ML20094C008
| ML20094C008 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 07/25/1984 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| References | |
| PROC-840725, NUDOCS 8408070336 | |
| Download: ML20094C008 (426) | |
Text
{{#Wiki_filter:7% , SM-3$2/353 O EXERCISE MANUAL NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION July 25, 1984 [O' Aj Sections II and III are CONFIDENTIAL j%. CONTENTS NOT TO BE DISCLOSED
) TO EMERGENCY RESPONSE' t(
2- d EXERCISE PARTICIPANTS { F 0 PDR 2 g\ g h
? # N'
-J; LIMERICK GENERATING STATION PRACTICE EMERGENCY RESPONSE EXERCISE July, 1984 TABLE OF CONTENTS SECTION.I- GENERAL INFORMATION
.Part A Exercise Schedule Part B Controller and Evaluator Assignments Part C Exercise Objectives Part D -Reference Documents Part E Participating Emergency Centers Part F Participating Agencies Part G Exercise Guidelines I .
Part H Instructions for Controllers and Evaluators t - SECTION II EXERCISE SCENARIO Part A S'ummary of Exercise Scenario , Part B Detaile! Exercise Scenario Part C Significant Events Time Line eq,-%
) SECTION III DATA Part A Plant Monitoring Data
- 1. Reactor' Coolant Activity Concentration (pCi/gm)
- 2. Drywell and Suppressica Chamber Air Space Concentrations ~(pCi/cc)
- 3. Suppression Pool Activity Concentration (pCi/gm)
- 4. Reactor Enclosure Concentrations (pCi/cc)
Part B Chemistry Sample Data Exposure Rate from Post Accident Sampling System Samples (mr/hr) Part C North Vent Stack Sampling Data
- 1. North Vent Stack Release Data (Source Term)
- 2. North Vent Stack and Effluent Data A. Gaseous Eftluent Monitor Readings B. Expocure Rate Increase from Iodine Collection on Charcoal Cartridge C. Exposure Rate from Stack Sample x 3. Meteorological Conditions
. [v).
i
TABLE OF CONTENTS (Cont)
,ag .
d ') Part D Field Monitoring Data
- 1. Whole Body Dose Rates
- 2. SAM II Readings ..
- 3. Anticipated Dose Assessment Group Results Part E Onsite Radiation Levels
- 1. Site Map (Plot Plan) Divided Into Zones
- 2. Dose Rate Vs Time for Each Zone
- 3. Airborne SAM II Readings for Each Zone and Time
- 4. Surface Contamination Levels Part F Inplant Area Radiation Levels
- 1. Area Radiation Levels, Surface Contamination Ievels, and Airborne Radioactivity Levels by Region
- 2. Maps Showing Plant (Unit 1) Areas and Regions
- 3. Area Radiation Monitoring System Data Part G Exercise Events '
Part H Control Room Messages ' Part I Headquarters Support Requests Part J -Plant and Reactor System Values Part K Site and Field Monitoring Maps Part L Controller and Evaluator Checklist
-e- ..
'ws/
( I h
'_)
11
i L' , d Et , ' EXERCISE SCHEDULE x /? 1984 NRC/ FEMA OBSERVED EMERGENCY RESPONSE LIMERICK GENERATING STATION
~
' On-Site Controller / Evaluator Briefing Date: Tuesday,~ July 24, 1984 5 Time: -10:00 am Location: Limerick Energy Information Center
Purpose:
Pre-Exercise Scenario Briefing Attendees: .PECo Controller / Evaluators NRC Evaluators
. Coordinator: .M. Gallagher
- Exercise ,
- b. - Date: Wednesday, July 25, 1984 Location: Limerick Generating Station
Purpose:
Radiological Emergency Response
- Attendeed: Site Personnel I- .
Coordinator: R. Kankus, M. Gallagher Exercise Debriefing 7-K- .: Date: . Thursday, July 26, 1984 Time: 1:30 pm t (/j' A-- - Location: Limerick Energy Information Center
Purpose:
~ Players and Controller / Evaluator Debriefing Attendees: PECo Players NRC and PEco Controller / Evaluators Coordinator: M. Gallagher .
- Exercise Critique Date: ' Friday, July. 27, 1984
- Time: 10:00 am Location: Pottsgrove Junior High School, Pottstown,- PA
Purpose:
FEMA /NRC Public Comment Attendees: PECo-FEMA NRC Coordinator: R. Kankus, M. Gallagher Liq . v .' h 1A-1
c CONTROLLER AND EVALUATOR ASSIGNMENTS NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE e's LIMERICK GENERATING STATION ' j JULY 25, 1984 CONTROL ROOM NAME Head Controller M. Gallaghar s Controller - Hand Outs R. Vanasse (SVEC) Controller -- C. Madsen Controller - R. Gambone (PBAPS)
- Controller - Accident Assessment W. Mattiford
- Controller - Accident Assessment H. Carlberg (SWEC)
TECHNICAL SUPPORT CENTER NAME Lead Controller D. Graves (SWEC) Controller - Dose Assessment C. Mazzola (SWEC) Evaluator - Dose Assessment D. Burwell (SWEC) Evaluator - Persor sel Safety Team Leader H. Lipschitz (SWEC) Evaluator Chemistry Team Leader E. Micheel (dwnu)
- Evaluator - Security Team Leader J. Basilio
, Evaluator - Tech Support Team Leader F. Cross (PBAPS)
Controller - Field Monitoring Team Red J. Dietrich (HP-NSS) J50 Controller - Field Monitoring Team Blue A. Bergey (HP-NSS) Controller - Field Monitoring Team Green M. Hurvatinovic (HP-NSS) Controller - Field Monitoring Team Yellow R. Bernhardt (HP-NSS) Controller - Chemistry C. Doherty (SWEC) Evaluator - Chemistry Lab
-f 1 W. Leinheiser (Chemistry-GP)
Evaluator - Chemistry Team S. Blacklock (Chemistry-GP) Evaluator - PASS M. Clifton (Chemistry-GP) Evaluator - Fire & Damage Team Leader M. Restaino (PBAPS) Controller - Assembly / Accountability / Evacuation D. Taylor Controller - ERFDS HanJouts K. Serotkin (SWEC) Controller - Evacuation Offsite S. Gallagher (NSS-HP) OPERATIONS SUPPORT CENTER NAME Lead Controller - _ D. McDavitt (SWEC) Evaluator - Maintenance Supervisor R. Hennessey Controller - Damage / Repairs W. Stull Controller - Damage / Repairs C. Wyler Controller - Fire Team- S. MacAinsh Controller - First Aid Event V. Affatato Evaluator - OSC Coordinator (later) Evaluator - ARMS Handouts R. Bettisoa (SWEC) Evaluator - In Plant Rad. Monitoring Teams J. Richardo (NSS-HP) Controller - Damage / Repairs J. McElwain EMERGENCY OPERATIONS FACILITY NAME Head Controller _(Offsite Activities) R. Kankus Controller - Command & Control E. Firth Controller - Dose Assessment E. Salomon (SWEC)
-~x Evaluator - Communications / Status Boards R.. Smith (SWEC) l Evaluator - Dose Assessment D. Leonard (SWEC)
Controller - ERFDS Handouts / Engineering Support V. Warren IB-1 & j
~
I HEADQUARTERS EMERGENCY SUPPORT CENTER NAME =. g 3 - Lead Controller K. Schlecker
~ Evaluator _ - Comand & Controller Evaluator - Public Relations /C munications E. Doncarellis (SWEC)
(Offsite Medical Facilities Controller ~ K. Mandl M
. i U
6 N O IB-2
OBJECTIVES FOR THE 1984 x NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
; LIMERICK GENERATING STATION
.s In order to demonstrate the radiological emergency response preparedness of the Limerick Generating Station, the Philadelphia Electric Company (PECO),
the Pennsylvania Emergency Management Agency (PEMA), and the surrounding risk counties, an integrated radiological emergency response exercise will be conducted. The-PECO objectives of the exercise are as follow: A. Accident Assessment
- 1. Demonstrate the ability of site personnel to recognize an emergency initiating event and properly characterize and classify the emergency according to the pre-established Emergency Action Levels.
- 2. Demonstrate -that PECO personnel can perform offsite dose projections and accident assessment, for both radioactive noble gases and radioiodine, quickly and accurately.
- 3. Demonstrate that onsite and offsite field monitoring tesms can be dispatched and deployed in a timely manner; that field communications are adequate; that radiological monitoring n-!- equipment is functional; that simulated data are accurately
~i obtained and transmitted to the appropriate location and
'# individuals; that results for area radiation levels and air sampling and analysis for radioiodine and particulates can be effectively used in - determining protective action recom-mendations.
B. -Activation'of Emergency Facilities
- 1. Demonstrate the ability of station and corporate personnel to activate and ' staff the emergency response facilities as appropriate for the existing emergency class' and to transfer functional ~ responsibilities to the appropriate operations center when escalating or de-escalating to a different emergency class.
- 2. Demonstrate that adequate security of facilities can be maintained.
- 3. Demonstrate functional: capabilities of equipment in both EOF and TSC. (Functional capabilities may be simulated on real-time computer equipment.)
;- 3 l l 'J IC-1 a . .
y C. Notification and Communication Demonstrate that' station and offsite notification of PECO
'N l.
' ' ~
_ staff and officials can be accomplished in a timely manner and - that all initial notification and updating is verified and logged.
- 2. Demonstrate the ability to comununicate with in plant
. monitoring teams, rescue parties, and other station personnel as needed.
'3. Demonstrate that the decision to notify the public officials can be accomplished in an effective and timely manner.
- 4. Demonstrate that messages are transmitted in an accurate and timely manner; that messages are properly logged; that status boards are accurately maintained and updated; that appro-priate briefings are held and incoming EOF personnel are
. briefed and updated.
-5. Demonstrate that public information is coordinated between PECO and offsite officials; that there are accurate and timely press releases and briefings; that designated public
.information personnel are inplementing their procedures.
D. Station Health Physics and Security
- 1. Demonstrate the ability to account for all persrunel within the protected area onsite.
}
/-
- 2. Demonstrate the ability to provide adequate radiation
' protection services such as dosimetry and personnel monitoring (frisking).
- 3. Demonstrate the ability to perform area surveys under emergency conditions.
- 4. Demonstrate the ability to enter a highly contaminated area for the purpose of rescuing casualties.
- 5. Demonstrate the ability to provide first aid and transporta-tion to a suitehly prepared medical facility for an injured individual who has been contaminated or has received a high p radiation dose..
. 6. Demonstrate the ability to maintain plant security under emergency conditions.
-7. Demonstrate the ability to perform post-accident sampling and analysis of in-plar.c airborne radioactivity and surface contamination levels.
p dv) IC-2
- 6
- 8. Demonstrate the ability to pniorm personnel and equipment decontamination.
). 9. . Demonstrate the use of post-accident sampling equipment to obtain transport, and analyze samples of reactor coolant
-and/or containment air samples under conditions involving fuel damage.
E. Direction and Control
'1. Demonstrate that local offsite support agencies such as life squads and fire companies will provide timely support.
- 2. Demonstrate the ability of the directors to direct thq emergency organizations in the implementation of the Emergency Plan and the Emergency Plant Implementation Procedures (EPIPs).
- 3. Demonstrate. the capability to technically evaluate the incident conditions and implement appropriate corrective actions.
, e
.4. Demonstrate that PECO has 24 hr capability. Demonstrate that all agency representatives who a r,e assigned emergency
-~
reponsibilities can effectively operate from their planned location inside or outside the E0F. (May be done on a limited scale by designating two shifts.)
'-\ (_j) F. Protective Actions
- 1. Demonstrate protective actions (including mock evacuation and sheltering) by preparing an exercise scenario which provides for a hypothetical total integrated whole body or thyroid dose ~ exceeding the evacuation PAGs for at least the nearest residents.
- 2. Demonstrate' the ability of the site and the EOF to make recommendations on both the taking and relaxing of protective actions.
1 s L G. Parallel and Other Actions u
- 1. Demonstrate ~ tb.e ability to call on a designated hospital to 4
treat a hypothetically contaminated injured patient and that the ambulance service can, effectively transport hypothet-ically contaminated injured personnel to the hospital. Demonstrate that 'the ambulance and associated equipment can be~decontuminated and that contaminated clothing and dispos-able materials are properly discarded. y , IC-3
- 2. Demonstrate the ' licensee's capability for self-critique and
-- s ability to identify areas needing improvement in order to make future appropriate procedural changes.
x-The PEMA objectives of the exercise are to test and evaluate 'he capabilities of- state, counties and municipalities to interface and coordinate with each other in~the following areas:
- a. Notification of Officials and Staff The adequacy of the nuclear incident notification and alert procedures from the fixed nuclear facility to PEMA, BRP, risk counties and municipalities, and support counties.
- b. Public Alert / Notification and Information The ability of state, county and municipal authorities to alert, notify and updats the public of incidents within the plume exposure pathway emergency planning zone, to include actual use of sirens, EBS announcements, route alerting and other communications means available.
- c. Communications The adequacy of and/or the need for all planned internal and external communications systems among and between the participants to include backup communications system, EBS and RACES.
m
) d. Emergency Operations Center The adequacy of state, county and municipality emergency operation centers with respect to security, space, comfort, staffing and function for managing responses to nuclear facility incidents.
- e. Direction and Control The ability of key state, county and municipal emergency response personnel and elected officials' support for the initiation and coordination of timely and effective decisions and their ability to provide resource requirements for incidents.
- f. Emergency Plans The adequacy and capability of implementation of state, risk and support counties, and municipal emergency response plans.
- g. Public Information The adequacy of the interface of state, county and nuclear facility public information systems with the news media, to include news media briefing rooms, rumor control measures, etc.
%,j IC-4
-)
- _ _ - ~ _ _ . - - - ..
-h. !Accident Assessment (Bureau of iladiation Protection)
The' effectiveness' .of nuclear facility accident
-f
(]f ~ state BRP assessment system, - to include . adequacy of equipment, personnel
. staffing and competency skills with respect to reporting dose I projection, field measurement, coordination and communications.
-1. -Protective Measures The capability of the state, county and municipal emetgency response systems to implement sheltering of evacuation and to take actions to activate such support functions a s reception centers,
' mass. care / decontamination centers, decontamination stations, risk school district procedures, ambulance services, bus operations, and pickup points,
- j. Radiological Exposure Control The ' capability of state, county and municipal emergency response
- personnel to implement access control points and traffic control points, the issuance of dosimetry and KI and the record keeping
_. and decontamination procedures. i : l[ \ w[ I f
'/ .
).
10-5 i-e... j
~ REFERENCE DOCUMENTS i NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE c(N_ / ) LINERICK GENERATING STATION
- 1. . Limerick Generating Station, Emergency Plan
- 2. . Limerick.benerating Station, Emergency Procedures
- 3. ' Limerick Generating Station, Final Safety Analysis Report
- 4. Title 10, Code of Federal Regulations, Part 50, Appendix E
- 5. NUREG-0654/ FEMA-REP-1, Revision 1 b
l 4 l l 1 I l l
\
ID-1
.t . i
r _ b PARTICIPATING EMERGENCY CENTERS 4}' f NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION Pennsylvania
;"..g' Bureau' of Radiation Protection Headquarters Assessment Center, Fulton Building, Harris.3arg, PA State of Pennsylvania Emergency Operations Center, Transportation Building, m - Commonwealth & Forrester' Streets, Harrisburg, PA Montgomery _ County Emergency Operations Center, 100 Wilson Blvd., Eagleville, PA 19408
~
. Chester County Emergency Operations Center, 14 East Biddle St., West
. Chester, PA 19380.
' Berks County Emergency Operations Center, Leesport, PA 19533
. Philadelphia Electric Company Headquarters Emergency Support. Center, 2301 Market St., Philadelphia, u PA' 19101
~f Limerick' Generating Station Technical Support Center, Limerick, PA L./
Limerick' Generating Station Emergency Operations Facility, Plymouth Service Building, Ridge Pike & Chemical Rd.,. Plymouth Meeting, PA 19462 t 4 x b O v IE-1 L
- ai G
N I T A
<' PI _
C _ IS TR RE AT
- W PN FEC O
g S CY n sr N N Ru E OE
;*,* , , o T
Rc IG T Ay u, AR
', , #, oo CE
, ' ,e ,
oo, cap o u OM LE pws_
~ 7 GF NO
, . ,N, ,g * -
,u%,
se KIET - . CAN I O ~ RRI EET
, ') y ,
MNA ,s ,, , ,fQ. - IET LGS s, rs G 2 4 o N NI CATN .' n e nRIO e EET MNA IET LGS Y R Cv E O. M EE n."" _ " C
2 5
OY 7' GT TN e l '" e
$ NU OO
" l --
MC e e m m R Er 0 Ti 0; *
- sm uC
'o w woo CCt g
e
.j gii o
e -
/ ,
p
'N 7
fe i m , L l E V _ 7 ST _ NN RuC EoO BCE o t, it 18 _ s E _ t i o, u t E t A
- C
_ s 1 9 O,
= ,
e, g r t
.'s,' A i
bJ = D iS t 4 N f r v t A
' L
' r Y s,R
- N A N" N M
,' E P
/
A
/R SE RT i
M EN , TE " , RC a uT QN DE I AM g s ES
, E P
MS E
. PS j RS BA
[
r ]
, u;3.a i .i+ - . e. n v a >s-~J - :" ,
Lu f j 8,. ., ;_- ,$ ~} , e
, . , _ , s : w. , - ~ +- ). -, .
~*l. - t -
J.
..~x
" ;% W.,[,~, . . * ' ' > .:.Q ;,.
3 9 V E . I
. .- n
'\? '. fA . ,
' ~ WIID t
GE teERaTsssG w g STATION ,
.M i . , .
[ ' uutnics aiC-
'y f' s T. PECO * eem PEmsvtvania * \* ,,% w aoouanTEns .
svaTE Eoc 7 j * ' "* " * - " one wao0uanTERs/ HarrisburI**
,a
.t , u aSSE$$ MENT CENTER g O. 1/.2 .
' ee ,
as sC au -usu s "
-) 3
~,
~
g% , ' '
/j-
*r 99 PHILADELPHIA DETAll OF HARRISBURG (Downtown) 0 1 2 O t/2 I
= ' '
scatt-mites scale-utLES
**' MomTGouEny CouNTVEOC l ~
*'/ ., ,
s'4%# f-
<,' '. b, d *
. \
n $ @MESTER, ' ' .a'_ , s DETAll OF EAGLEVILLE
.#, \ 0 1/2 * *
\s ',caa:.,a; s .5 >
s - ,-
/
p' 216 s *e e , o M 216 f L IME RIC N d 2
- DETAIL OF WEST CHESTER $1"o^,'{"oi ...,,
9 t/2 ; sCa u -witEs DETAIL OF PLYMOUTH MEETING AREA DETAILS OF PARTICIPATING i 2 9 EMERGENCY CENTERS SC a6E - M*L E S
- ~, t w
7 _h s.
'!U 10 tj~ p jjh PARTICIPATING AGENCIES !
i ,/ '~ ' 'NRC/ FEMA OBSERVED EMERGENCY RESPONEE EXERCISE
.g. LIMERICK GENERATING STATION l 4
n , i
\' D
, PENNSYLVANIA-
" }; State Amencies
~
PennsylOania Emergency Management Agency (PEMA) l Bureau of Radiation Protection (BRP) State Staff' Sections Department of Aging
. Department of' Agriculture
' Banking i Department of Commerce
. Department of Community Affairs
- Department of: Education Governor's Energy Council Department of Environmental Resources
^
Bureau of Radiation Protection
'3 Department :of General Services y ~wf Department of Health s i: Insurance' trep . Labor and Industry
( ~ Department of Milit9ry Affairs
-Public Utility Commission Department of Public Welfare
, Red Cross Pennsylvania State Police Department of Transportation Turnpike Commission Pennsylvania Game Commission lO
- Risk Counties Berks County Chester County. :
Montgomery County ( Support Counties Philadelphia County
-Lehigh County e
~ Federal Agencies o jq o. Nuclear Regulatory Commission (NRC) 1
.- b~s/
1F-1 ,
r GUIDELINES FOR CONDUCT OF THE JULY 1984
, NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION I. ~ PURPOSE AND SCOPE This document provides guidance for conducting the July 1984 LGS emergency preparedness exercise. It provides methods for demonstrating emergency response capability, conducting the exercise, and evaluating results. Table 1.G-1._ summarizes the degree of simulation to be employed by PECo in demonstrating emergency response capabilities.
II. CONCEPT OF OPERATIONS AND CONTROL OF THE EXERCISES Philadelphia Electric- Company (PECo) and Stone & Webster Engineering Corporation (SWEC) will supply official controllers and/or evaluators for
;each- location where an emergency response is being demonstrated. Prior to the - exercise, the controllers and evaluators will be provided with the
~
. appropriate locations, maps, time periods, guidelines, and an evaluator
' evaluation checklist corresponding to their assignments, g-
~
- g. _ Contro11ers ' will ' hand out messages arid cue cards and will make judgment decisions. If crisis situations arise, they will contact the Lead Controller in their assigned Emergency Response Facility (ERF) for advice or resolution of the problem. Lead Controllers are designated for the TSC,
-0SC,1 and EOF to keep these ERFs on track. If. required, they will contact the . Head Controller to force play of some events. The Head Controller, stationed. in the Control Room, will be in overall charge of ccnducting the A exercise. All requests for modifications or holding periods must be cleared
-through the Head Controller.
, -The exercise initiating events will be controlled by lead controllers.
y
.. Hypothesized initiating events will consist of three types of information:
(1) ' plant information and data provided to Control Room and Technical Support Center personnel; (2) release rates; (3) hypothesized environmental radiation levels. The Head Controller in conjunction with the Lead State
" -Controller has the authority to determine the time sequence of these
, , initiating. events to ensure an orderly flow of exercise events. All other actions during. the exercise will occur through a free play response as the plant and corporate participants respond to the initiating events.
' As .the initiating events are provided to the plant staff, they will determine the nature of the emergency and the implementation of the
' appropriate emergency response procedures. These procedures are expected to
. include a' determination of the emergency classification in accordance with NUREG-0654. FEMA-REP-1, Revision 1. Notifications will be made to the
- appropriate federal, state,'and county authorities.
1G-1 w
h a
- The hypothesized emergency will continue to develop based on data and information provided to the Control Room and TSC personnel. As the situation develops, information will be forwarded to appropriate plant and corporate personnel for the determination of actions to be taken in response to the hypothesized emergency. Where information would normally be h.
f confirmed via an independent source (such as National Weather Service for weather data), the confirmation data will be simulated. If a conflict exists between the hypothesized data and the actual data, the hypothesized data will be utilized. Certain inconsistencies (such as plume width, release duration, technical reason for the simulated releise, etc.) may be intentional and required to provide an exercise basis which tests the plant and corporate capabilities to the maximum extent feasible in a limited time frame. If an inconsistency is known or determined to be intentional, then the emergency response personnel will note the inconsistency and ignore it. The lead controllers will have the authority to resolve or explain any inconsistencies or problems that may occur during the exercise. With the exception of the already cited and potential inconsistencies, the internal operations of the emergency response facilities will be identical with their intended operation in a real emergency. III. GENERAL GUIDANCE FOR TIIE CONDUCT OF Tile EXERCISE
-1. Simulating Emergency Actions Since exercises are intended to demonstrate actual capabilities as realistically as possible, participants should act as they would during a real emergency. Wherever possible, actions should be carried out. The actions that PEco will actually perform and those that will be realistically simulated are identified in Table 1.G-1, 0 2 1y, when it is not feasible to perform an action should it be simulated. Any orders given that for any reason cannot or should not actually be performed should begin with the word
" Simulate." For example, the order to put out a fire that is being hypothesized would state: " Simulate discharging the fire extinguisher."
Where such actions are being taken, it is suggested that participants inform any observers in the area of what action really would be taken had the emergency been real.
- 2. Avoiding Violation of Laws Intentional violation of laws is not justifiable during any exercise. To implement this guideline, the following actions must be taken:
- a. All evaluators and potential exercise participants must be specifically informed of the need to avoid intentional violation of all federal, state, and local laws, regulations, ordinances, statutes, and other legal restrictions. The orders of all police, sheriffs, or other authorities should be followed as would normally be the case.
1G-2
m -- J
- b. Exercise participants will not direct illegal actions beias taken
, by other exercise participants or members of the general public.
(m_ V' y
- c. Exercise participants will not intentionally take illegal actions when being called out to participate in an exercise.
Specifically, local traffic laws such as speed laws will be observed.
'3. Avoidian Personnel and Property Endannernent Participants and evaluators will be instructed to avoid endangering property (public or private), other personnel responding to the exercise, members of the general pubile, animals, and the environment.
' i 4. Actions to Minimise Public Inconvenience It is not the intent, nor is it-desirable or feasible, to effectively train or test the public respouse during the . conduct of radiological emergency exercises. Public inconvenience is to be minimized.
The actions of federal, state, and county agencies and nuclear power plant operators receive continuon public notice and scrutiny; therefore, the conduct of an exercise could arouse public concern that an actual emergency is occurring.
- 5. Maintainina Emeraency Readiness f'T During 'the performance of an exercise the ability to recognize a real l' emergency, terminate the exercise, and respond to the new situation must be maintained. Therefore, the exercise scenario and actions of participants will not include any actions which seriously degrade the condition of systems, equipment or supplies, or affect the detection, assessment, or m response capability to radiolostcal or other emergencies.
~
~
Actions'taken by the participants will also avoid actually reducing plant or public safety. The potential for creating real radiological or other emergencies will be specifically avoided.
- If a L real seersency occurs during the exercise, requiring the actions of plast, and corporate personnel, then the exercise will be terminated. All messages about real events will be clearly identified as such. For example, precede a real . message with: "This is NOT, repeat, NOT an exercise
-message."
IV. IIERGENCY RESPONSE INPI.EMENTATION AND OPERATIONS
- 1. Initial Notificatios
!aitial motification will be made in accordance with the appropriate Bestgency Plan Implementing Procedures (EPIPs).
I \e l
\ <
1G-3 i J
t
'2. Plant Operations -
7-- ( ) . ~It should'be emphasized that the exercise will in no way interrupt normal
. plant operations, production, and safety. The responses of Control Room personnel and plant operators will be simulated when taking action to combat
.the emergency. Instead, a controller will narrate the initiating events and
.the postulated plant response directly to the Shift Supervisor and other Control Room , personnel who will then employ the appropriate emergency
-procedures.
- 3. Environmental Monitorina Teams I.08 will : dispatch - field environmental monitoring teams. The controllers will provide hypothesized field data which will be used to determine
-radiation readings at preselected locations. . However, these teams will be equipped with the necessary equipment to enable them to determine actual area gamma dose rates and airborne radiciodine concentrations. The monitoring teams will not be suited up in anticontamination clothing, but will have such equipment at their. disposal.
- 4. - Public Notification Actual emergency message transmissions via the Emergency Broadcast System will not occur.
- 5. Public Information Press releases to the general public and news media will be simulated. The
( - C)s simulated press releases will contain all necessary information on - the current status of the exercise but will not be transmitted.
- 6. Communications Communications between the exercise participants will . occur in accordance with the - appropriate Emergency Plan Implementing Procedures. Should any primary communication path become inoperative or prove inadequate, backup means of communication will be utilized as appropriate.
V. CI.0SEOUT OF THE EXERCISE The exercise will be terminated by PEco and SWEC lead controllers, at their discretion, when the scenario is completed. This will occur after the plant has entered the recovery phase. 4 G 10-4
NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE s . LIMERICK GENERATING STATION TABLE IG-1 SCOPE IDENTIFICATION OF ACTUAL AND SIMULATED EVENTS ACTUAL SIMULATION
- 1. EMERGENCY CLASSIFICATION AND DETECTION o Demonstrate the ability of site personnel X to recognize an emergency initiating event and condition.
o Demonstrate the ability of site personnel X to properly classify events into an emergency class-according to the pre-established Emergency Action Levels (EALs) which includes escalation and de-escalation of the classifica-tion.
- 2. EMERGENCY RESPONSE ORGANIZATION o Demonstrate the response of the on-shift X
,s emergency organization.
I o Demonstrate the timely augmentation of the X
.on-shift emergency organization.
o Demonstrate that there are sufficient X qualified personnel to respond to the postulated events. o Demonstrate the timely augmentation of the X plant staff emergency organization by corporate support personnel. o Demonstrate that emergency personnel under- X stand and can implement their responsibilities
- 3. ENERGENCY RESPONSE SUPPORT RESOURCES o Demonstrate the ability of PECo corporate X personnel to provide support.
o Demonstrate the ability to procure assistance X
~from outside contractors and private organiza-tions, o Demonstrate the ability to request assistance X '~'n t from Federal resources.
IG-5
j C ACTUAL SIMULATION . m4 i,. 'N i c~<
] ". 3. ' EMERGENCY RESPONSE SUPPORT RESOURCES l - ,
Lo- Demonstrate;the ability to obtain assistance X
'from nuclear and other facilities, organizations or individuals identified in the LGS Emergency Plan.
'4 . EMERGENCY FACILITIES ACTIVATION o Demonstrate the ability of station and X corporate personnel to activate and staff the following emergency facilities: Operations Support Center (OSC); Technical Support Center (TSC); Emergency Operations Facility (EOF);
Headquarters Emergency Support Center (HESC) f , and Emergency News Center (ENC). y a o Demonstrate the ability to provide adequate X supplies and equipment for use by emergency e , response personnel.
. , o Demonstrate functional capabilities of equip- X im . ment in both EOF and TSC. (Functional cap-
)-
abilities may be sirnlated on real-time computer equipment.) F 5 .- NOTIFICATION AND COMMUNICATION o ' Demonstrate the notification of state and X local response organizations based on the emergency classification. .
^
o Demonstrate the effectiveness of notifica- X tion messages and verification of these messages. o Demonstrate the' ability to alert, notify, X
. < and mobilize emergency. response personnel, o Demonstrate the operation of the public X alerting system.
s-o Demonstrate the adequacy of comununications X with state / local governments during the exercise.
- o. Demonstrate the adequacy of communications X
-x with federal emergency response organizations
[ ') . including the NRC Regional Office Emergency d- Operations Centers. 1G-6 E' . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
r ACTUAL SIMULATION
~
- 5. NOTIFICATION AND COMMUNICATION o Demonstrate the adequacy of communications X between the pECo emergency facilities and field survey groups.
o Eemonstrate the adequacy of communications X with offsite fire fighting company.
- 6. ACCIDENT ASSESSMENT o Demonstrate proficiency in the assessment X of plant conditions and radiological consequences in determining appropriate actions to response and recovery from an emergency.
o Demonstrate that personnel can perform X radiological accident assessment and offsite dose projection techniques by using plant monitor readings, environmental data, and meteorological parameters, o Demonstrate the ability to effectively use X the post Accident Sampling Station. o Demonstrate the ability to perform field X monitoring within the plume exposure Emergency planning Zone. o Demonstrate the ability to estimate X integrated dose from projected and field monitored dose rates and compare these estimates with protective action guides.
- 7. RADIATION PROTECTION CONTROL o Demonstrate the ability to provide X adequate radiation protection services, such as personnel dosimetry, respiratory protection, protective clothing, and personnel monitoring (frisking) to emergency response personnel during the exercise when required (donning of protective clothing, dosimetry, and respiratory protection equipment may be simulated in certain situations).
- 7. RA!)lATION pHOTECTION CONTROL o Demonstrate the ability to provide and X monitor dosimeters for emergency workers.
10-7
ACTUAL SIMULATION Demonstrate the ability.to evaluate the X
~
x :o
.need for and provide the means for personnel f _. .
p7
' decontamination.
>o Demonstrate the ~ ability to provide X
- contamination control measures such as areas b '
' access control.
o- Demonstrate the application of onsite X
' exposure guidelines consistent with Emergency
~ Exposure Guidelines.
o- Demonstrate the ability for radiological X monitoring of people evacuated from the site
- 8. CORRECTIVE ACTIONS o= Demonstrate the ability to determine the X cause of the emergency condition, terminate the condition with consideration of appropriate engineering safeguards, and place the plant in a safe condition, i- ,
o- Demonstrate the ability of PECo personnel X
. . to' respond to.and terminate a fire.
- 9. . PROTECTIVE ACTIONS o Demonstrate the ability.to warn or X advise personnel onsite of emergency
^
conditions.
^
fo Demonstrate the ability to evacuate X nonessential personnel from the site..
~(A preselected group of onsite personnel will participate in this activity.)
o . Demonstrate the ability to provide timely X and accurate protective action recommendations
'to the state and local authorities.
O
- 10.-. MEDICAL ASSISTANCE o . Demonstrate the ability to provide first X aid and transportation for an injured individual who has been contaminated.
- 11. PUBLIC INFORMATION m
Demonstrate -the adequacy of facilities used
-p
!, o X
\ "'
for dissemination of information to the news media. 1G-8 d
ACTUAL SIMULATION A c.
, Q().
Demonstrate the ability of the PECo spokes-o X person to receive and disseminate necessary information. o Demonstrate the ability for timely exchange X of information among designated spokespersons.
;o- . Demonstrate the ability to deal with rumors X
- 12. PARALLEL.AND OTHER ACTIONS
- o. Demonstrate proper procedures for emergency X security measures, including control of access /
- egress and personnel accountability at the plant
. site.
o Demonstrate the establishment of a recovery X organization 4 o Demonstrate the capability for self-critique X and the ability to identify areas.needing improvement in order to make future appro-s priate plan and procedural changes. N x_f _
)
f-f 3
).
Q t. 1G-9
A INSTRUCTIONS FOR CONTROLLERS AND EVALUATORS NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION
- 1. Personnel are assigned ac controllers or evaluators at all key function areas to monitor - and control the exercise. In addition, they will
. accompany radiological monitoring teams, plant health physics personnel, and maintenance repair / rescue teams.
- 2. The inplant controllers will be coordinated by the Head Controller located at the Control Koom (ext. 2498). If unable to reach the Control Room, contact the Lead Controller in the TSC (ext. 2630). He will be responsible for the overall conduct of the exercise scenario.
Field controllers should contact the Lead Controller in the EOF (ext. 2604) regarding coordination problems or questions. The Lead controller at the EOF will be responsible for contacting the Lead State Controller to maintain schedules.
.3. Message forms and simulated Control Room data will be used to initiate, modify, and complete the events comprising the overall scenario.
Selected controllers will use the message forms to place the scenario events in effect and to trigger responses from the involved emergency response organizations. Each controller will have copics of the messages controlling the portion of the exercise scenario he/she is 1 responsible for. Two kinds of messages will be used: Controlling Messages used as a primary means of implementing scenario events by announcing or placing an event in effect by hypothesizing conditions resulting from previous actions. Contingency Messages used at the discretion of the controllers with the approval of the Head Controller in the Control Room in order to maintain the scenario plan continuity or schedule. Controlling messages will be presented to the designated exercise participant at the time specified in the event schedule. The controller should follow up with an explanation of the message and answer questions to ensure that the participant understands the message. Controllers will not initially provide information to the participants regarding scenario development or resolution of problem areas encountered. The participants are expected to obtain information through their own organization and exercise their own judgment in determining response actions and resolving probicas. In the event of incorrect or incomplete responses, or if the participant indicates lack of knowledge of how to proceed, the controller will prompt the IH-1 J
participant with necessary instructions or contingency cards and will note the deficiency on his/her critique sheets.
- 4. Note that the scenario events are hypothetical. Any portions of the scenario depicting plant system operational transients are sinnulated events. No Control Room actions, or reactions involving operation of plant systems or affecting generation capability, will be initiated.
All exercise scenario messages will be prefixed and suffixed with the words "THIS IS A DRILL." Controllers stationed at areas vital to maintaining generating capability should be especially aware and take extta precautions in issuing messages or giving instructions regarding the scenario events.
- 5. Required controllers will have the time-related plant and radiological parameters of the exercise scenario. This information should be issued upon request to the appropriate exercise participants by either the .
Control Room controller or controllers accompanying the radiological ronitoring field teams.
- 6. Some exercise participants may insist that certain parts of the scenario are unrealistic. The controllers and evaluators have the authority, with the approval f rom the Lead controllers, to clarify any questions regarding scenario content. In some cases, it may be necessary to exercise " controller's prerogative" or "this is due to exercise requirements" to preserve the continuity and objectives of the exercise.
- 7. Prior to commencement, all teleconsnunications should be tested to ensure satisfactory communications between the Icad controllers and all other controllers.
- 8. All et ntrollers and evaluators will synchronize their watches to ensure that messages are delivered at the proper time. Times on messaacs are set relative to the beginning of the exercise, with delivery of the first message of "7 + 0:00".
- 9. Controllers will commence their assignments at assembly locations for players that they are to observe or as directed by the Lead Controllers. (See Controller Assignment, Part B.)
- 10. Scenario equipment problema not covered in the Exercise Events section of this manual will be handled by the controllers in the Control Room,
- 11. Players are not allowed to introduce items project free play into the k exercise or its scenario.
- 12. He sure to return all exercise books to the Lead Controller.
i 13. Lunches will be provided by PECO however, there are no such lunch j breaks in the exercise. Players and controllers shall be relieved for lunch as situation permits. Emergency team leaders should decide when team members may take a lunch break.
- 14. Be sure to have a hero hat with you when entering the plant.
1 11 - 2 L
i i CONTROLLER'S AND EVALUATOR'S RULES } D0s
- 1. Know the overall Controller's Organization (Part B).
- 2. Remember that there are two clocks: a scenario time and a clock time.
- 3. Identify the players by name and function.
- 4. Identify yourself at all times to all players. Wear T-shirts or tags as provided by PECO.
- 5. Identify the phone (or radio for field teams) you will use to maintain communications with lead controllers.
- 6. Position yourself in order to m4ximize your effectiveness in issuing messages and observing the players.
- 7. Be sure you understand the player's scenario script and the master scenario.
- 8. Keep the play on schedule by checking your script.
- 9. Issue the message on time. Make sure the players understand it.
- 10. Remember to call the Lead Controller or Head Controller to report on status of players actions if off schedule or if in doubt about what to do. Call for advice if players depart signicantly from the scenario script which will create a major delay. If necessary, intervene with player action and put players back on scenario track.
- 11. Allow the players reasonablei flexibility to do their functions and demonstrate their skill, knowledge, and initiative.
- 12. Identify the federal evaluators (s). Make sure they are reasonably aware of all your actions and those of the players.
- 13. Make notes on good and had points of players' actions, the strtngths and weaknesses, and areas for improvements. Use the Evaluatorn's Critique Sheets.
- 14. Attend the post-exercise critique session to provide your comments and
, recommendations to the Chief Controller on what happened, l') . Identify the players' icaders. Work with them as appropriate.
- 16. If a real coergency occurs and this af fects the players, call of f your ponton of the exercise, and notify (later) immediately.
- 17. He at your post at 1 cast 20 minutes prior to any player action i commentroent, fict yourself up, lit = 3
- 18. The federal evaluators will not issue " surprise" messages or direct
. f -~.
" surprise" actions at the players. They must work through the 9;
i, controller. This is essential for the success of the exercise.
- 19. Controllers and federal evaluators do not have to follow the radiation exposure control practices for the simulated radiation levels from the emergency exercise scenario. However, the players must follow the radiation protection rules. Controllers and evaluators will be exempt from accountability end have access to all areas.
DON'Ts
- 1. Don't leave your post at key times.
- 2. . Don't prompt the players to take action.
c .3. Don't coach the players.
- 4. Don't criticize the players' actions during the play.
- 5. Don't forget to call the lead controllers to seek advice or help as necessary.
- 6. Don't allow the media /other. external influences to distract the players. No interviews with players are allowed.
[]
' I
- 7. Don't allow free play to be interjected into the exercise scenario.
%/
- 8. Don't allow simulation when equipment and facilities are available except for causing flow discharge of fire extinguishers, etc.
+
4 k s s N. %; . o ' ' s
%_ g a #'*
+
_, 3 ' 1,- ws ., _ s',
*%. y t j.[
'* '} 3 , . A + 4N \,
g3 , .. ,q . ~ s I l e+. . .L / O G . s 4 '< " > ' Q ', .
,Lj. " ~;NT 3 -
m, q, pgv - s
, ,. ; . % N- .
*k *
# t g . [. <, $
,- , .- - n ,
, A A T h% , A 4 -
.iw 5h:
l
SUMMARY
OF EXERCISE SCENARIO I
^ I NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE (Y' , -LIMERICK GENERATING STATION l
v' Unit.1 'is : operating.- at full power and has accumulated eight full power
- D r.anths fof ; operation since the previous refueling. At that time, 15 fuel
' assemblies of a new design were installed so that they_ could be qualified under : c.ommercial operating conditions. The 15 fuel assemblies represent i
~a bout 2'per:ent-of~the fuel in the core. All power generation equipment is
, operating, and all safety system equipment is operable. ;
'At 1105, fire is reported at the instrument air compressor 1AK101. Offsite assistance is _ required: since the fire is spreading and threatens the nearby (lubeoilstoragetanks- The fire is reported extinguished at 1145.
- e UNUSUAL EVENT should be dech. red ***
Fire l
- A spurious ."High Steam Flow" alarm causes isolation valves in two inain cteam
. lines - to trip shut. The. resulting transient causes isolation of the other main steam lines, due to . high steam flow, and reactor scram. The spurious
; alarm ' occurs at 1315. !
*** UNUSUAL EVENT should be-declared ***
Unplanned reactor scram w 4 2The thermal / mechanical transient resulting from the unbalanced isolation of the main steam lines and . reactor scram caused damage to the 15 new design
-/ t
([ fuellassemblies. Pins holding fuel rods:in the upper and lower tie plates
. shattered, and . fuel rod spacers became dislodged. The mechanical damage to
~
the fuel is not an immediate cause of increased primary system activity, but
-it:has resulted in .significant loss of cooling flow paths at both lower and upper. ends of the assemblies and the fuel begins heating up. The transient, y
- Lwith peak pressure of 1170 psig, also causes reactor ' vessel head seal ileakage : and cracks ~in the piping of several safety / relief valves (SRV)
, fdischarge_ lines at the point that they enter the drywell floor. The reactor
-vessel head seal leakage will cause pressurization of the drywell if reactor
; pressure is maintained,~ while the cracks . in the SRV discharge piping will
.cause pressurization of the drywell if reactor pressure is reduced. At
.approximately 1345,. reactor depressurization is begun. l By 1400, drywell'. pressure.has reached 2.4 psig and radiation levels are 2.0
_R/hr. Reactor coolant and drywell atmosphere samples indicate that nearly g m - alli the . radioactivity . is Xenon'.~ and Krypton. RHR A and-B pumps are lined up [for suppression pool cooling mode.
. At ~ 1430, ' the control room is notified that an assistant plant operator has
" been found, unconscious - and bleeding from a head laceration. He was on routine inspection of the radwaste enclosure and was found lying in a puddle thatL . appears . to be leakage from the fuel' pool holding pump (00P340).
rDrywell radiation' level' has increased to .14 R/hr at 1500 and reaches 100 1R/hr ati1600. Sample analysis continues to indicate primarily noble gases f f N- -in the drywell atmosphere. . _\]' 2A-1 w 4 wMtr ,
4
;r
~
***' ALERT should be declared ***
-Containment radiation monitor reading exceeds 100 R/hr 4! ):
J At 1615, it. is. noted . that the discharge flow of RHR pump B has started decreasing. Personnel are sent to investigate the cause. At 1630, airborne radiation ' levels - in . the 1 secondary . containment rise significantly due to l'^ '
. leakage from . the primary containment. Evacuation of the Unit I reactor building is ordered.. Contact is lost with the personnel investigating the RHR pump problem, and a search is begun.
By(1700, reactor coolant activity indicates more than 300 pCi/gm of I-131 l equivalent and . drywell' radiation . level is 400 R/hr. Drywell pressure is leveling off at 4.5 psig. HPCI and RCIC have been secured, and the vessel is being filled with available LPCI.and core spray pumps. tat 1715, the CO 2 Portion of . the fire protection system is declared in- l
- operable due to' decreasing tank pressure. A fire watch should be
' implemented'until the-system is restored. Alarms. sound at 1730 indicating a fire in the East .RHR ' heat exchanger room on el 177 f t-0 in. Reports are l
< < ; received that 'the -fire has disabled both RHR.B&D pump motors. Cause of the
; fire is unknown ~, but it is fueled by scaffolding material brought there in preparation for .. an inspection of . the. RHR heat exchangers.
Station fire
' fighters are able to extinguish.the fire.
At 1730,fdrywell radiation level'has reached 1,000 R/hr. l T i.1 *** SITE EMERGENCY should be declared *** [j '(Containment radiation monitor reading exceeds 1,000 R/hr.)
~
e ; At? 1800, . the Standby. Gas Treatment System (SGTS) effluent monitors detect l
' ^
- , - radioactive ' releases. . Subsequent analyses of SGTS exhaust samples indicate -
~
, releases are . approximately . 0.1 Ci/second of noble gases. Meteorological
. conditions - are not - expected to change significantly for 12 to 24 hours.
Wind is from the South Southeast (158') at 3 mph. Reactort pressure is nearf 30. psig at'1830. : Containment radiation level is snow 2,000~R/hr, and drywell; pressure is approximately 4 psig. The control-f, M' ' room is .- notified that the result of the 1830 sample of the ' cooling tower P' l blowdown-is 7N6 pCi/cc. Samples taken at 1815 and 1845 were both negative. g At 1845, status . lights on .the control board indicate the containment purge Eisolation valve :(HV-57-114) has backed off the fully-closed position. The
! valve 1 does ( not : respond - to . controls. At :1900, radioactive releases have
@w : increased :to levels corresponding to site boundary-whole- body dose rate of l 2: mrem /hr and' thyroid dose . rate of7 4 mrem /hr. l Although there is as yet no
. confirming . indication' in the control. room, the release is coming from
' leakage pass the closed isolation valve'(HV-57-115) on the containment purge
'line. 'Drywell-radiation level has increased t'o 4000 R/hr.
I r 1 g
,4
^L/
O' 2A-2' w
-. -r u .__.
'At 1915, status lights indicate that the containment purge line isolation valve - (HV-57-115) is unseated and it also fails to respond to controls. l
- 1 Effluent releases increase rapidly, and ventilation exhaust monitors exceed
,j. : the General. Emergency Action Level by 1930 hours. Drywell radiation level reaches 10,000 R/hr.
*** GENERAL EMERGENCY should be declared ***
-Potential or actual effluent releases correspond to 5 rem /hr thyroid or containment monitor reading exceeds 10,000 R/hr
~ Personnel in the . reactor building report that it will require 10 hours to terminate the release from the containment purge line. At 1945, radioactive
- releases level off at values corresponding to offsite whole body and thyroid
- dose rates of 800 mrem /hr and 11,000 mrem /hr, respectively. Wind speed has increased to 4 mph but continues from the South Southeast.
l
. At 2040, CS pump A trips. CS pumps B and D are manually initiated. CS pump l
- C is tripped. Personnel are dispatched to diagnose the problem.
At 2145, the release is terminated by repair of the containment purge line valves. De-escalation of the emergency to SITE EMERGENCY and later to ALERT l status is now feasible. At 2145, the exercise will be terminated after the plant has demonstrated recovery. [T
\
a
)
.m.
fY : Q ,I 2A-3 L
- .o
%- a y '. '_
.e- -
DETAILED SCENARIO FOR UNIT 1
](]:'
/3
, NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK. GENERATING STATION
. July 25, 1984
- Initial Conditions
~
, Unit'.1(is operating'at full power and has accumulated 8 full power months of
. operation since the. previous _ refueling. At that _ time,15 fuel assemblies of 7- .a new design were installed so that they could be qualified under commercial g;- operating 1 conditions . The 15, fuel assemblies represent about 2 percent of
;the: fuel in~the core. -OnLt'wo occasions in the past three months, Unit I has Z, -
experienced :- reactor - trips caused by spurious main steam isolation valve 7 < 1(MSIV) y closure signals. -All power generation equipment is operating, and _ _ all; safety ' system equipment is operable.
- Thel initial plant and reactor: system values are shown in Table 1.
A ~ i }TherMeteorological; conditions at:1100 are characterized by the influence of l r M J an ' t almost - stationary ,high pressure area. centered over Greenwich,
' Connecticut. The -clockwise-' flow around its center is evident by the
'following-ground level' Limerick Generating Station Met tower data:
- Wind direction-
,- Southeast (137 degrees)
, ; : Wind: speed. .5.2 mph
- 1. . . Temperature 71*F
_/Sp - Delta Temperature -1.3*F fj, , Sigma. Theta- 6.7 degrees. azimuth The National Weather Service indicates = that the high is expected to slowly ,
- drift- to.'the ! south during the' next .12 to 24 hours. Skies will remain sunny
~
. . _' 'with light': winds gradually backing to the South Southeast.
2: ~
~
4 + 1
+ F-
'] w-
~
I ,k '[ s ~!1 ~ e
," L
~
I L _g, $ v& gm ;F -
- " s p., C i'
.;ign = Ngl. e
/ \
.,-r e.-
~
, , '2B ,
. 's ~
;. u:'.
9 " .6 r 'l __
-1100L 'Reacto'r power is 100 percent, reactor pressure and water level are
~1 020 psig -and +35.in., respectively. Drywell pressare and "n temperature are 0.6 psig and 130 F, respectively.
j 1105 Control room is notified of a fire in the turbine enclosure at el 217 ft-0 in. Instrument air cc,mpressor 1AK101 is on fire.
.Offsite assistance is required since the fire is spreading and threatens the nearby-lube oil storage tank.
***UNU:iUAL EVENT should be declared ***
. EP-101-5 Fire: Fire in ' protected area lasting 10 minutes or more
- after initial attempts to extinguish it as indicated by observa-tion or fire alarm on OA(B)C850.
,e '.1145- -The control room is notified that the fire in the turbine enclosure is extinguished.
g 1200' Reactor continues to operate at full power.
- 1315- A~ spurious high steam flow signal causes main steam isolation l
valves _(MSIV) HV-41-1F028A and C to shut. The remaining'MSIVs close due to high steam flow. The reactor scrams.
.f ~
The reactor' pressure increases to 1,170 psig. j.
- Three groups of safety relief valves (SRVs) open.
.The reactor water level decreases.
- *** UNUSUAL EVENT should be declared ***
EP-101-12 Unusual. Shutdown: Shutdown other than' normal controlled shutdown and for the . purpose of placing the plant in a safer condition.
- 1316 The - reactor pressure. and water level decreased to 1,050 psig and
-38'in., respectively. The SRVs have closed except for two SRVs
'which the operator has kept open in order to control pressure.
-HPCI and RCIC systems are initiated on low-low water level.
y9
. Standby gas treatment system (SGTS) is initiated.
1317- The reactor pressure has. decreased to 1,040 psig.
-Reactor water level has decreased to -40 in.
' Drywell pressure and temperature begin to increase due to reactor vessel head seal-leakage and cracks in SRV discharge lines. The reactor water . level begins to increase due to HPCI and RCIC v a injection.
]
x./ 2B-2 L_
v E
. ' 1325 l. Reactor ' pressure and water level are 1,025 psig and +50 in.,
f~j respectively. Drywell pressure has increased to 1.5 psig which l
-- y t: results in a high drywell pressure alarm in the control room.
HPCI pump .is manually operated for pressure level control.
'Drywell pressure h'as increased to 1.68 psig.
.-1330 l
. Containment group isolations occur.
1
- HPCI is initiated in injection mode and trips at +54 in. Once the highLlevel signal clears, HPCI is initiated and operated for
. pressure / level control.
1345j heactor ~ pressure and water- level are 1,000 psig and +50 in.,
-respectively. l
- Containment radiation level is 1 R/hr.
_ Depressurization of the reactor using SRVs is begun.
',' .1400- ' Reactor pressure .- and water level are 860 psig and +50 in.,
~ respectively. l Drywell pressure is 2.4 psig.
~
Containment; radiation level is 2 R/h"r.
. p,
- ,1 %
', !?, ~ Reactor. coolant and drywell samples indicate that nearly all the
". *- radioactivity is Xenon and Krypton.
' RHR A and B . pumps are ' lined up for suppression pool cooling mode.
~ '
- The : wind ' speed ' has decreased to ~ 4.8 ' mph. the wind direction is
- , from the Southeast (145: degrees).
n.
~
1430 : Reactor pressure is 670 psig. l lt . .
,-d;3; (Reactor water level is being maintained at +50 in.
- g ,
e1F '
- 1430: The / control - room : is ' notified of a . contaminated injury in the 'l
. Tradwaste' enclosure.
s
.1500'. '.Cooldown and depressurization of.the reactor' continues. l mga;;#2 e=z . x~ ;.
- 2 Reactor pressure is 560 psig.
n
- i . EDrywell pressure,is 4.0 psig.
jL -
,.}
jDrywell'radiationlevelhasincreasedto-14R/hr. 1545. ) Reactor pressure is 440 psig. Core spray (CS) and RHR in the LPCI
, .; node are initiated.-
l .f w - -
~
2B t. b9 hf?F$.L. '.
t w
+
i' 1548 - RHR - A and B pumps are returned t'o suppression pool cooling mode. l ( / ~ 1600/ -Drywell radiation level has increased to 100 R/hr. Sample I analysis reveal primarily noble gases in the -drywell atmosphere.
~
*** ALERT should be declared ***
EP-101-8 Damage of Fuel: Containment post-LOCA radiation monitor greater.than 100 R/hr. 1615 RHR f pump B flow decreased to 500 g;m. Personnu are sent to
. investigate _the _cause. Reactor pressure and water level are l
380 psig sad +50 in., respectively.
' 1630- The control room is notified that the airborne radiation levels in !
the' reactor enclosure have risen significantly and exceed 10 MPC. The-;high airborne radiation levels are due to small leakage from the primary containment. Evacuation of the Unit I reactor enclosure is ordered.
- The wind speed has decreased to 4.1 mph. The wind direction is from the South Southeast (151 degrees) 1650 - The control room is notified that the person investigating RHR pump-B is unaccounted for. A search is begun. l
' T] -
i 1700 Reactor pressure is 300 psig. g Drywell pressure is leveling off at 4.5 psig. . Drywell radiation level is 400 R/hr. Reactor- coolant- activity sample results indicate more than 300 uCi/gm of I-131. RCIC and HPCI pumps are manuall'y tripped. Reactor vessel is flooded with CS and LPCI.
. 1715. A low pressure alarm from the CO2 storage. unit 00S133 is received. l
- 1730 The control room is not'ified that the CO2 portion of the fire l protection ' system -is inoperable due to low tanx pressure. A y
continuous fire watch is established for those areas in which
+ >
' redundant systems or components could be damaged.
1730 Annunciator alarm on the fire protection panel in the control room l is received. The alarm indicates that the. fire is located in the RHR heat ' exchanger and pump room at el 177 ft. RHR pump B trips. Control room is notified that the fire has disabled the motors for both RHR pumps B and D. Cause of the fire is unknown, but it is
/ fueled by s'caffolding material brought there in preparation for an
' 'i ]f
'%/
2B.-4
"r) ' +'
d N, . _ inspection.of the RHR heat _exchangers. Offsite assistance is not f~N , ' required - to ' ext.inguish' the fire,
- f, nL .
7 . Drywell radiation level reaches 1,000 R/hr.
' ^
*** SITE EMERGENCY should be declared ***
i p JEP-101-8-Damage'of Fuel: Containment post-LOCA radiation monitors J . greater than.1,000 R/hr. _ _.1755' ' LPCI' is tripped once the reactor vessel is flooded. l
~
~ Coo 1down:;is ; continued by circulating reactor vessel inventory through the~ SRVs lto the suppression pool using available CS pumps.
"1800 SGTS effluent monitor detects radioactive release concentration of
. .0.01 pCi/cc. _ Subsequent analyses of SGTS exhaust samples indicate
' releases are: approximately 0.llCi/second of Noble gases. The wind
!~ zis from- .the . South . Southeast (158 degrees) at 3 mph.
Meteorological conditions are not expected to change significantly for 12 to 24 hours.
- Reactor pressure is 30 psig.
~
1830
. Containment drywell' radiation level is_2,000 R/hr. ,' - l Drywell pres'sure is 4 psig.
ya. - J! ): 1845: Status. lights Lon 'the control board indicate. the containment l M isolation D valve' .HV-57-114 in the containment purge system has
~
backed 'off- the fully ' closed position. Repeated attempts to close
'the' valve are unsuccessful.
' ~ '
.1900 _ Drywellj pressure is 3'.8 psig. Reactor enclosure . local radiation' l
-levels in the.-area of. the ' containment purge system line are increasing.
4 iThe control room is' notified that the result of the 1830 sample of
- ' s .the cooling' tower blowdown'is 7N6 'pci/cc.
Samples taken at 1815 Land'1845 were both-negative. Analysis of.1830L sample = indicates that at least 60 percent of the
~
- activity _is Technetium-99M.
g &, . , y . -- o m Radioactive , releases have ; increased to levels corresponding to , Qf site 9 boundary-whole body dose rate of 2 mrem /hr ' and thyroid dose - rate n- of;._4' mrem /hr. 'The releases are due to leakage: pass the
.;r '
closed tisolation valve ' HV-57-115 in the containment purge line
~ ] although there is no indication in.the control' room.
f h
^
x
-m -
2B-5
)
4
' R- % 7 m' 3 )
f: . 1915' Status' lights on the control board indicate that the outboard l 4 containment purge line isolation valve HV-57-115 is unseated.
'w) -
Repeated _ attempts to close the valve are unsuccessful. Effluent releases increase rapidly.
' Personnel investigating the purge valves report that it will require 10 hours to terminate the release.
1930. " North stack effluent radiation monitor indicates 10 uCi/cc. !
. Radiation releases correspond _ to offsite whole body and thyroid dose rates of 800 mrem /hr and 11,000 mrem /hr, respectively.
Drywell radiation level reaches 10,000 R/hr.
'*** GENERAL EMERGENCY should be declared ***
a EP-101-6 Radioactive Release: Projected thyroid dose greater than 5 rem at the site boundary o_r EP-101-8 ~ Damaged Fuel: Containment post-LOCA radiation monitor greater than 10,000 R/hr. 1945 - The wind speed increased to 4.0 mph. The wind direction remains j from the South Southeast. 2000 . North stack effluent radiation monitor indicates 10 uCi/cc. Drywell pressure is 3.2 psig. 2040' - CS pump A trips. CS pumps - B and D are manually initiated. CS l pump C is tripped. Drywell radiation levels off at 1.8 x 104 R/hr. 2115 Drywell pressure- is 2.5 psig. Drywell ' radiation level is ! 18,000 R/hr. Personnel investigating the seizure of CS pump A report that they have encountered high radiation fields and it will be some time before they can enter the area. 2130 -Drywell pressure is 2.3 psig. Drywell radiation level is
-17,000 R/hr. North stack effluent ~ radiation monitor indicates 10 uCi/cc.
.2145 The containment purge line valve HV-57-115 is repaired. Releases !
to the atmosphere are terminated. Deescalation ' of emergency to SITE EMERGENCY and later to ALERT
,, status is now feasible.
2230 Exercise is terminated after the plant has demonstrated recovery. l
, y(
2B-6 i Y
/% ' ~ ~N %
\w/ ) ,- \ ) \ l
.a v TABLE 1
; Limerick' Generating Station Initial Plant and Reactor System Values Reactor' Level '+35 1 inches Drywell Press a i psig Reactor Pressure 1020 psig Drywell Atmos Temp. inn ' F Reactor Power
~
100 '% Full Power Supp Pool Press 0.6 psig Core Plate DP 100 1% Full Power Supp Pool Temp 90 *F Core Flow '100 lb/hr x 10 8 Supp Pool Level 22.1 feet Total Steam Flow' 14 lb/hr x,10 8 Main Stm Line Rad Hon 1100 mR/hr Total Feedwater Flow 14 lb/hr x 10 6 Containment Rad Level 2 R/hr Condenser Vacuum 9a inches Hg Cond Stor Tank Level 38 feet Hotwell Level 4n inches RCIC Flow 0.8Pm
?CRDChargingPressure a psig HPCI Flow 0 8Pm
" Inst. Gas to ADS Pressure 110 psig RHR A Flow n 8Ps Equip. Drain Coll Tank Level 3 feet RHR B Flow n 8Pm Equip. Drain Surge Tank Level 3 feet RHR C Flow n gpm Floor Drain Coll Tank Level 4 feet RHR D Flow 0 ' gpm Floor Drain Surge Tank Level 3 feet Core Spray A Flow 0 gpm
'll2Concentration 0% Core Spray B Flow 0 gpm 0 2 Concentration 2,8 % RHR Hx Outlet Temp 80 *F SGTS Flow 0 cfm RHR SW Inlet Temp 80 *F North Vent Stack Concentration SN6 pCi/cc North Vent Stack Release Rate 7P2 pCi/sec L
. a
,- , ,,-n -
,/ ,
-(Q,) .\
- i )
%) NJ
.SIGNIFICANT EVENTS TIME LINE'
.NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LINERICK GENERATING STATION Emergency Classification Time Scenario Event Expected Actions None 1100 Initial-Conditions
- Unit I at Full Power.
- All power generation equipment operating
*. All safety systems operable
- Heteorological conditions
- Stable
- Wind velocity 5.2 mph from 137* (Southeast)
None 1100 Exercise Starts l UNUSUAL EVENT 1105 Fire is discovered at instrument air compressor 1AK101 which threatens l Lube Oil Storage Tank
- Fire Fighting Group responds to fire
- Offsite fire assistance is required
- Local fire company responds
- Unusual Event should be declared
- Internal Notification .
- Offsite Agencies Notified UNUSUAL EVENT 1145 Fire is reported extinguished 1
2C-1 C
7- ~~
- \
SIGNIFICANT EVENT E LINE (C ut)
'~
Emerg ::cy Classification Time Scenario Event Expected Actions UNUSUAL EVENT 1315 Reactor scrams on spurious Main l Steam Isolation Valve (MSIV) closure signal
- Reactor operators follow
- Safety Relief Valves standard operating procedures (SRVs) open and emergency procedures
- Reactor level decreases
- Unusual Event Declared
- Standby Gas Treatment-
- Internal notification System (SGTS) initated
- Offsite agencies notified UNUSUAL EVENT 1330 Drywell "lli-Pressure" setpoint i of 1.68 psig is exceeded I
- Containment group isolation
- Isolation valves on instrument occur nitrogen lines opened to reestablish manual control of SRVs.
- IIPCI placed on manual control
- Operators attempt to stop leakage by backseating of valves UNUSUAL EVENT 1345 Drywell pressure increase continues
- Depressurization of reactor l using SRVs is begun UNUSUAL EVENT 1400 Reactor coolant and drywell samples l
indicate that nearly all radio-activity is Xenon and Krypton UNUSUAL EVENT 1430 Worker is injured and radioactively
- Search and Rescue /First Aid l contaminated in the Radwaste Group dispatched Enclosure
- Emergency medical First Aid administered
- Personnel contamination survey performed
- Personnel decontamination per fo rmed
- Offsite medical assistance requested from hospital 2C-2
7_
,, ; . .w ..
~
')
SIGNIFICANT. EVENTS; f3 LINE'(Cont)
)
,/ . % Q J:
Emerg:ncy Classification Time Scenario Event ' Expected Actions-ALERT 1600 Drywell Radiation Level has , increased to 100 R/hr
- Alert should be declared
- Offsite notification-
- Internal notification
* . Technical Support Center activated
- Operations Support Center-activated .
- Offsite emergency teams placed on standby
- State and County EOCs partially activated ALERT 1615 RIIR pump B flow decreases to
- Personnel dispatched to
, l 500 gpm investigate cause of reduced flow ALERT 1630 Control room is notified that g significant airborne activity levels are detected in the reactor enclosure
- Local evacuation of reactor enclosure ordered ALERT 1650 Contact is lost with personnel investigating RIIR pump B
- Search and Rescue /First Aid ..
Group dispatched to find missing person. ALERT 1700 Reactor coolant sample indicates
- The Search and Rescue /First activity of more than 300pCi/gm Aid Group finds the person of I-131 equivalent and escorts the individual out of the affected area.
- The individual is not injured or contaminated.
ALERT 1715 Low pressure alarm from~ CO2 sto rage
- Personnel are sent to tank of the Fire Protection System investigate CO2 portion of fire protection system 2C-3 b
a _./*K
# sc-
'( Jl SIGNIFICANT.EVENTSi Q) -
7,LINE~(C:nt)- [, ;
.q)
Emerge:cy
- Classification. Time Scenario Event Expected Actiona .
1
~
.I
-ALERT' '1730. Alarm indicates that there is a.
fire'in the RHR heat exchanger and pump room: * . Fire Fighting Group responds to fire and: extinguishes it SITE EMERGENCY 1730' Drywell radiation' level has Site Emergency should be .l increased to 1000 R/hr'
- declared
- Notification of offsite agencies-
- Emergency Operations Facility activated
- Headquarters Emergency Support Center activated
- News Media Center activated
- Field survey groups deployed
*- State and Local EOCs fully activated SITE EMERGENCY 1800 North Stack efflueht monitors detect radioactive concentrations of 0.01 pCi/cc
- Dose assessment team should conclude that no protective action required SITE EMERGENCY 1845 Status lights on control board indicate 1 of 2 isolation valves l on containment purge line has backed off fully-closed position *, Plant personnel will attempt to get the valve closed SITE ENERGENCY 1900 Local radiation levels near the containment purge line are increasing s
2C-4 C
r , ( SIGNIFICANT EVENT LINE (C.it) Emergency Classification Time Scenario Event Expected Actions SITE EMERGENCY 1900 High radioactivity in cooling
- Dose assessment per EP-318 tower blowdown reported and EP-319 l
- Continue sampling of blowdown
- Perform notification in accordance with EP-312 SITE EMERGENCY 1915 Status lights indicate that 2nd isolation valve on containment purge line is unseated
- Personnel checking isolation l valves estimate 10 hours to repair GENERAL EMERGENCY 1930 Drywell radiation level reaches
- General Emergency should be l 10,000 R/hr declared
- Offsite notification of North stack effluent radiation agencies monitor indicates 10 pCi/cc
- Dose projections should continue
- Field surveys continue and confirm that site boundary doses are 200 mrem /hr whole body and 4,000 mrem /hr thyroid GENERAL ENERGENCY 1945 Radioactive releases continue
- PECo recommends evacuation of l nearby residents GENERAL EMERGENCY 2000 Radioactive releases continue
- State recommends protective l action of evacuation GENERAL EMERGENCY 2015 Radioactive releases continue
- Public alert sirens are l sounded GENERAL EMERGENCY 2040 Core Spray pump A trips
- Personnel are sent to l
investigate
- Core Spray pump manually tripped
- Core Spray pumps B and D started 2C-5
/
n SIGNIFICANT EVENT LINE'(Crnt) [ r,
'l Emergency -Classification ; Time- Scenario Event Expected Actions GENERAL EMERGENCY 2145 Containment purge line isolation e' Field survey groups to valves _are. repaired confirm that releases have' stopped Radioactive releases ended
- Deescalation to Site Emergency.
and later to Alert is considered 2230 Exercise Terminated 2C-6 m
a NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
.J .
LIHERICK GENERATING STATION Reactor Coolant Activity Concentrations (pci/gn)
~
7
'Y ; :Kr-85 'Kr-85M 'Kt-87 Kr-88 Xe-133 Xe-135 Total I-131 I-133 Total. Gross
. -/ Noble Iodine Beta Gas
.1100-1330' *4.N2 8.N1- 6.N4: 2. 4. 4. **1.P2 5.N3 1.N1 8.N1 1. 6P?.
1330-1400- : 1.5 - 3'.P1 '2.PI' 6.P1 2.P2 1.2P2 8.P2 2.N2 3.N1 1.5 1.P3
. 1400-1430- 3. 6.Pl. 3.P1 1.2P2 2.5P2' 2.P2 2.P3- 6.N2 5.N1 2. 2.P3 S1430-1500 1.P1 -2.P2 , 1.2P2 5.P2 '1.P3 1.P3 6.P3 2.N1 1.0 4. 6.P3 11500-1530 2.P1 4.P2 2.P2 9.P2 2.P3 2.P3 1.P4 8.N1 3.5 10. 8.P3 1530-1600 2.8P1. G.P2 3.P2 1.4P3 3.P3 3.P3 1.4P4 2.2 9. 3.P1 1.P4 1600-1630 4.P1 8.P2 4.P2 1.8P3 4.P3 4.P3 1.8P4 2.5P1 1.P2 2.5P2 1.P4 1630-1700 4. PI - 8.P2. 4.P2 1.9P3 4.P3 4.P3- 1.8P4 9.P1 3.5P2 8.P2 1.P4 1700-1715 4.P1 8.P2 4.P2 2.P3 4.P3 4.P3 1.8P4 2.5P2 1.P3 2.P3 9.P3 1715-1730 4.P1 9.P2 3.7P2 2.P3 4.P3 4.P3 1.6P4 6.P2 2.5P3 5.P3 8.P3
.'1730-1745 14.P1 9.P2 3.P2 2.P3 4.P3 4'.P3 1.6P4 8.P2 3.P3 6.P3 8.P3 A
i 1745-1800 ~4.2P1 -9.P2. 2.7P2 2.P3 '4.2P3 4.P3 1.5P4 9.P2 3.5P3 7.P3 7.P3 AJ
-1800-1830- 4.5P1 9.P2 2.5P2 2.P3 4.2P3 4.P3 1.5P4 9.P2 3.5P3 7.P3 7.P3
.1830-1900 4.8P1 .1.P3 2.P2 2.P3 4.5P3 4.P3 1.5P4 9.P2 3.6P3 7.P3 6.P3
'1900-1915- 5.P1 1.P3 2.P2 1.8P3 4.5P3 4.P3 1.4P4 9.P2 3.6P3 6.P3 6.P3 1915-1930 5.P1 ~ 1.P3 2.P2 1.8P3 4.5P3 4.2P3 1.4P4 9.P2 3.5P3 6.P3 5.P3
.S.
11930-2000 15.P1 '1.P3 1.8P2 1.7P3 4.5P3 4.2P3 1.4P4 8.P2 3.P3 5.P3 5.P3 2000-20301 -5.P1 1.P3 1.7P2 1.5P3 5.P3 4.2P3 1.2P4 8.P2 3.P3 5.P3 5.P3 2030-2045 5.P1 9.P2: l'.6P2 1.5P3 -5.P3 4.2P3 1.2P4 8.P2 3.P3 5.P3 5.P3 2045-2100 .5.P1 9.P2 1.5P2 1.3P3 5.P3 4.5P3 1.2P4 8.P2 3.P3 5.P3 5.P3 2100-2145, 5.P1. 8.P2- 1.3P2 1.2P3 5.P3 4.5P3 1.2P4 7.P2 3.P3 5.P3 4.P3
*4.N2'= 4 x 10 -2
~
~**1.P2 = 1 x 10 2-
~;[
).
3A-1 d m _
e-NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIHERICK GENERATING STATION Drywell and Suppression Chambers Air Concentrations (pCi/gm) 7 . Gross Kr-85H Kr-87 Kr-88 Xe-133 Xe-135 Total I-131 I-133 Total i
' l- Kr-85 '
' ~ ' -
' Noble Iodine Beta Gas
'2.N5 5.N5 1.N4 1.N4 2.N3 2.N8 3.N9 2.N7 4.N3
- 1100-1330 *1.N6 2.N5 1330-1400 2.N4 4.N3 3.N6 1.N2 2.N2 2.N2 5.N1 6.N8 1.5N7 8.N7 8.N1 1.N2 ,3.N2 1.N1 6.N2 4.N1 1.5N7 6.N7 3.N6 5.N1 1400-1430- 8.N4 1.5N2 1.5N2 6.N2 1.5N1 1.2N1 1. 5.N7 2.N6 7.N6 1.
1430-1500 1.5N3 3.N2
'5.N3 1.N1 6.N2 2.5N1 5.N1 5.N1 3. 5.N7 2.N6 6.N6 3.
1500-1530 2.N1 1.N1 4.5N1 1. 1. 5. 3.N6 1.N5 3.N5 4. 1530-1600 1.N2 1.4N2 3.N1 1.5N1 7.N1 3. 1.5 7. 7.N6 3.NS 8.N5 5.
~ 1600-1630 4.N2 8.N1 4.N1 2. 8. 4. 2.P1 1.N4 4.N4 8.N4 **1.P1 1630-1700 1700-1715 1.N1 -2. 1. 5. 2.P1 6. 3.P1 3.N4 1.2N3 2.N3 2.P1
- 2. 1. 5. 2.P1 1.P1 5.P1 7.N3 3.N2 6.N2 2.P1
- 1715-1730 1.N1
- 4. 1.6 1.P1 3.P1 2.P1 8.P1 1.5N2 6.N2 1.2N1 4.P1 1730-1745' 2.N1 1.5 1.P1 2.P1 2.P1 7.P1 2.5N2 1.N1 2.N1 3.P1 j745-1800 2.N1 4. .
. 1800-1830' -2.1N1 4.2 4. 1.P1 2.P1 2.P1 2.P2 6.N2 2.5N1 5.N1 1.5P2 4.5 4. 2.P1 4.P1 4.P1 2.P2 8.N2 3.N1 6.N1 2.P2 1830-1900 5.N1
'5.N1 1.P1 6. 2.5P1 5.P1 5.P1 3.P2 4.N1 1.6 2.5 3.P2 1900-1915
,1915-1930 2.P1 1.PI- 4.5P1 1.P2 1.P2 5.P2 1. 4. 7. 4.P2 1.
5.P1 1.P1 9.P1 1.8P2 1.8P2 5.P2 4. 1.6P1 3.P1 2.P2
'1930-2000 2.5.
1.P1 8.P1 2.P2 2.P2 6.P2 1.P1 4.P1 7.P1 2.P2
- 2000-2030 2.5 5.P1 1.P1 8.P1 2.5P2- 2.2P2 6.P2 9. 3.5P1 6.P1 2.P2 2030-2045 2.5 5.P1 4.5P1 8. 7.P1 2.5P2 2.2P2 6.P2 9. 3.5P1 6.P1 2.P2
- r. 2645-2100' 2.5
'2100-2145 2.5' 4.5P1 6. 6.P1 2.5P2 2.2P2 6.P2 9. 3.5P1 6.P1 2.P2
-6
,. *1.N6 = 1 x 10 I
**1'.P1 = 1 x 10 7~
d
-h-3A-2 i
S:y _
~NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
=a LIMERICK GENRATING STATION Suppression Pool Activity Concentrations (pCi/gm)
N.,] -,
- I-131 I-133 Total Gross Noble Beta Gas
.1100-1330 ~*S.N7 3.N8 7.N7 2.N5 1330-1400. 2.N6 4.N6 2.N5 3.N5 1400-1430 1.5N5 5.N5 7.N5 7.N5
'1430-1500 8.N5 3.N4 6.N4 6.N4
.1500-1530 4.N4 1.6N3~ 3.N3 2.5N3 1530-1600 2.N3 8.N3 1.4N2 1.N2 1600-1630 6.N3 2.5N2 4.N2 3.N2 1630-1700 1.N1 4.N1 6.N1 3.N1 1700-1715 5.N1 2. 3. 2.
1715-1730 1.5 6. 1.P1 8.
's ,,e. 1730-1745 5. 1.8P1 3.P1 2.P1 1745-1800 **1.3P1 5.P1 8.P1 6.P1 1800-1830 1.7P1 7.P1 1.P2 7.P1 1830-1900 2.0P1 8.P1 1.2P2 9.P1
.1900-1915 2.3P1 1.P2 1.4P2 1.P2 1
11915-1930 2.5P1 1.P2 1.5P2 1.P2 1930-2000 2.7P1 1.1P2 1.6P2 1.1P2 2000-h030 2.9P1 1.1P2 1.6P2 1.2P2
-2030-2045 3.1P1 1.2P2 1.7P2 1.2P2 2045-2100 3.3P1 1.3P2 1.8P2 1.3P2 2100-2145 3.5PI- 1.4P2 1.9P2 1.3P2
~7
*5.N7 = 5 x 10 m
l I *kl.3P1 = 1.3 x 10 3 V 3A-3 Y
7^ . NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION 4 ' ' Reactor Enclosure Atmosphere PASS Sample Concentrations (pCi/cc) Gross Kr-85 Kr-85R Kr-87 Kr-88 Xe-133 Xe-135Noble Total I-131 I-133 Total Iodine Beta Gas 2.0N6 ** ** ** 4.0N6
- 1100-1315 *2.0N8 1.3N7' 2.4N7 3.6N7 9.2BN7 1.8N7 1315-1800 1.7N8 3.6N7 1.0N7 7.9N7 1.5N6 1.5N6 4.3N6 1.8N10 7.2N10 9.0N10 6.N6 6.8N8 4.3N7 8.5N7 8.5N7 2.4N6 1.8N9 7.2N9 9.0N9 3.N6 1800-1900 1.2N8 -2.4N7 3.5N7 1.0N6 2.ON9 8.0N9 1.0N8 1.0N6 1900-1915 '5.0N9 9.8N8 2.8N8 1.8N7 3.5N7 V 4.9N8 1.4N7- 2.0N9 8.0N9 1.0N8 1.047 1915-1945 7.0N10 1.4N8 3.9N9 2.5N8 4.9N8 2.4N9 1.5N8 3.0N8 3.0N8 8.5N8 2.ON9 8.0N9 6.0N8 7.N8 1945-2145- 4.0N10 8.4N9 i
i
*2.0N8 = 2 x 10
**less than detectable t'./' T t
- n. =
f5 (f 3A-4 J
,m. .r.
,n m i f k._-) .-
)
~
NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION Post Accident Sampling System Readings (mR/hr) From 1100 1330 1400 1430 1500 1530 1600 1630 1700 1715 '1730 To 1330 1400 1430 1500 1530 1600 1630 1700 1715 1730 1745 System Sample Distance Shield Size Drywell 15.m1 1 inch none- - 0.3. 1.5 3. 13. 23. 50. 90._ 150. 250. 400. Atmosphere 1 ft none - - 0.02 0.03 0.15 0.25 0.5 0.9 1.5 2.5 4. 1 inch 2" lead - - 0.01 0.02 0.1 0.2 0.4 0.7' 1.2 2. 3. I ft 2" lead - - - - - 0.01 0.01 0.02 0.03 0.06 0.1 Reactor 10.m1 1 inch none 2.P3 1.6P4 4.P4 1.2P5 2.P5 3.P5 3.6P5 3.7P5 4.P5 4.2P5 4.4P5 Coolant I ft none 20. 160. 400. 1.2P3 2.P3 3.P3 3.6P3 3.7P3 4.P3 4.2P3 4.4P3 1 ft 2" lead 0.4 3. 8. 25. 40. 60. 70. 75. 80. 85. 90. I ft 4" lead 0.01 0.06 0.16 0.5 0.8 1.2 1.4 1.5 1.6 1.7 1.8 Gas Stripped 15 ml 1 inch none 1.5P3 1.2P4 3.P4 9.P4 1.5P5 2.2P5 2.7P5 3.P5 3.P5 3.P5 3.P5 From Reactor 1 ft none 15. 120. 300. 900. 1.5P3 2.2P3 2.7P3 3.P3 3.P3 3.P3 3.P3 Coolant I ft 2" lead 0.3 2.5 6.0 18. 30. 44. 55. 60. 60. 60.. 60. I ft 4" lead - 0.05 0.1 0.4 0.6 1. 1.1 1.2 1.2 1.2 1.2 Suppression 10 ml 1 inch none - - - - 0.15 0.7 2.0 30. 90. 500. 1.5P3 Pool Liquid 1 ft none - - - - - 0.01 0.02 0.3 0.9 5. 15. 1 inch 2" lead - - - - - - 0.01 0.2 0.7 4. 12. Ambient Radiation Level 0.2 0.2 0.7 2. 3. 3. 5. 5. 8. 10. 15. 3B-1
. ym.
(, lg i b) * (
.Q-1 Nf NRC/ FEMA. OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION Post' Accident Sampling System Readings (mR/hr)
From 1745 1800 1830 1900 1915 1930 2000 2030 2045 2100 To- 1800- 1830 1900 1915 1930 2000 2030 2045 2100 2145 System -Sample Distance Shield Size Drywell 15.m1 1 inch- none 600. 800. 1.5P3 1.P3 2.5P3 4.5P3 4.P3 4.P3 3.5P3 3.P3 Atmosphere 1 ft- none 6. 8. 10. 15. 25. 45. 40. 40. 35. - 30. 1 inch 2" lead 4. 6. 4. 13, 20. 35. 35. 35. 30. 25. I ft 2" lead- 0.15 0.2 0.3 0.4 0.7 1.2 1.1 1.1 1.0 0.8 Reactor 10.m1 1 inch none 4.4P5 4.4PS- 4.4P5 4.P5 4.P5 3.8P5 3.4P5 3.4P5 3.4P5 3.4P5 Coolant 1-ft none 4.4P3 4.4P3 4.4P3 4.P3 4.P3 3.8P3 3.4P3 3.4P3 3.4P3 3.4P3 1 ft 2" Icad 90. 90. 90. 80. 80. 80. 70. 70. 70. 70. I ft 4" lead 1.8 1.8 1.8 1.6 1.6 1.6 1.4 1.4 1.4 1.4 Gas Stripped 15 ml 1 inch none 3.P5 a.P5 3.P5 2.7P5 2.7P5 2.5P5 2.3P5 2.3P5 2.0P5 1.8P5 From Reactor 1 ft none 3.P3 3.P3 3.P3 2.7P3 2.7P3 2.5P3 2.3P3 2.3P3 2.0P3 1.8P3 Coolant I ft 2" lead 60. 60. 60. 55. 55. 50. 45. 45. 40. 40. I ft 4" lead 1.2 1.2 1.2 1.1 1.1 1.0 1.0 0.9 0.8 0.8 Suppression 10 ml 1 inch none 4.P3 5.P3 6.P3 7.P3 7.5P3 8.P3 8.P3 8.5P3 8.5P3 8.5P3 Pool Liquid 1 ft none 40. 50. 60. 70. 75. 80. 80. 85. 85. 85. 1 inch 2" lead 30. 40. 50. 55. 60. 65. 65. 70. 70. 70. Ambient Radiation Level 15. 20. 20. 20. 20. 25. 25. 25. 25. 25. 3B-2 u___ -
~
), NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
- j. LIMERICK GENERATING STATION North Vent Release Data (Source Term) 1315- 1800- 1900- 1915- 1945-Time Interval 1800 1900 1915 1945 2145
~
North Vent Stack Flow (cfm) 3000. 3000. 3000. 3000. 3000. Stack Concentrations (pCi/CC) of release Kr-85 2.0N8 *3.N5 1.N4 2.N2 6.N2
-85M < 4.2N7 7.N4 2.N3 4.N1 1.2N1
-87 1.2N7 2.N4 6.N4 9.N2 2.N1
, -88 9.0N7 1.5N3 4.N3 7.N1 2.
Xe-133 1.8N6 3.N3 1.N2 2. 6.
-135 1.8N6 3.N3 9.N3 1.8 5.5 I-131 2.0N11 5.N7 5.N5 7.N3 3.26N2
-133 8.0N11 2.N6 2.N4 3.N2 1.3N1 North Vent Stack Release Rate (pCi/sec) -
Kr-85~ 2.8N2 43. **1.4P2 3.P4 9.P4 .fN -85M 6.N1 1.P3 3.P3 6.P5 1.8P6 '!' ") ;
-87 1.7N1 3.P2 8.P2 1.3P5 3.P5
-88 . 1.3 2.P3 6.P3 1.P6 2.8P6 Xe-133 2.5 4.3P3 1.4P4 3.P6 8.5P6
' 135 2.5 4.3P3 1.3P4 2.6P6 7.P6 I-131 2.8N5 0.7 70. 1.P4 4.7P4
-133 1.N4 3. 3.0P2 4.3P4 2.0P5
-Exposure Rate from 100 ml 3 Sa.nle at - 1." (mR/hr) -
- 3. 10. 1.9P3 4.P3
~
*3.N5 = 3 x 10
**1.4P2 = 1.4 x 10%
?3 3C-1
. .]
f' ' 'p NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
%_/ LIMERICK GENERATING STATION North Vent Stack Effluent and Sample Data 1315- 1800- 1900- 1915- 1945-1800 1900 1915 1945 2145 Gaseous Effluent Monitor Readings (pci/CC)
Low Range 2LE-076 5.0N6 *8.5N3 2.6N2 Off-Scale Off-Scale
'Mid Range IME-076 -
9.N3 3.N2 5. 15. High Range 3EE-076 - - -
- 5. 15.
Composite Channel (pC1/sec) 7.0 1.2P4 **4.P4 7.P6 2.P7 4TE-076
< Increase in Readings from Iodine Collection Cartridge Normal Range Detector 2/5 1.0N10 2.5N6 Off-Scale Off-Scale Off-Scale IE-075 (pCi/cc)
Dose Rate from Unshielded - -
- 1. 120. 240.
Cartridge (mR/hr/ minute) .
.n A ,/. Dose Rate from 2" Lead - - -
2.4 5. Shielded Cartridge (mR/hr/ minute) Dose Rate from Unshielded Stack l Sample (mR/hr)
~15'al sample -
0.4 1.6 300. 600.
- 100 m1 sample -
- 3. 10. 1.9P3 4.P3 750 mi sample -
- 22. 80. 1.5P4 3.P4 Dose Rate from 2" Lead Shielded .
Stack Sample (mR/hr) 15 al sample - -
.03 6. 10.
3, 100 alLsample - 0.05 0.2 40. 80. 750'al sample - 0.4 1.6 300. 600.
*8.5N3 = 8.5 x 10"
**4.P4 := 4'x 104 I-- /
' /
'%/
3C-2
9 . 23_
'NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION Meteorological Parameters 1100- 1400- 1630- 1800- 1945-1400 1600 1800 1945 2400 Wind Speed - aph g Ground 5.2 4.8 4.1 3.0 4.0 7 Elevated 7.1 6.3 5.1 3.1 4.3 Wind Direction - deg aza Ground Elevated
. Sigma Theta - des aza 137 145 151 158 158 144 152 157 158 158 i- Ground 6.7 5.9 11.0 10.6 10.2 Elevated 8.0 6.9 13.6 12.9 12.4 p ~ Delta T - des F b Ground -1.3 -1.7 -2.3 -2.1 -2.1 3 ' Elevated -1.1 -1,3 -2.3 -2.1 -2.1 Temperature - des F Elevated 71 75 82 79 16 .
'%)
3C-3
O j^.. . ( 8 -; - ( NI
~
Y' i l IEtC/ FEMA Observed Emergency Response Exercise Limerick Generating Station Whole Body dose Rate Aloeg Centerlir.e,of Plume (mR/br) l 2 3 4 5 6 7 8 9 10 Distance (Miles) 0.5 'l Release 1 2041 Arrival Time 1810 1820 1840 1900 1920 1940 1956 2011 2026 205] l Reading 0.14 0.05 0.02 0.01 ---- ---- ---- ---- Release 2 2126 2141 Arrival Time 1910 1920' 1940 1956 2011 2026 2041 2056 2111
- keading 0.38 0.13 0.05 0.02 0.01 ----
Release 3 2152 1925 1935 1952 2007 2022 2037 2052 2107 2122 2137 i Arrival Time 0.4 Reading 68. 24. 6. 3.6 2.2 1.5 1.0 0.8 0.6 0.5 Release 4 2200 2215 Arrival Time 1952 2000 2015 2030 2045 2100- 2115 2130 2145 150. 55. 19. 8. 5.0 . 3.5 2.6 2.0 1.6 1.2 1.0 Reading 2215 2230 2245- 2300 1315 2330 2345 2400 2415 End of Releases 2152 2200 Ncte: Use these values for areas shaded red; 0.5 of these values for areas shadded blue;
. 0.3 of these values for areas shaded om. nge; .
0.1 of these values f or arcas shaded yellow; . 0.01 of these values for areaa shaded green 3D-1 l
'--- _ _ _ _ _ _ l
f ~ ,- U
} '
V s . IRC/fDIA Observed Emergency Response Esercise Limerick Generating Station SAM-II Readings Along Centerline of Plume (cpe above backgreemd)
- 1. .4. 6. 7. 8. 9. 10.
Distance (Miles) 0.5 2. 3. 5. Release 1 Arrival Time 1810 1820 1840 1900 1920 1940 1956 2011 2026 2041 2056 s, ding ---- Release 2 1910 1920 1940 1956 2011 2026 2041 2056 2111 2126 2141 Arrival Time ---- ---- ---- Reading 140. 50. 19. 9. ---- ---- ---- Release 3 Arrival Time 1925 1935 1952 2007 2022 2037 2052 2107 2122 2137 2152. Reading 2.P4 *8.5P3 2.8P3 1.1P3 710. 510. 390. 310. 250. 200. 150. l Release 4 1952 2000 2015 2330 2045 2100 2115 2130 2145 2200 2215 Arrival Time Reading 8.P4 3.3P4 1.P4 4.P3 2.5P3 1.8P3 1.3P3 1.1P3 850. 700. 600. l 2230 2245 2300 2315 2330 2345 2400 2415 End of Releases 2152 2200 2215 Note: Use taese values for areas shaded red; 0.5 of these values for areas shadded blue, l 0.3 of these values for areas shaded orange; l 0.1 of these values for areas shaded yellow; 0.01 of these values for areas shaded green .!
*8.5P3 = 8.5x103 f 3D-2
.b
TX
, {- / i ~ ; j .-
\ / / ' >
t .'
%,/, b/l . \,.q s
~
.c . ,o .a
" 't' s
)' .f' ,
, _,4 .
.f G
/;.i);$ s. ,. .
5 {a}-
+
- m. ,r j-f h U.
?.
9 A; -A".
- r: >? f
." on. ; m' Q.' ; f' J ' g) , , ,
;s,,., v. y., .lL w:.
', . ~
sg
+ r.- .r .- y a- i .,, ; . ;s '$ 1'
- 1 Zy
- . g. a ;9:
.,p4 ; g, ONRC/ FEMA Observed Emergency Response Ex,crcise' '
4 ,f -
. [*9s ,
- .'d -
G.. !; 'C Lhaerick Geneysting St'ation .
, ,y<- /
' L % *, ' -
4j , ,
/
, ;. j /!
;>/ , , p!,'-g C 'O,, 'I-131 Concentcation Cen,t,erline of. Plume (pCi/cc)',. J -f
.~ < - .: *
. .,- sa t;. . .
- }'R
__ f .q-
- y; : ]*/, .
j_ cw . d't . q ., 3 'f . , L 0.5
- 1,0 ~ , y i 2, . 0 : Jn7 " 5 0; 6 .04 ': 10. <
~ i r Isistance e,- (Miles.) . -
- 3 . 6 ' s, y: [,. 0 ' ,p/,J -
. . s,,, :,n,/ 7. 0.v
- yg >- <<j48..,,0 L. ,O ;. ,--=
. ,. ,s. 4.!.
v e, v-
- p : /y 28 -
a . , .
- t 4 ', ,. * '
, ;p ,j
.- :l1 f u .," J . : .
, ,o j
.- pt. y
" c' 4 Release ) .3 r" W< P ,, %,. ), , . J' ;,' - '!.;'f
. . e.,9
., s ,
) )., r
,20:6~~ ~ ' "
1900' , '1920.i.
~
'Arrivat Time --.1'O.Nr a1820.
. 18 -1840" 194314 'y----~O , 1956;/ -2011 202E, . 2041f x,* Reading ---i.];p ----. ----.;;. -
r-- 4---}- g ---- y ; ;; ' < , s .
,,9 . - - / ,q.
'RL-lease' 2 ', ,~. U 16 '
+
l' > , / , / % /*.
' ' A .
1925 '
~
J,[~ , Aeriva1' Tied *' I1910 1940 '1956 '2011
.2026 h 25'45' s '205M ' 1L 21k1/
21i6 . 215 C ~ ( - .
, . Reading : 1.4N9 5. A/ /6,A, 1.7 N O, 7.N11 ----
s.---- 3---- ---{f --...2 s
' , - -- F .f'{
s
. ~ -f .
_ ,, f
.q l ,d M i- ! - Release 3 , . .
- 2007 2022c,
/ _,,
2052 ~ 2107
%/ f2122- '2137
.2152.. 'J,
) ' ,-
Arriva1 Time 1925 1935' 41952a z, . -2037- - ' 4.N9 , 13.N91 [ Reading .2.3N7 8.N8 2.8N8' 1.3N8'. ' q.N97 ' 5.1N9 ~ 2 l5 N9 ' - 2.ii9 1.5N9 \. ,n'
, s. >2 . ,
a , , ,
-Release 4 - -
r 4
, ' ,e 2000' 2100 /;. 2200 22 G;'
Arrival Time. 1952 2015 2030 '2045' 2115 7 2130 2145
?
Reading 7.N7 2.5N7 9.N8 3.9N8- 2.5N8' 1.8NS-1.3N8 j 1.N8-S.N9
,e A.N7
,s -
6.N9
. I -
; End of Releases 2152 2200 2215- 2230 -2245 2300 2315 2330- l2345 s 24001 'r 7415
/
4
? ,. .
} ,
. , /(
*1.4N9 = 1.4x108 e
3 1 - e l I i i I l l 3D-3 o
- .. ~. .
'kJ-Qf f s
R-) m_ a , q t-ll.
'f ,, .
-NRC/ FEMA Observed' Emergency l Response Exercise Limerick Generating. Station I Inhalation Thyroid' Dose Rate Along~ Centerline'of Plume:
Distance (Hiles). 0.5 1.0 2.0 3.0. '4.0 5.0 .6.0 7.0 ' - 8.0 ' .9.0- 10. l i j . Release 1 . 1810 1820 1840 1900 1920 1940' 1956 2011 2026 ,2041 2056' l Arrival Time' ---- ---- ---- Reading ---- ! Relesse 2 j Arrival Time
- 1910 1920 1940 1956- 2011 2026 2041 2056 ' 2111 2126 2141 Reading 6.2 2.2 - 0.8 0.3 ---- ---- ----
i Release 3 1935 1952 2007 2022 2037 2052- 2107 2122 2137 2152 Arrival Time 1925 I-Reading 890. 320. 110. 50. 30. 22. 16. 12. 10. 8.2 6.9 Release 4 Arrival Time 1952 2000 2015 2030 2045 . 2100 2115 2130 2145 2200 221S Reading 3000. 1060. 380. 160. 100. 70. 55. 40. 33. 27. 23. 2200 2215 2230 2245 2300 2315' 2330 2345 2400 2415 End of Releases 2152 3D-4 W ,
w .
;,c y ,, Y- ._/' ..
NRC/ FEMA Observed Emergency Response Exercis'e Limerick Generating Station Whole Body.Does Rate at Various Field Monitoring Location (mR/hr). with Plume Front Arrival Times Field'Honitoring NW-2.2 Location NNW-0 NW-l' NNW-l' N-1~ N-2 LNW-2.1 NNW-2.1 NNW-2.2 1826 1832 1830 1840 1840 1842 1852 1852 Arrival' Time 1816 WB Dose Rate 0.06 ---- 0.03' ---- ---- ---- 1926 1932' 1930 1940 1940 1942 1950 1950 Arrival Time- 1916 WB Dose Rate 0.14 ---- 0.09 ---- ---- ---- 0.02 0.02 --- - 1931 1941 1946 1945 1953 1953 1954 2002 2002 Arrival Time ' WB Dose Rate 27. 0.7 16. ---- 0.04 0.06 2.7 4.0 0.4 1957 2005 2009 2007 2015 2015 2017 2024 2024 Arrival Time WB Dose Rate 60. 1.5 37. ---- 0.09 0.15 6.1 9.1 0.91 2 Field Monitoring i Location N-3.1 NNW-3 NW-3 NNW-4 N-4 N-5.1 NNW-5.1 NNW-5.2 Arrival Time 1900 1910 1914 1932 1924 1942 1944 1950 WB Dose Rate ---- 0.02 ---- ---- Arrival Time 1956 2004 2007 2020 2014 2028 2029 2035 WB Dose Rate ---- 0.02 ---- ---- ---- ---- 0.01 ---- Arrival Time 2008 2015 2018 2032 2026 2039 2041 2047 WB Dose Rate ---- 2.7 0.01 1.2 ---- ---- 1.4 0.6 Arrival Time 2030 2038 2041 2054 2048 2102 2104 2109 WB Dose Rate ---- 6.1 0.03 2.7 ---- ---- 3.0 1.5 3D-5
( tw
?',: -
p
'} 'g 1 - <- _ , , ,4
&. , Q- '
\_ v ll.
e - T. i .
' F'icld Monitoring'. ..
Location ' NNW-6.1~ .NNW-6.2~ N-6.2. N-7.1, :NNW-7.2 NNW-7.1- NNW-8.3'- Arrival Time 2002 2004 2001 '2016.- -2016- ~2019 2031 WR Dose Rate. ----- ---- - ---- ----- ----
' Arrival Time 2047 2049 2046 2101 2101 2104 2116 WB Dose Rate. ----- ---- --- . ---- ---- ----
Arrival Time '2059. 2100' 2058- 2112 2112 2115 2127 WB Dose Rate -0.09- 0.92 0.09 ---- 0.65 0.27 0.54 Arrival Time 2121 2122 - 2120- 2135 2135 2138 - 2150 WB Dose Rate' O.2 2.1 0.2 --- 2.0- 0.6 1.2
. t 3D-6
~
n.
-~
~~; ,
)f_
j'") _ ' t , , i- -t 1 C9 / %f -Q/ ; NRC/ FEMA Observe'd Emergency Response Exercise
. Limerick Generating Station JSAM-II Readings at Various Field Monitoring Locations (cpm above-background) with Plume. Front Arrival Times
-Field Monitoring Locarion NNW-0 NW-1 NNW-1 N-1 N NW-2.1 NNW-2.1 NNW-2.2 Arrival Time- '1816 1826. 1832 '1830 1840 1840 1842 1852 SAH-II. ---- ---- ---- ---- ----
Arriva1 Time 1916' 1926 11932- 1930 1940 1940 1942 1950 SAH-II 65. ----
- 29. ---- ---- ----
- 6. 9.
Arrival Time 1931 1941 1946 1945 1953 1953 1954 2002 SAM-II 9.1P3 260. 5.5P3 ----
- 13. 26. 910. 1.3P3 Arrival Time 1957 2005 2009 2007 2015 2015 2017 2024 SAM-II 3.0P4 730. 1.8P4 ----
- 47. 83. 3.1P3 4.7P3 Field Monitoring Location NW-2.2 N-3.1 NNW-3 NW-3 NNW-4 N-4 N-5.1 NNW-5.1 Arrival Time 1852 1900 1910 1914 1932 1924 1942 1944 SAM-II ---- ---- --- - ---- ---- ----
Arrival Time 1950 1956 2004 2007 2020 2014 2028 2029 SAM-II ---- ---- 6 ---- ---- ---- Arrival Time 2002 2008 2015- 2018 2032 2026 2039 2041 SAH-Il 140. ---- 910. 5. 420. ---- ---- 440. . Arrival Time 2024 2030 2038 2041 2054 2048 2102 2104 SAM-II 470. ---- 3.1P3 16, 1.4P3 ---- ---- 1.5P3
+
3D-7
^
~;' yQ ,
- J ~ '(, g) .!
- ( .n
;(. -
- ( );:
. ~s -
q.) . . .uj 4 4 f s Field Honitoring N-6.2 NNW-8.3~ Location- -NNW-5.2- . NNV-6 ' .' 1 - NNW-6.M' N-7.1. -NNW-7.22 NNW-7.1 7 Arrival Time 1950 2002 200'4 2001" 2016 -2016- 2019- 2031 SAti-II ---- ---- ---- ---- ---- ' ---- ---- '---- Arrival Time 2035 2047: 2049 2046' 2101 2101 2104^ -2116
.SAH-II ---- ---- ----~ ---- ---- ---- ---- '----
Arrival Time 2047 2059' 2100 2058 2112 2112 2115 2127. SAti-II 250. .34. .340. 34. ---- 310. 90. 180. Arrival Time 2109 2121 2122 2120 2135 2135 2138 2150. SAti-II 730. 100. 1.0P3 100. 13. 940. 310. 600. 3D-8' C
jv -
', %j ,
(' O: q,/
'NRC/ FEMA Observed Emergency Response Exercise' Limerick Generating Station I-131 Concentration at Various Field Monitoring Locationa
'(pCi/cc) with Plume Front Arrival Times Field tionitoring Location' NNW-0 NW-1 NNW-1 N-1 'N NW-2.1 NNW-2.1 NNW-2.2 Arrival Time 1816 1826 1832 1830 1840 1840 1842- 1852 I-131 Conc. ---- ---- ----
Arrival Time 1916 1926 1932 1930 1940 1940 1942 1950 I-131 Conc. 5.6N10 ~---- 3.4N10- ---- ---- ---- 5.4N11 8.IN11 Arrival Time 1931 1941 1946 1945 -1953 1953 1954 2002 I-131 Conc. 7.9N8 2.3N9 4.7N8 4.5N12 1.IN10 1.9N10 7.9N9 1.IN8 Arrival Time 1957 2005 2009 2007 2015' 2015 2017 2024 I-131 Conc. 2.ON7 6.3N9 1.0N7 1.3N11 4.1N10 7.2N10 2.7N8 4.1N8 Field tionitoring Location NW-2J N-3.1 NNW-3 NW-3 NNW-4 N-4 N-5.1 NNW-5.1 Arrival Time 1852 1900 1910 1914 1932 1924 1942 1944 I-131 Conc. ---- ---- ---- Arrival Time 1950 1956 2004 2007 2020 2014 2028 2029 I-131 Conc. 9.0N12 --- . 5.4N11 ---- ---- ---- ---- 2.7N11 Arrival Time 2002 2008 2015 2018 2032 2026 2039 2041 1-131 Conc. 1.2N9 2.2N12 7.9N9 4.IN11 3.6N9 2.2N12 ---- 3.8N9 Arrival Time 2024 2030 2038 2041 2054 2048 2102 2104 I-131 Conc. 4.1N9 1.3N11 2.7N8 1.4N10 1.2N8 6.8N12 2.2N12 1.3N8 3D-9 C-
>- c
;r'% j-~3 .. m. .,, ,
( )- If j. ). "-Q V ,
'k_
i_f ~ F s Fie1<1 Monitoring . Location NNW-5 2.
. NNV-6. I'- NNW-6.2 . N-62 .. N-7.1 'NNW-7.21 =.NNW-7.I' ' NNW-8.3 Arrival Time 1950 '2002 2004 2001 2016- -2016- 2019 2031' l I-131. Conc. . .
i . , 4 . Arrival Time 2035 2047- 2049 2046 2101- 2101 2104 2116 I-131 Conc. 1.6N11 --- - 1.6N11 ---- ---- 1.6N11. 9.ON12. 9.ON12 i-1
- Arrival Time 2047 2059- 2100 2058 2112 2112 2115 . 2127 I-131 Conc. 2.2N9 2.9N10 2.9N9 2.9N10 2.3N11 2.7N9 7.9N10 1.6N9.
Arrival Time 2109 2121 2122 2120 2135 2135 2138 - 2150 l i I-131 Conc. 6.3N9 8.8N10 '8.8N9 8.8N10 1,1N10 8.1N9 2.7N9 5.2N9 4 4 t. 3D-10
- u. _ _ _ _ _ _ _ . _ _ _ _ _
m . , _ .- ,
/~ ~, ~.
;(y ,
([ k k
^ - '
-NRC/ FEMA;0bserved Emergency Response Exercise -
Limerick Generating Station Inhalation Thyroid Dose at Various Field Monitoring' Locations (mR/hr), with Plume Front' Arrival Times Field Monitoring Location NW W-1 NW-1 N N-2 ' W-2.1 ' NW-2.1 NW-2.2
~ Arrival Time 1816 1826-' 1832' 1830 5840 1840 1842 ~1852-Thyroid Dose Rate ---- ---- ---- ----
Arrival Time 1916 1926- 1932 1930 1940 1940 1942 1950 Thyroid Dose Rate 2.5 ---- 1.5 ---- ---- ---- 0.24 0.36 Arrival Time' 1931~ 1941 1946 1945 1953 1953 1954 2002
. Thyroid Dose Rate 350 10 210 0.02 0.50 0.85 35 50 Arrival Time -1957- 2005 2009 2007 2015 2015- 2017 2024 Thyroid Dose Rate 1170 28 710 0.06 1.8 3.2 120 180 -Field Monitoring Location W-2. 2 N-3.1 NW-3 W-3 NW-4 N-4 N-5.1 NW-5.1 Arrival Time 1852 1900 1910 1914 1932 1924 1942 1944 Thyroid Dose Rate ---- ---- ---- ---- ---- ---- ---- ----
Arrival Time 1950 1956 2004 2007 2020 2014 2028 2029 Thyroid Dose Rate 0.04 ---- 0.24 ---- ---- ---- ---- 0.12 Arrival Time 2002 2008 2015 2018 2032 2026 2039 2041 Thyroid Dose Rate 5.3 0.01 35 0.18 16 0.01 ---- 17 Arrival Time 2024 2030 2038 2041 2054 2048 2102 2104 Thyroid Dose Rate 18. 0.06 120 0.60 53 0.03 0.01 59 i 3D-11 m
- = a
( / ~~^ ./ ' .- ,
's,- '
.p .\,/
Field Monitoring . Location NNW-5.2 NNW-6.1 NNW-6.2 .N-6.2 N-7.1 NNW-7.2 10fW-7.1 NNW-623. i
-Arrival Time 1950 2002 2004 '2001 2016- 2016 -2019 2031 Thyroid Dose Rate ---- ---- ---- ----- ---- ---- ----- ----
Arrival Time 2035 2047 2049 2046 2101 2101 '2104 ~2116 Thyroid Dose Rate 0.07 --- -
~0.07 ---- ----
0.07 0.04' O.04 Arrival Time 2047 2059 2100 2058 2112 2112 2115 2127 Thyroid Dose Rate 9.6 1.3 13. 1.3. 0.1 12. 3.5 7.1 Arrival Time 2109 2121 2122 2120 2135 2135- 2:38 2150. Thyroid Dose Rate 28. 2.9 39, 3.9 0.5 36. 12. 23. 3D-12
,cs .: ,
~q -
-- 4
.cj j;n .
~
u ._ .,
- NRC/ FEMA Observed Emergency Response Exercise Limerick Generating Station-
-I-131 Concentration on Downwind Pastures (pci/m'4)
Distance (miles) 0.5 1. '2.- 3. 4. 5. 6. 7.- 8. 9. 10. 1815-1830 2.5N4 ---- ---- ---- ---- ---- ---- ---- 1830-1845 5.ON4 '1.N4 ---- ---- ---- ---- ---- ---- ---- ---- 1845-1900 7.5N4 2.N4 3.5N5 ---- ---- ---- ---- ---- ---- 1900-1915 .4.N2 3.N4 6.7N5 1.4N5 ---- ---- ---- --- - - ---- ---- ---- 1915-1930 8.N2 1.6N2 1.ON4 2.9NS ---- ---- ---- ---- ---- ---- 1930-1945 2.N1- 6.7N1 5.6N3 4.2N5 ---- ---- ---- ---- ---- ---- ---- 1945-2000 3.4N1 1.2N1 1.8N2 2.6N3 ---- ---- ---- ---- ---- ---- ---- 2000-2015 4.8N1 1.6N1 3.5N2 1.ON2 1.4N3 ---- ---- ---- ---- ---- ---- 2015-2030 6.2N1 2.N1 5.3N2 1.8N2 6.4N3 1.0N3 ---- ---- ---- ---- ---- 2030-2045 7.6N1 2.6N1 7.ON2 2.6N2 1.1N2 4.6N3 6.9N4 ---- ---- ---- ---- 2045-2100 9.0N1 3.N1 8.8N2 3.4N2 1.6N2 8.3N3 3.2N3 6.N4 . 2100-2115 1.0 3.5N1 1.1N1 4.2N2 2.1N2 1.2N2 5.8N3 2.7N3 4.8N4 ---- ---- 2115-2130 1.2 4.N1 1.2N1 JF.N2 2.6N2 1.6N2 8.3N3 4.8N3 2.1N3 4.N4 ---- 2130-2145 1.3 4.5N1 1.4N1 5.8N2 3.N2 1.9N2 1.1N2 6.9N3 3.7N3 1.6N3 3.N4 2145-2400 1.5 4.9N1 1.6N1 6.6N2 3.5N2 2.2N2 1.3N2 9.ON3 5.3N3 3.ON3 1.2N3 3D-13 u
f y\ y .v
~ V' k k - g.
~
NRC/ FEMA Observed' Emergency Response Exe'rcise
- D Limerick Generating Station I-131 Concentration in Milk Produced by .
.CowsLGrazing on Downwind Pastures.(pci/literT Distance (miles) 0.5 1. 2. 3. 4. 5. .6. 7. 8. '9. 10.
1815-1830 1.8N4 ---- ---- ---- ---- ---- 1830-1845 3.6N4 6.3NS ---- ---- ---- ---- ---- ---- 1845-1900- 5.4N4 1.3N4 2.1N5 - ---- ---- ---- ---- ---- 1900-1915 2.9N2 1.9N4 4.2N5 8.8N6 ---- ---- ---- ---- ---- ---- 1915-1930 5.8N2 1.N2 6.3NF 1.8NS ---- ---- ---- ---- 4.2N2 3.5N3 2.6N5 ' ---- ---- ---- ---- ---- 1930-1945 1.4N1 ---- 1945-2000 2.2N1 7.4N2 1.1N2 1.6N3 --- - ---- ---- ---- ---- 2000-2015 3.1N1 1.ONI 2.2N2 6.5N3 8.8N4 ---- ---- ---- ---- ---- 2015-2030 4.ONI 1.3N1 3.3N2 1.1N2 4.N3' 6.4N4 ---- ---- ---- ---- ---- 2030-2045 4.9N1 1.6N1 4.2N2 1.6N2 7.N3 2.9N3 4.3N4 ---- ---- ---- ---- 2045-2100 5.8N1 1.9N1 5.5N2 2.1N2 1.N2 5.2N3 2.0N3 3.8N4 ---- ---- ---- 2100-2115 6.7N1 2.2N1 6.6N2 2.6N2 1.3N2 7.5N3 3.6N3 1.7N3 3.N4 ---- ---- 2115-2130 7.6N1 2.5N1 7.7N2 3.1N2 1.6N2 9.8N3 5.2N3 3.N3 1.3N3 2.5N4 ---- 2130-2145 8.4N1 2.8N1 8.8N2 3.6N2 1.9N2 1.2N2 6.8N3 4.3N3 2.3N3 1.N3 1.9N4 2145-2400 9.3N1 3.1N1 9.9N2 4.1N2 2.2N2 1.4N2 8.4N3 5.6N3 3.3N3 1.9N3 7.5N4 3D-14 __a
Ii
/
N / .' NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
-LIMERICK GENERATING STATION ONSITE RADIOLOGICAL SURVEY DATA 1800-1900 1900-1915 1915-1945 1945-2145 Whole Body Dose Rate (mR/hr)-
~
Upwind of Line A-A 1.6 5. 850 *1.8P3 Between A-A and B-B .6 1.9 340 700 Downwind of Line B-B , .14 .38 68 150 SAM-II Count Rate (cpm)- Upwind of Line'A-A 150 1.7P3 2.2P5 9.P5 Between A-A and B-B 60 680 9.4P4 3.8P5
' ~'
. Downwind of Line B-B <10 150 2.1P4 8.1P4
' Iodine-131 Concentration (uci/cc)
' Upwind of Line A-A **1.4N9 1.6N8 2.5N6 8.No :
Between A-A and B-B 5.7N10 6.8N9 1.N6 3.3N6 , Downwind of Line B-B - 1.5N9 2.4N7 7.2N7 :
- f'~';' '
n,_j Inhalation Dose Rate (ares /hr) Upwind of Line A-A 6.2 70 IP4 3.3P4
. Between A-A and B-B 2.4 28 4.1P3 1.4P4 -
Downwind of Line B-B - 6.2 890 3.P3
. Contamination Survey (dps/100 cm3 ) .
Upwind of Line A-A. <10 <10 3.P3 1.2P4 Between A-A and B-B <10 <10 1.3P3 5.P3 . Downwind of Line B-B <10 <10 250 1.5P3
*1.8P3 = 1.8 x 10 3
-**1.4N9 = 1.4 X 10 8 Note:
Use these values for areas shaded red; one half of these values for areas shaded blue; one tenth of these values for areas shaded yellow; and one hundredth of these values for areas shaded green. Note: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm/100 cm2 .
/,_;'l u
3E'-1
- )
yu Hs, . NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
}, LIMERICK GENERATING STATION
' d; -
Reactor Enclosure El.177 Ft r 1100 1400 1500 1600 1630 1715
, 11400 1500 1600 1630 1715 1730 Ambient. Radiation Level (mR/hr)
Core Spray 1 1. 1. 3. 10. 150. 1500. A 2 1. 1. 1. 4. 60. 600. A 3 1. 1. 1. J. 15. 150. A 4 1. 1. 1. , 6. 60. 5 I* I* I* 1. 3. 30. A , RCIC' I 50. 400. 700. 1.2P3 2.P3 600. C 2 12. 100. 175. 300. 500. 150. C Core Spray I D
- 1. 1. 3. 10. 150. 1.5P3 2 1. 1. 1. 4. 40. 400.
D 3 1. 1. 1. 1. 15. 150. 4 1. 1. 1. 1. 4. 40. 5 1. 1. 1. 1. 1.5 15. D 6 1. 1.0 1. 1. 0.1 8. D NPCI Ig 50. 200. 200. 200. 200. 200. 2 1. O. 50. 50, 50. 50. H
'RHR 1 10. 10. 30. 100. 300. 1500.
- 2. 2. - 5. 20. 60. 300.
2f 3g 0.5 0.5 1. 5. 15. 75. 4 0.5 0.5 0.5 2.5 8. 40. b S 0.5 0.5 0.5 1. 4. 20. 0.5 0.5 0.5 0.5 1.5 8. 6f
- All Other Areas 0.5 0.5 0.5 0.5 1.5 5.
i ARM -01 100. 800. 1.4P3 2.5P3 4.P3 1.3P3
-02 80. 300. 320. 320, 320. 320.
-03 1. 1. 1. 1, 2. 20.
f. l-C' 3F-1 L_
U
- f. NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
' \' >)
LIMERICK GENERATING STATION Reactor Enclosure El. 177 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 Ambient Radiation Level (mR/hr) Core Spray 1 A 6.P3 1.5P4 2.P4 2.5P4 2.P4 2 2.4P3 6.P3 8.P3 1.P4 8.P3 A 3 600. 1.5P3 2.P3 2.5P3 2.P3 A 4 A 250. 600. 900. 1.3P3 900. Sg 120. 300. 400. 500. 400. RCIC Ic 600. 600, 600. 600. 600. 150. 150. 150. 150. 150.
~2f Core' Spray I 6.P3 1.5P4 2.4P4 2.5P4 2.P4 D
2 1.6P3 4.P3 7.P3 7.P3 6.P3 D 3 600. 1.5P3 2.4P3 2.5P3 2.P3 D 4 160. 400. 700. 700. 600. D S 60. 150. 240. 250. 200. D ('( 6 30. 80. 120. 130. 100. A._) HPCI 1 200. 200. 200. 200. 200.
- 2. 50. 50. 50. 50. 50.
RHR 1 6.P3 6.P3 6.P3 6.P3 6.P3 b 2 1.2P3 1.2P3 1.2P3 1.2P3 1.2P3 b 3 300. 300. 300. 300. 300. b 4 150. 150. 150. 150. 150. b S S0. 80. 80. 80. 80.
- 30. 30, 30. 30. 30.
6f-All Other Areas 3. 2. 5. 15. 20. ARM -01 1.2P3 1.2P3 1.2P3 1.2P3 1.2P3
-02 320. 320. 320. 320. 320.
-03 .80. 280. 300. 350, 280.
\ __,
3F-2
/
NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION Reactor Enclosure El. 177 Ft (Cont) 1100 1400 1500 1600 1630 1715 1400 1500 1600 1630 1715 1730 Contamination Survey (dpm/100 cm4)
...... 1
-Inside- <100. <100. <100. 500. 1.4P3 5.P3
,'Inside' 200. 400. 700. 1.P3 1.5P3 4.P3
-//////
/Inside/ 100. 200. 300. 600. 4.P4 1.P5
//////
\ NOTE: Survey meter readings of swipes in cpm are 1/10 of
,_ contamination values in dpm/100 cm4 l
l
'.)
l Airborne Radioactivity Level
------ cpm /100 ft4 140. 240. 300. 400. 1.8P4 4.P4
-Inside- cpm /6 ft4 <20 <20 <20 24 1.1P5 2.4P3
% I-131 15. 20. 20. 20. 20. 20.
% I-133 70. 80. 80. 80. 80. 80.
1
' ' ' ' ' ' cpm /100 fte 600. 1.P3 1.2P3 1.4P3 1.2P4 1.8P4 l
'Inside' cpm /6 ft4 40. 60. 72. 80. 720. {
' ' ' ' ' ' 1.1P3
% I-131 5. 10. 15. 20. 20.
- 20. l
% I-133 15. 50. 85. 80. 80. 80.
////// cpm /100 ft4 100, 140. 200. 300. 6.P4 1.4P5
/Inside/ cpm /6 ft3 <20 <20 <20 <20 4.P3
////// % I-131 8.P3 l
- 15. 20. 20. 20. 20.
% I-133 20. l
- 80. 80. 80. 80. 80. 80. I 1
1 l
/N i . _,I i
NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
/7 , LIMERICK GENERATING STATION -- N ,) Reactor Enclosure El.177 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 Contamination Survey (dpa/100 cmV)
- -Inside- 1.P4 3.P4 5.P4 7.P4 9.P4 e a , ,:, ,
c'Inside' 9.P3 2.P4 5.P4 6.P4 8.P4 L/ / /:/ / /
/Inside/ 2.PS. 1.9P5 .1.7P5 1.7P5 1.5P5
//////
. NOTE: ' Survey meter readings of swipes in cpm are 1/10 of contamination values in dpe/100 cm3
- -'"] -
1:
/ . Airborne Radioactivity Level
------ cpa/100 ft3 3.P4- 3.2P4 3.2P4 3.2P4 3.2P4 e , -Inside-- '
.cpe/6 ft3 1.8P3 2.P3 2.P3- 2.P3 2.P3
' % I-131 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
' cpm /100 ft3 2.P4 1.P4
, 1.P4 8.P3 6.P3
'Inside' cps /6~ft3 .1.2P3 600. 600. 400. 400.^
'L' % I-131 15. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
./ / / /J/./ cpu /100 fte-4.P4 1.8P4 1.8P4 1.4P4 1.P4
/Inside/- cpe/6 ft4 2.4P3' 1.2P3 1.2P3 8.P2 600. .
~/./ /L/7/ / J% I-131- 20. 20. 20. 20. 15.
% I-133 80. 80. 80. 80. 85.
f .
~'
-.)
d~ 3F-4 1
~ '
h ia NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
; LIMERICK GENERATING STATION
,, Reactor Enclosure El. 201 Ft 1100 1400 1500 1600 1630 1715 1400- 1500 1600 1630 1715 1730 Ambient Radiation. Level (mR/hr) 1 g'
- 2. 2. 6. 20. 60. 300.
2 1. 1. 2. 7. 20. 100. 0.5 0.5 0.5 2. , 6. 30. 3f 1 0.5 0.5 1. 2. 2. 5. 3 2 0.5 0.5 0.5 1. 2. 5. 8 3 0.5 0.5 0.5 1. 2. 5. All Other Areas 0.5 0.5 0.5 1. 2. 5. ARM- -06 0.5 8. 50. 80. 120. 160.
-08 8. 8. 25. 80. 240. 1.2P3
-09 8. 8. 25. 80. 240. 1.2P3
^[ } Contamination Survey-(dpa/100 cm4)
N._/ .
-Inside- 300. 300. 300. 400. 500. 2.P3 e e e . .e
'Inside' 100. 200. 500. 800. 1.3P3 5.P3 e e e e e i NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm/100 cm4 airborne Radioactivity Level
------ cpm /100 ft4 80. 80. 180. 300. 1.4P3 1.6P3
-Inside-- cpe/6 ft4 <20. <20 <20 0 84. 100.
% I-131 10. 20. 20. 15, 20. 20.
% I-133 16 0 , 80. 80. 75. 80, 80.
' ' ' ' ' ' cpm /100 ft4 -160. 200. 600. 800. 5000. 6.P3
'Inside' cpm /6 ft4 <20 20. 40. 50. 300. 360.
' - ' ' ' % I-131 15. 20. 20, 15. 20. 20.
[~'N % I-133 70. 75. 30. 80. 80. 80.
\
v) 3F-5 i -. .,~.- - - - - , - - . - - - - - , ,
j, . NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
'/ LIMERICK GENEI:ATING STATION Os_]\' Reactor Enclosure El. 201 Ft (Cont) 1730 ': 'O 1900 1930 2045
-1800 '
.3 1930 2045 2145 Ambient Radiation Level (mR/hr)
.I 1.2P3 1.2P3 1.2P3 1.2P3 1.2P3 n
2 400, 400. 400. 400. 400. 3g 120. 120. 120. 120. 120. I 8. 16. 40. 100. 120.
, 2g 5. 10. 16. 40. 50.
3 3
- 5. 10. 10. 20, 30.
'All Other Areas 10. 10. 10. 15.- 20.
e ARM -06 160. 160. 160. 200. 240.
-08 5.P3 5.P3 5.P3 5.P3 5.P3
-09: 5.P3 5.P3 5.P3 5.P3 5.P3
,Li Xl 1 Contamination Survey-(dps/100 cm4)
-Inside- 4.P3- 6.P3 7.P3 1.P4 1.P4
- e-. e e., .
'Inside' -9.P3 1.2P4. 1.3P4 1.6P4 1.8P4
- .~,.. ,;
NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination. values in dpe/100 cmV.
. -3 3F-6 8
I." " ' .
NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
.7- LIMERICK GENERATING STATION ob' -
^
Reactor Enclosure El. 201 Ft (Cont)
.. Airborne Radioactivity Level cps /100 ft4 3.P3 4.P3 6.P3 8.P3 6.P3
-Inside- cpm /6 ft4. 180 240. 400. 500. 400
% I-131 20. 20. 20. 15. 20.
% I-133 80. 80. 80. 80. 75.
' ' ' ' -cps /100 ft4- 8.P3 1.2P4 1.6P4 1.2P4 1.P4
Inside' cps /6 ft4 480. 700. 1.P3 800. 600.
-'~' - ' ' ' -' % I-131 20. 20. 20. 20. 20. ' ,
- 80. 80. 80. 80.
% I-133 80.
4 7 6 4 4- . l
\
3F-7 l
g -, _p i, NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION Reactor Enclosure El. 217 Ft 1100- 1400 1500 1600 ,1630 1715 1400 1500 1600 1630 1715 1730 Ambient Radiation Level (mR/hr) Ag 0.5 0.5 3. 5. 8, 25. B 0.5 0.5 1. 2. 5. 10. 8 C 0.5 0.5 0.5 1. 4. 5. D 0.5 0.5 0.5 0.5 4. 3. E 0.5 0.5 0.5 0.5 4. 3. 0.5 0.5 0.5 0.5 4. 3. 1 0.5 0.5 0.5 0.5 3. 3. 2, 0.5 0.5 0.5 0.5 3. 3. D All Other Areas 0.5 0.5 0.5 0.5 3. 3. fy ARM -10 0.5 0.5 2. 8. 15. 20. Contamination Survey (dpe/100 cm4)
-Inside- 200. 200. 200. 300. 1.P3 4.P3
.- . .. , e e
'Inside' 400. 400. 400. 600. 1.2P3 4.P3 e e e e e e NOTE:' Survey meter readings of swipes in cpm are 1/10 of contamination values in dpe/100 cmV.
Airborne Radioactivity Level
- - - - - cpe/100 ft? 160. 340 600 1.P3 3.2P3 4.P3
-Inside- cpn/6 ft4 <20 20. 40. 60. 200. 240.
% I-131 15. 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 75. 80. 80.
' ' ' ' cpe/100 ft? 100 180 400. 600. 1.6P3 2.P3
..Inside' cpe/6 ftV- <20 24. 40. 100. 120
,(] <20
- 20. 20.
' '~' ' ' '
% I-131 15. 20. 20. 20.
(? 60. 80. 80. 80. 80. 80.
% I-133 3F-8 y
e -
p s NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE 4 i LIMERICK GENERATING STATION
-/
Reactor Enclosure El. 217 Ft (Cont) 1730 1800 1900 1930 2045
-1800 1900 1930 2045 2145 Ambient Radiation Level (mR/hr)
A 60. 90. 110. 130. 150. B-- 20. 45. 50. 55. 60. C 10. 20.. 25. 32. 30. L 6. 8. 8. 13. 15. E 8
- 3. 4. 4. 7. 8.
F 3 1.5 2. 2. 3. 4. 1 6. 10. 20. 60. 60.
?, 3. 5. 10. 30. 30.
q
;; = .: -All Other Areas 1.5 1.5 1.0 1.0 1.0 ARM -10 20. 20. 20. 20. 20.
s
. .C'T Contamination Survey (dpm/100 cmW)
~~'
)
-Inside- 6.P3 7.P3 1.P4 1.2r' 1.2P4
'Inside' 6.5P3 7.5P4 1.1P4 1.2P4 1.3P4 e , , , , .
NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dps/100 cm4 Airborne Radioactivity Level
------ cpm /100 ft4 6.P3 6.P3 7.P3 7.P3 8.P3
-Inside- cpm /6 ft4 400. 400. 500. 500. 500.
-- =--- % I-131 10. 15. 20. 20. 20.
% I-133 70. 80. 80. 80. 80.
' ' ' ' cpe/100 ft4 2.6P3 3.P3 3.6P3 4.P3 4.P3
'Inside' cpe/6 ft4 160. 180. 216. 240. 240
' ' ' ' 20. 20. 20.
, % I-131 10. 20, p % I-133 70. 80. 80. 80. 80. 3F-9 m
A NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE k'j LIMERICK GENERATING STATION Reactor Enclosure El. 253 Ft 1100 1400 1500 1600 1630 1715 1400 1500 1600 1630 1715 1730 Ambient Radiation Level (mR/hr) I D 0.5 0.5 0.5 1. 4. 3. 2 D 0.5 0.5 0.5 1. 4. 3.
. All 'Other ' Areas 0.5 0.5 0.5 1. 4. 3.
Jdef -15 0.5 - 0.5 0.5 1. 4. 3.
-16 0.5 0.5 0.5 1. 4. 3.
-17 0.5 0.5 0.5 1. 4. 3.
-18 0.5 0.8 4. 8. 10. 15.
'7~,q Contamination Survey.(dps/100 cm*) 4
)
i l; General 400. 500. 700. 900. 1.5P3 3.P3-NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpe/100 cmV. Airborne Radioactivity Level General cpe/100 ft? 80. 160. 160, 240. 600. 1.P3 cpe/6 ft? <20 <20 <20 <20 40. 60.
% I-131 15, 20. 15. 20. 20. 20.
% I-133 80. 80. 80. 80. 80. 80.
4 O i 3F-10
, _ . . . ~ , ,? y
1
-f-~ NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE ,
('^ ) LIMERICK GENERATING STATION Reactor Enclosure El. 253 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145
- Ambient Radiation Level (mR/hr) 1 D
- 4. 6. 20. 35. 35.
2 D
- 3. 2. 8. 12. 12.
All-Other Areas 3. 2. 2. 2. 2.
~ "
~ ARM -15 3. 2. 2. 2. 2.
-16 3. 2. 2. 2. 2.
-17 '3. 2. 2. 2. 2.
-18 20. 20. 20. 20. 20.
Contamination Survey (dps/100 cm4)
/^N . General 5.P3 6.P3 7.P3 9.P3 1.P4 u..
NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpa/100 cm4 Airborne Radioactivity Level General cpe/100 ft4 1.2P3 1.2P3 1.4P3 1.8P3 2.P3 cpa/ 6 ft4 70. 70. 80. 110. 120.
% I-131 20. 20. 20. 20. 20.
%'I-133 80. 80. 80. 80, 80.
~,n 4
3F-11 p
p.y NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE i LIMERICK GENERATING STATION ij ' Reactor Enclosure El. 283 Ft 1100 1400 1500 1600 1630 1715 1400 1500 1600 1630 1715 1730 Ambient Radiation Level (mR/hr) Injection A C
. . 5. 10. 250. 2.P3 Valve B C
. . 5. 5. 120. 1.P3 Area C C
- 3. 5. 5. 5. 60. 500.
D C 0.5 5. 5. ~,. 30. 250. Recombiner A p 1. 1. 1. 2. 4. 9. B 1. 1. 1. 1. 2. 5. Cp 1. 1. 1. 1. 1. 2. Dp 1. 1. 1. 1. 1. 1.
' All Other Areas 0.5 1. 1. 2. 3. 7.
' ARM -21 0.5 1. 1. 2. 3. 7.
-22 0.5 1. 1. 2. 3. 7.
-23 0.5 1. 1. 2. 3. 7.
) -24 1. 1. Il 2. 4. 9.
Contamination Survey (dpm/100 cm4) ,
-Inside-- 500. 500. 500. 700. 800. 2.P3
- , . , ,, e
'Inside' 600. 800. 1.P3 1.7P3 1.9P3 4.P3 e . . . . .
NOTE: Survey meter readings of swipes in cps are 1/10 of contamination values in dps/100 cm4 Airborne Radioactivity Level
- ---- cpe/100 ftV 240. 340, 400. 600. 1.4P3 1.4P3
-Inside- cpe/6 ft4 <20 20. 24. 24, 78. 78. l g ------
% I-131 20. 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80, 80. 80.
' cpm /100 ft? 140. 180. 340. 380. 800. 1.P3
?- s
'Inside' cpe/6 ft4 <20 <20 22. 22. 48. 60.
' ' ' ' ' 20. 20. 20. 20.
l' ) .' % I-131 20, 20, J % I-133 80. 80. 80. 80. 80. 80. 3F-12 j J
). - r. NRC/ FEMA OBSERVED EtERGENCY RESPONSE EXERCISE LIMERICE GENERATING STATION
- h. Reactor Enclosure El. 283 Ft (Cont) p 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 Ambient Radiation Level (mR/hr)
Injection A 1.P4 3.P4 3.P4 4.P4 4.P4 C~ 2.P4 Valve B 5.P3 1.5P4 2.P4 2.P4 Area 3.P3 8.P3 1.P4 1.P4 1.P4
.Cf o 1.5 ,3 4.P3 5.,3 5.P3 5.P3 c
- t. Recombiner- Ap 70. 100. 500. 4.P4 7.P4
"- B 35. 50. 250. 2.P4 3.5P4
- 20. 25. 120. 1.P4 1.8P4 C,f D 10. 13. 60. 5.P3 9.P3 All Other Areas- 7. 6. 5. 5. 5.
ARM -21 7. 6. 5. 5. 5.
-22 7. 6. 5. 5. 5.
-23 7. 6. 5. 5. 5.
-24 70. 100. 500. >1.P4 >1.P4 s
-Contamination Survey (dyn/100 ce4)
-Inside- 3.P3 3.P3 4.P3 4.P3 6.P3 e., e. ee
'Inside' e ,, , e e 6.P3 6.P3 6.P3 7.P3 7.P3 NOTE: Survey meter readin8s of swipes in cpm are 1/10 of contamination values in dpe/100 cm8 Airborne Radioactivity Level
- - - - - -cpe/100 ft4
~
1.6P3 1.6P3 1.6P3 1.6P3 2.P3
-Inside- 'cyn/6 ft4 100. 100. 100. 100. 100.
-----. % I-131 20. 20. 20. 20, 20.
% I-133 80. 80. 80. 80. 80.
' ' ' ' ' 'cpe/100 ft3 1.2P3 1.2P3 1.4P3 1.4P3 1.4P3 cpe/6 ft4
'Inside' 70. 74. 80. 80. 90.
' ' ' % I-131 20, 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
.L}
3F-13
' e'
i
- I i
o NRC/ FEMA OBSERVED EMERGENCY RESPONSE EERCISE LIMERICK GENERATING STATION
)
Reactor Enclosure El. 313 and 331 Ft L 1100 1400 1500 1600 1630 1715 II00 1500 1600 1630 1715 1730 Ambient Radiation I.evel (mR/hr)
- 1. 1. 1. 2. 4. 9.
- 1. 1. 1. 1. 2. 5.
,p 1. 1. 1. 1. 1. 2.
e D 1. 1. 1. 1. 1. 1.
,. P ,
^' 1 1. 2. 2. 5. 60. 800.
., 57 2 , ?- 1. 1. 1. 2.5 6, 80.
- p!
U YJi
-) '
13 il
, 1. 1.. 1. 2. 3.5 20.
- 2. 5.
'.' 3 1. 1. 3.
o. A - ' 0.5
- 1. 1. 2. 3. 7.
<*' , ..$> ,s/A.Allye.l.er . x s
Areas, ,. I'
,iL <- i-
-27 1. ~ '1. 1. 1. 1.5 3.0
, ARN x A l h} y, b ii; ,,l .
!, Coa.tamination Surw v (dyn/iOO cm3)
. ,N ,
M:',
. General a.00. 200. 200. 200. 200. 200.
f r i g ,y
. i Su r i e of swlped in cpm are 1/10 of M
- 4 '> '
contamination values Ati dyn/100 ' ced . r y , t
'4 Airborne Radio 4ctivity Level '
4r . 3f General eps/100 ft# 100. 140. 200. 400. 500.
% cys/6 ftV :J('<#0.
' i . 20 <20 (20 <20 24. 30.
1 1-131 ' Lt0. 20. 20. 20. 20. 20.
.1.1-133 )^,, 80.- 80. 80. 80. 80. 80.
l' v 3 -r 43 ,, I.', i 'y _ M I'3 ,' (;l,kg
\.
'\ I \ '
i /( ' if) \ , } s,'.. . s n ;" 9, , .
,? , ,
p"'Q j s. , P 8 )y ,
' l, s
.ilg r .. o . ;
,i -
'yg,4 {
o
?
' , \
.r (,, ,
s ! (f ' 1' ( /, F I i. t,
, e,
)'
j' ,-y_ 8 < a g r. c , ,
*L- 4 ( 1 , 4 1
w.-
- .+.
>4
, , a >, )
k g
-x NRC/ FEMA OBSERVED EMAGENCY RESPONSE EXERCISE f LIMRICE GENERATING STATION
; Reactor Enclosure El. 313 and 331 Ft (Cont) 1730 1800 1900 1930 2045 II30 1900 1930 2045 2145 Ambient Radiation Level (mR/hr)
- 70. 100. 500. 4.P4 7.P4
- 35. 50, 250. 2.P4 3.5P4
- 20. 25. 120. 1.P4 1.8P4
- 10. 13. 60. 5.P3 9.P3 Df 1 1.1P3 1.4P3 1.6P3 1.7P3 1.7P3 7
2 110. 140. 160. 170. 170.
- 30. 35. 40. 40, 40.
3f 4 10. 15. 20. 20. 20. 7 All Other Areas 7.0 6. 5. 5. 5. ARN -27 25. 35. 150. >1.P4 >1.P4
,- s Contamination Survey (dps/100 ce#)
~
)
t ./ General 200. 300. 500. 600. 700. N0ft: Survey meter readings of swipes in cps are 1/10 of contamination values in dya/100 cmV.
' Airborne Radioactivity Level General cpe/100 ft8 600. 800. 400. 800. 1.P3 cpe/6 it# 40. 48. 50. 60. 60.
% I-131 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
r%
\_
4 3F-15 J
# h s ,
.c, ,
l< ( -
?NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE A, ]j -
~ 'q '.
I.DERICK. GENERATING STATION j Turbi:le Endlosure El. 200 Ft _? /1'100 1400 1500 1600 1630 1715
. - - 1400 1500 160i> 1630 1715 1730
' AmbiInt Radiation I.evel (aI/hr) -
~
- ..9_' 1 80. 30. 15. 15. 15. 15.
"2[ A
- 40. 15. 8. 8. 8. 8.
3 i ~ 10.~ 4. 2. 2. 2. 2. A
,=,y' i~ %
- All Othe'r Arpa'c' O.2 0.2 0.2. 0.7 1.1 2.
ARN ~
. . ! -d4< 0.2 0.2 0.2 0.7 1.1 2.
_ :105 , 0.2I 0.2 0.2 0.7 1.1 2.
-07 -
90.~ 35. 20. 20. 15. 15.
-34 0'. 2: 0.2 0.2 0.7 1.1 2.
u _ , . w , ~ ~ - a
- Contamination lSurv$y'. (dpm/1001 cm4) r
.. --- ,. ' = ,
-Inside-
. 250. 400, 700. 750. 900. 900.
if~ -( ._ . _ . . . _ . . g
,; , ,;e +;,3 e3 x ' ' p g,j ;
,,'Inside'. . ' 200.> 350. 550. ~ 600. 600. 600.
, , ,w, -
'l ^l-' / { / /-
. /Inside/3 .
500. 1800. 1.P3 1.1P3 1.1P3 1.3P3 i
/ / / / /)/ -
t ' NOTE: Survey meter readingsof swipes in cpm are 1/10 of - icontamination values in'dpe/100 cmV. ,, Airborne, Radios,ctiviti Level . ML ,._ n
~
- - ;-_-...:.de'p/100ft? \
- 40. 60. - 40. 150. 240 340
..-Inside-t ejn/6 ft?' # - (20 42/0 <20 <20 <20 20
--- 20. 20. 20.
_--1. .; g t 131' <- '20. _20. ' 15. a %.I-133 80. 30. >- 70. 80. 80.
.' S0.
~ s
,,., I '
q' 3 - _[ h--U . .. ., f- s.w..'. . s ' - 8' i
'/f9',cpe/100 ft 8
'60.
. ,., . , . ' , 60f '80 120. 120. 120.
4,1 ;+
~
7'Inside' 'cpv/6.ft ~ 3 -
,"< 201- , <20 ..<20 <20 <20 <20 A e'e,e..e *E g;1 131.; 10. 15. 20. 20. 20. 20.
s L%'I-133 4Q. '.,60 r 80. 80. 80. 80. I[/://;/,/
/ cpm /100ft? .300c : 300._ 400.. 600. 1.P3 1.4P3 1/Inside/ ;cem/6.ftE . 1<20 :(20 3' 24, 40. 60. 110.
'/ /././ 6# f /J% li13F i("p :20 5 E'20. '_ _20. - -20. 20. 20.
/ kI-133 ? rys
- 80. ~ 780.'- 80 .- =80. 80. 80.
w"
- v
'[.
. q ag ; .,' - r
.}_ y .!
c. {/-' . , ' "f 'd 3, 3F '
. t :.anf: %,g, . -l >
. ql ~* . j q; -Q-
-~ r _' , , .
p., - -
-NRC/FEMI. OBSERVED EMERGENCY RESPONSE EXERCISE
( ; LIMERICK GENERATING STATION A Turbine Enclosure El. 200 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 Ambient Radiation Level (mR/hr) 1 15. 15. 15. 15. 15. A 2 8. 8. 8. 8. 8. 3 A
- 2. 2. 2. 2. 2.
.All Other Areas 3. 3. 3. 3. 3.
. ARM -04 3. 3. 3. 3. 3.
-05 3. 3. 3. 3. 3.
-07 20. 20. 20. 20. 20.
-34 3. 3. 3. 3. 3.
7 Contamination Survey (dpm/100 cm4)
-Inside- 1.P3 1.P3 1.P3 1.1P3 1.1P3 e i . .. .
-r~' 'Inside'- 800. 800. 800. 900. 1.P3 7( j-' e . .. . .
~ . -
,[,},,
/Inside/' 1.7P3 1.7P3 1.7P3 2.P3 2.P3
//////
NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm/100 cm4 _ Airborne Radioactivity Level
- - - - - -cpa/100'ft 3 500. 700. 1.P3 1.6P3 3.P3
--Inside- cpm /6 ft? 30. 44. 60. 100. 180.
- 20. 20. 20. 20. 20.
- .- - - - % I-131
% I-133 80. 80. 80. 80. 80.
' ' ' ' cpm /100 ft3 140. 180. 180. 200. 200.
'Inside' cpm /6 ft3- <20 <20 <20 <20 <20
' ' - ' ' % I-131 20. 20. 20. 20. 20.
-% I-133 80. 80. 80. 80. 80.
'/J/ / / / / cpm /100 ft3 3.2P3 5.P3 8.P3 1.2P4 1.8P4
/Inside/ cpm /6 ft4 200. 300. 500. 600. 1.P3
/ / / /-/ / % I-131 20. 20. 20. 20. 20.
, -~; % I-133 80. 80. 80. 80. 80.
t
..\%
,/ -
3F-17
v4 NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION [-s-]
^,-- Turbine Enclosure El. 217 Ft 1100 1400 1500 1600 1630 1715 1400 1500 1600 1630 1715 1730 Ambient Radiation Level (mR/hr)
I 120. 50. 20. 20. 20. 20. T 2 60. 25. 10. 10. 10. 10. T 3 T
- 20. 10. 3. 3. 3. 3.
~
-All Other Areas- 0.7 0.7 1. 1. 1. 1.5 h '-12 0.7 1. 1.
ARM- 0.7 1. 1.5 s
-13 50. 20. ~7. 7. 7. 7.
Contamination Survey (dpm/100 cm8) 4 .
-Inside . 400. 400. 400. 500. 600. 600.
4.34
.: [ \
.t']f 't f 'f'
~
f vt}s j ' 'Inside' 900, 900. 900. 900. 900. 900. A NOTEi . Survey meter readings of swipes in cps are 1/10 of
'*" - contamination values :bs dpe/100 cm%.
L, y LAirborne'Ra'dioactivity Level
- -"..- - -cps /100 ft3 400. .400. 400. 400. 600. 800.
4
-Inside- cpm /6;ft '_ 4 24. 24. 24. 24. 40. 50. c
% I-131, 20. '20.
- 20. 20. 20. 20.
% I-133. 80. 80. 80. 70. 80. 80.
' ' '"' ' ' cpm /100 ft3 300. 600. 1.2P3 1.2P3 1.2P3 1.4P3
='Inside' cpe/6.ft3
<20- - 36. 70. 70. 70. 80.
y -- - ~ r.*-*:'<* *: .% I-131 e
- 10. -20. 20. 20. 20. 20.
%'I-133 60.~ 80. 80. 80. 80. 80. . s,.
a f 4 n
%, [
3F-18 -
m.
)' NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
~ LIMERICK GENEP.ATING STATION Turbine Er. closure El. 217 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 Ambient Radiation Level (ar/hr)
~
l I 20. 20. 20. 20. 20. T 10. 10. 10. 2 10. .10. T 3. 3. 3. 3 3. 3. T All Other Areas 1.5 '1.5 2. 2, 2. ARM-: .-12 1.5 1.5 2. 2. 2.
-13 7. 7. 7. 7. 7.
Contamination Survey (dpm/100 cm4)
- .Q _ _ ... . .
Inside- 600. 600. 700. 700. 700. p,
~
) ., e, e s.
'Inside' 900. 900. 900, 900. 900.
~ ^
NOTE: Survey meter' readings of swipes in. cpm are 1/10 of contamination values in dps/100 cm%. Airborne Radioactivity Level
- - - - -epa /100 ft 3 800. 800. 1.P3 1.2P3 1.4P3
-Inside- cpm /6 ft4 50. 50. 60. 70. 80.
% I-131 -20.
- 20. 20. 20. .20.
% I-133 80. 80. 80. 70. 80.
' ' 'L' ' cpm /100 ft? 1.4P3 1.4P3 1.4P3 1.4P3 200.
N <
'Inside' cpm /6 ft?- ~ 80. 80. 80. 80. 80.
' '- '- ' ' ' % I-131 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
s k m .. 3F-19
' * " " +er +--e~-- . - - , - , - . . , . . _ , , , , , . , . . _ , , , _ _ , _ , , _ , . , . . _ _ _ _ . . __ _
T - NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION
-Turbine Enclosure El. 239 Ft 1100 1400 1500 1600 1630 1715 1400 1500 1600 1630 1715 1730 Ambient Radiation Level (mR/hr) 1 100. 40. 20. 20.. 15. 15.
8 2 100. 40. 20. 20. 15. 15. 3 20. 8. 4. 4. 3. 3.
.4 8 5. 2. 1. 1. 1. 1.
I p 0.5 0.5 0.5 0.5 1. 1. 2 0.5 0.5 0.5 0.5 1. 1. 3 0.5 0.5 0.5 0.5 1. 1. 0.5 0.5 0.5 0.5 1. 1. 4f
,. All Other Areas 0.5 0.5 0.5 0.5 1. 1.
' ARM -19 100. 40. 20. 20. 15. 15.
-20 100. 40. 20. 20. 15. 15.
j,__ Contamination Survey (dpm/100 cm4) t i
\, ,/. ___.--
-Inside-- 300. 300. 300. 400. 500. 600.
f- E :
'0 t f l'
' <100. <100. <100. 170. 170.
, Inside' .
<100.
//////
-/Inside/:. <100. <200. 700. 700. 700. 700.
//////:
. NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm/100-am"4
< SAirborne Radioactivity Le' vel
-:- - - - -cpm /100'ft4 320. 400. 400. 400. 400. 600.
-Inside- cpe/6 ft4 <20 26. 36, 26. 26. 40
- - - ~- -
. % I - 131 - 5. 15. 20. 20. 20. 20.
% I-133 50. 70. 70. 80. 80. 80.
'E ': ' cpm /100 ft? 40. 100. 120 140. 140. 340.
'Inside' -cpm / 6 ft4 <20 <20. .<20 <20 <20 <20
% I-131 10. 20. 20. 20. 20, 20.
~
% I-133 70. 80. 80. 80. 80. 80.
'y/
3F-20 N
5 4 . V'h :.
' "j ~ ,
NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LINERICK GENERATING STATION Turbine Enclosure El. 239 Ft (Cont) 1100 1400 1500 1600 1630 1715 1400 1500 1600 1630 1715 1730 I L/ / / / /./cpe/100 fts 120. 320 400. 400. 400. 400.
;;;, . /Inside/ cpe/6 ft4 <20 <201 24. 24. 24. 24.
////// % I-131 15. 20, 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80. 80. l
-s
. a i'-
1 4 ,-.g )
-v; 1
3F-21
. ~ , _ . _ _ . , - . _ . . _ _ _ - . _ _ . _ _ , - . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ , _ _ . _ -
l_: tj NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE [^ LIMERICK GENERATING STATION Turbine Enclosure El. 239 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 L Ambient Radiation. Level (mR/hr) 1 20. 15. 15. 15. 15. 2 20. 15. 15. 15. 15. i
-3
=
- 4. 3. 3. 3. 3.
8
~4 ,1. 1. 1. 1. 1.
1 p 1. 1. 1. 1. 1. 2p 1. f. 1. 1. 1. 1. j3 p 1. 1. 1. 1. 1. 4p 1. 1. 1. 1. 1. LAll Other Areas- '1. 1. 1. 1. 1. ARM -19 20. 15. 15. 15. 15.
- 20. 15. 15. 15. 15.
; Contamination' Survey (dpm/100 cm4).
f'~') ) - - , - 600. 600. 600. 700, 700.
-Inside-
... e i.
' 170. 170. 170. 200. 200.
s 'Inside.-
.'/ L/ / / / : /
~ /Inside/1 1400. 400. 500. 700. 700.
- / /:/ I'/ /:
INOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values ':ba dpm/100 cm4
~
Airborne ~ Radioactivity Level
-.- --- - -cpe/100 ft? 800 800 800 1.P3 1.2P3
-r '-Inside -cpe/6 ft4 '50. 50. 50, 60. 70.
- 20. 20. 20. 20. 20.
% I-131 _
o - -
'%-I-133 80. 80. 80. 80. 80.
' ' 'L epa /100 ft4' 400. '400. 400. 400. 600.
- 'Inside ,cpa/6 ft4 24. 24. 24. 24. 38.
.L' :' ' - ' 1% I-131
- 20. 20. 20. 20. 20.
7 9 ~y. % I-133 80. 80. 80. 80. 80. u ). 1
*L n 3F-22
s f~'}
\v' -
'NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION ~
Turbine Enclosure El. 239 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145
' ' ' ' ' ' cpm /100 ft? 600. 800. 800. 800. 1.P3
'Inside cpm /6 ft4 34. 48. 50. 48. 60.
' ' ' ' ' ' 20.
% I-131' 20. 20. 20. 20.
% I-133 - 80. 80. 80. 80. 80.
~ v i
.'.),.
'r t
4 e t LO 3F-23
p 1 s g. i
,s,p ,
) \ 'NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE c'-- LIMERICK GENERATING STATION I Turbine Enclosure El. 269 Ft 1100 1400 1500 1600 1630 1715 1400 1500 1600 1630 1715 1730 Ambient Radiation' Level (mR/hr) 1 100. 40. 20. 20. 20. 15.
G 2 50. 20. 10. 10. 10. 7. 3g 10. 4. 2. 2. 2. 1.5 fall Other Areas 0.5 0.5 0.5 0.5 1. 1.
/duf : -25 0.5 0.5 0.5 0.5 1. 1.
-57 0.5 0.5 0.5 0.5 1. 1.
Contamination. Survey (dpa/100 cmV) General- 500. 600. 600. 600. 600. k,j} ' ~ Survey meter readings of swipes in cpm are 1/10 of
~
NOTEi contamination values in dpe/100 cmV. 951rborne Radioactivity' Level
~
1;
; General cps /100 ft?
120. 120. 120. 140. 340. 340. cpe/6 ft? <20 <20 <20 <20 - 20. 20.
% I-131' 15. 20. 20. 20. 20. 20.
-% I-133- 70. '75. 80. 80. 80. 80.
9 4 b
-N. ) ,
3F-24
iv [ i '- NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE LIMERICK GENERATING STATION Turbine Enclosure El. 269 Ft (Cont) 1730 1800 1900 1930 2045 4i- 1800 1900 1930 2045 2145
~
~ Ambient' Radiation Level (mR/hr) 1 15. 15. 15. 15. 15.
2 - 7. 7. 7. 7. 7. 3g 1.5 1.5 2. 2. 2. Al'1 Other Areas 1. 1. 1. 1. 1.
' ARM -25 ' 1. 1. 1. 1. 1.
-57 1. .1. 1. 1. 1.
Contamination Survey (dps/100 cm4) General 600. 700. 700. 700. 770. g k_,)/ ' NOTE: -Survey meter readings of swipes in epm are 1/10 of contamination values in dpm/100 cm3 ~ Airborne Radioactivity Level General ~ cpm /100 ft3 -400. 400. 600. 600. 600. cpe/6 ft3 24. 24. 40, 40. 40
% I-131 15. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
4 e V. 3F-25
4 [ NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
's LIMERICK GENERATING STATION Turbine Enclosure El. 302 Ft 1100 1400 1500 1600 1630 1715 1400- 1500 1600 1630 1715 1730
~
- Ambient Radiation' Level (mR/hr)
I 1* l' 1* l* l' 1' F
.2 0.5 0.5 1. 1. 1.5 1.5 0.5 0.5 1. 1. 2. 2.
3h All Other' Areas 0.5 0.5 -1, 1. 2. 2.
~
ARM -28 0.5 0.5- 1. 1. 2. 2.
' Contamination. Survey (dpe/100 cmV) 600. 600.
~
' General '500. 600. 600. 700.
.f \
L~ J . NOTE: Surve'y meter rea' dings of swipes in cpm are 1/10 of contamination values in dpm/100 cmV.
~
f Airborne' Radioactivity Level 1 General cpe/100 ft4 200. .400. 640. 400. 800. 800. cps /6 ft? <20- 24. 24, 24. 50. 50.
% I-131 20. 20. 20. 20. 20. 20.
% I-133 80. _80. 80. _80. 80. 80.
c- ~.. 4 t., E + Yy .
.N~n',-
V 3F-26
,_ 'NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
; LIMERICK GENERATING STATION Af Turbiae Enclosure El. 302 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145
~
Ambient Radiation Level (mR/hr) 1 1. 1. 1. 1. 1. 7 2 7
-1.5 1.5 1.5 1.5 1.5 3 2. 2. 2. 2. 2.
F All Other Areas 2. 2. 2. 2. 2.
, - ARM -28 2.. 2. 2. 2. 2.
Contamination Survey (dpa/100 cmW) General 700. 700. 700. 700. 700. NOTE: . Survey meter readings of swipes in eps are 1/10 of contamination values in dpm/100 cm%. j-
-\j Airborne Radioactivity Level General-cpm /100 ft3 800. 1.2P3 1.4P3 1.4P3 2.P3 cpe/6 ft4 50. 50. 80. 80. 120.
% I-131 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
fD V l 3F-27
a 4. .J J -
~
l i l l
,cq 'NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE l f LIMERICK GENERATING STATION V Turbine Enclosure El. 321, 332, and 350 Ft I 1100 1400 1500 1600 1630 1715 1400 1500 1600 1630 1715 1730
' Ambient Radiation Leni (mR/hr)
I F 0.5 0.5 0.5 0.5 1.5 5. 2 7 0.5 0.5 0.5 0.5. 1. 1. 3 F 0.5 0.5 0.5. 0.5 1. 1. 4 7 0.5 0.5 0.5 0.5 1. 1. I *
- I* I* I* I*
N 2
. N 0.5 0.5 0.5 0.5 0.5 0.5 General-Elevation 321 0.5 0.5 0.5 0.5 0.5 0.5
-Elevation 332 0.5 0.5 0.5 0.5 1. 1.
-Elevation 350 0.5 0.5 0.5 0.5 0.5 0.5
. ARM -58 0.5 0.5 0.5 0.5 1.2 2. Contamination Survey (dpm/100 cm4)
/ ^T = General-Elevation 321 600. 700. 1.P3 1.2P3 1.2P3 1.5P3 if -Elevation 332 700. 800. 1.2P3 1.3P3 1.4P3 1.6P3
-Elevation 350 1.P3 1.P3 1.4P3 2.P3 2.P3 2.5P3
-NOTE: Survey. meter readings of swipes in epm are 1/10 of contamination values in dpm/100 cm4 Airborne. Radioactivity Level General-
-Elevation 321 cpe/100 ft4 120. 140. 200. 260. 340. 400.
cpa/6 ft4 <20 <20 <20 <20 20 24.
-% I-131 20. 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80. 80.
' Elevation 332 cpm /100 ft? 140 180 260 320 400 600, cpe/6 ft3 <20 <20 <20 <20 , 24. 40.
%:I-131 20. 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80. 80.
7 q 3F-28 I e ,
ry;- u
~
-^v NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
.( )- LIMERICK GENERATING STATION -
Turbine Enclosure El. 321, 332, and 350 Ft (Cont)
'1100 1400 1500 1600 1630 1715
-1400 1500 1600 1630 1715 1730 Elevation 350
-epa /100 ft 3 120. 160 200 240 280 380 cps /6 ft4: 72. <20 <20 <20 . 0.
2 22.
>4 % I-131' 10. 20. 20. 20. 20. 20.
% I-133 70. 80. 80. 80. 80. 80.
Aj : k h t
.Y.
pO S 3F-29 ; ll
NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE [_ ' LIMERICK GENERATING STATION NM) Turbine Enclosure El. 321, 332, and 350 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 Ambient Radiation Level (mR/hr) 1 8. 15. 25. 7.P3 2.6P4 F-2 1.7 3.5 5. 1.7P3 6.P3 F 3 1. 2. 2. 600. 2.P3 4 1. 2. 2. 170. 600. 1 2. 4. 12. 700. 3.P3 2 1. 2. 6. 350. 1.5P3 General-Elevation 321 1. 1. 2. 2. 2.
-Elevation 332 1. 2. 2. 3. 4.
-Elevation 350 1. 1. 2. 2. 3.
' ARM 4. 7. 10. 3.5P3 1.2P4 Contamination Survey (dpm/100 cm'4)
General-Elevation 321 1.7P3 3.P3 4.P3 6.P3 7.P3
-Elevation 332 2.5P3 4.P3 7.P3 9.P3 1.P4
-Elevation 350 2.5P3 3.P3 4.P3 6.P3 6.P3
. ('~ S 4
L v-NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm/100 cm*4 Airborne Radioactivity Level General-Elevation 321 cpm /100 ft4 800. 1.2P3 1.4P3 2.P3 3.4P3 cpm /6 ft4 50. 70. 80. 120 200.
} I-131 20. 20, . 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
-Elevation 332 cpe/100 ft4 1.2P3 1.4P3 2.8P3 3.2P3' 4.P3
.cpe/6 ft4 72. 84. 170. 190. 240.
g_ _ _
% I-131 20. 20. 20. 20. 20. -
% I-133 . 80. 80. 80. 80. 80.
Elevation 350 cpe/100 ft4 700. 900. 1.6P3 1.8P3 2000. cpm /6 fc4 44. 56. 100 110 120.
% I-131. 20. 20. 20. 20. 20.
%=I-133 80. 80. 80. 80. 80.
j 3F-30 L
.. .~
';_ NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
, 4 LIMERICK GENERATING STATION Ex_)' Radwaste Enclosure El. 162 Ft 1100 1400 1500 1600 1630 1715 I-1400 1500 1600 1630 1715 1730 L
' Ambient Radiation Level (mR/hr) 1 0.5 0.5 1. 2. 3. 5.
2 T 0.5 0.5 1. 1. 1. 1.5
=3 T
0.5 0.5 0.5. 1. 1. 1. All.0ther Areas 0.2 0.3 0.4 0.8 0.8 0.8 ARM- -41 0.2 0.3 0.4 0.6 0.8 0.8
-42 0.2 0.3 0.4 0.6 0.8 0.8 Contamination Survey (dpm/100 cm8)
g- General 300. 600. 1.P3 1.5P3 2.2P3 .3.P3
'u,) '
NOTE: Survey meter readings of swipes in cps are 1/10 of contamin~ a tion values in dpa/100 cm4 Airborne Radioactivity Level General-cpt/100 ft4 400. 5.4P2 800. 1.4P3 2.6P3 5.P3 cps /6 ft3 24. 32. 50. 80. 160 300
% I-131 10. 10. 15. 20. 20. 20.
% I-133 50. 60. 70. 80. 80. 80.
I b b 3F-31
$ NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE E- LIMERICK GENERATING STATION
.4[~ Radwaste Enclosure El. 162 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 i
Ambient Radiation Level (mR/hr) , I 10. 20. 40. 60. 110. T 2 T.
- 3. 7. 13. 20. 35.
3 T
- 1. 2. 4. 7. 10.
All'Other Areas 0.8 0.8 2.5 5. 8. ARM -41 0.8 0.8 2.5 5. 8.
~
-42 0.8 0.8 2.5 5. 8.
-Contamination Survey (dpm/100 cmV)
General 4.P3 6.P3 9.P3 1.4P4 2.P4 7- y Q,!.
, NOTE: Survey neter readings of swipes in cpm are 1/10 o'f contamination values in dpe/100 cm%.
Airborne Radioactivity Level'
.Ceneral-cpa/100 ft4 - 1.P4 ,1.6P4 1.6P4 1.6P4 1.6P4
, cpm /6 ft4 6.P2; 1.P3 1.P3 1.P3 1.P3
% I-131 20. 20, 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
n
,/ -
\ .
3F-32 s
3_ .. NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE I L LINERICK GENERATING STATION
'L s
Radwaste Enclosure El. 191 Ft (Cont) 1100 1400 1500 1600 1630 1715 1400 1500 1600 1630 1715 1730 Ambient Radiation Level (mR/hr) 1,. 1. 1. 2. 5. 10. 10. 2*Jg 0.5 0.5 0.5 1.5 3. 3. ~ h 3 7 0.5 0.5 0.5. 1. 1. 1. All-Other Areas- 0.5 0.5 0.5 1. 1. 1.
~ ARM -43 0.5 0.5 0.5 1. 1. 1.
-46 0.5 0.5 0.5 1. 1. 1.
-47 0.5 0.5 0.5 1. 1. 1.
. Contamination Survey (dpm/100 cmV) I
> ./( . General. 400. 700. 900. 1.P3 1.2P3 1.5P3 ds .h ..
NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm/100 cm3 1 Airborne Radioactivity Level , iGeneral-cpm /100 ft4 340 400 500 540 '800 1.2P3 cpm /6 ft3 20. 24. 30. 32. 50. 70. d
)
.% I-131 20. 20. 20. 20. 20. 20.
% I-133 40. 50. 60. 70. 80. 80.
l l i 1
\
V{ 3F-33
tr C
, pc - !'
NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE Lt
\- } LIMERICK GENERATING STATION Radwaste Enclosure El. 191 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 Ambient Radiation Level (mR/hr)
I n
- 15. 15. 15. 20. 20.
.2 g 5. 5. 5. 7. 7.
3 3 1.5~ 1.5 1.5 2. 2.
'All Other Areas 1. 1. 1. 1. 2.
ARM -43 1. 1. 1. 1. 2.
-46 1. 1. 1. 1. 2.
-47 1. 1. 1. 1. 2.
Contamination Survey-(dpa/100 cm4) 6;<x
-/ 1: General 2.P3 3.P3 4.P3 5.P3 7.P3
(_,/~ NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpe/100 cm4 Airborne Radioactivity Level General-cpe/100.ft? 1.5P3 2.P3 2.6P3 3.P3 3.6P3 cpe/6 ft4 80. 120. 160. 180. 2.2P2
% I-131 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
i . .
- d /j's i 3F-34 l.
u
, g: , -- .
o , g ,i; ,
- n
- r.
~ s r ' ** -
s 'NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE ([m ' LIMERICK GENERATING STATION Nd Radwaste Inclosure El. 217 Ft
~1100 1400 1500 1600 '1630 1715
;1400 1500 1600' 1630 1715 1730
~
iAmbient Radiation. Level (mR/hr)
, .:All14reas' O.2 - 0.2 0.4 0.5 0.5 0.8
~ ARM: ~-51 0.2 0.2- 0.4 0.5 0.5 0.8 Contamination _ Survey (dpm/100 cmV)
-Inside-- 100. 200. 250. 300. 350. 600.
.. J'Inside' 300. 400. 500. 600. 700. 1.2P3 2{7 g_t W
~
^
NOTE: Survey meter readings cf swipes in cpm are 1/10 of contamination values in dpe/100 ca?. ur ' Airborne Radioactivity Level
-- - - - - -cps /100 ftV
~
- 80. 120. 160. 220. 280. 360.
-Inside- cps /6 ft3 <20 <20 .<20 <20 <20 22.
- - - - - -% I-131 .10. 20. 20. 20. 20. 20.
% I-133 70. 80. 80. 80. 80. 80.
'_'~' ' epa /100 ft4 120 180 2.8P2 400. 5.P2 6.P2
'Inside'. cpn/6 ft? <20 <20 <20 24. 30. 40. ,
'+'~' ' '1'% I-131 20. 20. 15. 20. 20. 20.
jL I-133 30. 50. 75. 80. 80. 80.
. /-~
if 3F-35
. -. _ NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
] LINERICK GENERATING STATION
'N.
Radwaste Enclosure El. 217 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 Ambient Radiation Level (mR/hr) All Areas '1. 1. 1. 1. 1.
- fSe ARM -51 1. I' . 1. 1. 1.
Contamination. Survey (dpe/100 cm4) ' - 'e
-Inside . 800. 800. 800. 800. 800.
I 1 e .e e e-e l'Inside'- 1.5P3 2.P3 2.5P3 3.P3 4.P3
- e. , e e e ,
_ f3 <
%)'= ~
NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dps/100 cm4 Airborne Radioactivity ~ Level
"- - - - - ~-cpe/100 f t4 500. 700. .800. 900, 1.P3
-Inside- cpe/6 ft -- 4 30. 42. 48. 54. 60.
20.
- - - - - - -% I-131 20. 20. 20. 20.
% I-133 _ 80. 80. 80. 80. 80.
(jf. '
'cpa/100 ft3'
'1' '
800. I.P3 1.4P2 1.6P3 2.P3 V;; 'Inside' Ecps/6 ft4 50. -60. 80. '100. 120.
' ' ' ' 20. 20.
% I-131 -20. 20. 20.
% I-133 80. 80. 80. 80. 80.
g * - , g)
. 4 3F-36 f
-+
.,y .NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE
'l i- LIMERICK GENERATING STATION
~ Radwaste Enclosure El. 237 and 257 Ft
$;h. , 1100 1400 1500 1600 1630 1715
'S 1400 1500 1600 1630 1715 1730
'4
> Ambient Radiation Level (mR/hr) 1 D_
0.1 0.1 0.2 0.3 0.5 0.5 2 0.1 0.1 0.1 0.3 0.5 0.5 D 1 0.2 0.2 0.4 0.6 1.0 1.0 2 0.2 0.2 0.4 0.6 1.0 1.0 General-Elevation 237 0.2 0.2 0.4 0.6 1.0 1.0
-Elevation 257 0.1 0.1 0.2 0.3 0.5 0.5 ARM -55 0.1 0.1 0.2 0.3 0.5 0.5 Contamination Survey (dps/100 cm3) 3 sY
. General-Elevation 237 200. 300. 400. 500. 600. 1.P3
-Elevation 257 100. 200. 300. 350. 400. 700.
NOTE: Survey meter readings of swipes in cpm are 1/10 of contamination values in dpe/100 cm2 Airborne Radioactivity Level General-Elevation 237 cpe/100 ft3 80. 100. 120 180. 360. 300. cpe/6 ft3 <20 <20 <20 <20 <20 <20 t% I-131 20. 20. 20. 20. 20. 20.
'% I-133 80. 80. 80. 80. 80. 80.
U,a 3F-37
/N 'NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE Q' LIMERICK GENERATING STATION Radwcste Enclosure El. 237 and 257 Ft (Cont) 1100- 1400 1500 1600 1630 1715
~
1400 1500 1600 1630 1715 1730 Elevation 257 cpa/100 ft3 60. 80. 100. 140. 180. 200. if '
- cpe/6 f t3 <20 <20 <20 <20 <20 <20
% I-131 20. 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80. 80.
i
'[.
o i g x} t . r I-
-3
, ik) l 3F-38 J
[ s- NRC/ FEMA OBSERVED EMERGENCY RESPONSE EXERCISE. ('~) LIMERICK GENERATING STATION Radwaste Enclosure El. 237 and 257 Ft (Cont) 1730 1800 1900 1930 2045 1800 1900 1930 2045 2145 Ambient' Radiation Level (mR/hr) 1 0.7 0.8 0.8 0.8 1.0 9 0.8 0.8 1.0 2 0.7 0.8 D I g 1.4 1.5 1.5 1.5 1.5
, 2 1.4 1.5 1.5 1.5 1.5 9
-General-Elevation 237 1.4 1.5 1.5 1.5 1.5
-Elevation 257 0.7 0.8 0.8 0.8 1.0 3 ^2 -
' ARM -55 0.7 0.8 0.8 0.8 1.0
' ';;;;g. . - Contamination Survey (dpm/100 L cm%)
, -j4;
/ General-Elevation 237 1.2P3 1.5P3 1.6P3 1.7P3 2.P3 A,.
,)
-Elevation 257 800. 1.P3 1.P3 1.1P3 1.1P3
.+ . NOTE: : Survey meter readings of swipes in cpm are 1/10 of contamination values in dpm/100 cm%.
Airborne Radioactivity Level-General-Elevation 237
. cpm /100 ft 3 400. 500. 600. 700. 700.
cps /6 ft4 24. 30. 36. 44. 46.
% I-131 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
Elevation 257 cps /100 ft4 260. 320. 360. 400. 500. cpe/6 ft4 <20 20. 22. 24. 30.
% I-131 20. 20. 20. 20. 20.
% I-133 80. 80. 80. 80. 80.
-p
'd 3F-39
x If Y jy p .
~
' ~
- p. .
l l
)? ,
. (,f: , ,
f b NRC/ FEMA OBSERVED EPERGENCY REPONSE EXERCISE LIMERICK GENERATING STATION
~ -Area Monitor Readings (mR/hr)-
' Full '
ARM ~ Scale 1200 1400; ~ 1500 1600 1630 '1715 1730 1800 1900 1930. .2045 N). Location : Reading 1400 1500' 1600 1630. 1715: 1730 1800- 1900 1930 2045- 2145 RE-01.RCIC Pump _1.P4 100. 800. '1.4P3 ~ 2.5P3 4.P3 1.3P3 1.2P3 1.2P3- 1.2P3 - 1.2P3 '1.2P3.-l Compartment <
-02 HPCI Pump 1.P4 80. 300. 320. 320. 320. 320. 320. 320. 320. 320. 320. '
Compartment. .
-03 Sump Compart- 1.P4 1. 1. I. '1. 2. 20. 80. 200. 300. 350. 280.
ment-
-04 CRD Pumps' 1.P4 0.2 0.2 0.2 0.7' 1.1 2. -3. 3. 3. 3. 3. ,
Area
-05 Turb. Aux. Bay 1.P4 0.2 0.2 0.2 0.7. 1.1 2. 3. 3. 3. 3. 3.
Hallway
-06 Isolation Valve 1.P4 0.5 8. 50.' 80. 120. 160. 160. 160.- 160. 200. 240.
Compartment
-07 Condensate Pump 1.P4 90. 35. 20. 20. 15. 15. 20. 20. 20. 20. 20. '
Compartment
-08 RHR Div.I 1.P4 8. 8. 25. 80. 240. 1.2P3 5.P3 5.P3 5.P3 5.P3 5.P3 !
Compartment '
-09 RHR Div.II 1.P4 8. 8. 25. 80. 240. 1.2P3 5.P3 5.P3 5.P3 5.P3 5.P3 l Compartment
-10 Steam Vent Area 1.P4 0.5 0.5 2. 8. 15. 20. 20. 20. 20. 20. 20. '
Stairwell
-12 Hallway,Cond.Filt. 1.P4 0.7 0.7 -1. 1. 1. 1.5 1.5 1.5 2. 2. 2. t Demin. ,
-13 Condensate Area 1.P6 50. 20. 7. 7. 7. 7. 7. 7. 7. 7. 7.
-15 CRD HCU Area East 1.P4 0.5 0.5 0.5 1. 4. 3. 3. 2. 2. 2. 2.
-16 CRD HCU Area West 1.P4 0.5 0.5 0.5 1. 4. 3. 3. 2. 2. 2. 2.
-17 Neutron Mon. 1.P4 0.5 0.5 ' O.5 1. 4. 3. 3. 2. 2. 2. 2.
System Area :
-18 Neutron Mon. Drive 1.P4 0.5 0.8 4. 8. 10. 15. 20. 20. 20. 20. 20.
Mech. P 3F-40 C_ l
. 7,; ,
p u. -
- :c s 1
_ , , ,, p ;. < ? e_ . y . O_., 'l 1F
+v .
l fJ e
~
?(
3 , , :n
~ p .
V M
~
9 { <- e ' 3 .w ?. "L #
~
~
NRC/ FEMA OBSERVED EDERGENCY REPONSE RYNISE ' ' s
- LI!ERICK GENERATING STATION . ' '
s Area. Monitor Readings (mR/hr);(Cont)' , , Full . . 4
-ARM Seale- 1200. =1400 1500- 1600- 1630 >1715- 1730' 1800 1900 ~1930~ 2045V Ns. Location Readina 1400' 1500 1600 ~ 1630' 1715~ 11730 ;1800 1900 1930- 42045- :
2145' RE-19 Turb. Aux. Bay 1.P6 100. 40. '20. 20. 15. 15. 15.- 15. 15.- '15. -15. Hallway. East . . a
-20 Turb. Aux. Bay 1.P6 100 40.- 20. ~20. 15. 15. 15. 15. 15.. 15. 15.
Hallway West
-21 RWCU Heat 1.P4 0.5 - 1. .- 1. '2. 3. 7. 7. 6. 5. _5.. .5.- ,
4 Exchanger Area .
-22 RWCU Pump Area 1.P4 0.5 L1. 1. 2. '3. 7.. 7. 6. 5. 5. 5. ' .
-23 SLC System Area 1.P4 0.5 1. . 1. 2. 3. 7. 7. 6. :5. 5 .- 5.
-24 RWCU Instr. Rack 1.P4 1. 1. 1. 2. - 4.- 9. . 70. 100. 500. > 1. P4 - .>1.P4 Area
-25 Turb. Aux. Bay 1.P4 0.5 0.5 0.5- 0.5 1. 1. 1. 1. 1. 1. 1.
-27 RWCU Filter Area 1.P4 .1. 1. 1. 1. 1.5 30. 25. 35 .- 150.- >1.P4. > 1. P4 .
-28 Eq. Comp. Ex. 1.P4 0.5 0.5 1. 1. 2. 2. 2. 2. 2. 2. 2 .-
Filter Area
-34 H 2 /02 Analyzer 1.P4 0.2 0.2 0.2 0.7 1.1: 2. 3. 3. 3. 3. . 3.
Area
-36 OSC Area 1.P4 0.5 0.5 .0.5 0.5 1. 1. 1. 1. 1. 1. 1.
-41 Sludge Disch. 1.P4 0.2 ~ 0.3 0.4 0.6 0.8 0.8 0.8- 0.8 2.5 '5. 8.
Mixing Pump Room
-42 Radwaste Enclosure 1.P4 0.2 0.3 0.4 0.6 0.8 0.8- 0.8 0.8 2.5 5. 8.
Hallway
-43 Conc. Storage 1.P4 0.5 0.5 0.5 1. 1. 1. 1. 1. 1. 1. 2.
Disch Pump Room ..
-46 Fuel Pool Holding 1.P4 0.5 0.5 0.5 1. 1. 1. 1. 1. 1.- 1. 2.
Pump Room
-47 Precoat Tank and 1.P4 0.5 0.5 0.5 1. - 1. 1. 1. 1. 1. 1. 2.
Pump Room
-51 Radwaste Enclosure 1.P4 0.2 0.2 0.4 0.5 0.5 0.8 1. 1. 1. 1. 1.
Hallway 3F-41 C-
- a. .-. . .
., ,x . , ,
/ i ./
'\ j l \ i
, w .
/
.. ze- . %>
s
,r.
- s. .m ,
s . er ~. -
~
.-~ t.;
.y a
3.; y . ,f' *;Q 4 ..s *x 7 _L_ - ,,. -~ - ,L u _, ,- *~. W , , _ y "
? ': _J. ^M.
-g y'%
- n. -)
?
.f :
-:.p ],
i'* 3 -i. .~
- >, g- -.
~pf ' p
^ " .
, .NRC/EENA_.0BSERVED E ERGENCY REPONSE EXERCISE , . t _ g. l ' i' +
--" ' ? ' '
'~r 1 TL1hatTCK: MMFRATING STATI0tf ~.. 7 s
~
- ,6 s.,
[, ' Area henitor Reutlings1(mR/hr) (Coni) I ' '- f
a ,.
~ - - ;-
( ~; ",
-y~ .
x_'
. ._ y- 33.. . FGita q ,
N _ j' _- 3 ~, -
,WJf Scale ^1200: 1400 .2045 7[_^
l' ~ 1500 1600 IMOv 1715 -1730 _ 1800- ^ 1900 _ _1930 I No. Location Readina 1400- 1500 -1600 1630 1715 1730 1800 190a 1930 2045 2145 -
,q i.
- t. . - , , . .. -u --
~
.,g.
J18-55 Radwaste Ex. Faa' c 1.P4- 0.1 0.1.- ' C.2 - 0.3 _hi5 0.5 0.7 0.8 0. P. . 0.8 ~ 1. , u' .
; Area .- _
~
-56 Control Room 11.P4 J f .1_ ~ 0.1 , . c.1 0.1 ,
'W1' O.1- .0.1 0.1 0.1 0.T 0.1
- '57 T.are. ; Area 2.5 0.5 0.5 0.5 , . 1. 1.
-1. 1. 1. 't. 1. ! Operating Floor ' 1.P4 '
J
-58 SGTS filter Room 1.P4' i c.5 - 0.5 0.5 0.5 1.2 2. 4. 7. -10. 3.5P3 >1.P4
-60 North Stack Sample Rosa . 1.P4' .5 .5 .T .5 .5 .5- .5 .5 .5 1.5 100. 430.
\ .
l . . ~ 1 - . i i - 1 i t i 2 4 i l I t 3F-42 e
s
,I w-,.14
- N O
I T A T E S R G U N S I T L O A R C E N N
- w. E E G
R O'7 K C T7I C R1 A E ELM REu
~
7y 4 .
\ 1~ r .
. i.
- F. -
/ l l% . [ Y*1_X- / .
'*/.
/*p*..
7
/ .
/ /' ' .
{4 0 g0 u n3
~
A
?::
l
. ]
ll,, .. 4'/
.. - l.
/ .
/ ,.- s 'y 'l\1 '
/f)'.
~. '
' .J;w.7
^);
s l /' , .
/t .
. Y. ., ..
'2 -. .
/ -
/ '
&u I.
7 p/ j i
'M h",u n9., .
s )yff~ i
- w h
2 i. l . l
- }c
'g a
,\rW u5' g'i r a
p 7 .' O 0 l. s e/j //. w
*,u ..
=@a
, u as a
c
.j }] .
.[ R q.
- c. , Y*'
s^ q t_% , i' 1
~~q b5~
/ .
t e-i. 1M .,MJ~ 1
, c tl s v g%;
/ "
- N. . ,
C 4" m L a" r 2 f j 'l
- a. ?O 2].u. . .
[
'.. i.
g @ g e h e
'v,
, e ]
J' {n .
' I,,
;' s N
O j TI
;i A I
T 3-E S
;- R G x
U N
, S I O T
. - ' A L R f '
C E
, ?r -
N N
. E E t
G R e- ' O 'lKC TOI
' C2RE
, A ELMI REL n
3
. , 1 f
, xA 9g 1 - ,
=
)'
f
# {- 1
.!6 y\ ,
\
\
\
)
1ll
.)/.,
y- _ s
, A* , l1 l c j
~ j. r .
!4 s
x [
- s Ny%p\
Ny \ i
\
l b_.43 6 u xN. ns ao
'c
!4 s:
r . s/1 1
,'a. !e
. .v
% ,N
. (c.:
- . u' e no
\ A.
s ip h .!e r'y.' a 1 iy
.+
/ ~
k" ,
,/f/ / *YfI
?
// i,=
y-A
.. I
!6
//y7
,, 8 N\ J.
y/
/
N } ( M _ [L
~
!6 e e :g o W t,
a
~ ,
. , ,-a N
O I T A T E S R G U N S I O T A L R C E - N N E E G R'7 O T1C K C2RI
.EM A
- ELI REL h"f c-
- L
;- . = s
).
i t t
~
^
,\l g J o
- )
!s gq
) W l.,. o, N)
'7 ,,
g
$w/
ly'O.f' I.4 . k
- W, j
I . iI.6 S j
- f 5%w -
I.s l&~:. - e o 1lI [ ., k}, .. N /. ,_ L -
\
< . e
" 2 .
s 7i
! '. [l.
i4
~
"7_-.
W~ g y'tj-S g g g
,,i\ s.
F
N
~
OI T A T E S R
/ G U N S I q'
.- O T A
- L R C E
, N N E E G
R O'3 CK T5I R C A 2.EM ELI REL o
./
g
=
=I P Y
e =T { . _ , - % s a, "35
^ , ,
a , ,' 0
- ) i n
r i 2 - 'o K eC
' - 4 nO aL
.. 'st R
}j .
I i A
- o
'e s
l o K t I f , N j
\
,i,
. ~ l, O
- &7 7 ' , '
0
- , 2 f
~
1 I, L
~ ~
6 7.
. I 2_
a
'yr g 0 @
.(
1 I
a. 4 N O I T A T E S
- R G
- U N
% S I T
O A L R
v C E N N E E G
R* O3KC T8I C2R E A EL.MI
-. REL
, C
'h n..::y h_ e % @
g
~ -
- b
=. d
' 2 .
/
*f sp ld
- Y/*. ,
c s
'-~ .
' i ,
Id i
,e
- k. i' . ~ /
g
.' o , I
[ A [L b 3 U I F.
, )
a 4 I I i d r s L,D e g 9'WA
, C M
- R A 5
[] . . b l\l/ m
',L,s.
- /
r' Y
r s
~ N O
, TI
.y4 A 1 T E S 2
R G U N S I q O L T A R C E N N E E R G K O'3 T1C I C3R A .E EL IM REL s i
.t '
+
c s
, 7l.
1,d. _]* 7 - 4 i
;. 5* ' > .
).
3 l- . <
. I
;4 .1 y_ ,, -
.A - n 2 4 .
Aw. ~. m I b l "O
'1 3
3
~ .
Q L E F T
. 4 A
[ N
, 7 e .,. & *,
A L P L c ~. 1 _ E'_ A I O ,. ! T
. lo .-
lm
)
F U
. R A
.~ P
; 3i g s
d 3 . 9 t.. 4 .p - s A ' t + ' ., H' 7 -
.r '. V i
S,' . S c
,1' P , aA' s a hIF
- l. n s .E .
oT iE I' O ; 1t p,' 1uF i cD
; Isl
.[
a I' ' T_7
] Ia :
g . i n 7
,F j ,
,l' .. . ? .l .
i'-- s. e g g g
~
+
+ :s l
? i-W>: g
,,'r .
1
,5 e'- ,
8
?
,;y-
,.7-
. +
. n 'n s r
y N i.yy f- O I _
, q2-v- s,b_- - T
.~9?.
A i T _ E S
. c. '
R G cQ m f,y'-.- A . U N S
- O TI _
L A s .. 3 . C R E
.g".geY
.,,~;p ;
N N
.' ." , E E G
, e
(. R O'2 K T5IC
.v
. - c
- C3R A .E
,r" i ,
ELI M
' REL
,e s
,! r; e
/*i.
a I
-m M] t. -
- v
,gV .- '
f:;-
,,,<'a ~ : -
_s)-
- u e
, r n
^ ;
*,1
.y r
a
,N -
. 'n_ f/,s q-
.. p yc..
,;\
. {
.t', '
,9 S
A _
*t T E N E 7 .
E H R VT A
- 3. ,' . .
E G E N
. LVI .
- LL L I
OE R D VU N F E
. O I R
N r , i
~
s
.s i
- y. -
gps.; e
~ _
_( w ^ b e + ,
. yp{
}w I . *
- j h ; ;,111i 1t4$ e i4 lti 4 I,
9,-. +
, '".i , ,
e-:s. c';o .- ._ x
~
.g' a y ~ ==s - g
. m :
(' r Y $E O
,.' ,. . ;j .gg
,; 3 e- 2 z 1 k U w. zo ; ty'.
. g c ..
7
=~s m;=
1,..' F- W .J [ @( 1- ,
- s. ,._ **
'a **l ].
k M
'A u; -
. (sp.__. '
$.. .T x
Q ' . N
;;/ 1 i@ -
R d. Wem g- ,
\ .
N-1DI ill i.' - s
;- , 1 Ti !.
et O
\
~
ss
,,,ss s . .- -5 7 -_. .g et p ,
*l n
2, 3, O hk
- p-< .
g N L-I o . g..... .... .+ i i 1 0 0 0 * - E f4
_ m ;1"
;y; i, Q -
[ +
,'7 yly. '
f c K , s -
+.. '
..._' N n"y; s
~
', A g .
l O TI A u: 1 E S T r, R G U N s: S I T O A
- '~
l
's f, L R C
E H. N N =' E E G N CK E'7 I1 I
-i B 2R R .E
, ULIM TEL
. . -- i y-,
wm. -
=
.f . '
s. s i g b ?
' , _ f
; _ t l
-. \7' .
J-
- i .. - jI' i, + ,.
. l p.. - 4 !c n
r . ,
.b .
. s I ,C s ,
, y' i
e' IT' g d a S
^ _
j T
,Q
' ~
.S i.
l - l ic g' t
.f
{- . Q b 1^ -
.V ra
}
^
q I f i L
-s Lq_ .
a ' g" 2 t r.
. I. ^ ' l p %
(, I,* iJ
', i p b a
- . m I
r i g- t m
' J-l i.
- e. 2 T 2 r-
~
7 - . N T C y-
~ ,
s g T 2 t ei R3I Al i .. ..
,. ) )
( ' U O( _ V 7 3
.o n s} .s (
ss a
]
mpm
?
as -s
, uco f
[ s e
u gbUtL J . h i I T P s I e
-- _ i-
. ~. -
p G h p h C
(. ,_
~.
e- u , u
;IIi_ + li V k V- / L 1
- a!
i 1 = g
. e- r) g, 59;
~5 1
4'
,U jgj 8
av, n=d! E
\ :9' s!!
e- _\ \ 1
\ L J /_/_ .
~YN w/ y[ a ,
\ % J :/- > h N- . .W: ./ .-
E y
/ d I
/ (6 2;- ,
,P (N's lw () n N j )
(
+ .
[
= \
t
\
6 q N e-i (- r . i \ .a
- a. .
v c (, e-- y t. I
\ (3
_ 5 'h I) e --
\ n (I :' .
3
<-/
') p -
l u }\
\y g ,
m t 5 e-. - ae x~.. , t c) . e\x s- q, . y __ \m l ikxs \ i Nx e e 6 e 4 e 4 1
{- 1 l' . Qf " W '~-; - T '- - if - l , N O d Y ag. I T A i T
, E S R G U N S I 8 O T u7 A L ; m5 C R
E A N N =n T E E
> N G
- E E lC K E
N '9 C 6A i MF I6I ARU B2R
+
ES R .E L BR ULM I TEL R A O. N M UE SN O a O ART O EOA I R MB D I L OIR A g I r O NAR R T O O C N f Q n k .
\' , )/ f x7 2 ,G X J
2 IG k.I
.I/.
N.
.\'
4 T
}
E S 4-u P e u P C R I C E R R O T
M C R A E .
A R G y 2
/
s 2 j - i
, 'g g 3 3 s .
r t
- f. f L
k.I i
. sij i(\ -
k.I i
]
- k. - - _
O @ g e h g g
f N O I T A T
.!.f E S s
?
' - R G U h
.. S l g\%. .I- O T
,i n .
A
. L R
- C E N N E E G
.I E'2 N K C
. I0I R B
R 3 E ULI.M TEL s O _y I
+
i.
.l' r
2 m v n
. - a I
},,'
' O
" "r E.
s
'e i
f _ E
.l F / I iI f
- f. .
2 r t c~
.r 3 _
c g.
^
Q':-
. i I
,yY;
- i I J, y" , , ;t i I s
i I s
~
4
.'},'
' p
,l;'w.
t
.,t ,.
,p ._
O g Q"* ~
g -_
- p. -
s-
+
2 9 n, O' h'?$. J
%g e: E s w
< tJ o
- co'o U is5 ans (L M 3 f
3." ,*. J@ 4 - 3 m* tsN i N O o
- o
~r -j -f -;
N ~$ e*= A ;; n m
' s a a ,
" J
/v w W e-F ,,- A ~w k y
'/ 2 g ,
d
>t 3 < i
\f r a
= i Y h.
\ .
~
i g
~M g I
/~~ A
! ! 4'
(' )
./ -
L
a . . > .4
,3-<
T; T' N
~
s O [ TI E A R T S al'
/ U
' S"O G T OIN L'2 T T (
% C6 RA N1 E . E LN j ' EEEG
~
TT SAK A C
~
WNR I DAE M AL I RPL ef
. 'e
$i(3j '
T ?c na T N a l E r 8e =. u ,,,
-Ov o c
a
/g r 2 i P
m .a . y'y. g 0 om, 1 V i
,Y E p 6j
= 3 7
=
- 3 ]1 k -
v_ p
.a le e2 R
A4 , n 6 I Q 2 5 s 7" r ]s b L n6 0 4 - - ~
. P 1
~
4 Ii Ja y f. p s *. -
-r y' x
- 1;
,+ ,# ,
< - , i s e
p g e t b
\ , c h
h h O 0
')*
=
f
}
5 g% :.f ; w-
'(
2'-
. ,. N
=
' > - OI v -
E T f
' A F
R T r U S S G O N L T I C A N R E E N E E T G S K A '1 C W9I D 1 R E ALI REL M (
)
c
+
,.s 7.
g-s b 7
^
s h ' l n* =? F g .a * - lg e E 6; . ; 1
}6
- i. 1 j
. ;g .
r I ! c T l i
.3 41i ::
4 / i.
. =W -
I . .
}6
- 9. ' ..
. _ - . _ ~
~ _
i g h'
. 9. I -
7 9.' p. q.! . . l e, g e
@ g bh M
'N
/,\'
m
n N O I E T R A T U S S"O OGN L'7 C T I 1A N2R E .E LN EEE T G STAK A C WNR I DAE ALM I RPL X C
. jT!/-
i l 5 rl
? ;
02 g U _ A< b - -
~'
i nE
- _F u m Ill ,
2n uD OU l l a L 5 . .
-_ 7 l
i 0u hL 1
- ~ - "
g e b e @
j? X. ( p;i . . N OI T E A R T S U "O S G j O *- IN L7 T C3 A N R N .2"O E E
) :-
E LE N E '7 G
'. TT5 SA2K s
A .C WNLR I
" DAEE AL M RPGL I
.1 g
W j O g O- S "c e_ _. h' ._ . I W f 2
~
I "O L e . . 7 3
,,'l' l ,
j 2
.. L F
4 E
. T A
-._ u F
I N
. A
. - L P
I . .- .
. 'M
.i " *
~
, 0 2
g - I
*I .. .
'O r
o '7
*l l 5
2 L E T
. A
.5 N
.i A.8 m... . A L
P
'lI
'I I
r.
~ /_ ,i 'T E
, . , m
.<- - o < t ,-- ,- ..
l 't 'l .$ ) LJ - G Q,i;
, EVENT
SUMMARY
Event' No. Time : Location - Description Initiation: Page Number 1 1105 Turbine Enclosure Fire. Instrument Air Compressor Cont.rol Room Message ' 3G-1 2 1430 Radwaste Enclosure Contaminated Injury . Control Room Message 3G-4 3 1600 North Parking Lot Construction Workers Site After Alert Declared 3G-17
- Evacuation 4 1615 -Reactor Enclosure RHR Pump B Flow Decreases Control Room Message 3G 5 1650 Reactor Enclosure Search & Rescue Control Room Message 3G-21
.6 1715 Turbine Enclosure - Co2 Storage Tank Low Press. Control Room Message 3G-23 7 1730 Reactor Enclosure Fire in RHR Hx Room Control Room Message 3G-25
. 8 1845 Reactor Enclosure Purge Exhaust Line Leakage Control Room Message 3G-28 9 1900 Chemistry Lab. High Activity Cooling Tower Chemistry Controller 3G-33 Sample Message 10 2040 Reactor Enclosure Core Spray Pump A Trips Control Room Messara 3G-35 3G-0 m
'P' iE i(/ EVENT NO. 1
'; Fire at The Instrument Air Compressor (IAK101)
~
' Approximate Time
^ of Event: 1105 Location: Instrument air compressor (1AK101) area in turbine enclosure el 217 ft-0 in.
??roblem: Fire has broken out at the ingtrument air compressor (IAK101) and is spreading. The sprinkler system in the area is inoperable and the fire threatens the nearby lube oil storage tanks.
- Response: Dispatch Fire Fighting Group members to the scene. l They will determine that assistance will be necessary from Linfield/ Limerick Fire Department.
The fire is extinguished at 1145. Controller
. Locations: One in the area.
-j.
q . L, i
)
FOR CONTROLLER USE ONLY O 3G-1 1 J
- =:
t (. . 7N r
=t
\ /
v DRILL / EXERCISE SCENARIO FORMAT EMERGENCY PREPAREDNESS DRILL i DRILL TYPE / EVENT NO. 1 ,
, CUE CARD NO. 1-1 FOR: FIRE FIGHTING GROUP MEMBERS TIME: 1105 LOCATION: TUR8INE ENCLOSURE 217 FT-0 IN., EL THIS IS A DRILL j- DO NOT. initiate actions affecting normal plant operations.
;, Instrument air compressor 1AK101 is on fire. The sprinkler system in the
-area is - inoperable and the fire is spreading rapidly to nearby lube oil fm storage tanks.
- . (s._ --.
;;n-_n ----n,--nn Nb;N;; __ ;N;;;N ; ; ;;;; N-- bN THIS IS A DRILL
_;_-_ ;;.-_ :::.:: ; :;;;;;;_;;;; :.;;;;;;;;;;;;;;;_-_ a;;;;;;- ;;;-- ;;;;.-_ -
, -(
f %, ,
.A k'
\
v l 30-2
. ~ . . - - . -.
- 0
-~
- / s
-s - DRILL / EXERCISE SCENULIO FORMAT I:
I J EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 1 CUE CARD NO. 1-2 . FOR: FIRE FIGHTING GROUP MEMBERS TIME: 1145 LOCATION: . TURBINE ENCLOSURE ; 217 FT-0 IN., EL THIS IS A DRILL ,
-DO NOT initiate actions affecting normal plant operations. ,
-FIRE IS OUT.
THIS IS A DRILL ,
- . . . .-e. .
I 1 i i /
/
N v-30-3
EVENT NO. 2
.f 3 kj Contaminated Injured Individual Approximate Time of Event: 1430 Location: Fuel pool holding pump 00P340 in radwaste enclosure el 191 ft-0 in, Rm 236B.
Problem: An assistant plant operator who was dispatched for routine inspection in the radwaste enclosure is found unconscious lying in a puddle that appears to be leakage from the fuel pool holding pump (00P340). He is bleeding from a head laceration. Response: The Search and Rescue /First Aid group should be dispatched to the area. Remove the man's contaminated clothing, put him in clean anticontamination clothing, and escort the man out of the radwaste esclosure to the personnel decontamination room where he should be externally decontaminated and be prepared for transfer to the Pottstown Memorial Medical Center. In the medical center, he should be treated for his bleeding from
.. ;-w the head laceration and then released to the RMC ,x-( y) for . treatment of possible internal contamination.
Controller Locations: One initially in the radwaste enclosure and then in the ambulance going to the Hospital. One at Hospital. FOR CONTROLLER USE ONLY n y' 3G-4 m
m ,-s. , ( l -( ) x _,/ ,
'\s__/
TABLE 3G-4A" CONTAMINATED OPERATOR'S VITAL SIGNS Right After_ Injury Ambulance Arrives Leaving Ambulance . After Hospital (Unconscious) (Conscious But Disoriented) Proper Care Improper Care Treatment Pupils Dilated Dilated Dilated Dilated Dilated Responsive Responsive Responsive Responsive Responsive Blood Pressure 106/76 90/60 110/78 80/60 120/80-Pulse 100 116 116 120 88 Skin Pale, Cool Pale, Cool Pale, Cool Pale, Cool Normal, Warm Clammy -Claamy Clammy Clammy Dry Respiration 12 16-18 16-18 18 12-25 3G-4A
, DRILL / EXERCISE SCENARIO FORMAT
\'
, s/
EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 2 CUE CARD NO. 2-1 FOR: OPERATOR INSPECTING RADWASTE ENCLOSURE TIME: 1430 , LOCATION: RADWASTE ENCLOSURE 191 FT-0 IN., EL; RM 236B
*-: :. :. : :. :.:. :. :. ;. a a ;. ;, a ;. :. :. :. :. : :. : a a ;. :. :. :. :. ;. ;. ;. :. :. :. :. :. :. :. ;. ;. :. :. ;. a a ;. :. :. ; ;. :. :. :. a a a a ;. :. a a a a THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- . ;, ::. a a a ;. : :. a ;. ;. :. ;,;. :. :. a ;. :. :. :. ;. ; :. :. ;. :. : :. :. ;. ;. ;. a a a a a ;. :. a ;. ;. :. :. ;. :. :. a ;. :. ;. :. :. a a ;. :. a a ;. a a ;. : :. :
i
)
x,-,. YOU SLIP AND FALL IN A PUDDLE NEAR FUEL POOL HOLDING PUMP (00P340). YOU GO UNCONSCIOUS. azazaa :azzazzzzazazza ::a :::::::::::::::::::a ::::aaa :::::::aa:::a ::::: THIS IS A DRILL aaaaaa :::::::::::azzza:azza:aaza aa azaazzazaaaaa ::::aaaa :::::::::a az'
/m'g .
~
/
v 3G-5
p DRILL / EXERCISE SCENARIO FORMAT a > EMERGENCY PREPAREDNESS DRILL t
. DRILL TYPE / EVENT NO. 2 CUE CARD NO. 2-2
.FOR: ' PERSON FINDING THE INJURED OPERATOR TIME: 1430
.. LOCATION: RADWASTE ENCLOSURE 191 FT-0 IN., EL; RM 236B A;;;;;;;;AA;;;;;;;A;;AAA;;;A;;;;;;AAA;;AAA;;;;;;AAAA;;AAA;;;AAAAAAAAA;AAAAA THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
,-.s ;,1,;,;;;;,;,;. A A A A A A A A; A A A;,;,;.;,;, A;,;,; A A;, A;,;,; A A;, A;, A;,;,; ;,;;;, A A;,;,;,;,;. A A A; ;,;,;,;, A A A; ;,;,;. A A A
- s.
'%.J THE MAN IS UNCONSCIOUS LYING IN A PUDDLE THAT COULD BE LEAKAGE FROM FUEL POOL HOLDING PUMP.(00P340). HE IS BLEEDING FROM A HEAD LACERATION.
A;;;;;;AAAA;;;;AAA;;;AAAAAAAA;;;;;;AAAAAAAAAAAAAAAAAAAAA;;AAAAAAAAAAAAA;;AA THIS IS A DRILL A1,; A A;, A A;. A A;. A; A A A A A A A A A;, A A1,; A A A A A A A A+A A A;, A A;,; A A A A;,;,;,; A A;; A A A A A AA A A;. A A; ;, A;, A A s
/
1 ,l
\ .s/ '
3G-6
.,y
- \'
DRILL / EXERCISE SCENARIO FORMAT EMERGENCY PREPAREDNESS DRILL
- DRILL TYPE / EVENT.NO. 2 CUE CARD No. 2-3 FOR: SEARCH AND RESCUI/FIRST AID GROUP LEADER TIME: 1430+
LOCATION: RADWASTE ENCLOSURE 191 FT-0 IN., EL; RM 2368 THIS IS A DRILL
~
DO NOT initiate actions affecting normal plant operations.
/
- rw - ; - - - - - - - - - - - ; ; ;
.( /.
^
.-------------..------ ----r.- -----rw--------.u-rw---rwr. - rw sw -
THE MAN IS LYING UNCONSCIOUS WITH HIS MANDS AND FACE IN A PUDDLE THAT LOOES LIEE LEAEAGE FRON FUEL POOL HOLDING PUMP (00P340). HE IS
. BLEEDING FRON A READ LACERATION.
GENERAL ARIA RADIATION 1.0 MR/MR INJURED EXTERNAL CONTAMINATION LEVELS UP TO L20,000 CPM (SURVEY INSTRUMENT).
--------------------- :---- :: a z ------- :---- :- z z z ------ :: ;; a -- :e THIS IS A DRILL e
r, su si n av rw evei rv av - av - su rw r= ri - ei n av rw ev av - - rw re es - - es e 59 - rw av rw sw
- av rw rw rw ru rw - n ru ru ru ru rw ri n rw rw r= n sipu
,y,
.i 1 Ad B
/ 3G-7
- U' )
y 96 , l i 1l,; 5 :. '
, l \
_/: DRILL / EXERCISE SCENARIO FORMAT l s !
+ l EMERGENCY PREPAMMm DRILL
~ DRILL TTFE/ EVENT NO 2'- CtB CARD NO. 2-4 l ,-
l FOR: SEARCN AND MSCIE/FIMT ' AID GROUP LEADER TIMES. 1430+ PERS0IORL ' l l t LOCATION: DECONTAMINATION AMA , l THIS IS A DRILL !. I M initiate actions affecting normal plaat operations.
- / __ ____ ___ __ _ _ __ _- --__- ___ _ -____ --- -__ _ __..______ _ _
l
^3 'u }J i
CONTANINATION LEVELS AFTER REMOVAL OF SNIRT d- (SUWEY INSTRtRIENT):- [
' RIGET ARM - FRONT FROM SHOULDER TO WRIST '
2,000 CPN RIGrf SIDE OF FACE, JAW, AND LIPS 10,000 CPN LEFT MAND, WRIST, AND FOMARN 6,000 CPM [ 1 1 ______________________________________=_-_==_;.____=:.....:._ t I r TNIS IS A DRILL [ ( u z u = = u ;. u u u = = :. :. .- :. a = _ .. , .. u _ _ .. . .... :.= , a u u:. -. :--..:.=-..=:.
,l
! {
,/
30-8 L _
I
/
l l ' I I : i i I !I i I i t , t ii i i i I m / 'N A
! ! i I ,
i
! ! i ! ' i j ( , \ l i i + i f \ \ 1 / i i i . -
/ -JNi / ' i
.l l } / [ TJ G L_ -_
i'i .
/ / l T ,
. I t i / / J \
i ! i n s.cn -
/ / / '
./ m i \ t s. f r s ' i v nn ,]'
_ { ! ff /\ \1 n p Nm
' I i - U/ / /; '
il l'N A i + t < f I / / ( I A li
/
~
; : t / / i
/ \ I I l ' \
, ' ,) 1 ( '
I \ '
\ s I t ._ _1 t. l .} '
('
- J l
]. I Lf / d I
( - i , f '
- k. I , d ff \1 L lA i '
i i II ., I,,Y (*/ 'l. ! l \N ;
- !: I 'I l' ;
I' A_. + vt '
/
mi; y, ,it i u - vy t -
! Ii j it i i i J,., - "~
] / 'I V l
; p ; - El i i
- T / l\ !
. .n -
l } i i , l , I I\ l CO Al r A Mild AN!c.M l / I E, ' l AW d n i i l I ' I. i_
>: i !I i t l' I iii _ _ _ ,
I 't i I
. i i i i i i ,1 '
; i ,
- 1) I l I
("I i ; - l t : I e , , I l l l
~-1 : I
, i e - ,
) '
I e i !
' '
- I /1 } _ li l% l
. . i I I , Il '
/ / l NN l j 6 i i ;. i t i i I 'T II _! Pt I : I i l'igure 3G-2+ t Contaminated Arcas of Ilocly i
3G-9
t 4 DRILL / EXERCISE SCENARIO FORMAT 4 L EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 2 CUE CARD NO. 2-5 FOR: SEARCH AND RESCUE /FIRST AID GROUP LEADER TIME: 1430+ LOCATION: DECONTAMINATION AREA
;;;;AAA;;;;;AAAAAAA;;;;;;;;;AAA;;AAA;;;;;;;AAA;;;;;AAAAA;AAAAA;# :A;;AAAAAA l
THIS IS A DRILL D0 h0T initiate actions affecting normal plant operations.
;;; A A;. A A A A;;;;; A A A A; A A A A A A A;;; A A A A A A A A A;; A A A A A A A A A A A A A A A A A A A A;; A A;;; A;; A A A A t
CONTAMINATION LEVELS AFTER INITIAL CLEANING OF CONTAMINATED AREAS ARE (SURVEY INSTRUMENT): RIGHT ARM - FRONT FROM SHOULDER TO WRIST <100 CPM RIGHT SIDE OF FACE, JAW, AND LIPS 3,000 CPM LEFT HAND, WRIST, AND FOREARM 2,500 CPM
***** A ;. a :. a A :. :. A A a a a A ; ;, :. ;. :. :. A A :. :. :. :. ;. :. :. :. ;. :. :. ;. :. A :. ;. ;. :. : A :. ; ;. A :, a A :. ;. ;. a :. A a :. :. A . : :. :. A :. :. A . :. :.
THIS IS A DRILL A A A A A A A;. A A,. A A A A;, A A;;. A A;. A A A A A;;at.; A A A;;;;;;;;;; A ;;;;;;;; A;;. A; A A A A A;; A A A A A A A A 30-10
\
/
im 5 D DRIII/E}2RCISE SCENARIO FORMAT E_MERGENCY PREPA. REDNESS DRITI DRIII TYPE / EVENT NO.'2
- - .' s CUE CARD NO. 2-6 1430+ I FOR: SEARCH AND RESCIE/FIRST AID GRO,UP I2ADER - _ 'JIME:
.w..
w ~ LOCATION: DECONTAMINATION AREA t
. - s u . . :. ;. . ; :. :. ;. . ;. :. . ;. :. ;. a u :. ;. :. a a
******* :. ; :. : :. :. ;. ***++++t. ;, ;, :. :. ;. :. .a ;. :. :. ;. :. :. ; :. :. ;. ;. :. : :.
<. s s
THIS 13 A DRILL ec. DO NOT 'initiaca actions affecting normal plant operations.
;. ; ;. ;. :. ; ;. ;. ;. :. .d.+ ;. ;. ;. :. ;. :. :. ;. :. ;. :. : : :. ;. :. ;, :. :. :. :. :. ;. :. :. :. ;arws**+tra ;. ;. ;. :. :. ;. : xkt-k+*******
I m. D F CONTAMINATIONLEVELS'AFTr22NDCLEANINGGF ' ls - CONTAMINATEIi' AREAS.ARE (SURVEY INSTRUMENTN s - - RIGHT SIDE OF FACE, JAW, AND LII'S ,
<I00 CPM LEFT HAND,4 WRIST, AND FOREARM- - 1,500.CPMN
; a ; :. : :. ;. :. ;. :. ;,:+r*+M :. :. :. ;. :. :. :. ;. ;. ;9 **mr+k+*s****bcw+vs+*+msw : :. :. :. :. :. ;, :. ; :. a ;. a :. -k
+ ,
~
"- c THIS IS A DRILL' .
< - ~
- ; ;. :. :. :. :. :. ;. :. :. :. :. ; ;. :.-t******s c
. .. . .. . . . . - .v;. :. :. :. :. :. :. :c*< p ;. ;. ; ; ; ; ; ; ; ;. : : ;*** . m
, , - . y- .t N % % 4 y ,
., \_
. s,
/
s A P
.4 , s5 J
t f
$_ b
-it' ,, _
d f A ,. l
-~ -
- e. . , s -
, .~.; .
et \: ., ,
- \ j < *2 l ', ' ( -
~'
;% / ,
p- . .
.r. >
y jf- ~m3G-11
/
' , ~~
'-m tw -
e d *- e --- -dw*g-,s e s + -rww, w * - * - - + e es-we--+c-*w---~e*wr-n-e--r- w w e m 'a --e-m * -
w r ,y : :
~,.
h I
,, /
\'
k.,[ ' l DRILL / EXERCISE SCENARIO FORMAT I
~
EMERGENCY PREPAREDNESS DRILL i I CUE CARD NO. 2-7
~
DRILL TYPE / EVENT NO. 2 n )FOR:I-SEARCNANDRESCUE/FIRSTAIDGROUPLEADER TIME: 1430+ LOCATION: DECONTAMINATION AREA ~ TKIS IS A DRILL
.DO NOT ' initiate actions s'ffecting normal plant operations.
4- - ., u . R R :. :. :. :. : :.;;.:.:.:.u ; ;. :. :. :. :. :. ; ;. :. = ; ;. RR Ru ; , ;. :. :. :. :. :. :. ; ;. ; '. :. :. :. :. :. :. :. R ;. :.= :. : :. :. , :,c~._ i CONTAMINATION LEVELS AFTER 3RD CLEANING OF CONTAMINATED AREAS ARE (SURVEY INSTRUMENT): l LEFT HAND, WRIST, AND FOREARM 1,000 CPM
. RRRRRRRRRR8 RRRRRRR R RH R R RR R R i
THIS IS A DRILL F.p.p.W.p.p'.F.p.F.F.F.F.F'.f. H f.F. f. R E, f. RI.E.E.E.E. R R R E.R R E.E.ERORRERERRERRRRRRHE R R RRRRN R t ": [ .
- i. '/
- .{ W Y. -
z.
. ~\ '
Lc ' 3G-12 L'_
. / ~, .
(d). DRILL / EXERCISE SCENARIO FORMAT EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 2 CUE CARD NO. 2-8 l FOR: HOSPITAL STAFF TIME: 1430+ LOCATION: POTTSTOWN MEMORIAL MEDICAL CENTER
- . :. - - . :. ;. :. :. ; ; ; ;. :. . z : : ;. ; ; ; ;. :. ;;. :. ; ;, ;. :. ; ;. :. . :. :. :. : : ; ;. ;. :. :. :. :. :. :. :. :.m+**
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
-------- ;---- ::::::a;;;;;;;;; ;;;;;;;- ;;;; az ;; : ;;;;;;; ;;; ;;;;; ;;; i
_,-~ a,,
\ .
MAN'S CONTAMINATED TO (20,000/1,000)' CPM
- ALONG WITH INJURY.
- DEPENDING ON WHETHER HE WAS DECONTAMINATED AT LGS.
----- ;;;; ;;; ::::: ;;; : ::::: :;;;;;;;;;;;;;;;;; a ;;;;;;.;;;;; ;;;;;;;
THIS IS A DRILL
-------- : :- ::::: :::: ;;.;; ;;;;;;;; zaz;;;;;.;;;;;;;;;;;;;;;;;;;;;;;;;;'.
/
. -:/
P if 3G-13 I
1 1
,,-~,
( ) b' DRILL / EXERCISE SCENARIO FORMAT l EIERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 2 CUE CARD NO. 2-9 FOR: LGS HEALTH PHYSICS TECHNICAN TIME: 1430+ LOCATION: AMBULANCE GOING TO POTTSTOWN MEMORIAL MEDICAL CENTER
------ ;;;;;;;;;:---- :: -- ;; ; a ::a;;;;;;;- ;;;;;;;;;;;;;;;;;;;;;;;;;
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
. ------- ;;;- ;;;;;;;; ::;;;;;--- za;;;;; -- ::: a;;;;;;;;;;;;;;;; ;; ;;;;;
~
f"'(
;( ) CONTAMINATION LEVELS INSIDE THE AMBULANCE ARE
* ~ LIMITED TO THE STRETCHER (400 CPM > BKGND).
----- ----- -- EI -- -- --- ----- ---- - r - NE -
THIS IS A DRILL
;;;;;;;;;;- :::azazaza ;;;;;;;;- :.;; ::::.;;;;;;;;;;;; ;;;;;;;;; : .;;;;;;
l i-i i 1 I J m i 3G-14 I , +-
(D t *
.V. DRILL / EXERCISE SCENARIO FORMAT EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 2 CUE CARD NO. 2-10 FOR: LGS HEALTH PHYSICS TECHNICIAN TIME: 1430+
LOCATION: AMBULANCE GOING TO POTTSTOWN MEMORIAL MEDICAL CENTER THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- nnnaza;;;n:::: n n a ;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
I . CONTAMINATION LEVELS INSIDE THE AMBULANCE AFTER
~ w/ DECONTAMINATION ARE 100 CPM BKGND.
n n n n n n n n n n n n a. n n n n n e. n n n n n nnn n e n n si n e n e. n n n e. n n n n n annnnna nn n r. n n s. n n n #. n n F. THIS IS A DRILL
;;;;;;;nz;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;.;;;;;;;;;;;;; ;;;;;;.;;; n ; ; ; .. . :. ;
i.5
. /^g .
( ) v, 3G-15
l 7 ,.; ) [ -DRILL / EXERCISE SCENARIO FORMAT EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 2 CUE CARD NO. 2-11
! FOR': WHOLE BODY. COUNTER OPERATOR TIME: 1430+
P . LOCATION: WHOLE BODY COUNTER * (LGS, RMC) THIS IS A DRILL ~ DO NOT initiate actions affecting normal plant operations.
.W
-( SCAN INDICATES NEGATIVE FOR POS9IBLE INGESTION
\_eJ' 0F RADIONUCLIDES.
- SIMULATE THE EVENT IF WHOLE BODY COUNTER IS NOT ACCESSIBLE.
. THIS IS A DRILL V
3G-16
m 1 N, {/ .
-A. EVENT NO. 3 Preselected Construction Workers Site Evacuation Approximate Time of Event: 1600
- Location: North parking lot.
Problem: After an " Alert" has been declared by the control room, preselected Unit 2 construction personnel
'should evacuate.
Response: All preselected construction workers should report to North parking lot for personnel accountaoility. Controller Locations: One at North parking lot.
'd-i k FOR CONTROLLER USE ONLY
. k-
~
%,/
3G-17
fy
/-
~
EVENT NO. 4 RHR Pump (IBP202) Discharge Flow Drop Approximate Time of Event: 1615 l
-Location: RHR discharge valve (HV-51-1F047B) in reactor enclosure el 217 ft-0 in.
'Probles: Discharge flow on RHR pump (IBP202) starts decreasing to 500 gpa. There are no apparent problem indications in the control room.
Response: An operator is sent to investigate the problem locally. An extremely loud noise is heard at the RHR discharge valve (HV-51-1F047B). The valve has partially closed and the operator's attempts to manually open the valve are unsuccessful. Due to the noise, the operator does not hear the announcement to evacuate the reactor enclosure at 1630, nor can he clearly consunicate with the l > control room. Finally, a Search and Rescue /First
, Aid Group finds him and asks him to evacuate the -i reactor building.
Controller Locations: One accompanying the operator from the control room.
's l
FOR CONTROLLER USE ONLY O 9, 3G-18
?/"
f DRILL / EXERCISE SCENARIO FORMAT EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 4 CUE CARD NO. 4-1 FOR: CONTROL ROOM OPERATOR TIME: 1615 LOCATION: CONTROL ROON
***************1. :. ;. ;. :. :. :. :. ; :. ;. ;. :. ;. ;. ;. ;. ;. :. ;. :. ;. ;. ;. :. :. ;. :, : :. ;. ;. ;. ;. ; :. :. ;. ;. ; :. :. ;. :. ;. ;. ;. A ; :. = ; :. :.
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- ;;--R---------;;;;;; A ;;;;;- ;A;;;;;;; A- : ;;;;A;;;;;;;;;AA ;A;;;;A;A;A c . THERE ARE NO PROBLEN INDICATIONS IN THE CONTROL ROON.
m
-/ 'I M-RAA;;AA;; ;AAAAA;;;;;;A;;;;;;;;-RAAAAA;;;;;;;;;;;;;;;AAAA;AA;AAAA;AAA;;;;
THIS IS A DRILL
-RRRRRpnRRR RRRR MMM R R RR R R R RR .
RRRpnpRRM RR-R R f t u
.t Q 3G-19
1
.,.-~
'(
)
M _/- DRILL / EXERCISE SCENARIO FORMAT EMERGENCY PREPAREDNESS DRILL
. DRILL TYPE / EVENT NO. 4
. CUE CARD NO. 4-2 FOR: 0PERATOR INVESTIGATING RHR PUMP B TIME: 1615+
LOCATION: REACTOR ENCLOSURE-217 FT-0 IN., EL THIS IS A DRILL
-DO NOT . initiate actions affecting normal plant operations. .., ~~;
J'" ) AN EXTREMELY LOUD NOISE IS HEARD AT RHR DISCHARGE VALVE HV-51-1F047B. THE VALVE HAS PARTIALLY CLOSED AND ATTEMPTS TO MANUALLY OPEN IT ARE , UNSUCCESSFUL. YOU CANNOT CLEARLY COMMUNICATE WITH THE CONTROL ROOM DUE TO HIGH BACKGROUND NOISE. nn N g. N n THIS IS A DRILL
; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; :. ; :. ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;. ; ; ; ;a
$A s 3G-20
l l l j--y EVENT NO. 5 1
,\
.(
? Search and Rescue /First Aid Group ;
Approximate Time l of Event: 1650 g.
~
Location: RHR discharge valve (HV-51-1F047B) in reactor
-enclosure el 217 ft-0 in.
2 iProblem: An operator was dispatched to investigate the ceuse for RHR pump B discharge flow drop at 1615. l Communication with the dispatched operator becomes
.very difficult .due to extreme background noise.
Due to high - radiation levels, evacuation of the reactor building is ordered at 1630. The operator is still unaccounted for at 1650, n Response: A Search and Rescue /First Aid Group is dispatched l to -find the operator. They find the operator and evacuate the reactor building. Controller Locations: One accompanying the Search Group from the OSC.
- f~1 ~
%)
FOR CONTROLLER USE ONLY
~
? .: L i (M. $.\. j
~
3G-21 [ p
.;. y r
;y' DRILL / EXERCISE SCENARIO FORMAT t ?
' . ./
EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 5 CUE CARD NO. 5-1 FORi SEARCH AND.RSSCUE/FIRST AID GROUP TIME: 1650+
. LOCATION: DECONTAMINATION AREA a a ;. :. :. :. $ ;. :. :. :. :. ;. :. :. a ;. :. ;. ;. ;. :. :. a ;. :. :. a ;. ;. :. :. :. : ;, $ ;. :. :. $ . ;. ;. a ;. a a ; ; ;. $ ;. ;. ;. :. :. a ;. ;. a a $ :. :. :. : : :. :. k*
-THIS IS A DRILL DO NOT- initiate actions affecting normal plant operations.
- a. ;. :. $ a ;. a ;. ;. a ;. ;. :. :. a ;. ;. :. :. :. :. ;. :. :. :. ;,:. ;. :. : :. ;. ;. :. ;. ;. :. :. :. :. a a a a :. ; ;;. :.1. ;. a :. :. :. $ :, a ;. a a a :. :. :. : a
'RESULTS OF PERSONNEL CONTAMINATION SURVEY WITH INSTRUMENT ARE <100 cpm.
/ \
- , 4
, ,5 -
.%,_d .
'Nkk$kk$$$$ $$$M.k$$$$$$$$$$$$$$$$$$$$$kk$$$$$$$$$$$$$$ $$$$ESk$NbNkk$k$N$$
THIS IS A DRILL A A A A A ;. A aaA A ;.;;. ;. A . A;.;.;;.;. A A A A ;. A :. A A ;;;. A A A A A ;. ;. A A A ;. A A A ; ;. A ;.;.;.; ; A A ;.1. A ; A A ; aa k***** [ -. I ' ff"' 5
'\
3G-22 y . .. L _-
- []
V EVENT NO. 6 Low Pressure Alarm at The CO, Storage Unit (00S133)
- Approximate Time-of Event: 1715 Location: CD Storage Unit 00S133, in turbine enclosure el 239 ft-0 in.
Problem: A low pressure alarm from the CO 2 storage unit
-(00S133) is received at 1715. l Response: A . Damage Repair Group is dispatched to investigate l the problem. The control room is notified that the pressure relief valve PSV-22-065 is leaking and the CO 2 Portion. of the Fire Protection System is inoperable due to low tank (00S133) pressure at ,
1730. I A continuous fire watch is established for those areas in which redundant systems or co:sponents could be damaged. For other areas, establish an hourly fire watch patrol. N Controller f} -( A Locations: One in the control room. One accompanying the dispatched Damage Repair. Group. l J
-e FOR CONTROLLER USE ONLY 3G-23
-]
C 7 ~s-y p~ -
, y._/ DRILL /EERCISE SCENARIO FORMAT '1-\ .
. i l EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 6 CUE CARD NO. 6-1 FOR: DAMAGE REPAIR GROUP LEADER INVESTIGATING TIME: 1715+ STORAGE UNIT 00S133 LOW PRESSURE AIARM . LOCATION: TURBINE ENCLOSURE
.239 FT-0 IN., EL THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
. , ~q
- t. }
V A WHISTLING NOISE CAN BE HEARD AT PRESSURE RELIEF VALVE PSV-22-065. . LOW TANK (00S133) PRESSURE ALARM.
******************u THIS IS A DRILL
- :. :. : :. :. :. ;, :. :. ;. :. :. :. :. : :. ;. :. :. :. :. :. :. :. :. ;. ;. :. : :. :. ;. :. :. ; : :. ;. :. :. :. ;, :. :. :. :. :. ;. :. :. ;, :. :. :. ; : ;+A**********
s 3G-24
s (% EVENT NO. 7 f Fire at The East RHR Heat Exchanser Room (103) I a-Approximate Time l of Event: 1730 Location: East RHR heat exchanger room (103) in reactor enclosure el 177 ft-0 in. Pro,blem: Alarms sound at 1730 indicating a fire in the east l RHR heat exchanger room on reactor enclosure el 177 ft-0 in. Cause of the fire is unknown, but it is fueled by scaffolding material brought there in preparation for an inspection of the RHR heat exchanger. The fire has disabled both RHR pump B & D motors.
- Response: Fire Fighting Group members are dispatched to the l scene and they are able to extinguish the fire at 1800. l Controller Locations: One in the area. , ,-m _
A i a FOR CONTR0LIIR USE ONLY 3G-25
> l l
1 j 'y - .
.'s,f DRILL / EXERCISE SCENARIO FORMAT ,
EMERGENCY PREPAREDNESS DRILL 4
- DRILL TYPE / EVENT NO. 7 CUE CARD NO. 7-1 FOR: ' FIRE FIGHTING GROUP MEMBERS TIME: 1730+
LOCATION: - REACTOR ENCLOSURE 117 FT-0 IN., EL-THIS IS A DRILL
. DO NOT initiate actions-affecting normal plant operations.
EAST RER HEAT EXCHANGER ROOM (103) IS ON FIRE. :THE FIRE IS FUELED BY SCAFFOLDING
., s; ' MATERIAL LEFT NEAR THE RHR HEAT' EXCHANGER.
'( d
) 0FFSITE' ASSISTANCE IS NOT NEEDED. MOTORS FOR BOTH RHR PUMPS B AND D HAVE BEEN DISABLED. .
; ;. :. :. :. ; ;. :. :. :. :. :. : :. ;. ; ;. :. :. :. :. : :. ; ; ; ;. :. :. :. :. '. : :. :. : :. :. ;. :. :. :. ; ;, :. :.1 :. ; ;. :. :. :. :. ;. :. :. :. ; ;. :. :. :. :. :. :. :. : :. :. :. :.
THIS-IS A DRILL
. [%
A 3G-26 Y eP--' -Je---'e- +y%e i.-,-.-,*wr, ,--.,vg- & = , ,--,--ww
7 s . f.g 7 N- , DRILL / EXERCISE SCENARIO FORMAT I EMERGENCY PREPAREDNESS DRILL DRILL TYPE /E'RNT NO. 7 CUE CARD NO. 7-2 FOR: . FIRE FIGHTING GROUP MEMBERS TIME: 1800 LOCATION: REACTOR ENCLOSURE 117 FT-0 IN., EL 4
+k*********
THIS IS A DRILL
'DO NOT initiate actions a'ffecting normal plant operations.
.e***
. +
- (V
() FIRE IS Oltr. ,
- c THIS IS A DRILL p.
i s e 3G-27
4 j '3[.
+ ; ,-g y E l
V- EVENT NO. 8
- -w
. Containment Purae Exhaust Line Leakage
-Approximate Time
.of Event: 1845 l.
' Location: Containment purge exhaust line isolation valves (HV-57-113), (HV-57-114) and (HV-57-115) in reactor
# . enclosure el 283.
Problems: . Status lights on the control board indicate the containment isolation valve -(HV-57-114) in the containment . purge system has backed off the fully . closed position at 1845. Reactor enclosure local l radiation levels in the area of the containment _ purge system line are increasing. The releases are due to leakage pass the closed isolation valve
.(HV-57-115) in the containment purge line. Status lights on the control . board indicate that the containment purge line isolation valve (HV-57-115) is unseated at 1915. !
. Response: Damage Repair Group is sent to investigate and try l 1
v3- to shut the valves . locally. Dispatched personnel
!- ' estimate that it will take 10 hours to terminate
'the release. The . containment purge line valve (HV-57-115) is repaired at 2145 and releases to the l atmosphere are terminated.
Controller Locations: One accompanying the dispatched team. FOR CONTROLLER USE ONLY 5 u \ Q) ' 3G-28
O 2
,m . +
p) -t DRILL / EXERCISE SCENARIO FORMAT t EMERGENCY PREPAREDNESS DRILL ^ DRILL TYPE / EVENT NO. 8 CUE CARD NO. 8-1 I . FOR: GROUP INVESTIGATING CONTAINMENT PURGE TIME: 1845+ EXHAUST VALVES.
' LOCATION: REACTOR ENCLOSURE 283 FT-0 IN., EL -
1 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. 1
\
~-(
CONTAINMENT PURGE EXHAUST VALVE HV-57-114 s . HAS BACKED OFF CLOSED-POSITION. EFFORTS
. TO MANUALLY SHUT VALVES HV-57-113 OR HV-57-114 ARE UNSUCCESSFUL.
-THIS IS A DRILL
[ i h I t ./ S ). ',
- . N/
l- 3G-29
.n
-{L') - DRILL / EXERCISE SCENARIO FORMAT EMERGENCY PREPAREDNESS DRILL CUE CARD NO. 8-2 l DdILL TYPE / EVENT NO. 8
'FOR: GROUP' INVESTIGATING CONTAINMENT PURGE TIME: 1915+
EIHAUST VALVES. LOCATION: . REACTOR ENCLOSURE 283 FT-0 IN., EL THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
' Q'O . CONTAINMENT PURGE EXHAUST VALVE HV-57-115 HAS ALSO BACKED OFF CLOSED-POSITION AND IS ;
OPEN. THE MANUAL HANDWHEEL DOES NOT TURN. REPAIR ESTIMATES ARE 10 HOURS TO SHUT THIS l VALVE. i
****t ; ;. :. :. ; ; ;. :. :. :. ; ; ;. :. :. _ :. :. :. . :. :. :. :. :. :. :. :. :. ; ;. :. :. :. :. ; ;. :. :. ; ; ;. :. :. :. :. :. ;, :. :, :. :. :. ; ; ;. :. :. :. ; ;. :. :. :. :. :.
7;y THIS IS A DRILL s P 1 G i 3G-30 P -
- 1. -
ry
),
I' v/ - DRILL / EXERCISE SCENARIO FORMAT - EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 8 CUE CARD NO. 8-3 h FOR: GROUP INVESTIGATING CONTAINMENT PURGE TIME: 2145 l' EXHAUST. VALVES. LOCATION: REACTOR ENCLOSURE 283 FT-0 IN., EL
; ;;;;; :::::::; ;;;; ;;;;;;;;;;;;;; :::::::: :::::azzza;;;;;;;;;;a :::::
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
/
N;N aN ;; nan k N;$Na; ANN $N E ;b;aNbk N CONTAINMENT PURGE EXHAUST VALVE HV-57-115 IS REPAIRED.
;;;;- ;;;;;;;; ;;;;;;;;;;;;;a ::::azaza;;;;;;;;;;;;;;;;;;;;:.;;;.;;;;;;;;;;
THIS IS A DRILL
;;;;;azza:.;;;;;;;;;;;;;;;;;;.:::azzzazzazaa ::a;;;;;;;;;;aa;;;;;;;;; :: :.;;
/% .
3G-31
~ t x
.j'3
\ i.
N4 DRILL / EXERCISE SCENARIO FORMAT l EMERGENCY PREPAREDNESS DRILL l l DRILL TYPE / EVENT NO. 8 CUE CARD NO. 8-4 i FOR: GROUP INVESTIGATING CONTAINMENT PURGE TIME: 2200 EXHAUST VALVES. l
- LOCATION: REACTOR ENCLOSURE 283 FT-0 IN.,.EL i
THIS IS A DRILL > DO NOT initiate actions affecting normal plant operations.
,.x .
~
i i CONTAINMENT PURGE EXHAUST VALVE HV-57-114 IS REPAIRED. l
-THIS IS A DRILL l i
e I
/
1 e i e l V i l 3G-32 l I . - . , , , . _ . . - . . _ . _ , . . . _ . . . . _ . . . . , _ . _ _ _ . , _ . . . _ . _ _ _ _ __;_......._......._ _._.-.__._.,_.._,,m
7 sm. . I EVENT NO. 9
- (Q.
Cooling Tower Blowdown Sample Analysis Approximate-Time l of Event: 1900 I + Location: Chemistry laboratory, radwaste enclosure el 217 ft-0 in. Problem: The result of the 1830 sample of the cooling tower blowdown is 7N6 pei/cc. Samples taken at 1815 and 1845 were both negative. Response: The control room and city authorities are informed
. for possible Schuulkill River sontamination.
Controller Locations: One in chemistry laboratory. e
/~'s i
\_j) .
1 O t FOR CONTROLLER USE ONLY
;. ['~]
V 3G-33
e, ,
.m
- s. DRILL / EXERCISE SCENARIO FORMAT a >
EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 9- CUE CARD NO. 9-1 l FOR: CHEMISTRY TECHNICIAN TIME: 1900 l LOCATION: CHEMISTRY LAB., RADWASTE ENCLOSURE 217 FT-0 IN., EL THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. L C00 LING 1 TOWER BLOWDOWN SAMPLE TAKEN . AT 1830 INDICATES 7N6 pCi/ce,
.:'# f w FROM WHICH AT LEAST 60 PERCENT OF THE ACTIVITIY IS DUE TO
) TECHNETIUM - 99M.
- ~,J SAMPLES TAKEN AT 1815 AND 1845 ARE BOTH NEGATIVE.
;;;;;;;;;;;;;;azzzaraz;;;;;;;;;;;azaaa;;;;;;;;;;;;aa :::.;;;;;;;;;;;.uaaka-*
THIS IS A DRILL 49 65 $h 0% 0% 0% 0% WS SS $b b $ $b f f-
\si i' ; i 3G-34 ,,p f L'
m gm is s_.s
) EVENT NO. 10 Core Spray Pump A Trip Approximate Time of Event: 2040 Location: Core Spray Pump 1AP206 in reactor enclosure el 177 ft-0 in.
Problem: Core Spray Pump 1AP206 trips at 2040. CoreSprayl Pump C is not affected and continues to operate. Response: After all attempts from the control room fail, a Damage Repair Group is dispatched to determine l cause/ solution for the pump trip. Due to high area radiation levels, the Group has to evacuate the reactor building without sufficient time to diagnose the problem. Core Spray Pumps B and D are manually initiated and Core Spray Pump C is tripped. . 4
. Controller Locar.; 2ns : One accompanying the dispatched team from OSC.
,~
~
'a FOR CONTROLLER USE ONLY
,V' c.
3G-35 (,
m r.gf , s 1 w 4
-3_
7 x DRILL / EXERCISE SCENARIO FORMAT EMERGENCY PREPAREDNESS DRILL DRILL TYPE / EVENT NO. 10 CUE CARD NO. 10-1 FOR: . GROUP INVESTIGATING. CORE SPRAY PUMP 1AP206 TIME: 2040+ LOCATION: REACTOR ENCLOSURE ' 177 FT-0 IN.,~EL
------------ : :::;-- ;;;;;- :aa;;; :::; ;;;;; :: ;; : :; aaaaaaa; THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
m:. :. :. :. :. :. :, :. :. :. :. :. :. :. :. :. :. :. :. :. ; ; ;. :, : : :. ; ;. :. :. :. :. :. :. :. :. :. :. : : : :. ; ;. :. :. a-a CORE SPRAY PUMP A IS SHUT OFF.
.THE PUMP MOTOR IS SMOKING AND FEELS VERY HOT.
CORE SPRAY PUMP C IS RUNNING. If g p 4
\ t- ',\ j _
- :. :. :. :. :. :. ; ;. :. :. , ;. :. a ;. :. : :. :. :. :. :. :. :. :. :. :. :. , ; ;. , :. ; ;. :. :. :. :.
-THIS IS A DRILL .
Nh zh [. $ bk; ; Nk h b Nbh bbb $ Nb bbh zh kNkN kN $$k k
. Q; b
v
'l
/
L 3G-36
.c :
.n ;, 1 ,
- ( s .. u,
, e. ,
i \ t , Ns; - , DRILL / EXERCISE SCENARIO FORMAT, s
, EMERGENCY PREPAREDNESS DRILL s' .- ,
, DRILL TYP:/ EVENT NO.10 CUE CARD NO. 10-2 5,
- FOR: GROUP INVESTIGATING C0hE SPRAY PUMP 1AP206 TIME: 2040+ l
= T 1
LOCATION: REACTOR ENCLOSURE 7- i 177 FT-0 IN.', EL o
'i ' **mi. :. :. :. ;, ;. :. ;. , ;. :. ;. :. ;. :. ; ;. :. ;. ; ;. :. ; ;. :. ; ;. ; ;. ;. : :. :. :. ;. ; ;. - ; ;. :. :. :. :. ;. :. :.
s THIS IS A DRILL
+ '.
DO NOT initiate' actions affecting normal plant operations.
.s u A g
****************+-l, L :. a ;. ;. ;. ;. ;. ;. ;. ;. a :. . ;. ;. :. ;. : A :. ; :.
/ h
-/ \ DUE TO HIGH' AREA RADIATION LEVELS, YOU HAVE TO '
() LEAVE AND RETURN IN ABOUT 2 HOURS. 4% , m :.'\:. :. :. ;. . ;. ;. ;, ;. ;. :. ; ;, :, :. ;. :. ;. :. :. ;. :. :. :. :. :. ; :. ;, e**t. ;. ; :. :. ;. :. :. ;. ;. ;. ;. :. :. ;. :. :. :. i .: , b- , THIS IS A DRILL
.,,- .f.
s\ 4 't ' 9 4, .
,4 s
9
< m
~
;.p '[
)
-' , b
* 's
. s,.
'N b
4 i,,', k 9 ,
\ /
- w. ,
s 3G-37 1 L
w.y . s
f t r-kj 'Date -7/25 Time 1100 n
- WSSAGE FOR:'- Control: Room SIMULATED PLANT CONDITIONS': Full Power
.;;;; ;; ;.. :. . 1--- ; ;.;. :. - ;;;.;... ;.;.;. -- ;.;;. - ;.;. ;.;.;;.:.;.;;.;.;.;;.;. ~.-
THIS IS A DRILL
'D0 NOT initiate actions affecting normal plant operations.
. __;------------- ;- .;;;--- ;;;;;- ;;;; ;;------- ;;;;;- ;;;;;;;;;;;;;;- ;r MESSAGE:. Initial Conditions:
Unit I has accumulated 8 full power months of operation since the previous refueling. At that time, 15 fuel
, assemblies of a.new design'were installed so that they could be qualified under commercial operating conditione. The 15 fuel assemblies represent about 2 percent of the fuel in the core. On two occasions in j/~~ . the past three months, Unit I has experienced reactor
- (]/L' . trips caused by spurious main steam isolation valve (MSIV) closure signal. . All power generation equipment
'is operating, and all safety system equipment is operable. . The initial plant and reactor system values are shown in the attached table.
1 The meteorological conditions at 1100 are characterized by the influence of an almost stationary high pressure ares centered over Greenwich, Connecticut. The clockwise flow 'around its center ir evident by the , following ground - level Limerick generating station met l tower data: , Wind Direction Southeast (137 degrees) Wind Speed 5.2 mph TeJaperature 71*F Delta Temperature -1.3*F Sigma Theta 6.7 degrees azimuth
. The National Weather Service indicates that the high is expected to slowly drift to the South during the next 12 to 24 hours. Skies will remain sunny with light winds gradually backing to the South-Southeast. l '\c\ 'V FOR CONTROLLER USE ONLY 3H-1
,k 4- e' j .~, - s x' 7 4
- =~ -
d-
*4.
,). A ,
/ , Date 7/25 Time 1100 a k-4 MESSAGE FOR: Control Room'
~ .
SIMULATED . PLANT CONDITIONS:
- s. v
**HrAd*A**llnK A A A A A A A A A A A A Hr****ft*1d A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A
.THIS IS A DRILL _
~
DO NOT-l initiate actions affecting normal' plant operations.
***iru a A A ; :, A :.:, A ;. A ; A aa A :,:.:..; A A ;. A u :. A k:.-A A A ;.:. A:.u A : AM A ;.:.;.:. A , A A A A A A A ;. A A A A A ;. A ;. A A
.' . MESSAGE: - Inil:ial Conditions: ' ^
, ./ \ .
"W c^. I UniCf lias accumulated 8. full' power months of operation
- s. ., since the previoW , refueling. At that time, 15 fuel
- . . ,' ' a'siemblies of a new design were installed so that they us ,
could be qualified- under commercial operating
* . _ cond,ihions ., The 35 fuel assemolies represent about
;,3 2 Percent of 'the fuel in the core. On two occasions in
} ): 4 j the;; pastl three-tonths, . Unit l' has experienced reactor ;
K./ . Q q trips caused by . spurious main steam. isolation valve :
- (MSIV) c closure sibal.
All power generatlon equipment i
'.o 'lis : J ophratirig', f !and til, safety system equipment is !-
. operable.. The; initial- plaat and reactor system values i l "are shoka in the attached table.
_e
, . e. . <
,g; .
G i The. mett.orological conditions . at 1100 are characterized
, , , N ' by the . influence :of .an almost stationary high pressure ;
l w- s,rea centered 1 over Greenwich,- Cohnecticut. The
' *: clockwise flow N round its center is evident by the J .
? )..; 7 ;followisg ground ~ lev 61 Iimerick generating ' station met
, , tower data
'1 .
E ,
..= Wind Direction Southeast -(137 degrees)
Wind Speed- 5.2 aph
, y Temperature: 71'F.
'p - -Delta Temperature - 1. .?"
. Sigma Theta.- N 6.
- 6 reera'ziriath 1 ,
The .Nitionalr. Weather Sei .H ;; . , :ates that the high is B -
' expected to slo 41'y drift v., the .e Ab during the next 12
' tof 24 . hours '. - Skies will restain's.unny with light winds gradually backing-to the South-Southeast.
t - *
-? -
s r,? , t 4 s
, I _
+ O An-u ::q; W- ,
.s,;) . s s s
*>^ ^
s
(m.
,TABb _ I I Limerick Generating Station Initial. . ant and Reactor System Values Reactor Level +35 inches -Drywell Press nA Psig-Heactor Pressure 1020 psig . . Drywell' Atmos Temp - a *F .
ReacLor Power 100 % Full Power Supp Pool Press 0.6 psig Core Plate DP 100 '% Full Power Supp Pool Temp 90 *F Core Flow 100 lb/hr x 10 8 Supp Pool Level 22.1 feet Total Steam Flow 8 1 lb/hr x 10 Main Stm Line Rad Hon 1100 mR/hr Total Feedwater Flow 14 lb/hr x 10 8 Containment Rad Level. , 2 R/hr Condenser Vacuum yo inches Hg Cond Stor Tank Level. 38 feet l Ilotwell Level a inches RCIC Flow 0 . spo CRD Charging Pressure 11nn Psig HPCI Flow . O gym Inst. Gas to ADS Pressure 110 psig' RHR A Flow n gPa Equip. Drain Coll Tank Level 3 feet RHR B Flow n gPe Equip. 1) rain Surge Tank Level 3 feet RHR C Flow n gym Floor Drain Coll Tank Level 4 feet RHR D Flow O ' gpa Floor Drain Surge Tank Level 3 feet Core Spray A Flow 0 gym 112 Concentration 0% Core Spray B Flow 0 gpa 0 2 Concentration 2.8 % RHR Hx Outlet Temp 80 *F SGTS Flow 0 cfm RHR SW Inlet Temp 80 *F North Vent Stack Concentration SN6 Ci/cc North Vent Stack Release Rate 7P2 pCi/sec 112-1471200-15 3H-3
p
~
_q V' TABb (con't)- d Limerick Generst..4 Stction . Area Radiation Monitor.Readinga . I (mR/br) Time: 1100 Date: 7-25-84 AHti No. I.oca t ion . Reading ARN No. Location Reading ItE-01 RCIC Pump Compartenent 100. RE-22 RWCU Pump Area 0.5 HE-02 IIPCI Puisp Compartment 80.- RE-23 Standby Liquid control Sys. Ares 0.5 ItE-03 Sump Compartment 1. RE-24 RWCU Instrument Rack Area 1. ItE-04 CHI) Pumps Area 0.2 RE-25 Turbine Auxiliary Ray 0.5 HE-05 Turbine Aux. Ilay llallway 0.2 RE-27 RWCU Filter Area 1. HE-06 Isolation Valve cosepartment. 0.5 RE-28 Equip. Compt. Exh. Filters Area 0.5 HE-07 Condensate Pump Compartment 90. RE-34 Hydrogen /0xygen Analyzers Area 0.2 HE-08 EllR Division I Compartment n_ RE-36 OSC Ares 0.5 HE-09 HilR 1)ivision II compartment n. RE-41 Sludge Discharge Mixing Pump Room 0.2 i ItE-10 Steam Vent Area Stairwell n_s RE-42 Radwaste Enclosure Hallway 0.2 HE-12 llallway, Condensate Filter Demins. o.7 RE-43 Concentrate St9r. Disch. Pump Room 0.5 HE-13 Condensate Area 50. RE-46 Fuel Pool Holding Pump Room 0.5 HE-15 CHl) IIEll Area East 0.5 RE-47 Precoat Tank & Pump Room 0.5 HE-I6 CHD llCY Area West 0.5 0.2 RE-51 Radwaste Enclosure Hallway HE-17 Neutron ilonitoring System Area 0.5 RE-55 Radwaste Exhaust Fan Area 0.1 NE- Ill Neutron tionitoring 1) rive Hechanis. 0.5 RE-56 Control Room 0.1 _ HE-19 T5.rbine Auxiliary Bay IIallway East 100. RE-57 Turbine Area Operat.ing Floor 0.5 ItE-20 Turbine Auxiliary Bay llallway West 100. RE-58 Standby Gas Treatment Filter Room 0.5 itE-21 HWCU lleat Exchanger Area 0.5 RE-60 North Vent Stack Sample 0.5. 3H-Y -
f3t. TABLE f (cont) LIMERICK GENERATING STATION TIME: 1100 DATE: 7-25-84 Reactor Coolant Drywell and Suppression Activity Concentration Chamber Air Concentration
~
(pCi/gn), '(pC1/gn)
~Kr-85 4.N2 1.N6 Kr-85M 8.N1 2.N5 Kr-87 6.N4 2.N5 Kr-88 2. 5.N5
.Xe-133 4. 1.N4
- Xe-135 4. 1.N4 l Total Noble Gas 1.P2 2.N3 l
-7 %
cfx . I-131 5.N3 2.N8 f I-133 1.N1 3.N9 ! Total Iodine 8.N1 2.N7 : 1 Gross Beta 1.6P2 4.N3 l i l \ l- 0 l l 3H- f L_-
1 O d-. TABLE 1 (cont) LIMERICK GENERATING STATION SUPPRESSION POOL ACTIVITY CONCENTRATIONS (pCi/gm) F TIME: 1100 DATE: 7-25-84
- I-131 5.N7 I-133 3.N8 a ;.; Total Noble Gas 7.N7
'Y' Gross Beta 2.N5 i 5 mo i +,
. (2
....) :
TABLE 1 (cont) LIMERICK GENERAIING STATION ISOTOPIC STACK CONCENTRATIONS TIME: 1100 DATE: 7-25-84 North Vent l South Vent * (pCi/cc) (uci/cc) Kr-85 2.ON8 2.0N8 Kr-85M 4.2N7 1.3N7
.Kr 1.2N7 2.4N7 i
Kr 9.0N7 3.6N7 l Xe-133' 1.8N6 9.2N7
-Xe-135 1.8N6 1.8N7
\>. :
i
'l . Assume North Vent Stack Flow Rate of 300,000 cfm.
2 Assume South Vent Stack Flow Rate of 120,000 -fm. I s
/
l ..\ l 3H-7
'~....-
'l^\).
w/ , Date 7/25 Time 1105
-MESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS: Alarm is received in the control room due to a fire in the turbine enclosure at elevation 217 ft-0 in. Offsite assistance is required.
,, THIS IS A DRILL DO NOT- initiate actions affecting normal plant operations.
MESSAGE: Fire ALARM at instrument air compressor 1AK101 in turbine enclosure. (Event No. 1) ACTION EXPECTED: " Unusual Event" should be declared. Fire Fighting Group l should be dispatched to the scene.
)
f e
)_
-4
; i s' . FOR CONTROLLER USE ONLY
..z 3H-8
-~
r.. I- 5
. a.
- vu . _ _ _ ,
x.
>\
-(..-;A- Date 7/25 Time 1105
. MESSAGE FOR: Control Room e.-
' SIMULATED PLANT CONDITIONS:
THIS IS A DRILL
- c. IDO NOT. initiate actions'affecting normal plant operations.
;;;;;;;;;;;;;;;;;;a;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
MESSAGE: Fire ALARM at instrument air compressor 1AK101 in turbine enclosure.
~ ACTION EXPECTED:
-w w
.g r
F \ G 3H-9 t
. (]
\s_ / Date 7/25 Time 1315
.NESSAGE FOR: Control Room
-SINULATED
. PLANT CONDITIONS: Spurious MSIV's closure which causes Reactor Scram.
Reactor vessel pressure increases to 1170 psig. Reactor water level decreases. THIS IS A DRILL L y DO NOT initiate actions affecting normal plant operations.
*********s a z z a z z a z a ;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
HESSAGE: MSIVs close. Reactor scrams. SRVs open. ACTION EXPECTED: " Unusual Event" should be declared.
./ ~%
l 1 s
- ~
hl. k
- - / G
- , 1-l' / FOR CONTROLLER USE ONLY 3H-10 t p
x. Date Time 1315 4 7/25 f N_ /
.NESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS:
'l THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
;;;;;;;;;;az;;;;;;;;;;; ::::::: ;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;aaaa;;;;;
- MESSAGE: MSIVs close.
Reactor screas. SRVs open. ACTION EXPECTED:
,~ .
1
%j i
b 3H-11
i
} gg,,33,g Date 7l25 o* 1 CONTINGENCY MESSAGE
-MESSAGE FOR: Control Room
~
SIMULATED PLANT CONDITIONS: The reactor pressure and water level have decreased to 1050 psig and -38 in., respectively.
;, ;. ;. ;. ;. ;. :. ;. ;. ;. ;. ;. ;. ;, ;, ;. :. :. ;. :. :. ;, ;. . :. = ;. :. . :. = ;. :. ;. :. :. :. = ;. :. ; :. = = = $= = = = = = = = =
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
;. ;. ;. ;, ;;. ;. ;. :. :. ;. ;. ; ;. :. :. :. :. ;. :. ;. ;. :. :. ;. :. :. :. :. :. :. :. :. :. :. . :. :. :. :. :. :. ;. :. = ; = = = = = ;. = ;. = = = = = =
MESSAGE: HPCI and RCIC systems are initiated. Standby gas treatment system (SGTS) is initiated. ACTION EXPECTED: Two SRVs are kept open to control pressure. r.,,,/ _[ \ w!) FOR CONTROLLER USE ONLY 3H-12
- n
fh ) Date 7/25 Time 1316
- %./ .
CONTINGENCY MESSAGE MESSAGE FOR: Control Room
' SINIEATED PLANT CONDITIONS:
~
;.;; :.;;;.;;.;;;;.;;;. ::. : ;. :.;,a;.;. :. :::.;;;. :,;.:.:.:. :. ::.:. ::::.:.;. :. :::. ::.:.;. *****
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- a:. ::: :::::: a;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
HESSAGE: HPCI and RCIC systems are initiated. Standby gas treatment systes (SGTS) is initiated.
- ACTION EXPECTED: .
;j ._
5, s/ k ? l I
- e l
l
\
! 3H-13 L
g- -
, _ ,4- Date 7/25 Time 1325 MESSAGE FOR: Control Room
-SIMULATED PLANT CONDITIONS: Reactor pressure and water level are 1025 psig and
+50 in., respectively.
- ----- z;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;.:. ::::::::::::: :: : ::: :::::.
THIS IS A DRILL
-DO NOT initiate actions affecting normal plant operations.
- --- ;;;;;;;;;;;;;;;;;;l;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;k*
MESSAGE: High drywell pressure ALARN ACTION EXPECTED: HPCI pump is manually operated for pressure / level un control.
/\ ~
sv
.? ,/
(m ). FOR CONTROLLER USE ONLY 3H-14
p71 J
-~.,.
.; \ r
- Aj Date 7/25 Time 1325 MESSAGE FOR: -Control Room SIMULATED PLANT CONDITIONS:
-- ;; :: ; ;;;;;;;;;;;;;;;;;;;;;;;;;-:::::::::::::::::::: ; ;;a;aaaaaaa----
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- - ;. : :. :. :. ;. ;. ; ;. ; ;. ;. :. :. ;. ;. :. ;. : :. :. : ;. ;. ; ;. ; ;. :. :. :. :. :. :. :. :. : ;. ;. :. ;. m
. MESSAGE: High drywell pressure ALARM ACTION EXPECTED:
em i l: uj 1
!,U) 3H-15 u- _.
y~ (,,,!. Date 7/25 Time 1330 CONTINGENCY MESSAGE MESSAGE FOR: Control Room SINULATED PLANT CONDITIONS: Drywell pressure has increased to 1.68 psig.
- a;;;;;;;; :::::::::::::: :: ::::::::azza;;;;;;;;;;:: ;;;;;;;;;;;;;;; -****
y
,.-- THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
*+++**+;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
-MESSAGE: Containment group isolations occur on high drywell pressure. HPCI is initiated in injection mode and trips at +54 in.
ACTION EXPECTED: HPCI is initiated and operated for pressure / level g control.when the high reactor water level signal clears.
,;ry
%< p u,1 4
?" ~%
- j. FOR CONTROLLER USE ONLY 4
3H-16 i t'
+ -
-', \ ,_ ! \
f _,/_ - Date 7/25 Time 1330 CONTINGENCY MESSAGE
. MESSAGE FOR: Control Room g SIMULATED-PLANT CONDITIONS:
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;azaaaaa ::::::::::::
THIS IS A DRILL.
's 'D0 NOT initiate actions affecting normal plant operations. * - ::a;;;;;;aza;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
f MESSAGE: Containment group isolations occur en high drywell pressure. HPCI is initiated in injection mode and trips at +54 in. ACTION EXPECTED: (j: Qj , p
'O 3H-17
*g. s Q Date 7/25 Time 1400 CONTINGENCY MESSAGE MESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS: Reactor pressure and water level are 860 psig and
+50 in, respectively. Suppression pool temperature is 110*F.
1- . AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAnAAAAAAAAAAAAAAAAAA4AA THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. t
- AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA ; MESSAGE: RHR A and B pumps are lined up for suppression pool cooling mode.
fy
^~
ACTION EXPECTED: Depressurization of the reactor using SRVs has begun lsx_ since 1945.
-m i [ h I l FOR CONTROLLER USE ONLY
's./
3H-18
\ 'y~/ Date 7/25 Time 1400 c.
CONTINGENCY MESS' AGE MESSAGE FOR: ' Control Room SIMULATED PLANT CONDITIONS:
;;;t.;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;a THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- - - ; ;. :. ; ; ; ; ;. :. :. ; ; ; ; ; ;. :. ; ; ;. ; ;. ; ; ; ; ;. ; ;. ; ; ; ;. :. ; ; ;, ;. :. ; ; ;. ; ;. ; ;. ; ; ; ; ; ; ; ;. :. ; ; ;; a a a ;. ; ; ; ;. :. ; ks MESSAGE: RHR A and B pumps are lined up for suppression pool cooling mode.
ACTION EXPECTED: s
%/
J' 4 9
)
N,,_,,/ 3H-19
,m
, 1:
't_) .
Date 7/25 Time 1430 CONTINGENCY MESSAGE MESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS: Reactor vessel cooldown is continued. Tli!S IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: An assistant operator has been found unconscious lying
- in a puddle that appears to be leakage from the fuel pool holding pump (00P340). He is bleeding from a head laceration. (Event No. 2)
ACTION EXPECTED: Search and rescue /first aid group should be dispatched l to the area. : " Unusual Event" should be declared. w/
~5 FOR CONTROLLER USE ONLY
,- 3H-20 F k!_ ,
s t
,v I Date 7/25 Time 1430 W CCNTINGENCY MESSAGE
- MESSAGE FOR: Control Room
- SIMULATED
- PLANT CONDITIONS:
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
-MESSAGE: An assistant operator has been found unconscious lying in a puddle t' .t. eppears to be leakage from the fuel pool holding pu.np (00P340). He is bleeding from a head laceration.
ACTION EXPECTED:
,hm i i
't)
I b - 3H-21 l- <-- )
.<m.g-Date 7/25 Time 1545 CONTINGENCY MESSAGE MESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS: F.eactor pressure and water level are 440 psig and
+50 in., respectively.
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Core Spray (CS) and RHR in the LPCI mode are initiated. ACTION EXPECTED: RHR A and B pumps are returned to suppression pool cooling mode. i
,'~%,
l \
-A _/
_j y
! \
l
/ FOR CONTROLLER USE ONLY 3H-22
L. 3 Y d Date 7/25 Time 1545 CONTINGENCY MESSAGE . MESSAGE FOR: Control Room SIMULATED-PLANT CONDITIONS: THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Core Spray (CS) and RI:R in the LPCI mode are initiated. ACTION EXPECTED: r8 I, 4 f a e
/
Y 3H-23
i YM f i N, / Date 7/25 Time 1600 CONTINGENCY MESSAGE
' MESSAGE ~FOR: Control Room SIMULATED
-PLANT CONDITIONS: Sample analyses reveal primarily noble gases in the drywell atmosphere.
azzazzazzaaaaaaaa;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;a :a THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- :::::::azzaa;;;;;;;;;;;; ::::: ::::a;;;;;;;;;;;;;;;;;;;;;;;;;
MESSAGE: Drywell radiation level has increased to 100 R/hr. ACTION EXPECTED: " Alert" should be declared.
-;^g
,/
m, - f V) FOR CONTROLLER USE ONLY 3H-24 i~
l
,r w'y .
6 ,__) - Date 7/25 Time 1600 CONTINGENCY MESSAGE
' MESSAGE FOR: Control Room SINULATED PLANT CONDITIONS:
;. :. ;. :. :. ; :. :. ;. ;. : ;. ;. ; :. :. ;. :. ;. :. ;. : :. ;. ;. ;. ;. ;. ;. ::. : ;. ;. ;. :. :. ;. ;. :. ;. :. :. ;. ;. ;, : ;. : :. :. :. ;. ;. :. :a k****
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- . ::;. :::::.;;;;;;;;;;;;;;;;;;k* ::::::::::::::::::::::::::::::
MESSAGE: Drywell radiation level has increased to 100 R/hr. ACTION EXPECTED: 73-
.t
_) 9
\
l l 3H-25
_~ _
,.s
( \ '.- 5._/ Date 7/25 Time 1615 CONTINGENCY MESSAGE MESSAGE FOR: Control Room
. SIMULATED PLANT CONDITIONS: Reactor pressure and water level are 380 psig and
+50 in., respectively.
********** ;. ; ;. :. : A ;. ; ;. ; ; ; ;. ; ;. :. ; ; ;. ; ; ; ; ; ; ; ;. ; ; ;. ;. ; ; ; ;. :. ; ; ; ; ; ;. :. :. ; ;. ; ; ; ;. ; ;. a a :. ;. ; ; a a :. ; ;. :.
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;t.<;;;;;;;;;
MESSAGE: RHR pua.p B flow has decreased to 500 gpm. (Event No. 4) ACTION EXPECTED: An operator is dispatched to investigate the problem with the RHR pump B. l )
'J t
f')i
\m/ FOR CONTROLLER USE ONLY 3H-26
f5 l-"% s / Date 7/25 Time 1615
- v.-
CONTINGENCY MESSAGE MESSAGE FOR: Control Room SINULATED PLANT CONDITIONS: THIS IS A DRILL D0'NOT initiate actions affecting normal plant operations.
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;::: :::::::::::akaa- a-;. : :
MESSAGE: RHR pump B flow has decreased to 500 spm.
. ACTION EXPECTED:
/ . !v! e x_ / 3H-27
s.
'.. 1' .
s s
- n. n s ,
N, i i te j 3 s Date 7/25 Time 1630
\v s ,
t. 3 i- t i.
-s= i CONTINGENCY MESS' ACE w
MESSAGE FOR:
- Control Room
;i': . ,,
SINULATEDs C '
.M PLANT CONDITIONS:" Airborne radiation levels in the reactor enclosure start rising significantly due ,to suull, leakage from the '
primary containment. '
. a THIS IS A DRILL' DO NOT initiate actions affecting normal plant operations.
. . ; ) :. : - - - - - - - - - :. ;. :. :. ; ;. u ;. . - - ; ;. ;. ;, ;. :. :. ; ;. :. ; ;. :. ; ;. : :. :. ;. ; ;. ;. : :. ;, ; ; ;. ; :. :. ;. :. :. ;,
Due to ttish airborne radiation levels, evacuation of the MESSAGE: i" Unit l' reactor enclosure is required.
; s ACTION EXPECTED: Reactor enclosure personnel accounting and investigation
(] for high airborne radiation source. (>' j
, :( %
,,-+>
x. r ,
' 3 s ,t ,
- t. .
A s %, ,
^ ,'
. , I '( h
~
( , s i
- k. . s
' ( g , h , \,
s t - s.., if- so i
^ ! ' '
'l,_ .)
Q , n ,'- _ f: v
/ /
s/,
; i
,l
*y y- g$ p; o ,..i 7(
q s t
. a,,
g ,
- y. p/ , ; {: -
. ..t 8,
*4 e e t' '%
** a .
x
'l 4
) (A - ,4 s
t 16,
, e s i fs % ,
t-I
\ 4 *l e
u) 5q .t , FOR CONTROLLER USE ONLY t.
*\
t
.. -'L j '
\,,
igs 35-28' 6 L a .
,i,
[ , N.
s ( ,,) ' Date 7/25 Time 1630 CONTINGENCY MESSAGE MESSAGE FOR: Control Room SINULATED PLANT CONDITIONS: i
***:::::::a;; ;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
THIS IS A DRILL , DO NOT initiate actions affecting normal plant operations. !
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;e MESSAGE: Due to high airborne radiation levels, evacuation of the Unit I reactor enclosure is required.
ACTION' EXPECTED: fy l
.'w J C
311- 2 9
~. ,
w
/
s-
/ ~'N* -;(
Date 7/25 Time 1650 q) . CONTINGENCY. MESSAGE
' MESSAGE FOR: Control Roca a
SIMULATED PLANT CONDITIONS: LAirborne radiation levels in the reactor enclosure still rising. i AAAAAA n., A A A A A A A A A A A 4 4 A A A A A A AN$ $ A A A A 4 4;. .MMM,. THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. m+ 4 :. ;. :. :. ;. ;. A :. 4 :. :. : :. :. :. ;. ;. ;. ;. : ************ :. ;. :. A A A ;. A A A :. ;. ;. A :. :. :. ;. MESS'GE: A The person investigating RHR pump B is. unaccounted for. (Event No. 5) l
. ACTION EXPECTED: A Search and Rescue /First Aid Group is dispatched to l find the person investigatirig the RHR pump B and to ask
- him to evacuate reactor enclosure.
~h, ,/.
A I
/
_4m-G
-(n)J v
% FOR CONTROLLER USE ONLY .
o we 3H-30
@ \
(_ 'g.
+ -e
. = WL- - r --,., . - , - - , , , , - - , , - . - , , , _ , . , _ . - -
t e I p, . , , j .
) Date 7/25 . Time 1650 CONTINGENCY MESSAGE e
MESSAGE FOR: Control Room SIMULATED-PLANT CONDITIONS:
- . :::::: : :::: ::::::::::a;;;;;;;;;;;;;;;;:: ::a*
TT.iS IS A DRILL DO NOT initiate actions affecting normal plant operations.
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;. ::::::: a;;;;;;;;;;;;;;;;;;;;
MESSAGE: The person investigating RHR pump B is unaccounted for.
' ACTION EXPECTED:
p. ( I s /
.v A
i l n
., 4 f.' '%
t 3H-31 l'
t ~s. ( ,) , Date 7/25 Time 1700 CONTINGENCY MESSAGE MESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS: Reactor pressure is 300 psig. Drywell pressure is leveling off at 4.5 psig.
- ;
- ::::aza :::: ;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
THIS IS A DRILL DO NOT initiate actions af fecting normal plant operations. MESSAGE: RCIC and HPCI pumps are manually tripped. ACTION EXPECTED: Reactor vessel is flooded with CS and LPCI.
. ,rb. -
A h 7(
. \x _ ,<) FOR CONTROLLER USE ONLY 3H-32
7- Time 1700 i i Date 7/25 8 ) m-CONTINGENCY MESSAGE
- MESSAGE FOR: Control Room
- SIMULATED PLANT CONDITIONS:
*****s ;. ;. :. ;. ;. ; :. :. :. : :. ;. :. ;. :. :. ;. ;. ;. ;. ;. : ; :. ;. :. :. :. :. ;. ;. :. :. :. ;. ;. ;. ; :. ;. ;. ;, ;. ;. ; :. ;. ;. : :. ;, ;. ;. ;. ;. . :. ;. ;. ;. ;. ;. :. ;. ;. ;, :. ;.
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: RCIC and HPCI pumps are manually tripped.
- ACTION EXPECTED:
.7'N 4
( L.)
- s. .-
t t - v 3H-33 e
,Ns **
l Time 1715 Date 7/25 Q) MESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS: LPCI is manually tripped once the reactor vessel is flooded. Cooldown is continued by circulating reactor vessel inventory through the SRVs to the suppression - pool using available CS pumps. THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- a;;;;;;;;;;;;;;;;;;;;;;;;a ::::::::::a;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
MESSAGE: CO2 storage unit 00S133 low pressure ALARM. (Event No. 6) ACTION EXPECTED: Investigation for the cause of the ALARM.
., - y Vf xx > i FOR CONTROLLER USE ONLY 7
( ,/ 3H-34 j
i Date 7/25 Time 1715 fjh/ ) l NESSAGE FOR: Control Room
~SINULATED PLANT CONDITIONS:
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: CO2 storage unit 00S133 low pressure ALARN.
. ACTION EXPECTED:
O v l l-i u. 3H-35 t-
7-. Date Time 1730 i 7/25 V* . CONTINGENCY MESSAGE MESSAGE FOR: Control Room SIMULATED
~PLAq CONDITIONS: Reactor vessel cooldown is continued. .
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. m i.;;;::;;;;;;;;:. ;a :.;.:.:. :: :. ;:::;;;;;;;;:.;;;;;, :: :
- MESSAGE: CO2 Portion of the fire protection system is inoperabl'e due to low tank pressure. (Event No. 6)
-ACTION EXPECTED: A continuous fire watch should be established for those areas in which redundant systems or components could be damaged. For other areas, an hourly fire watch patrol is established.
4
,-g . -
< . _.I. I FOR CONTROLLER USE ONLY c xj - 3H-36 e-mer -, ,,,r-+-,-,w,- ,-
Date 7/25 Time 1730 ^ [ )3 s,_ CONTINGENCY MESSAGE MESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS:
- :. - - - ;. : :. ;.:. A ;. A ;.;. A A A ;.:. A A ;. ;, A A A A ;. : :.:.:. A ;. A ;.:. :. A ;. A A ;. A ;. A A A A A ;. A ;. :. :,;.:. A A A ;. A A ;. :. A A A A A ;.
THIS IS A DRILL t DO NOT initiate actions affecting normal plant operations. AAAAAAAA-- AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA;.AAAAAAAAAAAAAAAAAAk D
- MESSAGE: ~CO2 Portion of the fire protection system is inoperable due to low tank pressure.
. ACTION EXPECTED:
rm ( i l j-V(- 3H-37
]
Ux_ - Date 7/25 Time 1730 NESSAGE FOR: Control Room SINULATED PLANT CONDITIONS: Reactor vessel cooldown is continued. THIS IS A DRILL d' DO NOT initiate actions affecting normal plant operations. MESSAGE: East RHR' heat exchanger room (103) fire ALARM. RHR pump B trips. (Event No. 7) ACTION EXPECTED: Fire Fighting Group is dispatched to the scene. i',-.3)
-\,_/
im ( . or ..
\, )f FOR CONTROLLER USE ONLY 3H-38
,~ _ , Date 7/25 Time 1730
' MESSAGE FOR: Control-Room SIMULATED:
PLANT CONDITIONS:
' ~
h ;. :. :. ; ;. ;. ;. :. ;. :. ;. ;, ; ; ;. ;. :. :. ;. ;. ;. ;. :. '. :. ;. ;. ;. :. :. ;. :. :. :. ;. :. :. :. : : :. :. ;. ;. ;. ;. ;. ;. ; ;. ;. : : : ;. :. ;. :. ;. a ;. :. ; ;. ;ck THIS IS A DRILL
-DO NOT initiate actions affecting normal plant operations.
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;; :::::::::::::::::::a 1
- MESSAGE: East RHR heat exchanger room (103) fire ALARM.
RHR pump B trips.
' ACTION EXPECTED:
k t
,y.a .A '}
- %)
I l-
~
i 3H-39
- - = . - - - - . - - - - . . , , - - - . r,,-.,_ _ - . . . . . _ , , _ . - - . . _ . _ . ,
1
,c-( ).
LI Date 7/25 Time 1730+ CONTINGENCY MESSAGE MESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS: Cause of the fire is unknown, but it is fueled by scaffolding material brought there in preparation for an inspection of the RHR heat exchangers. Fire has disabled both RHR pump B and D motors.
;;;;l:.:. :.:. :::::::. :::: :. ::::aa :::::;;;;;;;;:. ::::;.;;;;;;;;;; :;. :::. :::
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. MESSAGE: Drywell radiation level 1000 R/hr.
- ACTION EXPECTED: " Site Emergency" should be declared.
p-g
, 4.
gf 4 A k J
,m.
/ \
- b. /
FOR CONTR0 LIER USE ONLY 3H-40
- w. . _.
o
.<=-
Time 1730+
.. !. / Date 7/25 CONTINGENCY MESSAGE MESSAGE FOR: Control Room SIMULATED PLANT CONDITIONS:
a; ; ;. ;. :. ; ; ;. ;, ;. :. ; ; ;. :. :. :. :. :. ; ;. :. :. :. : : :. :. :. ;. :. ;. ;. . :. : :. :. ; ; ;. :, :: : :. ; : ;. :. :. :. :. ;. ;. :. :. :. :. :. a*** THIS IS A DRILL DO NOT initiate actions affecting normal plant operations .
- . ;. ;. :. :. :. ;. ;. ; ;. ;. :. :. ;. :. :. ;. :. ;. ;. :. . : ;. :. :. ;. ;. ;. :. :. :. :. :. ;. :. ; ; ;. :. :. ;. :. ;. ;. :. :. ;. ;. :. :. :. :. :. :. :. :. :. -A4 ; ; ; ; :. :. :ckk
.' MESSAGE _: Drywell radiation level 1000 R/hr.
. ACTION EXPECTED: ,
~
'\ l
~
%)
I i 1 s I \
\j.
3H-fi e t-- -- e- *-m-- ,------rm , ---e e . - - , , _ . - - . - -
l, y-()g
-t Date 7/25 Time 1845 MESSAGE FOR: Control Room
. SIMULATED PLANT-CONDITIONS: Containment purge exhaust isolation valve HV-57-114 indicates open position.
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- a::::::::::
MESSAGE: Status lights on the control board indicate the con- _tainment isolation valve HV-57-114 in the containment purge system has backed off the fully closed position.
.(Event No. 8)-
ACTION EXPECTED: Repeated attempts from the control room to close the valve. p -.< y 1 % / . f i 5 _ h. ( \
;\ /- FOR CONTROLLER USE ONLY
.~.-.
3H-42
]
5
.u*-w-r i N[ 'Date- 7/25 . Time 1845 MESSAGE FOR: LControl Room
' SIMULATED' PLANT CONDITIONS:
4 THIS IS A DRILL
.DO NOT initiate actions affecting normal plant operations.
MESSAGE: Status lights on . the control board indicate the con-tainment isolation valve HV-57-114 in the containment Purge - system has backed off the fully closed position. ACTION EXPECTED:
.,-q
~( ,
L _]%/ , ' I ~
\
3H-43
-n -
v - - . ',. - - - . - . . . __
kj. , Date 7/25 Time 1915
+
[ MESSAGE FOR: Control Room
~
SIMULATED PLANT CONDITIONS: Repeated attempts from the control room to close the containment. purge exhaust isolatiou valves are unsuccessful. THIS IS A DRILL DO NOT' initiate actions affecting normal plant operations. i MESSAGE: . Containment purge exhaust isolation valve HV-57-115 indicates open position. (Event No. 8)
-ACTION EXPECTED: -Personnel will be dispatched to try to shut the valves
,q locally.
.j-
..'g {-
's / ~
- p .
T
'/% '
e'
~.' .FOR. CONTROLLER USE ONLY 3H-44 C ^ j
h :-,
t i
)- Date 7/25 Time 1915 xx
- MESSAGE FOR: Control Room.
SIMULATED PLANT CONDITIONS:
- a; ::::::::::::::: ::::::::::: :::::::::: :: :: :::: :: :::::
THIS IS A DRILL DO NOT initiate actions affecting normal plant cperations.
;;;;;;;;;;;;;;aza:::::::::::::::::::: : ::azaaaa :::::: ::: : : : :: ::*
M_ESSAGE: Containment purge exhaust isolation valve HV-57-115 indicates open position.
ACTION EXPECTED:
.) m -
c'? \ t 4
\ /
- .'%J
)
4. t'
- ~!.y 3H-45 8 w -w -
Vs Date 7/25 Time 2040 MESSAGE FOR_: Control Room SIMULATED
- PLANT CONDITIONS: The radiation release path to the atmosphere is still open. It is estimated that it will take about 9 hours to' terminate the release.
THIS IS A DRILL DO NOT ' initiate 1 actions affecting normal plant operations.
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;aza;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
1
. MESSAGE: ~CS pump A trips.
CS pump C is not affected and continues to operate.
~
(Event No. 10) ACTION. EXPECTED: Personnel will be dispatched to investigate the problem. CS B'and D pumps are manually initiated. f~~N; g CS pump C is tripped, a.g/ -- 4 4 4 L
" ! r, . ..
~U1
'kT j .
.'"*\
( + 2( l- FOR CONTROLLER USE ONLY
. 3H-46
- m. , d
y, -~\
?
'\ /
! Date 7/25 Time 2040 m./
-MESSAGE FOR: Control Room -
SIMULATED _
- PLANT CONDITIONS:
*********************k*a ; :. :. :. ;. ;. ;. ; :. :. ;. ;, ; ;. ;. ;. ;. ;. ; ; a :. : : :. ;. : :. : ;. ;. :. ;. ;. : ;, ;. ;. ;. ;. ;. : :. ;. ;. :
THIS IS A DRILL DO NOT' initiate actions affecting normal plant operations. , ::::::::::::::::::::::::::::::::::::a;;;;;::: :::::::::::::::::::::::::::::
-MESSAGE: CS pump A trips.
.CS pump C is not affected and continues to operate.
ACTION EXPECTED: 7-~
- e e A/
4 % i a t l i ( \
%J-3H-47
< jm. Date 7/25 Time 2145 CONTINGENCY MESSAGE MESSAGE FOR: Control. Room 1 i
' SIMULATED '
Releases-to the atmosphere are terminated. PLANT CONDITIONS: THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. A :::a;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;::::::::::-
- MESSAGE: Containment purge exhaust isolation valve HV-57-115 is repaired. (Event No. 8)
' ACTION EXPECTED: Deescalation of emergency to " Site Emergency" and later to " Alert" status is considered.
p,
, s
' u.,]
s. q.. i .. V:
. i - (sl
'V FOR CONTROLLER.USE ONLY 3H-48
.I
; 's - Date 7/25 Time 2145
\ /-
%,s -
CONTINGENCY MESSAGE MESSAGE FOR: Control Room SIMULATED. PLANT CONDITIONS:
****h************kr. :. ;. ;. :. 4 :. ;. ;. ;. ;. ;. A A :. :. :. ;. ;. :. :. A A ;. :. :. A :. ;. ;. ;. ;. ;. ;. ;. ;. ;. ;, ;. ;. A :. A ;, :. :. A :. ;. ;. A :. ;. A :. :. :.
.THIS IS A DRILL DO NOT- initiate actions affecting normal plant operations.
i AAAA- AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA;rAAAAAAAAAAAAAAAAAAA MESSAGE: Cont,ainment purge exhaust isolation valve HV-57-115 is repaired. ACTION EXPECTED:
-:'[ ny- I.
1: J
'~
3H-49
-4 i_ -
's_,/ Date 7/25 Time 2200 CONTINGENCY MESSAGE MESSAGE FOR: ' Control Room
-SIMULATED PLANT CONDITIONS: Releases to the atmosphere are terminated.
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;k MESSAGE: Containment purge exhaust isolation valve HV-57-114 is repaired. (Event No. 8)
' ACTION EXPECTED:
Deescalation of emergency to " Site Emergency" and later to " Alert" status is considered.
- s
( )
< *g N
1
- ?
Aj- FOR CONTROLLER USE ONLY 3H-50 m
? \
( s/ , 4 Date 7/25 Time 2200 CONTINGENCY MESSAGE MESSAGE FOR: Control Room
-SIMULATED PLANT CONDITIONS: 1
- :::::::: :::azzazzazazazaaaaaaa;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
THIS IS A DRILL' l DO NOT initiate actions affecting normal plant operations. NESSAGE: Containment purge exhaust isolation valve HV-57-114 is repaired. ACTION EXPECTED: k
.Q 4
i
\'
l 3H-f/
HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 1830 MESSAGE FOR: EMERGENCY DIRECTOR
.j i
3 < ( v /-
; ;;;;;; ;;;;;. ;;;;;;; ; ;; ; ;;; ;; o ;;;;;;;; ;;. ; ;;;;;;;;;; ; ;;;;;; ;; ;;;;;;; ; ;; ;; ; ; &*
THIS IS A DRILL DO NOT. initiate actions affecting normal plant operations.
******+; ;. ; ; ;. ;. ; ;. ; ;. ; ; ;. :.-; ; ;. ;. :. ; ;. ; ;. :. :. ; ; ;. ;. ;, :. ; ;. ; ;. :. :. :. ; ;. ;. ; ;. ; ;. ;. ;. :. :. :. :. :. :. ; ;. ; ; ;. :ct.+.wa+k;*
MESSAGE: Headquarters engineering support is needed to devise supplementary radwaste processing methods. Temporary system and storage tanks should be sent to
. LGS.as soon as possible.
v
') -
ACTIONS EXPECTED: Submit request to Site Emergency Coordinator. FOR CONTROLLER USE ONLY
/
.- / \- SI-l'
)
HEADQUARTERS SUPPORT MESSAGE ~ DATE: 7/25/84 TIME: 1830
. ,f s ' MESSAGE FOR: EMERGENCY DIRECTOR 3
t, )
%l .
**ka z a a ;. :. : :. ;. :. :. ;. :. : :. :. ;. :. :. : ;. :. :. : ;. ;, ;. ;. :. : :. :. ;. ;. : :. :. ;. :. : :. : ;, : ; ;. ;. ;. :. :. :. :. :. :. : ;cu a ;. :. :wk THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
***ks i. :. :. ;. :. :. :. :. :. :. ;. ;. :. ;. :. :. :. : :. ;. ;. ;, ;. :. ;. ;. ;. :. ;. ;. ;. ;. :. ;. ;. ;, ;. :. :. :. ;. ;. ;. : ;. ; ; ; ;. :. : : : : : :. ;. : :
MESSAGE: Headquarters engineering support is needed to devise supplementary radwaste processing ' methods. Temporary system and storage tanks should be sent to LGS as soon'as possible. () ACTIONS EXPECTED: i l.
.k
- ~
l [ .. 3I-2 2
. HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 1850 MESSAGE FOR: EMERGENCY DIRECTOR
- .rm .I \
'%-) .
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. a;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
' MESSAGE: .
' Headquarters support is needed to expedite the following purchasing requirements:
300 Anticontamination Suits and Hoods 500 Pairs of Rubber Gloves 1,00'O Rolls ~of 2.in. Masking Tape
,# y x
ACTIONS EXPECTED: Submit request to Site Emergency Coordinator. e FOR CONTROLLER USE ONLY I a i
\ .'
3I-3
.1
HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 1850
, $2.; MESSAGE FOR: EMERGENCY DIRECTOR-
g,~ . ,
/,v/ ,
i + ,t _ > . '$ ,\ k
'I ~ k'$I;A;;AAA;:$$ plt;Lj&;l:l;:::
. .......AA; ;. E;. A ;. ;. l. A ;. l. A : ;.1 A ;. A ;. :. :. :. ;. :. l. :. ;. :. :. :. A ;. :. :. ;. :. A A ;. ;.
,. ,Is - %\
s THIS IS A DRILL s i-.
.: 9 DO NOTg ,initiate actions affecting nousal plant operations.
s .
\
_(_ A A ;. A A A;.;. A A A A (A A;. a j. A A A A A A A ;.J. A ;. A A A A ;. ;.l. ;. A A ;. A A A ;.;.;.;.;;. J.J. A ;.l. A A ;, A ;. A A A A A A ;. A A ; J. A A A A k ( - B
' MESSAGE:
\h \
- Investigate' arrangements for feeding emergency center and plant personnel on an extended basis, i
\q
,W ,
,L t
T gg i
'()
t \ ACTIONS EXPECTED: Submit request to Site Emergency Coordinator.
.s b
FOR CONTROLLER USE ONLY y
, L]f: l r)
.c -
.- w s
t [%s,.. - e i i i L.) . u o N.!. . - [ f- 1. s
+f 3I-5
+ j
ed HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 1910
,_,s -
MESSAGE FOR: EMERGENCY DIRECTOR
/ T-
; /
.us
***11nir*1lrA A A A A A A A A A A A A A A A A A A A A A A A A A A A A ;;41 A A A A A A A A Aa a a A A A A A A A A A A A A A A A A A A A A A A A THIS IS A DRILL
., DO NOT initiate actions affecting normal plant operations.
$$$NhNN$NANANENSANNNkSNN$$$NNNNNNEk$NNNEN$$AkNNNN$$k $NNNNENNNNbb NbN NNN b MESSAGE:
Investigate arrangements for feeding emergency center and plant personnel on an extended basis. ( ) w/ ACTIONS EXPECTED: 4 O 3I-6 l J
r l HEADER SUPPORT MESSAGE DATE: 7/25/84 TIME: 1925
' MESSAGE FOR: EMERGENCY DIRECTOR ., -
-L] ,
A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A ".*k**"A***** A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A I 4 THIS IS A DRILL
'D0 NOT initiate actions affecting normal plant operations.
AAAAAAAAAA AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAYrA*AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA MESSAGE:, '
, ,s The, Lieutenant Governor -is requesting a visit to the TSC and a briefing of
' the plant' status. ' State House presa representatives will accompany him. A D PECO: representative r,hould be assigned'to contact him.
6', , ,, ,
.-t ,.
W + . f
.,x.
?
~ j
. v.cs-
~, .f-J; t
n, , 81 I I ^ \v/ -
' - . 'e / '"
-ACTIONS EXPECTED:
~ ~ ' *
,N. :J
.' t _. / . f. ,
\
> ' Submit request to Site 1Etergency Coordinator.
n
. 1c -
.+
.. w , , j- .
u -,3 - .,
' ?
\ , >
s ,-~
/
, . -w^ .
t'
'l3 bi , FOR CONTROLLER USE ONLY ,
o . ['y _' ' l ..lge
,. . tf ar - .
1 ;j. :s ! ,
.a v?} ,
+
kj y
.w ,
I /
- p. ,
pt. N's Y^ ;+$ ' f 4
/,
t
' (' :
- s. i !s .
]J:
\ . . . .Jh* -j , .. ,-
.y
)_ /~ .
. N _../ - : * ,
45 5 y '.h' a,
- -/-
l ,=.
.l j,-
2 q L -: f :r $ 4 3I-7 y ~. , Q ... _
- .- /' )
8 e HEADER SUPPORT MESSAGE DATE: 7/25/84 TIME: 1925 MESSAGE FOR: EMERGENCY DIRECTOR
. ,m. '- J \. .\ n "%)_
I THIS IS A DRILL 1 DO NOT. initiate actions affecting normal plant operations. j MESSAGE: The Lieutenant Governor is requesting a visit to the TSC and a briefing of the plant status. State House press representatives will accompany him. A PECO representative should be assigned to contact him.
%/
ACTIONS EXPECTED: 1 v l t I i-f 3I-8 l' J
')f f HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 2030 MESSAGE FOR: EMERGENCY DIRECTOR
/^N
-(\ J)
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- :: azaa :::::::::::::::::::::::::: :::::::::
MESSAGP.; There is an -immediate need for 20 RM-14 Friskers at LGS. Units should be purchased or borrowed from supporting organizations.
/*
t,v) ACTIONS EXPECTED: Submit request o Site Emergency Coordinator. FOR CONTROLLER USE ONLY n
'[ ! s.\
u \_/ - o 3I-9 E -J
i HEADQUARTERS SUPPORT MSSAGE DATE: 7/25/84 TIE: 2030 l MESSAGE FOR: EMERGENCY DIRECTOR ! i. \ j k*******A :. : :. : ;. ;. :. :. :. :. : THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
. MESSAGE:
.There is an immediate need for 20 RM-14 Friskers at LGS. Units should be purchased or borrowed from supporting organizations.
O'xJ ACTIONS EXPECTED: I (~J 3I-10
HEADQUARTERS SUPPORT MESSAGE DATE 7/25/84 TIME: 2050 MESSAGE FOR: EMERGENCY DIRECTOR
\vr
**;;;;;;;;;;a****** ,;;;;;;;;;;;;;;;;;;;;;;;;;;.;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
;;;a;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;>e**
MESSAGE: ' ~ A call has been received from a Lieutenant of the Pennsylvania State Police. HHe would like to coordinate road blocking status with a PECO representative in Philadelphia. ACTIONS EXPECTED: L(;.A) . Submit request to Site' Emergency Coordinator.
,s FOR CONTROLLER USE ONLY f
sd + 0 /
%,/ ~ .
w 3I-11 i
HEADQUARTERS SUPPORT MESSAGE
. DATE 7/25/84 TIME: 2050 17%.t : MESSAGE FOR: EMERGENCY DIRECTOR
-i I f
L / . -
- 11
**************s a k a a ;. .;. ::;.;;.:. ;. ::.:. ;;;. ::.;;;.;. : ;. :. :::::;. ;.;.;;. ::::::: :.
~
THIS IS A DRILL D0'NOT initiate actions affecting normal plant operations. MESSAGE:
'A call.has been received from a Lieutenant of the Pennsylvania State Police.
-He would like to coordinate road blocking status with a PECO representative in : Philadelphia.
i A. ACTIONS EXPECTED: i \ s v 6 s 31-12 ;
HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 2110 MESSAGE FOR: EMERGENCY DIRECTOR y s, $ Y,
; A;;;;;;.; ;. A A-*%;;;;.; A A;./. A;;.;;;.; ;;;.1,;.;;.;;;;.;,;.; ; ;;;;..;;,;.;. ;;.;;.;.;. A;.l.; ; ;;;;;;; A A A-THIS IS A DRILL s DO NOT initiate actions affecting normal plant operations.
;;;;;;;;;;;;;;;; A;.;;;;;;; A A;. A;;;;;;;;;;;;;;;;;;;;; A;;;;;;;;; A;;-t a;;;;;;;;. A A MESSAGE:
A call ' has been received from a panicked nearby resident requesting help.
' A family member who was outside when the public alert sirens came on, has started vomiting and there is fear for high radiation dose exposure.
. ACTIONS EXPECTED:
n- ' Submit request to Site Emergency Coordinator. l i-
,' s f-FOR CONTROLLER USE ONLY l,
t
.J 3I-13 j
HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 2110
-MESSAGE FOR: EMERGENCY DIRECTOR
_ ;,3
)
w/ 4
.;;;;;;;;kaa;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
THIS IS A DRILL' DO NOT initiate actions affecting normal plant operations. M ; ; ; ;. ; ;. :. ; ;. ;, ;. ;. ; :. :. ; ; ;+; ; ;. ; ;. ; ;. ; ; ; ; ; ; ; ; ;. ; ;. ; ; ; ;. ;. :. :. ;. ; ;. :. :. :. ; ; ; ; ; ;. ; ;a ;. ; ;. ;. :. ; ; ; ; ; ; ;-aa MESSAGE: A call 'has 'been received from a panicked nearby resident requesting help. A family member who was outside when the public alert sirens came on, has started vomiting and there is fear for high radiation dose exposure. ACTIONS EXPECTED:
- -(
[ \ () 1' F i i-i v l l i l 0 LU t 31-14
)
HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 2130 MESSAGE FOR: EMERGENCY DIRECTOR
}"% .
'. r 3 NJ-
. : :. ;. ;. ;. ;. ;. ;. : : :. ;. ;. :. : A M. ;. :. : : :. :. : :. :. ;. ;, ;. : : :. : ;. :. ;. :. ;. : ;, :. ;. :. ;. ;. ;. : . . :. :. :. ;. ;. : ;. ;. :. ;, ;, ;. :. a ;.
THIS IS A DRILL 1 DO NOT initiate actions affecting normal plant operations. MESSAGE: I&C: support is. requested from headquarters to analyze the effects of steam
.and -radiation in containment on instrumentation. Need to know from environmental qualification data if any instruments' are susceptible to
-continue reading on scale after failure.
t" _t ! j$/ ACTIONS EXPECTED: Submit request to Site Emergency Coordinator. FOR CONTROLLER USE ONLY a 1 i
. (,/ ,
3I-15
HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 2130
' MESSAGE FOR: EMERGENCY DIRECTOR
.y l )~
%f AA;;AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA;;AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA MESSAGE: _, I&C support is requested from headquarters to analyze the effects of steam and- radiation in containment on instrumentation. Need to know from ! environmental qualification data if any instruments are susceptible to continue' reading on scale after failure.
'f") , \/ ' ACTIONS EXPECTED: !
i G O 3I-16 j
HEADQUARTERS SUPPORT. MESSAGE DATE: 7/25/84 TIME: 2150 MESSAGE FOR: EMERGENCY DIRECTOR
- g. -.
! 1 y/
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. a :::::::::::::: :::::::::; ::;;;;;;;;;:::::::::::::::::::::::::::::::::::: MESSAGE: Construction personnel are required to erect a temporary wooden storage building, with 200,000 cu ft storage capacity. Building will be ~ used to store emergency equipment enroute to LGS and is to be , erected near the information center parking lot area. 4 i im i 5 / _v ACTIONS EXPECTED:
' Submit request to Site Emergency Coordinator.
v, i FOR CONTROLLER USE ONLY l t
- Ch v
31-17 J
E ADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 2150 MESSAGE FOR: EMERGENCY DIRECTOR e 1
-1 /
v .
. ::::::AA :::::::::::;. ::::;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;;
THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- :::::::::::;;;;;;;;;;;. :::::::azaaaa;;;;;;;;;;:::::::::::::::::::::::::
MESSAGE: . , Construction personnel are required to erect a temporary wooden storage building, with 200,000 cu ft storage capacity. Building will be used to store emergency equipment enroute to LGS and is to be erected near the information center parking lot area. f I s-(m)
'tj' i
ACTIONS EXPECTED: r l l
- l. '
l 31-18 J
HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 2210 MESSAGE FOR: EMERGENCY DIRECTOR
'/ g- / 1 Q,)
AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA THIS IS A DRILL DO NOT initiate actions affecting normal plant operations. AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA;.AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA;,AAAAAAA MESSAGE: Headquarters QA/QC support is needed to inspect emergency repair methods and approve welding'in process.
. /m . 't \
- i ACTIONS EXPECTED:
Submit request to Site Emergency Coordinator. FOR CONTROLLER USE ONLY G 3I-19 k- J
T HEADQUARTERS SUPPORT MESSAGE DATE: 7/25/84 TIME: 2210 MESSAGE FOR: EMERGENCY DIRECTOR y m..
-( \.
t /
'v -
A;;;;;;;AAAAA ::AAAA :::::A AAAA :A AAA A A A :AA;;;;;AA :::A;;;aaAAA;;;;;; THIS IS A DRILL DO NOT initiate actions affecting normal plant operations.
- A A A ::A :AAAAAAA ::AAA;;A : A ::::A :A AAAA;;;;;;;AA ::::::::::.;;;;;;;
MESSAGE: Headquarters QA/QC support is needed to inspect emergency repair methods and
. approve welding in process. - n .t t '%)
- ACTIONS EXPECTED:
bst 31-10 J
rx a U U,rs U Time ' '00 Mours l IAS 7/25 Reactor Level +7f inches Drywell Press O.4 psig Reactor Pressure /000 psig SGTS Flow o cfm Re:ctor Power /001 Full Power Drywell Atmos Temp 17 0 *F Ccra Plate DP /0 0 1 Full Power Supp Pool Press 0. 6 psig Cars Flow /00 lb/br x 10 4 . 3,,,p g 7,,, yg .y Tctal Steam Flow // lb/hr x 10 8 Supp Pool Level 22s/ feet. Tatol Feedwater Flow /d/ lb/br a lo s Main Sta Line Rad Non //00 mR/hr condpascr Vacuus 29 inches Ng Containment Red Level 2 R/hr Notwell Level //O inches Cond Stor Tank Level 39 feet l CRD Charging Pressure /Joo psig RCIC Flow o spe Isat. Gas to ADS Pressure //O psig NPCI Flow o gym Equip. Drain C011 Tank Level J feet RNR A Flow o spa Equip. Drain Surge Tank Level J feet RHR R Flow a spa Floor Drain Coll. Tank Level / feet Core Spray A Flow o gym Floor Drain Surge Tank Level 8 . feet Core Spray B Flow 0 3p. Na Concentration 4 % RHR Mx Outlet Temp 96 *F 02 Concentration 26% RHR SW Inlet Temp $O *F RHR C Flow 0 gym RHR D Flow 0 sp. Ui W ~ ]
;f .
U V, Time /l30 Houro j tsS 7/2s Reactor Level f ff inches Drywell Press o./o psig Reactor Pressure /OJo psig SGTS Flow o cfm Reactor Power /40 % Full Power Drywell Atmos Temp A *F Core Plate DP /00 % Full Power Supp Pool Press 0.h psig Core Flow /00 ,Ib/br x 10 8 Supp Pool Temp 94 *F Total Steam Flow // lb/br x 108 Supp Pool Level 27/ feet Total Feedwater Flow /Y lb/hr x 10 8 Nain Stm Line Rad Hon //oo mR/hr Condenser Vacuum 27 inches Ng Containment Rad Level 2 R/hr Hotwell Level 1/0 inches Cond Stor Tank Level 78 feet CRD Charging Pressure /700 psig RCIC Flow O gym Inst. Gas to ADS Pressure //O psig , HPCI Flow 0 gym Equip. Drain Coll Tank Level 7 feet RHR A Flow a gym Equip. Drain Surge Tank Level I feet RHR R Flow O gym Floor Drain Call Tank Level / feet Core Spray A Flow 0 gym Floor Drain Surge Tank Level J feet Core Spray B Flow () gpa H2 Concentration O 1 RHR Nx Outlet Temp 90 *F 02 Concentration 28% RHR SW Inlet Temp 80 *F RHR C Flow O SPE RHR D Flow 0 SPm d h C
o _A q
~
Time /Jod Hours l LGS 7/25 Reactor Level /7f inches Drywell Press 0.6 psig Reactor Pressure /030 psig SGTS Flow d cfm Reactor Power /00 % Full Power Drywell Atmos Temp /JO *F Csre Plate DP /00 % Full Power Supp Pool Press 0.6 psig Care Flow 10 0 Ib/hr x 10e 3,,,p g y,,, pg_ ey
-Tatal Steam Flow // lb/br x 108 Supp Pool Level 27. / feet Tatal Feedwater Flow // lb/br x 108 Main Ste'Line Red Non //po mR/hr Condenser Vacuum 99 inches Ng Containment Bad Level 2 R/br Hotwell Level //B inches Cond Stor Tank Level 7,8 feet CRD Charging Pressure /Joo psig RCIC Flow d gym Icst. Gas to ADS Pressure //0 psig NPCI Flow O 3pm Equip. Drain C011 Tank Level J feet RHR A Flow O ape Equip. Drain Surge Tank Level J feet RHR R Flow 6 spe Floor Drain Coll Tank Level / feet Core Spray A Flow O spe Flood Drain Surge Tank Level 7 feet Core Spray B Flow 6 spe H2 Concentration 4% RHR Mu Outlet Temp 80 *F 0 2 Concentration 7.A % RHR SW Inlet Temp 88 *F RHR C Flow O spa RHR D Flow 1 gPm d
- L
O Time ),270 Mouro l LGS
/.
~
7/25 Reactor Level fII inches Drywell Press ..O,6 psig Reactor Pressure /p)O psig SGTS Flow O cfm Reactor Power /00 1 Full Power Drywell Atmos Temp /fo *F Core Plate DP /od 1 Full Power Supp Pool Press o.6 psig Core Flow /00 Ib/hr x 10 8 Supp Pool Temp 98 *F ' Total Steam Flow // lb/br x 108- Supp Pool Level 22./ feet Total Feedwater Flow /// lb/br x 108 Main Ste Line Rad Non //00 mR/br condenser vacuum J79 inches Ng Containment Rad Level J R/hr Notwell Level /B inches Coed Stor Tank Level 78 feet CRD Charging Pressure /.fdo psig RCIC Flow O ape Inst. Cas to ADS Pressure //O psig NPCI Flow d gym Equip'. Drain C011 Tank Level 7 feet RNR A Flow d spa Equip. Drain Surge Tank Level 7 feet R M R Flow d gym , Floor Drain 0011 Tank Level f/ feet Core Spray A' Flow O gym Floor Drain Surge Tank Level 7 feet Core Spray R Flow O gym Na Concentration d1 RW Ms Outlet Temp 60 *F 0 2 Concentration 47. 8 1 RNR SW Inlet Temp Fo *F l RHR C Flow O gym . RHR D Flow _O 3Pm L
O Time /10 0 Boers O IAS O 7/25 [ Reactor Level 157 inches Drywell Press o.6 psig Reactor Pressure /07 0 peig SGTS Flow a cfm Reactor Power /04 % Full Power Drywell Atmos Temp -
/SO *F Core Plate DP /# 1 Full Power Supp Pool Press O.& pois Core Flow /#4,Ib/br a 188 Sepp Pool Temp 94 *F Tatal Steam Flow /! lb/br x 188 Supp Pool Invel M / feet Tatal Feedwater Flow // lb/br a les Main Ste Line Red Non //44 mR/hr Condenser Vacuum 2 9 inches Ng Containment Rad level # R/hr Notwell Level MS inches Coad Stor Tank Level 7,8 feet CRD Charging Pressure /f40 peig RCIC Flow O gym last. Gas to ADS Pressure //s psig 'MPCI Flow d gym Equip. Drain 0011 Tank Level 7 feet Rim A' Flow O gym Equip. Drain Surge Tank Level 7 feet Rim B Flow 6 gym Floor Drain C011 Tank Level ! feet Core Spray A Flow 4) gym Floor Drain Surge Tank Level 7 feet Core Spray B Flow O gym M2 Concentration 8 1 RHR Ma outlet Temp 6'O *F 0 2 Concentration d.8 % Rim SW lelet Temp go *F RHR C Flow O SPm RHR D Flow 0 gen dI k_
,: , .y
~
Time /3[
~
Hours l . LGS 7/25 Reattor Level tJf inches Drywell Press O. 6 - psig
- Reactor Pressure /OJo psig SGTS Flow O cfm Reactor Power /00 % Full Power Drywell Atmos Temp /JO *F Core Plate DP . /00 % Full Power Supp Pool Press B,/r psig Core Flow m ,Ib/hr x 10 8
Supp Pool Temp To *F Total Steam Flow // lb/hr x 10 8 Supp Pool Level 27,/ feet Total Feedwater Flow // lb/hr x 108 Main Stm Line Rad Hon //00 mR/hr Condense.r Vacuum :PT inches Ng Containment Rad Level 1 R/hr Notwell Level t/O inches Cond Stor Tank Level 7f feet CRD Charging Pressure /Joo psig RCIC Flow C gpa Inst. Cas to ADS Pressure //O psig MPCI Flow d gpa Equip. Drain Coll Tank Level J feet RNR A Flow , O gpm Equip. Drain Surge Tank Level .7 feet RNR R Flow O gpa Floor Drain Coll Tank Level J/ feet Core Spray A Flow O gpa Floor Drain Surge Tank Level 7 feet Core Spray B Flow d spa H2 Concentration 8 1 RNR Ex outlet Temp 80 *F O2 Concentration 2,8 % RHR SW Inlet Temp @ *F JHR C Flow O gP" RHR D Flow gPm d a m
,7% p .
.(
\
Time S/F F Noura LGS 7/25 Reactor Level O inches Drywell Press 0,d, peig Reactor Pressure //0 0 psig SGTS Flow d cfm Reactor Power O 1 Full Power Drywell Atmos Temp 60 *F Core Plate DP 20 1 Full Power Supp Pool Press 0,6 psig Care Flow 20 Ib/br x le s 3,p,p g y,,, pg op Txtal Steam Flow O lb/br x 10 8 Supp Pool Level 3 % 9 feet Tatal Feedwater Flow 2. Ib/br x 10 8 Main Sta Line Rad Non /[B mR/hr Condenser Vacuum .I inches Ng Containment Rad Level /- R/hr Hotwell Level / inches 4d Cond Stor Tank Level }f feet CRD Charging Pressure /700 psig RCIC Flow C spe Inst. Gas to ADS Pressure //S psig NPCI Flow O ape Equip. Drain Call Tank Level 3 feet RHR A Flow 8 3pm Equip. Drain Surge Tank Level f feet RHR R Flow d gym Floor Drain 0011 Tank Level / feet Core Spray A Flow O gym Floor Drain Surge Tank Level 3 feet Core Spaay B Flow 6 spa H2 Concentration O1 RHR Ns Outlet Temp 88 *F 0 2 Concentration j.f] % RHR SW Inlet Temp 84 *F RHR C Flow O_, SPB RHR D Flow O _ EPs d 4 m
~
( v O~ V Time /J/7 Bours l I418 '7/25 Reactor Level -88 inches Drywell Press D,8 peig Reactor Pressure /d/O peig SGTS Flow ESC O cfm Reactor Power O 1 Full Power Drywell Atmos Temp /70 *F Core Plate DP 20 1 Full Power Supp Fool Press 0.6 peig Care Flow JO Ib/hr x 10 8 Supp Fool Temp 90 *F Tztal Steam Flow 0 lb/hr x 10 8 Supp Pool Invel J2 4 feet Tatal Feedwater Flow d Ib/br x 10s Main Sta Line Red Non /2b mR/hr condenser Vacuum O inches Ng Containment Rad Level / R/hr Motwell Level 79 inches' Coed Stor Tank Level 74 4 ' feet CRD Charging Pressure. -/700 psig RCIC Flow 6f0 spe Icst. Gas to ADS Pressure //O psig MPCI Flow f400 spa Equip. Drain Coll Tank Level 7 feet RR A Flow 6 spa Equip. Drain Surge Tank Level J feet RIR R Flow O gym Floor Drain Call Tank Leve! / feet Core Spray A Flow O gym Floor Drain Surge Tank Level 7 feet Core Spray B Flow d spo M2 Concentration 0 1 R R Mx Outlet Temp 80 *F O 2 Concentration d.8 % RNR SW Inlet Temp K0 *F RHR C Flow O gPm RHR D Flow O gym s N E
p .i
~
Time /f [ Nours l LGS 7/25 Reactor Level 7 [d inches Drywell Press /[ psig Reactor Pressure /OSfysig SGTS Flow M 8 0 cfm i , Reactor Power O 1 Full Power Drywell Atmos Temp /V+/ *F Core Plate DP Jo 1 Full Power Supp Pool Press 08 psig Core Flow 20 ~ lb/br x 10 8 Supp Pool Temp 9/ *F i Total Steam Flow 0 lb/br x 108 Supp Pool level JS,7 feet Total Feedwater Flow d Ib/br x 10s Main Ste Line Red Non g ,mR/hr Condenser Vacuum O inches Ng Containment Rad Level / R/br Notwell Level 19 inches Cond Stor Tank Level 24 4 feet CRD Charging Pressure 1700 pois RCIC Flow 410 spe Inst. Gas to ADS Pressure //O psig NPCI Flow 5600 spo Equip. Drain Call Tank Level J feet RHR A Flow O gym-Equip. Drain Surge Tank Level J feet RNR R Flow 0 gym Floor Drain 0011 Tank Level [ feet Core Spray A Flow O gym Floor Drain Surge Tank Level 7 feet Core Spray R Flow C spa Na Concentration C 1 RHR Ms Outlet Temp 80 *F O2 Concentration 2. A 1 RHR SW Inlet Temp 88 *F RHR C Flow O gen RHR D Flo, O gen - U a
Time /WO Moura IAS 7/25 Reactor Level /SO inches Drywell Press /,48 psis Reactor Pressure /ASO psig SGTS Flow WOO cfm Reactor Power O 1 Full Power Drywell Atmos Temp /fD *F , C re Plate DP 2 0 1 Full Power Supp Pool Press /,0 psig Care Flow 20 lb/br x 10 4 g,pp p.,g y,,, ff ey Tatal Steam Flow O lb/br x 104 3,,,p.,g g,,,g pp,7 feet Tetal Feedwater Flow O _ Ib/br x lo s Main Sta Line Rad Noa 24 mR/hr condenser Vacuum O faches Ng Containment Bad Level / R/hr Notwell Level T9 inches Cond Stor Tank Level 26. feet CRD Charging Pressure /foo psig RCIC Flow 450 spa I st. Gas to ADS Pressure //O paig NPCI Flow fd d 0 spa Equip. Drain Coll Tank Level J feet RHR A Flow o spa Equip. Drain Surge Task Level J feet RNR R Flow 0 spo Floor Drain Coll Tank Level [ feet Core Spray A Flow O spa Floor Drain Surge Tank Level 7 feet Core Spray R Flow 'd spa H2 Concentration 0 1 RHR Nm Outlet Temp 80 *F 0 2 Concentration 2.8 % RHR SW Inlet Temp 80 *F RHR C Flow A gP8 RHR D Flow A gPE U b
a V . Time IFd# Hoera
- l. LG8 7/25 Reactor Level 4 fo inches Drywell Press 2,2 psig Reactor Pressure /000 psig SGTS Flow 70ed cfm Reactor Power o 1 Full Power Drywell Atmos Temp //s2 *F Core Plate DP /f 1 Full Power Supp Pool Press /, / psis Core Flow /f Ib/hr x 108 Supp Pool Temp 97 'F T4tal Steam Flow 0 lb/br x 108 Supp Pool level 77.8 feet Tcta' Feedwater Flow o Ib/br x 10 8 Main Sta Line Rad Non F mR/hr Condenser Vacuum o inches ug Containment Rad Level / R/hr Notwell Level g_ inches Cond Stor Tank Level 28/4 feet CRD Charging Pressure /Joo psig RCIC Flow fp 2 spe I:::st. Cas to ADS Pressure //O psig NPCI Flow f4CO gym Equip. Drain 0011 Tank Level 7 feet RHR A Flow O 3pm Equip. Drain Surge Tank Level 7 feet RHP. R Flow 0 spa Floor Drain 0011 Tank Level # feet Core Spray A Flow d spo Floor Drain Surge Tank Level 7 feet Core Spray R Flow O gym M2 Concent ra t ion 0 1 RNR Ms Outlet Temp Fo *F 02 Concentration 2,8 % RHR SW Inlet Temp 86 *F RHR C Flow O spe RHR D Flow 0 gPm U'
L
m yx ,m x ' Time /'/CD Nours 3 LGS 7/25 Reactor Le ! +10 inches Drywell Press 2,Y psig Reactor Pressure 860 psig SGTS Flow Jooo efe Reactor Power d 1 Full Power Drywell Atmos Temp /68 *F Core Pla(e DP /C 1 Full Power Supp Pool Press /..'l psis Core Flow /C Ib/hr x 10e gepp p g y,,, //g y T:tal Steam Flow 0 lb/br x 108 Supp Pool Level G2,9 feet Tetal Feedwater Flow s Main Sta Line Rad Mon d [ mR/br _O lb/hr x le Condenser Vacuum O inches Ng Containment Rad Level '2. R/br Notwell Level g inches Cond Stor Tank Level 22.'/ feet CRD Charging Pressure //f0 psig RCIC Flow 670 gym Icst. Gas to ADS Pressure //O psig MPCI Flow 540 0 gym Equip. Drain Coll Tank Level 7 feet RHR A Flow /0,000 spa Equip. Drain Surge Tank Level J feet RHR R Flow /g odo gym Floor Drain Call Tank Level [ feet Core Spray A Flow 0 spa Floor Drain Surge Tank Level _I feet Core Spray B Flow 0 spa
,/ 1 Hz Concentration RHR Nm Outlet Temp f[ *F 0 2 Concentration 28 1 RHR SW Inlet Temp 90 *F RHR C Flow OPm RHR D Flow d gPm U
b
Time Id/f Neurs l IAS 7/25 Reactor Level v fd inches Brywell Press 2.8 psig Reactor Pressure ,-) fD peig SGTS Flow .~feg efe Reactor Power O 1 Full Power Drywell Atmos Temp / fB *F J Core Plate De f 1 Fsti, Power Supp Fool Press / 2 psig ~
//6 *F Core Flow 8 f _ J _ Ib/br x 18 Supp Pool;Taag -
T:tal Steam Flov , [ -d Ib/hr a 188 . Supp Pool Level I'
<re 30 feet j .
, - :, 6 Tatal Feedwater Flow O lb/hr z le s NaikhtmLineIsdMon[ d [ mR/br Conddaser Vacuue' O incb s Ng 7. ' Cents'insent Bad Level / R/hr Notwell Level inches Cod-Star Tank 14 vel 28-@ feet CRD Charging Pressure 4
~
470 spe
/Ofb psig RCIC Flotif, '
1 71 Inst. Gas to ADS Pressure //O peig NFCI Flow [" s.. (400 spa Equip. Drain Cell Tank Level 7 feet RIE A Flow Lo y gpa Equip. Drain Surge Tank Level J feet RIE R Flow pape Floor Drain Call Tank Level Y feet
/ Core Spray A Flow" O gre Floor Drain Surge Tank Level J feet _- - ' Core Spray R Flow 6 spe Na Concentration ,/ 1 Rig: Nu Outlet Temp 9[ *F 0: concentration ).8 1 Rim SW Inlet Temp 80 *F RHR C Flow Q _ spe RHR D Flow 0 spa
< b
,')
Time
/- I'7 Bouro IAS O.
7/25 Reactor Level ffo inches Drywell Press f.J psig Reactor Pressure 470 psig SGTS Flow Joe efe Reactor Power O 1 Full Power Drywell Atmos Temp 908 *F ! Core Plate DP / % Full Power Supp Pool Press /<8 pois Core Flow / lb/hr x Iga g,,,p ,g 9,,, jpg .y i l Trtal Steam Flow o Ib/br a le s g,,,p.,g g,,,g 77j g,,g s Main Ste Line Red Nom O f mR/hr Trtal Feedwater Flow O lb/hr x le ) Condenser Wcque O faches Eg Containment Red Level 4 R/br 1 Motwell Level Ji inches Coed Stor Tank Level (f./ feet CRD Charging Pressure //Ms psig RCIC Flow 454 gym Inst. Cas to ADS Pressure //0 peig NPCI Flow 56oO spe Equip. Drain Coll Tank Level 7 feet RM A Flow /oooogym Equip. Drain Surge Tank Level I feet RM R Flow Floor Drain Coll Tank Level M feet Core Spray A Flow O gym Floor Drain Surge Tank Level . 3 feet Core Spray B Flow 0 gym N2 Concentration ./ 1 R M Mx Outlet Temp 9[ *F O 2 Concentration ),8 % RM SW Inlet Temp 80 *F RHR C Flow O spe RHR D Flow 0 3Pm U t i
O O O'7/25 Time _ //'/[ 3ouro l LGS Reactor Level ffo inches Drywell Press 7 4 psig Reactor Pressure ff0 psig SGTS Flow f@ cfm Reactor Power O 1 Full Power Drywell Atmos Temp JS2 *F
- i. Care Plate DP / 1 Full Power Supp Pool Press /,f psig Care Flos ,
/ lb/hr x 10 8 Supp Pool Temp /27 *F Tetal, Steam Flow O lb/br x 10 8 Sepp Pool Level- 772 feet Tctal Feedwater Flow I O lb/hr x 108 Main Ste Line Rad Non 25 mR/hr 9
Condenser Vacuum __O inches Ng Coatsiement. Rad Level R/br i '. ~ ', ! Notwell Level J9 inches Coed Stor Tank Level 17 feet .N , , CRD Charging Pressure 7 78 psig ' 2RCIC Flow ' 4J0 spa i Icst. Gas to ADS Pressure //O psig- NPCI Flow f6do spe f. i
, t. quip. Drain 0011 Tank Level J feet RHR A Flow /0,000 spa
{ Equip. Drain Surge Tank Level 7 feet RER R Flow pape Floor Drain Coll Tank Level feet Core Spray A Flcw O spa i Floor Drain Surge Tank Level 7 feet Core Spray B Flow 6 spa Hz Concentration - ,/ 1 Rigt Nu Outlet Temp 9 'F 02Concentration % [d 1 RHR SW Inlet Temp __FO 'F
.RHR C Flow O ggen RHR D Flow O ypen d
w Time /50 Neuro l LGS 7/25 Reactor level ff0 inches Drywell Press do pois Reactor Pressure ffopsig SGTS Flow J mo cfm Reactor Power d 1 Full Power Drywell Atmos Temp 27f *F
! Care Plate DP / % Full Power Supp Pool Press /. h psig l Care Flow / lb/br u 10s 3,,,p g y,,, /pg ey lb/br x 10 4 Tctal Steam Flow O Supp Pool Level pf,J feet Tetal Feedwater Flow 0 lb/br x 104 Main Sta Line Red Non d [ mR/br j Crndenser Vacuum o inches Ng Containment Rad Level // R/br Notwell Level Jf inches Cond Stor Tank Level 15.2. feet
{ CRD Charging Pressure 9447 psig RCIC Flow 6 70 spe Inst. Gas to ADS Pressure //o peig NPCI Flow $$o pa s Equip. Drain Coll Tank Level 7 feet RIE A Flow /0,000 gpe' Equip. Drain Surge Tank Level 7 feet Rim B Flow /qtMpape Floor Drain 0011 Tank Level 9 feet Cow Spray A Flow O gym j Floor Drain Surge Tank Level 7 feet Core Spray B Flow O gym Hz Concentration ./ 1 RNR Nu Outlet Temp 96 *F O 2 Concentration ,2,81 RHR SW Inlet Temp IO 'F RHR C Flow 1 gPm RHR D Flow O gym U1 m
,y .
c\ ,s. Time 15/'[ Nours IAS 7/25 Re:ctor'LeveI. 150 inches Drywell Press f.2 ps13 Re:ctor Pressure f)O peig SGTS Flow- J000 cfm Re:ctor Power O 1 Full Power l Drywell Atmos Temp J/4 *F Cora Plate DP / 1 Full Power Supo Pool Press /,6 psig Cera Flow / lb/hr a le s 3,,,p,g y,,, . 77,7 op Tatal Steam Flow d Ib/hr x 108 Supp Pool Level 23l/ feet Tatal Feedwater Flow O lb/br x 108 Main Sta Line Rad Non Of mR/hr Condenser Vacuum 0 inches Na Containment Rad Level Ya R/br N2twell Level 79 inches Cond Stor Tank Level I3.T feet CRD Charging Pressure $ [d psig RCIC Flow 4JO ape Izet. Gas to ADS Pressure /td psig HPCI Flow 5400 gym Equip. Drain Coll Tank Level 7 feet RNR A Flow /B.0 & gpa Equip. Drain Surge Tank Level 7 feet Rim B Flow /ggmLspa Floor Drain Coll Tank Level M feet Core Spray A Flow 0 spa Floor Drain Surge Tank Level 7 feet Core Spray B Flow 0 spe H2 Concentration ./ 1 RIR Mu Outlet Temp 97 *F 0 2 Concentration 2.81 RHR SW Inlet Temp 80 *F JtHR C Flow 0 gPa RHR D Flow 0 spa U . h
O O O
~
Time 1f0 Nouro l IJi8 7/25 Reactor Level 150 inches Drywell Press /J psig Reactor Pressure # 0 peig SGTS Flow 3000 cfm Reactor Power O 1 Full Power Drywell Atmos Temp )M*F Care Plate DP / 1 Full Power Supp Pool Press /,7 psis Care Flow / ,Ib/br x 10s 3,,,p g y,,, fyg .F Total Steam Flow J_ lb/br x 10 8- Supp Fool Level Jf,f feet Tetal Feedwater Flow O lb/br x 108 Main Ste Line Rad Nom J f mR/hr Condenser Vacuum o inches Ng Containment Rad Level d4 R/hr Notwell Level 39 inches Coed Stor Tank Level 12.Y reet CRD Charging Pressure 800 psig RCIC Flow 670 spa Inst. Gas to ADS Pressure /10 psig NPCI Flow f6do spa Equip. Drain Coll Tank Level 7 feet RNR A Flow /O.dDagpa Equip. Drain Surge Tank Level 7 feet RINt R Flow g,#0gpm Floor Drain 0011 Tank Level / feet. Core Spray A Flow O apa Floor Drain Surge Tank Level 7 feet Core Spray R Flow O ape M2 Concentration ./ % RNR Mx Outlet Temp 98*F ; 0 2 Concentration 2.R 1 RNR SW Inlet Temp 80 *F RNR C Flow O s" RHR D Flow 0
. t
m ,- C Time /D/! Nours IAS 7/25 Reactor Level iS4 inches Drywell Press M,Mpsig R3 actor Pressure 4/VS psig SGTS Flow fdm cfm Reactor Power O 1 Full Power Drywell Atmos Temp 79 7 *F f Care Plate DP / 1 Full Power Supp Pool Press /,B psig
~
'Csre Flow / , Ib/br a 10 8 Supp Pool Temp /f0 *F Tstal Steam Flow O lb/br x 10 8 Supp Pool Level df./e feet Tctal Feedwater Flow O lb/br x los Main Ste Line Rad Hon 3/ mR/hr Crndenser Vacuum O inches Ng Containment Rad Level 80 R/br Hotwell Level 19 inches Cond Stor Tank Level ll.1 feet CRD Charging Pressure 7 f0 psig RCIC Flow 470 gym Inst. Gas to ADS Pressure //0 pois MPCI Flow f66C ape Equip. Drain Call Tank Level .7 feet RI0t A Flow /0@O spa Equip. Drain Surge Tank Level 3 feet RNR B Flow p ape Floor Drain Coll Tank Level / feet Core Spray A Flow 8 spa Floor Drain Surge Tank Level J feet Core Spray B Flow O gym He Concentration ./ 1 RIGt Mx Outlet Temp /80 *F 02 Concentration 28 1 RifR SW Inlet Temp h8 *F II" gHR C Flow I RHR D Flow di
l O Time / BOO Mours
' \d IAIS V-7/25 l
Reactor Level fio inches Drywell Press e/,/ psig Reactor Pressure //O pois SGTS Flow .7& cfm Reactor Power 8 % Full Power Drywell Atmos Temp 250 *F l Cere Plate DP / 1 Full Power Supp Pool Press- /,8 pois Core Flow / lb/br x lo s 3,pp p g y,,, /Jg ey l Tetal Steam Flow d Ib/br x 10 8 Supp Pool Level PZ 7 feet Tctal Feedwater Flow 0 lb/br x 10 4 Nain Sta Line Rad Non 7f mR/hr Condenser Vacuum d inches Ng Containment Red Level /40 R/hr l Notwell Level 1 inches Cond Stor Tank Level /A 2 feet CRD Charging Pressure 270 psig RCIC Flow 6 70 RPS i l last; Gas to ADS Pressure //t psig NPCI Flow ROO Spa i Equip. Drain 0011 Tank Level 7 feet RHR A Flow /0 ado gym l Equip. Drain Surge Tank Level J feet RNR R Flow /d[#0*SPe Floor Drain 0011 Tank Level feet Core Spray A Flow 8 gym
- Floor Drain Surge Tank Level 7 feet Core Spray R Flow O ape H2 Concentration ./ 1 RHR Mx Outlet Temp /80 *F 0 2 Concentration 28 % RHR SW Inlet Temp 80 *F RHR C Flow O t.Pm RHR D Flow D RP"
s Og Os U Time /6/[ Nours ( .IAS 7/25 Reactor I.evel /fd inches Drywell Press *T sig P Reactor Pressure 786 psig SGTS Flow Jacw cfm Reactor Power C 1 Full Power Drywell Atmos Temp MS *F Care Plate DP / 1 Full Power Supp Pool Press // paig Core Flow / , Ib/br x lo s 3,pp p g y,,, fyg .y Total Steam Flow d Ib/br x 10 8 Supp Pool Level 7%9 feet Total Feedwater Flow 0 lb/hr x lo s Main Stm Line Rad Mon Y mR/hr Condenser Vacuum O inches Ng Containment Rad Level 150 R/hr Hotwell Level Jf inches Cond Stor Tank Level 92 feet l CRD Charging Pressure 7b0 psig RCIC Flow 674 spa inst. Gas to ADS Pressure //d psig HPCI Flow ffdC spa Equip. Drain Coll Tank Level J feet RHR A Flow /po spa Equip. Drain Surge Tank Level f feet RHR R Flow 90 spa Floor Drain Call Tank Level Y feet Core Spray A Flow C spa Floor Drain Surge Tank Level .7 feet Core Spray B Flow B spa Hz Concentration ./ 1 RHR Ms Outlet Temp /do *F 0 2 Concentration 78 1 RHR SW Inlet Temp 80 *F RHR C Flow 1 gpm RHR D Flow OPm d < b
%) ~J' O Time /h]O Hours { LGS '7/25 Reactor Level < f0 inches Drywell Press 4 fpsig Reactor Pressure 7 70 psig SGTS Flow JOOO cfm Reactor Power d 1 Full Power Drywell Atmos Temp 2f3 'F Core Plate DP / 1 Full Power Supp Pool Press /.8 psig Core Flow / ,Ib/hr x 10e 3,pp p g y,,, fyg og Total Steam Flow d Ib/hr x 10 8 Supp Pool Level 329 feet Total Fee.dwater Flow 0 lb/hr x 10s Main Sta Line Rad Hon Jf mR/hr Condenser Vacuum O inches Hg Containment Rad Level 900 R/br llotwell Level J9 inches Cond Stor Tank Level . S.2. feet l CRD Charging Pressure 6fd psig RCIC Flow ff# gym Inst. Gas to ADS Pressure //0 psig HPCI Flow $60 0 gym Equip. Drain Coll Tank Level 7 feet RHR A Flow /o w spa Equip. Drain Surge Tank Level J7 feet RHR R Flow f40 gpa Floor Drain Coll Tank Level / feet Core Spray A Flow o spa Floor Drain Surge Tank Level 7 feet Core Spray B Flow 0 gym H2 Concentration ,/ 1 RHR Hz Outlet Temp /00 *F 0 2 Concentration 2.8 % RilR SW Inlet Temp go *F RHR C Flow O spa RHR D Flow O gps
- U b
~,
~
Time /bY),' _. ' Hours- LCS 7/25 Reactor Level efo inches Drywell Press d f psig Reactor Pressure 7)f psig SGTS Flow 7000 cfm Reactor Power o 1 Full Power Drytell Atmos Temp Jf*/ *F Care Plate DP / 1 Full Power Supp Pool Press /,7 psig Care Flow / Ib/hr x lo s g,pp p g 7,,, fyg .y Total Steam Flow o Ib/hr x 10 8 Supp Pool Level de/ feet j Total Feedwater Flow O lb/hr a lo s Nain Sta Line Red Mon 7f mR/hr Condenser Vacuum o inches Hg Containment Rad Level 700 R/hr Notwell Level T9 inches - Cond Stor Tank Level 7 2. feet CRD Charging Pressure [3[psig RCIC Flow fJo spa Inst. Gas to ADS Pressure _//O psig HPCI' Flow 560 0 spa Equip. Drain Coll Tank Level 7 feet RHR A Flow /4aan gpa Equip. Drain Surge Tank Level J feet RHR B Flow fpp gym Floor Drain Coll Tank Level / feet Core Spray A Flow C gym Floct Drain Surge Tank Level 7 feet Core Spray B Flow O ape H2 Concentration ./ % RHR'Hx Outlet Temp /00 *F 02 Concentration 08 % RHR SW Inlet Temp A *F RHR C Flow 0 gua RHR D Flow 1 gP" B2-1471200-15 U t b
Time ~799 Hourc LGS .7/25 l Reactor Level V50 inches Drywell Press 6 f pais i Reactor Pressure 700 psig SGTS Flow 7mo cfm ( R2 actor Power 6 1 Full Power Drywell' Atmos Temp _Jff *F Care Plate 1)P / % Full Power Supp Pool Press 3.0 pois Core Flow / , Ib/hr x 108 Supp Pool Temp /70 *F Total Steam Flow O lb/br a 108 Supp Pool Level _) U feet Total Feedwater Flow O lb/hr x lo s Main Sta Line Rad Non 9 f mR/br Cendenser Vacuum O inches Ng Containment Rad Level 4@o R/hr Notwell Level 79 inches Cond Stor Tank Level lo.2. feet CRD Charging Pressure [dp psig RCIC Flow 6 spa Inst. Gas to ADS Pressure //d psis HPCI Flow O spa Equip. Drain C011 Tank Level 7 feet RHR A Flow /gav spa Equip. Drain Surge Tank Level ./ feet RXR B Flow f60 spa Floor Drain Coll Tank Level / feet Core Spray A Flow h spa Floor Drain Surge Tank Level 7 feet Core Spray B Flow O gym H2 Concent ra t ion /1 RHR Hu Outlet Temp /04 'F 0 2 Concentration 2,/f 1 RIIR SW Inlet Temp 84 *F RHR C Flow M spa RHR D Flow O spa d b
~
~
-Time /7/#' 'Nours l . IAS 7/25 Reactor. Level f /)f inches Drywell Press M!psig Reactor Pres.nre 70 psig SGTS Flow 14MO cfm Reactor Power _O 1 Full Power Drywell Atmos Temp SS[ *F Care Plate DP / 1 Full Power Supp Pool Press /,7 psis Core Flow / ,Ib/br a lo s 3,,, p.,g y,,, jpg op Tctal Steam Flow d Ib/br x 10 8 Supp Pool Level 2,6' feet Total Feedwater Flow O lb/hr x 10s Main Sta Line Rad Mon 2 [ mR/hr Cendenser Vacuum C inches Ng Containment Rad Level fod R/hr llotwell Level J7 inches Cond Stor Tank Level /o.R feet CRD Cliarging Pressure 50 psig RCIC Flow 6 spe Inst. Gas to ADS Pressure //0 psig HPCI Flow 0 spa Equip. Drain Call Tank Level J feet RHR A Flow /tJmospa Equip. Drain Surge Tank Level f feet RHR R Flow foo spa Floor Drain Coll Tank Level / feet Core Spray A Flow f@d 3Pm Floor Drain Surge Tank Level J feet Core Spray B Flow 0 gpa Hz Concentration ,/ 1 RilR Mu Outlet Temp 99 'F 02 concentration J.8 % RilR SW Inlet Temp flo *F RHR C Flow fd00 gpa RHR D Flow O gPa di k .
m ,.. i L/- Hours U LGS U. 7/25 l Time _ /7?o Reactor Level f 27[ inches Drywell Press A/,/ psig , l R actor 1 ressure 5 70 pois SGTS Flow "f# # cfm R actor Power a % Full Power Drywell Atmos Temp sPf *F Core Plate DP / % Full Power Supp Pool Press /;9 psig l - 1 l Core Flow / 'Ib/br x los supp p g y,,, fp p ey i
- Tctal Steam Flow # lb/hr x lo s gapp p.,g g,y,g pga. g,,g l
() Ib/hr x lo s .7f mR/hr Total Feedwater Flow Main Stm Line Rad Hon condensetr Vacuum O inches Ng Containment Red Level (000 R/hr llotwell Level J9 inches cond Stor Tank Level 6.2 feet CRD Charging Pressure , IfB psig RCIC Flow d spa i inst. Gas to ADS Pressure //O psig HPCI Flow d spe 4 Equip. Drain Coll Tank Level 7 feet RHR A Flow yom spa
! Equip. Drain Surge Tank Level 7 feet RHR B Flow idd spa Floor Drain Coll Tank Level feet Core Spray A Flow f @ 3Pm Floor Drain Surge Tank Level 7 feet Core Spray B Flow 8 spa 112 Concentration ,/ % RHR Hx outlet Temp 99 *F 0 2 Concentration 28 % RHR SW Inlet Temp fB *F RilR C Flow ,,,$ E SPM RilR D Flow O 3Pm U
k __ - _ - - _ _ _
13 . 'p
. V -
Time /7 F Nours IAS '7/25 Reactor Level +])[ inches Drywell Press M,3 psig Reactor Pressure 70 peig SGTS Flow 7000 cfm Reactor Power O 1 Full Power Drywell Atmos Temp 33 [ *F Core Plate DP / 1 Full Power Supp Pool Press /.9 psig Core Flow / ,Ib/br u 108 Sepp Pool Temp /28 *F Total Steam Flow 0 lb/br a 10 8 Supp Pool Level 22 8 feet Total Feedwater Flow 0 lb/br a lo s Main Ste Line Bad Non M mR/hr Condenser Vacuum O inches Ng Containment Rad Level /200 R/br Motwell Level J$ inches Coad Stor Tank Level (p.2 feet CRD Charging Pressure ~ffd peig RCIC Flow 0 spe Inst. Cas to ADS Pressure //O psig NPCI Flow O apa Equip. Drain Cell Tank Level 7 feet RHR A Flow Aqa m spe Equip. Drain Surge Tank Level J feet RHR R Flow O gym Floor Drain Coll Tank Level / feet Core Spray A Flow & spe Floor Drain Surge Tank Level 7 feet Core Spray R Flow 0 gym Ma Concentration ./ 1 RHR Ms Outlet Temp N *F 02 Concentration 2, A 1 RNR SW Inlet Temp $0 *F RHR C Flow O spa RilR D Flow O gPm U
' $1
O O' O . V ' l i Time /830 Mours IJi8 '7/25 Reactor Level +72f inches Drywell Press M.G peig Reactor Pressure 70 psig SGTS Flow M cfm Reactor Power O 1 Full Power Drywell Atmos Temp J3/ *F - Core Plate DP / 1 Full Power Supp Pool Press I psig i Core Flow /
- lb/br u 148 Supp Pool Temp !)7 *F l
l Total Steam Flow d Ib/br x 104 g,,,p g g,,,g 77,g geeg ) } Total Feedwater Flow 0 lb/br a le s Main San Line Red Moe # mR/hr condenser Vacuum O inches Ng Containment Red Level #po R/hr Notwell I.evel J inches Coed Stor Tank I4vu (o.2 feet CRD Charging Pressure Jfd paig RCIC Flow 0 spe last. Gas to ADS Pressure //O psig NPCI Flow 0 spa Equip. Drain C011 Tank Level 7 feet RNR A Flew q aan spa Equip. Drain. Surge Tank Level 7 feet RNR R Flow 0 spa Floor Drain Call Tank Level / feet. Core Spray A Flow M spa , Floor Drain Surge Tank Level 7 feet Core Spray B Flow 0 som Na Concentration ,/ 1 RNR Ns Outlet Temp 77 *F 0 2 Concentration 2.$ 1 RHR SW Inlet Temp 80 *F RHR C Flow _O_. SPs RHR D Flow O SPm U
$s
rm ,m b Time /B/[ Nours l LGS 7/25 Reactor Level + 72f inches Drywell Press . _ Q psig Reactor Pressure 70 psig SGTS Flow 7600 cfm g Reactor Power O 1 Full Power Drywell Atmos Temp d2'/ *F Core Plate DP /: 1 Full Power Supp Pool Press /,f psis Core Flow / ,Ib/hr a le s 3,pp p.,g y,,, jpg ey Total Steam Flow 0. Ib/hr x 10s ( g,,,p.,g g,,,g 77,g g,,e Total Feedwater Flow 0 lb/hr x 10 8 Main 8tm Line Rad Non Jf mR/hr condense:r Wcuum o inches Ng Containment Rad Level /foO R/hr Notwell I.evel 79 inches Cond Stor Tank Level /,.3. feet CRD Charging Pressure Jfd psig RCIC Flow 0 spa last. Gas to ADS Pressure //O psig HPCI Flow 0 spa Equip. Drain 0011 Tank Level 7 feet Rim A Flow /4000 spa Equip. Drain Surge Tank Level J feet Rim R Flow 0 , gym Floor Drain Coll Tank Level / feet Core Spray A Flow 300f, spa
- Floor Drain Surge Tank Level 7 feet Core Spray R Flow 0 spa
- N2 Concentration ./ 1 ,
Rim Nm Outlet Temp 78 *F 02 Concentration 2, A 1 RHR SW Inlet Temp 80 *F RHR C Flow O gpm RHR D Flow O spa
- t
(
O . O O Time /87d Nours IAIS 7/25 Reactor Level , +]Jfinches Drywell Press . /,o pais Reactor Pressure 70 peig SGTS Flow M cfm Reactor Power O 1 Full Power Drywell Atmos Temp J2/ *F ! Core Plate DP / 1 Full Power Supp Fool Press / 9 psig
- Core Flow / ,Ib/br a 108 Supp Pool Temp I)I *F Total Steam Flow 0 lb/hr a 108 Supp Fool Level 22 8 feet Total Feedwater Flow 0 lb/br a 10 8 Main Ste Line Red Noe Jf mR/br i
Condenser Vacuum o inches Ng Containment Bad Level dopo R/br l j Motwell Level J inches cond Stor Tank Level M feet l CRD Charging Pressure Jfd psig RCIC Flow d spe Inst. Gas to ADS Pressure
//0 psig NPCI Flow 0 spe l Equip. Drain C011 Tank Level 7 feet RNR A Flow g spa Equip. Drain Surge Tank Level J feet RHR R Flow 0 sPe Floor Drain Call Tank Level / feet Core Spray A Flow 2000 spe l Floor Drain Surge Tank Level 7 feet Core Spray B Flow 0 spo Ma Concentration ./ 1 RHR Hs Gutlet Temp Yf *F i
0 2 Concentration 2. A 1 RHR SW Inlet Temp So *F RHR C Flow EP" RHR D Flow &Pm U b
Time 18 # 5eurs ' ! IAIS 7/25' Reactor Level +J2 finches Drywell Press . 7 9 psig Reactor Pressure 70 peig SGTS Flow- 742 0 cfm Beactor Power O 1 Full Feuer Drywell Atmos Temp 22/ *F Core Plate DP / 1 Full Power Supp Pool Press /,9 pais-Core Flow / lb/br a le s 3 ,, p g y , fp / ey l Total Steam Flow d Ib/br x le s Supp Pool Level 22.8 feet Tota,1 Feedwater Flow 0 lb/br x 10 8 Main Ste Line Red Non 3/ mR/br , Condenser Vacuum o inches Ng Containment Red Level F;CO R/br Notwell Level 39 inches Coed Stor Tank Level 6 2. feet ! CRD Charging Pressure Jfd psig RCIC Flow 0 SPs I l Inst. Gas to ADS Pressure //O psig NPCI Flow O SPs i
- Equip. Drain Call Tank Level J feet RMR A Flow S odo SPs -
Equip. Drain Surge Tank Level J feet Rim R Flow 0 spa Floor Drain C011 Tank Level / feet. Core Spray A Flow 2020 spa Floor Drain Surge Tank Level 7 feet Core Spray R Flow 0 spa ! Na Concentration ,/ 1 Rim Ru Outlet Temp @[ *F. Da Concentration 2 f3 1 RHR SW Inlet Temp 80 *F RilR C Flow SPs RilR D Flow SPs d b
O . O . O-Time /70 0 Boers LLSS- ~7/25 Reactor Level +7Jf iaches Drywell Press M peig Reactor Pressure 70 peig SGTS Flow' , M cfm Reactor Power O 1 Full Power Drywell Atmos Temp 28 *F Core Plate DP / 1 Full Power Supp Fool Press- 1 9 pois Core Flow / ,Ib/br s'Its g,,,p g y,,, /pg ey Total Steam Flow 0 lb/hr u 148 Supp Fool Imvel _2%8 feet Total Feedwater Flow O lb/hr a le s Main sta Line Red teen 3/ mR/hr Condenser Vacuum o inches Ng Contaianeet Bad Level 6000 R/br ,. Notwell Level Jfr inches Coed Stor Tank Level [p.A feet CRD Charging Pressure 7fd pois .RCIC Flow a som last. Gas to ADS Pressure //O psig NPCI Flow 0 spa Equip. Drain Coll Tank Level 7 feet R M A Flow q ano spa Equip. Drain Surge Tank Level 7 feet RHR 3 Flow 0 spa Floor Drain 0011 Tank Level / feet Core Spray A Flow E gym Floor Drain Surge Task Level 7 feet Core Spray R Flow a som Na Concentration ./ 1 RHR Ex Outlet Temp 7 *F 02 Concentration 2. A 1 RNR SW Inlet Temp 90 *F
. spa RHR C Flow RHR D Flow SPs d
- b
n U . G (mJ Time /O<f Beers l IAIS 7/25 Reactor Level +]2 finches Drywell Press 7,7 pois Reactor Pressure 70 peig SGTS Flow 742 0 cfm Reactor Power O 1 Fail Power Drywell Atmos Temp 200 *F Core Plate DP / 1 Full Pouer Supp Pool Press /. 8 pois Core Flow / ,Ib/hr u Igs g ,, p g y ,, /pg op f Total Steam Flow 0 lb/br x 10 8 Supp Pool Level 32 8 feet Total Feedwater Flow 0 lb/hr a le s Main sta Line Bad Noe Jf mR/br Condenser Vacuum O inches Ng Containment Red Level M R/hr ) Motwell Level 39 inches Coed Stor Tank Level (n.2- feet i CRO Charging Pressure 7fD peig RCIC Flow 0 spa s Inst. Gas to ADS Pressure //O peig MFCI Flow O spa f Egesip. Drain Cell Tank Level 7 feet RtB A Flow 4am spa ! Equip. Drain Surge Task Level J feet Rim B Flow 0 spa Floor Drain Coll Tank Level / feet Core Spray A Flow pooo spa Floor Drain Surge Tank Level 7 feet Core Spray B Flow 0 spa f i Na Concentration ./ 1 Rim Nu Outlet Temp Y/ *F 03 Concentration 2. A 1 RIR SW Inlet Temp 80 *F RHR C Flc., O SPs RilR D Flow 1 SPm U b
O O i d Time /??S _ Nour's l IAis 7/25 Reactor Level 1J_! finches Drywell' Press 7 8 peig Reactor Pressure 70 peig SdTS Flow 74t2d cfm Reactor Power O 1 Full Power Drywell Atmos Temp JS2 *F Core Plate DP / 1 Full Power Supp Pool Press /,8 pois ) Core Flow / , th/hr x 168 Supp Pool Temp //7 *F Total Steam Flow 0 th/hr x 10 8 Supp Pool Level 32 8 feet l Total Feedwater Flow 0 th/br x lo s Main Ste Line End Nom M mR/hr i Condenser Vacuum o inches Ng Containment Red Level /0,000 R/br Mofwell Inel 39 inches cond Stor Tank Level (0 2 feet CRD Charging Pressure Jfd peig RCIC Flow 0 spa Inst. Gas to ADS Pressure //O psig MpCI Flow 0 gem Equip. Drain Coll Tank Level 7 feet RHR A Flow g azo spa l Equip. Drain Surge Tank Level J feet Rim R Flow 0 gym Floor Drain 0011 Tank Level / feet Core Spray A Flow 2 PPD gym Floor Drain Surge Tank Level 7 feet Core Spray R Flow 0 spa Na Concent ration ./ 1 RHR Ms Outlet Temp 9 'F l 02 Concentration 7. A 1 RHR SW Inlet Temp 80 *F I ' .RHR C Flow O gPm l RHR D Flow O spa I 1 L * . _
nv - (^) . C' Time /7fY Nours LGS 7/25 Reactor Level +]2 finches Drywell Press 3 / peig Beactor Pressure 70 peig SGTS Flow 7@ cfm Reactor Power O 1 Full Power Drywell Atmos Temp 272 *F Core Plate DP / 1 Full Fever Supp Fool Press /,8 peig Core Flow / , th/br u 108 Supp Pool Tsep // 7 *F Total Steam Flow d th/hr u 308 Supp Pool Level .22 8 feet Total Feedwater Flow 0 lb/br a le s Main Ste Line Bad Hon M mR/br Condensgr Vacuum O inches Ng Containment Red Invel 34 W R/br Motwell Level cond Stor Tank Level 6,2 feet J$ inches CBD Charti ng Pressure Jfd psig RCIC Flow 0 spa last. Gas to ADS Pressure //O peig NPCI Flow O ape Equip. Drain Call Tank Level 7 feet RHR A Flow g ado spo Equip. Drain Surge Tank I4 vel 7 feet RNR R Flow 0 spa Floor Drain Coll Tank Level / feet Core Spray A Flow M spo Floor Drain Surge Tank Level 7 feet Core Spray B Flow 0 spa Na Concentration ./ 1 RHR Nm Outlet Temp Tk *F 03 Concentration 2. A 1 RNR SW Inlet Temp 80 *F , RHR C Flow O SPm RiiR D Finv O SPm UI - L
O O O Time d000 Nours IAIS 7/25 Reactor Level +]2f i nches Drywell Press 7.7 pois i Reactor Pressure 7 pois J0 SGTS Flow M cfm Reactor Power O 1 Full Power Drywell Atmos Temp SP / *F i Core Plate DP / 1 Full Power Supp Pool Press 1.7 pois Core Flow / , th/br a 108 'Supp Fool Temp hf *F Total Steam Flow d th/br a le s go,, y,,g g,,,g yp,g g g Total Feedwater Flow 0 lb/br a le s Main Ste Line Red Nom Jf mR/br Condenser Vacuus 0 inches Ng Containment Red Level / food R/br j Motwell Level 39 inches Coad Stor Tank level [p.S feet 1 j CRD Charging Pressure Jfd psig RCIC Flow 0 gym last. Gas to ADS Pressure //0 psig NPCI Flow 0 spa Equip. Drain 0011 Tank Level 7 feet RNR A Flow g gym Equip. Drain Surge Tank Level J feet RMR R Flow 0 spa Floor Drain 0011 Tank Level / feet Core Spray & Flow 2000 spa Floor Drain Surge Tank Level 7 feet Core Spray B Flow 0 gym Ma Concentration ./ 1 RHR Ms Outlet Temp k *F Oa Concentration 7. A 1 RHR SW Inlet Temp 80 *F RHR C Flow EPs RHR D Flow 0 SPm U
Time .Jo/I Sours 'J S '7/25 Reactor Levet +JJf inches Drywell Press 7,/ pais " Reactor Pressure 70 paig SGTS Flow 7 @ cfm
- Reactor Power O 1 Full Power Drywell Atmos Temp 32/ *F
- Core Plate DP / 1 Full Power Supp Fool Press , /, 7 psig Core Flow '
/
lb/br a le s g,,,p g y,,, ffy oy ! Total Steam Flow d Ib/br a 10 8 Supp Pool Level 32 9 feet Total Feedwater Flav 0 lb/br a le s Naia Stm Line Rad Non Sf mR/br i condensar Vacuum o inches Ms containment Red Invel /po R/br Notwell Level 79 inches Coed Stor Tsak Level 0.2 feet l CRB Charging Pressure Jfd pois RCIC Flow 0 spa ! last. Gas to ADS Pressure
//O paig WPCI Flow 0 8pm Equip. Drain C011 Tank Level 7 feet ilHR A Flow M odo spa Equip. Drain Surge Tank Level J feet RNR R Flow 0 spa Floor Drain C011 Tank Level / feet Core Spray A Flow (2000 spa l Floor Drain Surge Tank Level 7 feet Core Spray R Flov ,, O spa Na Concentration ,/ 1 RHR Ms Outlet Temp Tf 'F 02 Concentration 2,$ 1 13fR SW Inlet Temp 80 *F i RHR C Flow 1 SPm RHR D Flow 0 rpm i
1 i [ _ _ _
q rm, C ,
~
Time )oTo soura .IAS 7/25 Reactor Level +JJf inches Drywell Press 2.9 pois Reactor Pressure 70 peig SGTS Flow 7W cfm Reactor Power O 1 Full Power Drywell Atmos Temp ##d *F Core Plate DP / 1 Full Power Supp Poal Press /,7 pois Core Flow / ,Ib/br x 10 8 Supp Pool Temp // 7 *F Total Stese. Flow o Ib/br x 10 8 Supp Pool Level M.9 feet Total Feedwater Flow 0 lb/br a lo s liain Ste Line Bad Non Jf mR/hr condenser Vacuum O inches Ng Containment Red Level /B000 R/hr Notwell Level J inches Cond Stor Tank Level 4 2 feet CRD Charging Pressure 7fd peig RCIC Flow 0 spe Inst. Gas to ADS Pressure //O peig NPCI Flow 0 gym Equip. Drain 0011 Tank Level 7 feet RHR A Flow g aco gym Equip. Drain Surge Tank Level J feet RHR R Flow 0 spa Floor Drain Coll Tank Level / feet Core Spray A Flow 2Pfo gym Floor Drain Surge Tank Level 7 feet Core Spray R Flow 0 gym Ma Concentration ,/ 1 RilR Nm Outlet Temp k *F 0 2 Concentration 2. A 1 RHR SW Inlet Temp 80 *F RHR C Flow O gPa RHR D Flow O gPm d
Time 20 Boers IAS '7/25 Beactor Level +JS[ inches Drywell Press g psig Beactor Pressure 70 psig SGTS Flow . 70010 cfm Reactor Power O 1 Full Power Drywell Atmos Temp 720 *F Core Plate DP / 1 Full Power Supp Fool Press /0 paig Core fic,w / , th/br x les 3,,,y g y,,, //g ey l Total Steam Flow 0 lb/br a le8 Supp Pool Level 32 8 feet l l Total Feedwater Flav 0 - th/br a les Mais sta Line Bad Noe J f mR/hr l Condensar Vacuusi o inches Ng Coatsimment. Red Level 13mo R/hr Notwell Level g inches Coed Stor Tsak Level M feet CRD Charging Pressure ffd psig RCIC Flow 0 spa last. Gas to ADS Pressure //0 psig NPCI Flow 0 spa Equip. Drain Coll Tank Level I feet RER A Flow g aao spa squip. Drain Surge Tank Level. J feet Rim B Flow 0 gym Floor Drain Call Tank Level / feet Core Spray & Flow Jff0 spa Floor Drain Surge Tank Level 7 feet Core Spray B Flow 0 gym Na Concentration ./ 1 RIR Ex cutlet Temp 9M *F 0 2 Concentration J.S 1 RHR SW Inlet Temp 80 *F RilR C Flow 8:Pm RHR D Flow 0 Pm U
~ N ,
p - . Time d/M Boers IJis 7/25 Reactor Level +]Sfinches Bryvell Prese J.2 peig Reactor Pressure 70 pets SGTS Flow M cfm Reactor Power O 1 N'll Power- Brywell Atmos Temp 320 *F Core Plate DP / % Full Power Supp Feel Press /,6 pois Core Flow / ,Ib/br a 148 Supp Peel Temp /08 *F Total Steam Flow . O lb/br a 108 Supp Peel Level 22 8 feet Total Feedwater Flow 0 lb/br a les Male Sta I.ine Red blos #f mR/br condenser Vaciium o inches Ng Costoimaset Red Level h@ R/br Motwell I.evel Ceed Ster Teek Level lo,1 feet Jfr inches CRD Charging Pressure Jfd peig - RCIC Flow 0 spa Inst. Cas to ADS Pressure //O peig NFCI Flow 0 spa Equip. Drain Cell Tank Level 7 feet RIE A Flow Maanare Equip. Drain Surge Tank Level 7 feet RIE B Flow 0 are Floor Drain cell Tank Level / feet. Core Spray & Flev M spo Floor Drain Surge Tank Level 7 feet Core Spray B Flow 0 gym Ma concentratios ,/ 1 RIE Em Outlet Temp TJ *F 03Concentration 7. A 1 klR SW Inlet Temy A *F O SPs Ritt C Flow RHR D Flow SPs U b
O O O Time '3//[ Emers IAS - .[7/15 - s, ,
'Beactor Level 1))[ inches Drywell Prese .7..) 'peig Reactor Pressure 70 peig SGTS Flew M cfm Reactor Power , _' O 1 Full Power Drywell Atmas. Tamp 2/f *F x *, . .
Core Plate DP '
/ 1 Full Feuer Supp Peel Press /.le peig Core Flow / , th/br a les Supp Peel Temp /06 *F Total Steam Flow d th/br a 19e .g,,,y g g ,,g
.pp g_ g,,g Total Feedwater Flow 0 lb/br a Ita Main Sta I.iae Red Noe Jf mR/hr Condenser Vacuum O faches Es ,
~~
7 Containment' Red Level / g R/br [o.1 feet Notwell Level 2 inches, Coad Stor Task Level CRD Charaing Pressure 'Jfd peig'y RCIC Flew 0 spe Inst. Gas to ADS Pressure //O peig '
,> ') NPCI Flow
_ Q_ spa
~
Equip. Drain Cell Tank Level 7 feet RNE A Flow, Agnao spa
- ',f -
Equip. Drain Surge Tank I4 vel J feet .- . RM B Flow O spe Floor Drain Coll Tsak Level / feet , Core Spray A Flow 320 spe Floor Drain Surge Tank Level J feet Core Spray B Flow 0 spa Na Concentration . ,/ 1 R M Ms outlet Temp M 'F o s concentration 2.41 km SW Inlet Temp 80 *F RHR C Flow 0 SPs RHR D Flow O SPs d b c
,i o f'y f ).
(_) () Time c7 /JO Boers IAls '7/25 Beactor Level +7)[ inches Bryuell Press .7.! peig Beactor Pressure 70 peig SGTS Flow Jgag efs { Beactor l'ower O 1 Full Pouer Dryuell Atmas Temp 2 /9 *F 4 Core Plate DP / 1 Full Peuer Supp Peel Press /..Ipeig l l Core Flow / , th/hr u 148 Supp Feel Temy /aa/ *F { Total Steam Flow d th/br a 108 Sepp Peel level M feet Total Feedwater Flow O lb/br a le s Main San Line Red une 3/ mR/hr i Condenser Vacuis o inches Ng Containment and Level /B&m R/br Notwell Level 2 inches , Coad Ster Task Invel (**2 feet CBD Charging Pressure Jfd peig RCIC Flow 0 spa ] Inst. Gas to ABS Pressure //O peig NPCI Flow 0 are i Egesip. Drain Cell Tank level 7 feet RNR A Flow g spa l Equip. Drain Surge Tank Level 7 feet RM B Flow 0 are Floor Drain Cell Tank Level / feet Core Spray & Flev M som Floor Drain Surge Task Level 7 feet Core Spray B Flew 0 som Na Concentration ./ 1 R M Es Outlet Temp TJ *If Os concentration 2. A 1 RNR SW Inlet Temy A *F i RHR C Flow d- 8'" , RHR D Flow 1 Spa I i I l e . ! A;
-p p w
+
~ '
T S/V[ Emers -
~
Aa w
' .T IAIS 7/25 Reactor Level --+]2finckse BryveIIPress- .- J./pois m se v ~
Beactne Ps'e'ssure ' JO pois SGTS FlowJ v _ M cfm Beactor Power O 1FehlPower Drywell Atmos Temp ( J/8 *F A Core Plate DP . , / 7mit Power Supp Peel Press /.[ peig ' '
~
/ ;lb/hr a 108 /0 3 *F "
y -7 Core Flow Supp Peel Temy ,, Total Steam Flev 0 .lb/br a 108 Supp Peel I.evel M feet - , Tctal Feedwater Flow ' '0} lb/br a 1c8 e nair. ass Line med is T s f am/br _. Condensar Vacuusi O inches Ng Costalement dad Level /[20R/br - Hotwell Level 2 inches Coed Star' Tank Imel 6,2 feet CRD Charging Pressure Jfd pois RCIC Flow .Ah Inst. Gas to ADS Pressure
//O peig NPCI Flav 68isepe
~
Equip. Drain Cell Tank Level 7 feet RIR A Flow M ano spa Equip. Drain Surge Tank Level J feet BB B Flow \ 0 see Floor Drain Call Tank Leve! / festi Core Spr: A DA= E spa s , s floor Drain Surge Task Level 7 fdt s, Core Spray B Flow t O som.. Na concentrition . /1 1 ' g E R Ma outlet Temp 90 *F 03 ConcenUatica
- 2. A 1 RM SW Inlet Temp A *F RHR C Flow 1 See RHR D Flow 0 spo d
1 w
l Time 4900 Bours ESS '7/25 Beactor Level +J2f inches Dryuell Press h pois Reactor Pressure 70 peig SGTS Flow Jg2O_cfm'
-Reactor Power O 1 Full Power Dryuell Atasse Temp 2/8 *F Core Plate DP '/ 1 Full Power Supp Peel Press /,/ peig l
Core Flow / ,Ib/br x 148 Supp Peel Tesy /oo *F Total Steam Flow 0 lb/br a 108 Supp Peel lavel M feet i Total Feedwater Flow 0 lb/br a le s Main Ste Lies Red Men 3f mR/br Condenser Vacuusi o inches Ng Containment Red Imsel 10,000 R/hr Notwell I.evel 39 inches cond Ster Task Invel 0 2 feet i CRD Charging Pressure Jfd peig RCIC Flow 0 pa last. Cas to ADS Pressure //0 peig NPCI Flow 0 898 , Rquip. Drain Cell Tank Level 7 feet RNR A Flow Alamo spa Rquip. Drain Surge Tank Level J feet RMB B Flow 0 som l Floor Drain Cell Tank Level / feet Core Spray & Flev M spe Floor Drain Surge Tank Level 7 feet Core Spray B Flev 1 spa Ma Concentration ./ 1 RNR Ms outlet Temp _f_Q_ *F 02Concentration 7. A 1 RNR SW Inlet Temp. .90.*F RHR C Flos A I" RHR D Flow
- d
~
b ._ _
I', ( ' Q,) ) Time 29/I -Neurs IAIS 7/25 Reactor Level +]Jf inches Brywell Press g peig Reactor Pressure' 70 pois SGTS Flev M cfm Reactor Power O 1 Full Power Drywell Atmos Temp M *F Core Plate DP / 1 Fut! Peuer Supp feel Frees /./peig Core Flow. / , th/br a les g,,,y,,g y,,, fog y Total Steam Flow 0 '1b/br a 10 8 Sepp Feel Imvel M feet lb/br a 108 Jf mR/hr Total Feeduster Flow 0 Main Sta Line Bad Men Condenser Vacun O inches Na Contatement Bad, Level 920 R/br ! Notwell s.evel J inches Coad Star Tank I4 vel 6,2 feet CRD Charging Pressere 7fd psig RCIC Flew o spa last. Gas to ADS Pressure //O pois RPCI Flev 0 spa Equip. Danin Cell Tank Level 7 feet RER A Flev gao spa i Equip. Drain Surge Tank level J feet RER R Flow 0 gen Floor Drain cell Tank Leve! / feet Core Spray & Flow f. O ' : gym , Floor Drain Surge Tank Level 7 feet Core Spray B Flow )@ spa Na Concentration ./ 1 RW,Na outlet Temp d 'F f 0 concentration 7A1 RIE SW Inlet Temp #0 *F RHR C Flow - RHR D Flow U L w _____
E. s O (A i ) G J l. Time M FO 5eurs IAS 7/25 !- Beactor Level +]Jf inches Bryuell Press .,,f.:8,, pois j Reactor Pressure 70 pois SGTS Flow M cfm Reactor Power O 1 Full Power Drywell Atmos Temp _2/Z, *F i
~
i Core Plate DP ,./ 1 Full Power Supp Poel Press /./ pois l 4 Core Flow 8
/ ,'Ib/hr a 10 Supp Peel Teep /dd *F Total Steam Flow 0 lb/br a les g,,,, ,
y ,g g ,,g ggg Total Feedwater Flow 0 lb/br a les Mais sta Line Bad Nee # mR/br Condenstr Vacuum o inches Ng Containment Bad Invel % R/br f Notwell Level 2 inches Coed Ster Tank level 4 2 feet CRD Charging Pressure ~Jfd pois RCIC Flow _,_g ,_ som lest. Cas to ADS Pressure //O peig NFCI Flow 0 som Eq*ilp. Drain Cell Tank level 7 feet RIE A Flow Maassee Equip. Drain Surge Tank Level 7 feet RSR R Flow O are Floor Drain Call Task Level /! feet Core Spray A Flow d are Floor Drain Surge Tank Level 7 feet Core Spray B Flev JOOOgym Na Concentration ,/ 1 RIR Nu outlet Temp 78 *F Os Concentration '?. A 1 Ram Rf Intet Teep '
, _M *F RHR C Flow
- d SPE RHR D Flow SPs d
c
o; . o - o 4 - Time %W Beers , IAS 7/25 Reactor Level f])1 inches Brywell Press /.E'psis I Reactor"Pressere 70 pois SSTS Flow . Jg2g cfm Reactet Power O 1 Full Power Brywell Atmos Temp 2/8 *F Core Plate Rp / 1 Full i m e Supp Peel Press /,kpois Core Flow / ,Ib/br a les g,,,p,.g y,,, fog ey Total Steam Flow 0 lb/br a le8 Supp Peet Imel 22 8 feet l 3 Total Feedwater Flow 0 lb/he a le s assim see Line Red less # am/hr i l Condenser Vacuum O inches Eg Caetaiennet Red Invel 7f00 R/hr Notwell Level 2 inches M 1 feet Ceed Star Tank Inval 1 l ; CRD Charging Pressure y pois RCIC Flow , o spa t i 0 Inst. Gas to ADS Pressure A peig !WCI Flev sps a j Equip. Drain Cell Tank Level I feet RE A Flev g spa 4 j Eeuip. Drain Surge Tank Inval 7 feet BE B Flow O gym I Floor Drain Cell Tank Levnt / feet Core Spray & Flow i spa Floor Drain Surge Tank Level 7 feet Core Spray B Flow 2000 spa i 8 Na Concentration ./ 1 RIR Bu outlet Temp fB *F \ - i 0 Concentratios 3 2,81 SW Inlet Temp __ 80 *F j RHR C Flow O SP8
- i
- I ; RHR D Flow O SP*
I I l )
! U
- l. .
^
6 Time 2'IM Boests Iss ~ '7/.*5 ' Reactor level . +]Jf inches Bryuell Press le 7 peig Reactor Pressure 70_ peig SGTS Flev M cfm Reactor Power O 1 Full Feuer Brywell Atmos Temy 7/7*F Core Plate DP / 1 Full Power Supp Peet Press /,/ pois Core Flow / ,Ib/br a 188 Supp Peet T g /06 *F Total Steam Flow d Ib/br a 188 Supp Peel Is. vel 22 8 feet Total Feedwater Flow 0 lb/br x le s Main Ste Line Bad igen 3f mR/br j Condenser Vacuus O inches Ng Caetaianeet Bad Level 72'O R/br Ec.twell Level
~
; l inches Ceed Ster Tank Invel 6,2 feet CBD Charging Pressi.ee E pois RCIC Flow 0 spe Inst. Ces to ADS Pressure //O pois NCI Flow 0 som Equip. Drain Co!! Tank Level I feet RE A Flev g spa Equip. Drain Surge Task lavel 7 feet RE B Flev 1 spa Floor Drain Call Tank level / feet Core Spray A Flev dio sp Floor Drain Surge Tank Level 7 feet Core Spray B Flev 2800 spo Na Concentration ./ 1 R E Es outlet Temp M 'F f Os concentration M1 RIE SW Inlet Temp _ (0_ *F
, RHR C Flev 1 3pm But D Flow 0 sP= -
$i
_ . s - - . i s s O, , - O~' . O 1 Ti_ e 23/f- Neure l 'IAS '?/25
-Beactor Level *
'+32f inches Bryuell Press 1.7 ysig Beacto'r Pressere , 70 peig 8875 Flev M cfm
. Reactor Power 0 1 Full.Feuer Bryuell Atmas Temp M/ h *F j Core Plate DF / 1 Full Feuer Supp Peel Press M pois Core YIow / , Ah/br a 308 Supp Peel Temp /#0 *F i . Total Steam Flow d Ib/br a le s 3,,, y g g,,,g 77,g g g i
l Total Feedwater Flow 0 lb/hr a 148 Nela St Lies Red gene Jf mR/br
, Coedenser Vacuum o inches Ng' Centainment Bad Invel 4 @O R/br j Botwell Level y inches Ceed Star Tank Invel (a.d. feet
, CRB Charging Pressere E pois RCIC Flow 0 syn
! Inst. Gas to ABS Pressure //O pois RFCI Flow 0 spa l Equip. Drain Cell Tank Level 7 feet R M A Flow g a m spo j t Equip. Drain Surge Tank Invel 7 feet RW B Flow 0 ses Floor Drain Cell Tank Level / feet Core Spray & Flev 1 are 1 : i Floor Drain Surge Tsak Level 7 feet Core Spray'B Flev JMOCspe I Na concentration ./ 1 BE Ma outlet Temp 90 *F ); l, Os concentration 2. A 1 RIR SW Inlet Temp _(Q *F RHR C Flow SPe l , RHR'D Flow O SPm i i 1 i l . U b
r
~
p" _ p~. 0 .
~
)
,/
Time 56.70 Emera _ IA8 , 7/25
-Reactor Level +]2f inches Brywell Prese /,h psig Reactor Pressure 70' peig SSTE Flow ,
M cfm Reactor Power O 1 Fall Feuer Brywell Atene Temp 7/ 6, *F Core Plate DP / 1 Full Feuer Supp Feel Press / d peig t i i Core Flow / ,Ib/br x les g,,,y,,g y,,, fpg ey Total' Steam Flow 0 lb/br a le s supp Peel Level .27 8 feet , 4 l Total Feedwater Flow 0 lb/br a le* Main Ste Line Red Nea Jf mR/br I t Condenser Vacuum O inches Ng Centainment Bad Level 5foo R/br Notwell Level 2 inchen Camd Star Tank Level O feet
- I l . CRD Charging Pressure 7fd peig RCIC Flow 0 som i
Inst. Gas to ADS Pressure //0 pois NPCI Flow 0 spa i Equip. Drain Cell Tank Level 7 feet M A Flev g 3pm l Equip. Drain Surge Tank level 7 feet RIE R Flow 0 are Floor Drain Coll Tank Level / feet Core Sg. ray A Flew .D spa
! Floor Drain Surge Tank Level 7 feet Cora Spray B Flev 2000 som j 5 Na concentration ./ 1 Rm Ma Outlet Temp 1 *F C Concentration 7, A 1 R M SW Inlet Temp g *F RHR C Flow SPs RHR D Flow O SPs -
1 , l ; 1 d t
.rm .
-x
~
Tjae 374 # 5eers IAS- 7/25 , Beactor Level +]J[ inches Brywell Press M pois Reactor Pressure 70 pois SGTS Flow 7A:O cfm Reactor Power O 1 Full Power Brywell Atene Temp 7/4 *F Core Plate DP / 1 Full Power Supp Peel Press 1 7 pois
/ ,Ib/br x les [pg ey -
Core Flow g,,,y,,g y,,, Total Stems Flow 0 lb/br u le" Supp Peel Invel 22 9 feet Total Feedwater Flow 0 lb/br a le s Nela see Line Red Nea Jf mR/br j condenser Vacuum o inches Ng Ccatainment Bad Ievel g 'R/br
, Notwell f.evel 2 inches Coed Star Tank Invat 6.2 feet CRB Charging Pressure E pois RCIC Flow 0 are Inst. Gas to ABS Pressure //O psig NFCI Flow 0 spe i
l e Equip. Drain Cell Tank I4 vel 7 feet Rm A Flow Agado are } ! Equip. Drain Surge Task Invel ,, T_ feet RM B Flow 0 see i !j l Floor Drain Cell Tank Level / feet Core Spray & Flow .._ O ' spa-i ! j i, Floor Drain Surge Tank I.evel 7 feet Core Spray B Flow - 3@0:Pm l W Concentration ./ 1 RIE Nm Outlet Temp Yd*F
- i -
) l Os Concentration 2.41 RIR SW Inlet Temp 80 *F RHR C Flow O SPs Rut D riov 0:Pm -
- l 1
i ' I O : i
t [ f : J \ . v. Time 2/40 Neurs IJ38 7/25 Reactor Level +12f inches Brywell Press / [ peig Reactor Pressure 70 peig WGTS Flow M cfm Reactor Power O 1 Fall Power Brywell Atess Temp M *F Core Plate DP / 1 Full Power Supp Peet Press /.f peig
, Core Flow / lb/br a le" Supp Peel Temp A *F i Total Steam Flow 0 lb/br a 30" Supp Peel level' M feet i ! Total Feedwater Flow 0 lb/br a le s usin Ste Line Red less ;V mR/hr i Condenser Vacuum O inches Ng Containment Rad Level 55 0 R/hr i i M feet
, Notwell Level 2 inches Ceed Ster Test Level
; CRD Charging Pressure ffd peig BCIC Flow 0 Spa l:
1 Inst. Cas to ADS Pressure A ,pois - EpCI Flow 0 spa I , g, Equip. Drain Cell Tank Level 7 feet RIE A Flow Manoap= l l j { Equip. Drain Surge Tank Level 7 feet RIE B Flev 0 som
; Floor Drain Cell Tank Level / feet Core Spray & Flev 0(spa Floor Drain Surge Tank Level 7 feet Core Spray B Flow 3000 ap.
! Na Concentration ./ 1 R M Nm Outlet Temp
_ff,, *F C Concentration 2. A 1 RIE SW !alet Temp 80 *F
.RHR C Flow 898 l
RHR D Flow 0 SPs
- i i l i i
! O ,
i
p f C O . D U Time Oo(# Rours LCS 7/25 Reactor Level +]2f inches Drywell Press /.Y pois Reactor Pressere 70 psig SGTS Flow 74200 cfm Reactor Power O 1 Full Power Drywell Atmos Temp J /d *F Core Plate DP / 1 Full Power Supp Pool Press /,7 paig Core Flow / , th/hr a 108 Few Pool Temp 97 *F Total Steam Flow 0 lb/br a 148 Sepp Pool Invel "D.9 feet Total Feedwater Flow 0 Ih/br a le8 lesin ste Line Red Issa JI mR/hr condense,r Vacuum o inches Rs .Costainment Red Level (A D R/hr Rotwell Level J inches Coed Stor Tank Level [p.1 feet CRB Charging Pressere Jfd peig RCIC Flow 0 see Inst. Cas to ADS Pressure . //O pois RPCI Flow 0 see . Equip. Drain Cell Tank Level J feet RM A Flow g ano spa Equip. Drain Surge Tank Level 7 feet RM R Flow 0 See Floor Drain Cell Tank Level / feet Core Spray A Flow o gym Floor Drain Serge Task Level 7 ' feet Core Spray R Flow 2000 spa R Concentration ./ 1 Rm Ru Outlet Temp 89 *F - Os concentration 2.41 Rim SW Inlet Temp 80 *F RHR C Flow _d._. Spa RHR D Flow O SPs
- d b
O . O O Time d O E') _ _ Boers < IJi8 ' -
~7/25 .
Reactor Level +]2f inches Brywell Press /.J peig Reactor Pressure 70 psig SGTS Flav - 7 2 0 cfm i . . 'l Reactor Power O 1 Full Feuer Drywell Atmos Temp 2/f 'F ) Core Plate DP / 1 Full Power Supp Feel Press /, / peig Core Flow / , th/br a les g,,,y g y,,, ey l 4 Total Steam Flow d th/hr a 188 Supp Pool Level :12 9 feet Total Feeduater Flow 0 -th/br a les Main sta Line and lese 3/ mm/hr j condenser Vacuum O inches Ng Contafament Red Level S M R/br i i Motwell Level Jf. inches Coed Stor Tank Level 6.R feet. 1 l CRD Charging Pressure 7fd peig RCIC Flow 0 see ! Inst. Gas to ABS Fressure //0 psig NFCI Flow 0 spo , a l Equip. Drain cell Tank Level 7 feet RIE A Flow g ago gym I l Equip. Drain Surge Tank Level J feet Rim B Flow 0 som Floor Drain Cell Tank Level / feet Core Spray A Flow .O gym Floor Drain Surge Tank Level 7 feet Core Spray B Flev 2000 gym l Na Concentration ./ 1 Ram Nu Outlet Temp 88 'F ' 0 concentration 2.fj % Rim SW Inlet Temp 80 'F RHR C Flow i RIIR D Flow d see - l l 1 i
- O
\ .
-Time 00 6 seurs IAis '7/25 Seactor Level +]jfinches Bryuell Press /,/ peig Beector Pressure 70 pois SGTS Flow 743010 cfm ,
Beactor Power O 1 Fall Power Dryuell Atees Temp 2/J1 *F Core Place DP / 1 Fall Power Supp Peel Press /,0 pois core Flow / ,Ib/br a les g ,, y g y,,, 9/, og Total Steam Flow d Ib/br a 108 Sepp Peel Invel 27 9 feet Total Feedwater Flow 0 lb/hr a 14 8 Nele Ste Line Red Blas j f mR/br Ceedesser Vacuum O inches Eg Centalement Rad Level .f N R/hr ! Ilotwell Level 2 inches Coed Stor Tank Invel 4,2 feet CBD Charging Pressure Jfd pois RClc Flow 0 som Inst. Gas to ADS Pressure //O yela NFCI Flow 0 gym Equip. Drain cell Tank Level 7 feet RM A Flow M ado spa Egesip. Drain Surge Teek Level 7 feet RM B Flow 0 gym Floor Drain Cell Tank Level / feet Core Spray A Flow t O gym Floor Drain Surse Task Level 7 feet Core Spray B Flow 2000 spe Na Concentration ,/ % R M Nu Outlet Temp 9'[# *F On concentration 28 1 RM SW Inlet Temp 80 *F RHR C Flow -- EM RHR D Flow IN - d b
. O O O 313'Rev'<oawt ' CRITICAL PLANT VRRI ABLES 'catat so a *S '
DRVWELL
' Rpy I SRU I i SHHf l 1
CONTRIHMENT 4SRU LIFTI L130 D = U PRESSI /oso IPSIG 0=b l ohg) l (100*.BPU
/ 990 )
I GROUP l l No rtw I 4 TRIP HI 54 D . 4 OPER il 2.0 D LEVELI tJrEIN PRESSI o.6 IPSIG (SCRAM LO 12.5D
, 40PER HIl150D TEMPI IJo I'F POWERI/oo I%
_ _ _ 4APRM DHSCL 4D _ _ _ i (OPER HI 24- 3 D m LUL DJ FT / IH M # h w sA A_ 4 OPER HI ra v a A m 95 D l 40PER L0122- OD SUPPRESSIDH POOL i TEMP [E 'F ei ii i LIMERICK 0 8 8 25-JUL 198V //:00 300 FORMAT N0.3 ( ) Y
; w
I l lE 0
" *n f/
P UL W 0 1 o m. e s O #e hO O RB Gs M I I T l ' lE 4 M T AD 5 Fi 8 9 H ' 1 _ C E ' a 9 I i L U v l 0 i J a I H 9 F
\ n, i 2 lP A R
. E e 0 P M O E 0
' A T i S s4 0 E K m-EI C L I R
B Ur E M A Ru SH =
- [$ u I
L h I s ,> R II 0 A DG I ) D D D L O V 0 3 S 9 0 4 5 N I 5 5 4 O P 1 P 9 I 2 l 1 1 o L N T r o O o C M E O l I l 1 U 1 0 / S N y p T F o P B I H
+ L E
N D A R" C o I S S A R I L s P I L M A R. E M SN E R L U R S S 0'4 I R E V R C W O R P P P P S E R 1 0 T - E L S P A U 4P ( 4 ( 4 S L U A L
>)
C L E g D T I W S M V P 0 T R D 5 1 I c I . l i 3 R DN D 6l H s I I 3 0 C S R E P - - S P M 4
/
2 I O E E 2 2 4 R P (T l I T F 1 0 7 T N H L
)
#s E R 3
R o M E 3 E H N I P O L P O ( A 'i U U T (L 4 P N : R O . O 0 m, C H I T 3 A M tb 1 R O 3 F i :i i! : . ! [
O O O 313 I RPU No#mpt ICRITICAL PLANT VARIABLES 'catar --e i DRYWELL RPy I SRU E E 5//r I
; CONTRIHMENT SRU LIFT 1130 D ::
b (PRESSI /000EPSIG O:M l N/ l ( 100'4BPU 990 )
. I GROUP E lNo BLW l 4 TRIP HI 54 D .
40PER HI 2. 0 D LEVELI o r IIH [ PRESS PSig (SCRAM LO 12. 5 D (OPER HI 150 D TEMPI 17o I'F POWERI /oo I'4 q 4 APRM DNSCLI 4 D _ _ __ i (OPER HIl24- 3D SCRRM u_A A.A LUL x FT / IN M Ne^'E ! W A;u sAjuvvaA-4 OPER HIl 95 D l (OPER LO 22- DD TEMP [9'aI'F SUPPRESSION POOL i i ie i LIMERICK 0 0 0 25-JUL 1984 /z:00: 00 FORMRT NO.: ( ) O
. O O O 313'aru"oe"'et ' CRITICAL PLANT UARIRBLES scatar "o -<z '
W WELL RPV E SRU E l Sour l j CONTAINHENT SRU LIFT 1130D = i t U (PRESSI /o>oIPSIG U=M ' lo
/
l ( 100'4 BPUl 990 ) GROUP l l No EY2Nl E i l 4 TRIP HI 54 D . I (OPER II 2.0 D LEVELI #ffEIH 6 PSlg (SCRAM L0112.5 D f! PRESS i-li - - . . . . . , , . . TEMP 'F POWERE/oo I'4 l _ _ __.
, 4 APRM DNSCL 4D ,
) ) - -
,i (OPER HIl24- 3D SCRAM ll m LUL M FT / IN ##"* l h .A.A.; J A Aavv a AA A.A.sv (OPER LO 22- OD 4 OPER HIl 95 D 1 i - - TEMP [ 90 I 'F SUPPRESSION POOL i ii ie i LIMERICK 0 0 0 2F-JUL 1984 /?:30: 00 FORMRT N0.3 ( ) d ( .$ 1 -
O O O ECHTMT Nopp/4R 313 ' Rev "oemo CR1TICAL PLANT UARIRBLES DRVUELL
; RPV IE 5##
SRV l E ,i. CONTAIHMENT SRV LIFT .130 D .. E (PRESSI /esoIPSIG 0 l Mjv l 1 (100% BPV 990 ) I . GROUP lE Worss# El 4 TRIP HIl 54 D . l, 4 OPER il 2.0 D LEVELBeyrIIN
', PRESSI 0.& RPSIG 4 SCRAM L0ll2.5 D 40PER HI 150 D
! TEMPI /ro 5 'F POWERI /oo I% ___. _ _ 4RPRM DNSCLI 4D _ _ _ ii (OPER HI 24- 3 D e LUL @ FT / IN M oN h w uovarm 4 OPER HIl 95 D ll (OPER L0122- O D i T TEMP [ 40 I'F SUPPRESSION POOL i i i i i i 88 - 9 800 FORMRT HO. ( ) t
,[ b u . _ _ _ _ _ _
O O 0 313 i "P" "e">
' CRITICAL PLANT UARI ABLES s catar x'--een DRWELL Rpy Su jg l CONTAINMENT 4SRU LIFT .130D =
E PRESSI //aoIPSIG 0=h lgh[ l !: ( 100% BPV 990 )
. GROUP Worsts /l l l 4 TRIP HI 54 D .
! (OPER HI 2. 0 D LEVELE o IIH !I PRESS E o.6 EPSIG (SCRAM L0il2.5D l' I-(OPER HIl150D l TEMPI /7e I T POWERE 6 D l __ _ _ ( APRM DHSCL 4D _ _ _ , i (OPER HI 24- 3 D e LUL on FT 2 IN M # Al h A_A.s s A pay a a A.- 4 OPER HI 95 D 4 (OPER L0122- O D
-- TEMP [90I'F SUPPRESSION POOL i ii ii i LIMERICK 0 0 0 2F-JUL 1984 /s/s+100 FORMRT HO.2 ( )
d I
L O O O 313 ' aru *"- ' CRITICAL PLANT VARIRBLES s catar "o+ > i DRVWELL RPU I SRV 1 l DPM E CONTAIHMEH1 4SRU LIFT 1130 D = E PRESS PSIG O=k l[f)fl l: ( 100'4 BPV l 990 ) l - GROUP I l NorSu/ E l 4 TRIP HIl 54 D . l 40PER ill2.0 D LEVEL E - +'o E IN I! PRESS I o.B E PSIG 4 SCRAM L0ll2.5D (OPER HI 150 D TEMPI no E'F POWERI O I'4 _ _ _ 4APRM DNSCL 4D _ __ _ i (OPER HIl24- 3D u _A A A LUL 33 FT IN M #5 # h w sA 4 OPER HI A. s v a rm 95 D l (OPER L0122- O D
-- TEMP [F//E 'F SUPPRESSIDH POOL i ei ii i FORMRT N0.: ( )
d [ h
o o o V o V 313iaeu- e '3RITICAL PLANT UARIABLES 'cata'* o" i
; RPV l ,SJV l CONTRIHMENT 4SRV LIFT 1130 D =
!;' E 0=$k PRESSI sarIPSIG l 5 ah l l-
\ '
(100% BPU 990 ) I GROUP I lMorsw l 4 TRIP HIl 54 D . ! (OPER il 2. 0 D LEVELI tro IIH I! PRESS I /./ IPSlg 4 SCRAM LO 12. 5 D !' 40PER Hil150D TEMPI /# I 'F POWERI O I% l _ _ _ 4 APRM DNSCL 4D _ _ , _ _ li (OPER HI 24- 3 D SCRRM e LUL sa FT IN VM A#5 Ed l h _A A.s s A A Asa a A-l' I (OPER LO 22- OD 4 OPER HI 95 D SUPPRESSIDH POOL
- - TEMP [M 'F i i ii i
! LIMERICK 8 8 8 2F-JUL 1984 /3:25': 00 l FORMRT NO.: ( ) Y
. O O O 313 I RPU 4/44/1 iCRITICAL PLANT VRRIRBLES ICHTMT A N I DRWER ppg
- l l j CONTRIHMENT ( SRV LIFT ,130D =
U PRESSI /es IPSIG 0=M l
- ( 100'./ BPV 990 )
\ ' ' l' 5
. GROUP l lE TSM/
l i l 4 TRIP HI 54 D . l (OPER HI 2. 0 D LEVELI so IIH l PRESSI/6e IPSig (SCRAM LO 12.5D , ( OPER HIl150 D l TEMPI /ro I 'F POWERI o I'4
, 4 RPRM DNSCL 4D ,
i
) ) - --- - >i (OPER HI 24- 3 D j- e LUL 23 FT IN M h _A.As s ._ A A_ r u v a Am 4 OPER HI 95 D i! 4OPER LO 22- 0D TEMP [97 I 'F
) SUPPRESSION POOL i e i i j LIMERICK 0 0 0 2F-JUL 198413:30800
- FORMAT N0.3 ( )
; ?
O O O 313 I RPV A/##1 I CRITICAL PLANT VARI ABLES 'cH'aT * " - ' DRYWELL "Pu !> I J"# 1 i CONTAINHENT SRU LIFT .130 D = !' , b (P R E S S 0=M I /co o I P S 1 6 l ShuY l l-( 100'4 BPU 990 )
. GROUP l TSNb E
l E l 4 TRIP HI 54 D .
! 40PER il 2. 0 D LEVELI fro IIH PRESSI a.2 IPSIG 4SCRRM L0112.5D -
(OPER HI .50 D TErlPI /6 3 4 'F POWERI o I% 4APRM DNSCL 4D _ _ _ i 4OPER HI 24- 3 D SCRRM N LUL 33 FT /o IN M A##5J# l h .A.>U s ._A_ A>v 4 OPER HI v a A.- 95 D
! 4OPER LO 22- 0 D TEMP [ 97 I 'F SUPPRESSION POOL ii ii i LIMERICK 0 0 0 25-JUL 1984 's.-n 00 FORMRT N0.: ( )
t' . ( h
O O O 313iaevet "'
' CRITICAL PLANT VARIRBLES ECHTMTA m I ER RPy I SRU I
]' E CPEd I !- CONTRIHMENT SRV LIFT 1130 D !! E (PRESSI e60 U=[=k EPSIG l Sp ! ( 100'./ BPU l 990 )
\ '
l l GROUP E r<t.W l E 4 TRIP HI 54 D . 4 OPER 4I12.0 D LEVELI +ro IIN lI PRESS I M IPSlg 4 SCRAM LO 12.5D 40PER Hil150D TEMP //> 'F POWERI o I% - l , 4 APRM DHSCL 4D , _ __ _ k
) 5 _ __ _
i (OPER Hil24- 3D SCRAM l- e LUL 33 FT / IN M ##85 "' h AAs J A A.AJ u a Am 4 OPER HI )I
! 4OPER LO 22- 0D 95 D 1
TEMPI //o I'F SUPPRESSION POOL i a ie i LIMERICK 0 0 0 af-JUL 1984 /4:00: 00 FORMAT NO.: ( ) d j' k
. O O O 313 I RPU ABBa?
ICRITICAL PLANT VARIABLES ' cMtMr e~"' DRYWELL
. Rpy SRU l O PE N E
lE j CONTAIHMENT SRU LIFT 1130D -
=
i.
' E (PRESSE 750 0 hEPSIG '
l 5))N l q: (100% BPUl 990 ) iI it ; lB GROUP
,75NL I
E J
- 4 TRIP HIl 54 D ,
! 4OPER il12.0 D LEVELE <ro IIN jl. PRESSE 26 EPSIG 4 SCRAM LO 12.5& ] i*
'i
; (OPER Hil150D TEHFR /9o E 'F POWERI o 5%
l , 4 APRM DNSCL 4> , l
) ) _
fi (OPER HIl24- 3D M LUL 93 FT 0 IH & R N
& w supuunm 4 OPER HI 95 D ij (OPER LO 22- 0D TEMP [//4 I'F SUPPRESSION POOL i ei ie i IM S 8 8 2 - UL 1984 /C /5: 00 FORMAT HO. ( )
I Y S { _ _ _ _ _ -
O O O-313 I RPU #z#"" ' CRITICAL PLAHT UARI ABLES 'catara a'"' DRY 9 ELL Rpy l EOFM' SRV l E CONTRIHMENT SRV LIFT .130 D = E (PRESSI 67o U ::bIPSIG l5 l 11 ( 100% BPV 1 990 ) it , I GROUP l B T5e# I 4 TRIP HIl 54 D . 40FER 1 2.0 D LEVELI eso IIN .
! PRESSI IJ IPSig (SCRAM L0112.5 5 40PER Hil150D TEMPI sos I'F POWERI O I%
_ _ _ 4 RPRM DHSCLI 4 D _ _ _ i (OPER HI 24- 3 D RAM e LUL 91 FT / IN M #85 J# h A.> U s A A./v v 4 OPER HI a A^_A.Asu 95 D (OPER L0122- 0 D TEMPI /00 E 'F SUPPRESSIDH POOL i ii ii i LIMERICK 0 0 0 2F-JUL 1984 /4:30: 00 FORMRT H0.3 ( ) M . .
' E l l q ui qqpllui. 4 E' luilE u
- 15 O O O 313 I RPU pus ' CRITICAL PLANT VARIABLES ICHTNT M ##/r> I DRWER RPy I SRU R I OPM I CONTRIHMENT 4SRU LIFT 1130 D -
b PRESSI co IPSIG U ::M l$h l ( 100% BPUl 990 ) i t it :
. ms . ..
I "W I
,7- 4 TRIP-HI 54 D 40PER HI 2.8 D LEVELI +5o IIH,. .
i
' PRESS I 7.6 IPSIG (SCRAM LO 12.5) -
{ (OPER Hil150D TEMP I 229 I 'F POWERI o I'4
, 4 APRM DHSCL 4D ,
) ) - - -
i (OPER HI: 24- 3 D SCRAM m LUL 27 FT 3 IN M #M N l h .A A.; s._AA 4 OPER HI o o a Awm 95 D l (OPER LO 22- OD TEMPI /23 I 'F SUPPRESSION POOL i i i i i i LIMERICK 0 0 0 2F-JUL 1984/4dec :00 FORMRT NO.: ( ) M E . ..
' l 1 0 0
8 h 5 c O aa" m. o he S 2 4 S t : 1 a t AD 5 Fi 8 9 a 9 ' 1 c t A I L
' i U J l 6 i J JP I 2
/
H 5
. I 2 A R P
. E e 0 P M t E 0 i
A. O
. T i S J4 0 K
E l J C L /.. I R E B - A. - M Ug, R )S I L I =[$
=
,)
R l U A DG ) D D D L O V 0 3 I S 0 9 4 5 N I 5 I 4 O P 1 P 9 I 2 I OTN I 1 L N 1 o 1 o C M N O AT l I l T o U r 0 S I U P F s P B I H
+ L I
N D R CW S S A R I L I P E L M A R E M S W E
.R L U R
S S 0'/. I R E V R C W O R P P P P S E R 1 0 T E L S P R U S 4P ( 4 4 4 L E A ,) C R E pI G DF I S T I R D 0 2 l I H P I e o 0 ' 5 1 l I H I rr I a DH 3 I D O C R E I S R E P - - P S P M
' 0 E O E 4 2 2
2 4R P (T l I T F 1 0 T H L N e" E R 1 R
)
u N E 2 E e N P P I L O O ( A U v T (L ( e - H 3 O 'R 0 C 0 N T 3 1 3 M R M R O F e
. ' , i l
~ : j! , -
5
. O O O ,
i 313 I RPU nz##m ECRITICAL PLANT VARIRBLES scatar - -" i ; l DRYWELL
- RPU I SRU I l OPEH l
.; CONTAINNENT (SRU LicT 1130 D u E
PRESSI Sao IPSIG Ub l5 l ( 100'4 BPUI 990 ) i $t ? 1
- GROUP I rux I 4 TRIP HII 54 D .
l 6 LEVEL E #so E IH PRESSI & IPSIG (SCRAM LO ' 12. 5 ) f V J , A. 4 OPER HI A AJ u a Am 95 D t { (OPER L0122- OD ' TEMPI go I'F SUPPRESSION POOL i ii i i , LIMERICK 0 0 0 25-JUL 1984 /5:47:: 00 FORMRT H0.: ( ) Y j U
O O . O 313 I RPU 44##m ' CRITICAL PLANT VARIABLES ECHTMT #eBen I
, RPU l ,Sgug l j CONTAINHENT SRV LIFT 1130 D = ! E (PRESSI v/o 0=h IPSIG l fhr ^
( 100'4 BPV) 990 ) iI iI : l RW l 4 TRIP HI 54 D . 40PER 4112.0 D LEVELE <so EIN [ PRESSI & IPSlg SSCRRM L0112.5D 40PER Hil150D TEMPI pro I 'F POWERI o I'4 4 RPRM DNSCL 4D q ._, _ _ i (OPER HI 24- 3 D e LVL 93 FT (OPER L0122- O D IN M #*SCRRM r"l W ws , A. 4 OPER HI A A .; o a A-95 D TEMPI /Sc I'F SUPPRESSION POOL i i i i i i LIMERICK t t 4 25-JUL 1984 16:ot: 00 FORMRT N0.8 ( ) M [ b
O O O 313 I RPU B44#tn I C R I T 1 C A L PLANT VARIABLES scutar ~ ~on DRVWELL-CONTAIHMENT - E 4SRV LIFT 1130D)0 )::- l $hr l PRESS PSIG
- ( 100% BPVl 990 )
. I GROUP I I ZSJN' J
~
{TRIPHI 54 D .
! (0PER il 12.0 D LEVELI +ro IIN f PRESSI v.I IPS!g 4 SCRAM LO 12. $)
i! SOPER HII:.50 D TEMPI cra I'F POWERI o I% 4RPRM DNSCL 4D _ (, , li (OPER HI 24- 3 D e LUL 7 FT /0 IN (OPER LO 22- OD M SCRAM
! #005 2 " ! W .A A > s A A m.;o a A-4 OPER HI 45 D
TEMPI /70 I 'F SUPPRESSION POOL i i ii i i LIMERICK 8 0 0 25-JUL 1984 /c, M 00 FORMRT N0.? (
)
d
? N 1
O O O I 3 1 3 I RPU 4t##m ' CRITICAL PLANT VRRI ABLES ECHTNT r9udm I DRWELL
.. Rpy E SRU E l OPEd I CONTAINHENT 4SRV LIFT 130 D u i
E PRESSI rro IPS16 0h !5 l ): ( 100% BPU 990 ) - It it
. I GROUP I l XSLN l 4 TRIP HIl 54 D .
4OPER HIl2.0D LEVELI cro IIN , ,' PRESS .5 PSIG 4SCRAML0l1?g l.
! (OPER HII:.50 D TEMPI art I T POWERI o I%
4APRM DNSCL 4D e i (OPER HI 24- 3 D
- m LUL 73 FT / IN M # N h us uway 4 OPER HI li (OPER L0l22- O D' 95 D TEMP I iJo IT i SUPPRESSIDH POOL i i i i i IM 8 8 8 25- L 1984 /6
- 00 FORMRT N0.2 ( ) ,
Y
, a i
qb pJ o
, V 1
313 E RPU 4t##in I C R I T I C A L P L A N T V A R I A B L E S 'cstat e' '"J SR RPV l gg,U l g i CONTRIHMENT SRU LIFT 1130 D = E (PRESSE raf U ::MEPSIG l ha) l ' ,- ( 100% BPVl 990 ) i' 1I
\
. GROUP IStN li l 4 TRIP HIl 54 D .
! 4 OPER il12.0 D LEVELE*so IIN .! PRESSI v. RIP 318 4 SCRAM L0l12.5 D (OPER HI 150 D 3 TEMPI u v i'F POWER L o I'4
- l _ _
. ( RPRM DHSCL 4D ,
i _ _ _
\ \ _ __ _
l 40PER HI 24- 3 D j e LUL ov FT o IN M de N Q w nwgu 4 OPER HI 95 D
- l 4OPER LO 22- 0D i' - -
TEMPI /70 I 'F SUPPRESSIGH POOL i i i i i i l l LIMERICK 0 0 0 2F-JUL 1984 /6:45: 00 i FORMRT NO. ( ) u ![ b
. O O O 313 I RPU AMm ECRITICAL PLANT VARIABLES ECHTMT &Mn I I
DRVUELL S
; RPV l gg l CONTRIHMENT SRV LIFT 130 D =
U (PRESS o PSIG U=b su ( 100'./ k PU l 990 ) iI i? 1
. I GROUP I wx 4 TRIP HIl 54 D .
4 OPER il 12.0 D LEVELI +so EIH lI I , s PRESSI 4 /IPSIG 4 SCRAM LO 12.5D 1: 40PER HILL 50D i TEMPI a55 I 'F POWERI o I% ,
, (RPRM DHSCL 4D ,
) )
1 . i 40PER HI 24- 3 D m LUL o FT IH M P # h w suwum , ll 4 OPER HI 95 D i 4OPER LO 22- 0D TEMPE no E'F i SUPPRESSIDH POOL ii ii i LIMERICK 0 0 8 25-JUL 198417:00: 00 FORMRT N0.: ( )
O O O 313 ' Rev *ee" ' CRITICAL PLANT VARI ABLES
' carat *-a i ; RPV l ,SRg g l j CONTAINHENT 4SRU LIFT 1130D =
'! U PRESSI Jo IPSIG O=b l5y l l- ( 100'4 BPU 990 ) N 4 : l %W l l 4 TRIP HI 54 D . l (OPER il 2.0 D LEVEL I +i>I I IH .j PRESG PS!g 4 SCRAM LO 12.5& 40PER HIl150D TEMPI I'F POWERI o I'4 q 4RPRM DNSCLI 4 D _ _ ii (OPER HI l24- 3 D l il m LUL FT IN M ^' Q w n(warm
- j 4OPER L0122- 0D 4 OPER HI 95 D TEMPI l>9 I'F -
l
- SUPPRESS 10H POOL i ii i i l
888 - 984 mis :00 FORMRT N0.: ( ) lJ 0 jf .S
O O O 313 ' Reu e<ee- ' CRITICAL PLANT VARIRBLES ICHTMT AMMI DRYWELL CONTAINHENT RPV (SRV LIFT
\l gg l 11300)0 U PRESSI Jo IPSIG
\
ls y l
- CiBO% BPV 990 ) i! it :
! I aso& I ! 4 TRIP HI 54 D . , (OPER :il 2. 0 D levelly >7eI IH '! PRESSI # IPSlg 4 SCRAM LO 12 @ (OPER HIl150D i TEMPlast I 'F POWERI O I'4
, ( APRM DHSCL 4D ,
_ _ _ \ \ . _ _ _ _ (OPER HI 24- 3 D J e LVL 7 FT a IN (OPER L0122- O D M q, N! W .A>v s a A m.c u a 4 OPER HI 95 D x.- l _ TEMP I /a9 I 'F SUPPRESS 10H POOL i i i i i LIMERICK 8 0 0 25-JUL 1984 /7 w>: 00 FORMAT NO.: ( ) d I
O O O
^
313 i aru nee'- i CRITICAL PLANT VARI ABLES
.. c scatat a " -> i DRVUELL r ppy SRV E l opsa l
; CONTAINHEHT SRV LIFT 1130 D =
! E (PRESSE ro O=M IPSIG l feds l I- ( 100'/. BPV l 990 ) N it l
. E GROUP I l TS M I 4 TRIP HII 54 D (OPER HI 2. 0 D LEVELI mrIIH i! PRESSE7.3 IPSIG 4 SCRAM LO 12. 5 D j (OPER HI 150 D
!. TEMPI.225 I'F POWERI o j4' !I . 4 APRM DNSCL 4D ,
\
) ) D : :
- (OPER HI 24- 3 D SCRR M
m LUL x FT /0 IN #12' I h _A A.s s A.A.A.; u 4 OPER HI a A-4OPER LOI22- 0D 95 D i -- TEMP I /0# l 'F SUPPRESSIDH POOL i ii i F i LIMERICK 8 8 8 2F-JUL 1984 7::4T,00 FORMRT NO.: ( ) O r b 1 /
O O O 313 I RPU Be#An I CRITICAL PLANT VARI ABLES ECHTMT M # # I DR WELL Rpy SRU l l C/TN E g
- CONTAINMENT 4SRV LIFT 1130 D
- :
' E PRESSE To EPSIG U ::M l SfdN l - \
( 100'4 BPUI 990 ) ii tt : l RoF ] 4 TRIP HI 54 D . 4OPER il 2.0$ LEVELI nerIIN PRESSI da EPSlg [ 4 SCRAM L0112.5 D' 40PER HI 150 D TEMPl as/I T POWERI o I'4
! _ _ _ (APRM DNSCL 4D _ _ _
l (OPER HI 24- 3 D m LUL as FT /o IH M #2 < ' Q w ugwy 4 OPER HI [ (OPER LO 22- O D 95 D I TEMPR v 7 I'F l SUPPRESSION POOL i i i i i LIMERICK 0 0 0 25-JUL 1984 ar xt00 FORMRT HO.: ( ) L' N i
. O O O 313IRPVBl4W' ICRITICAL PLANT VARIRBLES 'catar a - '
RPV l ,SRg l
; CONTRIHMENT 4SRV LIFT 1130 D U ! PRESSI 70 EPSIG 0 =M l 5)hb l
( 100'4 BPU 990 ) II it : l RM l 4 TRIP HI 54 D . 4OPER HI 2.0 D LEVELI nerIIH i
!. PRESSI v.2 IPSlg (SCRAM LO 12. 5 D 40PER Hil150D TEMPI v>vl T POWERI d I'4 l _ _ 4RPRM DHSCLI 4 D _ _
(OPER HI 24- 3 D M LUL 0 FT to IH & & .AJJJ A A. M 4 OPER HI J A A.AM 95 D f (OPER LO 22- O D TEMPI />b I'F SUPPRESSIDH POOL i ii ii i LIMERICK 8 8 0 25-JUL 1984 /X /r :00 FORMRT HO.2 ( ) d r h J .
. O O O 313IRPUeu/cra- ICRITICAL PLANT UARIABLES %
' c" Tat =" '
; RPU -l g/fj SV l
j CONTAINMENT SRV LIFT 130 D u
U (PRESSI roUIPSIG M l feu$ l i: ( 100% BPV 990 ) if it i . GROUP l rud E
! 4 TRIP HI 54 D . 40PER'4112 6D , LEVEL na IN )f PRESS I i'.0 IPSlg 4 SCRAM LO 12.5D l! (OPER Hil150D
- l. -
TEMPI 3 W I'F POWERI O I% l! . (RPRM DHSCLI 4D , _ _ _ x, s, _ _ _ li (OPER HI 24- 3 D SCRAM l- m LUL x FT /0 IN M M'* J^' h .A.A.u A A_ 4 OPER HI o va A. - 95 D lI (OPER L0122- O D lI TEMPI /af I'F SUPPRESSION POOL i i ii i LIMERICK 0 0 0 25-JUL 1984 a:3c: 00 FORMRT N0.: ( ) M
? $
i
O O O 313.ERPV#2Me" ' CRITICAL PLANT UARI ABLES ECHTMT #z# h >E DRVWELL
. Rpy I SRU E ' l oput l ; CONTAIHMENT (SRV LIFT 1130 D =
E PRESSI ro IPSIG U=b ls)r ( 100'4 BPV 990) if It
. I GROUP I E .TSAN I 4 TRIP HII 54 D .
4OPER HI 2. O D LEVELI +nrI IN . PRESSE 5.! EPSlg (SCRAM LO 12.5D [ 40PER HIl150D TEMPI x v I'F POWERI o I P. l 4 RPRM DHSCL 4D _ _ __ i (OPER HI 24- 3 D SCRAM m LUL as FT IH & W" M l & .A ?J J A A. A.) a 4 OPER HIl s Am 95 D
! (OPER L0122- DD I
TEMPI iW I'F SUPPRESSION POOL i ii ii i LIMERICK 0 0 0 2F-JUL 1984 /20J 100 FORNRT NO.: ( ) 0
? $
1 _. --
1 O O O ! 313 I RPV move ICRITICAL T PLANT VARIABLES 'cataua" ' DRVWELL i '. RPV E SRU I l OPEN l
; CONTRIHMENT G SRU LIFT 1130 D l
' U PRESSI To IPSIG U:[f l 5 uh !
- ( 100% BPUl 990 ) id it
. I GROUP E I rs w I 4 TRIP HI 54 D 4OPER HI 2. 8 D LEVELImr IIN
- 4 SCRAM LO 12.5 D PRESSI 79 IPSIG f 40PER Hil150D l .
TEMP I 33J I 'F POWERI o I% l _ _ _ 4 APRM DHSCLI 4D _ _ _ l (OPER HIl24- 3D SCRAM m LVL as FT /0 IN M #Mf^/l h _A.A.J J A A A.J u a A A A.A AJ
! (OPER L0l22- DD 4 OPER HI 95 D I
TEMPI /32 I'F SUPPRESSION POOL i i i i LIMERICK 0 8 0 2r-JUL 198419: 00: 00 FORMAT NO.: ( ) o Y '
- j ?.
I l II
- r P UN O W W
h OL RS GT T M T 5 Fi H C I t i uD 9 I i o l 0 i I 3/
~
H
\
d w R E P Ii P M E O T S i n4 i E L B U ,g m A I R A
)S ,
l
=3
=
0
,)
DG ) D D D L O V 0 3 I S 0 9 4 5 N I 5 I 4 O P P T l l E 9 42 2 1 o I L C N O O i l l l T 0 U 7 0 S I N U P F 7 P B I H 4 L I H D S S A R I L I P I L M A R E M # E R L U R S S 0 0 I R E V R C W O R P P P P S E R 1 T E L S P A U S (P ( 4 4 4 L U A L
.)
C L E Dl S g D T W M I 0 P 0 Y 5 T R D 2 I 1 I g I 1 7 l I /. I R H l H x DN D I O R I 3 C R E I S E P M - o - P S P / 2 s O E 0 E 4 2 2 T
'o 4R P 4 l I
T F l 0
"e N
M T E
.l H
R E o c L R E
)
e H I P L P O ( R 0 v U e N T 4L ( : R O 0 C N O 3 1 3
- ! : l '
I m; j T A M R O F Ye r>
. l .: .;
i l 1 0 0 o "a f a c m huS F 9/ t 1 4 l ; 8 a 9 t ' 5 Fi a ' 1 s c t i uD9 I i L U 9 i J mlH I R
/
/
Ei P f 8 a E u i P M f O E 8 i T i S s4 0 K E C L B Vg j' w I R E M A Q-I Rc, I S, =[$
=
,)
L R l 0 A DG ) D D D L O V 0 3 I S 0 9 4 5 N I 5
*4 E
4 O P 1 P 9 I 2 I E r L n N o 1 1 T l l l 1 0 o C S r O N O T O U I w L H I S P F J P H E D 5 S B A R I L R P I L A M R E M # E R L U R S S
*/.
0 0 I R E V R C W O R P P P P S E R 1 T E S P A U (P ( (L 4 4 S L E A ,) C DI S G D T I T I R 0 2 I I H P E f 7 0 5 1 l I H E I 2 s p DN D 3 M I D C R E E S R E P - m - P S P M
' O 0 E 4 2 E T 2 2 4R P 4 l I
T F 1 0 T H I L a' N E s a
)
R R
'z M H E E A I P 0
I L P O ( A V U T 4L ( : P N R . O O C N I 0 3 1 m T R N R O Ob 3 F
.I ,j
; i! l
O O O l 313 I RPU mum ECRITICAL PLANT VARIABLES 'catar " * - i DRWER
; RPV lggpf l S
! i CONTRIHMENT ( SRO LIFT 1130 D = ! ' U PRESSI 70 IPSIG 0=[ l hr ! ( 100*/. BPU l 990 ) id i-t f
. GROUP I rsa I 4 TRIP HIl 54 D .
! (OPER HIl2.0D LEVELI+cr IIH
! PRESSI W EPSIG (5 CRAM LO 12.b) l 4OPER Hil150D i TEMPI av2l'F POWERI a I%
I
! , 4 APRM DHSCLI 4D ,
Z Z S I ) Z Z Z .i (OPER HI 24- 3 D SCRAM n'); Ng j m LUL r;> FT to IN n-M , h .A.As s A A /u a a AA.A A m 4 OPER HI 95 D l l (OPER L0122- O D TEMPI //7 I'F ! SUPPRESSION POOL i i ii i ! LIMERICK 0 0 0 25-JUL 1984 /q 45: 00 l FORMAT N0.: ( )
, Y
! ) ~$
O O O 313 I RPV Be##m ICRITICAL PLANT VARIABLES 'catat * "" DRYWELL-RPy E SRU R I Ma/ I
; CONTAINHENT 4SRU LIFT 1130) = ' b PRESSI ro IPSIG U =k l 5 /u l
( 100% BPU 990 )- iC i! ; l _ l RB l 4 TRIP HIl 54 D . > 40PER HI 2. 0 D LEVEL E aarIIH
; PRESSE II IPSIG (SCRAM L0112.5D i
! (OPER HI 150 D - TEMPI sai E T POWERI o I% q (RPRM DHSCLI 4D _ _ _ 1 i (OPER HI 24- 3 D ! m LUL FT /0 IN M 005 # h w nwurm 4 OPER HI 95 D j (OPER L0122- O D TEMPI //r I 'F SUPPRESSIDH POOL i i ii i l LIMERICK 0 0 8 25-JUL 1984 3:00: 00 i FORMRT N0.: ( ) M i i
O O O 313 ' Rev "1o " ' CRITICAL PLANT UARIABLES 'catat * "'" ' DRVWELL
. RPy l S RU E l OfEA I ; CONTAINHENT SRU LIFT 1130 D ::
I ' b (PRESSI 700 ::h EPSIG ! 5 pr l ( 100% BPV 990) iC it :
. I GROUP I l ISL N l 4 TRIP HI 54 D 40PER HI 2.0b LEVELI+3s> IIH .
PRESSI 7,/ IPSig (SCRAM LO 12.5D f l t { 40PER HIl150D TEMPI as/ I'F POWERI o I '4 I __ ___ __._
, 4 APRM DNSCLI 4 D ,
\ \ i
) (OPER HI 24- 3 D m LUL as FT /o IN M o 5 rv Q w nwug 4 OPER HI 95 D j 4 0PER L0l22- Op [ i -- TEMPI //7 I 'F i SUPPRESSIGH POOL i ii i i i 8 8 E- L 1984 m r:00 FORMRT N0.: ( ) 1 1 I d i s .
L O c a- n u 313iReveto'" ' CRITICAL PLANT VARIABLES 'catar e-~ ' RVWELL apy I IoSRU l j SRO LIFT 1130 D CONTAINHEHT =
' U (PRESSI roUIPSIG ::b l 5v r
- ( 100*.
/ BPU l 990 ) it it
. GROUP I l TSLN g . l 4 TRIP HI 54 D .
l (OPER HI 2. 0 D LEVELE +nrIIN
; PRESSI a.9 IPSIG 4 SCRAM LO 12.5D l
\ > (OPER Hil150 D TEMP E poo I T POWERI o I'4 j ! . 4 APRM DNSCLI 4 D , j
) )
~
---. : ~
(OPER HIl24- 3D AA.AA LUL s FT /0 IN M # / Q w nwug 4 OPER HIl 95 D
- j 4OPER L0l22- 0D l
~
TEMPR iis E'F SUPPRESSION POOL e ie i i i 8 8 0 25- UL 1984 ^rw:00 FORMAT NO.: ( )
- e i
i E i
O O O 3 1 3 i aev et o' ' CRITICAL PLANT UARIABLES ' catar ^""' ' DRVUELL lE OFEr/ lg ppy SRU i CONTRIHMENT 4SRV LIFT 1130D\==
' U PRESSI 70 EPSIG b l ffa
( 100'4 BPU 990 ) It it
. I GROUP I I .TSAN I 4 TRIP HI 54 D .
l 4OPER HI 2. 0 D LEVEL E *w I IN l PRESSE o.2 IPSIG (SCRAM LO 12.5D , ! (OPER HIl150D TEMPI JJo I'F POWERI O l'4 l 4RPRM DHSCLl 4D l _._ l l (OPER HI 24- 3D SCRAM i M LUL 22 FT lo IH & WOPS m-
& A >v J a r.nja a rm 4 OPER HIl 95 D f (OPER L0122- DD TEMPI //0 I*F SUPPRESSION POOL i i i i i LIMERICK 0 0 8 af-JUL 1984 zo:A r- : 00 FORMAT N0.: ( )
i [ 'b
O O O
'catat e" '
i 313iaeuaee"'" iCRITICAL PLANT VARIRBLES - DWWER ppy SRU R l lE OF6d
- E
) (SRU LIFT 1130 D -
; C0HiAIHMENT ::
l
' U PRESSE 70 EPSI6 0:h !5 l
l : ( 100'4 BPU 990 ) iI i0
! . E GROUP I E IS w E i 4 TRI_P HIl 54 D .
(OPER H: 2.8 D LEVEL E rra/IIH 4 I PRESSI 3 7 IPSlg (SCRAM LO 12.5 D , l . 40PER HI 150 D TEMPI sao I 'F POWERI o I'4 l , ( APRM DHSCLI 4D , Z j S S Z Z (OPER HI 24- 3 D m LUL as FT m IN M B d Q w nwgu 4 OPER HI 95 D j j 40PER LO 22- DD TEMP I /OS I 'F SUPPRESSION POOL i i, ,i i l M S S S 25-JUL 1984 m oc:00 FORMRT N0.: ( ) ! U { E
O O O
- 313sRevotee'"iCRITICAL PLANT UARIABLES 'ca m e" *" '
ER RPy I SRU E l oftN I i CONTRIHMENT SRU LIFT .130D -
= ' b (PRESSI 7e IPSIG b 5 l
- ( 100% BPU 990 ) if i!
I lE GROUP l TS/N E 4 TRIP HI 54 D 40PER HI 2. 0 D LEVELImIIIH l , ~ PRESSE 3.f IPSIG ( SCRAM LO 12.5 D j , ! l ! (OPER Hil150D
~ TEMPI 3/9 I 'F POWERI O I'4
, 4 APRM DNSCLI 4D ,
s s \ .
- : (OPER HI 24- 3 D N LUL Js FT /0 IN M /&' # Q w ngwu 4 OPER HI 95 D j (OPER L0122- 0D
{ J TEMPI /o6 I 'F SUPPRESSION POOL i ii ii , i LIMERICK 0 0 0 25-JUL 1984 >/r/5:00 j FORMAT N0.: ( ) I O l l 5
i l l 0 0
" 0 3 =" m 3
O /f f #
/
?.
t 4 l I a t AD 5 F 8 9 1 . a ' c 0 1 a 9 i L U v l i J
>_ I -
H 5 A. i 2 A. R E P e 8 P M d E 0 i AO T i S s4 K E I u C L v I R B
>s - E M
A I 4o R S .)
= ,)
h-I L R I 0 A DG ) D D D L O N V 0 3 I S 0 9 4 5 I 5
'/.
I 4 l O P l P 9 E 2 I l I r 1 o L N T i T o l U l o f 1 0 C S M AW O I O N U I < F T P L N R S P H I D C S A R I L I B P I L M A R E M S*' 8 E R L U S */. 0 I R E V R W R P R S 0 C O P P P S E R 1 T E L S P A_ U 4P ( 4 ( ( S L U A L
.)
C L E DI S G DF' I T I R W R D 0 2 l i H R P E V s 0 5 1 l i R H I I fi c DN 3 M I D D C. E P I S E P M P l
- 0
/
E S E 4 2 O E 0 2 2 T
' 4R P 4 l I F T 1 0
T H E L h N E R 2 2 R
)
t M E E H E P A I P O L O ( R U U P H T (L ( 3 R 0 0 C N I O 3 1 3 m f' T A M R O F d l
O O . O 313IRPUMt4#in ' CRITICAL PLANT VARIABLES 'catat * * ' DWWELL
' RPV IE OFENSRU lE
; CONTAINHENT SRU LIFT L 130 D -
' U (PRESSI 700RPSIG M ! 5 ar !
( 100% BPU 990 ) id it ; I #A"" l 4 TRIP HI 54 D 40PER HI12.0D LEVEL H+or IIN
! PRESSI M IPSIG 4 SCRAM LO 12 g 40PER HIl150D TEMPI p/f I'F POWERI O I%
, (APRMDNSCL 4D ,
3 3 _ _ _ (OPER HI 24- 3 D SCRAM j m LUL o FT /0 IN #W W h .A Av s A A_ C 4 OPER HI U A A.h 95 D l I (OPER LOI22- 0 D TEMPI /o# I 'F SUPPRESSION POOL i i : : LIMERICK 8 0 0 25-JUL 198V /F Mt00 FORMRT N0.3 ( ) i 2
O O O'
'catat = " '
313 I RPV de###1 CRITICAL PLANT VARIABLES . DRVUELL
; RPV l g$Ug l j CONTAINHENT SRU LIFT 1130 D -=
j
' b (PRESSI 700RPSIG M l ffs !
( 100*/. BPU 990 ) 14 it ; l Ss i 4 TRIP HI 54 D 40PER HI 2. 0 D LEVELivru RIN I PRESSI o.4 IPSIG 4 SCRAM LO 12.5D i 40PER HIl150D TEMPI se! I'F POWERI o I% I 4APRM DNSCL 4D f _ (OPER HI 24- 3 D l m LVL A7 FT /0 IN M # ^/ Q w sAwaarm 4 OPER HI 95 D l 4 DPER L0122- 0 D l TEMPI /00 l'F SUPPRESSION POOL i ii ii i LIMERICK 0 0 0 25-JUL 1984 22:00 00 FORMRT N0.: ( ) < r .Y g , y
p r L) O- . < . o'., ICHW WWp H 313IRPU4t4#/v ICRITICAL PLANT UARIABLES DRhWELL Rpy I SRU l OPEn/ lg
; CONTAINHEHT SRU LIFT 1130 D U
(PRESSLidPSIG O:M l ff/ l ( 100% BPU 990 )
. E GROUP I
. I rup I I 4 TRIP HIl 54 D (OPER HI 2. 0 D LEVELI47a/IIH
'- ~ ! PRESSI /.9 IPSig 4 SCRAM L0l12.5 &
(OPER HIl150D TEMP I 9// I 'F POWERI O I%
, 4RPRM DNSCLI 4 D ,
1
) ) - - _
1 (OPER HI 24- 3 D I m LUL 2a FT /0 IN M l'> ^' h .A>v s,_AA.o 4 OPER HI v a rm 95 D l 4 OPER L0l22- 0 D TEHPI /00 I 'F l SUPPRESSION POOL i ii i i LIMERICK 8 4 4 25-JUL 1984 r:/S: 00~ FORMRT H0.: ( ) s . O f
. O O O 313iRPV4t##/" ' CRITICAL PLANT UARI ABLES ' catat ^~- '
DR'/WELL Rpy SRU lg OPEA/ gl i
; CONTRIHMENT
( 1130D : -
' U[4SRV PRESSI 70 LIFT IPSIG k l5a
, ( 100'/. BPU 990 ) II it GROUP I l TS2d E l { TRIP HI 54 D . ) 4 OPER HIl2.0 D LEVELImrIIN ) PRESSE /,# IPS18 (SCRAM LO 12.5D I (OPER HIl150D
- TEMPI 0 0 I'F POWERI o I'./
f
! / , (HPRM DHSCL 4D
-)
) - - _
(OPER HI 24- 3 D wn LUL 22 FT /0 IH & A9 d
& jans sawaarm 4 OPER HI 95 D j 4OPER L0l22- 0D TEMPI /OS I 'F SUPPRESS 10H POOL i ii ii i LIMERICK 8 8 8 af-JUL 1984 22"r: 00 FORMRT N0. ( )
t A
) 8
o e c 313 I RPU ptp#m ICRITICAL PLANT VARIABLES LC8 tnt atoay) i
; RPU l ggr, SRU l
CONTAINHENT SRU LIFT 1130 D -
= ! U (PRESSI ro0IPSIG h !qhl
- ( 100'4 BPU 990 ) iI 3 M '
GROUP gl TS/N i 4 TRIP HI 54 D . l 4OPER HI12,8D LEVELI <7sr3 IN PRESSI A# IPSIG 4 SCRAM LO 12.5& ( [ i ! 40PER HIl150D - ! TEMPI 9/9 I'F P0lJERI O I'4 \ i l _ _ _
, 4 APRM DHSCL 4D ,
_ _ _ \ l - --- -
) ) - - -
i (OPER HI 24- 3 D SCRAM I hA A LUL 2 FT to IN M d95 h w sAwvarm 4 OPER HI 95 D f (OPER L0l22- 0 D j - TEMP I so I 'F i SUPPRESSI0li POOL i i ii i LIMERICK 8 8 8 2f-JUL 198V T W/5: 00 FORM 0T H0.: ( ) '
, Y I o.
O O O 313-I RPV tt/im ICRITICAL PL' ANT UARIABLES 'ca m a " ""' '
~
f DRVWELL
. Rpy E SRO E l ofw I i C0HTAIHMENT 4SRU LIFT 1130 D :: ' U PRESSI To IPSIG UM l5 l
i ( 100% BPU 990 ) id it lSEl l 4TRIPHI 54 D . , l 40PER HI 2. 0) LEVELI +nt I IH
'\
i
! PRESS I /.7 IPSlg 4 SCRAM LO 12.5D \
(OPERHil15D
\
TEMPl ai? I 'F POWERI o l'./ I _ _ _
, 4 APRM DNSCL 4D ,
) ) - _ _
4 i (OPER HIl24- 3D f u v t. u lVL 39 FT /0 IH M c'< ^' Q w nwou 4 OPER HI 95 D j (OPER L0122- O D TEMPI /vo I'F SUPPRESSION POOL i ii ii i
' ~
I ' ,200 FORMAT N0.: ( ) f 1
' E
O O O 313 I RPV 4tMin I CRITICAL PLANT VARI ABLES ICHTNT AN/r I DRVWELL ppy l Offr/ l SRU lg
; CONTAINMENT (SRU LIFT 1130 D -
PRESSI To IPSIG 0 ::M l SfM l (100% BPUl 990 ) if I 'l '
. GROUP I i 1tu W I 4 TRIP HI 54 D .
( OPER HI 2.0) LEVELI 4rorIIH i PRESS I /.7 IPSIG 4 SCRAM LO 12.5D (OPER HIl150D TEMPI s/6 I'F POWERI o 5% l 4 APRM DHSCLI 4 > \ 40PER HIl24- 3D SCRAM m LUL x FT 10 IH & A 'U*'l & .AJJ J ALA JJ A AM (OPER LOl22- D D 4 OPER HIl 95 D { TEMPI /00 l 'F i SUPPRESSIDH POOL i ie i i i LINERICK 0 0 0 25-JUL 1984 W.fS 00 0
~
' l l 0 _ ' 0 " P 7 " 0 3 _
0 e-p 5 0, Rg, m : G 4 t : g a t rD5 Fi 8 9 1 a ' c I i a 9 I i L U a l o i J I v
/ -
H 5 w E R P Ii P M E 2 8 I I a O T i 8 S s4 t K E II C L B w I R E h-M A Ud R I L I Sv/ =[$
= ,)
o R II A DG ) D L U 0 I S 0
)N D5 4 I
% 4 O
O 3 P 9 5 . 5 P 1 9 I 2 I T 1 I l r 1 1 o L C
" H D
n* l l aN yo U 0 S T I y I N p F P H L I ' S B D S A p I L I P I L M A R E M E R L U R S S 0 0 I R E V R C W O R P P P P S E R 1 T E L S P A U S (P ( 4 ( 4 L b A L
,)
C L E kI S G DF W M I O P 0 V 5 T R 2 I 1 I D l I 6 l I J-R H /, H i DH D C R I R E L P 3 I I O E S - o - P S P M 4 / 2 I O O E E 2 I 2 (P R ( T l T l ar N T H I I F 0 L d E s R
)
/2 M R E
a E H P l P 6 I O L O ( A U U T (L ( : P N . R O 0 C H e I T O 3 1 A M R O Ys 3 F
.l i j'
. .e i! , -
, ' f
o e a C+) 3 1 3 ' Rev neo d ' C R I T I C A L P L A N T U A R I A B L E S ' cam ada I
' DRYWELL S ; RPU l gg l C0HTRINHEHT SRU LIFT 1130D =
I U (PRESSI EPSIG700=M l' S y l ! ( 100'4 BPU 990 ) ii i t- ; I GROUP I l l I rnN 4 TRIP HI 54 D i 4OPER HIl2.8D LEVELIturlIN PRESS I /.6 IPSIG 4 SCRAM LO 12.5D i 40PER HIl150D l . TEMPI s/6 I'F POWERI o I P.
! / 4 APRM DNSCLI 4 D q _
j l 40PER HI 24- 3D m LUL z FT a IN M 8 ^' h, wsarwar.m 4 OPER HI 95 D l 4OPER L0122- 0D TEMPI /vo I'F SUPPRESSION POOL ii i i ! LIMERICK 9 0 0 25-JUL 1984 2 5f'45:00 FORMAT N0.: ( ) 9 i f
I lI 0 0 P 0 M Uw 0 O N A W 5 O 3 Rr G IE mV5 Fi 4
^
8 9 1 H C I t i uD 9 I i L U o i J g w I lH R
/
Ii P 5 0 2 E M e P E 4 O 8 T S 1 n4 i 0 ENl L B Ug w-K C I R E M A I I R A
/o; =)
S l
= , )
h- L DG ) D N D D L O V 0 3 I S 0 9 4 5 I 5
'4 I
4 O P 1 P 9 E 2 I 1 I r 1 L / N T l o I l 3 1 o C S O ONLA V T U I 5 0 I F T P # L N S P R I B H I I D n S L I P M R E L A E M R U S '/. I E R W R P S 0 R V P R 0 C O P P S E R 1 T E L S P A U (P ( 4 4 ( S L U A L
,)
C L E pI G S DF' I T I R W R D O 2 I I H P I I.
/
0 5 1 l I H R I I
/o
/
c DH 3 M I D 0 C R E [ S E P - I o/ - P S P M 4 2 I O O E E 2 I 2 4R P (T l I T F l 0 T H I L
#m p
N E > ) l M R E a R E A H P l P I O L O ( A U U T (L ( : P N . R O C 0 N e 5 T O 3 1 R M R O t' 3 l F
! l ,j
' i
O O O 313iaev "'"~ll CRITICAL PLANT UARIABLES 'catat ** ' DRVWELL ' ppy SRU R l oma l CONTAIHMENT SRU LIFT 1130 D 4:
-I U (PRESSI 700k IPSIG hf
( 100'4 BPU 990 ) ii iI :
. I GROUP I -
l TuM l 4 TRIP HIl 54 D . 40PER HI 2. 0 D LEVELIrr orIIH PRESS I /,V IPSig (SCRAM LG 12.5D (OPER HIl150D TEMPI s/S I'F POWERI o I'4 I , (APRM DNSCLI 4D ,
- \ \ _ _ _
(OPER HIl24- 3) f , m LUL Js FT /o IN M ' A' h w nwou 4 OPER HIl 95 D ! [ 4 OPER L0l22- 0 D I - - TEMP I '/9 I 'F SUPPRESSION POOL i i i e i 888 6- 1984 s'm/5: 00 FORMAT N0.: ( ) o Y l i g. I
. ,/
313 i Rev "^" "' ' CRITICAL PLANT VARI ABLES ' cat"T o-e ' i DR. ER Rpy SRU I I I OFM/ I l ; CONTAIHMENT SRU LIFT 1130 D u - l
' b (PRESSE To 0 EPSIG h l5 v. !
l ( 100'4 BPUl 990 ) ,, ., . l I M3" l ! 4 TRIP HI i 53 (OPER HI 2.0 D LEVELE narlIN . [ PRESS I /,7 IPSIG 4 SCRAM L0l12.5 D 40PER HIl150D TEMPI di5 I'F POWERE CI'4
! 4 RPRM DHSCLi j (OPER HIl24- 3D CRAM I
'm LUL @ FT /0 IN uM "R h _A.A./ s A A./ v v a A.m 4 OPER HI 95 D I
(OPER L0l22- O D TEMPI 99 I'F SUPPRESSION POOL i i ii LIMERICK 8 8 8 26-JUL 1984 0 s i50 l FORMAT N0.: ( ) i O f
O O O 313 I RPV Aep* ' CRITICAL PLANT VARIRBLES ' catat e""" ' DRYWELL
. Rpy I SRU I
- I orEN I CONTAINHENT SRU LIFT 1130 D 1 u
! U (PRESSI 70URPSIG M l.5 bl
( 100'4 BPUI 990 ) i! ->0
. E GROUP I l rS +N I 4 TRIP HI 54 D (OPER HIl2.0D LEVELI<urIIN PRESS I /. / IPSIG 4 SCRAM LO 12.5 D 1
1 I (OPER HIl150D i TEMPI s/s I'F POWERI o I'4 I 4 APRM DHSCLI 4D l , S 3 _ z l (OPER HIl24- 3D ! e LUL su FT /o IN M 095 ^/ Q w nwsu 4 OPER HI 95 D ! j 4OPER LOl22- 0D TEMPI 9/4 I'F SUPPRESSION POOL i i i i i l 0 0 U 198 o <#:00 j FORHRT NO.: ( ) l i o Y i $ f
. . . . ~
, ,- , y . .
j3 .:, A 4, ..y s ,
. 7-Q ..
+
.INDEX POR PLANT AND REACTOR SYSTEN PARAMETERS VS TIME GRAPSS
- Parameter- ' Units -Graph No. Parameter ~ . Units-- Graph Mo.-
. Reactor Level inches -1,lA,lB Drywell Press- psig' .20,20A Reactor Pressure ~ psig- 2,2A' SGTS Flow' ~cfm '21.
Reactor Power :-% Full Power; 3' Drywell Atmos Temp. 'F 122 Core Plate DP % Full Power- 4 Supp Pool Presa lpsig .23 Core Flow '1b/hr x'10 5 -Supp Pool Temp 'Ff 24 Total Steam Flow lb/hr' x :10' 6' -Supp Pool Leval: feet 25 Total Feedwater Flow lb/hr.x 10' .7 ' Main'Stm Line Rad Men mR/hr '26 Condenser Vacuum inches Hg 8. Containment Rad Level R/hr- 27 Hotwell Level- inches 9 Cond Stor Tank Level. feet 28 CRD Charging Pressure psig' 10- RCIC Flow gpa 29 Inst. Gas to ADS Pressure .psig 11 HPCI Flow gym 30 Equip. Drain Coll Tank Level feet 12- RHR A Flow 'gpa 31
- Equip. Dtain Surge Tank Level feet- 13 RHR B Flow spa- 32 Floor Drain Coll Tank Level feet 14 . Core Spray A Flow 'gpa 33 Floor Drain Surge Tank Level. feet 15 Core, Spray B Flow gpm 34 Hz Concentration % 16 RHR Hx Outlet Temp *F 35
, 02 Concentration % 17 RHRSWInletTeh 'F 36 North Vent Stack Concentra- pCi/cc 18 RHR C Flow gpm 37 RHR D Flow gpm 38 North Vent Stack Release Rate pCi/sec 19 a.
5
H' l O s g b' ' '
; O/00 I + .i .
'li i i . . ; l i I. .
. . ! i ,
- l.I ! i '
.l l 2'100 -l i . I ! ! ! '
'.r i ' -r I
a '
.I .
I l i j l
. lh.I
, i' , .
' i . .
' I i ! . i ! l ! !
l i l I l' ' l i , l i j ; l ! ' I 2300 j !"
-11 !~
r-' ' '-INCHE5 -N - ' E I I I !
~-
' I l@ 3 l . 'l i #3 2,0 ie ha' ,l='&o 8
l
. i l
g1 . I SFl } .Ii " i , 1 , ; . > i 1 1 .
' I 2200, 1 ,I....-. l i l I ! ! ! . l !
I I L., I I I ! ! !
! l.' ll : !h l '
! l 4
,~
i i i i .i' t i t' , 3 GRRPH-1 ! ! i : : i : i i i ,3
. i l '
!.2100 i
.!.! '.. I l l l l .'p. . .
. . , d, l l' i ! I ! ! j } i i j i I ,
l i l l i_ q
' I ! l l ! ! .'
I i . l i i l ' l ! ! j l j i l. $ i i i c ;i i j* i i . j
, . I y
20001 !j
; I
. ..: i.. ;
- 14. p
- l l i ' I I ,
u
' l ' ,
i a j li , ' i l i i - i i I d t e a f g 2 9 A I I l l l I
! ! ; i j i + : . j .
3 l: '
'i _1 i d _1 5 1900 I I ' l ! ! ! .
. . . [ 'y
. . j l , I i l i , ' e 4 > ,
j t e ! l' l i i ! l l-I N mcai5 f i! j,il y O '- * {l ! Re.ador Lwe.l(hR) U800 i m Je ll t a i I I 30 - o i ! , to r ;, ,i r- [ m;
' . . , , 4 II l I :
- l i , ;
e, l t I
!i ! lj ! l ! ll f'-Ml !
~(inc he,s) l j ; !
i ' l l l ' ! ! 1700.!- - i y l I
.i
.7 l l i
I l , 1 ! j ; i l ' l ' i t -
. . i i j .
l ' I i! i
, l l *
, ! ! I i
' 'I l !
I i I/oOO .
.i.-, .i .. ,! i l l .'.,: I i l ? ! l l 6 ! l l i
!i t
i l j - ! l! j ,
! ! ! i ; ! !
i
. ; l l i l l i i !
l I l1600 l l 1 l l l l . I i i
-'-T <
Pl , , . j ' i ' ;
' i I
j i T"!
- ' i ,
l ! i i [ l i , , i ! i l .
. l 1 .
, j l .i I , ,
6 1 i !
! 1 l l l l ' . t , i . , l l' i i . i a i e I ' ' l '
.i ij l ! I . i I
i
' ', l l t
/900i !
l t ! i
. , l ! ! .
j ! l l
,i', . . . . . ,
. p -il l ,. l i
l l Ii l INCH i .
. . I , j
' g I, '
l
! (9.E.S. %l i ,
58 i . R M, I l Fi .I : . . ! "l
, i 1
i' i i l l ,. l l l' I i l
/300.6 l i ; :
~ ~
l i t il ; ! i i 3'
+ , t -
i n l ; i l - i l i l i , j ,: : l. I i I , i i l i i ' i
; ! i ;- .
l l l !i
- i. ,
i i i j j i t
~
1200 i > I ! I I : . l l ,i . : , 1 - N(.TJ7T .ci t . .
"t-
T ~~ 1 3J-111 l'
. ~k .
'll[
- i. .
;I*
}
-l. .i .
t l.,' I' i
? .'
a'
a -- " f u.e_.yr_.lF~TrJ'>-9'jr,- t .
; pw l l
, u k -_b .a Lsc 4 m o._ W u ,
i l l lli ;I
. 2 2 ._
.L4 ..
I : p l j
~2400 l l _- _ -_ ___ _ __
o. g3oo azoo t G RBPH- I R _ d-l2 E( O O 3 4 i g_9, , l
.' - ' -/cp o o
! I Reo. dor kudGoR)
, /200
. (fnc.he.s) j tvoo
-__ /Go g (GO O lI ll 14mo /
- 1
---- -- . 6 - - -L-_
f -- r I
/300 t
l i d e r
- I I _,..; ! I l ! '
g g,o o j
! llllll 3J-112 l
i m . ,c
.l m . f., c .< a. ll e o .. r ,. I . d i l l l.
~ ~
~~
l ll l l jkull ll!l Hj !!j"'"' s :, g .. ge qs , 9 , 1 3 L -
. ! l l ! i.
yl;
,'I mac
/ . , , ,
i
' ; I .
- i. .
I
- ___ _ l _ l l.1 .
I li i! a' p i z3001
- .. .: I 1
l i 2200-
! l l .
~ " '
. G RRPH r.18 u n
7.J00- 4 f I ; ll - - . i I ww i l.l l ! 4 - __ _g l j i : : t f900 ! l i l! ! I i
~~~~
i i 1 '~~ Re.ach leve / i ; I l
) .Shutclown 'l '
pg 5 (l'nthts) .
~~~,
'}..t- 7 ,
l l/700-
, /&OO-
> b= .
i i /600-1 i i I .. . I l 1I ,
----7 /wo j
"~
.:J f j
, _.Lj coa.
r
. . - ,2.-
,g i .i i
I g u-u3 nm nmMm?ll e'n, - ',:,n W
muu o.u un a.o
.2 2 0 ,
l t i l - ' '
.a l
l l l2900 -
- g. ..q _ 1. ;
I l i zsoo< j I l
- t. l_ . 1 ;
! l ll' l. p -w! .2200
' _.L ._
.1.U __ L.
; .3 i i you ! -
G RR P H <2, I II - II
, , , . 2000 j ;
I ! p__. ___ _._ _
. i m n , ,
lll '
'! l l l
! .. iih I ! I nl
.., ! i l
l l l l F" l l' ;l i i I.
, , , IRoo I
r Reactor.Prusure.ChR) I.. __ _ _L _ l 3 (eap . . .. .
- th0C
.L. . . ... .. ..- .
t 500-Y l 'g
-4.qg
--... , I ll t' I' 2 I
I rm l l l ul
+
4 ii j L l' i coo. ' l I f l l
,~~ x
, ens, ..sa an. ntnisa lII 3J-114 P'i.
zu;4
'! 1 t .
- .. LL t
/.~ i e
p . ;
* ~
[![ 'i l' jlijjlj j {'jjj('[j j(!'j , ll I i i ll!h!$-
^
.kl l rl i wr ' : -
h '
'i j l !1' y -(
fj 4 f: p .l: p m i 2 , i
!!u=
r
~
. , e (pll p!
I i ul... I
! 22m!
l l ! ! L .,... . li l ..I l I l i.. i l l GRRBH-AA , - ~d 'r - Of i 121 * ~ ! I !I i; l l: il i
. t. . u I l!
t.. . All
' l .
5 3
.20m i ! i u, i n l ,
4
..j l ! i i q.g.., j
.1+ .g ..
I ! l- :1 '
...7l j;
!'ii j! ,!;.
i - I
- j l i n in i il ..
ii ,, l I' { "i~'
.R uc. tor. Pre.ssurcGod) ;
~~ ' "
- "l"
. -[ i (psig) '
--.. i I
, 7g .
t I 4
; / Goo
\
i : . j.. ... I \ l
! ..l ,w .
l s I q i l i, k. s ufoo y l\! 1 ll l l l I l J. g.ql ; l lH l Trit l jmj e i l ii i j
! l. I j
i . I , ! i s 000 Ij l l !! jIu +,
- r. , ,I4 r -
4;j]Il gp,
!i II ) 3J-115 mtin!,ii iir;!!M' in thu., o ao un i i: a L.
ft ,
.td .j,n p-
[ gh." "J. To 8f put Jf ..:!! .L gf I j li,: l. o' ! ' :1 p l
;h,:' t,:-
, -. p . . . .
----1400 e
i :p i '
'. j;;l ,
l 6 [. f' ! l: I '
. , ll id lp! i
;i, 30 '
UI 'I li 1 , ji . ;;; lll I ll lI !Ij ji!: .'l l M00
- , .m . n, , . h ..
n' , :
, G RA PH ni- ji!'
1 : r ::li :ii
. , .' l
! 2ico --
l I
- f I f
I -j i ! l 3 :!= * }; !. ill l l;1-il l
, t y -- '. za
- i j ,' l 8 f! l I I l ll I IIl- i 9
l l l*!l i ll !!i N
~ -
.y . Li , m i ,: .: . p i
ii "l! f Reach Power ! iP.,'
j ll. ill ![ h i.u. 11,, l . (% Full be) 4 9 }6.a!i, ! d. !!h.
.. .i , m I
i :
!!* i t
, i;I700' i
,l
- i. I.
l iIl l! k ! i f lk k" n:2 l
,; ' );//o00'
*lj Il
.t l' l
f l ;i .!
-' l' 11. i
' ' j' (;, /
li' l l lulflf,l'1 60C i . i j ., l
'lii-
.i,, i, it j
e l 3 :' ,, ;!; il ll i i
'f if i ll !
.(.r /4 oo i
L i !i
! i 1 1
a e i.i t I ji [, I 11 ! I' i! !! li gff i i I i l ll '
- l! l \
4 . ij . . 1 .
'l Ill I I l ' t l l 1 4: 4_/ggl
!! :L n. -
if aii I!!blii h!I$l l-
" 33-1 6 i f'I
s N., , p.7 .p , ,
.e a, c x r .
F gj;t' 1 d g] O/00-ap q:. c n ..
.i
, g
;' 'i;,. ,I ',, . .(
u,.. ;
- .1
- $ ", ,l ; , f.
' i 5
m 8
;, :- 1 3 r r- ----F i,t P , i 1; g't.i _... Jii'
- . I -
l ,
% fat :? ova E o ri,o n >r ..,. 30 ,, in ., .,
,i . .. : --2,300
- i , i..
i , 1 [J
, i, n :
', M -
' 3 I
I i l .1 -l t t' ,t . i , h GRAPH-% l. , j ,
! a t , ,
t lI $ . i [f . e
. .1 , - -. , . ,2JO0 p
e 9. 1 . - o 1 m I: li l e i y .
.r o w -- a u ., # ,, in m ,
f % i
'l!
q , .! .+
.----- , - m-
.a ,
't l ,
., /7o0' ,
- - s . C o re. Plate.' DP / . i
,l Il I f L w moo
(% Full Ibu) I s .
' L '
i
, 'l ,
4,, -
'l P p .. '1 1 ,t. - i ..
ii oi ,n .. v .: 'ai
< r so .;:ml - k f m!t ,U /
i i .. .I i\ y,in 1o .i ! :t !
-jl1 g Ji'
- P 1, ;
'!, ! .., 1 11 3 r ;i -l ,
[-: ' " j; i
! .! ) i, , . c i; 4 t j
i-i q.
, n
'j. !
.g. .i
. !, ., ;! 1,, ,.
i, n a., -a. ,, , ;/4o') i.
.' i! ' '
J -j f.htc p. .t '+ e
]i; ... ,
p ia. . ' r 1g
- i. + ,.
n .m . ,
- y. -
y 9
.. j
> :y o ,
- :,{...i
; ,q L ir. ,
c '. .n .,
+ y' y. 7"'Sco j.[,,fl '! '
i .nn.: 1 3 g, n }. . - i
'1 n' ji i[ A .' i. j! J ,,, g .l.
wa r . s v;-m i a. v.~. kd'Om :m . o i ei p j'/*'* i y i. o .
,; .. ,i n'
.I r" ' i il lq:N"i f' I P;' I
., ].,
.l. ! i if -. .
L .c - e " o p .c i. - . , , g n ji o
.i: r i f.> I- ,, ,
f gl; uli jl ,d i! :iy ?, - t .n.p q g ,
.. .i y l p i i. - .
p.- .
,. ,, a coo l M n; a 4 6' F di
.1
- i . ... I 1
! I Sa i :.! d. L,T, lf e -
i
, i,, '; ,
I
^
p, a k f! d 1.,, $il.'.I, ' hlg.O(>.fl l 3J-117 T L__, ." . Ah J
y-__ b - - ~~
, p .
;p.p .
m z - n v , n . ,, a u '
; o/OO' e .
n. N. 6 g . l'
- s K
l I izzoo GR APH-5 ,
!2,00 i I d I
i 2000 f l
; e
- 1
._]
i 18t 00 Co r e .Flou; '
! I .
- i l I I
l i it ,
, , , 1800' (Ibthe x 10') l '
l l 170 0 i I l uoco-l i l I i j ; eso. j L ..3 _ m .- . 3 o I , I i
.ipl l l
u i i l a '*1
- 1. .l ! 7 ..,.. .7l . , . ..g.
i i n i i n q ,,,, i 1 Ii
.., y .lu.. .
u . i l l l l l1 I 4 [.. . . . 2 , .- f 4lll. i
.._l:..y l
lli!Eb!I!l,,.,200gIf!!! !I!1 3-' 8 e
L k J)Ic)llWlWllWillJl,co o
.~ .. . . 1
!~ l l ll lH
'. ! J-woo
~ l 'I!! Ij:i .
!!l, i '- i ih....9 l
l l-zzoo j G R R.PH - 6 2l00-i 2000 l 1 l
/900 i
-s Total Sbm Flow I
<800 1 (Ih/hrxlo')
/70 0 '
(600 1500 1400
/
I ,I :' I ' l200
, l 1
3J-119 e _1: y . ..I l $da s la I rf ' lt'l t l! lllljllllI ! i' i s,'lA 1 3 b l !IIII!lll 11 I
7~
~
~ ~ ~
s
'I l. JLLlJ i 1J il.. lli!!!'
i i i I 1 1: !i ll u .17 , _ i l ll l. i .
. { . t __ t. ..
~~
! I l !!
; , 23 00 k'
- r. - . -_ _ --- ,
I l l, [; y ll l, i I
------moo GRA PH- 7 U
,j- {y![,
-. . t ,
UJ
! ... .zo ,!
I I i j
.__.t.
.,_ g, n ... _L- . .
I ! I ' t L,, j Total Fe.edater Flow - g I (lNhrA 10') ;
, ivoo l
! i i !
_ __ _ . .. _ _ J. 3 i-
'l ! I I /
l %. _ __ _L__ i I..d _. _ _ _ __
'l e..
l l 1600* I (400-i il l 'l uoo l l
' zoo l i * ' a
> ) ,f k l d- (L / P f L8 / Y ls /d d I I
__u hE ..tr' ! ..
. lip _o s 3J-120
.l llll lllllll: Iill !ill lll!
- - ~
.. mutalin,lw , :. 1; .
L',',Y ' :
,, Mc)O I
. i i l !
l! D i ! , !
- l ! . i
' -e 1 l r'-li
, l i.
i 8 t i j
' i 1
1 : l i '
; i , ; i i , 4
- , ; j ji i i
',ih!!, I .
, i l zuco ;
- l- 1l ,i i u- t 1 1
, i i , . : l
., 1
~
T'
.I.
l' 'i , ,
. j
' 9 I 9 l i
! l .
i l, l i i l l
, i ,
; i l i ; ;
I
'i i :
! ! l : l !
i , i ! , i ; l !
.E, s__o.' o, . , .
i l i ; l ! ! !Ll } ! i ! ! l
' ' i i l :
i j i l, i ! l i l ! i ! j i i ! i ,
- ! . i l
' ' l l ,
' ,, ,, l l '
l i , { i l l' } l i ll ' i I i l, l l :i l j l'
' i
- l. l j l22 00, d4 ' . .
t. l i f; l l i l l ji i
, i llll ;
GRRPH-8 ;!.lil I ' '
<!:r!!i l i l i j
l INCHES H
, 4 i j
l l l to I ! is !g h E100 ! 20 i l I 25 l so ; m m I ' ; l; I ' l l l l !
, !j i l l i l ,
I j,ll;' . , i j t j i j il i . ,l ,
. . i i
l' 2_000 . : ! : I -
, i
.i y ;i I 7 7. g;i 3 .
_7.9 li l: a e l - i t . l l !
, i l j l l ; l l i i - -
. l
, , . . j .
, i ': i .i ,
' '.,i i ,
i l ! ' 4 8 f i l r i l s l i 1900 i j i i i l e l! i i C, ! ! ! j iii. i iM i i ! , ; ' i . i i j .
- l i Condenser bumm i . .l L ! ! ; ;ii j i ,
i ' l i i i j i , , li
~
l t '
~/SCO' -
l i i 1 2 7 _ (inches3ik) i l i ; !:
- ; i l ,
! i!
I ; - l l' I I ' i ! ! i
' j .
i i i
'. ; i ', ', l. ', i i
, il' .
/ ! l ; ; ,
! ; i i,
.7eo.h.. t I '
i
's~
I. io ,- INCHE,5 Hg is . . 20 j l i l 25 l I i
, ao I I t
[; s l; t'lI i . t . I I !
/doO l ! ! i .
1 Ti j r
-t -
l i l ,l,l i a i
, I l -i
! !' l l l : h .
l l r i
,j i
#' i
! , , 1 1 -
l . , i ! ; i
.,I, i l ,
g l hl
'isoo ' '
; , , 4 F i i
j i [i Ij,!jj il i t j 1 l I 1 l l i e
~]I.
i, j j , I I I[i[' { l l l l , l ! , f 0 s i' i i > l l i ,
-l l
!' >i gA l i l Ltaoo i ! , ' i i ., 1 i lll I l l I i l l l l I l 'i
; l i I i ,
l i ! ! l I A I' i : ' 8
; ; jl 'i i l
'!, l i ,
I l ii !
! i f.3 o o l . I '
1 1 i , I l l 1 , I I I li l l : l 3 I i d lil,! t INCHf 5 H I.,li l l - l !
! l ll p s, ol l !
i f* l i
'flis'ifl!
tr_c o _l io 25 i ! so i < i i
' ' h d .
i '
' ' l w i'i L i-k'i' 3J-121 i I l
i' l '
; i ' .i i . l . ' . I l *J W
e - - ,, e. + u ,. m.u 4 m % < e n.. , . , , ,i i !
!! ! t i i, ! ; l pjj ; ii >ii
.Lt.I !" '
'II ! b .t ga 9.a .
(
l, . ii, i i i l i l l l l 'i i zhaf .i i . .
. ! i 1., i i i L_ u _ ..11a ._. [-_
, .,_ ql _ .. ._. L_
.j e
t :. 2300'
.j. o 1 I i
*o
)
r - - G RR.P H - 9 l ,
! l m
i L ... ._. l I i
!, ,il 1 , ,
i m H l i I il vll. .l :!Ill i (Ls 1 I i l 'll __ i l
! ,q%
l l Hotwell Le.ue.1 i . _ l
,200 i 1
(inek e.s) . . --.. .. .... .
, f700-L _.
} l I I
rum. g i l .
,s w . i.
I i a I !
, 14 9 i I L__
._ .- .- _ _._ n___u l I l
l : l/ s f2OO-s x_,e mmm.; . r . l , l
, i L'.'
g
' ~ ' "
i: __IT j ii.i {!" d!..it.5 QE l l ll l ! . N j ll ! g it: ! i l .; i , II , lh ll!]. !!! li! ! ' i
]! l l :ii . it i: o .
V i :i : l'l lj.! 'l [iit l i !,! .i[!Il! ih. l'W i li F ij , ji i : ,, it- , , 2hm -
'l l
'l lh ll ! '!. b! ll,
;- i i i'i : 'I. o m ..,
lp ll ! l! l! i l h. h;I k,; I: il; ij ! ; ll ,il . . I I l ill g;l - > .N kI! ;
!i l l ,' ' h :i', M' i ;! I llR I O!lin @ hi e
.a' y W
. , 2.200-ip.
. j q /
d hIl l$ tb !Hj !" i GRRPM - 10 ! >, ,,i i
.!4 ; ":! i' : ,; -
j '> ,, . II', I..: is t l;l! Od
.. p l ;
i, lh . 'ji '! ! l
'! I!ll llt lll' "l l'll .
j i'; i<: i 4;i ,i -; .. . i-
! : !!I' ' . .
b,' j _ g. 1,4 !? ;il ,j $ [,1 L'- -@ ' " N .
;f ni i! ,.
7
- li
- l. i' 'l al 'l l ii '
;- il *. Moe ll i i l
lI ,.. l! !" O hp I 3i lI l!' :!' I
;! J CRD Chnrgig hssure. ,
ili , L i ll ! !! ;' l li 'I l 1! 3: 'l; ! l' i l;ji - l l i
! Ii n- l l l l lI ll l i i
!'Jaco-(M l !l1,l l l !!! h :$ ll ll /lj"
~
NI] i If l i i
!l'
[
! : il l 1 i l li'll !! @?.!
l ;i ll : l' i i 1 : 4' lIsl li'j ;il i
;[ ,j'.i :
,1 i,
i ; ! ! i 'b"o! i,
't is ,2 1 i f f 'l i ll i dj, i.
l il'j l' i '! ;i "I' ; i F ! l' !l 'o . ; ai ro 3i i i""*' i 1
' ' . , d
,! !! h . l !
!! I -
li {
. ll h! \ ', l l
h /Scn l l
's -! :; j i i !j llii ; ,
l j l I iN! lll l l' l .Il lIi l ~ lj i ['! 'lll 3liNal'lI
.. ' t.
.i %;j liji,!, ji pll- 'r . ;; ' l-ll '
i ;' i, ij jL,:; ni ipti i: i - y]i 1 i.
- l; in.l: l!i 3
i t,: , p ti j __ , 1: ; ll ' gj 'nj iy i ei l ll.l' '_ r ! ! ll:
! i lll f d.l i I d. !i i !! i
", i !- l., '!l . ,p
. .- i , .
f u, .,. :. ,, , gg-- I2.00 ll! j;! ' JI :, ; i hl i,Ip: I' U , l- 3J-123
Jx >
.m_ . __2 . . _ _ . _ _ . , .
..y ,.; 3.,,. m, t.
- -l;1. .t.
- ij:.lil
.i 1.'l i
; pj i i : ij,l'i.'.
l 1I:r l i ," j) i'
'lI i.
- uoo!;.j I ,
n- j n . l;icliie f"]' 1 1
, ~j
,- : s V _<
b! -
.I l' '
., !, .I l l i ,! ' f I
,i!L'i; i
~
+: -ij i
!! ll, !i
,2axf i ' ' l . 4,l. l! ;ii. j.: !.. .t! ,
l !l ;!, !! I'L .'!!j i' li l [' t a
, i i
. i. . 3.r,. .. i t l l J ',
Izam l i i l l j ! !1 i ,.; i i
~
12
; .i . li . , . !
.i .
ri i .: - lI i, pl. j l: f i! :l ' I . ' i .* l i , . [. l 'l ilj , f' h 6 .
!i i ; {i GR R.PH :ll 12'm. i .! .! 4 .ll i , !. j !! ' '
t . e i,
.i ,
- t I
I li I l. l
+ '
.i ;
l . *l ! t
. h #
.l. , l M .
.l +
i t ,
'l f T. 1 , ,1 g- T -}: *7 7 r t
'q
- o. -j i j,a i , ! ,
jl i ijj ;:. l :l: . t '. l i l l l .
.:l l .
r .
^' ~~
[ . l 8 ,1 lfll!{ ki n 1
-l t ii l l l >4 :
12 1 l .
- : 'i
}'
-9 .
i! , i l ,. . Inst. Gas To Ros Nuu28*!' y
,li:
i ci! P-l,i!!T 1!4j = - I l' l'
l~ 'j ']. .l l .i ' l j ' '
[. A A l Il l. l F -(psip ,
- '700 l L!
i _ . :l
!.1 lu-I i l. . .
i i L[ . . ; i i-
.l; g . .
i
- 1. . .
i . : i hr r.,, i. l ;. i ls.[-
,I
. . r i r j . r l
- i i
j
'l, !
! I i
/@ .
,7
' ' l' : !
I , : i l i
}l .
lI t s i - l i i .I : , : l :" 5 lD l . . l
. . t !
i
. lh.d t
.i t
j I
,t_ !
s
' l } l ' ' '
l . ; l , l l ~l 3 I
.i l i
, i
+
1'8 l l . l 1 ! l ! i l ,
- l. i 1- .
i e I i ! li i :( l . 1/ % i I
.i i
t l i {
, . I i ,
p, , . 1 i ; - ' t ! , ' I
, . , i ! '
i - t , ! l : . . [
. i t l. '
i ; l I l
- g , l ,
I ' h-t.3oc l l p.I I l i l i
.'g 3
l . l l l . I g
- j. ' . i .
'. ;ll r- e l , . -
j
/200 .
m
! i t
', l i
_'1!
, ! l 'l I lr
' . i i!
'j t
'f i . l
' 4
!l : i ! I 3J-124 '
M ( f. To f_P ' C l C2'
.I noo Si@ i l '
i i
m
~ ~ ~ '
, ti l r ~I jiitt ?4;Pih ';i i!r n!i "ji jf.j L I I;jl li U ! W IQL!lbt@_
l ll I y i j-l - l-ll:P7 f !ll!! 7jjIl! i[ ll! Jg!lll! t,ri1J [ !)iJg i i; ll ! I: : l i ii l !. [- l r u oo; , p i m i i , j _.i ;
' I i , I IJi i l+
m , [.. . p ,.
. l. ,
a j 1 i 4 ll 1[ i '
- t I
GRR PH- 11 I l- , il l
!! i !
!l 1,! ! -
1 am- i 'jI ; l ,- i u 11. . 1
,l.
I j
- .,~ ,
l ln ,q nl .!!;; i j.i a o i I l
/9 g l: >
- w. . ..L;. . p.. ..g ll l 1 !
Equip Drain Call TanX trod j
-- 1 j
g:,li i i il.
!. 7.r i-g:,!I!j'c I r 3 7 I ;;. !
=
USeN f! l !! !.,I l! l! hi b' !! oi wl! s
.,e il .
f, 'i!! lili I,L .a iig' :hgm W !i I
#D i I ,*. ni j pi : :l l
l il i
! q:p l.
f[ ! ![ 'lil. $ $ bl g Py. Ibi!. L i ci: 4 ; , il l Ic.co
!!i
]
lli ii - -ill@il jj
- ^
i f
,R il i :l l
.' l 'l!i 4
, j !
' i I i, I ' m l
J .. L. hit.
- l. L! S
. I.I' !'@!
llli ! !, I !
'l L l l i i n i i l li l
I ;N: is tsbo,. - -
=
i, l '
! I
.1 Lt -
1
' l l Ii I..l H. i i l ll p !h
- t. '
"m,l -
l I I lu j!ji coo! 11 -
! l li l I I, 7}. $
i
, i ,i
- l. .l!.
i
! lil1 1
' ) {. I
. . . I .l .
1 ik I !I .[.I ! 3 4
,!hk)f$lkil' l 3J-125 b_ _
c lllh il .a o]Nh.lnli
;ii i i jl'
;}
b'bWii;f]!! ,1 ;i ; f a p h: 2- jr.
!h d$IE'II Ir'y, lh 'i 'l ll .' '
.F i j," "
l l I
'i(!.,[ !I !l i!
! l p!i
}'!i [I l d lii gi pi l'
plQ. ! i Q _ 1h0 N. y j '; @. h l
- i 2300 3r l
Il N li h UI!{illid I_ l ! r 3 ' i I. 1 ! I l i i I!I i! ll l I c2co h j! ) g G R R P H - 13 L E - - O F , li h h ll% ., 4 j.! ! 2/00
..L i
"!" !"O]H! _q .
i
). i.1 ll ;! e a
.l Il. >
pl...1I!I l j l 2m, , o . l r mi ;ij . j ;;, If%jj. g
-! i l l- j e o 0 j!l ' i I b .i .! l
~
! {':p!:p M-'%
j' ti if 'lI. i iff L ..
! 'I I
/900 -
I h ! I ! kuip Drain Suge.bbd il lb;d.d
~
]jij lj [,j jji j] !! !
fg. Ih A ll j! I.. D_.i[? N t) M(. -h)!!O!!!O
,i tM"j jh.!dI O.
li
%jlp;! ii
[ ljo 7lf .c l' lh>l; H lijl' fl!l d'i D :i Ivo ; t }, - i'
-f
! < i ,
i , ig i ,- 'd
;iji
' h f"lif"dl
' U. j hn
;i t f Lw ; l ii i! -
[h l ,il ,I ]id; lq iii !! ra m - - i F ! m ; : ; 1 L 1. 1 I 3 .
' 5"
, t ! ! i !; -
i l ll :Ti
..j !
. l . ..
[. . .
'" h i li i ll in u i
n n i 1: u[ p,j i}l!
!lP, l il i
;; i.ll. ;.! 1 1 !.%
Ili l .._
! ! , i 1
9 ll Il l{ l l l ll{l il IO!
] j j i i imod. .f ' ..d_ 1 L
(;h _j.11. 'gl. 9{ 'o ( I j
'N hi i
[I. 1 3J-126
,:til'il ll!m .
il .li i!n all ! !::i piu '. 5:1
e- en.- -
- 7 - -e ,- -
./. La
> o 1 i n,tl ,6 , , .
- l ili!; !
=
_ ll l __ e y,.
' 'i -
u,03 l I ' I ll - I .I._.a i, 23m l n , i ! !! l 3
, 'g i I
. 22m .
l
'l l
l --- i G RR P H - Itt um i
, -2cm
, em-I Fler Drain CollTa.nK koe.1 ,
i ___ _ leg. ( h t) l ll'l ;.li .. lu___ l I 1 l
! l
! l !!! ,em.
.ison.
j _ ma g i, I iscxy I. _ _ ._ _s. . _ _ . L in .i 3J-127 ll I
! il .fh i E- 4l 311 .._slJ1l.!i.1 lil L-
~
f y - m lil)l
; o l l l lb li ii ip i 10 iE '
F i, ip p
~'
'i i- I l f vm t il! , !! [ !!!! iii ; -llI ! @-
p o e
, p ,i .; ,
i i
~
- k. ... .' ,.g . . ..
li , ! ll l l1 . il 23 % , j , , ,
, l , ,. . i 1.
'..d. .. . .
i I ! . l l ll
.' li l l .
*: .l ! '
l !
! i! !i i ll: 'I I
il '
! ! l1 r 1i i
! l l "j( [
j[
' '~
-t GRR RH - 15' j l j j,. ; ,
i ! ' I um
&.j t.. Jg l i l' l d Ml 'i i ii i .
!I
- i. ni i
7 n 1 II I l l lj , .q ,l, l. -
' , Ul:ia j. 4 . . .
i Sl I I I !l,l!l. l pl Qe gl
'9 e f-i.. '
. i.. ....Idi i.I..LI!
Fl= r Drain Sury. tex La.] jl j j ! fe. d
!j _l;,
ll .
< l I
9 Fed I g ,l
! l u
I j m i 1 ii lI 1.: j l
/70 ,
g M"b f.l.7Jf j, L. .!
- I! y!!
t *Mitll ii i i ! i ,i y
' ;L.
(
..g[l.! l
i :
, 'I .
p i!
'J 7.
!i!
ISOO . , ,, , l
}
. p'..
,~ e u 7
i [t 1 , em . l
.j g eoo. , l j ,
l j, j-l?BN!d.4!,ib..LJl !j digh 32-128
t j:ji. j c! ; i i . ;:; i jj i .m a.soo '
.i!,, ri!i
!:,' i;ill
[l;i b y j'I;;
- , "i . i i it !.
i i
. 1, . l
, t ,
l l :.,i . l . l. i l'. .i. I d . i-
.ti il , .
l! I, . l- e.
.i ui it-ll.lI'iii!;;.i: ,oo e
' i. i
,' i .
t .
- l' l
'i. .i . ' .l ! I : f.
L 4 1,' i it; i l:i, ! . L i
.' 2soo i !, j ~l ,, i, 'i
'i i i ' @! b ,o
'ne cur g l ,j ! , t j 'i j ;
. ; ,s. ; ,
n:i 3 ,6 gs .w
..I.I.i, e
,,; ; ,.!, n i l. l.
) .-
,l':i ~i! II
' ~ i .
!i a2.og' .
I i l' !il- l .
- i. ,
.,;ji,,i . i j . t. i. ;
GRRPH-lb t ,
- : , , ,, ' .i
' .f i ; l ,'
i .i! i- (
! 2.t o o l
' I',I l ! :l'I;Ij i i
! l J"
[ , ; ' l l' ' ;( !"I' l
Ii. t l i I
!! l i g!l t
,Ii!l ll' l' t j i . l it ,
lI'{
-l I i '
e',.t,; l ! j i 8( tooo .
' l;
; ' i;[$ l ' I' ! ;l
,' l l'l li ,. , tll ll ;. , ..
l i t. tj.i,.l,;., 5 i.
- i. i ., .,,,
4 - ' ll l , 1900 , .'!' ,i:. .
.'l l '" !,' s, l
.l g .e}
Na C.on.c.e nhtion '
.I'lI !l4 5- '
i! ! !! '
'(
l- [ k ,i l 6}}