ML20081E034
| ML20081E034 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/18/1990 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20081E033 | List: |
| References | |
| NUDOCS 9008060013 | |
| Download: ML20081E034 (286) | |
Text
,
p~ -VERMONT YANKEE NUCLEAR POWER STATION-
- EMERGENCY RESPONSE PREPAREDNESS EXERCISE- -
1990
\
4
\
50
/ ,
s 9 o -
EXERCISE MANUAL
- v. ,
1 J
EXERCISE MATERIAL p; i ,
1
%! ,.. ~
1 9008060013 900517 ~f PDR ADOCK 05000271 / '
F PDC l i
e.
7 i-R;v. 0 n'" ) , VERMONT YANKEE NUOLEAR POWER STATION i
EMERGENCY RESPONSE PREPAREDNESS EXERCISE .
1990 i
TABLE OF CONTENTS Saction Page j
1.0 INTRODUCTION
1.1 Exercise Schedule............................................ 1.1-1 !
1.2 ' Participating Centers / Agencies...............................- 1.2-1 !
1.3 Definitions.................................................. 1.3-1 j 1.4 References................................................... 1.4-1 1
2.0 EXERCISE OBJECTIVES AND EXTENT OF PLAY............................ 2.0-1 ;
1 3.0 EXERCISE GUIDELINES AND SCOPE 3.1 Guidelines................................................... 3.1-1 l 3.2- Player Instructions and Ground Ru1es......................... 3.2-1 ;
3.3 P ro c e d ur e Ex e c u t i on Li s t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.3-1 -
l i
4.0 CONTROLLER /0BSERVER INFORMATION l 9
4.1 Controller / Observer Assignments.............................. 4.1-1 4.2 Controller / Observer Exercise Guidance. . . . . . . . . . . . . . . . . . . . . . . . 4.2-1 4.3 Controller / Observer Evaluation Criteria...................... 4.3-1 '
5.0 EXERCISE SCENARIO 5.1 ~ Initial Conditions........................................... 5.1-1 5.2 Narrative Summary............................................ 5.2-1.
5.3 Scenario Time Line........................................... 5.3-1 5.4 Detailed Sequence of Events.................................. 5.4 6.0 EXERCISE MESSAGES 6.1 Command Cards................................................ 6.1-1 6.2' Message Cards................................................- 6.2-1 7.0 -STATION EVENT DATA 7.1 Events Summary............................................... 7.1-1 7.2 Event Mini-Scenarios......................................... 7.2.1-1 8.0 OPERATIONAL DATA.................................................. 8.0-1 i
2143e
< R5v.0- "
VERMONT YANKEE NUCLEAR POWER STATION
.("
\- EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 TABLE OF CONTENTS (Continued) 9.0 RADIOLOGICAL DATA 9.1 Area Radiation Monitors...................................... 9.1-1 9.2 Process Radiation Monitors................................... 9.2-1 9.3 In-P l an t Ra d i a t i on Lev e 1 s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9.3-1 9.4 Plant Chemistry Data......................................... 9.4-1 9.5 Radiological Sample Dose Rates............................... 9.5.1-1 9.6 Plant Vent Stack Release Data................................ 9.6-1 9.7 Off-Site Monitoring Maps and Data............................ 9.7-1 10.0 METEOROLOGICAL DATA-10.1 On-Site Meteorological Data.................................. 10.1-1 10.2 General Area National Weather Service Forecas ts. . . . . . . . . . . . . . 10.2-1 10.3 National Weather Service Surface Maps........................ 10.3-1 7 4% [ b y.. .i I
'l ;
-lii-7 Ni/' 2143e
t d
i
. ~ ,)
.'- 4 i
) )
.c . ,
VERMONT YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990
.i
',1 i
+
1.0 INTRODUCTIQR lOlij 1
l
(. .' l l
l
\
l l
l Q 2146e-l l
+
. 1 Il
t
- 14'%.
.i f si
'(;
'i
)
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 i
i 1.1 EXERCISE SCHEDULE i i
t k
A*
t i
2146e
.{O'i.'
U.
1f',
siV
L J R:v. O Page 1.1-1 -r
.Cf
~x '
VERMONT YANKEE NUCLEAR POWER STATION s
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 1.1 EKEILCISE SCHEDULE A. Controller / Observer Briefing Date: July 17, 1990 Time: 9:00 a.m.
Location: - Vermont Yankee Corporate Office (Brattleboro, Vermont)
.i
=
Purpose:
. Controller / Observer Briefing.on Scenario and Assignments
.,-~
.. / Attendees: Vermont Yankee and Yankee Atomic Controllers / Observers B. Controller /Obserygr Plant Tour Date: July 17, 1990 4
Time:_ As necessary (contact Lead Controller)
Location: Emergency Response Facilities and In-Station Areas
Purpose:
- Familiarize Controllers / Observers with Af fected Areas
- Attendees: Controllers / Observers t
,( -
.7IY 2146e
.(&
l L !
L- Rov. 0 '
Page 1.1-2 f-~.,j x.! C. NRC Briefine .
i Date: July 17, 1990 \
Time: To be announced Location: To be announced
Purpose:
NRC Briefing and Review of Exercise Scenario Attendees: NRC Evaluators D. Exercise Date: July 18, 1990 :
r~, . Time: To be announced k,, ,
Location: Vermont Yankee Emergency Res'ponse Centers Designated States Emergency Response Centers
Purpose:
Emergency Response Preparedness Exercise Attendees: Vermont Yankee Emergency Response Organization, NRC Region I Incident Response Team, Select State
{
(Vermont, New Hampshire, and Massachusetts) Emergency Response Organizations, Controllers / Observers, NRC Evaluators, and Yankee Atomic Engineering Support !
Center Staff j t'lN 2146e h
4 Rovo O Page 1.1-3 fb=
E. Elticise Debriefing -
i Date: Day of Exercise t Time: To be announced during or immediately following exercise Location: Location to be designated by the Emergency Response Facility Controller ,
t Purposes Players and Controller / Observer DebriefinF 1
Attendees: Controllers / Observers, Key Participants i
F. Controller Debriefing a- Date After Exercise Player Debriefing
(
Time: To be announced Location: To be announced 3
-Purpose Exercise Debriefing :
Attendees: Exercise Coordinator ahd Controllers
- G. Exercise critlaue Date
- July 19, 1990 Time: 1:00 p.m. ;
n-I
' "l i Location: Vermont Yankee Corporate Office (Brattleboro, Vermont) e l
5
- ,
- 4
s v.sm
.t ;
,1 R2". O Page 1.1-4 *
.;k i.
7c
Purpose:
Utility Self-Critique /NRC Preliminary Findings -
i
. Attendees: Vermont-Yankee Management, NRC Evaluators, Exercise .
Ovntrollers (Observers'need not attend), and Vermont Yankee Key Participants -
- t t
t
'.i l.
f 2146e
.4 ;
' \;;
i i
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS'EXET.CISE i 1990 t
'1.2 PARTICIPATING CENTERS /AGENO[ES i
.4 r 2147e
\;%' /.>
s.
R2v. 0 Page 1.2-1 4 , tT-VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 1.2 FARTICIPATING CENTERS /ACENCIES VEBt1QNT YANKEE N11CLEAIL10HER CORPORATION Vermont Yankee Nuclear Power Stations o Control Room (notification and communication functions only)
I Technical Support Center-(2nd floor of Administration Building) o' l
o Operations Support Center (1st floor of Administration Building) ;
J
. ,q o Energy Information Center (Governor Hunt House)
Vermont Yankee Training Center
.[
o Simulator Room (Control Room functions - let floor of Training Center) i
-o Emergency Operations Facility / Recovery Center (1st floor of Training Center)
News Media Center (Vermont Yankee Nuclear Power Corporation Offices -
Brattleboro, Vermont).
IANKEE AIQtilC ELECTRIC COMPANY Yankee Atomic Corporate Headquarters:
, o Engineering Support Center (Bolton, Massachusetts) 2147e k.l h
Rsv. O Page 1.2-2 .
.x e
HUCLEAR REGULATORY COMMISSION ,
o' NRC Region I' Incident Response Base Team (King of Prussia, Pennsylvania) o NRC Region I Incident Response Site Team (Vermont Yankee Emergency i Response Facilities) i i
STATE OF' VERMONT Vermont Emergency Management Agency (State Response Agencies):
o Emergency Operations Facility / Recovery Center (State representatives located in the State Room) o Emergency Operations Center (Waterbury, Vermont)
,e s
\
STATE OF NEW HAMPSHIRE I
New Hampshire Emergency Management Agency (State Response Agencies):
oo Emergency Operations Facility / Recovery Center (State representatives located in the State Room) o Emergency Op'erations Center (Concord, New Hampshire) i
-i COMMONWEALTH OF MASSACHUSETTS
~
Massachusetts Civil Defense Agency-(State Response Agencies): !
o Emergency Operations Facility / Recovery Center (State representatives located in the State Room) l o Emergency Operations Center (Framingham, Massachusetts)
I 2147e
-l 1
l
(-
t i
I 4
VERMONT YANKEE NUCLEAR POWER STATION' EMERGENCY RESPONSE FREPAREDNESS EXERCISE 1990 i
' 1.3. MEREVIATIONS AND DEFINITIONS s
[ :
1 e i,' ' . . 2144e
]
l l
6
R:v. O, i Page 1.3-1 h' VERMONT YANKEE NUCLEAR POWER STATION ,
EMERCENCY RESPONSE PREPAREDNESS EXERCISE -
1990 ,
1.3 ABBREVIATIONS AND DEFINITIONS ..
A. Abbreviations i
o ACR0 -
Alternate Control Room Operator ;
o- AO - Auxiliary Operator o A00 -
Advanced Off-Gas System o APRM- 4 Average Power Range Monitor
-o ARM -
Area Radiation Monitor o CR -
Control Room / Control Rod o CRD -
Control Rod Drive .
o- CRP -
Control Room Panel o CS -
Core Spray o CTP, '
Core Thermal Power i
o DC0 -
DutyEand Call Officer o DW - -
Drywell l o_ EAL -
Emergency Action Level l
o ECCS -
Emergency Core Cooling System o ENS -
Emergency Notification System i
o EOC -
Emergency Operations Center l
- 1 o EOF -
Emergency Operations Facility o EPR -
Electric Pressure Regulator 1
o EPZ -
Emergency Planning Zone l
o ESC -
Engineering Support Center l o FEMA -
Federal Emergency Management Agency h o W -
Feedwater 2144e i
,7
- i j .
r
!l@ j Rsv. 0 'i
- j, .
Page 1.3-2 1
-$4 o' HPCI - High' Pressure Coolant. Injection o HPN - Health Physics Network )
I o- HRNG - High Range Noble Gas J
'p, ,
o I&C - Instrumentation and Control o LPCI - Low Pressure Coolant Injection !
o MCC - Motor Control Center o MPR; - Mechanical Pressure Regulator k
o MSIV .- Main Steam Isolation Valve o MSL ~- Main Steam Line o NAS - Nuclear Alert System 3 o NG -
Noble Gases
'o NRC -- Nuclear Regulatory Commission o NWS -
National Weather Service
[-
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 I
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.
\
2144e
Rsv. O Page 1.3-3
, >~ , . . .
L o- RPS - Reactor Protection System o RR - Reactor Recirculation System 1
o RRU - Reactor Recirculation Unit o RV - Relief Valve o, RWCU - Reactor Water Clean-Up
,, 'o Rx - Reactor o SAE - Site Area Emergency o SBGTS - Standby Gas Treatment System o SJAE - Steam Jet Air Ejector' o' SRM - Site Recovery Manager / Source Range Monitor o SRV - Safety Relief Valve o TAG - Technical Administrative Guideline
,. o TS - Technical Specification .
o TSC - Technical Support Center o UE -
Unusual' Event o VY - Vermont Yankee 1
o VYNPC -- Vermont Yankee Nuclear Power Corporation 1
o VYNPS ~- Vermont Yankee Nuclear Power Station o WSI -
Weather Services International o YNSD - Yankee Nuclear Services Division. l l
L
~ %, -2144e q(il/
Ls i.
1-
l Rove 0 Page 1.3-4 L (s. .l ~,
B. Definitions
.i o Alert - An emergency classification which is l
' defined as an actual or potential l substantial degradation of the level- l of safety of the plant. I o Controller - A member of an exercise control group. Each Controller may be assigned.to one or more activities or functions for the purpose of keeping the action going according '
I to a scenario, resolving dif ferences, supervising and assisting as needed.
o- Critique. - A meeting of key participants in an exercise, usually held shn:tly after l its conclusion, to identify weaknesses and deficiencies in emergency response capabilities .
o Emergency Action - Specific instrument-readings, system f Levels or event observation and/or
., radiological levels which initiate l
- event classification, notification procedures, protective actions, and/or the mobilization of the emergency response organization.
These are specific threshold readings or observations indicating i system f ailures or abnormalities.
o Emergency Assistance -
General term used to refer to the !
L Personnel radiation monitoring teams, sample >
analysis team, and in-plant search, and rescue teams. j o- Emergency Operations - Areas designated by state / local Center representatives as Emergency Plan assembly areas for their respective stcffs.
o Emergency Operations - An emergency response facility Facility / Recovery (Vermont Yankee Training Center, Center Brattleboro, Vermont) whics evaluates off-site accident consequences and coordinates emergency response and assistance with all off-site agencies.
2144e l
l 6
vn s
R:v. O Page 1.3-5 o Emergency Planning - The areas for which planning is !
recommended to assure that prompt Zones and effective actions can be taken to protect the public in the event of an accident. The two zones are the 10-mile radius
- plume exposure pathway zone and the 50-mile radius ingestion.
exposure pathway zone.
o Engineering Support - A YNSD emergency response facility Center (Yankee Atomic Electric Corporate Headquarters) established to provide additional engineering support to the affected site in plant assessment and recovery operations.
o Exercise - A demonstration of the adequacy of timing and content of emergency implementing procedures, methods, and equipment.
o Full Participation - An exercise,which tests as much of j- 1 Exercise the licensee, state, and local plans as is reasonably achievable without mandatoryfpublic participation.
o General Emergency - An emergency classification which is defined as actual or imminent substantial core degradation or melting with potential for. loss ;
of containment integrity.- 1 o News Media Center - An emergency response facility (VYNPC Corporate Offices, Brattleboro, Vermont) is dedicated to the news media for the purpose of disseminating and coordinating information concerning accident conditions.
All activities conducted within this center will be the responsibility of the Vermont Yankee Nuclear Information
- Director.
2144e L( {
l l
.__ _ . . _ __ . __- . - ~ _ . . _ - _ _ _ _ . _ _ . _ _ . . _ -
R;v. O Page 1.3-6 I o Observer - A member of an exercise control j' group.. Each Observer may be assigned to one or more activities or functions for the purpose of evaluating, recording, and reporting the strengths and weaknesses, and making recommendations for improvement, t
o: Operations Support -
An emergency response facility Center (1st floor Administration Building) established to muster skilled emergency response . !
personnel to perform activities
'in the plant.
o Protective Action -
Those emergency measures taken to ,
effectively mitigate the I consequences of an accident by a minimizin'g the radiological l exposure that would likely occur i if such actions were not .
i undertaken. ;
l
', o Protective Action -
Projected radiological dose (1 Guides values to the public which ;
warrant protective actions -i following an uncontrolled release of radioactive material.
Protective actions would be '
I warranted provided-the reduction in the individual dose is not l offset by excessive risks to j individual safety in implementing l such. action.. j o Scenario -
The hypothetical situation, from l start to finish, in an exercise which is the theme or basis upon-which the-action or play of the
.. exercise unfolds.
l o Site -
That property within the fenced i boundary of Vermont Yankee which ;
is owned by the Vermont Yankee Nuclear Power Corporation.
o Site Area Emergency -
An emergency classification that indicates an event which involves likely or actual major failures L/?; of plant functions needed for the
(,j,/ protection of the public.
2144e i'I
. I t
t Rev. O. I Page 1.3-7. l I o Small-Scale Exercise - An exercise which tests as much ,
of the licensee emergency plan -
and-procedures without participation of state and local government agencies.
o Technical Support - An emergency response facility Center (2nd floor, Administration Building) with the capability,to assess and mitigate the accident using plant parameters and highly qualified technical personnel.
Also, assists in accident recovery operations.-
o Unusual Event - An emergency classification that indicates a potential degradation of plant safety margins which is not likely to affect personnel on-site or the public off-site or result in radioactive releases requiring off-site monitoring.
o Yankee Nuclear Services - A division of Yankee Atomic Division (YNSD) Electric Company. An Engineering -
(.. support organization which q provides emergency response support to Vermont Yankee upon
- request.
l 2144e f/" s.
v i e *
... i (q?h ,,-
i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERf ISE 1990
1.4 REFERENCES
- +Q b
, tA [%,
2145e-
- i i i
t Rev. 0 -l Page 1.4-1 fd '
VERMONT YANKEE NUCLEAR POWER STATION l
4 D1ERGENCY RESPONSE PREPAREDNESS EXERCISE l
1990 l
1.4 REFERENCES
. 1 l
- 1. Vermont Yankee Nuclear Power Station Emergency Plan. Y d
- 2. Vermont Yankee Nuclear Power Station Emergency Plan Implementing I l
Procedures. l l
l
- 3. Vermont Yankee Nuclear Power Station Final Safety Analysis Report -
Vermont' Yankee Nuclear Power Corporation.
- 4. Vermont Yankee Nuclear Power Corporation - Communications Department Emergency Response Plan and Procedures.
e, %,
I# 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. Martink G. F., et al., " Report to the NRC on Guidance for Preparing.
Scenarios for Emergency Preparedness Exercises at Nuclear Generating
' 'ations "' March 1986 USNRC, NUREG/CR-3365.
Daily Weather Maps, National Weather Service, Climate Analysis Center. Washington, DC 20233.
l 2145e
[} .
l =
l.
g- s- A - a,- x -- a - .-
-' 4 (4 .
, . i:
9 4
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAPIDNESS EXERCISE 1990 1
2.0 EXERCISE OBJECTIVES AND EXTENT OF PLAY - VERMONT YANKEE 9
lg 21Se.
l
?
?-
l 1'
.o -:O' C$!~ j ;f -.
Rev. O Page 2.0-1 ;[
VERMONT YANKEE NUCLEAR POWER STATION 1 I!MERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 2.0 Extent of Play A. Accident Assessment -l
- 1. Demonstrate the ability of Control Room . A.1 The scenario events initiated on the simulator personnel to recognize emergency initiating provides the operational and radiological data events and properly classify the condition which allows personnel to demonstrate this ,
in accordance with pre-established objective by implementing Procedure A.P. 3125 emergency action levels. Emergency Plan Classification and Action Level Scheme.
- 2. Demonstrate the ability of'the' Control Room A.2 The scenario will provide technical and TSC staff to coordinate the assessment information to players which will allow them of plant conditions and corrective actions to analyse plant conditions and propose to mitigate accident' conditions. corrective actions.
- 3. Demonstrate i. hat information concerning A.3 Telephone communications links will be plant' conditions can~.be disseminated established by.. communicators between the between the Control Room and TSC in a simulator Control Room and the TSC in order to timely manner. transmit key information'and data.
Controllers / Observers will evaluate the timeliness of information.
2160e
p n ,
F/ :-
+
_j q) .
Rev. O Fage 2.0-2 Estent of Play 6 Demonstrate the ability of the TSC staff to A.4 The scenario provides events that vill enable initiate and coordinate corrective actions the TSC to coordinate in-plant corrective in an efficient and timely ==waer. actions through the use of OSC personnel.
- 5. Demonstrate the ability of appropriate TSC A.5 The scenario includes events which allow for staff te participate with Control Room and discussion between the Control Room, TSC, and the YJi/RC in emergency classification and EOF staff on classification.
EAL discussions.
Demonstrate the ability to asser' data f rom A.6 Scenario events will require Chemistry and 6.
appropriate chemistry samples i- support of Radiation Protection technicians located at the OSC to simulate taking reactor coolant, accident assessment activities i plant containment air, or plant vent stack samples conditions.
to assess plant conditions. Sample results will be provided by observers who accompany the technicians during their sampling activities. (Ofer to Frocedure OF-3530, "Fost-Accident Sampling.")
B. 1801':ficatie e---- Mcation
- 1. Demonstrate that messages are transmitted B.1 Various c - ications links will b in an accurate and timely aro -r and that B.3 established between the emergency response messages are properly logget a.id documented. ~ B.4 facilities in order to transmit information and data. Recordkceping and documentatioJ will be demonstrated in accordance with Procedure OP-3504, "Energency Communications "
Commuunications and transfer of data between facilities will be evaluated for timeliness and coepleteness.
2160e
~
Rev. O Fage 2.0-3 Extent of Flar Demonstrate the capability to notify B.2 Vermont Tankee staff, NRC, and state 2.
federal and state authorities of emergency authorities shall be notified in accordance classifications and significant changes in with established procedures. NRC will be plant status in accordance with established notified by utilizing the NRC ENS red phone.
The State authorities will be notified through procedures.* the Nuclear Alert System (Orange Phone).
- 3. Demonstrate that appropriate status boards are utilized to display pertinent accident information at the various emergency response facilities.
- 4. Demonstrate that adequate emergency coasmanication systems are in place to facilitate transmittal of data between the emergency response facilities and federal and state authorities.
C. Direction and control
- 1. Demonstrate the capability of key emergency C.1 All emergency response facilities have response facility management personnel to designated coordinators who will direct and direct and coordinate their respective coordinate emergency response activities in emergency response activities in an their particular area of responsibility.
efficient and timely manner.
- 2. Demonstrate appropriate coordination of C.2 The Control Room will initially contact the federal and state agencies, providing them activities with federal and state with appropriate information on plant government agencies. conditions and emergency status. This function will pass to the TSC and EOF /RC after the facilities are activated. NRC Region I Incident Response Team (Base and Site) will be
~
participating in the exercise. Commuunications and information flow with the NRC Region I
- Indicates NRC-identified improvement' items from Incident Response Team will be demonstrated.
the 1989 exercise.
2160e
- - . - . - - - . . -__. -.ww
") Q G) 2
.J Rev. O Fage 2.0-4 Estent of Play D. Emergency Resmonse Facilities *
- 1. Demonstrate the ability of station and D.1 Scenario data and exercise events will allow corporate personnel to activate and staff D.2 activation and operation of Vermont Tankee the emergency response facilities in a emergency response facilities. The Simulator timely manner. Control Room, Control Room (communication functions only), TSC, OSC, EOF /RC, News Media
- 2. Demonstrate and test the adequacy and Center and Engineering Sugryrt Center will be effectiveness of emergency response activated in accordance witz. established facilities, operations, and equipment.* procedures. Designated plant and corporate emergency response personnel will participate E. Radiological Rwaosure Control in the exercise.
- 1. Demonstrate the ability to provide adequate E.1 Scenario events will require OSC On-Site radiation protection corstrols for on-site E.2 Assistance Teams to be dispatched to emergency response personnel, such as investigate problems associated with plant
- appropriate personnel dosimetr,s -*sipemt, equipment. Investigation and repair
- and protective clothing. activities in the plant will require implementation of radiation protection
- 2. Demonstrate the ability to monitor and controls which include monitoring and tracking track radiation exposure of on-site of radiation exposure of OSC On-Site emergency response personnel. Assistance Teams. (Refer to Frocedure OF-3507, " Emergency Radiation Exposure F. In-Plant Corrective a W r Actions Control.")
- 1. Demonstrate that on-site assistance teams can be dispatched and deployed in a timely manner. F.1 Scenario events will require OSC on-site i
F.2 assistance teams to be dispatched
~
- 2. Demonstrate the ability of on-site F.3 to investigate problems associated with assistance teams to perform corrective plant equipment. Plant personnel will be p actions on plant equipment during emergency given the opportunity to perform corrective i
conditions. actions associated with d==mged plant equipment. Equipment mockup of the postulated damaged plant equipment will be available for
- Indicates NRC-identified improvement items from plant personnel to perform corrective actions.
the 1989 exercise.
2160e
_ _ _ _ _ - - . _ _ - _ _ _ _ _ - - - - - - _ _ _ _ - _ _ - - - _ - - - - _ - - _ _ _ _ _ _ _ - - - - -' -w wm me
w ~ w %ww-m - o--~v e- r- e"
- j
~
Rev. O Fage 2.0-5 Ex_ tant of Flay
- 3. Demonstrate the ability to provide adequate administrative controls and documentation for necessary repairs of' plant equipment and systems dur?ng an emergency situation. .
C. Radiological Astes. ament
- 1. Demonstrate that radiological assessment G.1 The scenario will provide information on plant personnel at the EOF can obtain .G.2 conditions and in-plant radiological conditions radiological and meteorological data in a G.3 to pisyers which will allow them to evaluate timely manner. G.4 potential off-site radiological consequences.
G.5 The scenario will postulate an off-site
- 2. De mastrate that adequate dose assessment radiological release through the plant vent procedures can be performed to determine stack which will allow players to evaluate off-site radiological consequences. off-site radiological conditions. Players i will implement appropriate sections of !
- 3. Demonstrate the ability to assess potential Frocedures OF-3513 " Evaluation of Off-Site off-site radiological consequences based on- Radiological Conditions" and OF-3511, plant conditions. "Of f-Site Protective Actions Recosamendations."
i 4 Demonstrate the ability to perform timely assessment of off-site radiolotical conditions to support the formulation of j protective action recomumendations for the plume exposure pathway.
- 5. Demonstrate the ability to project the plume trajectory and potentially affected downwind sectors utilizing the computer dose assessment model OPTFAC).
2160e 5
m- n.-nn-. -
, , , . ,e.,-
y y s-- v---.- gw.--- %w ,p , -*e- 1 +
ve-a-w - = W -
-wr *' 'ea- a ' - -eM-- V *-em'*-
Q Q
'~
. i
(:- l ..
Rev. O Fage 2.0-6 Extent of Play
- 6. Demonstrate adequate staffing, equipment G.6 Off-site monitoring teams will be assigned at readiness check, and deployment (if G.7 the OSC. Players will implement appropriate necessary) of off-site monitoring teams. sections of Frocedure OF-3510. "Off-Site and Site Boundary Monitoring."
- 7. Demonstrate the use of appropriate equipment and procedures to perform off-site radiological monitoring. .
H. Protective Action Decision Makinst
- 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 conessential personnel. after plant evacuation and accountability has been comp'leted, all plant personnel and contractors not directly involved in the exercise any be allowed to return to work.
- 2. Demonstrate the adequacy of the protective H.2 Protective action decision making will be action decision making process to make demonstrated in accordance with
- recommendations concerning off-site Procedure OF-3511, "Off-Site Protective !
] radiological consequences.* Actions Recommendations".
j .
j I, Parallel and Other Actions l i
- 1. Test and evaluate the adequacy of methods I.1 Security activities will be implemented in ,
i to establish and maintain access control accordance with established procedures to i and personnel accountability within the control access to the protected area. -
protected area. Assembly of emergency response personnel and evacuation of contractor / visitors will be implemented in order to test personnel accountability within the protected area.
However, after the plant evacuation accountability checks have been completed, contractors and visitors will be exempted froo
- Indicates NRC-identified improvement items additional personnel accountability checks.
from the 1989 exercise.
2160e
~
t- 9 a w~-
~
., ,~ l
.A Rev. O
= Page 2.0-7 Extent of Play
- 2. Demonstrate the licensee's capability for I.2 Exercise critique will be conducted with self ritique 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 Media Center will.be fully activated.
disseminate timely accurate press release J.2 Information on the simulated events occurring to the public and the news media. J.3 at the plant will be gathered, verified, incorporated into a news release, and
- 2. Demonstrate the ability to provide disseminated to key players. Also, after briefings for and to interface with the approval this inr'ornetion will be discussed at puilic l and news media.* the News Media Center.
- 3. Demonstrate the ability to communicate and coordinate news releases between the EOF and the News Media Center.
- 4. Demonstrate the ability to provide rursor J.4 A hot line will be established to provide control. rumor control for questions concerning the simulated accident.
Hols:
The annual radiological monitoring drill
, and semi-annual health physics drill will I
be included as part of the exercise. A
! separate health physics drill will be held to demonstrane the actual sample collection and analysis of in-plant chemistry samples which includes the use of the Post-Accident Sampling System (PASS).
- Indicates NRC-identified improvement items from the 1989 exercise.
2160e i
e
~
-i- c- w -
_ __ _u - _ _ _ _ -_____u_ s-__mm__
,es, VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 3.0 EXEkCISE CUIDELINES AND SCORE ,
(' , ,
t
/8
() 2154e ,
e I
1
(
\
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE !
1990 ,
3.1 EKERCISEJiUIDELINES .
8 f.
9
?
t t
e
.(j 2154.
1 1
l
I' ROvo 0 Page 3.1-1 i
e~.
VERMONT YANKEE NUCLEAR POWER STATIOP EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 3.1 EXERCISE GUIDELINES :
A. Zurpose This package provides guidance for conducting the 1990 VYNPS Emergency Response Preparedness Exercise. It provides the framework for demonstrating emergency response capabilities, conducting the exercise and evaluating response activities.
B. Concepta_of Jaarations and control of the ExtLCist 4
An Exercise Coordinator has been appointed by plant management to oversee all exercise activities. The Exercise Coordinator is responsible for approving the objectives and developing the scenario time sequence. The Exercise Coordinator is also responsible for the selection and training of the Controllers / Observers required to conduct and evaluate the exercise.
Vermont Yankee will supply of ficial Controllers and Observers for each location where an emergency response action is being demonstrated. Prior to the exercise, the Controllers and Observers will be provided with the appropriate materials necessary for their assigned function. The material will include any maps and messages to be used and forms for documenting and evaluating observed actions.
In each facility where an action takes place, the Controller will make judgment decisions to keep the action going in accordance with the scenario timeline. The Controllers will also. provide guidance to Observers and resolve minor problems which may occur. If a serious problem arises, an Observer should first contact the
'- # Facility Controller who will then contact the Exercise Coordinator 2154e ;
Rsv. 0 Page 3.1-2 for guidance or resolution of the problem. All major requests for _
scenario modifications or holding periods must be cleared through the Exercise Coordinator. Controllers also have the authority to resolve scenario-related problems which may occur during the exercise.
Observers for the exercise will observe the players as they perform ,
their assigned emergency response functions. Individual observers are responsible for being knowledgeable in the area of their i assigned function. The Observers will critique the ef fectiveness of the emergency response actions taken during the exercise and will -
also provide a written evaluation to their facility Controller.
The exercise initial conditions will be provided to a Control Room ,
operations crew, located in the Simulator, by the Controllers. The plant and reactor system parameters for the exercise will be generated by running the accident scenario on the simulator.
(
Additional exercise message cards and scenario parameters will be provided by Controllers / Observers at the times indicated in the exercise sequence of events, or when requested by the players.
As information is provided to the players, they should determine the nature of the emergency and implement appropriate emergency plan !
Laplementing procedures. These procedures should include a determination of the emergency classification in accordance with the Vermont Yankee Emergency Plan. Notifications will be made to the appropriate federal and state authorities.
The hypothesised emergency will continue to develop based on data and information provided to the operators located in the simulator.
Wherever possible, operators should complete activities as if they were actually responding to the plant events. Inconsistencies in the scenario may be intentional and may be required to test the capabilities of the emergency response facilities to the maximum !
/ )7T extent possible in a limited period of time.
2154e g- .---r - . , - - . ,
., n
I Royo 0 )
Page 3.1-3 l
O. fransral Guidance for the Conduct of the Exercise - ,
t
- 1. Simulatine raermanev Response Actions Since the exercise is intended to demonstrate' actual I capabilities as realistically as possible, participants should ,
act as they would during an actual emergency. Wherever possible, silaulation of response activities should be avoided.
3mergency response actions should be simulated only when it 16 )
not feasible to perform an action or when the action has been previously identified as being simulated during the exercise (refer to Section 3.2). When an emergency response is to be simulated, the Controller / Observer will provide verbal or written directions on which actions are to be simulated.
Radiation Work Permits (RWPs) have nel been issued for the conduct of the emergency response exercise. If scenario events f ,
r direct players to areas that are actually RWP-controlled due to ,
high radiation, surface contamination, or airborne radioactivity, players will simuiste response activities without actually entering the RWP-controlled area sYan if they are authorised on the RWP for some other duty. ;
2'. Avoidine Violatiana of Lawa Violation of laws is not justifiable during the exercise. To implement this guideline the following actions must be taken )
I All Controllers / Observers and potential exercise a.
participants must be specifically inforined of the need to avoid violating any fede.al, state and local laws, regulations,' ordinances, statutes and other legal restrictions. The orders of all police, eheriffs or other l
g authorities shall be followed as appropriate.
% l
)
2154e . . lj 1
I
. . u
R ;v. O Page 3.1-4
{3 :
I I ' b. Exercise participants will not direct illegal actions to be taken by other participants or members of the general j public.
- c. Exercise participants will not intentionally take illegal actions when responding to exercise events. Specifically, l local traffic laws (i.e., speed limits) will be observed.
- 3. t,voidina Paranaami and Property Endatzament All participants will be instructed to avoid endangering .
property (public or private), other personnel responding to the exercise, members of the general public, animals and the ]
environment. J
- 4. Actinna to Minimine Public InconvenienRt c
\q' It is not the intent, nor is it desirable, to effectively train or test the public response duritrg the conduct of the '
exercise. Public inconvenience is to be avoided.
The conduct of an exercise could arouse public concern that an actual emergency is occurring. It is important that conversations that can be monitored by the public (radio',
londepeakers, etc.) be prefaced and conclude with the words, "THIS IS A DRILLI THIS IS A DRII.L."
D. Imaraancy Rampanne T=ni tation ane Operatinna
- 1. Initial and Follow-Up Notification
- Initial and follow-up notification of the emergency classification will be made by the plant staff in accordance with existing emergency plan implementing procedures, unlesc directed otherwise.
i 2154e
R:v. O Page 3.1-5
-~
7 1
- 2. ContisLRoom_QasInti==
A Control Room emergency response crew will be positioned in the Simulator, located at the Vermont Yankee Training Center in Brattleboro, Vermont. The support staff normally on duty will initially be simulated until af ter the ALERT when it will be performed by the emergency response organisation. The plant and reactor system parameters will be provided to the Control Room emergency response crew by the simulator control board and the Controllers. Other information, such as radiological data and meteorological data, will be provided to the Control Room emergency response crew as necessary. Communications links that duplicate the emergency communications capabilities available at the Control Room will be used to communicate between the Simulator Control Room and other emergency response facilities. The actual Control Room communication system for
/ trannaission of emergency announcements and information (e.g., Gaitronics) will also be utilized.
- 3. IgghnicaLingport Center (TSC) Operationg ,
The TSC emergency response organisation will be activated during the exercise. TSC information will originate from the Simulator Control Room. Information that is normally accessible by TSC personnel from the plant computer will be provided by Controllers / Observers utilising telephone communicatio,ns between the simulator area and plant computer room. In addition. TSC Communicators, who would normally be assigned to the Control Room to pt622de TSC requested plant data, will be staged at the Simulator.
() 2154e i
< --m--y
i e
R:v. O ?
Page 3.1-6 i
- 4. Qparations suoport center fosc) 02sIAtions ,
The OSC emergency response organisation will be activated ,
during the exercise. Operations Support Center response i activities will be communicated to the Technical Support i Center. OSC Observers will acccrapany all OSC teams dispatched during the exercise and will provide appropriate operational and radiological data to the pie,yers. No team participating in the exercise should leave the Staging Area without an Controller / Observer.
- 5. *=armenev opsIAtions Facilitv/Bacovery Center (EOF /RC) paarations !
The EOT/RC emergency response crganisation will be activated -
during the exercise. Information and data will be transmitted
'" to the EOF /RC from the TSC and Control Room (Simulator). EOF Controllers / Observers will provide other data to EOF /RC players as necessary.
- 6. Off-site Monitorine T----
Off-site monitoring teams will be fully activated and
- i dispatched in accordance with existing procedures. Simulated ,
data will be provided to off-site monitoring teams by the
- Off-Site Monitoring Team Controllers / Observers.
- 7. Eswa Media cantar onaratiana The News Media Center will be activated and staffed during the exercise. News Media Center staff will obtain all the necessary information on current plant status through communications channels with the EOF /RC. Press releases will i 2154e :
._, ,-~---e- + - , , , ,e,- -, . >
RevJ 0 i Page 3.1-7 be generated and disseminated in accordance with the Vemont Yankee Cossounications Department Emergency Response Plan and Procedures. All press releases are to be clearly marked: THIS l IS A DRILL.
- 8. Escurity~onaratiana All exercice-related security emergency response activities will be implemented in accordance with existing procedures.
Access control and personnel accountability within the protected area will be demonstrated. At no time will actual plant security procedures be violated in support of the exercise.
- 9. Nuelaar Ranulatory Ca==lanlon (NRO) onataliSRS
- i The NRC Region I Incident Response Team will participate in the
- exercise. The NRC Region I will play a full participation role with a NRC Base Team located at the regional office in King of Prussia, Pennsylvania and the NRC Site Team at Vemont Yankee emergency response facilities. No NRC Public Affairs participation is planned.
1 E, Egggcima Termination l
l The exercise will be terminated by the Exercise Coordinator when all l emergency response actions have been completed in accordance with the exercise time sequence and exercise objectives.
The following steps will be implemented to terminate the exercise I 1
- 1. Tiie Exercise Coordinator will obtain information from the )
Facility Controllers regarding the status of player actions and 1
the demonstration of the exercise objectives. '
()
2154e .
l e
-.-# - ,. . . , , - -- . . , - , - ~ .
~
i R;v. O Page 3.1-8 j
- 2. The Facility Controllers are responsible for informing the ,
Exercise Coordinator of their facility status and whether the l l
emergency response actions and objectives have been i satisfactorily observed. I
- 3. Upon receipt of information from the Facility Controllers, the Exercise Coordinator will inform the Site Recovery Manager and TSC Coordinator that all exercise observations have been i completed and that the exercise can be terminated.
)
- 4. A coordinated decision to terminate the exercise will be made between the Site Recovery Manager and the TSC Coordinator. The Site Recovery Manager will also receive concurrence from the States to terminate exercise activities.
- 5. The Site Recovery Manager or TSC Coordinator will teminate the 5 exercise.
( '
The exercise may also be terminated under the following circumstances:
- 1. An actual plant emergency condition develops coincident with the exercise.
- 2. An actual off-site emergency impacts the response actions of Vermont Yankee exercise participants.
In the event that Item I should occur, the following actions will be taken:
- 1. The Shif t Supervisor will contact the TSC Coordinator and inform him j, of the plant status. The TSC Coordinetor will, in turn, contact the Site Recovery Manager and inform him of the plant statual 1
l l
2154e .
4 9
. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ , _ - _ ~ , - - - . . -- -
Revo O Page 3.1-9 (D
- The Site Recovery Manager will issnediately inform any State
- 2. ,
representatives at the EOF of the nature of the emergencyl
- 3. Concurrent with the notification in Step 2, the Control Room will anno mco the following statement over the plant paging system "The emergency plan exercise has been terminated. I repeat.
The emergency plan exercise has been terminated."
l This message may be immediately followed by the appropriate emergency announcements.
- 4. The Exercise Coordinator will be responsible for directing the actions of the Controllers / Observers and other exercise participants.
In the event that Item 2 should occur, the following actions should be
.s takent
- 1. The State Police, having been notified of the emergency, sho,uld open direct communications with the Vermont Yankee Control Room using the Nuclear Alert Systom.
- 2. The Shift Supervisor will notify the Control Room Controller who, in turn, will notify the Exercise Coordinator.
- 3. A coordinated decision will be made in conjunction with the Site Recovery Manager and/or the TSC and EOF Coordinators concerning the completion of the exercise. I
- 4. The Exercise Coordinator will be responsible for temporarily halting the exercise until such time a decision is made. ,
- 5. If the final decision is to cancel the exercise, the Exercise q Coordinator will be responsible for directing the activities of all
,D exercise participants, as well as for the notification of the NRC.
2154e l --
l
I R;v. 0 l Page 3.1-10 I 1
T.h
,o
- ~' 6. If the final decision is to continue the exercise, the Exercise Coordinator is responsible for informing all Controllers / Observers of any projected changes to the expected response action (s).
- 7. The Exercise Coordinator will direct the organisation as to the l appropriate action required to restore the exercise sequence.
1 l
l l
i
(' 'l eb1 2135e 1(([)
l
i r
i !
.,...y.
\. -
l .
t P
b VERMONT YANKEE NUCLEAR POWER STATION i
DtERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 t 3.2 EIMER INSTRUCTIONS AND GROUND RULES h.4 ,
e e
i
'1
+
):
R;v. 0 '
Page 3.2-1 tb g,)
VERMONT fANKEE NUCLEAR POWER STATION ,
EMERGENCY RESPONSE PREPAREDNESS EXERCISE
. 1990 l
1 3.2 F1AYER INSTRUCTIONS _AND GROUND RULES i
The Vermont Yankee Emergency Response Preparedness Exercise will be conducted on July 18, 1990. All emergency kesponse facilities will be fully activated, and the scenario will be driven by the simulator, as in past exercises. The successful demonstration of emergency response ;
capabilities will depend on player response and protocol. The following I
information contains exercise details and instructions for the players regarding the exercise. Department Heads are responsible for ensuring that personnel are trained on this infonnation. ,
g
~
A. General Guidelines ,
- 1. Exercise participants include the Exercise Coordinator, Players (including the NRC Incident Response Team), Controllers, Observers, and NRC Evaluators. Controllers will provide players with comunand and message cards to initiate emergency response actions. Observers and the NRC Evaluators will evaluate and note player actions. Controllers. Observers, an'd NRC Evaluators will be identified by badges.
- 2. Always identify yourself by name and function to the l Controllers, Observers, and Evaluators. Wear a name tag if one is provided.
- 3. You may ask the Controller / Observer for information such as:
I
- a. Initial conditions of the plant and systems including j
G o operating history of the core l
! 2148e f
l R;v. 0 ,
Page 3.2-2 )
- c. . ..
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. l t:
- c. Airborne data at the location of the plant and field survey teams after a sample has been appropriately taken. .
- d. ' Counting officiency of all counting equipment.
- e. Activity from nose swabs or skin contamination surveys.
- 4. You may not ask the following from the Controllers / Observers:
(. 3/ a. Information contained in procedures, drawings, or instructions.
- b. Judgments as to which procedures should be used.
- c. Data which will be made available later in the exercise.
- d. Assistance in performing actions in this exercise.
- e. Assistance in performing calculations.
! 5. Play out all actions, as much as possible, in accordance with your plan and procedures as if it were an actual emergency. If an action or data is to be simulated, a Controller / Observer will provide appropriate direction.
- ,;fp, 6. Always identify and discuss your actions to the SM Controllers / Observers and NRC Evaluators.
2148e -
l ,
1
-. _ ..~.. .,,.._ ... .. . _ . ,. ~_ _ _ . _ -. . .
1 R v. 0 l Page 3.2-3 j y\ l i, .
- 7. Periodically speak out loud, identifying your key actions and .
decisions to the Controllers / Observers and NkC Evaluators. 1 This may seen artificial, but it will assist the evaluators and ,]
is to your benefit. ;
i i
When you are assigned to complete a response action, be sure to 8.
be accompanied by a Controller / Observer at all times.
4 1
- 9. If you are in doubt about completing a response action, ask ]
your Controller / Observer for clarification. The )
Controller / Observer will not prompt or coach you. Emergency response actions must not place exercise participants in any potentially hasardous situations.
- 10. The controller / Observer will periodically issue messages or ]
' instructions designed to initiate response actions. You mual accept these messages immediately. They are essential to the J
proper conduct of the exercise.
i
- 11. If the contrt11er intervenes in your response actions and recommenis ?ou redirect or reconsider your play actions, it is 3 for a good reason. The Controller's direction may be essential to the overall success of thw exercise for all participating groups. ,
- 12. If you disagree with your Controller / Observer,. discuss your concerns. However, the Controller's/ Observer's final decisions aust be followed.
- 13. Respond to questions in a timely manner.
- 14. Do not accept any messages / instructions from NRC Evaluators.
They are required to work through your Controller / Observer if ig, ... they want to initiate additional emergency conditions. ,
2148e T
R:v. O Page 3.2-4
%v v?
.(J' However, you may answer questions directed to you by NRC Evaluators. If you do not know the answer, refer them to your lead player or Controller / Observer.
- 15. You must respond as if radiation levels are actually present in accordance with the information you receive. This may require you to wear protective clothing, respirators, and additional dosimetry and adhere to radiation protection practices.
- 16. Controllers / Observers /NRC Evaluators are exempt f rom simulated radiation IMFels and other emergency conditions. Do not let this confuse you or cause you to act unwisely. Howevsr, no one is exempt from normal station radiological practices and procedures.
- 17. Utilise status boards and log books as much as possible to s document and record your actions.
- 18. Always begin and end all communications with the words "THIS IS A DRILL." so that these communications are not confused with an actual emergency.
- 19. Keep a list of items'which you believe will improve your plans and procedures. A player debriefing will follow the exercise.
Provide any comments or observations to your lead player or Controller / Observer af ter the exercise. Areas for improvement or weaknesses when corrected vill improve the overall emergency response capability.
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
() 2148e n ow. - #4 4 e: s ew,*. en s e c. t -
i l
Revo O Page 3.2-5 h e other actions are to be performed in accordance with plant ,
procedures. No action will be allowed which alters or affects the I ongoing operation of the plant. The simulation list is as follows:
l
- 1. Scenario specific data will not be programmed into the plant process computer. This will be provided by Controllers / Observers utilising telephone communications between the Simulator and plant Computer Room.
l
- 2. A sufficient number of individuals from the Vermont Yankee Emergency Response Organization will be prestaged at the Simulator.
- 3. Meteorological data will be simulated using a " test" file available to the Simulator Control Room Meteorological Computer '
I System. )
,,.s 1 Y
- 4. After plant evacuation accountability has been completed, plant personnel and contractors / visitors not directly involved in the exercise will be allowed to return to work, at the discretion of the TSC Coordinator.
-i
$. The distribution of potassium iodide (KI) will be simulated.
- 6. Charcoal cartridges will be used as silver soolite cartridges during off-site monitoring activities.
- 7. The YNSD Emergency Response Team will be prestaged in the area.
- 8. No emergency response facility evacuation will be demonstrated during the exercise.
- 9. Off-site monitoring teams and security boundary monitoring personnel will not wear protective clothing and/or respirators.
I
. 2148e j l
e .
t_ . . s.. ,
i R:v. O Page 3.2-6 t
1
- 10. The inner gate and electrically controlled doors will not be .
left in the open position during the exercise.
The plant Gaitronics is not available from the simulator 11.
actual plant announcements will be made from the Vermont Yankee l plant Control Room.
1
- 12. Controllers / Observers will not be issued dosimetry unless plant access is required prior to the exercise. Security will be l notified of their assigned location. )
l
- 13. All decontamination actions associated with the exercise may be simulated after discussion and approval by the '
Controller /Observsr.
14 The use of respiratory protection equipment may be simulated by plant personnel after discussion and approval by the
( Controller / Observer.
- 15. Radiation Work Permits (RWPs) have not been issued for the conduct of the exercise. ,
C. Simulator Control Room InformatiDD The following describes how the Simulator Control Room emergency response activities will be integrated with the plant Control Room functions during the exerciset
- 1. Players reporting to the plant Control Room will be directed to an area (SS office) that will have a Controller and communications link with the simulator. All Control Room exercise communications should be directed to the Simulator Control Room.
1 X;]/ 2148e
= 3 % .,,. , ,
- - - v- , ,
,.,n ,- -
l R:v. 0 Page 3.2-7
? ',
- 2. All exercise-related Gaitronics calls to the Control Room and vice versa will be relayed or answered by the Control Room ,
Controller. Channel 3 should be utilized for all exercise messages. ,
- 3. Gaitronies plant announcements will be coordinated by the Simulator Controller. They will be made by the operating crew in the plant Control Room.
- 4. TSC Communicators normally assigned to the Control Room and a Radiation Protection Technician for transmitting initial radiological and meteorological data will be prestaged at the simulator. ,
- 5. Process cesputer ID data, normally accessible by TSC personnel, will be provided by a designated person in the simulator via personnel in the plant Computer Room.
(
- 6. ~ Personnel movement in and out of the Simulator Control Room will be limited to the Controllers / Observers.
- 7. Communications equipment in the Simulator Control Room is the i same as the plant Control Room. The commercial phone !
extensions are different but auto ring down and speaker phones i
are operable. The orange State phone and red ENS-NRC phone q will be operable. The orange phone extension is 613. l
. I D. Player's e----- nahin i i
1 i
The following is a list of items that should be followed to improve '
l gamesmanship during the exercise: .
l
- 1. Make it known when significant events occur or when you are
].
about to perform a significant action. l l
2148e i .
R;v. O f Page 3.2-8 F
- 2. Keep all messages, status boards, and problem boards accurate, current, timed, and dated. l l
- 3. Hold briefings regularly, at a minimum every 30 minutes.
- 4. Key players should wear badges which identify their role.
Bound log books should be used in all emergency response ,
l facilities.
- 5. All announcements, including those on the Gaitronics, should j state "THIS IS A DRILL." 1
- 6. Avoid simulation unless it has been specified. Use protective
- lothing where called for (e.g., step-off pads, etc.).
. l E. Paraannel Accountshility and Exercise Participation
(' IF.usagte d . . Ex e r c is e Pa r t i c ipant1.1 ;
1 Procedures require that all exercise participants be identified. I Proper identification will not only help eliminate confusion, but is necessary Ior security and accountability. This requirement applies to all arass within the plant fence, the Governor Hunt House, the EOF /RC, the simulator area, the News Media Center, and the Vermont l
Yankee Corporate Office in Brattleboro. '
Although it is expected that all personnel will respond to the declared emergency as delineated in the applicable procedures, it is recognised that a number of persons (e.g., normal plant operations shift, normal security complement, fire watches, etc.) will not participate due to the nature of their normal activities. The Department Heads should review their area of responsibility and provide the Exercise Coordinator with a list of names and positions for anyone that should be exempted from exercise participation.
2148e o
l l
rov. O Pasa 3.2-9
('
\ \
This list should be minimited. As in the past, people evacuated . I from the plant will be a110we6 to return to their normal duties upon j approval from the TSC Coordinator. )
Plant Security will be provided with a list of @ ompt personnel for i the exercise. All other personnel, not listed, are expected to participate as required by the Ianergency Plan. The exempt list of plant personnel will include the On-Shift Security Crew, Operating Crew, and Duty Chemistry and Pealth Physics Technician and the individuals identified by the Department Heads. Security at the i Training Center entrance will also limit access through the doors to exercise participants for the duration of the exercise.
F. Off-Site ParticipatiQD -
i This year, Vermont Yankee is conducting a small scale exercise which
- will involve the participation of the NRC Region I Incident Response .i Team. The NRC Region I will play a full participation role with a NRC Base Team located at the regional office in King of Prussia, Pennsylvania and the NRC Site Team at the Vermont Yankee emergency rssp noe facilities. No NRC Public Affairs participation is planned. The States of Verimont, New Hampshire, Massachusetts, and the local communities within the plume exper,ure pathway will have the opportunity to participate in the exercise.
The capability to notify federal, state, and local authorities of emergency classifications in accordance with established procedu~ s will be demonstrated as follows:
- a. NRC will be notified by utilizing the Emergency Notification r System (ENS) red phone.
4 2148e -
~ ' ~
1_ _ ___.
i . [. _. ___. _ _T
') r -l Rov. O Page 3.2-10 4@
Vermont, New Hampshire, and Maseachusetts State Police
~~
- b. ,
dispatchers and State Emergency Operations Centers (EOCs) will be notified-through the Nuclear Alert System (NAS) orange phone.
- c. NRC Region I Incident Response Team representatives and Vermont,'New Hampshire, and Massachusetts State officials present at the EOF /PC and the News Media Center (NMC) will be '
notified by the appropriate Vermont Yank % persennel.
If any state official tries to contact the plant Control Room REGARDING THE EKERCISE, the Vernon switchboard should transfer the h cii cc the Simulator Control Room in Brattleboro. The NAS orange 1 1
phone extension in da Simulator Control Room is 613.
a, G. rmarcine critiquam i
, The following is a brief description of the critique sessions that will be held after the exercise. The critique sessions are held to determine-whether the stated exercise objectives were met, verify the effectiveness of the emergency plan and procedures, and identify
_i areas for. future improvements. The specific schedule for the critique sessions will be announced at the conclusion of the exercise. 4 Emeraancy Rannonne Facility critinuaa The critique aessions will be conducted by the Controllers.
Exercise. participants will be debriefed on.the findings for.their particular emergency response facility (s). Three critique sessions
-will be held:
- 2. TSC and Simulator Control Room
, 3. Operations support Center and Security 2148e
. 8
Rsv. O Page 3.2-11
/.',,
Controllar Debriefine ,
This session will be conducted by the Ecercise Coordinator to coepile all exercise comments and findings. Participation is limited to Exercise Controllers.
Exercise critique This session will be conducted by the Exercise Coordinatur to present to management a summary of all major findings and deficiencies identified during the exercise. Participants include Vermont Yankee management, Exercise Controllers, key players, and the NRC.
NRC Exit r Immediately.following the exercise critique, the NRC will present
[' their preliminary findings. Participantc will be the same as in the exercise critique session.
9 l
()L 2148e-l j
l 4
,+-cc e # + y .- -- a
1 1
i L.' '.
a 1
VERMONT YANKEE NUCLEAR POWER STATION DfERGENCY RESPONSE PREPAREDNESS EXERCISE s
1990 -.
3.3 PROCEDURE EXECUTION LIST d'
l
}
i.
I 1
1 l
- 5150e l
l l
l
~ - . . . _ . . . .. : v. -
4
R v. O Page 3.3-1 -1
(
~
VERMONT YANKEE NUCLEAR POWER STATION ,
J EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1990
.,s 3.3 EMERCENCY PIAN IMPLEMENTING PROCEDURER RYRCUTION LIST ]
i Procedure Number Title [
1 AP 3125 " Emergency Plan Classification and Action Level Scheme" OP 3500 " Unusual Event" OP 3501 " Alert" OP 3502 " Site Area Emergency" OP 3503 " General Emergency" OP 3504 " Emergency Communications" OP 3507 " Emergency Radiation Exposure Control"
- r, 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 Response" OP 3525 " Radiological Coordination" OP 3530 " Post-Accident Sampling"
'(C 2150e 30'.
i
'" ~ ~ " " ' ' ~~
____' ~~^
-9'* %
(
?
VERMONT YANKEE NUCLEAR POWER STATION SMERGENCY RESPONSE PREPAREDNESS EXERCISE ,
1990 4.0 CONTR01.1.RR/DBSERVER INFOM1ATION i
.,MM 2
s 1
I l.
2152e i
i-I . , , J _-
4 ,
- j. , . .- ,
l' VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 4.1 CONTROLLER /0BSERVER ASE1QRi]2{IS 1
i NOTE: Assignment list will be provided
( at the exercise briefing.
I I
4 l
. l gt . 2152e .
{
ll
- v. -
l 1
a f?.
b.
i 4
QFrii"' YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 4.2 CONTROLLER AE_QRSERYFJLEKERCISL3HIDANCE n
a 2.s3.
I i- *
- me- *g =a4,-.,ae c. ,,.
Rsv. O Page 4.2-1
/~Sj l'..
'w- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 4.2 CONTR0llER AND OBSERVER EKERCISE CUIDANCE i
Prior to-the exercise, each Controller / Observer will be provided a scenario package and the plant emergency plan beplementing procedures which correspond to their assignment. It is the responsibility of the Controller / Observer to read the contents of the package and review the procedures. A Controller /
Observer briefing will be conducted prior to the exercise. Any questions regarding the scenario or the exercise assignments should be discussed at this time. Each Controller / Observer should ensure that they are f amiliar with the location (s) required by their assignment. Emergency response facility tours are available af ter the Controller / Observer briefing.
l The Controller is responsible for directing Observer activities throughout the course of the exercise. When the exercise is terminated, the Controllers will meet with the Observers to obtain their comments, observations, and exercise documentation. Each Controller will be responsible for ensuring that the documentation is provided to the Exercise Coordinator at the conclusion of the exercise. Each Controller is also responsible for providing a brief summary of their facility comments during the player debriefing.
(' 'l Controllers / Observers should identify themselves to the players and explain their role in the exercise. Players should be informed that any actions which deviate from standard plant or emergency procedures should be identified to-l the Controllers / Observers. Controllers / Observers should keep a detailed log throughout the exercise. This log should note the time, location, and player responses. Section 4.3 contains log sheets, checklists, and evaluation forms for documentation purposes.
The primary role of Controllers / Observers is to evaluate the emergency responses activities of the players. In order to document the adequacy of emergency response actions during the exercise, Controllers / Observers are required to complete the Emergency Exercise / Drill Observers Evaluation Form.
When completing this form, Controllers / Observers should attempt to differentiate their comments into either adequate or potential deficiencies.
For deficiencies of personnel, equipment, etc. provide recommendations for improvement which detail corrective actions, if possible.
. 2453e (4.'.)(Ek
. . ~ c... - . ..- ,. . ,. . . .. - . . . ,,. . . . . . .. - , - - .
E Rov. 0 ,
Pogs 4.2-2
,~
bi controllers / Observers should nat allow their biases to be documented as recognized weakness or deficiencies. Coments and recommendations should be further subdivided under the general headings as follows: Facility Activation / Organizational Control, Comunications, Adherence to Plans and Procedures Equipment Capabilities, Scenario, Training, Facility 1.ayout, ,
Off-Site Monitoring, Personnel Dosimetry / Exposure Control, and General Comments.
Facility Activation coments should identify (1) the time that emergency response personnel were notified; (2) when the facility was activated; (3) when initial activities became well organized; (4) whether personnel performance followed the organized arrangements specified by plant procedures; and (5) the efficiency of methods of authority transfer. If a transfer of responsibility occurred, then the Observer should determine if all affected personnel were aware that the transfer had occurred.
Comunication coments should identify: (1) personnel familiarity with emergency comunications use; (2) whether suf ficient communications were cvailable to ensure a timely, efficient, and effective flow of information; (3) whether there were enough comunications personnel to make use of all cvailable equipment; (4) the adequacy of comunications logs and the offectiveness of data transfer; (5) whether there were any problems in the '
design of the existing communications system (i.e., location relative to traffic flow); (6) whether there were any recognized dif ficulties in the use of computer systems; and (7) whether center status boards were ef fectively
-used. Observers should document their comments in this area very carefully, providing sufficient details to track any recognized deficiencies.
Plans and Procedural consnents should identify: (1) whether personnel were fami; with the details of the overall concepts of applicable procedurest (2) wnec..er situations developed which required deviation from the procedures or plan; (3) whether personnel were overwhelmed with procedural requirements which distracted them from performing their required emergency response function, and (4) whether the procedures adequately described the actions I required to complete an assigned function.
Equipment capability consnents should identify: (1) whether all necessary materials and equipment were available and functional; (2) whether emergency response personnel checked operability of equipment prior to conducting their l
assignment; (3) whether backup equipment was readily available when l
malfunctions were reported; (4) whether the available systems provided an adequate service; and (5) whether equipment malfunctions impeded the expected emergency response.
f Scenario related comments should address: (1) whether sufficient information l was available to ensure appropriate player response; (2) whether the scenario details deviated from actual procedural requirements; and (3) whether the l l e- 2453e '
- .h l
I l>
t l
. - - . , . _ ~ . ___:.. . - . . _ _ . . _ ,
Rsv. O Page 4.2-3 scenario detail provided any prompting to the player. The adequacy of the scenario in keeping the playera active and interested throughout the exercise should also be addressed by the Controllers / Observers.
Training comments should identify: (1) whether plant personnel have been provided sufficient training to handle "ad hoc" procedural deviations; and (2) whether-training identified improper procedural requirements.
Comments on facility layout deficiencies /recomendations should identify: (1) i whether the available work space was adequate; (2) whether traffic flow ;
hindered the response efforts; (3) whether the conununications available in the work area were adequate; (4) whether the noise level hindered emergency response efforts; and.(5) whether sufficient references were available to complete the job assignment.
Off-site monitoring team observers should identify: (1) the adequacy of sampling methods; (2) the adequacy of contamination control measures; (3) the adequacy of reporting and documentation measures; and (4) the effectiveness of the team in defining the plume condition and sample locations. Dose projection techniques should be evaluated in conjunction with this general category. Observations regarding dose projection technique should identify:
(1) the effectiveness of the system in allowing the correct interpretation of off-site conditions, and (2) the effectiveness of using the projection technique in positioning off-site teams.
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 Controllor/ Observer evaluation and documenta' M forms are found in Section 4.3. All-such documentation must be provided to the Controller after the exercise and prior to the plant critique.
2453e l
l 1 l l
(
- ..- , ,,a . . , . . . . . - -. .. j
rc i
l 1
1
.C% .;
y -: : ;
% 1 l
l
.i 1
6 VERMONT YANKEE NUCLEAR POWER STATION -1 i
EMERGENCY RESPONSE PREPAREDNESS EXERFSE 1990 I
4.3 CONTROf.f5R AND OBEERVER EVALUATION CRITERIA
.'.s. ,..- ,)
k e
6 I ih,dM*$ 2149e l
s
' " 8 ** b d M ' i - M / e4=e#* --p a g eir - cye,mam,, , , . . , ,,
R;v. O Page 4.3-1 i
- ' VERMONT YANKEE hUCLEAR.. POWER STATION -
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1220 4.3 CONTR0llER AND QBSERVER EVALUATION. CRITERIA As discussed in Sections 4.1 and 4.2, each Controller / Observer has been assigned specific areas of response to evaluate. This section has been
- developed to assist the Controllers / Observers in recording and documenting their findings and observations. The completed material will be an official record of the exercise observations.
Attachment A consists of forms to be used in maintaining an event.
chronology log.
Attachment B contains evaluation checklists for each emergency response facility. Each Controller / Observer should complete the appropriate ,
checklist.
' Attachment C contains an evaluation form which should be used to summarize major findings and observations. This form MUST BE completed by each Controller / Observer.
. N, All three attachments should be completed and submitted to the facility CD Controller. Each Controller will then submit the attachments to the Exercise Cooedinator for inclusion in the final exercise report..
9
\
[:y[ '2149e i
f.em .,. e .g n:+, mr w -+ ,..,*4,em, e , w e. , . . ,
R:v. O Page 4.3-A.1 W- VERMONT YANKEE NUCLEAR POWER STATION
~
EMERGENCY. RESPONSE PREPAREDNESS.. EXERCISE 1990 ATTACHMENT A -
Vermont Yankaa Nuclear Power Station Emermancy Response Exerciaa/ Drill Evaluator's ObaarvrLinna-chronoloalcal Ima
~
.24 = Obaarvation/C- .t 3
A.
- i l-t Name: Area Evaluated:
Date:
2149e i
s 419e* #4eem 4*viep+ - y -y- y .e-- . g
- e -,w.-e.i_b. y , , . .
V:
Revo O Page 4.3-A.2 3r ~y ' .
YZ8MONT YANKEE NUCLEAR POWER STATION '
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1 11!0 AIIACHt1ENI_A (Continued) t TM Obagnation/C agt i :s
. Qj i
Name ' Area Evaluated
! #kY' Date:
Y;;;/ -
2149e 4
4
- 4 , ,, , .
R;v. O Page 4.3-B.1 VERMONT YANKEE NUCLEAR POWER STATION A ZRGENCY RESPONSE PREPAREDNESS EXERCISE -
11EQ ATTACHMENT B Vermont Yankee Emeraency Exerciae/ Drill Evaluation Check List INSTRUCTIONS The following evaluation check lists are provided to assist the controllers / Observers with their evaluation of the drill / exercise. The Controllers / Observers should complete the check list (s) for their assigned location (s). To complete the evaluation check listis), utilize the rating scale listed below. Any comments or suggestiona for improvement, should be included on Attachment C, the Emergency ExerciaciDelli Evaluation Form or on a separate piece of paper.
Rating Symbol Cc- nts and Sunnanted T=_nrov-- nts Adequate A May be followed by comments and suggestions for improvements.
Iy especially if rating is marginal.
Inadequate I Must be followed by comments, together with-suggestions for improvement.
Not Observed or N No comments or suggestions Not Applicable- are required.
2'
(:) .
s s, e 4
- 6+ $ #**ee f e g+ ar e v.v ,w t
4
,>- t o
, R0v. 0 '!
~ !' Page 4.3-B.2
{
(
VERMONT YMfKEE NUCLEAR POWER STATION ~
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 '
ATTACllMENT B (Continued) ,
i Station ZAER ,
I. Control Room (Simulator and Actual) 4.3-B.2
,. I I . Techr.ical Support Center 4.3-B.4 III. Operations Support Center 4.3-B.7 IV. Emergency Operations Facility / Recovery Center 4.3-B.10 V. Si*e and Off-Site :lonitoting 4.3-B.13 VI. Security 4.3-B.14 VII. News Media Center 4.3-B.15 1.
1 I
i i
i l
1i
- (s.v,- 2149e j .
[. 3 1
R::v. 0 1 Page 4.3-B.3
[- .
VERMONT YAhKEE NUCLEAR POWER STATb?!
EMERGENCY RESPONSE PREPAREDNESS EXERCISE I
ATTACHMENT B (Continued)
I. CONTROL ROOM Ratine Comments l
A. . Accident A uctament/Emeraency Classification l l
- 1. Did the Control Room staff demonstrate Yes/No the ability to recognize emergency 1 initiating condities and classify the events in accordance with AP-3125.
- 2. Did the Centrol Room staff demonstrate Yes/No the ability to coordinate the assessment of plant conditions and corrective actions with l
the Technical Support Center? !
1
-(--
B. Notification and Cnn=nunication l 1.. Did the Control Room staff demonstrate the Yes/No ability to notify the plant staff of.an- I emergency through the~use of alarms and the I public nddress system?
- 2. Did the Control Room staff demonstrate the Yes/No- l ability to notify federal and state !
authorities of emergency classifications in 1 accordance with established procedures?
l
- 3. Was information flow within the Control Room Yes/No ,
and to other appropriate emergency response l facilities timely, complete, and accurate? l
- 4. Was adequate record keeping-of events, actions Yes/No and communications docuswnted and logged by the Control Room staff?
- 5. Were adequate emergency communication systems Yes/No available in the Control Room to transmit data'and information to other emergency response facilities?
- 2149e
. l I
. 1
R:v. O Page 4.3-B.4 ;
. (~"S VERMONT _ YANKEE NUCLEAR POWER. STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 19%Q ATTACHMENT L (Continued)
I. CONTROL ROOM Rating Commenta C. Activation and Rampgggg
- 1. Did the Control Room staff demonstrate the Yes/No ability to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
2.- Was the person in charge in the Control Room Yes/No clearly identifiable and was good ca-mand and -
control taken at the Control Room?
i l
(!
. Controller / Observer Name:
() '2149e ,
- l. '
E .
l- ;3- . 4 -
4 Rev. O j Page 4.3-B.5 L
V (^ > ,
I\-
VERMONT. YANKEE NUCLEAR.. POWER STATION '
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 122D i ATTACHMENT B (Continued)
II. TECHNICAL SUPPORT CENTER s
Rating Comments A. Accident Asses ===nt/Emermancy Classification
- 1. Did the TSC staff demonstrate the ability to Yes/No l
support the Control Room staff in identifying the cause .f the incident, mitigating the consequences of that incident, and placing.
the plant in a stable condition?
i
- 2. Did.the TSC staff demonstrate the ability to Yes/No -
coordinate the assessment of plant conditions and corrective actions with the Control Room?
- 3. Did the TSC staff demonstrate the ability to _ Yes/No to initiate and coordinate corrective actions in an efficient and timely manner?
- 4. Did the TSC staff demonstrate the ability to Yes/No direct and coordinate the taking of appropriate chemistry samples to analyse j plant conditions? q
- 5. Did the TSC staff demonstrate the ability to Yes/No participate with the Control Room and EOF /RC in emergency classification and EAL "l discussion.
B. Notification and C. mication l l
- 1. Was information flow within the TSC and to Yes/No other appropriate emergency response facilities timely, complete, and accurate?
.(:j)- 214 ,e il l
t- '- -wy w-
~
R:;v. O Page 4.3-B.6
.n VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EKEP"- s )
199D ATTACHMENT B i i
(Continued)
II. TECHNICAL SUPPORT CENTER Ratine Comments
-2. Was adequate record keeping of events, Yes/No actions, and communications documented and logged by the TSC staff? ,
- 3. Were adequate emergency communications systems Yes/No ,
available in the TSC to transmit data and information to other emergency response facilities?
- 4. Was information concerning plant conditions Yes/No disseminated between the Control Room and TSC
- performed in a timely manner?
(' l
- 5. Were status boarus utilized and maintained Yes/No to display pertinent accident information at the TSC?.
C. Activation and Remnanae
- 1. Did the TSC staff demonstrate the ability Yes/No
- to activate and staff the TSC?
p 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?
l 4 '. Did the TSC Coordinator establish and Yes/No coordinate access control into the Protected Area and Control Room?
-2149e I 1
- + , . - > - . , ,
i R::v. O J Page 4.3-B.7 E VERMONT YANKEE NUCLEAR POWER STATION ~
EMERGENCY RESPON$5 PREPAREDNESS EXERCISE ,
1210 ATIACEMENT B (Continued)
II. TECHNICAL SUPPOST CENTER Rating Comments
- 5. Did the TSC Coordinator demonstrate the Yes/No ability to maintain command and control of j TSC emergency response activities? l l
- 6. Did the TSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had i developed? I
- 7. Was the TSC organization and initiation Yes/No of activity efficient and well organized? ;
( )
9 l -Controller / Observer Names l([;)- 2t-
u l l
- I l
- 4 9 0-' 4 f 1 =+ve
I e
Rev. O Page 4.3-B.8 VERMONT. YANKEE NUCLEAR.. POWER. STATION ~
EMERGENCY RESPONSE PREPAREDNESS EKERCISE 1110- i i
ATTACHMENT B 1 (Continued) l III. OPERATIONS JUPPORT CENTER Rating Comments A. Notification and Cmumunication
- 1. Was information flow within the OSC and to Yes/No other appropriate emergency response facilities timely, complete, sud accurate?
- 2. Was adequate record keeping of events, actions,- Yes/No and communications documented and logged by the OSC staff? !
- 3. Were adequate emergency communications systems Yes/No available in the OSC to transmit data and
-(* information to other emergency response ;
facilities?
14 . Were status boards utilized and maintained to Yes/No display pertinent accident information at the OSC?
B. Activation and Reanonna 1
- 1. Did the OSC staff demonstrate the ability to Yes/No, ;
activate and staff the OSC?
- 2. Did the OSC staff demonstrate the ability to Yes/No !
appropriately implement Emergency Plan Implementing Procedures and did they follow them?
- 3. Were initial and continuous accountability Yes/No checks of OSC personnel performed?
(i 2149e s - .a ,
s
Rov. O Page 4.3-B.9 Q VERMONT YANrFF NUCLEAR POWER STATION
~
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 122D ATTACHMENT B (Continued)
III. OPERATIONS SUPPORT CENTER Ratine Comments
- 4. Did the OSC Coordinator and OSC Coordinator's Yes/No Assistant demonstrate the ability to maintain command and control of OSC emergency response activities?
- 5. Did the OSC keep other emergency response Yes/No facilities advised of the status of their activities and information which they had developed?
- 6. Was the OSC organization and the initiation Yes/No (l' ' of activity efficient and well organized?
- 7. Did the OSC staff demonstrate the ability to Yes/No provide adequate radiation protection controls for on-site emergency response personnel?
- 8. Did the OSC staff demonstrate the. ability to Yes/No monitor and track radiation exposure of on-site-emergency response personnel?
- 9. Did the OSC staff demonstrate the ability Yes/No to obtain and analyse appropriate-chemistry samples as directed by the TSC?.
- 10. Did the OSC staff demonstrate the ability Yes/No to initiate, brief, and dispatch On-Site s Assistance Teams?
2149e
+ . . ~ . - . . , . . . . . -
I
Rr,v. O Page 4.3-B.10 f:"
VERMONT YANKEE NUCLEAR POWER STATION -
EMERGENCY RESPONSE PREPAREDNESS EKERCISE 122Q
. 1 ATTACHMENT B +i (Continued)
III. OPERATIONS SUPPORT CENTER
- 11. Were on-site assistance teams able to trouble- Yes/No shoot and evaluate problems with plant ,
equipment and systems? l I
., 12. Were their adequate administrative controls Yes/No and documentation taken to perform the ,
necessary repairs of plant equipment and t systems during an emergency situation?
i Controller / Observer Names 2149e , !
l 4..
R:v. O Page 4.3-B.11 (
/'! L VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1910 ATTACIDiENT B (Continued) i IV. EMFRCENCY OPERATIONS FACILITY / RECOVERY CENTER Ratine Comments A. Notification and Ca-aunication
- 1. Was information flow within the EOF /RC and Yes/No to other appropriate emergency response facilities timely, complete, and accurate?
- 2. Were adequate emergency consnunications systems Yes/No available in the EOF /RC to transmit data and information to other emergency response facilities?
e 3. Was adequate record keeping of events, Yes/No ,
-( actions,-and. communications documented 4 and logged by the EOF /RC staff?
- 4. Was information concerning plant conditions hes/No disseminated between the TSC and EOF /RC performed in a timely manner?
- 5. Were status boards utilized and maintained Yes/No to display pertinent accident information at the EOF /RC?
B. Activation and Ramoonae
- 2. Did the EOF /RC staff demonstrate the ability Yes/No l to appropriately implement Emergency Plan Implementing Procedures and did they follow them?
i i
- N.
2149e u
l 1
s ' ~ 9 '
- n w e=*
Rov. O !
Page 4.3-B.12
^%
2' YERtiONT YANKEE NUCLEAR POWER STATION !'
plERGENCY RESPONSE PREPAREDNESS EXERCISE 1210 i ATTACHMENT B (Continued) ,;
1 IV. Elg1CENCY OPERATIONS FACILITY / RECOVERY CENTER Ratine Comments
- 3. Did the Corporate Security Force establish Yes/No access control into the EOF /RCf
- 4. Did the EOF Coordinator demonstrate the Yes/No j ability to maintain command and control of t EOF emergency response activities?
- 5. Did the EOF /RC keep other emergency response Yes/No facilities advised of the status of their !
activities and information which they had developed?
- 6. .Were the EOF /RC organization and the initiation- Yes/No of activity efficient and well organized?
- 7. Did the Site Recovery Manager demonstrate the Yes/No ability to maintain the command and control of ,
the overall emergency response effort and organization?
- 8. Did the Site Recovery Manager demonstrate the Yes/No !
ability to de-escalate from the emergency phase into-the recovery phase?
- 9. Were preliminary recovery plans established Yes/No and discussed between the Site Recovery Manager and appropriate personnel?
C. Radioloalcal Anama--nt
- 1. Was information concerning radiological and. Yes/No meteorological data obtained by appropriate EOF personnel in a timely manner?
- 2. Did the EOF staff demonstrate the ability Yes/No to perform off-site dose assessment in
.accordance with Procedure OP-3513?
h,~
2149e
Rev. O Page 4.3-B.13 C',
b VERMONT YANKEE NUCLEAR POWER STATION EMERGENCLRESPONSE._ PREPAREDNESS EXERCISE 1D.Q ATTACHMENT B (Continued)
IV. EMERGENCY OPERATIONS FACILITY / RECOVERY CENTER Ratine Comments
- 3. Did the EOF staf f demonstrate the ability to Yes/No ef fectively track and define the plume utilizing the computerised dose assessment model (METPAC)?
D. Protective Action Decision-Makine
- 1. Did the Radiological Assistant's staff Yes/No demonstrate the ability to perform timely assessment of off-site radiological conditions to support the formulation of protective action recommendations?
].
- 2. Did the EOF Coordinator obtain and provide Yes/No the necessary information to the Site Recovery Manager concerning protective action recommendations in accordance with Procedure 07-3511.
- 3. Did the' Site Recovery Manager demonstrate Yes/No the ability to make protective action recommendations to off-site authorities in accordance with Procedure OP-35117 Controller /0bseryer Name:
2149e -
t l
. . 1
- - _ _ _ - _ - - _ _ - _ - _ _ _ = .
1 R:v. O Page 4.3-B.14 q VERMONT _ YANKEE _ NUCLEAR POWER. STATION '
EMERGENCY RESPONSE PREPAREDNESS EXLRCISE 1910 ATTACHMENT B i (Continued)
V. SITE AND OFF-SITE MONITORING Ratinn Comments A. Activation and Reannnaa l
- 1. Did the site and off-site monitoring teams Yes/No I demonstrate the ability to transmit ,
information over the radio utilizing proper I units and terminology in acco'. dance with I Procedure OP-35107 l l
- 2. Were site and of f-site moritoring teams Yes/No 'l dispatched and deployed la a timely manner? I
- g. '3. Were team members f amilia r with the use of Yes/No g;b;~;-' equipment, field monitoring procedures. and I what was required of them?
- 4. Were off-site monitoring teams able to Yes/No l determine and consnunicate their location in the field using appropriate maps and sample points (landmarks)?
l l
l l
Controller / Observer Names t
'2149e-l l
l l
1 l I' * *
(l 2, .- - . _ '~_
,a Rov. 0 4,
Page 4.3-B.1$
Nh '
Mi# VERMONT YANKEE NUCLEAR POWER STATION jtg&fd2iCLRESPONSE PREPAREDNESS EKERCISE 1HD ATTACN'tMI 3 (Continued)
VI. RECURITY Aaling 0;amaan.ta A. Activation and Reananag
- 1. .Did the Security staff demonstrate the ability _ , . _
Yet,/No to perform accountability of personnel within the Protected Area in accordance with Procedures OP-3524?
- 2. Were access control points established and Yes/No maintained to control access at the site '
and the Protected Areat
- 3. Did the Security staff demonstrate the ability Yes/No f^)
(~ to appropriately implement Emergency Plan Implementing Procedures and did they follow thest Controller!Obser'ver Namet 2149e
R;v. O Page 4.3-8.16
- q VERMONT YANrrt NUCfFAD P%'ER STATION DiERGENCY krRPONSE PnFPAnrnNESS EXERCISE q O ATTACHMENT B (Continued)
VII.
- DEWS MEDIA CENTER Rating Cumnanta A. Activation and Respona_t
- 1. Did the News Media staff demonstrate the Yes/No ability to activate and staff the News Media Center?
- 2. Was information flow between the News Media Yes/No Center and EOF /RC timely, complete, and accurate? -
- 3. Were the News Media staff familiar with their Yes/No plans and procedures and do they follow them? i
- (.
- 4. Did the News Media staff demonstrate the Yes/No ability to provide accurate and timely information concerning the emergency to the public and the news media?
- 5. Did the News Media staff demonstrate the Yes/No ability to coordinate news releases with the state's public information representatives?
- 6. Did the News Media staff demonstrate the Yes/No ability to provide briefings for and to interface with the public and news media?
l Controller / Observer Names 2149e
l
~
Rev. O Pago 4.3-C.1 VERMQNT YANKEE NUCLEAR.PDFEILSTATION
(,,,, '
RtERGENCY RESPON$E PREPAREDNESS EKERCISE 1110 r
ATTACIDiENT. C Engggenev Fwarciaa/ Drill ,
Qbaarver's Evaluation Form Observer's Names Exercise / Drill Dates Exercise / Drill Title Observer's Location _. :
Time Startedt ,._ Time Ended (
Observed: Plavar Function Overall Performance and Observations (include the proper and effective use ,
f~s of procedures, equipment and personnel):
V, i 2
Recognized Deficienciest l
i Coannents and Recossoendations (Specific): ._ )
1 I
HQIE l
Use additional pages as required.
Signature: Tit 1e: .
l VYOPF-3505.02
$ OP-3505, Rev. 13 Page 1 of-1 2149e i
l l
-1
._......~4.,. ..,,,.c_, . . . . . .
Revo O Page 4.3-C.2
, ,~3 ,
(
VEkMONT YANKEE NIJCLEAR POWER STATION :
EMERGENCY RESPONSE PREPAREDNESS EKERCISE 1920 ATTACEMENT C (Continued)
- - . ~ .
9 5
i p**-
hg '
P Continued on Additional Pages Yes No ,
Signature:
Title:
Date s
f 2149e I
$ e
- 4. , . . , < . . . .. -, . . . , , , ,
i I !
6 !
i
. (. .. , '
- s. -
i t VERMONT YANKEE NUCLEAR POWER STATION . '
I EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 ;
5.0 EXERCISE SCENARIO h
b t
t : l' f
l g
,g4*' g .
4 I
r e
i4 i
1 v'* *i s. ,,
- s ,
e 0
h..
- 4. . ,
o ... , .
.r . * ,
r,
.1 h
4 L
VERMONT YANKfE NUCLEAR POWER STATION ENERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 5.1' 1NITIAL CONDIT10NE 9
4 4
.f '
i
. (: .
-r
) ,
t
'Y I3 .k I- e e t ,;
l-i l i
e l #_,_ h I,
-,.b.,e.,v.c y-mm,,,,,,.
- ,,,,,,,,'y,, ,,, , .. ., .,_,.__i,_ ___ __] '
k l
)
i i
Rev. O Page 5.1 2
{~
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than 104.
A high pressure system centered over Pennsylvania this morning will drif t to the southeast and slowly weaken during the day. This system will dominate the weather today.
l
i I
Rev. O Page 5.1 3 Table 5.1 1 1 Initial Plant and Panctor Svaten Valuaa j
)
Reactor Vessel Coolant level 162 inches i l
Reactor Pressure 1,006 psig 3 Reactor Power . APRM (average) 1004 Core Plate Differential Pressure 20.0 paid Total Core Flow 46 mil lbs/hr a Main Steam Line Flow Total 6.2 mil lbs/hr j Nain Steam 1.ine Radiation 194 mR/hr i condenser Hotwell level' $64 Condenser Vacuun 2.6 inchea Hg(Abs) ,
Condensate Storage Tank Level 52%
Reactor Coolant Temperature 527 'T !
Recirc Drive Flow (average) 30,000 gpm
. 9'; Feedwater Flow 6.4 mil lbs/hr Reactor Building Differential Pressure 0.75 inches Hg ,
Drywell Pressure 1.70 psig (
Drywell Temperature 140 'T -
Torus Water Level 1.16 ft Torus Temperature 72 'F ,
l Drywell/ Torus on Concentration 2.6% i High Range. Containment Monitors 2.7 R/hr Containment Cas/ Particulate 600/60,000 cpm l
Reactor Building Vent Monitors Cas/Part 500/4,000 cpm '
l' 1
- Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr ,.
I Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uCi/see Stack Caa I/II 150/200 cpm High Range Noble Cas Monitor 0.1 mR/hr I -c p + * ,,w < - , , v ,v.-,w
,\ r
. i: t
..j 4 ;
rp..
- }-2 V ,
, i l 1 f4 -
r,
, 3-. ;
- 2. x'p. .
5 )
4 -#
VERMONT YANKEE NUCLEAR POWER STATION ap.
ENERGENCY RESPONSE PREPAREDNESS EXERCISE.
1990 3
k t i; '
b 1 5
- - . 4,
"? S.2. n NATIVE stb 0hRY I
6 v
l 4.. i(- 9' wy:
.k
' A s.
b ,:'
b 9
a f
'." 4 i ,l- )
6 o
D A
Rev. O q Page 5.2 1 :
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EKERCISE 1990 1
5.2 MARRATIVE.
SUMMARY
The scenario begins at 0700 with the simulator reactor running at approximately 100% power. The reactor has been in a steady state for the past sixteen months with no recent shutdowns. . Night orders have instructed the operations crew that containment de.inerting has been
' started for a scheduled power reduction and drywell entry. The Reactor Engineering staff has determined that power reduction should not exceed 14 per 3 minutes. The drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs). RRUs 2 and 4 are showing s abnormal amperage fluctuations. The Auxiliary Operators have also been
~
directed to change the suction filters on the "B" Control Rod Drive (CRD)
Pump. All other power generating and safety system equipment is operable.
At 0730, an earthquake is sensed on. site and could be felt at various ,
locations around the plant. Upon confirmation that an earthquake has been sensed on. site, the Shif t Supervisor should declare an UNUSUAL EVENT. The UNUSUAL EVENT (approximately 0745) is based upon AP 3125, " Natural Phenomenon", due to any earthquake sensed on site as recognized by either observation, detection or notification.
The Shift Supervisor- should initiate the appropriate notifications concerning the declaration of the UNUSUAL EVENT and changing plant conditions. The shift operations crew will initiate appropriate procedures to check plant instrumentation and to conduct visual inspections for an assessment of any potential damage caused by the earthquake.
Y??
n r,
i i
- - -- .. - - - . . . -. .- . - - .. -- .=
1 l
Rev. O Page 5.2 2 At 0800, a h1 5h turbine vibration alarm occurs. The turbine trips on a hi Sh vibration signal causing an automatic reactor SCRAM signal. When the reactor SCRAM signal occurs, d.: e ntrol rods fail to insert causing the l reactor to remain critical and an Asticipated Transient Without Scram
- (ATVS) condition exists. This results in reactor power remaining above 24. l The Main Steam Isolation Valves (MSIVs) are still open snd pressure is being regulated by the Electric Pressure Regulator (EPR) asA the turbine bypass valves to the Main Condenser. ]
An ALERT should be declared (approximately 0815) based upon AP 3125, " Loss of Systems or Equipment", due to failure of Reactor Protection System I l
(RPS) to initiate or accomplish a required SCRAM. ;
l
,. Following the ALERT, the Technical Support Center (TSC), Operations Support ,
Center (OSC),' and Emergency Operations Facility / Recovery Center (EOF /RC) will be activated and staffed. Notifications should be made to the l appropriate personnel including the state and federal authorities.
The Control Roon staff will initiate actions to stabilize the plant, and the opera %rs will attempt to individually drive control rods into the reac*or core. The control rods will be allowed to be inserted.
successfully. Operators will insert the control rods in accordance with Reactor Engineering directions.
By d830, the "A" CRD Pump trips due to an electrical breaker problem.
Operators will not be able to continue to insert control rods into the .t reactor core because both "A" and "B" CRD Pumps are not available. Plant personnel should be dispatched to investigate the problem on 'A" CRD Pump or expedite the comp 16r.on of the filter replacement on "B" CRD Pump.
9
.R j
!+
l
Rev. 0
("'N Page 5.2 3
\' _
ty 0925, Loss of Main Condenser vacuum occurs due to condenser air in.
leakage problems. Loss of condenser vacuum causes the closure of the MSIVs. The Main Condenser is no lor.ger available as a heat sink. Control rods are still not fully inserted and reactor power is still above 24.
By 0935, one of the CRD Pumps will be returned to service (depending upon I
plant corrective actions and decisions). Operators will be able to continue to individually drive control rods into the reactor core.
Reactor power will be reduced as the control rods are successfully inserted.
A SITE AREA ENERGENCY should be declared (approximately 0945) based upon AP 3125, " Loss of Systems or Equipment", due to failure of Reactor
( Protection System (RPS) to initiate and accomplish a required SCRAM with the Main Condenser unavailable.
Upon primary containment isolation, operators will continue control rod insertion and implement actions to stabilize the plant. This will include :
using the Safety Relief Valves (SRVs) HPCI or RCIC with the torus as the heat sink to control reactor pressure and cooldown. Operators will also start RHR in the torus cooling mode and monitor torus temperature and level. l 1
l Reactor power raduction and pressure control will continue. Once all control rods havu been inserted into the reactor core, operators 'will >
commence a reactor cooldown, Plant conditions will be stabilizing and remaining fairly constant for the next hour and thirty minutes. Plant ;
discussions may begin on the possibility of de escalation from the emergency phase to a recovery mode of operation.
O .
il
. . - _ _ u
Rev. 0 >
Page 5.2 4 -
. j' ,
At 1130, the Simulator Operator will insert a casualty that causes a large f sesam line break inside the primary containment. A rapid depressurization of the reactor will occur with a rapid increase in containment pressure.
The rapid reactor pressure decrease causes fuel cladding failures and releases fission product gases into the primary contait ment. The containment radiation monitors will have increased significantly, i By 1135, a high drywell pressure alarm is received which initiates a Primary Containment Isolation of Groups 2, 3, and 4. The simulator control board will indicate that the Torus Purge Supply Valve (V161910) did not close on Group 3 isolation. Reactor operator efforts to isolate r the Torus Purge Supply Valve (V161910) are unsuccessful. Area radiation monitors in the Reactor Building are increasing significantly. Plant Vent
-r- ' Stack monitors are indiesting a release of radioactivity to the environment. The release pathway is associated with a ' flange being dislodged upstream of the Torus Purge Supply Valve (V16 19 10) in the ,
Reactor Building.
i
- (. A GENERAL EMERGENCY should be declared (4pproximately 1145) based upon AP 3125, " Fuel Damage ,' due to the loss of two of three fission product barriers with the potential loss of third.
By 1200, it is anticipated that on site assistance teams should be dispatched to investigate the leak in the Reactor Building and the problem associated with the Torus Purge Supply Valva (V16 19-10).
By 1300, the repairs associated with the Torus Purge Supply Valve (V16-1910) have been completed. The leakage into thi Reactor Building is isolated, s
- lgs I
i
i I
Rev. O !
Page 5.2 5
("'S-3 I
1 By 1330, the plant is stabilized, and the Plant Vent Stack monitors have ;
decreased. The source of the reluase into the Reactor Building has been controlled and isolated. Therefore, the release of radioactivity to the environment will continue to decrease with time based upon the volume ;
exchange rate of the Reactor Building through Standby Gas Treatment System. De escalation from the emergency phase into the recovery mode is now feasible.
At 1400, the exercise will be terminated.
t
}
'(a v 1
F**%
s
' w i
'k
- ~ . - . . - . - - - - . . . .
.- .. - - .q
- , i-u t- . i
.. 1 i < ;
13 t l 1
- e ,.,
p? :.,
j i
VERMONT YANKEE NUCLEAR POWER STATION M, . ENERGENCY RESPONSE PREPAILEDNESS EXERCISE .
a'8, . <
1990 s
l
- s i
ff!' 5.3 SCENARIO TIME LINE (
n
-er
- .h l h
s 6 -I 4
D
=!s t ' , il:
lr :
.'l
\*
s v h
J
.t. 2
'~
- 5 t
( >
..L.
) S' : , '3 t
i
- i. f. f 5
O 1 ! $
9
%:* { E -
.o - .
' .h
$ -I r1 ;i 4
Ta , ,
(i r x
l .s. .
' f; .
. -.4-- g
,r--
I i
)
4 %
I -- e
-q .*
s I. '?l .?
- l. 2. ~s
- :n . t' ls- i 3
~
b'g :
- p> ;, 3 3:
-i
.3. )
- ' +
1
" .. lJ ) F .
..M M
~
I- } _;
Rev. O Page 5.3-1 I VERMONT YANKEE NUCIEAR POWER GTATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE ,
1990 5.3. SCENARIO TIME LINE, i
CIDCK SCENARIO l l TIME' TIME . DESCRIPTION !
0700 0:00 - < Initial conditions established.
0715 0:15 -
i i -
0730 0:30 -
<- Earthquake sensed on-site.
1 !
0745 0:45 -
< UNUSUAL EVENT (AP 3125, NATURAL PHENOMENON) -
Any Earthquake sensed on-site '
as recognized by either observation, detection, or notification.
0800 1:00 - <- Turbine vibration alarm. Turbine trips. Rx SCRAM signal occurs with control rods not inserting. ATWS condition exists.
0815 1:15 -
<- ALERT (AP 3125, IDSS OF SYSTEMS OR EQUIPMENT) - Failure of Reactor Protection ,
System (RPS) to initiate or accomplish a required SCRAM. ,
i _
C830 1:30 - <- "A" CRD Pump trips. No CRD Pumps available to drive control rods. Plant personnel dispatch to investigate CRD Pump problems.
0845 1:45 -
Continued On Next Page 0900 2:00 - ***** ****
m s.,,
Rev. O i Page 5.3-2 i 5.3 SCENARIO TIFE LINE (continued)
CIDCK SCENARIO TIME TIME DESCRIPTION
. . - .0900 2:00 -
0915 2:15 -
^
C925 2:25 -
< Loss of Main Condenser vacuum causes MSIV closure. Control rods still not 0930 2:30 inserted and Reactor power above 2%.
0935 2:35 CRD Pump returned to service. Operators continue to drive control rods.
0945 2:45 -
< SITE AREA EMERGENCY (AP 3125, IDSS OF SYSTEMS OR EQUIPMENT) - Failure of Reactor Protection System (RPS) to initiate and accomplish a required SCRAM with the Main Condenser unavailable. '
1000 3:00 -
< Operators to continue control rod insertion and implement actions to stabilize
- l. -
the plant.
1015 3:15 - < '
Reactor pressure and cooldown is being controlled. Plant conditions ,
stabilizing and remaining fairly constant.
1030 3:30 -
1045 3:45 -
1100 4:00 -
~
1115 4:15 -
- Contin 2ed On Next Page ****
t 6
-,..-...._.e,_
-. x 4
. .. ) . .;
Rev. O Page 5.3-3 5.3 SCENARIO TIME LINE (continued)
CIOCK SCENARIO TIME TIME DESCRIPTION 1115 4:15 -
1130 4:30 -
<-- Steam Line Break Inside Primary Containment. Rapid depressurization occurs.
1135 4:35 - < PCIS occurs (Groups 2,3,4). Problem with Torus Purge Supply Valve V16-19-10.
ARMS in Rx Bldg. increasing significantly. Plant Vent Stack release begins. ,
1145 4:45 -
< GENERAL EMERGENCY (AP 3125, FUEL DAMAGE) -
Loss of 2 of 3 fission product barriers with the potential loss of third.
I 1200 5:00 - < Teams sent to investigate Reactor Building leakage and problem with the Torus Purge Supply Valve (V16-19-10).
l j 1215 5:15 -
i -
1230 5:30 -
~
i
- 1245 5
- 45 -
l'300 6:00 -
< Repairs to the Torus Purge Supply Valve (V16-19-10) have been completed. Leak into Reactor Building is isolated.
1315 6:15 -
- Continued On Next Page ***O .
t
_ _ _ _ . _ _ _ _ _ _ _ _ . . _ _ _ _ . ._ _ __._ _ _ _____ _ _ m __ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ ._mm___ _______._m ______m. = _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
"-( '
. v i Rev. O Page 5.3-4 I
5.3 SCENARIO TIME LINE (continued)
CIDCK SCENARIO TIME TIME DESCRIPTION i 1330 6:30 -
<- Plant is stabilized. Release from Plant Vent Stack has been controlled. -
De-escalation from the emergency phase into the recovery mode is possible.
l 1345 6:45 -
. 1400 -
7:00 EXERCISE IS TERMINATED. !
i t
'l O
4 1
i
- i. ,
6
.i.- . . . - ,
& , w a e ,"- 5 F ysm-er-r r g a 'e er + v*sia+" _-e -- W w -
w5-w ..-*iw e e Bw m we ww-
- ewe -e e wee _e_ iw __-w
P I
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 ;
i 5.4 D11Aftrn EEOUENCE OF EVENTS ,
L s
i i
1 9
2498e
('J?;
i
l i
I R:v. O Page 5.4-1
- 7. ,
\ - VERMONT YANKEE NUCLEAR POWER STATION ;
EMERGENCY RESPONSE PREPAREDf;ESS EXERCISE l 1990 l 5.4 DEIAILED SEQUZHCE OF EVjKI3 ,
I Clock Scenario fiaa_ T6 Event / Action Massage Command Prior to EXPECTED CONTROL ROOM (CR) ACTIONS 0700 00:00 WILL BE IMPLEMENTED BY AN EXERCISE OPERATIONS CREW (INCLUDING SUFFICIENT NUMBER OF PRESTAGED INDIVIDUALS FROM THE VERMONT YANKEE DtERGENCY ORGANIZATION) LOCATED IN THE SIMUIATOR COMPLEX IN THE CORPORATE TRAINING CENTER.
OPERATIONAL CONTROL ROOM DATA WILL ;
- BE PROVIDED BY THE SIMULATOR INSTRUMENTATION RESPONSES. IN CASES WHERE SPECIFIC INFORMATION NOT MONITORED BY THE SIMULATOR IS REQUIRED, IT WILL BE ISSUED BY CONTROLLERS /0BSERVERS ON MESSAGE CARDS. IN THE EVENT THAT A SIMULATOR MALFUNCTION OCCURS, THE EXERCISE WILL BE CONDUCTED USING INFORMATION DEVELOPED FROM SECTION 8.0 AND SECTION 9.0.
i
~(
v.
. 2498e
i!
!I Rev. 0 l Page 5.4-2 ;
Clock Scenario . 1 Time.. TN Event / Action Massaga Command Prior to The Simulator CR Controller issues SCR-M-1 SCR-C-1 0700 00:00 initial conditions to the simulator ! .
(Cont'd) CR players. Guidelines for use of !
Gaitronics and the plant evacuation alarm are provided i to players.
Initiating messages are also CR-M-1 provided to all emergency centers TSC-M-1 and f acility staf fs upon sub6quent TSC-N-2A activations. Operationsi and TSC-M-28 radiological data will be available OSC-M-1 to the TSC via TSC coassunicators SRM-M-1 ,
who normally respond to EOF-M-1 the CR prestaged in the ESC-M-1 simulator. Security will be ,
provided a list of Controllers /
Observers and nonparticipants who ,
will not have to be accounted for during the exercise.
0700- 00:00 Simulator is put into operation.
Reactor power is at 100 percent power. The reactor has been operating steady state for the past 16 monthe with no recent shutdowns.
~M
" 2498e
b R ;v. O !
Page 5.4-3 j 4
Clock Scenario liatt .limt Event / Action tiessage Command ii 0700 00:00 Night orders have instructed the (Cont'd) Operations crew that containment .,
de-inerting has begun on the previous shift for a scheduled power reduction and drywell entry. !
The Reactor Engineering staff has i determined that power reduction ,
should not exceed 11 per three minutes. The drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs). RRUs 2 and 4 are showing abnormal amperage fluctuations. The Auxiliary ,
(" Operators have been directed to change the suction filters on the ,
"B" Control Rod Drive (CRD) pump.
All other power generating and safety system equipment is operable.
0730 00:30 An earthquake is sensed on-site SCR-M-2 and can be felt at various locations around the plant.
Control Room operators should SCR-M-3 .
initiate Procedure OP-3127
" Natural Phenomena" which will instruct them to check plant instrumentation and to conduct
]
visual inspections for an f assessment of the potential {
damage caused by the earthquake.
l 2498e. l l
l
,J e - . . . . .
R;v. O Page 5.4-4 l
)
- 1. ,
Clock Scenario ^
Time._ Time Event / Action Menange CDauband 0730 00:30 This will include checking (Cont'd) indications on the seismic j accelerometer and contacting SCR4-4 SCR-C-2 l l
Vernon and Bellows Falls dams for an assessment of dam status. ]
Approx. Approx. The Shitt Supervisor should declare 0745 00:45 en UNUSUAL EVENT based upon the following EAL: AP-3125. " NATURAL PHENOMENON - Any earthquake sensed on-site as recognized by .;
either observation, detection or notification."
The S$/ PED should initiate .
Procedure OP-3500, Unusual Event and refer to Appendix I, the ,
SS/ PED checklist.
Operators may dispatch other plant personne1' (auxiliary operators or !
security force) to perform plant inspections / tours associated with the earthquake event and other plant' activities. ;
FOR EKERCISE PURPOSES, EARLY SCR-C-3 IN-STATION ACTIONS MAY BE CONTROLLED AND PERFORMED BY THE SIMULATOR CONTROLLERS.
y 2498e t
i
e Rov. 0 l Page 5.4-5 -
Clock Scenario ~
Tint . lima Ly. ant / Action tiassaga CQamand Ap;rox. Approx. Th6 SS/ PED should announce 0745 00:45 the Unusual Event over I (Cont'd) the Plant Paging System. This !
activity will be performed by players in the Simulator CR, and simultaneously performed by a Controller directed member of the operating shift crew in the actual Control Room.
The SS/ PED should notify Vermont, New Hampshire,_and Massachusetts State Police Agencies using the Nuclear Alert System (orange phone) and provide the
(
appropriate message to each agency.
The SS/ PED should notify the NRC on the red phone and maintain commanications until relieved by the TSC.
The Security Shift Supervisor should implement Procedure OP-3531, " Emergency call-In Method," to notify the appropriate emergency response personnel.
i
( l- 2498e
- 2
4 R;v. O j Page 5.4-6 l
(
Clock Scenario 1 Ik T4== Event / Action Massagg Command ;
Approx. Approx. The Security Shift Supervisor i
0745 00:45 should notify Yankee Nuclear
-(Cont'd) Services Division (YNSD) Security '
l
- and activate the YNSD Personnel
. Group Paging System.
t The Security Shift Supervisor ;
should also notify New England Hydro Power Station of the Unusual SEC-C-1 l Event. THIS CALL WILL BE SIMU1ATED. j 1
The Primary and Secondary Duty l and Call Officers (DCOs) should ;
report to the plant after notification of the Unusual Event !
Status.
The DCOs should contact the SS/ PED to be advised of the situation. l Responsibility for TSC and .
EOF Coordinator assignments would 't i
be discussed, as appropriate.
The TSC Coordinator should assume the overall supervision and J
! coordination of the on-site -
emergency response activities. l This will include escalating
! the emergency classification i
! as conditions warrant.
l
, ra - . ;) '
2498e Q :. j l I i
h l
l
5 f
Rev. O Page 5.4-7
~.
Clock Scenario Time. .liat_ EYtat/Aetion thtgaggt Command Attivation of the Technical Support Center (TSC) is optional at the Unusual Event.
0750 00:50 IF AN UNUSUAL EVENT RAS NOT BEEN SCR-C-4 DECLARED BY THE SS/ PED, NE WILL BE DIRECTED TO DO SO AT THIS TIME.
Plant personnel sent to perform a OSC-M-2 visual inspection of the plant ,
will find no damage from the eartbcuake.
0800 01:00 Simulator control board r indicates high turbine vibration alarm.
Turbine trips on high vibration signal causing an automatic reactor SCRAM signal.
When the reactor SCRAM signal occurs, the control rods fail to insert causing the reactor to remain critical. An Anticipated Transient Without Scram (ATWS) condition exists. Reactor power is also cbove 2%.
( * 'N}- 249Be l I
1 1
1
l R;v. O ;
Page $.4-8
.' s - l Clock scenario )
list . lime . . . Event /AetioD tit &Angt Command .]
l 0800 01:00' The SS/ PED should notify the TSC (Cont'd) Coordinator of the changing plant conditions, and that a partial -
reactor SCRAM occurred. I The TSC Ce,ordinator and $$/ PED a should start to review the plaat conditions against Procedure AP-3125. " Emergency Plan I Classification and Action Level Scheme." ,
The Control Room personnel will be working to stabilize plant conditions, and the operators will start to manually drive control rods that have not fully inserted into the core. Operators will insert the control rods in accordance with Reactor Engineering directions.
1 The Main Steam Iwolation Valves (MSIVs) are still open, and I pressure is being regulated by 1
the Electric Pressure Regulator -
(EPR) and the turbine bypass valves to the Main Condenser. )
)
I 1
2498e i
l
?
Rov. O Page 5.4-9 1/Q
!\'= Sdenario
! Clock 4 Time Time Zyent/ Action tiessage Command -
Approx. Approx. The SS/ PED or TSC Coordinator ;
0815- 01:15 should declare an ALERT based upor. the following EAL: AP-3125,
" LOSS OF SYSTDiS OR EQUIPMENT - f
. Failure of the Reactor Protection System-(RPS) to ir.itiate or accomplish a required SCRAM."
The SS/ PED directs the operations staff to initiate Procedure OP-3501, " Alert."
Aa Alert announcement should be -
made over the plant page
- instructing emergency personnel yn .
to report to their assigned emergency response facilities. {
and other personnel, contractors, and visitors return to the Governor Hunt Hour Information-Center and wait for 1 ther instructions. k I
At this time, the Technical
-Support Center (TSC), Operations Support Center (OSC), and tha Emergency Operations Tacility/
Recovery Center (EOF /RC) should be activated and staffed.
' ?' .% '
) 2498e ,
i l
. 6
, 1
1 , . . . .
b 5
Rov. O Page 5.4 -
Clock- Scenario Iing_ Time- Event /Actisn Massage Command l Approx. Approx. The SS/ PED should notify the Vermont, 0815 01:15 New Harpshire, and Massachusetts (Cont'd) State Police Agencies of the escalation to the Alert emergency i
classification.- i l
The NRC should be notified of the i escalation to the Alert.
ie The Security Shift Supervisor should initiate the emergency call-in method for the Alert j classification.
-l The Security Shift Supervisor ~j should notify Yankee Nuclear Services Division (YNSD) Security of the escalation to the Alert status.
i Upon Alert notification, the YNSD Engineering Support Center ,
(ESC) is activated.
- The Security Shift Supervisor should notify the New England i Hydro Power Station in Vernon !
of the escalation to the ;
Alert status. THIS CALL WILL SEC-C BE-SIMULATED.
(
.m 2498e
. i Ma.1
. . . .. - . _ . . --_ .=.
Rev. O Page 5.4-11 1- '
Clock Scenario Time _Ilme Eyent/ Action M11Aagt Command
^
t Approx. Approx.. The TSC Coordinator should
'0815 01:15 notify RENVEC of the Alert status : 4 (Cont'd) and plant conditions.
.'0820 01:20 The Security Shif t Supervisor-should ensure that an ;
accountability of personnel has been initiated in i accordance with procedures SP-0906, " Emergency ?
, Procedures" and OP-3524,
" Emergency Actions to Ensure Accountability and Security Response."
The TSC Coordinator should respond, I activate, and staff the TSC in accordance with Appendix III of OP-3501, " Alert."
TSC staff representing the s
following departments should assemble at the TSC following -
the declaration of an Alert:
- 1. Instrument and control Supe rvis'or
- 2. Radiation Protection Supervisor or desire *.ed alternate.
\]( 2498e
\d)
o i
h 'R3v. 0
." Page 5.4-12 l 1
i fi* .W.
k ' Clock Scenario Ca==nd Time = Time ErsatIAcdon- titanage 0820- 01:20- 3.- Reactor and Computer i (Cont'd) Supervisor !
4; Operations Supervisor t
- 5. Maintenance Supervisor Engineering Support I 6.
. Supervisor i
- 7. GE Resident Engineer (as necessary) i
- 8. Plant Services Supervisor
. 4g"6 "y;.
- 9. Other staff personnel to fulfill the functions of ..
, the TSC (i.e., Status Board Keepers , Communicators, I l
Switchboard Operators, etc.). l 0825 01:25 . The Emergency Operations Facility (EOF) Coordinator should activate and staff the EOF /RC in accordance with Appendix IV of OP-3501, i
" Alert."
I 2498e -
i i
4
4 W,
ll@l y ;
UG I'l
! /,5 11,.
4'A ciE Rsv. 0
' a: ,
Page 5.4-13 i
Jf;~'8{'
4, ! '
Clock Scenario- ~
Ilme Time Event / Action- Message' Command ;
\:
L 0825- 01:25 The emergency response staff that (Cont'd) reports to the EOF /RC includes the following:
- 1. Site Recovery Manager and designated corporate staff ,
- 2. ' EOF Coordinator k
'3. Purchasing Supervisor '
- 4. Public'Information Liaison
- 5. Additional trained plant staff members to assume the
);._7 < following tag board assignments: -
- EOF Coordinator's -<
Assistant .
- Radiological Assistat.t i
- Manpewer and Planning Assistant
- Communications -
Assistant r 24,8e l(32?J
_- -.___.______-_.__ __ _J.____ _ ._____ _ __ , - - -
f a R:v. 0 :
Page 5.4-14
'(&') ,
(~b t
~~
Clock. Scenario.
Event /Aetion
~
h Time ligganga Connans)
~ 0825 01:25 - Radiological Coordinator (Cont'd)
- Personnel and Equipment Monitoring Team
- 6. Corporate Security Force '
The Operations Support Center (OSC)
Coordinator (assigned 'uy the TSC i Coordinator) should activate and -
staff the OSC in accordance with Appendix VII of OP-3501,
" Alert."
J'- The plant staff that reports to the'OSC includes the following:
- 1. Radiation Protection and Chemistry Assistants and Technicians .
- 2. Control Instrument Specialist
- 3. Maintenance Staff
- 4. Status Board Caretaker
- 5. Other personnel as required.
- ( ) .
2498e l
lc, t
p r-Revo 0 -
Page 5.4-15 [
i
,0- 01ocu Scenario '
)*ime Time Evani/ Action tittsAgt Command 0825 01:25 The Site Recovery Manager (SRM)
(Cont'd) and staff should report to the EOF /RC and implement the procedural steps listed in l Appendix VIII of OP-3501, l
" Alert." !
I Radiation Protection Technicians from the OSC may s be dispatched to perform dose rate radiation surveys, air l
sampling, and contamination '
surveys of the plant.
j 0830 01:30 IF AN ALERT HAS NOT BEEN DECLARED SCR-C-5 BY THE SS/ PED, HE WILL BE DIRECTED TO DO SO AT.THIS TIME.
Approx. Approx. Simulator control board indicates .
1 0830 01:30 the "A" CRD pump has tripped. 1 i
Operators will not be able to continue to insert contro11 rods ,
i into the reactor core, j The SS/ PED should immediately.
inform the TSC Coordinator and '
SRM concerning the unavailability of both "A" and "B" CRD pumps.
i 4-2498e- -
l
- - . . .- - -- -- - ~ . -
-:- e
- . )
l l
Rovo O Page 5.4-17
~[~3'4' Clock. Scenario ^
l Ilms_ : Time Erag(/ Action Mt&AA&t CQsBland Approx. One of the CRD pumps will be OSC-M-5 ;
Approx.
.0935 02:35 declared operable and returned to service. Operators will be ,
able to continue to individually , '!
drive control rods into the reactor core.
Reactor power will be reduced as the control rods are successfully inserted. -
0935- 02:35 The SRM, TSC Coordinator, and SS/ PED should evaluate plant !
conditions against Procedure AP-3125, " Emergency Plan Classification and Action Level
{.] _
Scheme."
The SRM with consultation from the TSC Coordinator and SS/ PED should recognize the need to escalate to a Site Area Emergency. 1
[
o Approx. . Approx.- The SRM should declare a SITE AREA 0945 ~ 02145 - EMERGENCY based upon the fo11owing t
l EAL: AP-3125, " LOSS OF SYSTEMS OR 1'
L ,
EQUIPMENT - Failure of Reactor Protection System (RPS) to initiate and accomplish a required-scram l
with the Main Condenser unavailable."
1 1.
). l l !
[
l! ,
Rev.-0 Page 5.4-18 l
]W?y Clock Scenario l h Tine Event / Action Message Command
~
Approx. Approx. If present, the SRM should inform 0945 02:45 the NRC Site Teca representatives',
(Cont'd) the State representatives of Vermont, New Hampshire, and Massachusetts located at the EOF /RC and contact each State's j E00s via the Nuclear Alert System to inform them of the escalation
, to the Site Area Emergency.
The SS/ PED will also be directed to make the appropriate plant ,
announcement concerning the f escalation to the Site Area
.< w Emergency.
. Upgraded notifications should j also be made to YNSD and the NRC.
0950 02:50 .Upon primary containment isolation, operators will continue
. control rod insertion and implement actions to stabilize the plant.
' This will include using the Safety Relief Valves (SRVs). HPCI, or RCIC !
with the torus as the heat sink to control reactor pressure and
.cooldown.
s a
-L 2498e
-i .
n !
_.r - - . . , . . -- -..- . .-
.y Y Rsv. 0 Page 5.4 \.
[1 S. v i
Clock Scenario Ilmg_ Time Event / Action Henragg Conunand i
- 0950 02:50 .operstors will also start RHR in j
- (Cont'd) the torus cooling mode and monitor torus temperature and level.
l t
- D' 1000 03:00 IF A SITE AREA EMERGENCY HAS NOT -SRM-C-1 s
BEEN DECIARED BY THE SRM, HE WILL i BE DIRECTED TO DO SO AT THIS TIME.
1030 03:30 Reactor power reduction and pressure control will continue.
Plant conditions will be stabilizing and remaining fairly constant.
Plant discussions may.begin on the *
- r.g - possibility of de-escalation from
%> the emergency phase to a recovery mode of operation.
. . I
~
1040 03:40 The ESC should be providing ESC-M-2 technical and engineering.
support to the Ver:nont Yankee '
staff. The ESC. meteorologist- a should provide a specialized weather fore 1ast for the :
Vermont Yankee site.
e m, j W ,
. _l.,'
<.y-i Rev. 0 !
.d Page 5.4-20 yN
,.-( )7 '
1' Clock -Scenario -
j' Time Time Event / Action Masinge Command 1130 04:30- A casualty will be inserted by .i Simulator Operator that causes a large steam line break inside the primary containment. A- !
rapid depressurization of the ;
, reactor occurs with a rapid. l increase in' containment pressure.
The rapid reactor pressure decrease causes fuel cladding failures and releases fission l product gases into the primary i containment. The containment !
radiation monitors will have
- M increased significantly. y v.
A 1135 04:35 A high drywell pressure' alarm is received which initiates a Primary Containment Isolation j of Groups 2, 3. and 4. ;
Simulator control board will indicate that the Torus Purge Supply Valve V16-19-10 did not close on Group 3 isolation.
Area radiation monitors in the Reactor Building are increasing j significantly.
) 2498e t
il
. I
E ii <
m ", ,
Rsv. O Page 5.4-21 Clock Scenario ~
Time. Time Fiatal/.Ac tion tieaaage Connand
~1135 04:35 . Standby Gas Treatment System (SBGTS) initiated automatically on Group 3 isolation.
Stack Gas Monitors 1/II, and high-range plant vent stack monitor begin to increase as indicated by the simulator control board.
The release pathway is' associated with a flange being dislodged upstream of the Torus Purge Supply Valve V16-19-10 in the Reactor Building. ,
Reactor operator efforts to isolate the Torus Purge Supply Valve V16-19-10 are unsuccessful.
Approx. Approx. ~The SRM, with consultation from L 1145 04:45 the TSC Coordinator and SS/ PED, should recognise the need.to escalate to a General Emergency. ,
The SRM should declare a GENERAL EMERGENCY based upon the following EAL: AP-3125, " FUEL DAMAGE - Loss of 2 of 3 fission product barriers with potential loss of third." !
2498e .
t
s Rsv. 0 i ,
Page 5.4-23 3 .
~
' Clock Scenario
-I k Time' Event /ActiQn Message Comand 1150 04:50 Stsek gas s.onitors! continue.to escalate due to noble gases and iodines passing through the standby gas treatment charcoal filters. <
The appropriate EOF staff should initiate Procedure OP-3513
" Evaluation of Off-Site Radiological Conditions," to
. determine'off-site dose projections. ,
Off-Site Monitoring Teams should
- be dispatched to monitor the plume in the downwind direction.
The EOF Coordinator and Radiological Assistant should' initiate Procedure OP-3511.-
"Off-Site Protective Action Reconsnendations," to formulate >i protective action recomunendations I
based upon off-site radiological conditions. I The SS/ PED should inform the TSC ,
Coordinator and SRM that the Torus Purge Supply Valve V16-19-10 did I not close upon Group.3 isolation and attempts to isolate the valve 1 1
.were unsuccessful.
-2498e
!1 1
l' a
Rsv. O Page 5.4-24 '
(
~ L Clock Scenario ~
i Time Time Event / Action tiessaSt CDERAnd
(
1200 05:00 IF A GENERAL EMERGENCY HAS NOT BEEN SRM-C-2 DECLARED BY THE SRM, HE WILL BE I DIRECTED TO DO SO AT THIS TIME.
Approx. Approx. Team should be requested to take 1200 05:00 a plant vent stack sample (refer to Procedure OP-3530, " Post-Accident Sampling").
Plant personnel should be looking
-for the source of the leakage into the Reactor Building..
On-site assistance teams may be
- j. dispatched to investigate the
-leak in the Reactor Building.
Approx. Approx. TSC personnel should also be 1200 05:00 investigating the problem associated with the Torus Purge. j Supply Valve V16-19-10 (refer to Miniscenario 7.2.2). 1 l
l Approx. Approx. .The team sent to investigate the OSC-M-6
- 1215 05:15 53cblem vith the Torus Purge OSC-M-7 Supply Valve V16-19-10 -l will find that the valve indication is open. Corrective actions to close the valve will;be expected to occur by the team.
2498e
(;_;
, l w
> 1
> Rsv. 0 ,
'Page 5.4-25 Clock Scenario Time Time Ey.ent/ Action dessage Command 1230 05:30 The ESC has reviewed the latest ESC-M-3 NWS forecast and has updated l meteorological information for the site. :
.1 h
An updated weather forecast is EOF-M-3 !
available from NWS.
IF NOT ALREADY DONE, THE TSC TSC-C-1 COORDINATOR WILL BE DIRECTED TO DISPATCH ON-SITE ASSISTANCE TEAM
.TO INVFSTIGATE PROBLEM WITH THE TORUS PUkCE SUPPLY VALVE V16-19-10.
i 1245 05:45 IF A NATIONAL WEATHER SERVICE EOF-C-1 UPDATE HAS NOT BEEN REQUESTED
- BY THE- RA, HE WILL BE PROVIDED WITH ONE.
Approx. Approx. Repairs associated with the Torus OSC-M SCR-C-6 13'0 0 06:00 Purge Supply Valve V16-19-10 OSC-M-9 have been completed.
Simulator control board indications show that the Torus Purge Supply Valve V16-19-10 has closed.
Leakage past the Torus Purge Supply Valve has stopped.
~2498e f)
m ;
i
, R:v. O Page 5.4-26 :
- !!M L ", .' Clock' Scenario Time T4mm . Event / Action Message Command.
- i-- ; Approx.- Approx. The leak into the Reactor ;
+1300 06:00 Building is isolated. ,
r i
1330 06:30 Control Room indications show
, that plant conditions are !
stabilizing and the plant vent ,
stac'; monitors have decreased.
The source of the fission product release into the Reactor Building has been controlled and isolated.
The release of radioactivity to the environment will continue to decrease with time based ,
upon the volume exchange' rate
..,- of the Reactor Building i through Standby Gas Treatment System.
De-escalation from the emergency,
. phase into the recovery mode is now possible.
Approx. Approx. Exarcise is terminated.
p 1400 07:00 l
l'.
pr i
1.
2-
l)(11) j:
h I
'! _____m _
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ .-___m_
g l
-l i
i VERMONT YANKEE NUCLEAR POWER STATION ,
EMERGENCY RESPONSE PREPAREDNESS EXERCISE -l 1990 l i
i 6.0 EKERCISE MESSAGES 1
i
.(: T l
i i
1 1
~j
.o
(('4, 2499e' U ll 5
s
f ll D .
i VERMONT YANKEE NUCLEAR POWER STATION DIERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 f 6.1 COMMAND CARDS !
i i
4 k
O g m ,,.
k !
Rovo O Page 6.1-1
. . ,. 3 k
. VERMONT YANKEE NUCLEAR POWER STATION -
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO CQl91AND CARD FROM: -Simulator CR Controller C0tMAND KO. SCR-C-1 TO: Shift Sunerv'isor CLOCK TIME: Prior to 0700 LOCATION: S4=uintor Control Room SCENARIO TIME: Prior to 00:00 PARTICIPANT MESSAGE THIS IS A DRILL Communications systems that are available in the Control Room have been duplicated in the Simulator Control Room Area EKCTH for Gaitronics- and the plant evacuation alam.
Please use the Gaitronics/ Plant Evacuation Alarm in the Simulator Control Room to complete the required PA announcements. An Exercise Controller will then direct a member of the shift operating crew at the plant to repeat the announcements from the Main Control Room. .t
(' <
i f
-CY 2499e I
i
Rov. O Page 6.1-2 VERMONT YANKEE NUCLEAR P0h'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO CQtMAND CARD FROM: Simulator CR Controller CCitWiD NO.: SCR-C-2 TO: Shift Sunerv'isor CLOCK TIME: Q730 LOCATION: Simuistor Control Room . SCENARIO TIME: 00:30 PARTICIPANT MESSAGE THIS IS A DRILL For exercise purposes, Control Room communications with Vernon and Bellow Falle Dams will be simulated.
4 Rov. 0 Page 6.1-3 VERMONT YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO COMMAND CARD FROM: Simulator CR Controller COtMAND NO.: SCR-C-3 TO: Shift Sunervisor CLOCK TIME: 0745 LOCATION: Simuistor control Room SCENARIO TIME: 00:45 PARTICIPANT MESSAGE THIE IS A drill Early in-station actions will be simulated and information i requested at this time will be provided by controllers. ;
i 1
2499e U
1 R v. 0 l Page 6.1-4 ;
%. VERMONT YANKEE NUCLEAR POWER STATION ^ ^
1 EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO C0ft1AND CARD FROM: Security Controller COMMAND NO. SEC-C-1 TO: Security Supervisor CLOCK TIME: 0745 or when needed '
LOCATION: Sacurity Catehouse SCENARIO TIME: 00:45 PARTICIPANT MESSAGE THIS IS A DRILL FOR EXERCISE PURPOSES, communications with New England Hydro Power Station in Vernon will be simulated.
g: a 2499e i-
. %. / l 1
l
{
L '
y; __ _ _
l
< R:v. O Page 6.1-5
-L
.(dyg;
- c. s s
' W] VERMONT YANKEE NUCLEAR POWER STATION j I:MERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 l i
SCENAR10 00ttlAND CARD FROM Simulator CR Controller .._, COMMAND NO. SCR-C-4 TO: Shift Suoervisor CLOCK TIME: 0750 14 CATION: Simulator control Room SCENARIO TIME: QQ.150 PARTICIPANT MESSAGE THIS IS A DRILL DECLARE AW UNUSUAL EVCNT BASED UPON AP-3125, NATURAL PHENOMENON, ANY EARTHQUAKE SENSED ON-SITE AS RECOGNIZED BY EITHER OBSERVATION, DETECTION, OR NOTIFICATION.
Y Y 5
O '"-
i
?
Revo O Page 6.1-6
,7 lf VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO COMMAND CARD FROM: Simulator CR Controller COMMAND NO.: SCR-C-5 TO: Shift Supervisor / Plant CLOCK TIME: 0830 R==rnancy Director LOCATION: Simulator Control Room SCENARIO TIME: 01:30 PARTICIPANT MESSAGE IRIS IS A DRILL DECIARE AN ALERT BASED UPON AP-3125. LOSS OF SYSTEMS OR EQUIPMENT -
FAILURE OF THE REACTOR PROTECTION SYSTEM (RPS) TO INITIATE OR .
ACCOMPLISH A REQUIRED SCRAM.
,..3
(__,5) l
\.
l l
- l. .
l l,
4 L
l.
l- i lQ l
2499e 1
~
Rcv. 0-Page 6.1-7 Q
.. VERMONT YANKEE NUCLEAR POWER STATION ,
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO CG91AND CARD I FROM: sam contre 11er ColttAND NO. ERM-C-1 j TO: Site Recovery Manneer CLOCK TIME: 1000 LOCATION: EOF /RC -
SCENARIO TIME: 03:00 l
PARTICIPANT MESSAGE !
THIS IS A DRILL DECLARE A SITE AREA EMERGENCY BASED UPON AP-3125, LOSS OF SYSTEMS OR EQUIPMENT - FAILURE OF THE REACTOR PROTECTION SYSTEM (RPS) TO INITIATE AND ACCOMPLISH A REQUIRED SCRAM WITH THE MAIN CONDENSER UNAVAILABLE.
p%
,; l .l i
2499e -
l
% g
1 Rev. 0 ,
Page 6.1-8 {
b VERMONT YANKEE NUCLEAR POWER STATION {
EMERGENCY RESPONSE PREPAREDNESS EXERCISE {
1990 i i
SCENARIO COMMANQ_ CARD
\
TROM ERM Controller COM1AND NO. SRM-C-2
- TO:
Site Recovery Manneer CLOCK TIME: 1200 LOCATION: EQF/RC SCENARIO TIME: 05:00 i
PARTICIPANT MESSAGE IRIS.IS A_ DRILL DECLARE A GENERAL EMERGENCY BASED UPON AP-3125, FUEL DAMAGE, DUE TO LOSS OF 'IVO OF THREE FISSION PRODUCT BARRIERS WITH THE POTENTIAL ;
LOSS OF THE THIRD. !
3 il 1
e l 1
l
,. l.
- y- 2499e J ;
l Rev. O Page 6.1-10 3
,-w
.$[3 VERMONT YANKEE NUCLEAR POWER STATION !
I EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 r SCENARIO COMMAND CARD .
FROM: EOF Controller 00tt%ND NO.: EOF-C-1 TO: Radioloelcal' Assistant CLOCK TIME: 1245 LOCATION: EOF /RA-Dome Amnes===nt Area SCENARIO TIME 4 05:45 PARTICIPANT MESSAGE HIS IS A DRILL j REQUEST A WEATHER FORECAST FROM ESC AT THIS TIME.
([D b
g 2 ,,.
1 i
R3v. O i Page 6.1-11' I p>
. VERMONT YANKEE NUCLEAR POWER STATION ,
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO COPf4AND CARD FROM: Singlator CR Controller COMMAND NO.: 3CR-C-6 TO: Rhift Sunervlaor CLOCK TIME: 1300 or as needed LOCATION: Simulator Control Room SCENARIO TIME: 06:00 PARTICIPANT MESSAGE THIS IS A drill REPAIRS TO THE TORUS PURGE SUPPLY VALVE V-16-19-10 HAVE BEEN COMPLETED. SIMULATOR CONTROL BOARD INDICATIONS SHOW THAT THE TORUS 4
. PURGE SUPPLY VALVE V16-19-10 HAS CLOSED. LEAKAGE INTO THE REACTOR !
BUILDING IS-ISOLATED. ,
MAKE SURE THIS INFORMATION IS TOIL TO THE SITE RECOVERY MANAGER AND TSC COORDINATOR. ,
. T i
.t e
g s ,,.
i
't'-
~
VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 6.2 MESSACE CARDS
(.>v.. e
,f
....,.s 4M) 2502e
l-Rov. O Page 6.2-1 (m '
VERM0K! lANKEE WCLEAR TOWER STATION EMERGENCY RESPONSE PREPARt3 NESS EXERCISE 1990 SCENARIC MESSAGE CARDS f TROM: Elmulator CR Controller MESSAGE NO.: SCR-M-1 TO: Shif t Supervisor CLOCK TIME: Prior to 0700 LOCATION: Simulator Control Room SCENARIO TIME: 00:00 PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages.
1 d
P j e7 THIS IS A DRILL Y,.' A 2502e
Rev. O y ) Page 1 of 3 VERMONT YANKEE NUCLEAR POWER STATION EKERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 INITIAL CONDITIQH1 (This information will be provided to the players at the start of the exercise).
- 1. The Reactor is now at approximately 100% rated power. The reactor has been operating steady state for the past sixteen months with no recent shutdowns.
- 2. Night orders for the operations crew are as follows:
- a. Containment de.inerting has commenced on the previous shift for a .
scheduled power reduction and Drywell entry. Reactor Engineering staff has determined that power reduction should not exceed 14 per 3 minutes,
- b. The Drywell entry is needed to accomplish repairs t i the Drywell Reactor Recirculation Units (RRUs) . RRUs 2 and 4 are showing abnormal ar.perage fluctuations,
- c. The Auxiliary Operators are changing the suction filters on the "B" Control Rod Drive (CRD) Pump.
i
- 3. All other power generating and safety system equipment is operable. ;
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed , sph (lower / upper) 2.8/5.6 Wind Direction , degrees (lower / upper) 10/348 Delta Temperature , 'F (lower / upper) 0.7/ 0.6 Ambient Temperature , 'T 53.4 .
Precipitation , inches 0.0
. '1 1
L 1
I Rev. 0 1 Page 2 of 3 i
- 5. Regional Meteorological Forecast Information: ,
l 4
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late l morning. High temperatures 75 to 80. Probability of precipitation less than i l
106.
A high pressure system centered over Pennsylvania this morning will drif t to the southeast and slowly weaken during the elay. This system will dominate the weather today.
\
9 9
W Rev. 0
,en Page 3 of 3
(;
Initirl Plant and Reactor Syntam Values Reactor Vessel Coolant Level 162 inches Reactor Pressure 1,006 psig Reactor Power . APRM (average) 100%
Core Plate Differsntial Pressure 20.0 psid Total Core Flow 46 mil lbs/hr Main Steam Line Flow Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr Condenser Hotwell LaTel 56%
Condenser Vacuum 2.6 brims Hg(/bs)
Condensate Storage Tank Level 52%
Reactor Coolant Temperature 527 'F Rectre Drive Flow (average) 30,000 gpm i I
['D+ '
Feedw6ter Flow 6.4 mil lbs/hr Reactor Building Differential Pressure 0.75 inches Hg Drywell Pressure 1.70 psig Drywell Temperature 140 'T Torus Water Level 1.16 ft Torus Temperature- 72 'F Drywell/ Torus 0 Concentration 2.6% .
H15h Range containment Monitors 2.1 R/nr -
Containment Cas/ Particulate 600/60,000 cpm !
1 Reactor Building Vent Monitors Cas/Part 500/4,000 cpm '
Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uci/sec Stack can I/II 150/200 cpm High Range Noble Cad Monitor 0.1 mR/hr j pry i
R;v. O Page 6.2-2 g-t '
VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: Control Room Controller MESSAGE NO.: CR-M-1 TO: Control Room Communicator CLOCK TIME: Prior to 0700 LOCATION: Control Room SCENARIO TIME: 00:00 PARTICIPANT MESSAGE THIS IS A DRILL
, For initial conditions, see attached pages.
t, 1
j' '" 3 THIS IS A DRILL
(/
4 2502e
Rev. 0
/~ Page 1 of 3 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
1, The Reactor is now at approximately 100% rated power. The reactor has been operating steady state for the past sixteen months with no recent shutdowns.
- 2. Night orders for the operations crew are as follows:
- a. Containment de inerting has commenced on the previous shift for a scheduled power reduction and Drywell entry. Reactor Engineering staff has detereined that power reduction should not exceed 14 per 3 minutes,
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs) . RRUs 2 and 4 are showing abnormal amperage fluctuations, _
i
- c. The Auxiliary operators are changing the suction filters on the "B" Control Rod Drive (CRD) Pump.
- 3. All other power generating and safety system equipment is operable.
- 4. The following on site meteorological conditions exi. .: at 0700: 1 Wind Speed , sph (lower / upper) 2.8/5.6 Wind Direction , degrees (lower / upper) 10/348 Delta Temperature , 'F (lower / upper) . 0.7/.0.6 Ambient Temperature , 'F 53.4 Precipitation , inches 0.0 i
- l l
I
I Rev. 0 -
Page 2 of 3 i t
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late erning. High temperatures 75 to 80. Probability of precipitation less than lot.
A high pressure system centered over Pennsylvania this morning will drift to the southeast and slowly wee. ken during the day. This system will dominate the weather today.
4 I s s'
4
Rev. 0 fs Page 3 of 3
's ;
Initial Plant and Reactor System Values Reactor Vessel Coolant Level 162 inches Reactor Pressure - 1.006 psig Reactor Power . APRM (average) 1004 Core Plate Differential Pressure 20.0 paid Total Core Flow 46 mil lbs/hr Main Steam Line Flow Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr Condenser Hotwell Level 56%
Condenser Vacuum 2.6incheaHg(Abs)
Condensate Storage Tank Level 52% ,
Reactor Coolant Temperature 527 'T Recirc Drive Flow (average) 30,000 gpm Feedwater Flow 6.4 mil lbs/hr Reactor Building Differential Pressure 0.75 inches Hg Drywell Pressure 1.70 psig Drywell Temperature 140 'F Torus Water Level 1.16 ft Torus Temperature 72 'F Drywell/ Torus 0 Concentration 2.6%
High Range Containment Monitors 2.7 R/hr Containment Cas/ Particulate 600/60,000 cpm Reactor Building Vent Monitors Cas/Part 500/4,000 cpm Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr
- Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uci/see-Stack Cas I/Il 150/200 cpm
-High Range Noble Gas Monitor 0.1 mR/hr r y v
l 0, > . I
- n ' ' :
u' i o
Rev. 0-Page 6.2-3 j t??f!
VERMONT YANKEE NUCLEAR POWER STATION .
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS TROM: TSC Controller MESSAGE NO.: TSC-M-1 TO: TSC Coordinator CLOCK TIME: Upon TSC Activation LOCATION: TSC SCENARIO TIMEt PARTICIPANT MESSAGE THIS IS A DRILL ,
For initial conditions, see attached page..
\-
- p p
7 1;
THIS IS A DRILL 1502e i
k
I Rev. O i
,/ Page 1 of 3 VERMONT YANKEE NUCLEAR POWER STATION -
EKERCENCY RESPONSE PREPAREDNESS EXERCISE l
1990 i
INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The Reactor is now at approximately 1004 rated power. The reactor has been operating steady state for the past sixteen months with no recent shutdowns, i
- 2. Night orders for the operations crew are as follows: ,
- s. Containment de inerting has commenced on the previous shift for a scheduled power reduction and Drywell entry. Reactor Engineering staff has determined that power reduction should not exceed 14 per 3 minutes,
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reacto'r Recirculation Units (RRUs) . RRUs 2 and 4 are showing abnormal amperage i
fluctuations. -
- c. The Auxiliary Operators are changing the suction filters on the "B" control Rod Drive (CRD) Pump.
- 3. All other power generseir.6 and safety system equipment is operable, ,
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed , sph (lower / upper) 2.8/5.6 Wind Direction , degrees (lower / upper) 10/348 Delta 'issperature , 'F (lower / upper) 0.7/ 0.6 Ambient 'lemperature , 'F $3.4 Precipitation , inches 0.0 I
[.
I Rev. O Page 2 of 3 4
- 5. Regional Meteorological Forecast Information: ,
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. Hi5h t**Peratures 75 to 80. Probability of precipitation less than s 104.
i' A high pressure system centered over Pennsylvania this morning will drift to the southeast and slowly weaken during the day. This system will dominate 3 the weather today. ,
e 1
(, ,
f e
- '$'4
- c. '
, 3) t
'N-
l Rev. 0
/
Page 3 of 3 Initial Plant and Rameter System Valuaa Reactor Vessel Coolant Level 162 inches
- Reactor Pressure 1,006 psig j Reactor Power APRM (average) 1004 Core Plate Differentia 1' Pressure 20.0 psid Total Core Flow 46 mil lbs/hr Main Steam Line Flow Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr condenser Hotwell Level 56%
Condenser Vacuum 2.6 hvins H 6(16s)
Condensate Storage Tank Level 52%
Reactor coolant Temperature 527 'F Recirc Drive Flow (everage) 30,000 gpm Feedwater F) ,w 6.4 mil lbs/hr Reactor Building Differential Pressure 0.75 inches Hg Drywell. Pressure 1.70 psig ,
Drywell Temperature 140 'F Torus Water Level 1.16 ft Torus Temperature 72 'F Drywell/ Torus 0 Concentration 2.6%
High Range Containment Monitors 2.7 R/hr Containment Cas/ Particulate 600/60,000 cpm '
Reactor Building Vent Monitors Gas /Part 500/4,000 epa Reactor' Building Vent Exhaust N/S 1.5/1.5 mR/hr i
' Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uci/sec Stack Gas I/II 150/200 cpm High Range Noble Gas Monitor 0.1 mR/hr '
l i
l .
Rove 0 +
Page 6.2-4 VERMONT YANKEE NUCLEAR POWER STATION -
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROMt TSC Controller MESSAGE NO. TSC-M-2A TO: TSC Coordinator CLOCK TIME: Upon Assignment of Data Recorder LOCATION: TSC SCENARIO TIME PARTICIPANT MESSAGE THIS IS A DRILL To obtain plant computer parameters that are normally available to TSC staff, use the Controller / Observer telephone in the Plant Computer Room to request the information from the Simulator Computer Room.
l i
l l
l l
l
- ~; THIS IS A DRILL I
~.
2502e j i
l Rev. O Page 6.2-5 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990
. i SCENARIO MESSAGE CARDS l FROMt TSC Controller ,
MESSAGE NO.t TSC-M-2B TO: TSC Coordinator CLOCK TIME: Upon Assistnment of Communicators LOCATION: TSC SCENARIO TIME:
PARTICIPANT MESSAGE THIS IS A DRILL
_After assigning your TSC Communicators to the Control Room, the prestaged 150 Communicators at the Simulator Control Room will be made available.
(
(D.f i
,tHIS IS A DRILL 2502e
I 1
Rev. O Page 6.2-6 l e ' ' s, !
'\ , , I i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSACE CARDS FROM OSC Controller MESSAGE NO. OSC-M-1 TO: OSC Coordinator CLOCK TIME: Upon OSC Activation LOCATION: OSC SCENARIO TIME:
PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages.
k;. . -t- ,
f i
j; } THIS IS A DRILL 2502e
1 Rev. 0 ,
A '
Page 1 of 3
(
VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 i
INITIAL CONDITIONS (This information will be provided to the players at the start of the exercise).
- 1. The Reactor is now at approximately 100% rated power. The reactor has ,
been operating steady state for the past sixteen months with no recent shutdowns.
- 2. Night orders for the operations crew are as follows:
r
- a. Containment de.inerting has coassenced on the previous stift for a .
scheduled power reduction and Drywell entry. Reactor Engineering staff has determined that power reduction should not exceed _1% per 3 minutes,
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs) . RRUs 2 and 4 are showin5 abnorsal amperage fluctuations,
- c. The Auxiliary Operators are changing the suction filters on the "B" -
Control Rod Drive (CRD) Pump.
- 3. A'.1 other power generat!?g and safety system equipment is operable.
- 4. 'the following on site meteorological conditions exist at 0700:
Wind Speed , aph (lower / upper) 2.8/5.6 .
Wind Direction , degrees (lower / upper) 10/348 Delta Temperature , 'F (lower / upper) 0.7/.0.6 Ambient Temperature , 'F 53.4 J
((['; Precipitation , inches 0.0
, 'c i
e
Rev. O Page 2 of 3
{ '.
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than 104.
A high pressure system centerod over Pennsylvania this morning will drif t to the southeast and slowly weaken during the day. This system will dominate the weather today.
Y
.,r O
E 4
e t
I l
l l
Rev. 0
(,F'}' Page 3 of 3 y.
Initial Plant and Reactor System Values ;
Reactor Vessel Coolant Level 162 inches Reactor Pressure 1,006 poig Reactor Power APRM (average) 1004 Core Plate Differential Pressure 20.0 paid Total Core Flow 46 mil lbs/hr i Main Steam Line Flow Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr Condenser Hotwell Level 56%
Condenser Vacuum 2.6 inches Hg(AL )
Condensate Storage Tank Level 52% ,
' Reactor Coolant Temperature 527 'T <
Recirc Drive Flow (average) 30,000 gpm Feedwater Flow 6.4 mil lbs/hr Reactor Building Differential Pressure 0.75 inches Hg Drywell Pressure 1.70 psig
.Drywell Temperature 140 'F Torus Vater Level 1.16 ft Torus Temperature 72 'F Drywell/ Torus 0 Concentration 2.6%
High Range Containment Monitors 2.7 R/hr Containment Cas/ Particulate 600/60,000 cpm Reactor Building Vent Monitors Cas/Part 500/4.000 cpm Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr .
Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uci/sec 5
Stack Gas I/II 150/200 cpm High Range Noble cas Monitor 0.1 mR/hr w
1
I l
R:v. 0 Page 6.2-7 i l "-
) '
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MEbSAGE CARDS i
FROM SRM Controller MESSAGE NO.t SRM-M-1 TO: Site Recovery Mananer CLOCK TIME: Upon Activation
- i LOCATION: RC SCENARIO TIMEt PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages.
.(~~
, THIS IS A DRILL ,
2502e l'
t -r a
4-i key, 0 Page 1 of 3 VERMONT YANKEE NUCLEAR POWER STATION ,
EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 INITYAt.CONDIT1QHj, (This information will be provided to the players at the start of the exercise).
- 1. The Reactor is now at approximately 1004 rated power. The reactor has been operating steady state for the past sixteen months with no recent shutdowns.
- 2. Night orders for the operations crew are as follows: ,
- a. Containment de inerting has commenced on the previous shift for a .
scheduled power reduction and Drywell entry. Reactor Engineering staff
(, '
has determined that power reduction should not exceed in per 3 minutes,
- b. The Drywell entry is needed to accomplieh repairs to the Drywell Reactor ,
Recirculation Units (RRUs) . RRU. .d 4 are showing abnormal amperage fluctuations,
- c. The Auxiliary Operators are changing the suction filters on the "B" Control Rod Drive (CRD) Pump.
3.- All other power generating and safety system equipment is operable.
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed , aph (lower / upper) 2.8/5.6 Wind Direction , degrees (lower /upp.or) 10/348 Delta Temperature , 'F (lower / upper) . 0.7/ 0.6 Ambient Temperature , 'F 53.4 i Precipitation , inches 0.0 i I
i 1
6
~..s Rev. O
{
Page 2 of 3
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than 104.
A high press re system centered over Pennsylvania this morning 'till drift to the southeast, and slowly weaken during the day. This system will dominate the weather today.
f s.
E Rev. 0 ,
Page 3 of 3 '
7 Initial Plant and Reactor System Values Reactor Vessel Coolant Level 162 inches ,
Reactor Pressure 1,006 psig l Reactor Power + APRM (average) 1004 Core Plate Differential Pressure 20.0 paid ,
Total Core Flow 46 mil lbs/hr s Main Steam Line Flow Total 6.2 mil lbs/hr Main Steam Line Radiation 194 mR/hr ,
Condenser Hotwell Level 56%
Condenser Vacuum 2.6 inches Hg(Abs)
Condensate Storage Tank Level 52%
Reactor Coolant Temperature 527 'F Recirc Drive Flow (average) 30,000 gpm f Feedwater Flow 6.4 mil lbs/hr Reactor Building Differential Pressure 0.75 inches Hg Drywell Pressure 1.70 psig Drywell Temperature 140 'F Torus Water Level 1.16 ft Torus Temperature 72 'F Drywell/ Torus 0 Concentration 2.6%
High Range Containment Monitors 2.7 R/h_r Containment Cas/ Particulate 600/60,000 cpm .
Reactor Building Vent Monitors Cas/Part 500/4,000 cpm l Reactor Building Vent Exhaust N/S ,
1.5/1.5 mR/hr ,
l' Steam Jet Air Ejector 270 mR/hr* 1 SJAE Discharge Rate 50,000 uCi/sec
\ 150/200 cpm
- Stack Cas I/II ,
l High Range Noble cas Monitor 0.1 mR/hr I
,e l
L 1
l l
j L Rev. 0 Page 6.2-8 ;
- (' ,
VERMONT YANKEE NUCLEAR P0k'ER SYATION EMERGENCY RESPONSE PREPAREDNEcs EXERCISE 1990 ,
SCENARIO MESSAGE CARDS ,
FROMt EOF Controller MESSAGE NO. EOF-M-1 ,
TO: EOF Coordinator CLOCK TIME: Upon Activation LOCATION: EOF SCENARIO TIME:
PARTICIPANT MESSAGE THIS IS A DRILL For initial conditions, see attached pages.
+
e
() ,THIS IS A DRILL 2502e i*
I Rev. 0 Page 1 of 3 i
i VERMONT YANKEE NUCLEAR POWER STATION -
EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 INITTA1 CONDITIONS (This information will be provided to the players at the start of the j exercise). )
- 1. The Reactor is now at approximately 1004 rated power. The reactor has l been operating steady state for the past sixteen months with no recent shutdowns.
- 2. Night orders for the operations crew are as follows: l 1
i
- a. Containment de inerting has commenced on the previous shift for a I
. l scheduled power reduction and Drywell entry. Reactor Engineering staff ;
1
^ has determined that power reduction should not exceed 14 per 3 minutes.
I l
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor Recirculation Units (RRUs) . RRUs 2 and 4 are showing abnormal amperage fluctuations,
- c. The Auxiliary Operators are changing the suction filters on the "B" Control Rod Drive (CRD) Pump, ,
L
- 3. All other power generating and safety system equipment is operable.
- 4. The following on site meteorological conditions exist at 0700:
Wind Speed , sph (lower / upper) 2.8/5.6 Wind Direction , degrees (lower / upper) 10/348 Delta Temperature , 'F (lower / upper) 0.7/ 0.6 Ambient Temperature , 'F 53.4 S Precipitation , inches 0.0 i
Rev. 0
/ Page 2 of 3
- 5. Regional Meteorological Forecast Information:
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than 104.
A high ITossure system centered over Pennsylvania this morning will drif t to the southeast and slowly weaken during the day. This system will dominate the weather today.
l lx !
, ,_ .S s <
Rev. O !
(( Page 3 of 3 i
4 1
initini .inne and R ;_ tor System Values Reactor Vessel Coolant Level 162 inches R6 actor Pressure 1,006 psig b actor Power . APRM (average) 1004 Core Plate Differential Pressure 20.0 psid Total Core Flow 46 mil lbs/hr Main Steam Line Flow Total 6.2 mil lbs/hr Main Stsaa Line Radittion 194 mR/hr l Condenser Hotwell Level 566 Condenser Vacuum 2.6 inches lig(Abs)
Condensate Storage Tank Level 52%
Reactor Coolant Temperature 527 'F l Recirc Drive Flow (average) 30,000 gpm l
{ Feedwater Flow Reactor Building Differantial Pressure 6.4 mil lbs/hr 0.75 inches Hg I
trywell Pressure 1.70 psig l Drywell Temperature 140 'T -
Torus Water Level 1.16 ft l Torus Temperature 72 'F Drywell/Torua on Concentration - 2.6%
High Range Containment Monitors 2.7 R/hr Containment Cas/ Particulate - 600/60,000 cpm I Reactor Building Vent Monitors Cas/Part 500/4,000 cpm Reactor Building Vent Exhaust N/S 1.5/1.5 mR/hr Steam Jet Air Ejector 270 mR/hr
-SJAE Discharge Rate 50,000 uci/sec ;
Stack Gas 1/11 150/200 cpm High Range Noble Gas Monitor 0.1 mR/hr D
I 4
Rev. O Page 6.2-9
['
i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSACE CARDS ,
l PROM ESC Controller MESSACE NO. ESC-M-1 __
TO: ESC _ Director CLOCK TIME: Upon Activation :
LOCATIONI Enaineerina Support Center SCENARIO TIME:
PARTICIPANT MESSAGE l THIS IS A DRILL For initial conditions, see attached pages.
MS 7; THIS IS A DRILL ,, 1 2502e I
[
s Rev. O _;
Page 1 of 3 l VERMONT YANKEE NUCL. EAR POWER STATION !
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 t INITIAL CONDITIONS (This information will be provided to the players at the start of the i exercise).
~
- 1. Thi Reacter is now at approximately 100% rated power. The reactor has been operating steady state for the past sixteen months with no recent shutdewns. I
- 2. Night orders for the operations crew are as follows:
- a. Containment de-inerting has commenced on the previous shift for a scheduled power reduction and Drywell entry. Reactor Engineering staff has determined that power reduction should not exceed it per 3 minutes.
- b. The Drywell entry is needed to accomplish repairs to the Drywell Reactor '
i Recirculation Units (RRUs) . RRUs 2 arid 4 are showing abnormal amperage fluctuations.
I c. The A.uxiliary Operators are changing the suction filters on the "B" Cc 4 trol RM Pri.; (CD) Pump.
- 3. ail other power generating and safet.y system equipment is operable.
- 4. The following on site meteorological conditions exist at 0700:
' Wind Speed , aph (lower / upper) 2.8/5.6 Wind Direction ,~ degrees (lower / upper) 10/348 Delta Temperature , 'F (lower / upper) -0.7/ 0.6 Ambient Temperature , 'F 53.4 Precipitation , inches 0.0 I
m
, y ,.. _ _ . _
J. .t .:'- ,.
f Rev. O
"', Page 2 of 3
- 5. Regional Meteorological Forecast Information: ,
Mostly sunny today with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75 to 80. Probability of precipitation less than
..I 104. [
A high pressure system centered over Pennsylvania this mornin6 will drift to the southeast and slowly ucaken during the day. This system will dominate the weather today, 1 h
r
(?%
L I
e .
Rev. 0 Page 3 of 3
{"3-Initial Plant and Reactor Svatam Values Reactor Vessel Coolant 14 vel 162 inches o, Reactor Pressure 1,006 psig. !
l Reactor Power APRM (average) 1004 j Core Plate Differential Pressure 20.0 psid Total. core Flow 46 mil lbs/hr i Main Steam Line Flow Total 6.2 mil lbs/hr -j.
Main Steam Line Ra'diation 194 mR/hr j Condenser Hotwell Level 56% !
' Condenser Vacuum 2.6 inches Hg(Abs)
Condensate Storage Tank Level 526-Reactor Coolant Temperature 527 'F j
.Recire Drive Flow (average) 30,000 gpm i d,,z Feedwater' Flow 6.4 mil lbs/hr:
Reactor-Building Differential Prescure -0.75 inches Hg- ,
Drywell Pressure 1.70 psig !
Drywell= Temperature 140 'F .
To'rus Water Level- 1.16 ft h-
-Torus Temperature 72 'F
.Y
~ Drywell/ Torus 0 Concentration 2.6%
.High Range Containment Monitors 2.7 R/hr Containment Cas/ Particulate 600/60,000 cpm (
Reactor'Buildf.ng Vent Monitors Cas/Part 500/4,000 cpm Reactor Building Vent Exhaust N/S1 1.5/1.5 mR/hr
" Steam Jet Air Ejector 270 mR/hr SJAE Discharge Rate 50,000 uCi/sec Stack Gas I/II' 150/200 cpm High Range Noble Gas Monitor 0.1 mR/hr i
O
e Rev. 0 Page 6.2-10 ,
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990-SCENARIO MESSAGE CARDS FROMt Simulator CR Controller MESSAGE NO.: SCR-M-2 TO: Shift Supervisor CLOCK TIME: 0730
. LOCATION: Simulator CR SCENARIO TIME: 00:30 PARTICIPANT MESSAGE THIS IS A DRILL i
Guard House called to report that they sensed the ground moving and that abnormal river motion was observed.
A plant technician who was working in the Soath Warehouse called to report -
that be felt the floor moving and several items rattled on the storage racks.
h !
l 1
l l
l THIS IS A DRILL
.- 2502e l
)
4 Rev. O Page 6.2-11 17:,
('; ' ,
I VE?MONT YANKEE NUCLEAR POWER STATION EMERGEdOY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS
.i FROM: Simulator CR Controller MESSAGE NO. SCR-M-3 I
TO: Shift Supervisor CLOCK TIME: 0735 LOCATION: Sihiulator CR SCENARIO TIME: 00:35 PARTICIPANT MESSAGE j i
THIS IS A DRILL' i Auxiliary Operator reports a positive indication on the seismic accelerometer. .
s
,r? * -
t' ' ..s-: 1 i
~.
a i
s
, wr THIS IS A DRILL O 2502e j i
l s l
\-
. 5 i
Rev. O Page 6.2-12 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: Simulator CR Controller MESSAGE NO. SCR-M-4 T0: Shift Supervisor CLOCK TIME: Approximately 0740 -
IhCATION: Sjim:1stor CR SCENARIO TIME: 00:40 PARTICIPANT MESSAGE THIS IS A DRILL Dam personnel from the Vernon and Bellows Falls Dams have been cont--ted and report that they have observed abnormal river motion, but the dan .s intact and exhibit no signs of damage or failure.
?%
Qh' s
=
2502e I
I i
Rev. O ;
Page 6.2-13 !
i
.(Sk
. :;/.
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAG: NO.: OSC-M-2 ,
to: A0 or Plant Personnel CLOCK TIME: Approximately 0750 ,
Investinating Earthquake Damage et as needed LOCATION: Plant Site SCENARIO TIME: 00:50 l PARTICIPANT MESSAGE THIS IS A DRILL Upon inspection for damages caused by the earthquake, you have noticed no ,
visual damage to plant equipment.
'ts
',j THIS IS A DRILL
( f) 2502e i
T.
Rev. 0 I Page 6.2-14
(??r Qv)
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 I
SCENARIO MESSAGE CARDS FROM OSC Observer MESSAGE NO. OSC-M-3 701 On-Site Assistance Team CLOCK TIME: Approximately 0830- l or as needed i
LOCATION: Resetor Building SCENARIO TIME 01:30 !
i PARTICIPANT, MESSAGE
-i THIS IS A DRILL Team investigating problem with the "A" CRD pumps
- o. Visual inspection of the "A" CRD pump breaker reveals the relay is burnt. .
o Estimeted time to repair the breaker is approximately one hour.
9
' 'h ,
6 4
TMIS IS A DRILL 2502e
Rev. 0
-.,.- Page 6.2-15 l] i
- VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS-FROM: - OSC_.__Obse rver MESSAGE NO.: OSC-M-4 TO: A0 or On-Site Assistance Team CLOCK TIME: Approximately 0830 or as needed LOCATION: Reactor Building. El. 232'-6" SCENARIO TIME: 01:30 PARTICIPANT MESSAGE THIS IS A DRILL Estimated time to complete the suction filter change on the "B" CRD pump is approximately one hour.
l- ;,
N.;l l
I N .,
.. r-6./> THIS IS A DRILL
%:W 2502e
')
ot h-l I
i_
v?
Rev. 0 9,p Page 6.2-16 VERMONT YANKEE NUCLE.AR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1990 l
1 l
- SCENARIO MESSAGE CARDS FROM: News Media Center Observer MESSAGE NO.: NMC-M-1 j TO - News Media Center Staff CLOCK TIME: 0845 LOCATION: News Media Center SCENARIO TIME: 01:45 PARTICIPANT MESSAGE THIS IS A DRILL (The following information was heard on the local radio stations and local television network.)
This morning an earthquake was felt in soVeht:0 Vermont at around 7:30 a.m.
The New England Seismic Network estimated the mast.itude at 4.8 on the Richter
. scale. The epicenter was located near the town of Norti. field, Massachusetts 7-(latitude 43 degrees, 43 minutes and longitude 72 degrees, 28 minutes)
-( approximately 11 to 12 miles southeast of Bratthtoro, Vermont. No casualties
,or road and bridge damage have been reported, ~.: cording to local Brattleboro officials. However, several chimneys have fa; en and telephone service was temporarily interrupted in the Greenfield, ML sachusetts area. Scientists
- f rom the New England Seismic Network have also stated- that af ter shocks may be
, felt throughout the day.
' While it may be surprising to most people, an average of five earthquakes are
. . felt somewhere in New England each year. The probabilities of a damaging earthquake occuring somewhere in New England are small by worldwide standards. The chances that a potentially damaging earthquake, of equal or greater value than the one that occurred today will repeat somewhere in New England, are 1 in 300 per year.
l THIS IS A DRILL
. e# - 2502e I t
!i A
Rev. O Page 6.2-17
. VERMONT YANKEE NUCLEAR POWER STATION-EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-M-5 1 TO: On-Site Assistance Team CLOCK TIME: Approximately 0935 or as needed LOCATION: Reactor Building SCENARIO TIME: 02:35 l
PARTICIPANT MESSAGE THIS IS A DRILL Repairs to the CRD pump are completed. The CRD pump is operable and can be returned to service.
l
(""- . 1
\s - l l
l l
l s
2502e' l
'l 1
I 1
~~
, g Rev. O Page 6.2-18
- ,q -
gyw ' ' ~
VERMONT YANKEE NUCLEAR POWER STATION -
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: ESC Controller MESSAGE NO.: ESC-M-2 TO: ESC Meteorologist CLOCK TIME: 1040 or as requested LOCATION: ESC Yankee Atomic Electric Co. SCENARIO TIME: 03:40 PARTICIPANT MESSAGE THIS IS A DRILL Utilize the attached meteorological information to generate the weather forecast for the site.
't l
" 6, THIS IS A DRILL 2502e i
l
I '
e J Rev. 0 Page 6.2 ,l j
WEATHER FORECAST FOR SITE: VERMONT YANKEE Date of Forecasts Time of Forecast: _,1000 Current Site Meteorology (as of 0945 ):
Delta-Wind Speed Wind Direction Temperature Stability Precipitation Lower ,
4.9 mph 10 deg from -1.5 0F C 0.00 in/15 min '
Upper 5.4 mph 345 deg from -1.5 0F D Forecast Site Meteorology:
i Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation A. 1000- Lower 4 mph 350 deg from --
0F C' O.00in/15 min 1100 Upper 8 mph 345 deg from --
0F D
- B. 1100- -Lower 6 _ mph 330 ,deg from -- 0F B 0.00in/15 min '
1200 Upper 10 mph 335 deg from --
0F C
.c b' C.- 1200- Lower 5 mph 320 deg from~ --
0F B 0.00in/15 min 1300 Upper -10 mph 315 deg from -- 0F C National Weather. Service Forecast for site region:
f Mostly sunny today,_with' variable winds becoming northwest 5 to 10 mph by_ late-morning. High temperatures will be 75'F to 80'.F. Probability of precipitation less Lthan 10%.
A high pressure system centered over Pennslyvania'this morning will drift to the southeast.and slowly weaken during the day. This system.will dominate-the wedther
~today.
,i Special Weather Statements: .
, Winds ~predominantly from the north to north northwest. Neutral to slightly unstable conditions'should persist throughout the day. j i
t i
2502e
Rev. 0 l7 Page 6.2-20
- l-. '
VERMONT YANKEE NUCLEAR POWER STATION -
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS r10M: OSC Observer MISSAGE NO.: OSC-M-6 TO: On-Site Assistance Team CLOCK TIME: Approximately ~1215 or as needed LOCATION: Reactor Building. El. 252' - SCENARIO TIME: 05:15 South Side PARTICIPANT MESSAGE THIS IS A DRILL
, \
Upon arrival at the south side to the Reactor Building, El. 252', you observe the following:
--(, . ,, o You can hear a hissing. sound coming from the south wall of the Reactor Building.
o Upon looking up near the south wall, you see the bottom flange of Valve V16-19-9 dinlodged, r
4 1
1 1
l l
l
- y. ,
/ .THIS IS A DRILL 2502e
s .
Rev. O Page 6.2-21 L
(..-a
(:
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS ".XERCISE 1990 SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO.: OSC-M-7 TO: On-Site Assistance Team CLOCK TIME: Approximately 1215 ,
or as needed LOCATION: Torus Catwalk - Torus Purge SCENARIO TIME: 05:15 Supply Valve (V16-19-10)
PARTICIPANT MESSAGE THIS IS A DRILL ;
-Visual inspection of the valve reveals that the valve indication is open.
(
k THIS IS A DRILL 2502e
(
i
a
'?* .
Rev. 0 Page 6.2-22
[Y.,
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: ESC Controller MESSAGE NO.: ESC-M-3 Tn. ESC Meteorologist CLOCK TIME: 1230 or as requested LOCATION: ESC Yankee Atomic Electric Co. SCENARIO TIME: 05:30 PARTICIPANT MESSAGE THIS IS A DRILL Utilize the attached meteorological information to generate the weather forecast for the site.
I 1
1 l
THIS IS A DRILL
{" '
l 2502e i
i ji Rev. O Page 6.2-23 j;%
WEATHER FORECAST FOR SITE: VERMONT YANKEE.
Date of Forecast:
Time of Forecast: 1200 Current Site Meteorology (as of 1130 ):
Delta-Wind Spe(d Wind Direction Temperature Stability Precipitation-Lower 2.9 mph 309 deg from -2.1 0F A 0.00 in/15 min i Upper 6.2 mph 310 deg from -2.3 0F C Forecast Site Meteorology:
4 Delta-Time Wind Speed Wind Direction Temperature Stability Precipitation A. 1200 Lower 6 mph 310 deg from -- 0F B 0.00in/15 min i 1300 Upper 12 mph 320 deg from -- 0 F. C B. 1300 Lower 6 mph 310 deg from -- 0F A 0.00in/15 min 1400 Upper 10 mph 320 deg from -- 0F B ff, C.; 1400 Lower 5 mph 308 deg from -- 0F P 0.00iu/15 min I 1500- Upper 10 mph 325 deg from -- 0F C-
- National Weather Service Forecast for-site region:
3 Mostly sunny and warm this afternoon with a high-near 80*F. Northwest winds 5 mph 1 to 10 mph. Mostly clear tonight with a low around 55'F. Winds becoming light _and- I variable, ,
1 Tomorrow, becoming cloudy with showers. Highs in the mid 70's. Winds-becoming i south to southwest 10 mph to 15 mph.
Special Weather Statements:
i
-k$ . 2502e ,
1 1
l
t Rev. O Page 6.2-24 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 SCENARIO MESSAGE CARDS FROM: EOF /RA Controller MESSAGE NO : EOF-M-3 TO: Radiological Assistant CLOCK TIME: As Requested (Approximately 1230)
LOCATION: EOF / Dose Assessment Area SCENARIO TIME: 05:30 PARTICIPANT MESSAGE THIS IS A DRILL 12:00-18:00 - General Area Forecast Mostly sunny and warm this af ternoon with a high near 80'F. Northwest winds ,
5 mph to 10 mph. Mostly clear tonight.with a low around 55'F. Winds becoming l
. light and variable.
Tomorrow, becoming cloudy with showers. Highs in'the mid 70's. Winds
-f becoming south to southwest 10 mph to 15 mph.
l l
l I
i 1
? THIS IS A DRILL 2502e i
Rev. O Page 6.2-25 VERMONT YANKEE NUCLEAR POWER STATION ,
EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 i SCENARIO MESSAGE CARDS FROM: OSC Observer MESSAGE NO. OSC-M-8 TO: On-Site Assistance Team CLOCK TIME: Approximately 1300 or as needed LOCATION: Torus Catwalk - Torus Purge SCENARIO TIME: 06:00 Supply Valve (V16-19-10)
PARTICIPANT MESSAGE THIS IS A DRILL Upon completing repair efforts on the torus purge supply valve (V16-19-10).. .
you observe the following o You hear the air vent off from the valve and the valve will shut.
(-"
o Valve indication is showing closed position. .
I 1
l l
l THIS IS A DRILL
(
2502e t
Rev 0
-Page 6.2-26 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE I
1990 SCENARIO MESSAGE CARDS FROM s . 0SC Observer MESSAGE NO. OSC-M-9 TO: On-Site Assistance Team CLOCK TIME: Approximately 1300 or as needed LOCATION: Reactor Building .El. 252' - SCENARIO TIME: 06:00 South Side ,
PARTICIPANT MESSAGE THIS IS A DRILL NOTE: (Message card should be given to team only if the team proceeded to the south side of'the Reactor building, El. 252', before fixing the valve and team is located near the south side of the Reactor Building.)
. ..m
- ' ~
You hear no more hissing sound from the south wall of the Reactor Building,-
El. 252'.
s-THIS IS A DRILL 2502e jI
- a. .
4 - ..s a p =
?-
l
,.3
'/-~
P VERMONT YANKEE NUCLEAR POWER STATION
, EMERGENCY RESPONSE PREPAREDNESS EXERCISE
, 1990 1
l
-7.0 STATION EVENT DATA
( '.
O i
6 1
l l
l l'
l I
f ,,
E .
1 l l .
l l 1-
4 I
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 4
-I ~
'1990 T
7.1 EVENTS
SUMMARY
. j i
i l
y l
l 1
1
- 3,
ii!
4 Rev. O cb il Page 7.1-1 i
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 7.1 EVENTS
SUMMARY
The following information and supplementary material are provided for the Controllers /Obscrvers having in plant control assignments to ensure the proper development of the scenario. The information provided in this section assumes-that the " players, who are dispatched to perform repair, rescue, or other setivities,. will take certain actions in response to the scenario event. The controller / Observer must be cognizant of the actions of the players which assignments are given and provide information regarding the results of the ,
players actions as appropriate. The information provided in this section does not preclude the possibility that the Controller / Observer will be required
( co provide additional information to the players.
Approximate-Miniscenario -Time Event Location 7.2.1 0830 Plant Damage Assessment Reactor Bldg.
o CRD Pumps and Switchgear Room 7.2.2. 1200 Plant Damage Assessment Reactor Bldg. ,
o Torus Purge Supply and Torus Catwalk Valve (V16-19 10)
Inspection and Repair 4 6 i
-lI; 1
(L ,
..z .
,C.k- " . ..E i
4 1
VERMONT YANKEE NUCLEAR POWER STATION ENERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 l
l 1
i ;
..i; i
'1 7.2. EVENT MINISCENARIOS l 1
?
m >y., l
~l
.)
o l
i N
1 9
Rev. 0'
( ... ],' Page 7.2.1 1 VERMONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990 l
Miniscanario 7.2.1
. I. General Descrintion f The plant is in an Alert classification due to an ATWS condition. At 0830 ,
while operators are driving in control rods, the "A" CRD-Pump trips due to a breaker - problem, It is expected that plant personnel will be l
dispatched to investigate the ptoblem with the "A" CRD Pump or expedite the completion of the suction filter replaceae : on "B" CRD Pump.
' 11. Descrintion of Plaver Resnonses/ Observations / Corrective Actions ;
i p.
{;j,' The. Shift Supervisor should immediately inform the TSC Coordinator that.
the both the "A" and "B".CRD Pumps are not available to drive in control ;
e rods, The TSC Coordinator should direct plant personnel to investigate the l problem with the "A" CRD' Pump and to determine the status and completion j of the suction filter replacement on the "B" CRD Pump.
The plant personnel investi 5ating the problem with the "A" CRD Pump will determine that the relay in the "A" CRD Pump breaker cubicle has been burned out. The replacement of the relay will take approximately one hour l to complete the repairs (refer to Message Card OSC M.3). It will also be determined that the status of completing the suction filter change on the "B" CRD Pump is approximately one hour (refer to Message Card OSC M 4).
The TSC Coordinator may dispatch plant personnel to assist with the suction !
filter change or discuss alternative methods to allow for the "B" CRD Pump to be returned to service as soon as possible.
?
e 9
f_ _f,Q-Q:ijj
- c; ,,
C .4 Rev. O Page 7.2.1 2
%'[-
III. Event Clomeout Due to the interactive nature of this event, the actions taken by plant 4 -l E personnel will determine when the CRD Pumps are declared operable and g returned to service. The event will be completed upon returning one of i
the CRD Pumps back into operation (refer to Message Card OSC M 5).
p i
-,I ,
jlYf
' ;g :
i ;j 4
i1
)'.
l Rev. O h
.w.!
Page 7.2.2 1
}
VERMONT YANKEE NUC1. EAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990
.I l
Miniscenario 7.2.2
. I. General Descriotion 3.,
At approximately 1135, the simulator control board will indicate that the Torus Purge Supply Valvo (V16-19 10) did not close on Croup 3 isolation.
Reactor operator attempts to isolate the Torus Purge Supply Valve are unsuccessful. It is also apparent that there is a leak in the Reactor Building as indicated by significantly elevated Reactor Building ARMS and the Plant Vent Stack monitor readings increasing. It is anticipated that
- on site assistance team (s) will be dispatched to investigate the leak in-the Reactor Building and the problem associated with the Torus Purge Supply i (g.l Valve (V16 19-10).
II.. Descriotion of Player Rernonses/ Observations / Corrective Actions The Shift Supervisor should inform the TSC Coordinator and the Site 1 Recovery Manager (SRM) that the Torus Purge Supply Valve (V16 19-10) did not. close on Croup 3 isolation and attempts ~ to isointe the valve were unsuccessful. The TSC Coordinator, with consultation from the Shif t Supervisor and SRM, should dispatch on site assistance teams to investigate the leak into the Reactor Building and the problem associated with the Torus Purge Supply Valve (V16 19 10). Discussions on emergency exposure concerns, radiological exposure control, dose commitments, in plant radiological conditions and task assignments should occur prior to dispatching the teri(s).
It is expected that the on site assistance team will be directed to go to the Torus Purgo Supply Valve (V16-19-10) located on the Torus Catwalk.
There are two possible ways of accessing the Torus Catwalk by entering the i
'1 I
+- -
e .l 1
Rev. O Page 7.2.2 2 1
Reactor Building EL 252 (ground floor) and proceeding to the northwest access . hatch or . southeast access hatch. Upon entrance to the Reactor Building,. the team will encounter elevated radiation levels (refer to the i appropriate Tables and Figuras in Section 9.3). l If the team initially utilizes the southeast access hatch to the Torus Catwalk or. proceeds to the south side. of the Reactor Building EL 252, the team will be told that they can hear a hissing sound coming from the south j wall. The team will also be told upon looking up near the south wall, they can see the bottom flange of Valve V1619 9 dislodged (refer to Message I
Card OSC M 6). However, if the team initially utilizes the northwest access hatch to the. Torus Catwalk and does not proceed to the south side of Reactor Building EL 252, the team will only encounter the elevated radiation l'evels, !
a Upon proceeding to the Toruo Catwalk and locating the Torus Purge Supply
.* ].
, Valve (V16 19 10),. the team will fit. ' chat the valve indication is open. 1 1 (refer to Message Card OSC M-7). werective actions to close the valve will be expected to occur by the team, When repair efforts are successfully completed, the team will be cold.that they can hear the air vent off from the valve and the valve will shut. The team will also be told that the valve indication is in the close position (refer to OSC-M 8), If the team .i exits the south side of the Reactor Building and' initially entered the south side before closing the valve, the team will also be told that they cannot hear the hissing sound from the south wall (refer to Message Card OSC M 9).
- III.
Event Closcout The on site assistance team will have successfully shut the Torus Purge Supply Valve (V16 19 10). Simulator control board will also show that the Torus Purge Supply Valve (V16-19 10) has closed, The leakage into the Reactor Building has been isolated.
o ,
l l
.gr
.) .
VEPJ40NT YANKEE NUCLEAR PO*.'ER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990
- I 8.0 OPERATIONAL DATA EQIE1 The operational data is highly dependent on operator actions taken in response to the conditions presented within the scenario. The f operational data reflects plant conditions assuming certain basic
- \; operator response actions being taken. The operational data was 4
taken from ene plant simulator. 3 1
l.
i I
i
/^ !
i f G
[^ Vthee0NT VANKit NUCLEAR PWER STAfl0N kfV. 1 EMthGENCY RESP 0hlt PREPAktDNils Extacist PAGE 8.0 1 1990 8.0 OPttATIONAL DAIA SCENAtl0 flME 00:00 00:15 00:30 00:45 01:00 01:15 01:30 01:45 CLOCK TIME 07:00 07:15 07:30 07:45 08:00 08:15 08:30 08:45 litM PANtt INtf ID DtstelPfl0N Units 1 93 FT 23 108*1 NPCI FLN GPM 0 0 0 0 0 0 0 0 2 93 Fl.10 139A RNR A FLW GPM 0 0 0 0 0 0 0 0 3 93 F1 10 1398 RNR B FLOW ops: 0 0 0 0 0 0 0 0 4 93 Fl.14 50A Ct A FLOW GPM 0 0 0 0 0 0 0 0 5 93 Fl.14 50s CS B FLOW OPM 0 0 0 0 0 0 0 0 6 93 PI 16 19 12A DRYWELL Ptt99URE PSIA 17 17 17 17 14 16 16 16 7 93 PI 16 19*129 DRYWELL PRESSUht PSIA 17 17 17 17 16 16 16 16 8 94 Fl.13 91 RCIC FLOW CPM 0 0 0 0 0 0 0 0 9 94 fl 12 141A RWCU FLW OPM 60 60 60 60 0 0 0 0 10 94 Fl.12 141B RWN FLOW GPM 60 60 60 60 0 0 0 0 11 94 2 165A RK COOLANT ftMP DEC F 527 527 527 $27 532 517 524 521 '
12 94 2 1650 RX CODLANT YtMP DEG F $27 527 527 527 532 517 524 521 13 94 2 159A htCIRC A LOOP fin KGPM 30 30 30 30 30 0 0 0 14 94 2 1598 RECIRC D LOOP FLOW KGPM 30.1 30.1 30.1 30.1 30.1 0 0 0, 15 95 7 46A ArtM/lkM A X 100 100 100 100 65 13 13 13 16 95 7 46e AraM/laN e 1 99 99 99 99 65 13 13 135 17 95 7 46C APRM/lkM C X 100 100 100 100 65 13 13 13 18 95 7 460 APAM/lkN O E 100 100 100 100 65 13 13 13 19 95 7 46E APRM/thM E X 101 101 101 101 66 13 13 13l
( 20 95 7*46F APRM/lkM F 1 101 101 101 101 66 13 13 13 k 21 95 7 434 $RM A CPS 352000 352000 352000 352000 130000 9730 9410 9410 '
22 95 7*438 san t cps 429000 429000 429000 428000 146000 10700 10300 10300 23 95 7 43C seN C CPt 506000 _506000 506000 505000 174000 11500 11500 11500l 24 95 7 43n snM o cps 397000 397000 397000 396000 141000 (800 9800 9800 25 95 2 3 9) Coat FLOW MLB/NR 47 47 47 47 54 8 2 2 26 95 2 3d$ Coat DP PsID 21 21 21 21 23 4 3 3 27 95 F1 ?431f Ca0 FLOW GPM 45.9 45.9 45.9 45.9 120.6 45.9 0 0 28 95 6 9c WIDE RANGE PREl$Utt PSIG 1006 1006 1006 1006 969 925 923 923 29 95 6 96 NAktoW RANGE Parts Pslo 1006 1006 1006 1006 969 DSL DSL DSL '
30 95 6 97 FitDWAftt FLOW MLB/NR 6.2 6.2 6.2 6.2 h.3 0.3 0.1 0.1 31 95 6*97 MAIN SitAM FLOW ML8/NR 6.2 6.2 6.2 6.2 4 0.3 0.1 0.1 32 95 6 98 NAkt0W RANGE LtytL INCNES 162 162 162 162 '52 164 168 162 33 95 6 98 WIDE RANGE Ltytt INCHis OSM OSH OSH OsH 155 164 168 162l 34 96 Lt.107 5 Csf LEVEL I 52 52 52 52 52 50 50 50 '
35 96 Ll.102 5A NOTWCLL LEVEL N I 56 56 56 56' 55 62 66 65 36 96 Ll 102 58 N0fWtLL Ltytt t 1 54 54 54 54 52 53 54 54 37 97 Plaid 1 29 CONDEN$tR VACULM IN ' .3 2.6 2.6 2.6 2.6 3.1 1.6 1.3 1.2 38 98 D/G A DKR (foCL0$tDJFa0 PEN) F F F F F F F Fl 39 ~ 9 8 0/G s 8KR (foCLOSEDIF=0 PEN) F F F F F F F F 40 9 23 16 19 33A/C 10RUS ftMPERAfunt DEG F 72 72 72 72 72 72 72 72 41' 9 25 L1 46A TORUS Ltytt FEff 1.16 1.16 1.16 1.16 1.15 1.15 1.15 1.15 '
42 9 2$ Lt 463 foaVS LtytL 7tti 1.16 1.16 1.16 1.16 1.15 1.15 1.15 1.15 43 9 25 ft 16 19 44 torus PatstuRE PslA 14.7 14.7 14.7 14,7 14.7 14.7 14.7 14.7 44 9 25 TR 1619 44 DRYWELL PRES $Utt PSIA 17 17 17 17 16 16 16 16 45 9 25 PR*1 156 3 DW/f0RUS DP PSID 1.87 1.87 1.87 1.85 1.82 1.79 1.77 1.75 46 9 25 TR 1619 45 DRYWELL ftMPitATURE Dec 7 138 138 138 137 137 136 135 134 47 9 26 PI 1 125 3A RK BUILDI N DP IN H2O 0.75 0.75 0.75 0.75 0.7 0.68 0.68 0.68
[. 48 9 26 Pl*1'125 3B RX BUILC NG DP IN H2O 0.75 -0.75 0.75 0.75 0.7 0.68 0.68 0.68
\ 49 9 26 F1 1 125 1A st.fs F;0W 78 78 CFM 78 11 1500 1500 1500 1500:
50 9 26 Fl 1 125 it $ Git FLOW CFM 0 0 0 0 1500 1500 1500 1500 51 CAD DW/foaus 02 CONC. 1 2.58 2.58 2.52 2.58 2.58 ~2 .58 2.58 2.58 t
. l f.',n h VERMONT YAurtt uuCLEAR POWit STAfl0N REV. 1 t EMERGENCY kESPON&E PREPAkEDNEls EXERCist PAGE 8.0 2 1990 8.0 OPERAfl0NAL DATA (CONT'0) !
SCENAt tfi TIME 02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 CLOCK TIME 09:00 09:15 09:30 09:45 ' r:00
. 10:15 10:30 10:45 litN PANEL INST 10 DESCkiPfl0N UNITS 1 93 FT 23 108 1 NPCI FLW OPM 0 0 2414 3029 3029 4131 4130 4130 2 93 F1 10 139A RHR A PLW MI 0 0 0 0 0 0 0 0' 3 93 F1 10 1390 kNR $ FLOW BNt 0 0 5876 5976 5976 5976 $976 5976 4 93 ft.14 50A Cs A FLOW EPM 0 0 0 0 0 0 0 0-5 93 F*-14 500 Cs B FLOW OPM 0 0 0 0 0 0 0 0 6 93 E l6 19 12A DR M LL PRtt9URE P81A 16 16 16 15 14 14 14 15 7 93 Pl.16 19 12e DR M LL PatstuRE PstA 16 16 16 15 14 ' 14 14 15 8 94 Fl.13 91 RCIC FLW OPM 0 0 0 0 0 0 0 0 9 94 ft.12 141A RWCU FLOW OPM 0 0 0 65 62 65 65 63 10 94 Pl*12 1418 kWCu FLOW OPM 0 0 0 65 62 65 65 65 11 94 2 165A RK COOLANT ftMP DEC F 519 517 516 525 529 489 499 499 12 94 2 1650 ,
Rx COOLANT ftMe DEC F $19 517 516 525 529 489 499 499 13 94 2 159A RECIRC A LOOP FLOW KQPM 0 0 0 0 0 0 0 0 14 94 2 1598 REclRC B LOOP FLOW KGPM 0 0 0 0 0 0 0 0-15 95 7 46A APRM/lkM A "6 13 13 i3 5 0 0 0 0 16 95 7 464 APRM/lRN t t 13 13 13 5 0 0 0 0' 17 95 7 46C APRM/l;M C % 13 .13 13 5 0 0 0 0 18 95 7 460 APRM/lRM D 1 13 13 13 5 0 0 0 0-(- "
19 95 7 46t APRM/lRM t t 13 13 13 5 0 0 0 0 20 95 7 46F APRM/lRM F X 13 13 13 $ 0 0 0 0l 21 95 7 43A tRM A cps 9410 9410 9410 30 28.1 32.2 28.8 26.5 22 95 7 43a 3RM B cps 10300 10300 10300 30 27.6 31.8 28.4 28 23 95 7 43C 3RM C CP9 11500 11500 11500 30 27.8 31.9 28.5 28.1 24 95 7 430 SRM D cps 9800 9800 9600 30 27.B 31.9 28.5 28.2' 25 95 2 3 95 CORE FLOW MLt/MR 1 1 1 1 1 1 1 1 26 95 2 3 95 CORE DP PSID 3 3 3 3 3 3 3 3 27 95 Fl*3 310 CRD FLOW GPM 0 0 0 45.9 45.9 46 45.9 45.9, 28 95 6 96 WIDE RANGE PRESSURE PSIG 922 922 990 935 946 664 752 745+
29 9<$ 6 96 NARROW RANGE PRESS P$lt DSL DSL 990 DSL Dst DSL DSL DSL 30 95 6 97 FEEDWATER FLOW ML8/MR 0.1 0.1 0.1 0 ,0 0 0 0' 31 95 6 97 MAIN STEAM FLOW MLS/HR 0.1 0.1 0 0 0 0 0 0 32 95 6 98 NARROW RANCE LEVIL INCHES 162 164 170 167 156 158 166 158:
33 95-698 WIDE RANGE LEVEL INCHis 162 164 170 167 156 158 166 158=
34 96 Lt.107 5 Csf LEVEL E 50 49 49 lb 50 49 48 48 35 96 L1 102 5A NOTWELL LEvtL N t 65 65 65 56 55 57 58 58 :
36 96 Lt 102 58 HO M LL LEVEL s t 54 54 54 55 55 54 54 54 37 97 PI 101 29 CONotNSER VACLAJM IN HG 1.1 1.2 17.1 29.5 30 30 29.9 29.9 38 98 D/G A DKR (T*CLOSEDIF=0 PEN) F F F F F F F F 39 98 D/G B BKR (T=CL0stDIF=0 PEN) 8 F F F F F F F:
40 9 23 16 19 33A/C TORUS TEMPERATURE DEC F R 72 72 75 77 79 81 82 '
41 9 25 lit 6A TORUS LEVEL FEtt 1.15 1.14 1.14 1.01 1.03 1.06 1.08 1.1 42 9 25 Ll*468 TORUS LEVEL FEff 1.15 1.14 1.14 1.01 1.03 1.06 1.08 1.1 43 9 25 TR 1619 46 TORUS PRESSURE PSIA 14.7 14.7 14.7 14.4 14.4 14.4 14.4 14.4 -
44 9 25 TR 16 19 44 DR M LL PRissuRE PSIA 16 16 16 15 14 14 14 15 45 9 25 PR 1 156 3 DW/ TORUS DP PsID 1.73 1.7 1.68 0.07 0.07 0.07 0.07 0.07
, 46 9 25 TR 1619 45 DR M LL TEMPERATURE DEG F 133 .132 132 131 129 128 127 126.
i 47 9 26 Pl.1 125 3A RX BUILDING DP IN H2O *0.68 0.68 0.68 0.71 1 1 1 1-
'- 48 9 26 PI 1 125*38 RK SUILDlWG DP IN H2O *0.68 0.68 0.68 0.71 1 1 *1 1 49 9 26 FI.1 125 1A $GTS FLOW CFM 1500 1500 1500 1500 1500 1500 1500 1500 50 9 26 F1 1 125 1B sGit FLOW CFM 1500 1500 1500 0 0 0 0 0-51 CAD DW/Tonus 02 CONC. X 2.58 2.58 2.58 2.4 9.02 13.04 15.5 16.98'
t t
-. 3 0,
+3
- VthMOWT YAhKEt WUCLLAR POWER $f Afl0W kiv. 1 EMERGtWCY Rt6PONSE PREPAREDWitt EXERCist PAGE 8.0 3 1990 8.0 CPERAtl0NAL DATA (CONT'0)
SCthatto fleet 04:00 04:15 04:30 04:45 05:00 05:15 05:30 05:45 CLOCK tlMt 11:00 11:15 11:30 11:45 12:00 12:15 12:30 12:45 IftM PANEL Ikti 10 DtlCRIPfl0W UNIf8 1 93 FT 231081 MPCI FLW :PM 4130 4129 4126 0 0 0 0 0 2 93 fl.10 139A RNR A PLOW OPM 0 7363 7563 4449 5897 5097 5897 5897 3 93 Fl.10 1398 RHR 8 FL W ope 5976 5976 5976 0 0 0 0 0, 4 93 Fl.14*50A C5 A FLW OPM 0 0 0 0 0 0 0 0 C *3 F1 14 500 CS B FLW OPM 0 0 0 0 0 0 0 0 6 93 Fl*16 19 12A DRYWELL PktstuRt P81A 14 15 15 17 17 17 17 1?
7 b3 PP 16 19 12e DRyWtLL Pttttunt PstA 14 15 15 17 17 17 17 17 8 94 11 13 91 RCIC FLOW CPM 0 0 0 0 0 0 0 0 9 94 Fl.12 141A RWCU FLOW CPM 65 65 65 65 65 60 60 60 10 94 F1 12 1418 RWCU FriW CPM 65 65 65 65 65 60 60 60 11 9+4 2 165A RX C00LAuf trMP btL F 4 73 4 72 470 276 278 314 298 298 ,
12 94 2 1658 RK COOLANT ftW Dt', f 473 472 470 276 278 314 298 298 13 94 2 159A RECIRC A Loop FLOW K' PM 0 0 0 0 0 0 0 0 14 94 2 1598 RECIRC D LOOP FLOW EPM 0 0 0 0 0 0 0 0 15 95 7 46A APRM/IRM A 1 0 0 0 0 0 0 0 0 16 95 7 468 APRM/lRM 8 1 0 0 0 0 0 0 0 0 17 95 7 46C APR4/lkN C E O O 0 0 0 0 0 0 18 95 7 460 APRM/lRM D E 0 0 0 0 0 0 0 01
, 19 95 7 46E APRM/lRM t 1 0 0 0 0 0 0 0 0i
( 20 95 7. .67 APRM/lRM F X 0 0 0 0 0 0 0 0l 21 95 7 43A sRM A CPF 31.8 28.6 28 39.1 38.7 38.7 38.7 38.7 22 95 7 438 SRM t Cr d 31.3 28.1 27.5 38.6 38.1 38.1 38.1 38.1 23 95 7 43C SRM C CPS 31.4 28.2 27.6 38.8 38.4 38.4 38.4 38.4 24 95 7 430 SRM D CPS 31.5 28.3 27.6 38.8 38.3 38.3 38.3 38.3-25 95 2 3 95 CORE FLOW MLB/HR 1 1 1 1 2 2 1 1 26 95 2 3 95 CORE DP PsID 3 3 3 3 3 3 3 3 27 95 F1 3 310 CRD FLW GPM 45.9 45.9 45.9 59.8 35.1 35.1 35.1 35.1 28 95 6 94 WIDE RANGE Pktstutt Pslo 600 582 562 104 53 53 53 53 29 95 6 96 NARROW RANGE Pktt$ PSIG DSL DSL DSL OSL OSL DSL DSL DSL 30 95 6 97 ftEDWAftR FLOW ML8/MR 0.1 0 0.1 0 0 0 0 0 31 95 6 97 MAlW SitAM FLOW MLB/HR 0 0 0 0 6 0 0 0 32 95 6 96 NARROW RAWGt Ltv u li,CHE S 158 164 158 OSM OSH OSM OSN OSH 33 95 6 94 WIDE RANGE LEvtl INCHts 158 164 158 OsW 0$N 0$H
- 0$H OSW i 34 96 L1 107 5 CST Ltytt % 48 47 47 45 45 40 39 39 ,
35 96 LI 102 5A NOTWELL LtytL N 1 57 58 58 , 55' 54 57 $8 54 36 96 Lt*102 58 HOTWELL LtytL s 1 54 54 54 55 54 54 54 54 37 97 Pl*101 29 CONDENSER VACUUM IN HG 29.9 29.9 29.9 30 30 30.3 30.3 30.3 38 98 D/G A BKR (foCL0$tDlf =0PtW) F F F F F F F F 39 9*8 D/G B DKR (f*CL0$tDlfe0PtW) F F F F F F F F 40 9 23 16 19 33A/C TORUS fietRATURE Dtc F 84 86 87 93 95 98 98 98 +
41 9 25 Ll*46A TORUS LEYtt FEET 1.13 1.15 1.19 1.14 1.05 1.82 1.88 1.88 42 9 25 LI 468 TORUS LEvil itET 1.13 1.15 1.19 1.14 1.05 1.82 1.88 1.88 43 9 25 TR 16 19 44 TORUS PRttSURE PSIA 14.4 14.4 14.4 14.7 14.7 14.7 14.7 14.7 {
44 9 25 TR 1619 44 DRYWEtt PRtsSURE PstA 14 15 15 17 17 17 17 17 45 9 25 PR 1 156 3 DW/104US OP PSID C.07 0.07 0.07 2.2 2.12 2.56 2.62 2.62 46 9 25 TR 1619 45 DRYWELL TEMPERATURE DEG F 125 125 124 , 224 236 240 245 245 47 9 26 PI 1 125 3A kX BUILDlWG DP IN H2O 1 1 1 0.34 0.34 0.34 0.34 0.34 48 9 26 Pl*1 125 38 Rt tulLDlhG DP IN H2O 1 1 1 0.34 0.34 0.34 0.34 0.34 49 9 26 FI 1 125 1A SGit FLOW CFM 1500 1500 1500 1500 1500 1500 1500 1500 50 9 26 F1 1 125 1B scis FLOW CFM 0 0 0 0 0 0 0 0 51 CAD ,
DW/10Rus 02 CONC. 1 17.89 18.44 18.77 11.09 12.07 12.96 13.46 13.46 W
l
, i
'sj :
1 I
%g 1 ,,, . %
i ,,a YERMONT YANKtt WUCLEAR POWR STAfl0N ktV. 1 i
' EMERGENCY RESPONlt PktPAREDNtt$ ExtkCISE PAGE 8.0 4 1990 8.0 CPERAftouAL DATA (CONT'D)
.................. posy BCENAtle TIME 06:00 06:15 06:30 06:45 07:00 07:00 CLOC : T:Mt 13:00 13:15 13:30 13:45 14:00 14:00 lien PANtt Inst 10 Dt4CRIPfl0N UNif5 i 93 Ft 23 10$+1 NPCI FLOW em 0 0 0 0 0 0 2 93 Fl.10 139A Rut A FLOW em 5997 5897 5897 5997 5897 5897 3 93 F1 10 1396 RNA B FLOW opu 0 0 0 0 0 0 4 93 Fl 14 50A C8AFLW em 0 0 0 0 0 0 5 93 Fl.14 50s Cs a FL W om 0 0 0 0 0 0 6 93 Plai6 19 12A DRYWELL PRitsukt P8tA 17 17 17 17 17 17 7 93 Pl*161912s DayWELL Patssutt PslA 17 17 17 17 1r 17 4 94 Fl*13*91 RCIC FLW .Gm 0 0 0 0 0 0 9 94 Fl 12 141A RWCU FL W OPM 60 60 60 60 60 60 10 94 Fl 12 141R RWCU FLOW OPM 60 60 60 60 60 60 11 94 2 165A RM C00LANT TEMP DEG F 298 298 298 298 298 298 12 94 2 1658 tr COOLANT TEMP DEG F 298 298 298 298 298 298 13 98 2 159A RECIRC A LOOP FLOW KbPN 0 0 0 0 0 0 ,
14 94 2 159s REClRC e LOOP FLN KGM 0 0 0 0 0 0 15 95 7 46A APRM/lRM A 1 0 0 0 0 0 0 16 95 7 468 APRM/IRM s 1 0 0 0 0 0 0 17 95 7 46C APRM/lRM C 1 0 0 0 0 .0 0 18 95 7 460 APRM/IRM D E 0 0 0 0 0 0 19 95 7 46t APRM/lRM E t 0 0 0 0 0 0 k' 20 95 7+46F APAN/lkN F 1 0 0 0 0 0 0 21 95 7 43A SAM A CPS 38.7 38.7 M.7 38.7 38.7 38.7 22 95 7 43s SAM B CP8 38.1 38.1 .,d .1 38.1 38.1 38.1 23 95 7 43C stM C CPS 38.4 38.4 38.4 38.4 38.4 38.4 24 95 7 43D BRM D cps 38.3 38.3 38.3 38.3 38.3 38.3 ;
25 95 2 3 95 Coat FLOW MLt/NR i 1 1 1 1 1 26 95 2 3+95 CONE DP $31D 3 3 3 3 3 3 27 95 Fl*3 310 CRD FLOW GPM 35.1 35.1 35.1 35.1 35.1 35.1 28 95 6-96 WIDE RANGE PRES $Utt PSIC 53 53 53 53 53 53 29 95 6 96 NARROW RANGE PRC$$ P$10 DSL DSL DSL DSL DSL DSL 1 30 95 6 97 Fr[DWAftR FLOW MLt/MR 0 0 0 0 0 0 31 95 6 97 MAIN SitAM FLOW MLS/HR 0 0 0 0 0 0 32 95 6 98 NARROW RANGE LEVtl INCHtt OSH OSM OSM 0$N 0$N 0$H 13 95 6 98 vlDE RANGE LEvtl INCHES OSH OSM OSH OSH OSH 0$N 34 96 Lt.107 5 Ctf Ltytt t 39 39 39 39 39 39 35 96 Lt 102 5A HOTWELL Ltytt u I 58 58 58 58' 58 58 -
36 96 Lla102 58 NofWELL trytL $ 5 54 54 54 54 54 54 37 97 Pl 101 29 CONDEN$tt VACWM IN MG 30.3 30.3 30.3 30.3 30.3 30.3 38 98 0/0 A BKR (T=ClostDIF=0 PEN) F F F F F F 39 98 D/G B BKR (T=CLOSEDIF=0 PEN) F F F F F F 40 9 23 16 19 33A/C Tonus TEMPERATURE Dtc F 98 98 98 . 98 98 98 41 9 25 Ll*46A TORUS LivtL Ftrf 1.88 1.88 1.88 1.88 1.88 1.88 42 9 25 Lt 468 torus LivtL Ftti 1.88 1.88 1.88 1.88 1.88 1.88 43 9 25 1R 16 19 44 TORUS PREstuRE PSIA 14.7 14.7 14.7 14.7 14.7 14.7 44 9 25 TR*1619 44 DRYWELL PkttSURE PSIA 17 17 17 17 17 17
- 45. 9 25 PR 1 156 3 DW/10Rus DP PS10 2.62 2.62 2.62 2.62 2.62 2.62 i 46 9 25 TR 16 19 45 DRYWELL TEMPERATURE DEG F 245 245 245 245 245 245
< , 47 9 26 Pl 1 125 34 RX BUILDING CP IN N20 0.34 0.34 0.34 0.34 0.34 0.34
( '"
'48 9 26 Pl.1 125 38 RX SUILDING DP IN H2O 0.34 0.34 0.34 , 0.34 0.34 +0.34 49 9 26 Fl 1 125 1A SGTS FLOW CFM 1500 1500 1500 1500 1500 1500 50 9 26 Fl*1'125 1B SGTS FLOW CFM 0 0 0 0 0 0 51 CAD DW/ torus 02 CONC.
I 13.46 13.46 13.46 13.46 13.46 13.46 l
,. . . - ~ . . . ~. . . . - - . , - . - .- ...-... . - --... ,
p;. . -
. . 6 U , -. - ,
t
.. s, _
e
- E 4 -
.f a '
e-
..1, : . . ..., .%.c
,c.
W:
. . . ,i 0
l
. VEMONT YANKEE NUCLEAR POWER STATION j i
- 1 MERCENCY RESPONSE PREPAREDNESS EXERCISE w
t r
t J<' -
1990 !
- i I
- 4,, c:
' L g 3 1 j
..j 9.0 RADfotDCICAL DATA t t
- . js
' I
- { ,
"3 _
.{
,f
=.
j E'
- h e f
'l F ,7 , ,
isi .;
i
(
b t
~
+
.fb i
' i I
s 4
t-it t -
I
?
k f,'
-t
, '(
h
, -.. .- h a
+
.1 .-
' f' h
- -. ,{
.?
) .
'I
+ *
,, W; , +
- \ _'A
..n,-_,1 I
'n
()
-k 8
, i .
S e + ....m.
, I .$ - - p 8 4
- e t w . ,
?
5 : c 4!'
- ~.
l
, [;- .!
i 1
i e
I;+ 1
' i U, , VERMONT YANKEE NUCLEAR POWER STATION I v.-,.. , i
. ;. ENERCENCY RESPONSE PREPAREDNESS EXERCISE j i
1990- .
. -i,
< -)
~)
t f
i j
= (l'
. .i i
'f
-s 9,1. AREA RADIATION MONITolt2 '!
, t
.n ;
e
- i. 9
- ip F
9 h
i . ?
d
[- '
.' ?
t a -,
- I l
.if- A'f
.i 1
+
t s
, t
$ h
.1
'h v ?
?
{ '-,.
k
'i
=y;,
t . I
'r F
t A
3-t
'c i s I I . . .
g k.
i
-f-My{t
.a.., . I, P,;id .+ w, .r , 4
. . . - - . . - - . ~ . . - - - - . - . . - ~ . ~ . . - - - - . - .- .
,i -
~
VERMONT YANKit NUCLEAR PGAR STAfl0el Rtv. O IMERGthCT RESPONSE PREPAREDuttl (XtkCitt PAGt 9.1*1 1990 9.1 ARtA RADIAfl0N le0NITOR$
SCENARIO fint 00:00 00:15 00:30 00:45 01:00 01:15 01:30 01:45 CLOCK TIME G7:00 07:15 07:30 07:45 08:00 08:15 08:30 08:45 PAmtL BLDG /tLV DttCalPflou UNIT 8 INelll*1 9*11 RS/256 RX BLDG Mi RAD $ . N WNR <1 <1 <1 <1 <1 41 <1 <1 kM811 2 9 11 RS/254 RX SLDG HI RADS * $ R/NR <1 <1 <1 *1 <1 <1 <1 <1 RM811 3 9 11 R$/256 flP RM NI RAD R/NR *1 si 41 <1 si <1 <1 <1 1 9 11 R8/232 suPP CHAMS Rt EXT CW peR/let 8 8 8 8 8 7 7 7 2 9 11 RS/256 N PEttoeINEL Re ACCtst MR/NR 10 10 10 10 10 8 6 5 3 9 11 R8/256 8 teulP RR Re ACCitt leR/NR 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3
. 4 9 11 RS/256 Rt NEUTRON seou TIP let/NR 5 5 5 5 5 5 5 5 5 9 11 RS/256 PERT 0NutL NATCH Rt leR/NR 300 300 300 300 300 240 180 140 6 9 11 R0/280 ELEY ENTR 200FT RB MR/NR $ 8 8 8 8 8 7 7 7 9*11 at/256 CR0 REPAIR Rt(CR0 RM) set /NR 16 g 16 16 16 16 13 10 10 8 9 11 RS/303 ELEY ENTR 303FT Rt seR/NR 3 3 3 3 3 2.5 2 2 9 9 11 R8/303 N20 CLEANur($ AMPLE tlNK)est/NR 4 4 4 4 4 4 4 4 10 9 11 at/318 fttV tWTR 318FT RB MR/NR 5 5 5 5 5 4.$ 4 4 11 9 11 at/318 N20 CLEANUP (PRE
- COAT) MR/NR 5 5 5 5 5 4.5 - 4 4 12 9 11 RS/345 ELEV ENTR 348FT Re MR/NR 4 4 4 4 4 3 2.5 2 14 9 11 Rt/345 Wtti REFutt Rt seR/NR 3 3 3 3 3 2.5 2 2 15 9 11 RS/345 SetNT futL Poot he MR/NR 8 8 8 8 8 8 8 8
( 16 9 11 RS/318 NEW FutL VAULT Rt leR/NR 0.65 0.65 0.65 0.65 0.65 0.58 0.52 0.48 17 9 11 RW/230 RECIRC PUMP RN RW int /NR 1 1 1 1 1 1 1 1 18 9 11 RW/255 RADW omtR AREA RW MR/NR 1 1 1 1 1 1 1 1 19 9 11 RW/255 PUNP/ TANK AREA RW 80R/let 2 2 2 2 2 2 2 2 20 9 11 ft/248 W ACCtst 244FT TB seR/NR 3 3 3 3 3 3 2 2 21 9 11 10/248 MAlW STM VALVE ft let/NA 370 3 70 370 3 70 370 350 320 2 70 22 9 11 ft/232 CONDENSAft DEMIN TB seR/NR 0.3 0.3 0.3 0.3 0.3 0.28 0.26 0.24 23 9 .11 ft/252 DECONTAMINAfl0N ft $Nt/NR 0.16 0.16 0.16 0.16 0.16 0.16 0.16 0.16 24 9 11 ft/272 TUR8 $fM INLET ft IIR/NR 190 190 190 190 190 180 160 140 25 9 11 AS/272 VIEW GALLERT CR leR/NR 0.12 0.12 0.12 0.12 0.14 0.12 0.12 0.12 26 9 11 TB/252 REAR GATE TURS WAttMst MR/NR 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 ;
13 9 11' TB/228 slotti Stp AREA 18 MR/NR 150 150 150 150 150 140 130 110 i
. l
?
0 * .
4 VibeeowI TAwa:ti NUCLEAR PWER STATION RtV. O
.[^
\ E81tt0tNCT ktsPON$t PREPAktDNES$ EKERCllt PAGt 9.1*2 1990 9.1 AntA AADIAfl0N MONITOR $ (CONT'0)
SCENARIO TIME -
02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 CLOCK TIME 09:00 09:15 09:30 09:45 10:00 10:15 10:30 10:45
-ARM No. PANEL 8LDC/tLV DESCRIPfl3N UNITS RMsti+1 9 11 RS/256 RK BLD(e NI RADS
- W R/NR <1 (1 41 <1 El <1 E1 (1
, -RMsti.2 9 11 k8/256 RK BLDG NI r. ADS * $ R/NR *1 s1 41 <1 <1 <1 41 <1 RMstI*3 9 11 tt/256 TIP kN HI RAD t/NR <1 <1 <1 <1 <1 <1 <1 <1 ;
1 9 11 RS/232 SUPP CHAMB 48 EKT CW . MR/NR 7 7 6 6 6 6 6 6 2 9 11 90/256 N PER$0NNEL te ACCtts MR/M 4 3 3 2 1 1 0.7 0.6 +
3 9 11 he/256 8 teUIP ha Rt ACCtst MR/NR 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 1 4 9 11 ts/256 R8 NEUTRON MON *TIP MR/NR 5 5 5 5 5 5 5 5 5 9*11 RS/256 Pikt0NNEL NATCH R$ M/NR 100 90 75 50 35 20 15 12 6 9*11 PS/200 ELEV ENTR 280FT Re MR/NR 6 6 6 6 5.5 5.5 5 5 7 )*11 ht/256 CRD ktPAIR httCR0 RM) m/NR 8 7 7 6 5 4 4 4 8 9 11 ht/303 ELEY ENTR 303FT RB MR/M 2 2 2 2 i 1 1 1 9 9 11 RS/303 N20 CLEANUP (SAMPLE $1NK)tIR/NR 4 4 4 4 4 4 4 4 10 9 11 R8/318 ELtv tWTR 318FT RS MR/NR 4 4 4 3 3 3 3 3 11 9 11 RS/318 N20 CLEANUP (Pat COAT) MR/NR 3 3 3 3 3 2 2 2 12 9 11 R8/345 ELEY ENTR 348FT R$ MR/NR 2 2 2 2 1 1 1 1 14 9 11 RS/345 WEST RtfutL as MR/pt 2 2 2 1 1 1 1 1 15 9 11 88/345 SPENT FUEL POOL R8 MR/NR 8 8 8 8 8 8 8 8 16 9*11 40/318 NEW FutL VAULT kt leR/NR 0.45 0.4 0.4 0.4 0.4 0.35 0.35 0.35 17 fati RW/230 RECIRC PUMP RM RW MR/M 1 1 1 1 1 1 1 1 ,
18 9 11 kW/255 4ADW OPit AttA RW llR/NR i 1 1 1 1 1 1 1
(> 19 9 11 BW/255 PUMP / TANK AntA nW set /NR 2 2 2 2 2 2 2 2 20 9 11 78/248 N ACCtts 248FT TB MR/M 2 2 2 2 2 2 2 2 21 9*11 T0/?48 IIAIN STM VALVE TB IIR/NR 230 190 160 140 120 110 100 90 22 9 11 TB/232 CONDtlT I DEMIN TB MR/NR 0.2 0.2 0.18 0.18 0.16 0.15 0.15 0.14 23 9 11 Ts/252 DECONTAMitail0N T3 MR/NR 0.16 0.15 0.15 0.15 0.15 0.15 0.15 0.15 24 9 11 T8/272 TURS STN INLtf TB let/NR 110 95 40 70 60 55 50 45 25 9 11 AB/272 VitW GALLERY CR leR/NR 0.12 0.1 0.1 0.1 0.1 0.1 0.1 0.1 26 9 11 T8/252 Rf AR GATE Tutt WARENst MR/NR 0.02 0.01 0.01 0.01 0.01 0.01 0.01 0.01 ]
13 9 11 TB/228 N0!$T SEP AREA TB IIR/NR 90 to 65 55 45 40 30 30 l
. s 1 1
w , . _ . -, - . . - - - - _ - - - -
1 i
Vthee0NT TANKit NUCLEAR POWER 81Afl0N Rtv. O
.('
testRGtWCY RESPON$t PREPAREDNtt$ EXERCllt M Gt 9.1 3 9.1 Akt A kADI A110N se0Nif 0R$ (CONT *0) ,
SCENAtto fleet 04:00 04:15 04:30 04:45 05:00 05:15 05:30 05:45 i CLOCK flME 11:00 11:15 11:30 11:45 12:00 12:15 12:30 12:45 ARM No. PANEL BLDG /tLV DitCRIPfl0N UNIT 8 RM81t*1 tail RS/256 RX BLDG Mi RADS
- N R/NR *1 <1 <1 2 10 ~ 16 20 24 RMsti.2 9 11 RS/256 RX DLDG NI RAD $ * $ R/NR <1 <1 <1 3 12 20 25 30 RM$ll*3 9 11 as/256 ftp RM MI kAD R/NR <1 <1 <1 2 to 16 20 24 1 9 11 RS/232 SUPP CHAMS Rt EKI CW NR/NR 6 6 6 3000 6000 9000 (0$N)>184 (ORN) 2 9 11 RS/256 ~ N PCR$0NNEL R$ ACCES$ leR/NR 0.5 0.4 0.4 (0$N)>1t3 (0$N) (0$N) (0$N) (0$N) 3 9 11 RS/256 8 teUIP RR Re ACCtss leR/NR 0.3 0.3 0.3 (OsN)>1E3 (0$N) (O$N) (0$N) (0$N) 4 9 11 RS/256 RB M UTRON se0N flP fut/NR 5 5 5 1000 10000 (0$N)>1E4 (0$N) (DSM) ,
5 9*11 RS/256 PERSONNEL NATCH RS let/NR 9 8 7 6000 (0&N)>1t4 (DSM) (05H) (0$N) 6 9 11 RS/260 Etty tuft 240FT Re MR/NR 5 5 5 1700 5500 (0$N)>1t4 (DSM) (0$N)
T 9 11 RS/256 CR0 REPAlt ht(CR0 RM) leR/NR 4 4 4 200 630 1400 2100 2500 8 9 11 RS/303 ELEY INTR 303FT Rt let/let 1 1 1 6000 (0$N)>184 (OSM) (OSN) (OsN) ,
. 9 11 R8/303 N20 CLEANUP (SAMPLt $1NK) Met /NR 4 4 4 6000 (0$N)>1t4 (0$N) (OSN) (OSN) 10 9 11 RS/316 ELEV ENTR 318FT kB MR/NR 3 3 3 1700 5300 (OSM)>1t4 (DSM) (0$N) 11 9+11 RB/318 N20 CLEANUP (PRt.CDAT) MR/NR 2 2 2 1700 5500 (0$N)*it4 (0$N) (OsN) 12 9 11 Rs/345 (Ltv tuft 346ft RS MR/NR 1 1 1 600 1600 3900 5500 6600 14 9 11 RB/345 Wtti REFUEL Re MR/NR 1 1 1 600 1900 3800 5400 6500 15 9 11 RB/345 SPiht FUEL P00L Rt int /NR 8 8 8 600 1800 3800 5300 6400 <
16 9 11 RS/318 NEW FL'EL VAULT Re Mit/NR 0.35 0.34 0.34 6.7 20 45 68 68 17 9 11 RW/230 RECIRC l ser RM RW put/NR
( ,
18 9 11 RW/255 RADW OPER AREA RW int /NR 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 19 9 11 RW/255 PLaeP/fANK AttA RW IeR/NR 2 2 2 2 2 2 2 2 20 9 11 T8/248 N ACCitt 244FT fB But/NR 2 2 2 2 2 2 2 21 9*11 18/244 leAIN STM VALVE ft put/ int 80 70 65 60 55 3 50 50 22 9 11 ft/232 CONDth& ATE DEMIN 18 leR/NR 0.14 0.14 0.13 0.13 0.13 0.13 0.13 0.13 23 9 11 18/252 DECONTAMINATION TB NR/NR 0.15 0.15 0.15 0.15 0.15 0.15 0.15 0.15 24 9 11 10/272 fUas $fM INLtf it leR/NR 40 35 35 30 28 28 ?$ 25 !
25 9 11 AS/272 vitW r.ALLERT CR IWl/ int 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 26 9 11 fB/252 REAR GATE fung WAttHst int /NR 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 13 9 11 ft/228 140l$f SEP AttA 18 MR/NR 23 19 1* 16- 16 16 16 16 (OSN) 0FF SCAlt NIGH h
t s
J 6
.e.. .. - _,.
7 ,
9 VERMONT TANKtt NUCLEAR POWER STAfl0N Riv. 0 EMERGENCY RttPONSE PREPAREDNtts EXERCl$t 5-AGE 9.1*4 !
1990 9.1 AREA RADIATION Moult 0R$ (ccWT'D)
POST SCENARIO TIME 06:00 06:15 06:30 06:45 07:00 07:00 CLOCK Tint 13:00 13:15 13:30 13:45 14:00 14:00 t ARM he. PAmtL BLDG /tLV DttCRIPfl0N UNITS ,
RM881 1 9 11 RS/256 RK BLDG NI RADS
- N R/M 28 27 26 24 24
- i RM$18 2 9 11 RS/256 RK BLOG NI RADS * $ R/pt 33 33 32 30 30
- 1- 9 11 RS/232 tuPP CNANs At Erf CW . MR/M (DSM)>184 (OSM) (0$N) (0$N) (0$N)
- 2 9 11 RS/256 N Pett0NNEL Rt ACCtts MR/M (0$N)>1t3 (OSN) (OSN) (OSN) (OSN) 3 9 11 RS/256 8 teUIP RR Re ACCtts MR/pt (DSM)>1t3 (Osu) (Ost. (0$N) (OsN)
- 9 11 RS/256. RO NEUTRON MON *TIP (0$N)
- 4 MR/M (OSN)>1t4 (05N) (OSN) (OSN) 5 9 11 R0/256 PERs0NNEL NATCH Re- MR/NR (DSM)>1t4 (0$N? (OSM) ' (OSN) (DSM) * ;
6 9 11 RS/240 ELEV tWTR 280FT Rt MR/NR (0$N)>184 (OSN) (0$N) (0$N) (0$N)
- i 7
9 11 RS/256 CR0 REPAlt Rs(CR0 RM) MR/M 3000 2400 2700 2600 2500
- 4 9 11 RS/303 ELEV INTR 303FT Re MR/M (0$N)>184 (OSN) (0$N) (0$N) (OSN) *
- 9. 9 11 RB/303 N20 CLEAWP(SAMPLE $1NK)MR/M (0$N)>1t4 (0$N) (0$N) (DSM) (0$N)
- 10 9 11 kB/318 (LEY ENTR 318FT hl MR/NR (CSN)>1t4 (0$N) (OSN) (OSN) (0$N)
- 11 9 11 RB/318 N20 CLEANUPtP8F COAT) MR/NR (05N)>1(4 (0$N) (0$N) (0$N) (0$N)
- i 12 9 11 RS/345 ILEV INTR 364FT Re MR/NR 7600 7300 7000 6700 6500
- 14 = 9 11 RB/345 WEST REFutt as MR/NR 7500 7200 6400 6600 6400
- 15 9 11 ht/345 SPENT FUEL POOL R8 MR/NR 7400 7000 6700 6500 6200
- 16 9 11 R8/318 NEW FUEL VAULT 88 MR/NR 64 68 68 68 68 45
.i ~ 17 9 11 RW/230 RECIRC PUMP RM RW MR/NR 1 1 1 1 1 1 18 9 11 RW/255 RADW OPER AREA RW MR/NR 1 1 1 1 1 i 19 9 11 kW/255 PUMP / TANK A&tA RW MR/NR 2 2 2 2 2 2 20 9 11 TB/248 N ACCtst '48FT d TB MR/NR 1.5 1.5 1.5 1.5 1.5 1.5 21 9 11 TB/248 MAIN STM WtVE Tb MR/NR 50 50 50 50 50 54 22 9 11 TB/232 CONDENSAff DEMIN TB M/NR 0.13 0.13 0.13 0.13 0.13 0.13 23' ~9 11 ft/252 DECONTMINAfl0W TS MR/NR 0.15 0.15 0.15 0.15 0.15 0.15 24 9 11 TB/N2 TURB STM INLtf Te MR/NR 25 25 25 25 25 27 25 9 11 AS/277 VlfW GALLERT CR MR/NR 0.1 0.1 0.1 0.1 0.1 0.1 26 9 11 ft/2Si REAR GATE TURS WARENSE MR/NR 0.01 0.01 0.01 0.01 0.01 0.01 13 9 11 ft/228 Moisi stP AREA 18 MR/M 16 16 16 16 16 16
..o..........................................................................................................
(Osh) 0FF $CALE NIGN
- MONITOR READINGS WILL DECREAtt AS REACTOR OL81dlNG 15 VENTED VIA StGTS 4
e
~
r
.i .
(
1
)
VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.2 PROCESS MONITORS ,
I d
- x.
4 4
e a-L !. .
1 l -~
i l-l
- $ i VERMONT YANKEE IILICLEAR POWR STAfl0N REY. 0 EMERGENCY RitPONSE PREPAREDNEl$ EXERCllt PAGE 9.2 1 1990
?~t MtoCEll MONITORS Q..~................
SCENAR10 TIME 00:00 00:15 00:30 00:45 01:00 01:15 01:30 01:45 CLOCK TIML 07:00 07:15 07:30 07:45 08:00 08:15 08:30 08:45 ARM No. PANEL BLDG /tLV DtScalPfl0N UNIT $
9*2 8 TACK gat MON. GAS 1 CPM 150 150 150 150 150 150 150 150 92 STACK gat M0W GA8 2 CPM 200 200 200 200 200 200 200 200 92 STACK N1 RAmet MR/let 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 92 CONTAINMENT MON gal" Crit 600 600 600 MD 20 600 20 600 !
92 tuNTAINNENT It0N PART CPM 60000 60000 60000 60000 60000 60000 60000 60000 92 DRYWELL CN A 8/let 3 3 3 3 3 2 1 1 92 DRYWELL CN 8 R/HR 3 3 3 3 3 2 1 1 92 AM BLD0 VENT SAS CPM $00 500 500 500 500 500 $00 500 92 RX BLDG VENT . PART CPM 4000 4000 4000 4000 4000 4000 4000 4000 31 9 10 kN BLDG VENT NORTH MR/NR 1 1 2 2 1 1 1 1 32 9 10 RK BLDG VENT SOUTH MR/NR 1 1 2 2 1 1 1 1 453A 9 10 BPENT FutL POOL A MR/NR 10 10 10 10 10 10 10 8 4538 9 10 SPENT FUEL POOL B MR/NR 10 10 10 10 10 10 10 8 9*10 MAIN STM LINE A leR/NR 200 200 200 200 200 100 100 to 9 10 MAIN STM LINE I leR/NR 200 200 200 200 200 100 100 80 9 10 IIAlu STM LINE C IIR/NR 200 200 200 200 200 100 100 to 9 10 MAIN $TM LINE D IIR/NR 200 200 200 200 200 100 100 to 38 9 10 SJAE(Alt EJECTOR) MR/NR 270 270 270 270 270 260 250 240
(,
I l
l l
1 l
l l
1 I
l
VEspe0NT YANKtt IUCLEAR POWER $1Afl0N ktv. O teetICNCY CSPON$t PetPARRDNtts EFERCIO PA3 9.2 2 1,90 .
9.2 PRoctss sooW11085 (CONT'D)
SCENAtto filet 02:00 02:15 02:30 02:45 03:00 03:15 03:30 03:45 ,
CLXK f!ME 09:00 09:15 09:30 09:45 10:00 10:15 10:30 10:45 :
litM PANEL INST 10 DitCRIPTION UNifs 92 STACE ut le0N GAS 1 CPM 150 150 150 150 150 '30 150 150 92 8iACK GAS pe0N GA8 2 CPM 200 200 200 200 200 0 200 200 92 STACK HI RANot leR/M 0.1 0.1 0.1 0.1 0.1 0.1 0.1 0.1 92 CONfAlINetWI le0N GAB CPel 600 600 600 600 600 600 600 EO 92 CONTAINMENT MON PART CPM 60000 60000 60000 60000 60000 60000 60000 60000 92 DR M LL CN A R/M 1 1 1 1 1 1 1 1 92 DR M LL CN $ R/M i 1 1 1 1 1 1 1 92 RN BLDG YENT GAS CPM 500 500 500 500 500 500 500 500
- 92 kX SLDG YENT
- PART CPet 4000 4000 4000 4000 4000 4000 4000 4000 31 9 10 Ex tLDG vtui le0RTH MR/M i 1 1 1 1 1 1 1 32 9 10 kx SLDC YENT SOUfM PR/M 1 1 1 1 1 *1 1 1 455A 9 10 BPtWT Futt POOL A HR/M 8 8 8 8 8 7 7 7 4538 9 10 BPENT FUEL POOL B HR/NR S 8 8 8 8 7 7 7 9 10 MAIN $fM LINF. A HR/NR 60 55 0 0 0 0 0 0 9 10 MAIN sfM LINE 8 leR/NR 60 55 0 0 0 0 0 0 9 10 MAIN STM LINE C leR/M 60 55 0 0 0 0 0 0 9 10 MAIN STN LINE D IIR/M 60 55 0 0 0 0 0 0 38 9 10 SJAE(Alt EJtCTOR) M/M 230 225 0 0 0 0 0 0 k
_~. - - - - - . _ . . . .
VEtee0NT YANKit NUCLEAR POWER $1Afl0N Rtv. O testRGENCY CSPONtt PatPAktDNit$ ExtRCitt PAGE 9.2 3 1990 9.2 PROCil$ MONITott (CONT'0)
WCENAR10 flMt 04:00 04:15 04:30 04:45 05:00 05:15 05:30 05 45
(+- - CLOCK fleet 11:00 11:15 11:30 11:45 12:00 12:15 12:30 12 A5 litM PANEL INST 10 DESCRIPil0N UNill 92 STACK GAS MON GA$ 1 cm 150 150 150 0$N(*186) 0$N 0$N 0$N 0$N 92 $1ACK GAS MON GA$ 2 CM 200 200 200 0$N(*156) 0$N 0$N 0$N 0$N 92 $1ACK HI RANQt MA/NR 0.1 0.1 0.1 64 115 160 190 225 92 CONTAINMENT MON GA$ Cm 600 600 600 0$N(*1E6) OSM 0$N DIN 0$N j 92 CONTAINestNT plou PART CM 60000 60000 60000 0$N(*156) 05N DSM 0$N OSM 92 DRYWELL CH A k/NR 1 1 1 1300 3000 2600 2700 2500 92 DRYWELL CN 8 R/NR 1 1 1 1300 3000, 2600 2700 2500 I 92 RK SLOG vtNT GA$ CPM $00 500 500 0$N(*166) 0$N OSM ' 0$N OSM 92 ' RK BLDG VENT . PART CM 4000 4000 4000 0$N(*186)- 0$N 0$N 0$N 0$N 31 9 10 Rx BLOG vtNT NottM MR/NR 1 1 1 0$N(Dit3) 05N OSN OSM CSM 32 9 10 Rx SLOG vtNT south MR/NR 1 1 1 0$N(>103) 0$N OSN 0$N 0$N l 453A 9 10 SPtWT futL POOL A let/NR 7 7 7 600 2000 4000 5000 6000 4538 9 10 SPENT FutL Pool 8 MR/NR 7 7 7 600 2000 4000 5000 6000 :
9 10 MlW $IN LINE A let/NR 0 0 0 0 0 0 0 0 l 9 10 MIN $1N LINE $ leR/NR 0 0 0 0 0 0 0 0 9 10 9 10 MIN SIN LINE C MIN $iN LINE D let/NR seR/NR 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
]
38 9 10 $JAt(AIR (JECTOR) HR/NR 0 0 0 0 0 0 0 0 l
4 t
s 8
b
,!, CRMONT TANKit NUCLEAR POWER STATION ktv. O i EMEkrNCY titPON~3 PktPAREDMES$ ExtRCI.3 PAGE 9.2 4 1990
- f.2 PROCEtt Moulf0R$ (CONT't)
I (' SCENAtl0 flME CLOCK flME 05:00 13:00 05:15 13:15 05:30 13:30 05:45 13:45 06:00 14:00 litM PANEL IW81 ID DttCRIPflow uults 92 STACK GA$ Mok+ GAS 1 CPM 0$N(site) 0$N OSN 0$N 0$N 92 STACK QAl MON GAS O CPM OsN(*1t6) OSM 0$N 0$N 0$N 9*2 STACK HI kAh0t MR/NR 250 230 210 200 140 92 CONTAINMENT MON GAS CPM OsN(>186) 0$N 08N 0$N 0$N 92 CONTAINMENT MON PART CPM OsN(*186) OSM 0$N 0$N OSH 92 DR M LL CN A t/NR 2900 2200 2100 2000 1900 ,
92 DR M LL CM t t/NR 2900 2200 2100 2000 1900 .
92 RX BLDC VtNT 4At CPM 08M(*186) 04N 08N 00N OSH 92 RK BLDG VENT . PART CPM 0$N(*1t6) 0$N 0$N OSM 0$N 31 9 10 kN BLDG vtNT MORTH MR/NR OSN(>1[3) 0$N 0$N 08N 0$N 32 9 10 RN BLDG VtNT SOUfN MR/NR OsN(>1(3) 06N 0$N 0$N DSN 453A 9 10 SPENT FUEL POOL A MR/NR 7000 7000 6000 6000 2400 4538 9 10 SPENT PutL POOL A aut/Ma 7000 7000 6000 6000 2400 9 10 MIN $tu 1INE A MR/NR 0 0 0 0 0 ftie NAIN sim LINT 8 MR/NR 0 0 0 0 0
-9 10 MAIN STM LIN( C> MR/NR 0 0 0 0 0 9 10 MAIN SIM LINT 0 MR/NR 0 0 0 0 0 38 9*10 $JAt(AIR EJECTOR) MR/NR 0 0 0 0 0 G
s t
p, ;e .
!!j f ,
i ;
1 i
l).
.,t ._
t
) . n.>:x;v, a . ;
)
,a ;
' l 1
.x' VERMONT YANKEE NUCLEAR POWER STATION ENERGENCY RESPONSE PREPAREDNESS EXERCISE ~ l>
t 1990 : }
L a
- i i
v ?
,.1- ,
3
- c. r tf , i 3
-i e 9.3 IN P1 ANT RADIATION LEVELS '
.,' i
.s c ;
-!.' .. i
.i
?
l D
.=i 1 )
5 e
}
d .
I r
?
3 .r~ -.;.;
e -h i
e
+
3 t
i' I
k ?
t!
h o 4 li' ,j 4 ,
. f t kk
., i 4
+
t
..'f
.Li,' y i ij ,
-i . !
,9 1
- r. .
- O 6 , ; a TABLE 9.3-1 Rev. O Page 9.3-la Reactor Building Refuel Deck, Elevation 345' (mR/hr unless otherwise noted)
Clock Scenario Time Time ARM 12 ARM 14 ARN 15 453 A 453 B Zone I Zone II~ Zone III Zone IV t
i 07C0 0 4 3 8 10' 10 4 10 10 10 08CO 1:00 4 3 8 10 10 4 10 10 10 ;
C815 1:15 3 3 8 9 9 4 10 10 9 C830 1:30 3 3 8 9 9 4 9 9 9 C845 1:45 2 2 8 8 8 3 9 9 9 C903 .2:00 2 2 8 8 8 3 8 8 9 G915 2:15 2 2 8 8 8 2 8 8 8 ,
C930 2:30 2 2 8 8 8 2 8 8 8 !
I C945 2:45 2 1 8 7 7 2 8 8 8 i 1600 3:00 1 1 8 7 7 2 7 7 8 i 1015. 3:15 1 1 8 7 7 1 7 7 8 1030 3:30 1 1 8 7 7 1 7 7 8 1C45 3:45 1 1 8 7 7 1 7 7 8 !'
1103 4:00 1 1 8 7 7 1 7 7 8 1115 4:15 1 1 8 7 7 1 7 7 8 ;
1130 4:30 1 1 8 7 7 1 7 7 8 i -1145 4:45 600 600 600 600 600 600 600 600 600 1203 5:00 1800 1800 1800 1700 1700 2000 1700 1700 2000
- 1215 5
- 15 3900 3900 3800 3700 3700 4000 4000 4000 4000 1230 5:30 5500 5400- 5300 5200 5200 5500 5000 5000 5500
- 1245 5:45 6600 6500 6400 6200 6200 6600 6000 6000 6600 i i
13C0 6:00 7600 7500. 7400 7200 7200 7600 6950 6950 7600 l
1315 6:15 7200 7000 7000 6900 6900 7300 6600 6600 7300 1333 6:30 7000 6800 6700 6600 6600 7100 6500 6500 7100 -
1345 6:45 6700 6600 6500 6300 6300 6700 6100 6100 6700 1400 7:00 6500 6400 .6200 6100 6100 6500 5900 5900 6500 Notes: Zone readings are averge dose rates throughout zone. [
General area contamination levels 2K-10K dpm/100 cm2 in all zones after 1130. j
- g. , ,c.,
.S, g , ;
t REACTOR BUILDING ,
w-N , ELEVATION 345*
1 .
MONITORS 1 la ~
L__
12 - REACTOR BUILD 98G ELEVATOR ENTRANCE I C g 2 is . REACTOR BUILD 80G WEST REFUEL 98G AREA -
g OPEN HATCH '
- 453A - FUEL POOL WEST n 'i l -
a j 2 is - SPENT rua ,m 1 . i 4 -
I CAM N & i .
f' 4538 - FUEL POOL EAST . I*
. I 4
O
_ f 2 c
< n f() g 0,- % L
'r- - - - - - - ]
y l m i O .
' 's s :
8 e
' \
' l m. -
CAvrTY % ^
1 l !
sTORAas m SPENT FUEL POOL 5 - - - - - -
I e- '
9 ' I i I
- t_. - - -_ _ _
j t
]
_ _ _ . j s I _A
' 4 O ~~ \x /
r s
( t '
l % ~~ .. # '
A l ;
J g l VO '----- J -
= ST_ORAGE M
. = 3 RBAC-10 RRAC-1C
- E
. r ra r
. . r. I .
Y 5
m p. ,p
~ [ifl TABLE 3.?-2 I Rev. O R? actor Building, Elevation 318' Page 9.3-2a (I'R/hr unless othervire noted)
Clock Scenario Time Titee ARM 10 ARM 11 ARM 16 Zone I Zone II Zone III Zone IV Zone V Zone VI Zone VII
, 0700 0 5 5 1 5 5 3 5 4 1 1 C803 1:00 5 5 1 5 5 3 5 4 1 1 C815 1:15 4 4 1 5 5 3 5 4 1 1 C830 1:30 4 4 1 5 5 3 5 4 1 1 i C845 1:45 4 4 1 4 4 3 4 3 1 1 !
C900 2:00 4 3 0.5 4 4 3 4 3 0.5 0.5 t a
C915 2:15 4 3 0.5 4 4 3 4 3 0.5 - 0.5 i 0930 2:30 4 3 0.5 4 3 2 3 2 0.5 0.5 C945 2:45 3 3 0.5 4 3 2 3 2 0.5 0.5 1030 3:00 3 3 0.5 4 3 2 3 2 0.5 0.5 1015 3:15 3 2 0.5 3 2 2 2 1 0.5 0.5 !
! 1G30 3:30 3 2 0.5 3 2 2 2 1 0.5 0.5 1C45 3:45 3 2 0.5 3 2 1 2 1 0.5 0.5 11CO 4:00 3 2 0.5 3 2 1 2 1 0.5 0.5 1115 4:15 3 2 0.5 3 2 1 2 1 0.5 0.5 1130 4:30 3 2 0.5 3 2 1 2 1 0.5 0.5 -
1400 1145 4:45 1700 1700 7 1700 1700 1000 1700 800 1400 1200 5:00 5300 5500 20 5300 5500 4500 5500 3600 4200 4200 ^
j 1215 5:15 (OSH)>1E4 (OSH)>1E4 50 EiOOO 12000 10000 12000 8000 8800 8800 1230 5:30 (OSH) (OSH) 70 17000 20000 15000 20000 12000 14000 14000 1245 5:45 (OSH) (OSH) 84 20000 24000 20000 24000 16000 16000 16000 l'a OO 6:00 (OSH) (OSH) 98 23000 28000 22000 28000 18000 18000 18000 1315 6:15 (OSH) (OSH) 94 22000 27000 21000 27000 17C00 17000 17000 1330 6:30 (OSH) (OSH) 91 21000 26000 21000 26000 17000 17000 17000 1345 6:45 (OSH) (OSH) 85 20000 24000 20000 24000 16000 16000 16000 .
1403 7:00 (OSH) (OSH) 82 19000 23000 20000 24000 16000 15000 15000 Notes: Zone readings are average dose rates throughout zone.
General area contamination levels 10K-50K dpm/100 cm2 in all zones after 1130.
(OSH) OFF SCALE HIGH l
E t9)
^ v RuACTOR BUILDING w-y ELEVATION 318' i
MONITORS yn a i n a Ei y us l
y . OPUS 1
Fr L
=
10 - REACTOR DULDeeG ELEVATOR ENTRANCE BATTERY W )/ l l* HATOf M --
zg
. - = = E g
- ' ' ; ; U - -
H - REACTOR BULDOeG REACTOR MTER CLEANUP AREA E E- i M - -
I sutRitR i 1 -
m I O D r3- REACroR sutDeeG NEw ruEL vAuur n
, t D( 1111111'I CU FETER/DEMW8 g
I pfvERTER l ia [ HOLD 00G N N
E E k
[
i 3 ,
j - o ll O y 3 0 ,
g l curtievoEmme , y - - - - -
y - - Ja C c)r _
-Ne----
^7 g i
~
y BATTERY PACKS l l s a a E lX[ N I $
l m
, w
' E $3
! l
! . I
- FUEL STORAGE j POOL !
j DRYER SEPARATOR STORAGE y l
i i
- I s I i
(
)
i h []i-s As Coou=G mitR = 8 SuRm 1Am i T __ __6 __ __13_ l_l_l 50 l '> ga d'"B~ '""~" l#2'" NUELu SNGE I
- =
= a 1 7
! aEv i ,
M M M N M I
.J Q
- 3 4
- + Mh w
'f '
ia ':
9
)
TABLE 9.3-3 Rev. O Reactor Building, Elevation 303' Page 9.3-3a (mR/hr unless otherwise noted)
Clock Scenario Time Time ARM 8 ARM 9 Zone I Zone II Zone III Zone IV Zone V Zone VI Zone VII
'0700 0 3 4 4 3 6 3 6 5 5 0800 1:00 3 4 4 3 6 3 6 5 5 0315 1:15 2 4 4 3 6 3 6 5 5 0830 1:30 2 4 4 3 6 3 6 5 5 0845 1:45 2 4 4 3 6 3 6 5 5 0900 2:00 2 4 4 3 6 3 6 5 5 0915 2:15 2 4 4 4 6 4 6 5 5 0930 2:30 2 4 4 4 6 4 6 5 5 0945 2:45 2 4 4 4 6 4 6 5 5 1000 3:00 1 4 4 4 6 4 6 6 6 1015 3:15 1 4 4 4 7 4 7 6 6 1030 3:30 1 4 4 4 7 4 7 6 6 1045 3:45 1 4 4 4 7 4 7 6 6 1100 4:00 1 4 4 4 7 4 7 6 6 1115 4:15 1 4 4 4 7 4 7 6 6 i 1130 4:30 1 4 4 4 7 4 7 6 6
. 1145 4:45 1000 1600 1400 1400 900 1400 1400 1100 1400 l 1203 5:00 4000 5600 4200 4200 3000 4200 4200 3400 4200 1215 5:15 7800 9600 8800 8800 6000 8800 8800 7000 8800 '
1230 5:30 (OSH)>1E4 (OSH)>1E4 14000 14000 9000 14000 14000 11000 14000 1245 5:45 (OSH) (OSH) 16000 16000 10000 16000 16000 13000 16000 1303 6:00 (OSH) (OSH) 18000 18000 11000 18000 18000 14000 18000 1315 6:15 'OSH) (OSH) 17000 17000 11000 17000 17000 14000 17000 1330 6:30 LOSH) (OSH) 17000 17000 11000 17000 17000 14000 17000 l
1345 6:45 (OSH) (OSH) 16000 16000 10000 16000 16000 13000 16000 1400 7:00 (OSH) (OSH) 15000 15000 9600 15000 15000 12000 15000 Notes: Zone readings are average dose-rates throughout zone.
General area contamination levels 10K-50K dpm/100 cm2 in all zones after 1130.
(OSH) OFF SCALE HIGH
W
- n. 1 ,
REACTOR BUILDING ;
t i w -fy ELEVATION 303*
i j MONITORS i
- a - REACTOR BUILD 98G ELEVATOR ENTRANCE N = = !
i 9 - REACTOR BUILDING REACTOR VetTER i 5 2 2 a =
4 CAUBRATKW LAB t ctEANUP AREA i ca == t c-3
, c -
g m i.
o a
- _ _ _ _ _ _ _ _ _[unemfi . m _ __ _ __ ____ _ [ i i [-] , 5 i ' ' - I srrnx i 3 i 3
~
r' g _. r - -_ J. e!
~- 2l 4
l *
/ I C C D '
- /
A g *--~[ M l l , W l RBCCW N f l U. [ FUEL STORAGE POOL HDT 84RCHIEE
^ ( j suor w-1 '
RecCw w \ l 8 \ g
. N
\ l C r- O__ 's _ _ m _i _ _ _ . _
= = . ,
) hp 1 -
au po 7 :
- C3 - OQ- - - . _ _
Y l
@ i
- , _ . . _ . . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______m___..
, '4 :, .
~
'. ;- /
l TABLE 9.3-4 Rev. O Reactor Building, Elevation.280' (mR/hr unless otherwise noted) , < RB Vent RB Vent clock Scenario North South
- Time Time ARM 6 ARM 31 ARM 32 Zone I Zone II Zone III Zone IV Zone V Zone VI Zone VII .
07CO O 8 1 1 10 12 10 8 10 12 1 08CO 1:00 8 1 1 10 12 10 8 10 12 1 0815 1:15 7 1 1 8 12 8 7 8 12 1 C830 1:30 7 1 1 8 12 8 7 8 12 1 0845 1:45 7 1 1 8 10 8 7 8 10 1 0900 2:00 6 1 1 8 10 .8 6 8 10 1 , 0915 2:15 6 1 1 7 10 7 6 7 10 1 0930 2:30 6 1 1 7 10 7 6 7 10 1 0945 2:4' 6 1 1 7 10 7 6 7 10 1 1000 3: 0 ~, 6 1 1 7 9 7 6 7 9 1 1015 3:15 5 1 1 7 9 7 5 7 9 1 1030 3:30 5 1 1 7 9 7 5 7 9 1 . 1 1045 3:45 5 1 1 7 9 7 5 7 9 1 1100 4:00 5 1 1 7 9 7 5 7 - 9 1 1115 4:15 5 1 1 7 9 7 5 7 9 1 1130 4:30 5 1 1 7 8 7 5 7 8 1 1145 4:45 1700 OSH(>1E3)OSH(>1E3) 2000 2200 2000 1700 2000 2200 2000 1203 5:00 5500 OSH OSH 5500 5800 5500 5500 5500 5800 5000 1215 5:15 OSH(>1E4) OSH OSH 12000 15000 12000 11800 12000 15000 10000 1230 5:30 OSH OSH OSH 20000 24000 20000 17000 20000 24000 15000 1245 5:45 OSH OSH OSH 24000 29000 24000 21000 24000 29000 18000 13C0 6:00 OSH OSH OSH 28000 34000 28000 24000 28000 34000 20000 1315 6:15 OSH OSH OSH 27000 32000 27000 23000 27000 32000 20000' 1330 6:30 OSH OSH OSH 26000 31000 26000 22000 26000 31000 20000 1345 6:45 OSH OSH OSH 24000 29000 24000 21000 25000 29000 20000 1400 7:00 OSH OSH OSH 24000 28000 24000 20000 24000 28000 20000 Notes: Zone readings are average dose rates throughout zone. General area contamination levels 20K-100K dps/100 cm2 in all zones after 1130. Zone VIII same as Zone VI
- li! li!!l f ! .!.!j;; ! f;j ! !{' ,'Tlt;tI!:Iif
_. 3ocUN D v* ! ,, .Ye _ +
" : { , -
J
,! EE
_ i" I , i- - Qm 6 eR . tK
, l ii; K
g1y rC rA A I pg' M ,
% r. =
O - , mc = T* - " m N t V* w
=
t mc-= r g - E E r o
- p ,
O7 i> i y .,.
' ' e I*
s s .s E G 8 0 0 H_"'uH a 0 " _ N __D
%Gj
=
==
N 2 I D N J.. E- _T __ - ,,
- L O I
I g H n
~
~
U T G A o B A _T [ v8w G V x E .- \ [ A z R L / r \ E t 7 L QT - _ " i 1 Y,e. . _H x ( e f A [ - 3 r _ E " - B === A
="
=
H X
- _.m H 2 "5 D w
; i.
G u " .
. N M
g
- a "
u-
]
_'E I. _' 5 n= Fjt
' ,i7IgJ-_
0 - .
. y r 0 _ .
$_- _ 1 J _} "
E . C N A R T M E S m T R A V O T I E R - - ) N % i H T O D U M L U B mm_S a t O ( R m mm m,T O 1 r.. e s m._.m_ o o o m s , . 1
g" _79%, TABLE 9.3-5 Rev. O Reactor Building, Elevation 252' Page 9.3-Sa.1 (mR/hr unless otherwise noted) Clock Scenario RM- Zone Zone Zone Zone Zone Zone Zone-Time Time ARM 2 ARM 3' ARM 4 ARMS ARM 7 14-29* I II III IV V VI VII _ C700 0 10 1 5 300 20 100 5 12 1 300 1 20 28 0800 1:00 10 1 5 300 20 100 5 12 1 300 1 20 24 . 0315 1:15 8 1 5 240 10 100 5 12 1 24p 1 10 20 0330 1:30 6 1 5 180 10 100 5 10 1 180 1 10 18 0845 1:45 5 1 5 140 10 100 5 8 1 140 1 10 15 0900 2:00 4 1 5 100 10 100 5 7 1 100 1 10 13 0915 2:15 3 1 5 90 10 100 5 5 1 90 1 10 10 0930 2:30 3 1 5 70 10 100 5 5 1 70 1 10 10 0945 2:45 2 1 5 50 5 100 5 3 1 50 1 5 10 1000 3:00 1 1 5 30 5 100 5 2 1 30 1 5 10 1015 3:15 1 1 5 20 5 100 5 1 1 20 1 5 10 1030 3:30 1 1 5 20 5 100 5 1 1 20 1 5 10 1045 3:45 1 1 5 10 5 100 5 1 1 10 1 5 10 1160 4:00 1 1 5 10 5 100 5 1 1 10 1 5 10 1115 4:15 1 1 5 10 5 100 5 1 1 10 1 5 9 1130 4:30 1 1 5 10 5 100 5 1 1 10 1 5 8 1145 4:45 >1E3 >1E3 1800 6000 200 >500 2000 2000 3000 6000 3000 200 250 1200 5:00 (OSH) (OSH) 10000 >1E4 600 >500 10000 10000 12000 19500 12000 600 700 1215 5:15 (OSH) (OSH) >1E4 (OSH) 1400 >500 16000 16000 20000 41000 20000 1400 1800 1230 5:30 (OSH) (OSH) (OSH) (OSH) 2100 >500 20000 20000 25000 53500 25000 2100 2900 1245 5:45 (OSH) (OSH) (OSH) (OSH) 2500 >500 24000 24000 30000 64000 30000 2500 3500 1300 6:00 (OSH) (OSH) (OSH) (OSH) 3000 >500 28000 28000 35000 74P'O 35300 3000 4000 1315 6:15 (OSH) (OSH) (OSH) (OSH) 2800 >500 27000 27000 33000 7' me ?1000 2800 3800 6:30 (OSH) (OSH) (OSH) (OSH) 2700 >500 26000 26000 32000 lei: .900 2700 3700 1345 6:45 (OSH) (OSH) (OSH) (OSH) 2500 >500 24000 24000 3000' J- ?/ MM) 2500 3500 1400 7:00 (OSH) (OSH) (OSH) (OSH) 2500 >500 24000 24000 300f4 ^+Nw #s e0 2500 3400
^
I Nnte.n: Zone readings are avera9e dose rates throughout zone. ' General area contamination levels 20K-luck dpa/100 cm2 in all r; e mi 1130. w w , -
, a p- -.>,s- - . . . - , ,
<- s-m. W, i
Rev. O Page 9.3-Sa.2 TABLE 9.3-5 (Continued) Clock Scenario NORTH SOUTH TIP Time Time RMS II-1** RMS II-2** RMS II-3** 0700 0 <1.0 <1.0 <1.0 0800 1:00 <1.0 <1.0 <1.0 0815 1:15 <1.0 <1.0 <1.0 0830 1:30 <1.0 <1.0 <1.0 0845 1:45 <1.0 -
<1.0 <1.0 0900 2:00 <1.0 <1.0 <1.0 0915 2:15 <1.0 <1.0 <1.0 0930 2:30 <1.0 <1.0 <1.0 0945 2:45 <1.0 <1.0 <1.0 1000 3:00 <1.0 <1.0 <1.0 i 1015 3:15 <1.0 <1.0 <1.0 i
1030 3:30 <1.0 <1.0 <1.0 i 1045 3:45- <1.0 <1.0 <1.0 1100 4:00 <1.0 <1.0 <1.0 i 1115 4:15 <1.0 <1.0 <1.0 1130 4:30 <1.0 <1.0 <1.0 l 1145 4:45 2 3 2
! 1200 5:00 10 12 10 i 1215 5:15 16 20 16 i
1230 5:45 20 25 20 1245 5:45 24 . 30 24 1300 6:00 28 35 28 1315 6:15 27 33 27 *
'1330 6:30 26 32 26 -
1345 6:45 24 30 24 1400 7:00 24 30 24 l Notes:
** RMS II readings in R/hr (high-range accident ARMS - 1 R/hr to 10,000 R/hr)
. .w y - . . -
, , , . - . _ ____.__m_ _ ,
_ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . . . _ _ _. ,,___._m. ,_______ _ .__ . _ _,,_..__,.m ,,___ ...
, FIGURE 9.3 5 e.e. u.a l
n*
' - W e o , E _ ,
g I , , , i . -
~
9 l
,M U a 3.8 W l c- a c a inve m n e m nos
**#g l': l l - ;- 4 N--
Ia gie e-
;* 3 r ,- ,wgg x cr> l !/ g Y ~ ~- - - ~~
g L Il L- 'j j f""j, g l
- l. -
pSA j th::
,. =_
qy s g j_ _ .__ _ _ _ _ _ I / :- 7I alO t 5 / '~~~N ' E I N i i _ , [gr- . 5l-p i s ni l< l 9 b wc= == a m' N : y t; [l.i lC i _gg i -<.m oo m - g_ g gggi 9 ,
, -- - m i ,
a! ii q@i ls :i 1! 1.1 s e O ~-l_5 $ g! 5
!, ,l,. l1
;E !$
!l lll E i.! x ,E E
8 " 85
*~*
EEE Ufwlalwlt!Ell.i a a a i
. - . =
s.n~m-~....w _ a.. t
-. A' m
*-' y' A U
'. 1 TABLE 9.3-6 Rev. O i Turbine Deck, Elevation 272' Page 9.3-6a ,
(mR/hr unless otherwise noted) Turbine Deck clock Scenario CAM (cpm) i Time Tina ARM 24 Zone I Zone II Zone III NG Particulate' 0700 0 190 100 150 190 250 900 0800 '1:00 190 100 150 190 250 900 0815 1:15 180 80 140 180 250 900. 0830 1:30 160 75 120 160 250 900 . 0845 1:45 140 75. 120 140 25G 900 0900 .2:00 110 75 90 110 250 900 0915 2:13 100 50 ~ 80 100 250 900 6930 2:30 80 30 70 80 250 900 0945 2:45 70 40 60 70 250 900 1000 3:00 60 -40 50 60 250 900 1015 3:15 50 30 50 50 250 900 1030 3:30 50 30 40 50 250 900 1045 3:45 40 20 35 40 250 900 1100 4:90 40 20 35 40 250 900 1115 4:15 40 15 30 40 250 900 1130 4:30 30 16 22 30 250 900 1145 4:45 30 16 22 30 250 900' 1200 5:00 30 11 22 30 250 900 1215 5:15 30 11 22 30 250 900 1230 5:30 25 11 22 "25 250 900 1245 5:45 25 10 20 25 25G 900 1300 6:00 25 10 20 25 250 900 , 1315 6:15 25 10 20 25 250 900 , 1330 6:30 25 10 ~ 20 25 250 900 1345 6:45 25 10 20 25 250 900 - 1400 7:00 25 10 20 25' 250 900 Notes: ' Zone readings are average done rates throughout zone. General area contaminattan levels <1K dpm/100 cm2. _ . - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - - _ _ - - . _ ' ' ' ' ' " * ' ^-_A _ - " M- -v- " -
. ip! t[ L y. f" ,[ i'. . t i;<: ;! ;!:l! ,
nm
- em ,,1 ? .
_r , m__
.~ '
4 _
- ,o,i;ii'l
- 4 h
n4 .
, ,l i!
-j y
, r _
p
, L' _
I ( K' C. E 2 7 2 p t _N _ 4 D. .'
/
E O N 3_ 2 N I T F - I B A - . R V 4 - U E p T L L I E T _ r . u } a_
. w-o.
n 4]
._ R l
)
. ' iiL
+
N- e _ O e n _ M
- R E
N eg@ - E G 4 ( T i M M M l l gii ls A E T S -
.R E N
O ._ O R ii, T I U T , j < i.!!3 ._ N G rixg!i ._ N n" O I Ec e -
=
M D L I U oen - , B E NI
' ,p'_
B R
. U T .
4 ~
- n. 2
.- 7 _
7 . _
f f,,w. v' -. i* . M: j. ~ y-
' TABLE 49. 3 Rev. O Turbine Building Truck Bay, Make-Up Demineralization Cond. Page 9.3-7a ,
Demineralization. Areas, Elevation 252'
- (mR/hr unless otherwise noted) l Clock Scenario RM-14-23A RM-14-36 Time Time (cpm) - ARM 26 (cpm) Zone I Zone II Zone III Zone IV '
0700 0' .150 0.02 :150 0.2 0.2 0.1 0.2 - 0800 - 1:00 '150 0.02 150 0.4 0.3 0.2 0.2 0815 1:15 150 0.02 150 0.5 0.3 0.2 0.2 0830 - 1:30 130 0.02 150 0.5 0.3 0.2 0.2 0845 1:43 150 0.02 150 0.5 0.3- 0.2 0.2 0900 2100 150 0.02 150 0.5 0.3 0.2 0.2 0915 2:15 .150 0.01 150 0.5 0.3 0.2 0.2 0930 2:30 150 0.01 150 0.5 0.3 0.2 0.2 0945 2:45 150 0.01 150 0.5 0.3 0.2 0.2 ' 1000 3:00 150 0.01 150 0.6 0.3 0.2 0.2
- 1015 - 3:15 15D 0.01 ~150 0.6 0.3 0.2 0.2 1030 3:30 150 0.01 150 0.6 0.3 0.2 0.2 1045' 3:45 150 0.01 150 0.6 0.3 0.2 0.2 1100 4:00 150 0.01 150 0.6 0.3 0.2 0.2 ,
1115 4:15 150 0.01 150 0.7 0.3 0.2 0.2 1130 4:30 150 0.01 150 0.7- 0.3 .0.2 0.2 1145 4:45 150 0.01 150 0.7 0.3 0.2 0.2-1200 5:00 150 0.01 150 0.7' O.3 0.2 0.2 1215 5:15 150 0.01 150 0.7 0.3 0.2 0.2 l 1230 5:30 150 0.01 '150 0.7- 0.3 0.2 0.2 1245 5:45 150 0.01 150 0.7 0.3 0.2 0.2 - 1300 6:00 150 0.01 150 0.7 0.3 0.2 0.2 1315 6:15 150 0.01 150 0.7 0.3 0.2 0.2 'I 0.01' l 1330 6:30- 150 150 0.7 0.3 0.2 0.2 1345 6:45 150 0.01 150 0.7 0.3 0.2 0.2 1400 - 7:00 150 0.01 150 0.7 0.3 0.2 0.2
- Notes
- Zone readings are. average dose rates throughout zone. - -
General area contamination levels <1K dpm/100 cm2. l
~ , . - y
"'. > , - _ .s . m'...J ....._.2-re [.
ELEwdlON 252' PRETREATMENT ROOM, BOILER R6Ohil, TURBINE LOADING BAY, MUDS, DIESELS. COND. DEMIN. HATCH s .. . . <
'g 26 j -
~
l h EE U _ [;;gg g I
"*** Il III' I f__
1 MONITORS !
, ((
- g L- . . .- l Ete
- we ll -
23A - TURBHE B"ELDMG RALHOAD _ g l # TRACK RM-145 Z l i . I O I i 36 - WEST TLMBNE BULDMG EXIT 5 m TB C@ T*'*
*' o l RM.ws h6 ,, a I g l g g ,o i CAM ; gg:
I- " ' ] 26 - IlNIBINE LDWG RAE.HOAD DOOR C' - I- '
- n 2 ~
_l lPCM l -l Generehr 3 h or s I
.I i
t
, _sivi "mg 6ci i
i g5 1, Q (j
- l l 3 co -
i c m o t- a i O o i i
- =
- =
_L'__ _ J-i m 9 000
~~
f- _ _. ~
. iri F 1' i :
u IG I
- l I l
" ' " ~ ~
Yl .I f SJAE ROOM F 5 k _ _ _ _ _ - l
'I _
o _ ~] - , 1 l _ _ _ _ J g l i- y ._ _ _
\ _ _ _ ._
DIESEL 'g DIESEL g'l GEN 1Ei a GEN 1 A u_- O O O O O
- , _ _ _ ..., 3 c
O -
- 5 O o o o 4 -
Plop ltJI o . . o
. 33m[.v t-l TABLE 9.3-8 Rev. O Turbine Building Cond. Bay, Elevation 248' Page 9.3-8a (mR/hr.unless otherwise noted) l Clock Scenario Time Time ARM 20 ARM 21 Zone III Zone IV Zone V Zone VI Zone VII Zone VII 0700 0 3 370 2 2 4. 8 300 3 0800 1:00 3 370 2 2 4 8 300 3 0815 ~1:15 3 350 2 2 4 8 300 3 0830 1:30 2 320 2 2 4 8 300 2 ~
0845- 1:45 2 270 2 2 4 4 300 2 0900 2:00 2 230 2 2 3 . 4 200 2 0915 2:15 2 190 2 2 3 4 150 2 0930 2:30 2 160 2 2 3 4 150 2 0945- 2:45 2 140 2 2 3 4 150 2 1000 3:00 2 120 2 2 3 4 100 2 1015 3:15 2 110 2 2 3 3 100 2 . 100 1030 3:30 2 2 1 3 3 90 2 1045 3:45 2 90 2 1 3 3 80 2 0 1100 4:00 2- 80 1 1 3 3 80 2 1115 4:15 2 70 1 1 2 3 60 2 1130 4:30 2 65 1 1 2 3 60 2 1145 4:45 2 60 1 1 2 2 50 2 1200 5:00 2 55 1 1 2 2 50 2 1215 5:15 2 55 1 1 1 1 50 1 1230 5:30 2 50 1 1 1 1 50 1 1 1245 5:45 2 50 1 1 1 1 50 -1 1300 6:00 2 50 1. 1 1 1 50 1 1315 6:15 2 50 1 1 1 1 50 1 1330 6:30. 2 50 1 1 1 1 50 1 . 1345 6:45 2 50 1 1 1 1 50 1 1400 7:00 2 50 1 1 1 1 50 1 Notes: Zone' readings are average dose rates throughout zone. General area contamination levels <1K dpm/100 cm2. 4
s . p/.
' ~
TURBINE BUILDING ELEVATION 248' t
- N-,-
4
~
MONITORS 1lr - - s 20 - TURBME BUE DMG NORTH ,, PERSOpelEL ACCESS g .
; y - - - - -- -- -- - - -- - - - -
p '
~ ~
a1. TURBN6 BULDMG MAN STEAM 20 E f STOP VALVE AREA @f FW HIR B-2 3 {F FW HTR-18-@ f .. - q . . i>e ! C 1 I
@f FW HIR-A-25 (F FW HTR-1 A-@ g E
l i I i me S i OO O Ol } b
- g h "1"^"TAM "
ge.cx=G g 6 _ __ J [_.._ _ J:p
~
i l i i
;A _1 -
t_ _ i. i r ..= 4 a I a n STOP VALVEj! 2j m i i m i ' 8:3 CONDENSER I , CONDDISER
; I GENERATOR LEADS ROOM g l'
~
- l g"' 'y -
l 8 m l
-7 g I v v v vo ! l 3 1 L _ _ < _
l -A- i 00 MAN STEAM
- ___ _ ._ s i
'~
BYPASS VALVES l l 1 - j' ' l . e l 1 y
, i s i E-
. 8 ,
. , . ,. = .
~. - _ _ . __ _ _ _ _ _ .____________ __________
- ~
c'
~
u-q m. . g ~ ~ ej a
;,a * .g .
~
- Rev. O TABLE 9.3-9 Page 9.3-9a Turbine Building, Demineralization /OG Areas, Elevation 232' (mR/hr unless (,cherwise noted)
Clock Scenario Time Time JGUI 22 ARM 38 Zone I Zone II Zone III 0700 0- 0.3 17 0 0.2 0.5 0.2 0800 1:00 ^0.3 70. 0.2 0.5 0.2 0815 1:15 0.28 60 0.2 0.5 0.2 On?O 1:30- dJ 26 50 0.2- 0.5 0.2 0345 1:45 0.24 40 0.2- 0.5 0.2 0900 2:00 0.20 '30 0.2 0.5 0.2 0915 2:15 0.20 25 0.2 0.5 0.2 s O '. 0 2:30 0.18 D/S 0.2 0.5 0.2 094F 2:45 0.18 D/S 0.2 0.5 0.2 1000 3:00 0.16 D/S 0.2 0.5 0.2 1015 '3:15 0.15 D/S 0.2 0.5 0.2 - 1030 3:30 0.15 D/S 0.2 0.5 0.2 1045 3:45 0.14 D/S 0.2 0.5 0.2 ' 1100 4:00 0.14 D/S 0.2 0.5 0.2 1115 4:15 0.14 D/S 0.2 0.5 0.2 1130 4:30 0.13 D/S. 0.2 0.5 0.2 1145 4:45 0.13 D/S 0.2 0.5 0.2 1200 5:00 0.13 D/S 0.2 0.5 0.2 1215 5:15 0.13 D/S 0.2 0.5 0.2 1230 5:30 0.13 D/S 0.2 0.5 0.2 1245 5:45 'O.13 th/S - 0.2 0.5 0.2 1300 6:00 0.13 D/S 0.2 0.5 0.2 1315 6:15 0.13 D/S 0.2 0.5 0.2 1330 6:30 0.13 .D/S' O.2 0.5 0.2 1345 6:45 0.13 D/S 0.2 0.5 0.2 1400 7:00 0.13 D/S 0.2 0.5 0.2 Notes: Zone readings.are average dose rates-throughout zone. General area contamination levels <1K dpm/lon 4
- D/S ='Downscale reading.
ng'- , , , j r ~,. _ , n- N ,<~r .- y _ _ ._______________________________,_____._,____;.., _,
is ,
+
+
FIGURE 9.3 9 Page s.3 9b L. . A , ,, o " r i
, ('E' l b l F
, .k I. ,
W 4 n, ' 5 O E, " E d
] Eh
@D
; @D gg
.28 jg le-5 @ 8 g n l
s agi-i s e g.g i e.
. Is n- L 8
do 1 , g n. . -r- i!g g _E g" _ ._____ I r ' - T
~ ~ '"
. e e i
=-- ' w-'- . " ' ,
EE ""U 1.. . . __5!!la 0 1 R 3os -'""?!-'
= .
E d i g DW CONDENSATE EE H '6 5 CD I BACKWASH neCeiven TANK E O W j r T - E Rg >lf ~ ul x ; R p g g g- i CoNoeNS 1e oeu,NenAtizens gg
~
e
;fg L_._@_.__@_.._@_._@__.
COND M __ k COND DEM,N TINK
. ~!
i' ' ' ' ' ' ' ~ ._ E,
.I '
C lo 5 6
' ' ~ s.
~
H. f$ - g 1 2g g s, , , 2 y* $
- r. g- 5
- g llr k f d.
i
. . . . - ._. . s a
- :'t
. e- g. j
'O 4 TABLE 9.3-10 Rev. 0 .
Page.9.3-10a Turbine Building Cond. Bay, Elevation 222'6" & 228'6"
-(mR/hr unless.otherwise noted)
Clock . Scenario Time Time' ARM 13 Zone-I Zone II Zone III Zone IV Zone V Zone VI 0700 'O 150 3 ., 1 50 150 2 75 ' 0800 1:00 150 3 1 50 150 2 75 0815 1:15 140 3 1 45 140 2- 70 0830 1:30 130 3 1 45 130 2 70
.0845 1:45 110: 3 1 .35 110 2 55 0900 2:00 90 3 1 30 90 2 45 0915' '2:15 80 3 1 25 80 2 40 0930 2:30 70 3 1 20 70 2 35 0945 2:45 60 1 1 20 60 2' 30 1000 3:00 50 ' 1 1 15 50 2 25 1015 3:15 40 1 1 10 40 2 20.
1030 3:30 30 1 1 RO 30 2 15 1045 3:45 30 -1 1 10 30 2 15 1100 4:00 20 -1 1 5 20 2 10 1115 '4:15 :20 1 1 5 20 2 10 1130 4:30 15 1 1 5 15 2 7 1145 4:45 15 - 1 1 5 15 2 7 1200 5:00 15 1 1 5 15 2 7 1215 5:15 15 1 1 5 15 2 7 1230 5:30 15 1 1 5 15 2 7 l 1245 5:45 15 1 1 5 15 2 7 l 1300 6:00 15 1 1 5 15 2 7 . 1315 6:15 15 1 1 5 15 2 7 1330 6:30. 15 1 1 5 15 2 7 - 1345 6:45 15 1 1 5 15- 2 7 ' 1400 7:00 '15- 1 1 5 15 2 7 - Notes: Zone readings are average dose rates throughout zone.
. General : area contamination levels <1K dpm/100 an2.
f l .- _ -__ _ _ . _ . ~ ..
~
- g. ,4,, ', , , - s TURalNE BUILDING .. . g .
a- -' 9 ELEVk.' ION L 222' & 228,. _ s ., 9
*N~ .
~
l 1
.: i MONITOR .
i 3 I -1 I ; 23 - tunene suitono uOisme SEPARATOR AREA , , , , , , , , y,cc r p a ri l O Ml
~
R a
~
- ,_ BOX PRNARY PUMPS g El H -
'o
- A B o m
#l . _
L _UBE OIL
.i
'" '* "** ' l tuRB LM i
i /=\ D A / \ DO 'i t @@ < i M" ~ ITITTTITT1 q l' ; M O g j ; F- i i-- -
'l ! 3
, 2 ._
i n - l c - s= i 4 1 5 l^ , g "
, x .
s t _ _ _.o_ .4 's I l
--] [- - !_ _
m so _ T y C Ms C Ms = = - CO coND BACKWASH RECENER RMM E
~
U -
'^
I * '8 5 l.' O= 1 i H1R .W tl e,, - COND BACKWASH RECENs TAMK oEfn i -etars- Eow - - - 1 DRAM O
) Of'og ' g
( l - - Sk"I I ( LP FW HTR-1 A-3 0 E
~
3 Q LP FW HTR-1A-4 ) l fi: l 6 ( te rW ums-3 D l W O tP FW HIR 18-4 ) -
. . s a I e f-
- ~ , m r.,-w.
e r..- - e ~,
, , ~-+--y. -
..m
m m p%) ~ : t,- n u l Rev. 0 - l TABLE ~9.3 1 Torus Catwalk - (mR/hr unless otherwise noted) ) Clock Scenario Time Time' ARM 1 Zone 5 , 0700 0 8 10 1 0800 1:00 8 10 0815 1:15 7 10 l 0830 1:30 7 10 0845 1:45 7 10 0900 2:00 7 10 0915 2:15 7 10 6 8' 0930 2:30 6 8 0945 2:45 8 1000 3:00 6 6 8 1015 3:15 8 1030 3:30 6 3:45- 6 8 1045 8 1100 4:00 6 .p
.4:15 6 8 1115 8 3 L30 4:30 6 ;
1145 4:45 3000 4000 1200 5:00 6000 6500 1215 5:15 9000 9500 1230 5:40 (OSH)>1E4 . 16000 , 1245 5:45 (OSH) 19000 1300 6:00 (OSH) 22000
- 1315 6:15 (OSH) 22000 1330 6:30 (OSH) 20000 1345 6:45 (OSH) 20000 1400 7:00' (OSH) 19000 Notes:' Zone readings are average dose rates throughout zone.
-(OSH).OFF SCALE:HIGH 1
.. -. 4 ~
i_ _ . . _
...m.. - - - - . .1 - . - . ~ . _ - .- _ _ .
_ ..-._.~ .. . ___ __m. . . . _ _ _ _ _ . . _ . . . _ _ . _ _ . . _ _ _ _ _ _ _ . . _ _ _ _ . . _ _.
, :7 'g. .. ,
.v.,
-1 Page 9.311b FIGURE 9.3411 I '.
; %s ' ,
h t 4 5 w f 5 E g 1 h W I@ ' I W-
~
(i' .: 4
-a f-(
B~
- (.
O Vb
~3 IE O M '
l H 5 . ,- MONITORS. 1 REACTOR BLALDNG SUPPRESSION CHAMBER EX1. CATWALK t
- p. .
b - a. I
;:) . fg?..
.OY VERMONT YANKEE NUCLEAR PC'JER STATION 1 1
SMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1 1990 ;
-j 4
)
- l
.j l
i a l
>k l
l 9,4 PLRTT CHEMISTRY DATA *
--{
,(. : !
-i i
i r i
-- l l
i
.) '
.N e
i 4 .
. .6 -
, 'l 1
['f
. ,- 7, ',3
; u; .
VERMONT YANKEE NUC1. EAR POWER STATION , 1 EMERCENCY RESPONSE PREPAREDNESS EXERCISE 1990- ! i , 9.4 Pl. ANT CllEMISTRY DATA SECTION g 9,4,1 Reactor Coolant Activity Data,,,,,,,,,,,,,,,,,,,,,,,, 9.4.1 1 9.4.2 Primary Containment Air Activity Data................, 9.4.2 1 i 9.4,3 Reactor Building Air Activity Data ,,,,,,,,,,,,,,,,,,, 9.4.3 1 e t
~'
i
'i i
P 7 w
~1
-i
.(
.' y ^*'1
. f.. ,
VERMONT YANKEE NUCLEAR POWER STATION EMERGSNCY RESPONSE PREPAREDNESS EXERCISE 1990 " l 9.4.1 REACTOR COOIANT ACTIVITY DATA
.i
)
k i
'M 4
i l
.[. 'l l
~
j x ___2 __m . _ _ . _ _ _ _ _ _ _ _ _ _ _ __.
k ', t k Rev. O Page 9.4.1 1 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1h 9.4.1 REACTOR C001 ANT ACTIVITY DATA A. Reactor Geolant Activity Concentrations (uCi/al) Time Isotope Prior to 1130 1130 1145 1145 1200 I.131 2.5E.03 1.1E+02 1.0E+02 I.132 2.8E.03 1.1E+02 1.0E+02 1 133 5.2E.03 2.0E+02 2.0E+02 I.134 4.1E.03 9.3E+01 7.5EA01 I.135 4.5E.03 1.8E+02 1.7E+02 Total Iodine 1.9E 02- 6.9E+02 6.5E+02 , I.131' Dose 4.5E.03 1.8E+02 1.8E+02 s Equivalent Kr.83m 1.2E.03 6.1E.01 1.3E+00
. Kr.85m 2.5E.02 4.3E.01 4.1E.01 i Kr.85 4.8E.03 2.4E.02 2.4E.02 Kr.87 2.9E.03 5.0E.01 4.3E.01 Kr.88 1.0E.03 9.9E.01- 9.1E.01
. Xe.133 5.3E.03 4.4E+00 4.6E+00 Xe.135m 5.8E 03 8.2E+00 1.7E+01 Xe 135 2.2E-03 2.6E+00- 5.5E+00 1 4
Total Noble 4.8E.02 1.8E+01 3. 0E4 01 ' Gas. 1 Note: Reactor coolant sample dose rates are provided in Section 9.5.1. l l 1 I 1 1 1 1 y ' l
1 . i .. i
.C n'T -3 .; ' i W Rev. O r Page 9.4.1 2 l4 VERMt NT Y.\NKEE NUCLEAR POWER STATION ;
EMERGEhiY RLiPONSE PREPAREDNESS TXERCISE 1990 9.4.1 REACTOR COOLANT ACTIVITY DATA
............................. 1 A. Reactor Coolant Activity Concentrations (uCi/al) l Time Isotope 1200 1215 1215 1230 1230 1245 I.131 1.0E+02 1.0E+02 9.9E+01 1 132 9.2E+01 8.4E+01 7.6E+01 !
I.133 1.9E+02 1.9E+02 1.8E+02 1 134 6.1E+01 4.9E+01 4.0E+01 I.135 1.6E+02 1.5E+02 1.5E+02
.( T6tal Iodine 6.1E+02 5.8E+02 5.5E+02 1 131 Dose 1.7E+02 .1.7E+02 1.6E+02 Equivalent Kr.83m1 1.8E+00 2.2E+00 -2.5E+00 i Kr.85u 3.8E.01 -3.6E.01 3.4E.01 )
Kr 85 2.3E.02 2.3E.02 2.2E.02 -; Kr.87 ~3.7E.01 3.2E.01- 2.7E.01 a Kr-88 8.4E.01 7.8E.01 7.2E.01 -)
-Xe.133 4.8E+00 5.0E+00 5.1E+00 i Xe-135m 2.1E+01- 2.2E+01 2.2E+01 i Xe.135 8.3E+00 1.1E+01 1.3E+01 !
Total Noble 3.7E+01 4.2E+01 4.5E+01 1 Cas i i i 1 l
, .............. j t
Note: Reactor coolant sample dose rates are provided in Section 9.5.1. j r f f
,1
, 1 L 1
.u_ i
p., . \.
= t- )
4 Rev. O i Page 9.4.1 3 ;
. I VERMONT YANKEE NUC1. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE !
1990 1 9.4.1- REACTOR C001 ANT ACTIVITY DATA , A. Reactor Coolant Activity Concentrations (uCi/ml) i Time Isotope 1245 1300 1300 1315 1315 1330 I.131 9.7E+01 9.5E+01 9.4E+01 '! I.132 7.0E+01 6.3E+01 5.8E+01 1 133 1.8E+02 1.8E+02 1.7E+02 i 1 134 3.2E+01 2.6E+01 2.1E+01 1 1 135 1.4E+02 1.4E+02 1.3E+02 i
! h: Total Iodine 5.2E+02 5.0E+02 4.7E+02 i
I-131 Dose 1.6E+02 1.6E+02 1.5E+02 Equivalent I Kr-83m 2.8E+00 2.9E+00' .3.0E+00 Kr 85m 3.3E.01 3.1E.01 2.9E.01 Kr.85 2.2E.02 2.2E.02 2.1E.02 Kr.87 2.3E.01 2.0E.01 '1.7E.01 Kr.88 6.7E.01 6.2E.01 5.7E.01. Xe-133 5.3E+00 5.4E+00 5.5E+00 Xe 135m 2.2E+01 2.1E+01 2.1E+01 Xe.135 1.6E+01 1.8E+01 1.9E+01 Total Noble 4.7E+01 4.8E+01 5.0E+01 Oas
- 4
.; .............. 9 q.
-i
.Hote: Reactor coolant sample dose rates are provided in Section 9.5.1.
s
'.y-t
- i
i ?.' R3v. 0 ~
-Page 9.4.1 4 l VERMONT YANKEE NUCLEAR POWER STATION
-{i. EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.4.1 REACTOR COOLANT ACTIVITY DATA
- A. Reactor Coolant Activity Concentrations (uci/ml) !
Time l 3 1 Isotope 1330 1345 1345 1400 ! i 1 131 9.2E+01 9.0E+01 ) 1 132 5.3E+01 4.8E+01 ' I.133 1.7E+02 1.6E+02 i 1 134 1.7E+01 1.4E+01 I.135 1.2E+02 1.2E+02 4
~ Total: Iodine. 4.5E+02 4.3E+02 1 131 Dose 1.5E+02 1.5E+02 l LEquivalent i~
I 4- - Kr.83m 3.1E+00: 3.1E+00 Kr.85m' 2.8E 01 2.6E.01 Kr.85 2.1E.02 2.1E.02-Kr.87 1.5E.01 1.3E.01-Kr 88 5.3E.01 4.9E.01 Xe.133 5.7E+00 5.8E+00 he.135m 2.0E+01 1.9E+01 , Xe.135 2.1E+01 2.3E+01 Total Noble 5.1E+01 5.2E+01 Cas , i s Note: Reactor coolant. sample dose rates are provided in Section 9.5.1. ! Post 1400 values continue to decline steadily with time. I
;p } ? '
t l l l
+
O Y s 4 S i s. VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE I 1990 i i 1 r i 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA l
.i I
t i ( ; ) 4 e . a
-1 I.
i
-i ,
- j
,f 7
+
ti I
- I;
. 6 .
I i
~ , ,-r, .
p
-N. '
Rev.-0 Page 9.4.2 1~ i VERMONT YANKEE NUCLEAR POWER STATION . EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1990 l
-9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uCi/cc)
Time Isotope Prior to 1130 1130 1145 1145 1200 I.131
- 3.1E 01 3.0E 01 1 132
- 3.2E 01 2.9E.01 1 133
- 6.0E.01 5.8E 01 1 134
- 2.7E 01 2.2E.01 I.135
- 5.1E.01 4.9E.01 ,
k- Total Iodine
- 2.0E+00 1.9E+00
.i
.I.131 Dose
- 5.3E.01 5.2E.01 -1 Equivalent; Kr.83m
- 1.3E+01 1.2E+01
-Kr.85m
- 2.5E+01 2.4E+01 ,
Kr.85
- 1.4E+00 1.4E+00 Kr.87
- 2.9E+01 2.5E+01 Kr.88 .* -5.BE+01 5.3E+01 :
Xe 133
- 2.5E+02 2.5E+02
-Xe.135m
- 3.4E+01. 3.2E+01 -
Xe-135
- 6.9E+01 7 .1E+0?
Total-Noble *- 4.8E+02 4.7E+02 Cas-
- Below MDA at specified time.
. Note: Primary containment sample dosa rate provided in Section 9.5.2.
I m.
~
k , -
\;; . .,
I i i
. 1
- l. b '
'Rev. O Page 9.4.2 2 j
VERMONT YANKEE NUCl. EAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1990 l 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA 1
..................................... l A. Primary Containment Air Activity Concentrations (uCi/cc)
Time Isotope 1200 1215 1215 1230 1230 1245 I.131 3.0E 01 2.9E.01 2.9E.01 I.132 2.7E-01 2.4E 01 2.2E.01 I.133 5.7E 01 5.6E.01 5.4E.01 1 134 1.8E.01' 1.4E 01 1.2E-01 1 135 4'7E.01
. 4.5E.01 4.3E 01 Total Iodine 1.8E+00 1.7E+00 1.6E+00
{ I-I31 Dose 5.1E.01 4.9E.01 4.8E.01 Equivalent Kr.83m 1.2E+01 1.1E+01- 1.1E+01 Kr.85m- 2.2E+01 2.1E+01- 2.0E+01 Kr.85 1.4E+00 1.3E+00 1.3E+00 Kr.87 2.2E+01 1.9E+01 1.6E+01 ' Kr.88 4.9E+01 4.6E+01 4.2E+01 Xe.133 2.4E+02 2.4E+02 2.4E+02 , Xe.135m 3.1E+01 3.0E+01 2.9E+01- ' Xe.135 7.2E+01 7.3E+01 7.4E+01 Total Noble 4.5E+02 4.4E+02 4.3E+02' Gas-
. i -.
, Note: Primary containment sample dose rate provided in Section 9.5.2. 1 4
' js A
, .e _
l
, I e.%
l u., 1 - ;f;" Rev. O Page 9.4.2 3 VERMONT YANKEE NUCLEAR POWER STATION i EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1 1990 l l 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA
..................................... t 1
A. Primary Containmant Air Activity Concentra ions (uCi/cc) j Time Isotope 1245 1300 1300 1315 1315 1330 1 131 2.8E 01 2.8E 01 2.7E.01 1 132 2.0E.01 1.9E.01 1.7E.01 I.133 5.3E 01 5.2E.01 5.0E 01 1 134 9.4E.02 7.6E.02 6.1E-02 1 135 4.1E.01 4. 0E.01 3.8E 01
- (-. Total Iodine 1.5E+00 1.5E+00 1.4E+00 l1 I 131 Dose 4.7E.01 4.6E.01 4.5E.01 -
Equivalent Kr.83m 1.0E+01 9.9E+00 9.4E+00 Kr.85m 1.9E+01 1.8E+01 1.7E+01 Kr.85 1.3E+00 1.3E+00 1.2E+00
.Kr 87 1.4E+01 1.2E+01 1.0E+01 Kr 88 '3.9E+01 3.6E+01 3.4E+01 ,
Xe.133 2.3E+02 2.3E+02 2.2E+02 L Xe.135m 2.8E+01 2.8E+01~ 2.7E+01 L E
'Xe.135 , 7.5E+01 7.6E+01 7.6E+01 Total Noble 4.2E+02 4.1E+02 3.9E+C:
. Cas t i
l: l: ,: .a l: , 1, Note: Primary containment sample dose rate provided in Section 9.5.2. l 4 I C
- j >
l l i R;v. O Page 9.4.2 4 cx
.' , VERMONT YANKEE NUCLEAR POWER STATION , ; t EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1990 .-
l 9.4.2 PRIMARY CONTAINMENT AIR ACTIVITY DATA A. Primary Containment Air Activity Concentrations (uCi/cc) Time Isotope 1330 1345 1345 1400 ' 1 131 2.7E.01 2.7E.01 I.132 1.5E 01 . 1.4E.01 I.133 4.9E.01 4.8E.01 1 134 4.9E 02 4.0E-02 : 1-135 3.6E.01 3.5E.01 Total Iodine 1.3E+00 1.3E+00 1 131 Dose- 4.4E.01 4.3E.01 . Equivalent i. Kr 83m 8.9E+00- 8.5E+00
'Kr.85m -1.6E+01 1.5E+01-Kr.85 1.2E+00 1.2E+00 Kr.87 8.6E+00 7.4E+00 >
Kr 88 3.1E+01 2.9E+01 Xe.133 2.2E+02 2.2E+02 Xe 135m- 2.6E+01 2.6E+01 Xe.135 7.*E+01 7.7E+01 Total Noble 3.9E+02 3.8E+02 Cas Note: Primary containment swiple dose rate ,provided in Section 9.5.2.
' Post 1400 values continue to decline steadily with time.
v
O .
.i:
e 1 i y T.
- . e i V4*MONT YANKEE NUCLEAR POWER STATION EMERCENCY RESPONSE PREPAREDNESS EXERCISE >
t-L. , 1990 ( -- ~r 1 l L I l 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA l.-: ! i S l l l l 1 1 1-l l l l l l
.I i
,l; f 1' S
l
- 1 I
I 6 .j Rov. 0 Page 9.4.3 1 > VERMONT YANKEE NUCLEAR POWER STATION
- <" EMERCENCY RESPONSE PREPAREDNESS EXERCISE ' (7 1990 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA. '
A.- Reactor Building Air Activity Concentrations (uci/ce). Elevations 252' and 280' . See Notes Below* Time Isotope Prior to 1130 1130 1145 1145 1200 I 131 ** 1.6E.04 4.6E 04 I.132 **- 1.6E.04 4.5E.04-I.133 ** 3.0E.04 8.9E.04 I.134 ** 1.4E.04 3.4E.04 I-135 **- 2.6E 04 7.5E.04 i Total Iodine ** 1.0E.03 2.9E.03 - I.131: Dose ** 2.7E.04 7.9E.04 ; Equivalent Kr.83m ** 6.4E.03 1.8E.02 Kr.85m ** 1.3E.02 3.6E.02
- (. Kr.85 ** 7.1E 04 2.1E.03 Kr.87 ** 1.5E.02 3.8E.02
- Kr.88 ** 2.9E.02 8.1E.02 Xe.133 ** 1.3E.01 3.4E.01 Xe.135m ** 1.5E.02 3.1E.02 Xe.135 ** 3.5E.02 1.0E.01 Xe.133m ** 3.7E.03 1.1E 02 Total Noble **- 2.5E.01 6.6E.01 Gas
- Notes:
- 1. . Reactor Building Elevations 303' and 318' . divide concentrations by a facto: of 2.
- 2. Reactor Building Elevation 345' . divide concentrations by a factor.of 5.
- 3. Reactor Building air sample dose rates are provided in Section 9.5.3.
** Activity is below the MDA of the plant gamma ray spectrometer at this time.
- ~
n; R:v. 0 ,. Page 9.4.3 2 I [d VERMONT YANKEE NUC1. EAR POWER STATION . I- O, EMERGENCY RESPONSE PREPAREDNESS EXERCISE l 1990 t 9.4.3 REACTOR BUILDING AIR ACTIVITY DATA A. Reactor Building Air Activity Concentracions (uCi/ce). Elevations 252' and 280' . See Notes Below* Time Isotope 1200 1215 1215 1230 1230 1245 1245 1300 I.131 7.6E.04 1.0E.03 1.3E 03 1.6E 03 I.132 6.8E.04 8.7E.04 1.0E.03 1.1E.03 s I.133 1.4E.03 2.0E.03 2.5E.03 2.9E.03 I-134 4.5E.04 5.1E.04 5.3E.04 5.2E.04 I.135 1.2E.03 1.6E.03 2.0E.03 2.3E.03 Total Iodine 4.5E.03 6.0E.03 7.3E.03 8.4E.03 l I.131 Dose 1.3E.03 1.7E.03 2.2E 03 2.6E.03 1 Equivalent . Kr.83m 2.8E.02 '3.6E.02 4.3E.02 4.8E.02
-(- Kr.85m Kr.85 5.7E.02 7.5E.02-4.7E.03 9.1E.02
'6.0E.03 1.1E 01 7.2E.03
.3.4E.03 L
I Kr-87 5.5E.02 6.5E.02 7.2E.02 7.5E 02
- Kr.88 1.3E4 01 1.6E.01 1.9E.01 2.2E.01 1 Xe.133 6.1E.01 8.4E.01 1.1E+00 1.3E+00
- t. Xe.135m 3.9E.02 4.2E.02 4.2E.02 4.2E.02 Xe.135 1.7E.01 2.4E.01 3.0E-01 3.7E.01 Xe.133m 1.8E.02 2.5E.02 3.1E.02 3.7E 02
. Total Noble 1.1E+00 1.5E+00 1.9E+00 2.2E+00 j Gas l
- Notes:
I
- 1. ' Reactor Building Elevation 303' and 318' . divide concentrations l
by a factor of 2. l 2. Reactor Building Elevation 345' . divide concentrations by a 1: factor of 5.
- 3. Reactor Building air sample dose rates provided in Section 9.5.3.
I I '. l l f; 12.
4 i. I d;- h l /W-'
'1.'.
A Am Rev. O Page 9.4.3 3 VERMONT YANKEE NUCII.AR POWER STATION .. EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.4.3 REACTOR BUII.DINC AIR ACTIVITY DATA A. Reactor Building Air Activity Concentrations (uCi/cc). Elevation 252' and 280' See Notes Below* Time Isotope 1300 1315 1315 1330 1330 1345 1345 1400 ;
....... ......... ......... ......... .........- i 1-131 1.7E.03 1.7E.03 1.6E.03 1.5E.03 I.132 1.2E.03 1.1E.03 8.4E 04 7.6E.04 1 133 3.2E.03 3.1E.03 2.8E.03 2.8E.03 1 134 5.1E 04 4.6E.04 2.4E.04 1.9E.04
,e I.135 2.4E.03 2.4E.03 2.1E.03 2.0E 03
.-{ ....... ....... ....... .......
Total Iodine 9.0E.03 8.7E.03 7.6E.03 7.2E.03 I.131 Dose 2.8E.03 2.8E.03 2.6E.03 2.5E.03 Equivalent ,. Kr 83m 5.1E.02 4,8E.02- 3.4E.02 3.0E.03 Kr.85m 1.1E.01 1.1E.01- 9.1E.02 8.6E.02 L Kr 85 7.7E.03 7.7E.03 7.2E 03 7.0E.03 l Kr.87 7.6E.02 7.0E.02 4.4E 02 3.8E.02 Kr.88 2.3E.01 2.2E.01 1.7E.01 1.6E 01 Xe.133 1.4E+00- 1.4E+00 1.3E+00 1.2E+00-Xe.135m 4.2E.02 3.0E.02 3.9E.03 2.1E.03 i Xe.135 4.0E.01 3.9E.01 3.5E.01 3.3E 01 L Xe 133m- 4.0E.02 4.0E.02. 3.7E-03 3.6E 02 [ ....... ....... ....... ....... Total Noble 2.4E+00 2,3E+00 2.0E+00 1.9E+00 p Cas l p ..............
- Notes:
1 ~. Reactor Building Elevation 303' anc~ 318' . divide concentrations by a factor of 2.
- 2. Reactor Building Elevation 345' - divide concentrations by a
, factor of 5- .
( 3. Reactor Building air sample dose rates provided in Section 9.5.3.
- 4. Post 1400 values continue to decline ateadily with time.
t f . g [> s '_ $ [h e i e w ro. j
'" i v.l. .)
l
. i VERMONT YANKEE NUCLEAR POWER STATION ,
i EMERGENCY RESPONSE PREPAREDNESS EXERCISE I
-1990 3..
' t 9 i f i s 9.5 MDIOLOGI AL SAMPLE DOSE RATES
.l
.i l
-r
-i t s
- f '- ..
YA: ,i
.3 I
i 2
- i
_'____________________z____.___________.____.__1___________.___
I tg .
- i *
\ t. 'l H -
ll I NI5/ ~ Rev. O Page 9.5.1 1 VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990
- 9.5.1 Reactor. coolant Sample Dose Rates A.. Gas Samples Unshielded (mR/hr per cc)* Shielded (1 in. lead in mR/hr per cc)*
l 'I L Time Contact 1 ft Contact l'ft Prior to 1130 1.4E.02 9.6E.05 1.7E.04 1.2E.06 , 1130 1145 '5.2E+00 3.6E.02 6.4E.02 4.5E.04 { L . 1145 1200 8.7E+00 6.0E.02 1.1E.01 7.5E.04 kD , 1200 1215- 1.1E+01 7.4E.02 1.3E.01 9.3E.04 1215 1230' 1.2E+01 8.4E.02 1.5E.01 1.1E.03 1230 1245 1.3E+01 9.0E.02 1.6E.01 1.1E.03 l 1245 1300 1.4E+01 9.4E.02 1.7E.01 1.2E-03 1300 1315 1.4E+01- 9.6E.02 l'.7E.01 1.2E.03
' 1315 1330- 1.5E+01 1.0E.01 1.8E.01 1.3E.03 1330 1345 1.5E+01 1.0E.01 1.8E.01 1.3E.03 1345 1400 .1.5E+01 1.0E.01 1.8E.01 1.3E 03 Post 1400 values continue to decline steadily with time.
r
-
- Notes: Value must be multiplied by the sample volume in cubic centimeters for gas samples to obtain the sample dose rate in mR/hr.
~
( 4'- s
., . h c.
O 't 4 Rev. O Page 9.5.1 2
- j. f, '
1
-VERMONY YANKEE NUCLEAR POWER STATION I EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.5.1 Reactor Coolant Sample Dose Rates B. Liquid (Iodine)
Unshielded (mR/hr per ec)* Shielded (1 in lead in mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 1130 1.5E.02 1.0E 04 1.9E.04 1.3E.06 1130 1145 5.4E+02 3.7E+00 6.7E+00 4.6E.02 1145 1200 5.1E+02 3.5E+00 6.3E+00 4.3E.02 1200 1215 4 '. 8 E+02 3.3E+00 5.9E+00 4.0E.02 1215 1230 4.5E+02 3.1E+00 5.7E+00 3.8E.02 1230-1245 4.3E+02 3.0E+00 5.4E+00 3.6E.02 1245 1300 4.1E+02 2.8E+00 5.1E+00 3.4E.02
-1300 1315 3.9E+02 - 2.7E+00 4.9E+00 3.3E.02 1315 1330 3.7E+02 2.5E+00 4.6E+00 3.1E.02 1330 1345 3.5E+02 ' 2.4E+00 4.4E+00 3.0E.02 1345 1400 3.4E+02 2.3E+00 4.2E+00 2.8E.02
-Post 1400 Values continue to decline steadily with time.
- Notes: Values must be multiplied by the sample volume in milliliters for liquid samples to obtain the sample dose rate in mR/hr.
C . ____.._-_A__.-.__
1 4 .4 , R:v. O. q' l Page 9.5.2 1' i VERMONY YANKEE NUC1. EAR-POWER STATION t} T EMERCENCY RESPONSE PREPt. REDNESS EXERCISE op - kh,h. 7 1990 . 9.5.2 Primary containment Sample Dose Rates A. Cas Samples ' Unshielded (mR/hr per cc)* Shielded (1 in lead in mR/hr per cc)* Time Contact 1 ft Contact 1 ft Prior to 1130 As Road As Read As Read As Road l 1130 1145 1.4E+02 9.6E.01 1.7E+00 1.2E 02 1145 1200 1.4E+02 9.4E.01 1.7E+00 1.2E.02 1200 1215 1.3E+02 9.0E.01 1.6E+00 1.1E.02 .- 1 1215 1230 1.3E+02 E.8E 01 1.6E+00 1.1E.02 y 1230 1245 1.2E+02 8.6E 01 1.5E+00 1.1E.02 l l 1245 1300 1.2E+02 . 8.4E.01 1.5E+00 1.1E.02 1300 1315 8.2E.01 1.5E+00 1.0E.02 (. , 1.2E+02 131541330 1.1E+02 7.8E 01 1.4E+00 9.8E.03 1330 1345- 1.1E+02 7.8E.01 1.4E+00 9.8E-03 1345 1400 '1.1E+02 7.6E.01 1.4E+00 9.5E.03 Post 1400 values continue to decline steadily with time. l l H
*Noteh$ Values must be multiplied by the sample volume in cubic centimeters I for gas samples to obtain the sample dose rate in mR/hr.
'1
- l l
l 1 l l , l' . \' I I l (= l
~ * ^ ^ '^ ~~ . -a n . - ,.. . .. A , 6 : ,-. c- . ,
t
-Rev. 0-Page 9.5.3 1'
'VERMONY YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 l 9.5.3 Reactor Building Air Sample Dose Rates (Iodine Cartridge Only)
Elevation 252' and 280' . See Notes Below > t Unshielded (mR/hr per cc)*- Shielded (1 in. lead in mR/hr per cc)*
................~.......... ......................................
Time Contact 1 ft contact 1 ft Prior to 1130 As Read As Read As Road As Read 1130 1145 7.8E.04 5.4E 06 9.7E.06 6.8E-08 1145 1200 2.3E.03 1.6E.05 2.8E.05 2.0E.07 i 1200 1215 3.5E.03 2.4E.05 4.4E.05 3.0E.07 - j 1215 1230 4.7E.03 3.2E.05 5.8E.05 4.1E.07 l s 1230 1245 5.7E.03 3.9E.05 7.1E.05 4.9E.07 l
, 1245 1300 6.5E 03 4.5E.05 8.2E.05 5.7E.07 1300 1315 '7.0E.03 4.8E.05 8.7E.05 6.1E 07 1315-1330 .6.8E.03 4.7E 05 -8,5E.05 5.9E.07 1330 1345 5.9E.03 4.1E.05 7.4E 05 5.1E.07 1345 1400 5.6E.03 3.9E.05 7.0E.05 4.9E.07 Post 1400 values continue to decline steadily with time.
- Notes: 1. Values must be multiplied by the sample-volume . in cubic centimeters to obtain the sample dose rate in mR/hr.
- 2. Reactor Building. Elevations 303' and 318' . divide dose rates by a factor of 2.
- 3. Reactor Buildin5 Elevation 345' . divide dose rates by a factor of 5.
)
\
1 . _ , , .. , .. . -,. m. . . _ . 44. . _-. . - . - . _ . _ .t s , Roy. O Page 9.5.4 1 f([$'
- b' ',O VERMONY YANKEE NUCLEAR POWER STATION EMER0ENCY RESPONSE PREPAREDNESS EXERCISE 1990 -1 9.5,4 Plant Vent Stack Sample Dose. Rates A. Gas (Crab Sample)
Unshielded (mR/hr per ec)* Shielded (1 in. lead in mR/hr per.cc)* Time Contact 1 ft Contact I ft
.... ....... .... ....... .... l Prior to 1 1135 As Read As Read As Read As Read- l 1135 1145 2.0E.03 1.4E.05 2.4E.05 1.7E.07 l 1145 1200 5.7E.03 4.0E.05 7.0E.05 5.0E.07-1200 1215 9.1E.03 6.4E.05 1.1E 04 8.1E.07 l
8.6E 05 1.5E.04 1.1E.06-1215 1230 1.2E.02 1230 1245- 1.5E.02 1.0E.04 1.8E.04 1,3E.06 .l (- l 1245 1300 1.8E.02 1.2E 04 2.2E.04 1.6E.06 .) 1 1300 1315 1.8E.02 1.3E 04 '2.3E.04 1.6E-06 l 1 1315 1330~ 1.SE.02 1.3E.04 2.3E.04 1.6E 06 -l I 1330 1345 1.6E 02 1.1E.04 2.0E.04 1.4E.06 . 1345 1400 1.5E.02 1.0E.04 1.8E.04 1.3E.06 l Post 1400 values continue to decline steadily with time, , 1 l l 1 Notes: *Value must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rates in mR/hr.
- ** Plant vent stack sample dose rates remain constant from 0700 1130 l given the same sample volume.
e r s
]
1 . l- - l
- i; 1 r
l
u : n. , . , m; , ..~ r . . ~ . . :.. : L ' ^ , ... . . . - . .. . a ,
'1 .
b .
. R:v. 0 .
Page 9.5.4 2 VERMONY YANKEE NUCl. EAR POW.R STATION- [> EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 j M 9.5.4 Plant Vent Stack Sample Dose Rates L .................................. 1 B. Air Sample-(Iodine Cartridge) Unshielded (mR/hr per cc)* Shielded (1 in lead in mR/hr per ec)* Time Contact 1 ft contact- 1 ft l Prior to I 1135' As Read As Read As Read As Read l i 1135 1145 1.2E.06 8.0E.09 1.4E.08 1.0E.10 I i b 1145 1200 3.2E.06 2.3E.08 4.0E.08 2.8E.10 1200 1215 5.0E.06 3.5E.08 6.2E.08 A.4E.10 1 l- l t-1215 1230 6.6E.06 4.6E.08 8.2E.08 5.0E.10.
/ 1230 1245 7.7E 06 5.4E 08 9.6E.08 6.7E.10
.i
1 1245 1300 9.2E.06 6.4E 08 1.2E.07 8.1E-10 1300 1315 1.0E.05 7.0E.08 1.2E 07 8.8E.10 I. 1315 1530 1.0E.05 7.0E.08 1.2E.07 8.8E.10 i 1330 1345 8.4E.06 5.9E.08 1.1E 07 7.4E.10 p-1345 1400 7.7E-06. 5.4E.08 9.6E.08 6.7E.10-l l= Post 1400 values continue.to decline steadily with time. (' Notes:. *Value must be multiplied by the sample volume in cubic centimeters to obtain the sample dose rates in mR/hr. E 1, . l :
** Plant vent stack sample dose rates remain constant from 0700 1130 l ,
given the same sample volume. 9
. b i
. . . , . ~ +. ~ y,. . .
. .,..~. . . a:.~.. .. . - . . . . - . , - . . .
_[ ,' .
.~ Rev. 0 Page 9.5.4 3
'{' ,
VERMONY YANKEE NUCLEAR POWER STATION l EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.5.4 Plant Vent Stack Sample Dose Rates
.C. General Area Exposure Rates at Stack (mR/hr)
'l Time At Stack Door Inside l Prior to 1135 As read
- As Read
- 1135 1145 10 10 .
l 1145 1200 20 20 i 1 1 1200 1215 35 35 ! l 1215 1230 45 45 1230 1245 50 50 b- 1245 1300 60 60 1300 1315 60 60 1315 1330 55 55 1330 1345 50 50 1345 1400' 45 45 Post 1400 Dose listes Continue to Decline d ...........................................................................
- Background as read on survey meter,
.ni .s 't i
I .
e , 1 W
' t VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 l
-1 1
l l l 9.6 PIANT VENT STACK RELEASE DATA l l l l l 1
..(.,.
l l
-1 l
l HQIE: If the stack filter paper-is analyzed, it will be assumed that the-gamma isotopic results will show all radionuclides below the MDA-of the multi-channel analyzer. An RM 14/HP 210 survey of the filter will show no. counts above background. l l l
- i t; -
l l i. I t b /.1 _ _ _ _ _ _ _ , _ _ _ _ _ _ - _ _ _ _ . - _ _ _ _ _ -_ _ _ _ _ _ _ _ _ _ _ _ - 4
.. . . .a . . .
~
.s . .c , w -- 4
. . n , _ .
F
. Rev. 0 Page 9.6 1 i
(I' VERMONT YANKEE NUCLEAR POWER STATION -i EMERGENCY RESPONSE PREPAREDNESS EXERCISE' l
. 1990 1 1
9.f PLANT VENT STACK RELEASE DATA 1 A. Plant Vent Stack Activity Release Concentrations (uci/cc)
........................................................ 1 Time Isotope Prior to 1135 1135 1145 1145 1200 l V
I.131 3.3E.13 2.3E.07 6.7E.07 1 132 4.8E.13 2.4E.07 6.5E.07-I.133 7.5E.13 4.4E.07 1.3E.06 'l I.134 6.6E.13 2.0E 07 4.8E.07 i I.135 6.3E.13 3.8E.07 1.1E.06 Total Iodine -2.9E.12 1.5E.06 4.2E.06 l I.131 Dose 6.1E.13 3.9E.07 1.1E.06 Equivalent Kr.83m ** 1.9E.04 5.2E.04 Kr.85m ** 3.7E.04 1.0E 03 Kr.85~ ** 2.1E.05 6.1E.05 Kr 87 ** 4.3E.04 1.1E.03 Kr.88 ** 8.5E.04 2.3E.03 Xe.133 ** 3.7E-03 1.1E-02 Xe-135m ** 4.2E.04 9.1E.04 l Xe.135 ** 1.0E.03 3.0E.03 j l Total Noble ** 6.9E.03 2.0E 02 l Cas l l
* . Activity concentrations (in uCi/cc) may be converted to activity. ;
release rates (uci/sec) by multiplying by the assumed stack flow l rate of 4.9E7 cc/sec. l L -
** Noble gas release rates are minimal at this time and below KDA of I n the multi-channel analyzer.
l l
\
Note: Plant vent stack sample dose rates provided in Section 9.5.4. l l
hg , IL k, -- .- Rev. O Page 9.6 2 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.6 PLANT VENT STACK RELEASE DATA A. Plant Vent Stack Activity Release Concentrations (uci/ce) Time Isotope 1200 1215 1215 1230 1230 1245 1245 1300 I.131 1.1E.06 1.5E.06 1.9E.06 2.3E.06 1 132 9.8E 07 1.3E.06 1.5E.06 1.6E-06 I.133 2.1E.06 2.8E.06 3.5E.06 4.2E.06. 1 134. 6.5E-07 7.3E.07 7.6E 07 7.5E.07-I.135 1.7E.06 2.3E.06 2.8E.06 3.3E.06 Total Iodine 6.5E-06 8.6E 06 1.0E 05 1.2E.05 1 131 Dose 1.8E.06 2.5E.06 3.2E 06 3.8E.06 Equivalent Kr.83m 8.0E.04 1.0E 03 1.2E.03 1.4E 03 Kr.85m 1.6E.03 2.2E.03 2.6E.03 3.0E.03 Kr.85 9.9E 05 1.4E.04 1.7E.04 2.1E.04 Kr.87 1.6E.03 1.9E.03 2.1E.03 2.2E.03 Kr.88 3.6E.03 4.7E.03 5.5E 03 6.3E 03 Xe.133 1.8E.02 2.5E.02 3.1E.02 3.7E.02 Xe.135m 1.1E.03 1.2E.03 1.2E.03 1.2E 03 Xe.135 4.9E.03 6.8E.03 8.7E.03 1.1E.02 1 Total Noble 3.2E.02 4.3E 02 5.2E.02 6.2E.02 Cas
- Activity concentrations (in uCi/cc may be converted to activity release rates (uci/sec) by multiplying by the assumed stack flow rate of 4.9E7 cc/sec.
** Noble gas release rates are minimal at this time and below MDA of the multi. channel analyzer.
Note: Plant vent stack sample dose rates provided in Section 9.5.4. 4
Rev. O Page 9.6 3 s VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.6 PLANT VENT STACK REl. EASE DATA A. Plant Vent Stack Activity Release Concentrations (uCi/cc) Time Isotope 1300 1315 1315 1330 1330 1345 1545 1400 1-131 2.4E-06 2.4E-06 2.3E 06 2.2E.06 I-132 1.7E-06 1.6E-06 1.2E-06 1.1E 06 I 133 4 5E-06 4.5E-06 4.1E-06 4.0E-06 I-134 7.3E-07 6.6E-07 3.4E-07 2.7E-07 I-135 3.5E-06 3.4E 06 3.0E 06 2.9E 06 Total Iodine 1.3E 05 1.3E-05 1.1E 05 1.0E-05 I-131 Dose 4.0E-06 4.0E-06 3.7E 06 3.6E-06 Equivalent 8.7E-04 Kr-83m 1.5E 03 1.4E-03 9.7E.04 Kr 85m 3.2E-03 3.1E 03 2.6E-03 2.5E-03 Kr-85 2.2E 04 2.2E-04 2.1E-04 2.0E 04 Kr 87 2.2E.03 2.0E.03 1.3E.03 1.1E.03 Kr-88 6.6E 03 6.3E 03 4.9E.03 4.5E.03 Xe.133 4.0E.02 3.9E 02 3.7E-02 3.6E-02 Xe-135m 1.2E 03 8.8E-04 1.5E 04 1.1E 04 Xe-135 9.3E.03 1.1E-02 1.0E-02 7.0E-03 Total Noble 6.4E-02 6.4E.02 5.7E-02 5.2E.02 Gas Post 1400 values continue to decline steadily with time.
- Activity concentrations (in uCi/cc may be converted to activity release rates (uci/see) by multiplying by the assumed stack flow rate of 4.9E7 cc/sec.
** Noble gas release rates are minimal at this time and below HDA of the multi-channel analyzer.
Note: Plant vent stack sample dose rates provided in Section 9.5.4.
i t
-T 1_ -
I,
- l{ ;
8 7 VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 - i l 1 l 9.7 0FF-SITE MONITORING MAPS AND DATA l 1 I 4 Y
.g-o 2501e l
-- - - - _ _ - - - . _ _ _ - - - - _ . . - _ . - - _ _ . _ - - _ _ . - - - _ _ _ . . . - _ - - - - - - - - - - - - . _ - - w w
~
I Rev. 0 '
. 4/6/90 Page 9.7-1 +-
Q.[gr.. w, VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 9.7 0FF-SITE MONITORING MAPS AND DATA i Off-site plume centerline whole body dose rates and radiciodine concentrations have been estimated as a function of time and distance from the site using a variable trajectory dose assessment model. Geographical representations of the plume are provided in this paclass for each 15 minute average of meteorological conditions, starting at 1130. During the exercise, off-site monitoring team observers will use the information contained in this package to provide field monitoring teams with radiological data for various times and locations. During the exercise, the Survey Team Coordinator (s) will direct off-site monitoring teams to monitor locations relative to the meteorological conditions postulated for the exercise scenario. Use Figures 9.7-1 through 9.7-11 to provide survey results to the off-site monitoring teams. Figures 9.7-1 through 9.7-11 depict the plume conditions at various times throughout the axercise. These figures represent a plume width' which is equivalent to a-3-sigma value of the centerline conditions. Since the figures show a plume width relative to the centerline, gamma dose rates can be estimated using the color coded maps and off-centerline value provided. Radiological data for other locations within the plume can be calculated as a function of the centerline and outer edge values at a given segment / distance. Radiological data has been provided for each particular segment at centerline. Dose and count rates for locations between two segments can be estbnated as a function of the values at those segments. 2501e r w
- ~ - ' ^-~ --
.. ~, m . .-.- c .
..g. -
~
Rev.-0 4/6/90 Page 9.7-2
\;)3fl' - '
'i Prior to the exercise, training will be provided to the off-site monitoring team controller / observers on the use of this package. The fcilowing are specific instructions which off-site monitoring team-controller / observers should use during the exercise: 1 1
-l
- 1. As off-site monitoring teams are designated, check that Procedure I l
Number OP-3510 is followed by team members. This will include the J initial equipment check.
- 2. While enroute to the assigned monitoring location, or whf.le traversing the plume, use the attached figures and tables to issue appropriate radiological data.
- 3. Attcmpt to estimate the team's accrued exposure as a function of I l
their continual job assignment. Do not issue pocket dosimeter l results to team members, unless they actually simulate checking their { dosimeter reading. The pocket dosimeters in the kits have a range of-0-500 mR, which are subdivided into 20 mR intervals. Attempt to ; provide realistic values! 5 R dosimeters may be provided. Always check to ask them the range.
- 4. Ask the off-site monitoring teams what equipment they have available for their use. Ask them the scales associated with the equipment; log these answers to ensure that you do not provide them with data !
I that exceeds'the range of their equipment. If, at any point during
- the exercise, a situation occurs where the upper range of their equipment is exceeded, then issue them an "off-scale high" value.
o If the off-site monitoring team stops to take an air sample: 5.
- a. Report the appropriate whole body dose levels at that location.
-i 2501e
,(
. --l
- i Rsv. O E^ 4/6/90 p . Page 9.7-3 w :( (.;
- b. If an RM-14/HP-210 is left on'to track the plume while driving the meter count rate can be estimated using the following ,
relationships (1) 3,500 eps on the RM-14/HP-210 is equivalent to approximately 1.0 mR/hr. Therefore, 14 mR/hr will cause.the RM-14/HP-210 to read "off-scale high." - (2) The upper range of RM-14/HP-210 = 50,000 cpm.
- 6. Whenever a team takes a " ground level" survey, the results should be L the same as the waist-high survey.
- 7. The Verme,nt Yankee of f-site monitoring teams will substitute a - ,
L charcoal sample instead of a silver-zeolite sample for the purposes l' of this exercise. All data will be given f rom the tasks provided as - L though silver-zeolite samples were being utilized. (. l
- 8. Cer,tain field monitoring teams may take open window and closed window readings with their dose rate survey meters. If a team is located in the plume and air concentration is greater than zero (see maps),
assume the open window reading is three times the gamma (closed I window) line dose. rate reading given on the map. j l
- 9. Air sample assumptions used to calculate the count rates (net cpm) J for the silver zeolite cartridges with the RM-14 instrument. l l
l Foumulas
- 1
-1 Cone'I-131 in uci/cc = (net epm) (4.5 E-10 uCi-1/dpm-ec) ;
I (E)(V)(T) i 1 1 2501e e i I 1 l
.U l, , Rev.L0 4/6/90 Page 9.7-4
}ns q, t- where E = efficiency (0.025 for RM VY). -
V = flow rce.e in liters per minute (VY flow rate - 10 1pm). T = sample collection time in minutes (VY sample time - 10 minutes). therefore Conc I-131 in uCi/cc = (not epm) (1.8 E-10) or (Cone I-131 in uci/cc) (5.6 E+09) = net cpm
*** Remember this assumes a sample volume of 100 liters and a RM-14 efficiency of 0.025.***
( EDIE - THE PLUME PLOT FIGURES ARE GRAPHIC REPRESENTATIONS OF NINOSPHERIC DISPERSION. THE THREE-DIMENSIONAL PLUMES VARY IN TIME AND SPACE. A SIMILAR. VERSION OF THE FIGURES OVERLAYED ON A LARGER TIELD SURVEY MAP WILL BE USED TO ASSIST CONTROLLERS-IN INTERPRETATING DATA. 4 I e 2501e 4
h et c. 0 9last 0.7.1 6/a/90 D Sitt utsetetstat CIeDittmatssit mePI pang 0.7 3 ! CA ettit Mla(CBetStheels 10tteu aeta cases astatertfl 9905) 1 101I PL184 tillanti GMC. tAIE4A ble Gebit peBlitKatt lhe006 t& % tapa ll PestichlLatt tasent t> h SAR il patt . ED allts 0*131 9001 tatt 100 Litles $14140 test matt 100 alltes fittle east ante les Litets 71Lige es t/sa Pit 4 en la llList McLift 881 pit.4 to M llLVit Mellit elf Pit 4 to H SIL194 IseLitt ett I l.00 4 08/98 CDs sti CDs ett Com Con et/as Cut Mt tre 911 tem spe 88/80 tre Mt C58 ett est C8e 1135 1948 Itte: 0.4 9 as Ste 1990 at See M ese e at Me tM as 988 al Ste 6 al Me al ete M etat 45 Me 9 illi 14el l 0.1 6 at ete IJ00 as See as see $ M Me 130 as Me at 984 9 , al Me as Gle al GRA9 as MAD 0 tMS 1996 It 04) 0.4 0 1 SMS al MAD M Me 6 al GRA$ 3%$ as 98A9 as 084 0 at Me as Me as Atap 48 Ste 9 11 0 1300 t 4.1 0 1 3500 as see as ele 0 as ese 3M as see as See 8 as sie as Me as tem at Me $ 1700 1211 8tMI t4 0 t feet as als 40 stAp 9 as See 750 at esas at etAs 6 as ese 79 at ete at See 0 1300-1811 1 0. 6 0 1 4100 at Me as sIAS 9 as Mal 310 M READ al MS 0 as etap at Ste as See as Me e litl 14M ttM) 0.4 0 4 7000 at tem at Me 9 as sie MD at Ste as mas 6 as tem 79 As ele as ese 8 13M 11M 1 4.* 6 I 7000 at ele as See 0 as asas 793 al mas as Me 0 as ese 70 at Me as MAD 0 14.50-1345 te.nel 4.4 0 3 14N0 as see M esat 6 as ate leap u elas as ese 0 as eue im M Dee as etas s II30 titt 1 0.1 0 3 70so as ele as ese 0 as etAs 700 as He as 4848 0 as ete M as stae as Me 0 13 0 -1300 tite) 0.4 0 3 10100 at saae as sim 9 as es less aseut at See 0 as ste 100 as tem as etas 0 14 0 1980 1 0.1 0 8 7900 M tie as Me S 48 SEAe 750 48 etAD al Mas 0 &I see 79 as asas as Me e 1300 1315 Stat) 0.4 6 $ 19100 at see at etAo 4 as 0446 test as Ste as ele 0 as Ste lee at etAs as age $ 1340 1313 1 0.1 0 2 FWet as 8640 as Me 6 as elm PW A8 Age ah agae 0 as Map 79 as ste as asas 0 1319-1130 Ittg 3 0.4 0 3 Iflee 48 ttA0 al sie t as Mae test aseup at 88A0 0 40 Ate 100 at ete 48 tes 0 1315 1350 1 0.1 0 t Plles as esas as ese 0 as etap Me as Stae at mas e as ese 73 as ate as ele 0 1310 134l Itte n 6.4 0 2 Ptee as ese al ele $ as etAS 700 at aus as Ole 6 as See M al ese at GRAS 4 13 M- tl45 1 6.1 4 3 7000 as Ste at Me 0 as Mae M0 at sie atste 4 as age 70 M 0149 as ese 0 lHS lete list) 4.4 0 3 7000 at GRAD as DBA9 0 43 RBs 756 alGOD as 885 0 as Ate PD AS STAS A8 984 $ ll45 l&80 1 S.1 9 1 3100 as ate as See 6 M GRAD 3M as tas as ele 6 as Mas as tue as eue as ate 0
, S
.'"' .\
's
;.. v,.\.g.. ..\
( ...
\ - . .. .. N. . . ,
\ _ '.\ j .
' . ;?
e . ) 4
.Y ',,,s n
c%y , s {
, ;l
- ~: q.. - ,n .. .\
h , 3 *j ! i ' I I. ', r \ g . > h: .,}a\ i y 1: N' N-
, t
% j o i iD:
h -
\ ( l
{. o' I 1 i
's t i ? . 6
;\.
... s
-r~"
1, s i. o . .- q 0 ' l ..o o ', ij . ( - { I ' as t - u e/h N t-
- i tO
# 4
?
uy i e,, - 1, i
) ;
i o n. e .... i
- e. ', .
vf i A. s r, ,.
- O
*** /
o y ; / I I \ e j s y p?.
. * *)
e I w f'
'l . . . .. .=*
/
5 k
'. l
.\ .
\
\ /
i
e.. .
. . . . . . . . . . . .""'J;';i . .. m.,, . rl.,
q T "l'".".' bi *~ ,. * $$3 "l"O'" '",. Sib" 9"O'" d Yd "';. ' p .1'A "% "J .ll';ll"J L "'
'O J *J J * "# 1 1 '
J O "J J::""; "J t : t: l ": ll: : ::= " ": " l ll: "::l= ll: l
~~ # -
h Wh *
%y)y_
i l
- n,_ Qr' m w
i . n ,. , I t, I k . 6 p i y ..
,h .J $8-
~ >..,
,>\. .c , \ .
n, : - r"- ^ k .f - c i s i ;3$
~..
e9s, '
- 3. -
c a E'4 {% ,
~
( i,_# 1: .[- - " s
\
N E
'i . ,
7 ./ { ' i "!
., y 1
. ; ',. f, , ,-
b, ~
. {;
, r9i Q O 5 4 elg d g
. ve ,
- g. .m -
t s 4 +' ,-
-w in a (
e'
.s,_
i
'} -
)
=< **
}, -
./- .
i + ,q < j -
- - ' ,[
p r N i
~
_;_ A /Ijk
.- jw c pi . ip,
Mv. 9 estat 9.F.5 0/6/98 est tift taelaklisttak teueltsess 01 (tect flee tul lut paea 9.7 7 66W8 metattletteLista vlLLes aega galga aMatestet tel
- t/L PLlB4 Digteett 91Est. tasse nn te tap ll pattlCLILalt 44 peta BR % $a911 PaEtlGILa f t SafEls 32 44 San il DaS t .
9 131 gest tatt fittle eget tatt 100 Litttl 91L140 tatt tatt te titett FIL160 50 Sitti les Littet i j, tEl/se Pet 6 en-la little IteLift att pit 4 an M litvEt SIELitt Et Pit 4 3 44 $1Lv53 300L118 Ot t Spu W1 ton Mt ten Era sa/es (se alt ten get (pe Epm at/st tres ett Epu get (pm (su B l.W +4 et/sA (- .
. = u. u n. u == = u. .
... e i su. m == = m . . u=====
i i i.i e u n. == u m. . . . = u. i.n. = = = a n. . as u. == = =. = == . 1 1.4 6 M esas no as asas as at. 9 as esas as es. as aue as asas e as ease u esas as u. se el. O
; g -- - g j pa ~
g-
+
g
/g
[" 4 g' b g {$ 2 q/ I - i t- - . - J t g 3p,- Wa m K.A L.. Li _ JIL f (pg
~~ ~
%; 10 M,.m
< 3 .
-i rp
.. . _g .
~
hpg
' w y' ..
gM, . {d),i..m/ l n. j- . a i nf :'.ly. 3, 6, i' 31 , r l (, . .. j. fm % q" ' - , [ , et .g-@ ,
'i l 4; r - 4, ) 1 - -
p s 9,
's.o j ,f g / t (g
.I N
I Of ,
,,=,s , 'p~ ty.
7 ,, x ,"w , ea*
- N %
I $- N l ) 4' 8' -- 3 ("
*- p#"* 1 *>( [ j b N
i
' r
- . Ne ~ *
_%- . _ .[
) a .s ' .
. ..- p g:
[S g' Sg47 .i m.A j g . c.
- e
.9
<.g.y e. . . .y s g'
j .
; =
' d a ; ;e' y
}p a . m .,
i-7.-s - y/ /* b $ m E ---W f j j M/, g ( s '. .' w,
,1 ,
r- " 1
, l ,
3 4_* w , l J
. s 9 ,
.. .. i , 3, ,
/
^
^^
- n If -
j a 4 N l
; i
= y i ,
j [ ,t, _ ' ['l ' },3 p / ' [ i L
/ ,
s. f
- - v.,,
; ; pw ,. '
. I 1.
- . . . . . , - ~ . ~ ~ ~ . ~ . . - . .
. - - -,~.--n.. - . _ - . ~ -
V C./.,. .
,les. .
Cf...Itt .asi.L.it44 lfles f I get. fM 18 *1,11 .ed, f.F.,
.I a .qqe a Atart., g.a )
.LIII A804t f8 61 83 tatt
.t/. m.H .an l .duana te.ttW pastigan.t. .assin
,,;,,. 944 5 .t.1a.cs .amia mM. ...an tl ,.... .a ,. an M . . ..an
. . tt ,,,,.
... .C.
......l ,,,.
pastle,.t.1, 94,. 8. .
, s. . ... . ..
.> M
.It . an. l. .It 9 4..
Ist M lL.I. a.eLi.t.
.1
.est/ce
... 91.,
. . ..l.U.0 .. Is.L.i.tt . ., . .t.it 30.L.i.t. . . .
assee o tr m . c,, .
. 5 - -
,, J 3
, m b...
(kA-." E l t b [ 2[ T
- h. ,p 7 [- ,
l
,& - > , m.
t y m. W ,:-.f 1 ._.j t u
\
m.'y,.
.t I
* \
, :- w,ft a - , ,. ,
d ,/ i ,
,, e .
!( 1 Y Y.;# - ,
h e s u .s
' It , ,
\ ,)'r s % j 1
,- n
.x /' .g $3' (
[! . ,
.g.
6
.-s,(. ') t : $,,- --
,, l,,, s . ,
* ., n'h )
y-\_ ~ n v ., x s 1 , m. 1 sy:9m' h' * *R g.'
~t 3 m "s- e
;[I ',, [
..t 6 .';e, [l
,-' .: I ,17,
- t 'c '.i . . , , ,
.c ;;r .!
- - / c1 I o ...'- 4 4
} 7 g
t d.b. "hg , j
- 2
- l & -@ p j a l s,. ~
{ '
. [ . ,- ,
~
T. - ' l
- - : e A
, s
- l m /- I
- t
/ ,,, " ir i r
s . l 9 l c
~
; H fik '
c g .- {'s ,
._lene.xm h MJM.' N .ssa_. ~_ I
i 4 -
.3,...
. .....,__l.a._,,.., ., . , _ , . . . . . . .....
l l ,,,
.n . i_, .. ..
- a. _. . ,.,,
.i_,,
,.,...n ,.
..M . . ...
lL
.L ..t..,.n.-
. ... . , . , - . .M
. . N L.I . ,
..,. _ .,. ... it.
M Li1 x'
. [.
t.ttse.
,t.,..
9 8.,
. ,g -
- ) L, ^ 4 .
y,. . I,. , a 4 ' .< , i
. % _ ._ n g ^ '
4 a- ll e' I ' x
.L
'M l .
<g o.
a, e
~
O L, !%k -
. - d k LI a y . NS b. i; o
~
I k I ,, k. 1 3 t 9
.: fI i
\Y * '
,f g ., 1 ,
it
.=. .
1 N 'N 88' e g*e g
' ~
( s ,, gy.p' ink * ' ?
,\ , , _
. . i' 1 '- " 'o.e
-_ c e* .
, s'y, ,,y,t t 'jt ,
.: l {
h, M? '- ( l
% I,'.:l.h g,,, ,,[h; 8)5i
'AyW /
7
.....+- ,g n ,
- r
(
,4 _ =. .
- f. 4
~
l 3
\ I m .
I . /.
/l, Sl
. , ~ -
- j. , + ,,7
.. I -
/ \ i .
[ l { W p 1 tk
~
c . e.
- t i . ((l' i 1 I
. 1
e a
.89. .
O#./t.
.r8 *.118 etes4C.6 . Ct.ts tens 1 3 . 1341 t/t hell .s.(teattets.t 3 Tru.W t. .atte e .twite .Nel
.L4 45 .I.T C8 E.ut . .apuan on l4 .an - I t t 63A.18 .mena .a- te .an sl .e.f ttWL.It .w.u .e 14 .asi il .es t .
.5604 l 13) et it t Lille. . it tle sg .t 9 431891 78L140 st t.tg 1 L11333 .lg tte
.it . .n l4 .lLVlt IIR111 1 .14 . . e-44 .16W18 It.Litt .E l # 1. en 64 St6vit 184116 et t
.tC i tee l .. . 6 en/ta tre .Et tem get (De tea as/gg ten 41 ten Utt tsui tre e.i es teu ..T tra .st (su ten
..., . . . , . . . .t . .. . . . .. , . ........ .
.t .. ..
f.
. 7.7 . . .t 7. . ..s .t . . .I .t. a.a. . . . . et. . .s .s. .t at. gs st. .. t
,\
fr u y {" I ,
^b MgJ sQ ._
e .: i $y -~~ 4 h . . u?.y. C; g.; }&- j- . .. .
- u. . . ,
%.x 'h,o -
; m,?on ,A #
.i 8* ,
. . .J , : ::
}A,\ y Da* ' ' ~
$ (
' L<
r ,. 4 i l , Q ' (y*
# j pj ,.
. m i
@ lk o -
# , - i 4 ,f,@ 1 g ,q , j ,
$$ f .j # 3 ,. J' L ,*~ '
u, 5, b / , 3 ... ~ ~ NI l': "4 0, % l p' '
/ ,3 N y a 'l s y
\ .. c, -
r 1 , 5, ,,,s. .I I.T -@ y g. n.x, -
, , a-z , ..
- g. oa:s.,.. . . . g v' i '
, ~
e 'l D 2
,wa ty . ".
x g
' Sg; < n 4g s ,.# /
\ , '.....
.o== * $ 'G l t's
( W .) a' r t' E ' h sn A
~
.. . .. - w ,
a1
' }- I$ . ,
j
,1) ..
- .f; l , , i e
, x -. .
~
y M
~
\
\. s ;
.~. / 1 ~1. ,
7/
'l *1- .I y Q y
< Oc d sit
% I 6 i ' '
W /q
.v t- ,
; ' pf .
;* O"
~
r . [ .P g ~ J L. f ,o 10,f \<
. l i.
* <* min s k d.n n ea in't . . .
elv. 0 089 8110 tolsesstat $ thest 14ss IMl+less pass .F.11 t,, e,H -ote.. 4,Is., ,,um As.a M.te M.M.,,,8 ,e.,4
> an.u een ti Peel.
PLlee Dtiteett temt. tasen en M tan.it testicAatt egen , an.te tan.it peatte&att smam J-> -
";3 50 pull t *131 - essb uit les %B18e5 fittt4 tems satt les Littet flLife seal uit les tittet fittet
- - . eCites 915 4 an H S14848 McLitt att 964 4 gn.M glgeta geeLitt ett pit.4 9b % SILlet 8t',.818 ell d tsu satse seu att tse set gas gsu
. .', ., 31.0E*H e8/04 tem ett Epu ett feu seu se/M apa ett gee est Ese as Me teos asese MMe as ese too as He as Mas 4 1 0.4 4 5 twee as esae 'al Me e t
$ %.4 9 4 19se M Mae M M4e 4 at Me fee alele atMe 4 M Me Fe at 304e M els 4 8 3.4 0 1 35ee as ese as ese 6 at ese M4 M eMe as aus 6 at ese H ese at 464 M elm $
4 4.4 0 M 884 ese M esas at age 9 44 esas to M ese M esas 4 M esas se ese M tem M Me 4 5 4.4 6 M Ma9 acD at Me M Me 4 M ese M sie es eSac M Ma8 O M esas M ese M eMe M Mas 0 4 M Me M sede M Me 9 44 ele 48 o$# at Mae M 4848 4 M ese as ese at esse M ese 0 4, .f.?
.. . M ese .S.eeM eM. M Me A.He M Me a.e.e atHe M e.e M ele M eMe n. -
m
. ~.
~, ,
yy - 7
.. \
M 5 a' 3 ;.y i G .? m/.i w > c <
-. , p; 3 1!
t 4
% M. il ,
1
-{
'8' M k. . ( J I '
( r . g
' .k I ii
%l 'g j
j d, i~ ; s
': g, g y i I
/ I -
fs. , . gv , . p
~" -
u / e... m
,, s ,
~
)I g
.F. .g4 (*
) '
e** 4 b
\ 1./ u r .a gf . 4 eg ,
. ,a o
.,x J
*~
- t'g ;, "' = e n' . et y ,
3'M g ft O' . GW ,- - 4\ k J
~.
~
~
y, , I W =
a. '.' > e: h
((.
% s w L ,
t 1,pg, fsf'/ U
+ - s. o y ;
l 1
.= ,. *-
2 m .0
/ /E $ L h in .
- .. -5w e/5 l -
Il i
, m- . .
l.l - C '_ & s w
\ g .
g . l. 9
. . .. - \
. _ ja e,ir 4
^ '
1 -
,/, ;N . , -
[ i Y - i pr s ' ~ g o ( E; i t'i e
~
g
} _ m
(, I
- J'
~ ^
~'.
i . . l j e..
.lkmq .f.. 4/6/ -
I .s -.it. .a.i.Lessta6 .usses gr .6.ss tas.1.st-1 1. . ass g,..g3 6t. ass.tt t. 61st) ttLL.W as.4 ngen as.6LWt ett Pan 84 .l.taset .$/L gut. .assia ..u .am il .estlinkat. .agm WM .m- 81 848titt&It amm .s+ M .an It .as t 4' .o .8441 1 134 es .att t Ltt e .sm t .ittee .sa g
#- pi.ttee ins.e .tggas ett .it a. >M 81 Ptt s . ate pM .L i t. .st . . .att .> t . g Lite ti.ttet It.u se .t1E.t.te..
Litt .it
'*3 8 1../.s. LL.u..
( . .ree M It se .tt too esa estre .se t1 tse ges seine .se it IIe t see .se i ... . . t . . . . ..t . . . . . . . . .-. . 1
! 1:t
? = ll..= .."4 .
ll = :: ll. = " = l " = o':..
= ll -= !
t t
.. .. .. . . = = . . .
. . == = . - = = . . . . . . . . . . . .
r .. . .. t . . - . . . .- -==. . Wt 9e / 7 . 5, 0 ' N h [i [ N.fs I-- [. c _
- c. . . , ,. .
N'
- / 1 N T '
;b p ,. 1 n
s h)=6.. *,r,j
" ,- q 1 Jy f / LW. L i I
[ I
- g.- .
I y..
~
=
l
-g y i
( , y . =>
. f'
, j i u
[\ ~
/ '
. g$'N !
Yg % g'..
* &_ K W ~, d t'. .k "
~*
~
j l jh R .:L..> (. p,. .'a
=
Pi
, -aw.v.g !
, ~ 1f.t M y ;% j
' m ,,
m
. I '
....\. .;,w
~
/ ,
11 ,. t} ha
.--# l i
,. t
. z ei[
-- 7. - if 9 -
~
I k s
' V
[ -
- i. - E 1d.f_ g \s i
'Gh-4 l..
___ . . ~ _ . . _ . - _ __ . .
. .-. .__...m_.m..~. -_ . . _ _ _ _ _ _ . -._
cn.i's immi6 E [ .'$n .no n.u. ,,. o
.A ht. .A at .t v.6g.g .a..
s .e a..talt. ) htse ,1,18a .m.. . ass .m M .an+s.te. 1 . .nsuin .m* M .an It .as t s.w.t. amin t i ! 44.. .t e. .u .41 1,.s.,. e t e.a..t.
. 36 v. D . 5 61..
.n M .an- 1
. It t.,.
j .. . . t .. I .af.. .. . ..Li=t ., ti . a. .af... . .Lm i it... i 8 . i,....a.... /sa .se t .mi =t .se .ps esp e .
.se t .se ? .ps
.t t. .t
. t .se s./us .se t .ps t .se .os l
.E.
. . a.
& /
g N Q%bk ' b%-1
< %- m% m r.
.g Nt, , ,h,* [ 2
, i w - v~ ,
ku c.c: m, - , t 9' g , g' <g p 's #8 @, L
, \\ ,,
3 g5'
- a1 -
e , s. .
, lw -
, ,, ... y.
(. f8 ' gi * .- Ii / ; r .- d Ws 1 .,,,,
,)r// (,p, q, ~, 'p s
3,~
'(
g.p , y
- f. l ,.,
, i .. g. r,
.- :- ,/ .. , , , ... ,,;s .
N ' - v.3 ls > ( t{ g"e, [;~.' A '
-; t .,,, /R l l
=
3 '[
- p. c g:
- i .vc. y s
.ar.: p h'p L. ,
. m 9
./ .,
e A we... -;.w gi *- . l II - 4*
/ ,1 . * - , , . r- .
. t e s . s .
. U , h l . 1, . .
M ,l[
"~ 1
'" } \
N A l ; T -
, L ' s illE' /
' V
;- ' '5't I
, a N
. I'
! ...,t. t..l l.%'f - .m b.,..
i
.L....,1, u. . ....,t..,
66 4 .Iltaart get. .n. h .ap lt .e.fittiL.tl .assen Du .am. I t .a.f th..it . asset .m. t. .am. 8, .e. t . I
,- .4L84 1 01 . .ama t4 18 6 .149,9 .e.s .att . Litt.t ,84tte t ,lg tt. j
.it se .att .s M itt. 8ealte s# 61t t .n M .1 .m. s a .LitI .t 8
.etl. l.ie.
I saret .se tl .pe .81 spe f,se as/as .pe .B1688 t tre E.13..Ltit (vs .se .it .. t .att .ese s./.e t tse .It tse . . tre tit. 413..t t .. . . . . . . . . . ... .. . . . l Jyv] ! '.. !r ? 9... . D, e D A , 4 v vf~ ' A h s J} 6 W~
. ,a e 7- $ -
A ri i I f {
- g. v x ,
. d . e. %,
;\Y
;l...
; ,, i J .j h Cf , ,
)
9 W s .. g f,'
/ , . . "' A -
' g,8 "
...- ty
, p : ,
, 4 ;,,
\ '
f 11
~~
. + 1 -
c . . , >,,, 1 gh **
- i
- tig'a W Nl",q "
( i -:F' t.@'v ..,g, +j qj j . p i , ap ; g
,,, .s ,, y 1
/ I 9 l
l
,e c.... -uu g, .i u n
)
,1 r h*
1 4 . t s
. f I
, \ ) .
l , - . 1, ? ,/ O 7*'I i[f = ,, i P[ et
. ,[
t p l
\ 1 w q. i) s
[\
. I 1 '*
1 -
t .
...t,11 es...t.,1%';". 3,e EM ..aee $'!.,.,,
4/L 06tt antaggestgestat) tt6 Lev anta cases seguestes geegg estes tittaaet gent. ensis an u esp tl pasticatatt eassen pH ten.41 satt HMLatt taisin an. H ee.tl past. l l et alttl 8 13% gest tatt les Littet $14180 eget &< tel Littet flLtte get hatt top Litges e tL110 ! I ' # estsee .est.e en.h titeet seeLift at t Plt 6 en 14 SILVEt INLitt est 986 6 en 94 Sitwe geeLitt est { k a t.et.e serue esa ert tsu ett spa tem enroe ten ett tem ett see tsu en A t tse ' Mt tse ett tse tsu ! e __ t 9.4 0 3 pese at sta as ese 4 ~ as ele me alese 48Me 4 as sea- 70 as ese as ese $ 8 3.4 0 t Mee at ese se ese 0 et ese att as ese as Me 9 as ese na ele al ese as ese $ I 3 a.4 6 as Me en as ese as ese e as ese se as ese se Mae 9 se ese M ese as ese al eld 9 I a $ at e64 See afese atMe 9 as has el M ese at Mae 9 asese ,4ese atMe 44ese $ l a,6$ 0 M Me les MMe atMe 6 M Me H at ese as Me $ alete 44Me M ele atMe 0 4 9.1 4 M Mas act al asas as ele . O M Me alMe atMe asMe 9 as ele M Me M ele AI ese 0 .
*-a !
+
_e
. l l, n , ,
< . ,9 f' p
e L' , aj
\ '
- Lh hM5 j yp,. n
.* ^ * , $ b
- j ***neessee
- r. ~.~
t f y t
~
f,-{^.7 ,
- .o s ,, , y,.%s-
- s. 1
\ . .2 ib
,' o
/ % l M.
A t 3 # e &
. .J, ,
%.L i i I 7' - - .
) w ., g ;
.e ,
t.%,. I i p g il - i c.f. " r .
.- t i
l , i
+
8
+
g j , .g ,
- I 0$ i ,j h,e '
, , . l
/. -, e.... ,
, g,'
( p'
\
( ' (J P.-
]
i pr[
?
Yh. j . .
, , . 9
=
. .- 8 5 = t,e ,
..i Ne ,v, .. i' %
- I '
/. (.
,h
' j
.n y 1- L'>.g-f 1.
,8.
- =
o , v .;.. e n p . n .. t
.' 2?.h. AYe a.'
no { i , g g & #j ,
/
k ' N i
.- .. - n-
, g, n, ,,
(
. - g. . Ej. '
i
. a e.
, al -
*/
- l ,,"
\
w , \ , t-1 '
- e. ,e 3
9 _ l# G. e ,ir '
~j
/ ,
\, -
j i e i VERMONT YANKEE NUCLEAR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EXERCISE 1990 10.2 CENRRAL AREA WS FORinARTE ,
,I
.(.
I f 1 i 2156e
~ ~ .
Rev. O Page 10.2-1 l .{ THIS IS A DRILL a 10.2 CEWrRA1. ARRA WS FnRMARTS 6t00-12:00 - Qgggral Aram Foraemat Mostly sunny today, with variable winds becoming northwest 5 to 10 mph by late morning. High temperatures 75'T to 80'F. Probability of precipitation less than 10%. A high pressure system centered over Pennsylvania will drift southeastward and slowly weaken during the day. This system will . dominate the weather today. l IEls IS A DRILL ( 2156e 1
...-w-. g.
h i Rev. O Page 10.2-2
.l THIS IS A DRIII I 10.2 CENERAL AREA WS F0HCASTS ,
i 12:00-18t00 - Canaral Area Fornemat j Mostly sunny and warm this aftornoon with a high near 80rt'. Northwest winds 5 to 10 mph. Mostly clear tonight with a low around 55'F. Winds becoming light and variable. Tomorrow, becoming cloudy with showers. Highs in the mid 70's. Winds 1 l I becoming south to southwest 10 to 15 mph. 1 l I 1
.k l 1
i l 1 l i HIS IS A DRILL l . ( 2156e 1 d
, _7 , .,t .i',
9
~j .J ?' \-
j. l VERMONT YANKEE NUCL5AR POWER STATION EMERGENCY RESPONSE PREPAREDNESS EKERCISE 1990 l:' 10.3 NATIONAL WEATHER SERVICE SURFACE MAPS t l l: A
! i l'
t { t
,- 2156e
\
FW D
..- .- .. .. ,, . , ,, . a .. , ,, ,
Page 10.31 g/[ h
'hfT.' 4- mn __. -
g is s'
- , , e .
/
,j '
- 4 ---
e <,, lh*'
' ,s i 4l Mu g ,
9j - P
.h f '\
pg/
,(.fik,x
.,wg . o" gdu'
~
I
} ,' # j 7 , 4.:
s v@ k'-I Y- s ,.
.. m, , .
(
.;; *[-.v . _ . . --: $~; .' py.; W,, *:ng . Q., , . ,
h5 .. hhh.hi::;k. 9 ghf . y
;r
~ :y ',
ywygapgry . -r ~ y , . . * . @%q . . 4 yx.xp x ,, p ' s r ..
.?( g-fy q' 'w$ %.n.4]%jzy.#1[h' {s,d pE ,
\ .. _ .
; g3,4. ,g 7 s s ;4 , ... . .
ter,
, V[c kp9% t. .,t w: ,;
c
.= = == = :- - c -
tw, pt ! . .*g.t W w{' .: l M:!,'!,,'.,*A. tu,.,ltr ,.L 1 _xx _5 " _E _ -u n -. =
. oo m
., . e see aar- e. e- e. e t*,* .s** iaf" it' t#' ' W ' ' N ' te tW* e* B' st* ef= w* ea .p* pa ili ,
g, MT ; 4, i
' ~ . is * '
' s3 e 6* '
7, --.- . sg , -4( T i" 4 i 41,
~
E N
.' hb"ug[3. D _1 r L I
- ** s. %x%
s b~/ ' 3; e
.r
'& , r .e s5* s 1
": j
,f f ,e k: t gfp 3 v._., w- e w , [O,9 z v m*.
, 1 4., , g,..g u p t ,
, s u s.- s ]-
g, mg _0p.. , - --
- Ca6
; N
.y, } -
senz:x+ < r
- W:
, j .o; -
3 s h s > 3 ) g. 0'?
...4
)+.,.
s.;;toi-f',m
'Nb* 9 g
. y1
~,
yg n u'
,i p.. 4, 3.;.
fbf L..? N'? k k W [- go. ,,p,...,, p ,co
,ov.,
,y gVN,w ";4*.,-
.. . ,,,. . . . ... .. ... . ... .. . . . . r , r. , , , , . , . . . , , ' 1_}}