7 2.3E-4 2.3E-3 i I-134 3.0E-7 2.0E-4 2.0E-3 ! ; I-135 2.9E 1.9E-4 1.9E-3 t
- Total Iodine 1.3E-6 8.8E-4 8.8E-3 i i [
I-131 Dose 2.9E-7 1.9E-4 1.9E-3 j Equivalent l l
< .1
] Kr 85m 2.0E-5 2.4E-2 2.4E-1 i , Kr-85 2.0E-6 1.0E-3 1.0E-2 ! Kr-87 2.6E-5 2.2E-2 2.2E-1 ! I Kr-R8 4.7E-5 5.4E-2 5.4E-1 ! } Xe-133 1.1E-4 2.2E-1 2.2E4 I
- Xe-135m 2.9E-5 3.0E-2 3.0E-1 I
< Xe-135 2.4L-5 9.0E-2 9.0E-1 l' 1 .
- Total Noble 2.6E-4 4.4E-1 4.4E+0 '
j Gaa ! I ! I ! I i l i
- l j Notet Primary containment sample dose rates provided in Section 9.5.
i
}
1905e/20.598 l 1 ! l I l 4 I l i
i E a
- Rev. 2
- 8/26/88 !
l Page 9.454-4 VERMONT YANKEE NUCLEAR POWER STATION .! EMERGENCY RESPONSE PREPAREDNESS EXERCISE I l 1988 i 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA , 1 A. Primary Containment Air Activity Concentrations (uCi/cc) ; l Time t Isotope 0815-0830 0830-0845 0845-0900 l ! I-131 3.5E-3 6.7E-3 1.0E-2 ' , I-132 5.0E-3 9.75-3 1.5E-2
- I-133 7.9E-3 1.5E-2 2.3E-2 ,
I-134 6.9E-3 1.3E-2 2.0Er2 f I-135 6.6E-3 1.3E-2 1.9E-2 [ 2 i ! Total Iodine 3.0E-2 5.8E-2 8.8E-2 l 1 l I-131 Dose 6.6E-3 1.3E-2 1.9E-2 L ) Equivalent i i l
- Kr-85m 5.5E-2 1.6E+0 2.4E+0 i
! Kr-85 3.5E-2 6.9E-2 1.0E-1 l } Kr-87 7.5E-1 1.5E+0 2.2E+0 J Kr-68 1.8E+0 3.6E+0 5.4E+0 l i ) Xe-133 7.5E+0 1.5E+1 2.2E41 Xe-135m 1.0E+0 2.0E+0 3.0E+0 i f Xe-135 3.1E+0 5.9E+0 9.0E+0 f I Total Noblo 1.5E+1 2.9E+1 '. 4E+1 Gas i ! 4 l ] i i 1
- i. !
- Notet Primary containment sample dose rates provided in Section 9.5.
)
l ! l 190$e/ia MA 1 i : l I ! l i . l
d 1 Rev. 2 8/26/88 [) Page 9.4.2-5 v , VERNOW YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 l 1 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA j A. Primary Containment Air Activity Concentrations (uCi/ec) l Time i Isotope 0900-0930 0930-1000 1000-1015 I-131 1.4E-2 1.7E-2 2.1E-2 4 I-132 2.0E-2 2.5E-2 3.1E-2 I-133 3.1E-2 4.0E-2 4.9E-2 ! I-134 2.7E-2 3.5E-2 4.3E-2 I-135 2.6E-2 3.3E-2 4.1E-2 Total Iodine 1.2E-1 1.5E-1 1.8E-1 I-131 Dose 2.6E-2 3.3E-2 4.1E-2 Equivalent l i Kr-85m 3.2E+0 5.5E*0 6.9E+0 Kr-85 1.4E-1 6.9E-1 8.7E-1 Kr-87 3.0E+0 7.2E*0 9.1E+0 Kr-88 7.3E+0 1.3E+1 1.7E+1 I Xe-133 3.0E+1 3.1E+1 4.0E+1 ? Xe-135m 4.1E+0 8. 0 E' O 1.0E+1 j Xe-135 1.2E+1 6.6E*0 8.4Ee0 i Total Noble 5.9E+1 7.3E+1 9.2E+1 Gas ] i j i Note: Primary containment samp1w dose rates provided in Section 9.5. I P 1905e/20.598 J 6
. - _ _ _ =. . -
Rev. 2 i 8/26/88 I Page 9.4.2-6 i VERMONT YANKEE NUCI. EAR POWER STATION EMERGENCY RESPONSE PREPARELNESS EXERCISE 1988 l ] 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA l l A. .' imary Containment Air Activity Concentrations (uCi/ce) i Time Isotope 1015-1030 1030-1415 I-131 5.1E-2 6.2E-2 l I-132 7.4E-2 9.1E-2 i I-133 1.2E-1 1.5E-1 j I-134 1.0E-1 1.3E-1 I-135 9.7E-2 1.2E-1 , Total Iodine 6.4E-1 5.5E-1 i I-131 Dose 9.7E-2 1.3E-1 Equivalent i i Kr-85m 1.2E+1 1.4E+1 j Kr-85 5.2E-1 6.3E-1 . i Kr-87 1.1E+1 1.3E+1 ; ) Kr-88 2.7E+1 3.3E+1 t 4 Xe-133 1.1E+2 1.4E+2 ! ! Xe-135m 1.5E+1 1.8E+1 Xe-135 4.5E+1 5.5E+1 . J Total Noble 2.2E+2 2.7E+2 ; 1 Gas j l > t I I ) ( ) Notes Primary containment sample dose rates provided in Section 9.5. l I : 1 1 l 1905e/20.598 i
. _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ . . . _ _ _ _ _ __ _ _ _ . _ _ _ _.___ _.__.._- _ _ . . . . _ . _ _ _ . . _ . _ _ _ _ _
t 1 1 1 i f l' ! ) ) ) I I i
- l l i
i 1 1 1 VERMONT YANKEE NUCLEAR POWER STATION ! i EMERGENCY RESPONSE PREPAREDNESS EXERCISE , o 1988 i t .'i
}
l :
,I l 1 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA l i
i : i ! l ! t l i i 4 t 1 , i s i I I l k l J l l 1 i i l I i 1905e/20.598 I 4 ) l l i l l i_. . . _ _ _ - _ . _ , - . . . - - - - . - - . . . _ ___ .. . . . _,
Rev. 1 8/15/88 (} V Page 9.4.3-1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONFE PREPAREDNESS EXERCISE 1988 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA f A. Reactor Building Air Activity Concentrations (uCi/ce)(1) ! Sample Type Time (2) Gross Particulate (3) 2.0E-10 to 1.0E-9 Gross Iodine (3) <1E-10 Gross Noble Gas (3) <1E-10 Notes (1) Activity concentrations (uci/ce) listed is for all Reactor Building elevations. (2) Time period is for the entire exercise. () (3) If air samples are analyzed, it will be assumed that the gamma isotopic results will show all radionuclides below the MDA of the multi-channel analyzer. Also RM-14/HP-210 survey of the air samples (filter or cartridge) will show no counts above background. < I r i
),905e/20.598 l
i
t t l l 4 i i l t i i
)
1 , ! VERMONT YANKEE NUCLEAR POWER STATION j 1 EMERGENCY RESPONSE PREPAREDNESS EXERCISE I i i 1988 i 1 I 4 , J 9.5 RADIOLOGICAL SAMPLE DOSE RATES l 4 i ) , I i 1 i I I ! l ! ! l t I i 1 1 J i. I l f 1912e/20.603 4 i J
\. __ _
I ) I ' Rev. 1 l 8/26/88 i , Page 9.5.1-1 4 O ,
't VERMONT YANKEE NUCLEAR POWER STATION ,
EM'.RGENCY RESPONSE PREPAREDNESS EXERCISE 7 1988 , 9.5.1 Reactor Coolant Sample Dose Rates !
- A. Gas Samples Unshleided (mR/hr per ee)* Shielded (1 in. lead in mR/hr per cc)*
j Hat Contact 1 ft Contact 1ft ! ! [ 0615-0700 1.8E-3 1.3E-5 2.3E-5 1.6E-7 ] j 0700-0745 7.5E-3 5.2E-5 9.4E-5 6.5E-7 0745-0815 8.3E+2 5. 8 E+ 0 1.0E+1 7.2E-2 0815-0900 7.5E+2 5.2E+0 9.4E+0 6.5E-2 0900-0915 6.6E+2 4.6EtC 8.3E+0 5.8E-2 0915-0930 6.0E+2 4.2E+0 7.6E+0 5.3E-2 l 0930-1015 2.7E+2 1.9Et0 3.4E*0 2.4E-2 1015-1030 3.5E-1 2.4E-3 4.1E-3 3.0E-5 f i 1030-1415 1.5E-2 1.0E-4 1.9E-5 1.3E-6 [ > i B. Liquid (Iodine) { 0615-0700 1.0E-1 7.0E-4 1.3E-3 8.7E-6 0700-0715 4.0E-1 2.8E-3 5.0E-3 3.4E-5 l 0715-4 745 1.3E0 9.0E .1 1.6E-2 1.1E-4 i ! 0745-0815 2.0E+2 1.4E0 2.5E0 1.)E-2 1 j 0815-0930 1.6t+2 1.1E0 2.0E0 1.4E-2
'0930-1030 8.6t+1 5.9E-1 1.1F0 't.6E-3 !
) 1030-1415 7.5E+1 5.2E-1 9.4E-1 6.5E-3 l I l 4 !
!
- Note Values must be multiplied by the samole volume in cubic centimeters
! for gas samples and milliliters for liquid samples to obtain the l sample dose rata in mR/hr.
i 1912e/20.603 a
Rev. 1 8/26/88 2 Page 9.5.2-1 f' O VERMONT YANKEE NUCLEAR POWER STATION , EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988 ] 9.5.2 Primary Contain.nent Sample Dose Rates 1 I A. Cas Samples Unshielded (mR/hr per ee)* Shielded (1 in. lead in mR/hr per ec)* Time Contact ift Contact ift 0615-0700 2.0E-5 1.4E-7 2.5E-7 1.8E-9 ! 0700-0730 4.3E-5 3.0E-7 5.4E-7 3.8E-9 730-0745 7.5E-5 5.2E-7 9.4E-7 6.5E-9 l I ] 0745-0800 1.3E-1 8.8E-4 1.6E-3 1.1E-5 0800-0815 1.3E0 8.8E-3 1.6E-2 1.1E-4
- 0815-0845 6.4E0 4.4E-2 7.9E-2 5.5E-4 0845-0930 1.5E+1 1.0E-1 1.9E-1 1.3E-3 0930-1000 2.1E+1 1.5E-1 2.6E-1 1.8E-3 i
) 1000-1015 2.6E+1 1.8E-1 3.3E-1 2.3E-3 l i l 1015-1415 7.7E+1 5.4E-1 9.7E-1 6.7E-3 i B. Todine < j 0615-0700 2. M-7 1.9E-9 3.4E-9 2.4E-11 0700-0730 5.8E-7 4.QE-9 7.tt-9 5.0E-11 ! l 0730-0745 1.0E-6 7.0E-9 1.3E-8 8.8E-11 ! 0745-0800 6.8E-4 4.8E-6 8.6E-6 5.9E-8 i ' i 0800-0815 6.8E-3 4.8E-5 8.6E-5 5.9E-7 i i a 0815-0845 2.5E-2 1.7E-4 3.1E-4 2.2E-6 C845-0930 6.SE-2 6.5E-4 1.2E-3 8.1E-6 i t i 0930-1000 1.2E-1 8.1E-4 1.5E-3 1.05 5 ) 1000-1015 1.4E-1 9.7E-4 1.7E-3 1.2E-5. l 1015-1930 3.4E-1 2.4E-3 4.3E-3 3.0E-5 : j 1030-1415 4.2E-1 3.0E-3 5.3E-3 3.7E-5 l O
- Note Values must be multiplied by the sample volu=e in cubic centimeters to
{ i obtain the sample dose ra?e in mR/hr. l 1912e/20.603 , 1 ) i___ ___-___ _ __-____.-_ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l I ! 1 i l ! I i , i i i
- ) VERMONT YANKEE hTCLEAR POWER STATION l l
EMERGENCY RESPONSE PREPAREDNESS EXERCISE i ) 1988 i f i k .i 9.6 PLANT VENT STACK RELEASE DATA ! i i f c i i I ,l 1 I l l 4' .! 1 i i 4 !
+ !
1987e/12.570 4 1 i J I i t i _ . . - ,-~.---..-_.___._._..,_,m, _ , _ _ , , , _ , , . . - , . _ , , , , , , _ _ _ _ _ _,,_,_r,_ _ . . ,. ,_. , _ _ .
Rev. 0 , 8/11/88 Page 9.6-1 VERMONT YANKEE hTCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1988
) 9.6 PLANT VENT STACK RELEASE DATA ,
Plant Vent Stack Activity Release Concentrations (uCi/ce) Sample Tyn Time (l) Gross Noble Gag (2) <1.0E-6 l Gross Iodine'D 2.9E-12 Gross Particc'. ate (2) <1.0E-12 1 1 i i i 1
.1
) ] i i l l l 1 i 1 l NOTES:
- i
; (1) Time period is for the entire exercise. i.
1 (2) If plant vent stack samples are analyzed, it will be assutoed that the I , gama isotopic results will show all radionuclides below the MDA of the multichannel analyzer. Also. RM-14/HP-210 survey of the stack filter or l a cartridge will show no counts above background. I 1987e/12.570 i l 1
l . l I I 1 i t' i I l
' i k
i I l l l l l > l . t j VERMONT YANKEE NUCLEAR POWER STATION f f i 4 EMERGENCY RESPONSE PREPAREDNESS EXERCISE f 1 l 19SS 1 i 10.0 ' METEOROLOGICAL DATA l ! 9 I
)
j j f 1 i 1 I I l l I i I O 1909e/3.214
i e 1 i i l ' VERMONT YAhTEi; hTCLEAR POWER STATION E!1ERCE'!CY RES*2E PREFAREDNESS EXERCISE ' 1953 1 10.1 ON-S'ITE METEOROLOGICAL DATA I l l I i i l J i i IL . } , I 4 1 i i i l 1909e/3.214 1 e
.- - - - - - - ,,y . - -- .- .- ,.e .. - -
-----.---_.---pn a. ,n_ . , , , .- - , . - - , - - . ~ -.~, , . _ , , , . , ,en- -- +,_ n -s
~
j ! i Revision 2 ' I 6/20/88 Page 10.1-1 VERMONT YANKEE NUCLEAR POWER STATION l RtERGENCY RESPONSE PREPAREDNESS EXERCISE
- 1988 I
i 10.1 ON-SITE METEOROLOGICAL DATA i Time ! 06:00-07tJO ! ! 06:00 96,21), 96t30 06:45 07:00 07:15 07:30 I LOWSAV AVG LOWER SPEED MPH 5.2 6.5 6.9 7.9 7.6 7.8 9.7 ' UPWSAV AVG UPPER SPEED MPH 9.1 9.3 10.2 11.4 11.8 11.5 12.5 ) LOWDAV AVG LOWER DIR DEGS 356 358 6 8 15 12 4 j 14WDSD AVG LOWER DIR SIGMA 13 13 11 15 14 15 11 i UPWPAV AVG UPPER DIR DEGS 359 3 5 8 11 11 5 ' } 6 7 7 8 9 10 7 I UPWDSD AVG UPPER DIR SIGMA ! LOTTAV AVG LOWER TEMP DEGS (F) 60.3 60.6 61.1 61.7 62.2 62.8 63.2 l l 14DTAV AVG LOWER DELTA T DEGS (F) -0.8 -1 -1.1 -1.2 -1.3 -1.3 -1.4 l j UPDTAV AVG UPPER DELTA T DEGS (F) -1.1 -1.3 -1.3 -1.4 -1.5 -1.6 -1.6 SOLRAV AVG SOLAR RAD LGGS 0.18 0.25 0.33 0.4 0.47 0.54 0.62 RAINTO 15 MIN RAINFAIL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 t i !O 07:45-09:15 Time j i I ] , I 07:45 08:00 08:15 08:30 08:45 99100 09:15 1 [ < r 14WSAV AVG LOWER SPEED MPH 7.8 7.1 7.9 7.9 8.3 9.1 10.1 i ! UPWSAV AVG UPPER SPEED MP)f 11.3 9.4 11.7 11.7 11.4 13.7 14.3 [ , LOWDAV AVG LOWER DIR DEGS 356 35R 345 355 2 359 359 l LOWDSD AVG LO4Elt DIR SIGMA 16 16 15 16 15 13 14
] ,
- UPWDAV AVC UNE'i D!R DEGS 357 357 351 356 0 357 359 l UPh"$D AVG UPPER DIR SIGMA 6 9 7 10 10 6 6 t th!TAV AVG LOWER TEMP DEGS (F) 63.9 64.4 65.4 60 66.6 66.8 67 (
10DTAV AVG LOWER DELTA T DEGS (F) -1.8 -1.7 -2.1 -2 -2 -2 -2 ' UFDTAV AVG UPIER DELTA T DEGS (F) -2 -1.9 -2.A -2.5 -2.3 -2.4 -2.3 i j SOLRAV AVG SOLAR RAD lANCS 0.69 0.75 0.82 0.88 0.95 1 1.02 l RAINTO 15 MIM AA!NTALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 i i i i 4 4 09e/3.214 , { s i
- I 4
j d twvision 2 ; S/20/88 j PaSe 10.1-2 1 I VERMONT YANKEE NUCLEAR POW'JR STATION : j EMERGENCY RESPONSE PREPAREDNESS EXEP.CISE 1988 i 4 i l ! ) 10.1 ON-SITE METEOROLOGICAL DATA 'l ' 1 3 09:30-11:30 Time - l ) l 09:30 09:45 10t00 10:15 10:30 } 0_: 45, 11:00 }_},t_} 5 11:?C l 1 l ECWSAV AVG L0bTk SPEFD MP!' 10.7 9.9 9.4 8.7 9.5 8.7 8.8 9.0 7. : ]' UPWSAV AVG UPPER SPEYD MPH 14.6 14.9 13.3 11.5 12.1 14.2 13.1 12.3 8.S ! ' LOWDAV AVG LOWER DIR DEGS 360 359 358 13 9 352 355 19 7 l LOWDSD AVG LOWER DIR SIGMA 12 15 15 18 15 20 21 21 29 l ) UPWDAV AVG UPPER DIR DEGS 3 359 357 8 10 352 358 15 9 : ! UPWDSD AVG UPPER DIR SIGMA 6 7 7 19 15 9 14 14 25 l I LOTTAV AVG LOWER TEMP DEGS (F) 67.3 68 68.9 69.2 69.1 70 70.2 70 70.7 6 l LODTAV AVG LOWER DELTA T DEGS (F) -1.8 -2 -2.3 -2 -1.8 -2.5 -2.4 -2.1 -2.1 l j UPDTAV AVG UPPER DELTA T DEGS (F) -2.2 -2.4 -2.6 -2.4 ~2.1 -2.8 -2.7 -2.4 -2.4 l ' l SOLRAV AVG S0!N. RAD IANGS 1.04 1.12 1.17 1.15 1.19 1.26 1.3 1.32 1.33 RAINTO 15 MIN RAINFALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 , f
- O 11:45-13:30 T!ne f '
I 11.45 12:00 12:15 12:30 12:45 13:00 13:15 13:30 l LOWSAV AVG LOWER SPEED MPH 6.9 9.3 7.1 7.3 6.7 7.1 7.3 6.3 ; i UPWSAV AVG UPPER SPEED MPH 9.8 11.9 10.3 10.1 8.9 9.1 8.7 8.? l i LOWDAV AVG LOWER DIR DEGS 358 27 12 12 11 19 27 27 : 1 14WDSD AVG LOWER DIR $1GMA 20 20 19 22 23 25 18 22 i LPWDAV AVG UPPER DIR DEGS 2 23 5 8 18 20 20 32 . .l UPWDSD AVG UPPER DIR S!CMA 14 10 14 10 13 15 21- 21 l 14TTAV AVG LOWER TEMP DEGS (F) 71.3 71.4 71.9 72.5 72.9 72.9 73.* 72.9 [* l LODTAV AVG LOWER DELTA T DEGS (F) -2.3 -2.1 -2.2 -2.1 -2.1 -2 -1.8 -1.6 t'?PW .'.VG i,TFZn DELTA T DEGS (T) -2.5 -2,3 -2.5 -2.5 -2.3 -2.1 -1.9 -1.8 i i 50!JLAV AVG $01AR RAD 1.ANGS 1.35 1.36 1.29 1.34 1.4 1.24 1.12 1.03 j RAINTO 15 MIN ILAINTALL INCHES 0.00 0.00 0.00 0.00 0.00 0.00 0.07 0.11 , ! i a : i : i i ! i l C c9 /3.21t . f t i
--..-----...-....-m..- ., . . - , . - .--,--..-6. .
1 O l l l VERMONT YANKEE hTCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE , l' 1988
'.0. 2 GENERAL AREA WS FORECASTS O \
i I i 9 !O 1909e/3.214 l i l l l i
I t I l
,l l
I Revision 1 ! S/27/SS f l9 l Page 10.?.-1 THIS IS A DRILL ' 4 i l 10.2 CENERAL AREA NWS FORECASTS 6100-12:00 - General Area Forecast Mostly sunny with northerly winds today. High teaiperatures in tne mid 70's, with a slight chance for an afternoon' shower. 1 I As a strong high pressure moves further east, strong winds will give way i to light variable conditions. l l \ l G l
\
l l I I , I l - ! ) l l l l , i t ! THIS IS A DRILL 1909e/3.214 l l 1
1 i i f ( Revision 1 ; 5/27/88 f j Page 10.2-2 i j l t, i I THIS IS A DRILL ! J i i 10.2 CENERAL AREA NWS FORECASTS } l i ! 12:00-18:00 - General Area Forecast i i I J Mostly clear this afternoon and tonight. Low temperature thit evening in the high 50's, winds northerly 5-10 mph. Tomorrow sunny, clear, high l near 80. l t 1 l 1 ! 1 , i, I t, , i j l l l 1 10 j
- I 1
THIS IS A DRILL l ] G 1909e/3.214
i l t O ! l 1 VERMONT YA'3EE .'NCLEAR F0WER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE i ! 1988 10.3 NATIONAL k'EATHER SERVICE SURFACE MAPS O l I h i t I l i l O 1909s/3.214 i l i l r i
Rev. 0 6/6/53 10.3-1 im. m.. I w., . - - _ . - n m 'i. A%
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1 NRC Briefing Agenda 1988 Vermont Yankee l Emergency Preparedness Graded Exercise 3: August 1988 l h
. Introduction . .. .. .. .
........... . ..... . ... . Stan Jefferson
. Schedule .... . . . . . . . . . . . . . . Ed Porter ;
j . Organization / Layout -... . ........ ......... . .. . Ed Porter
. Exercise Manual Review ....... ........ .. .... . Ed Salomon
- . Questions / Errata .. .. ...-.. .. . . . . .... . Ed Porter J
i i . ERF Tour (s) . .. . . .. .. . . . . .. .. .. .. . . Ed Porter 1 1 l j l l
r 4 Vermont Yankee Nuclear Power Corporation Emergency Preparedness Organization & Facilities 1988 Graded Exercise 31 August 1983 Contents EI ercise Org a niz ation ............ ... .. . ... . .. .... ..... .... ..... ...... 1 Contraller/Ob seryer Organization .... ...... ........- .............. .... 3 On Shitt Emergency Organization ....... ... .... .. _...__.. -. .. 4 Emergency Management Organ!zation . .. ........ .......-....._.... 5 Technical Support Center (TSC) ........ . . . .. .... ....... .. .. 6 Operation: Support Center (OSC) -..........-. . ..... ..... . .. .. 7 l Emergency Operations Facility (E0F) ... .. .... .. .. ... .... . 8 1 YNSD Emergency Response Organization .... .. ........... .... 9 ' ERF Layouts: T S C .. . ..... ..............-..... ..-.......... ......... ....-.... ......... 10- 1 OSC......_.........-.......-...........................II EOF.._........ .. .. ............. .. . _. .... 12 News Meuia Center: Or g aniz a t ion . ....... ... . .... ........ . ... -.... ... I3 Facility L ayo u t s .... . .. .. .. ...-.. .. . .- ..._ .. ... 14
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_2-1955 Exercias Organization SuePMT MouP i (PSG) i 3CENAMl0 DEVELOPMENT i t. () i CONTROLLER l OBSERVER saour (COG) ' l i l I I PIannIng & Suppert orcup Functiens:' r plannin, a so,,,t uso,, I. Maintala schedule Personnel *. 2. Maintain punCA list
- 4. Interface wita ef t-site groups j Sten Jefforsen (SM for eMerClse orep/ Conduct
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- 11. ConeuCt Critleves
{ I l ) ' 4 SCENARIO DEVELOPMENT TEAM (SDT) 1 j MEMBERS /3UPPORT i RESPONSIBILITIES
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CAMER00f 1. DETEM!NE SCENARIO j SALOMost 2. DETEMINE RAD DATA
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PORTER 4. DETEMIME OPERATIONAL DATA ' ' SURDA 5. DEVELOP MIN!-SCENARIOS 3CENE! DER 6. TEST ON 3!MULATOR } DEAL 7. SERVE AS OBSER/ CONTROLLERS
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ERV!N 8. DETEMINE PLANT ACTIVITIES STAFFORD WILDER NWMD i CRESLEY l SLAUENWITE TUTTLk j KRIDER 1 3R0= PLANT I i l
ConTSOLLER/caSERTER OaGANIZATIon GRADED EXESCISE AEGWST 31, 1988 EXESCISE COORCINATOR S. J. JEFFESSOE SIN?j LATOR CA PLANT Ca TSC OSC EOF eeeeeeeee... ......... San SEC BMC . ESC
.e eseeeeeeeeee seeeeeeeeeee eeeeeeeeeeee seeeeeeeeeee seeeeeeeeeee ....... .... eeeeeeeeeeee.
COeTSOLLER CostacLLEB COSTROLLES COSTaOLLES ComTSOLLES COSTaOLLER COerTSOLLE R COsTaOLLES COSTaOLLER Chesley $ 1 amen wt & t e sawsburst Deal Salones Foster Sese Sahares Wojaas OSSEnvEa5 OSSERVESS OSSEaWERS OSSERVESS GestaTEa5 OSSERVERS OSSEtvERS OsStaVEa3 OBSEavERS Tuttle some LeClair Mc Da w s t t Traegde Arms Gileam Lorebswo None Gr& der farmesser Camerem mergen saada McArdle Erw&m Cardatells Thomas Stafford , (Sta Data) usader i i sabbi tE j
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