ML17309A684

St Lucie Nuclear Power Plant 1992 Emergency Preparedness Evaluated Exercise,920212.

ML17309A684
Person / Time
Site:	Saint Lucie
Issue date:	02/12/1992
From:	FLORIDA POWER & LIGHT CO.
To:
References
NUDOCS 9207270285
Download: ML17309A684 (403)

Text

DOCKET¹05000335 05000389 ACCLLEKAAEu ulb 1 5lDU i LULL LJLLVLVLAO l L~i Lvl w u x v xwiri REGULBTC INFORMATION DISTRIBUTIONSTEM (RIDS)ACCESSION NBR:9207270285 DOC.DATE: 92/02/12 NOTARIZED:

NO FACIL:50-335 St.Lucie Plant, Unit 1, Florida Power&Light Co.50-389 St.Lucie Plant, Unit 2, Florida Power&Light Co.AUTH.NAME AUTHOR AFFILIATION

• Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"St Lucie Nuclear Power Plant 1992 Emergency Preparedness Evaluated Exercise,920212." DISTRIBUTION CODE: IE35D COPIES RECEIVED:LTR Jg ENCL SIZE: TITLE: Emergency Preparedness-Appraisal/Confirmatory A tion Ltr Exercise NOTES: Rep D S RECIPIENT COPIES ID CODE/NAME LTTR ENCL PD2-2 PD INTERNAL.AEOD/DOA/IRB NRR/PMAS/ILRB12 OC FMB.~EG FILE 02 EXTERNAL: NRC PDR RECIPIENT COPIES CL NRR/DREP/PEPB9D NUDOCS-ABSTRACT OE DIR RGN2 FILE 01 NSXC ID CODE/NAME.

LTTR EN NORRISFJ 1 D D D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI D D S TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL ll pt C Vpf+St.Lucie Nuclear Power Plant~~r<,~~1992 EMERGENCY.

PREPAREDNESS.KVAj'ATEDj EXERCESE-'"."-:

lFEBRUARY'll;'1992 I r CO~8?XNTL4EL 9207270285 9202i2 PDR ADOCK 05000335 F PDR FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 TABLE OF CONTENTS

1.0 INTRODUCTION

1.1 FOREWORD

1.2 SCHEDULE OF EVENTS 1.3 PARTICIPATING AGENCIES 1.4 CONTROLLER ORGANIZATION

2.0 SCOPE

OBJECTIVE AND RULES 2.1 SCOPE 2.2 OB JECTIVES 2.3 RULES 3.0 SCENARIO 3.1 NARRATIVE

SUMMARY

3.2 SCENARIO

TIMELINE 3.3 SEQUENCE OF EVENTS TIMELINE 4.0 MESSAGES 4.1 CONTROLLER MESSAGES 4.2 MEDICAL SCENARIO AND MESSAGES 4.3 MINI-SCENARIOS

5.0 PLANT

PARAMETER 5.1 PLANT PARAMETER DATA

SUMMARY

5.2 PLANT

PARAMETER DATA CARDS 5.3 AK'AJNCIATOR MIMIC SHEETS FPL/PSL Rev.2 TOC-i 02/10/92 92 EX TABLE OF CONTENTS (Continued)

6.0 METEOROLOGICAL

PARAMETERS

6.1 METEOROLOGICAL

FORECAST DATA 6.2 METEOROLOGICAL DATA

SUMMARY

6.3 METEOROLOGICAL

DATA CARDS 7.0 RADIOLOGICAL DATA 7.1 REACTOR COOLANT SYSTEM RADIOLOGICAL DATA 7.2 PROCESS RADIATION MONITOR DATA 7.3 AREA RADIATION MONITOR DATA 7.4 ONSITE RADIOLOGICAL DATA 7.5 OFF-SITE RADIOLOGICAL DATA 8.0 MISCELLANEOUS

8.1 EVALUATION

MATERIALS

8.2 REFERENCES

8.3 ACRONYMS

AND ABBREVIATIONS 8 4 SITE LAYOUT DATA FPI/PSL Rev.2 TOC-n 02/10/92 92 EX FLORIDA POWER AND LIGHT COMPANY--ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992

1.0 INTRODUCTION

This Scenario Section contains the following information:

Section 1.1 FOREWORD-A brief introduction to the basis for the exercise and the layout of the scenario data.Section 1.2 SCHEDULE OF EVENTS-Date, time, location, purpose and participants foi the following meetings and critiques for exercise performance and evaluation.

1.2.1 Player

Briefing 1.2.2 Nuclear Regulatory Commission Entrance Briefing 1.2.3 Exercise Scenario Review 1.2.4 Controller/Evaluator Training 1.2.5 Nuclear Regulatory Commission Plant Tour 1.2.6 Exercise 1.2.7 Facility Critiques 1.2.8 Florida Power and Light Controller/Evaluator Critique 1.2.9 Florida Power and Light Management Critique/Nuclear Regulatory Commission Exit Section 1.3 PARTICIPATING AGENCIES-A listing of the agencies from the following areas that will be participating in the performance of the exercise.1.3.1 Utility 1.3,2 Federal 1.3.3 State 1.3.4 County 1.3.5 Volunteer Agencies 1.3.6 Support Organizations Section 1.4 CONTROLLER ORGANIZATION

-A listing of the FPL Controllers and Controller assignments for the exercise.FPIJPSL Rev.3 1.0-1 02/10/92 92 EX FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 1.1 FOREWORD In the interest of assuring that the health and safety of the general public is protected in the event of an accident at St.Lucie Nuclear Plant (PSL), and to meet the requirements of 10 CFR 50, Appendix E, the Florida Power and Light Company (FPL)plans and conducts annual emergency preparedness exercises.

This scenario has been written to conduct the 1992 Annual Evaluated Emergency Preparedness Exercise on February 12, 1992.I\The exercise scenario will be performed during normal working hours (7:30 A.M.to 4:00 P.M.EST)on February 12, 1992 and will involve partial activation and participation by State and Local Government Agencies.The participation will include the activation of Emergency Response Facilities, mobilization of resources and full communications networks activity in response to an escalating emergency condition at St.Lucie Nuclear Plant resulting in a simulated release of radioactivity to the environment.

In accordance with NUREG 0654, FEMA-REP-1, Rev.1, Criteria for Preparanon and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants: "An exercise is an event that tests the integrated capability and a major portion of the basic elements existing within the emergency preparedness plans and organizations." This exercise will include the elements of a Control Room drill, a communication driU, a radiological monitoring drill, a Health Physics drill, a fire and a medical emergency drill.It will require the activation of the Florida Power and Light Emergency Response Organization and Facilities.

It will also include the exercise of the response activities of the State of Florida and Local Government Agencies.The exercise is scheduled to be conducted on Wednesday, February 12, 1992.Exercise participants

(" players")will have no prior knowledge of the exercise scenario.The intent of this exercise is to demonstrate that those individuals that axe assigned responsibilities in a radiological emergency are adequately trained to perform in accordance with emergency preparedness plans and procedures.

FPIJPSL Rev.1 12/12/91 92 EX

1.1 FOREWORD

(Continued)

The exercise will be observed, evaluated and critiqued by representatives of the Nuclear Regulatory Commission (NRC).The exercise wiH be controlled, observed, evaluated and critiqued by an FPL Controller Organization for the St.Lucie Plant portion of the exercise.The exercise will be controlled, observed, evaluated and critiqued by a State and Local Government Controller Organization for the off-site portion of the exercise.Portions of the off-site organization will be observed and evaluated by representatives of the Federal Emergency Management Agency{FEMA).This scenario manual has been prepared to provide the Controller Organization the information and data necessary to conduct the exercise in an efficient and coordinated manner.It contains the following scenario sections: Section 2.0, SCOPE OBJECTIVES AND RULES;describes the exercise scope and objectives and sets forth the guidelines for conducting the exercise to meet those objectives.

In addition, the rules for conduct of the exercise are detailed.3'.D.EDDEN~Ed

'h U 3 I d D f U h id D'he various onsite and off-site Emergency Response Organizations to respond.3'D~ME 4 E;i Id if'M 3 3 h hih utilized to control scenario activities.

Messages will be used to initiate activities and ensure proper progression of the scenario.In addition, this section provides a scenario and messages for conducting the radiological medical emergency drill and mini-scenarios associated with various in-plant response teams.Section 5.0, PLANT PARAMETER; includes information concerning the status of plant parameters and equipment to provide simulated operational data to the exercise operations shift in Unit 1 Control Room.Section 6.0, METE ROLOGICAL PARAMETER; contains postulated meteorological information to be used for the scenario.FPL/PSL Rev.1 1.1-2 12/12l91 92 EX 1.1 FORPVORD{Continued)

Section 7.0, RADIOLOGICAL DATA;contains time-related information concerning simulated radiological conditions at postulated onsite and off-site monitoring locations.

Also included in this section is information concerning primary coolant activity, radiological release data, area radiation monitor readings, process radiation monitor readings and plume data for the teams tracking and monitoring the simulated release of radioactivity.

Section 8.0, MISCELLANEOUS DATA;contains evaluation materials for the FPL Controller/Evaluators, reference data for the plant parameters and a listing of acronyms and abbreviations.

Copies of this manual will be provided to the exercise controllers, evaluators and observers prior to the exercise.NOTE: 7he scenario sequence of events, tt'ming and data are to be maintained confidenrial and not available to the panicipants prior to the exercise Fo.llowing the exercise, copies of this manual should be made available to key exercise participants for their information and review.FPIJPSL Rev.1 1.1-3 12/12/91 92 EX FLORIDA POWER AND LIGHT COMPANY., ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 1.2 SCHEDULE OF EVENTS 1.2.1 Player Briefing Date: February 10, 1992 Time: 2:30 P,M.Location: Plant Assembly Room, NTC, PSL Purpose: Exercise play overview.Review of rules for players.Participants:

Players 1.2.2 Nuclear Regulatory Commission Entrance Briefing Date: Time: Location: Purpose: Partlcl pants: February 11, 1992 10:00 A.M.North Service Building Conference Room, PSL Exercise conduct.Introduction of Key Players, Controllers and'RC evaluators.

Plant Management, Key Players, Controllers and Nuclear Regulatory Commission Evaluation Team.1.2,3 Exercise Scenario Review Date: T1IIle: Location: Purpose: Participants:

February 11, 1992 1:30 to 2:30 P.M.Energy Encounter Auditorium, NTC, PSL Exercise scenario review.Scenario walkthrough.

Scenario data/play clarification.

Controllers and Nuclear Regulatory Commission Evaluation Team.FPL/PSL Rev.2 1.2-1 1/29/92 92 EX

1.2 SCHEDULE

OF EVENTS (Continued)

~~1.2.4 Controller/Evaluator Training Date: Time: Location: Purpose: Participants:

February 11, 1992 2:30 to 3:00 P.M.Energy Encounter Auditorium, NTC, PSL Exercise control aad evaluation overview.Review of rules for controllers.

Florida Power and Light Company Controllers, Controller/Evaluators and Evaluators.

1.2.S Nuclear Regulatory Commission Plant Tour Date: Time: Location: Purpose: Participants:

February 11, 1992 3:00 to 4:00 P.M.St.Lucie Unit 1 Control Room (CR), Technical Support Center (TSC), Operational Support Center (OSC), Emergency Operations Facility (EOF)and Emergency News Center (ENC).Plant and Emergency Respoase Facility (ERF)familiarization.

Nuclear Regulatory Commission Evaluation Team.1.2.6 Exercise~~~Date: Time: Location: Purpose: Participants:

February 12, 1992 Normal%'orkiag Hours (7:30 A.M.-4:00 P.M.)St.Lucie Nuclear Plaat, St.Lucie County, Martin County, Indian River County and Palm Beach County.Demonstration of emergency response capabilities.

All exercise participants.

FPL/PSL Rev.2 1.2-2 1/29/92 92EX

1.2 SCHEDULE

OF EVENTS (Continued)

~~~~~~1.2.7 Facility Critiques Date: February 12, 1992 Time: Exercise Termination Location: All Emergency Response Facilities Purpose: Review and evaluate exercise play.Participants:

All exercise participants

1.2.8 Florida

Power and Light Company Controller/Evaluator Critique Date: Time: Location: Purpose: Participants:

February 13, 1992 8:00 to 11:00 A.M.Plant Assembly Room"B", NTC, PSL Review and evaluate exercise play.Formal exercise critique.Collect and prepare final critique comments.A'll Florida Power and Light Company Controllers, Controller/Evaluators and Evaluators (Note: mandatory for all Lead Controllers).

1.2.9 Florida

Power and Light Company Management Critique/Nuclear Regulatory Commission Exit Date: Time: Location: Purpose." Participants:

February 14, 1992 9:00 A.M.g,'no Plant Assembly Room"A", NTC, PSL Presentation of major critique items to Plant Management, Nuclear Regulatory Commission preliminary Exercise findings.Plant Management, Key Players, Lead Controllers and Nuclear Regulatory Commission Evaluators..

FPL/PSL Rev.2 1.2-3 1/29/92 92 EX FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 1.3 PARTICIPATING AGENCIES 1.3.1 Utility Florida Power and Light Company (FPL)St.Lucie Nuclear Plant (PSL)1.3.2 Federal United States Nuclear Regulatory Commission (NRC), Region II-Evaluation Team 1.3.3 StateState of Florida Division of Emergency Management (DEM)State of Florida Department of Health and Rehabilitative Services (DHRS), Office of Radiation Control 1.3.4 County Martin County St.Lucie County Indian River County Palm Beach County 1.3.5 Volunteer Agencies American Red Cross (ARC)1.3.6 Support Organizations Martin Memorial Hospital FPL/PSL Rev.2 1.3-1 1/29/92 92EX FLORIDA POWER AND LIGHT COMPANY-ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 1.4 CONTROLLER ORGANIZATION Exercise Controller:

Onsite Lead Controller:

Off-Site Lead Controller.

Control Room: Rick Walker Rick Walker Don Mothena Lead Controller.

NPS/ANPS/Messages:

Operators/Messages:

Operators/Messages:

Data: HP'lant Operators/SNPO:

Technical Su ort Center: Roger Walker Roger Walker Dave Brown Dennis Borgman Tom Ashley Lang Jacobus Ray Voss Lead: EC/Communications:

Dose Assessment/Chemistry:

HP: ERDADS: Sergio Valdes Sergio Valdes Tom Ware J.R.Smith Mitch Williford FPL/PSL Rev.0 1.4-1 02/10/92 92 EX L4 CONTROLLER ORGANIZATION (Continued) 0 rational Su ort Center.Lead: Repair Team: Repair Team: Fire Team: First Aid/Decon Team: HP: HP{Medical):

Chemistry:

Field Monitoring Team: Field Monitoring Team: Field Monitoring Team: Thorn Coste Russell Williams Roger Thomas Bob McDaniel Joel Burgess Ray McCullers Joel Burgess Joel Burgess~Sec urit: Security Team: Security Team: Dick Czarnecki Peter Plantz Emer enc rations Facili Lead: EOF/EC/State/County:

EOF/HP/Dose Assessment:

EOF/Medical/County EOC: Communications/Engineering; Recovery Manager/staff:

EOF/ENC: Greg Casto Greg Casto Don Mothena Dean Miller Phil Green Dave Sager Fitch King Emer enc News Center/Mock Media: Mock Media: Mock Media: Mock Media: Mock Media: Mock Media: Roger Scott Genevieve Blair Kathleen Wisniewski Jo Magennis Phyllis Cordover Simulated Nuclear Re ulato Commission 0 erations Center: NRCOC Simulation:

John Zudans FPUPSL Rev.0 1.4-2 02/10/92 92 EX FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 2.0 SCOPE OBJECTIVES AND RULES This section contains the following information:

Section 2.1 SCOPE-Describes the overall content and intended activities of the exercise.Details the anticipated responses and the emergency facilities to be activated.

~k Section 2.2 OBJECTIVES

-Describes the objectives that will be evaluated for determination of satisfactory performance during the course of the Plume Exposure Pathway portion of the exercise.Section 2.3 RULES-Describes the rules for Participants, Controllers, Evaluators and Observers which will be applied to the conduct of the exercise.FPIJPSL Kev.1 2.0-1 01/30/92 92EX CONROENTNL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 2.1SCOPE To assure that the health and safety of the general public is protected in the event of an accident at St.Lucie Nuclear Plant (PSL), it is necessary for the Florida Power and Light Company (FPL)to conduct an annual emergency preparedness exercise.This is the 1992 Evaluated Exercise at St.Lucie Nuclear Plant.'his exercise'involves mobilization'of FPL;State of Florida and Local Government Agency personnel and resources to respond to a simulated accident scenario.The exercise will be evaluated onsite by the Nuclear Regulatory Commission (NRC).An FPL Controller/Evaluator organization will contml, observe, evaluate and critique the PSL portion of the exercise so that the emergency response capabilities of the utility may be assessed.A State of Florida and Local Government Agency Controller/Evaluator organization will control, observe, evaluate and critique the off-site portion of the exercise so that the emergency response capabilities of the off-site agencies may be assessed.Representatives of the Federal Emergency Management Agency (FEMA)will be observing and evaluating portions of the off-site organization.

The exercise will postulate conditions necessitating a declaration.

of a NOTIFICATION OF UNUSUAL EVENT, continue to escalate through an ALERT, a SITE AREA EMERGENCY and eventually result in the declaration of a GENERAL EMERGENCY.

Due to the compressed timeline of the exercise, some portions of the FPL Emergency Response Organization may be prepositioned.

All onsite Emergency Response Facilities will be activated in accordance with simulated conditions and appropriate emergency response procedures for the exercise.Exercise participants

(" players")will not have any prior knowledge of the simulated accident events, operational sequence, radiological effiuents or weather conditions.

A radiological medical emergency will be integrated into the operational and radiological portion of the exercise scenario in order to evaluate the ability of the PSL plant staff to effectively respond to a contaminated/injured individual.

The medical emergency will also test the ability of the designated hospital, hhtrtin Memorial Hospital, to treat a contaminated/injuted patient.State and Local Government Agencies will participate partially in the off-site portion of the exercise.FPIJPSL Rev.1 CONFlOENTfAL 2.1-1 01/30/92 92EX CONRDENTIAL

2.1 SCOPE

(Continuedi In addition, the exercise incorporates the following:

Radiological Monitoring Drill-both onsite and off-site teams will be dispatched during the exercise to obtain required air samples and measurements associated with a simulated off-site release of radioactivity and communicate these results to the appropriate Emergency Response Facility (ERF).(Field monitoring team protective clothing and respiratory protection will be simulated'in the field.)Health Physics Drill-involves the response to and analysis of simulated elevated activity-airborne or liquid samples, radiation exposure control, emergency dosimetry and the useof protective equipment onsi'te.Communications Drill-Actual usage and demonstration of the integrity of emergency response communications links and equipment.

Fire Drill-a demonstration of the onsite Fire Team to respond to and extinguish a simulated fire in emergency electrical panels in the Unit 1 Reactor Auxiliary Building (RAB).Medical Emergency Drill-a demonstration of the response to a simulated medical emergency situation involving radiological considerations including the packaging and transport of the simulated injured person to the designated off-site treatment facility.The preceding sub-drills are incorporated into the exercise scenario and will be demonstrated concurrently in the course of the exercise.The overall intent of the exercise is to demonstrate that the FPL staff assigned responsibilities in an emergency situation are adequately trained to perform in accordance with emergency preparedness plans and procedures.

FPUPSL Rev.1 CONRDENTIAL 2.1-2 01/30/92 92EX FLORIDA POWER AND LIGHT COMPANY ST.LUCIE PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 2.2 OBJECTIVES The St.Lucie Plant (PSL)1992 emergency preparedness evaluated exercise objectives are based upon Nuclear Regulatory Commission requirements provided in 10 CFR 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilittes.

Additional guidance provided in NUREG-0654, FEMA-REP-1, Revision 1, Criteria for Preparation and Evaluation of Radiological-Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, was utilized in developing the objectives.

The exercise will be conducted and evaluated using a realistic basis for activities.

Scenario events will escalate to core damage and subsequent release of radioactive material to the environment.

The following objectives for the exercise are consistent with the aforementioned documents:

A.Accident ssment and Classificatio 1.Demonstrate the ability to identify initiating conditions, determine Emergency Action Level (EAL)parameters and correctly classify the emergency throughout the exercise.B.~Notificatio Demonstrate the ability to alert, notify and mobilize Florida Power and Light (FPL)emergency response personneL 2.Demonstrate the capability to promptly notify the U.S.Nuclear Regulatory Commission (NRC), State and Local Authorities of an emergency declaration or change in emergency classification.

3.Demonstrate appropriate procedures for both initial and follow-up notifications.

4.Demonstrate the ability to provide follow-up information to State, Local and Federal Authorities.

FPIJPSL Rev.2 2.2-1 01/30/92 92EX

2.2 OBJECIYVES

(Continued)

B.Notification (Continued) 5.Demonstrate the ability to provide accurate and timely information to State, Local and Federal Authorities concerning radioactive releases in progress.C.Emer enc Res onse Demonstrate staffing and activation of Emergency Response Facilities (ERF).2.Demonstrate planning for 24-hour per day emergency response capabilities, 3.Demonstrate the timely activation of the Technical Support Center (TSC)and Operational Support Center (OSC).4.Demonstrate the functional and operational adequacy of the TSC, OSC, Emergency Operations Facility (EOF)and Emergency News Center (ENC).5.Demonstrate the adequacy, operability and effective use of designated emergency response equipment.

6.Demonstrate the adequacy, operability and effective use of emergency communications equipment.

7.Demonstrate the ability of each emergency response facility manager to maintain command and control over the emergency response activities conducted within the facility throughout the exercise.8.Demonstrate the ability of each facility manager to periodically inform facility personnel of the status of the emergency situation and plant conditions.

9.Demonstrate the precise and clear transfer of Emergency Coordinator responsibilities from the Nuclear Plant Supervisor to designated senior plant management and transfer of Emergency Coordinator responsibilities to the Recovery Manager.10.Demonstrate the ability to promptly and accurately transfer information between Emergency Response Facilities.

FPL/PSL Rev.2 2.2-2 01/30/92 92EX 2,2 OBJECTIVES (Continued)

C, Emer enc Res onse (Continued) 11.Demonstrate the ability of the TSC and OSC to coordinate the deployment of emergency teams.12.Demonstrate the availability of qualified personnel and timely organization of reentry teams to assist in accident assessment and mitigation.

13.Demonstrate the capability for development of Protective Action Recommendations (PAR)for the general public within the 10 Mile Emergency Planning Zone (EPZ).14.Demonstrate that PARs can be communicated to State and Local Authorities within the regulatory time constraints.

D.Radi lo ical ment and Contro Demonstrate the coordinated gathering of radiological and non-radiological (meteorological) data necessary for emergency response, including collection and analysis of in-plant surveys and samples.2.Demonstrate the capability to perform dose assessment.

3.Demonstrate the ability to compare onsite and off-site dose projections to Protective Action Guidelines (PAGs)md determine and recommend the appropriate protective actions.4.Demonstrate the ability to provide dosimetry to emergency response personnel as required and adequately track personnel exposure.5.Demonstrate the capability for onsite contamination control.6.Demonstrate the ability to adequately control radiation exposure to onsite emergency workers, as appropriate to radiological conditions.

7.Demonstrate the decision making process for authorizing emergency workers to receive radiation doses in excess of St.Lucie Plant administrative limits, as appropriate.

FPUPSL Rev.2 2.2-3 01/30/92 92EX 2,2 OBJECI'IVES (Continued)

D.Radiolo ical Assessment and Control (Continued) 8.Demonstrate the ability to control and coordinate the flow of information regarding off-site radiological consequences between radiological assessment personnel stationed at the TSC and EOF.9.Demonstrate the ability of field monitoring teams to respond to and analyze an airborne radiological release through direct radiation measurements in the environment.

10.Demonstrate the collection and analysis of air samples and provisions for effective communications and recordkeeping.

11.Demonstrate the ability to control and coordinate the flow of information regarding off-site radiological consequences with State radiological assessment personnel in the EOF.E.Pu lic Informati n Pro ram 1.Demonstrate the timely and accurate response to news inquiries.

2.Demonstrate the ability to brief the media in a clear, accurate and timely manner.3.Demonstrate the ability to coordinate the preparation, review and release of public information with Federal (NRC), State and Local Government Agencies as appropriate.

4.Demonstrate the ability to establish and operate rumor control.F.M dical Emer nc Demonstrate the ability to respond to a radiation medical emergency in a timely manner.2.Demonstrate the capability of the First Aid and Personnel Decontamination Team to respond to a medical emergency, administer first aid and survey for contamination on a simulated contaminated injured individual.

3.Demonstrate the capability to arrange for and obtain transportation and off-site medical support for a radiological accident victim.FPL/PSL Rev.2 2.2A 0 1/30/92 92EX

2.2 OBJECTIVES

(Continued)

F.~MCh E E tC E)4, Demonstrate the ability of Martin Memorial Hospital personnel to treat an injured and/or contaminated patient.5.Demonstrate the administrative means to document and monitor status of a medical emergency victim.G.~F'1.Demonstrate the ability of the Fire Brigade to respond to a simulated fire emergency in a timely and appropriate manner.H.Evaluation 1.Demonstrate ability to conduct a post-exercise.

critique to determine areas requiring improvement or corrective action.L~Exem tion Areas of the PSL Emergency Plan that will~NT be demonstrated during this exercise include: 1.Site evacuation of nonessential personnel 2.Onsite personnel accountability 3.Actual shift turnover (long term shift assignments will be demonstrated by rosters).4.Actual drawing of a sample utilizing the Post-Accident Sampling System (PASS)FPL/PSL Rev.2 2.2-5 01/30/92 92EX

FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 2.3 RULES The following general rules have been established to help delineate the extent of play for participants to meet exercise objectives.

Five groups of personnel may be in attendance and will function as described bel~'dr Rlg low: A.PLAYERS: Managers, supervisors, operators, health physics technicians, chemistry technicians, maintenance personnel, etc., who have been assigned a"Participant" role during the simulated emergency.

These persons serve to take necessary actions to mitigate, terminate, correct and/or recover from the simulated events.B.CLINRRRLLRRR II d Ig ddl'd P RLIgd C p I (FPL)and contracted personnel who serve an active role during the exercise by providing scenario data to participants.

CONTROLLERS also serve to initiate certain actions (i.e.: contingency messages)in order to assure continuity of the events described in the exercise scenario, CONTROLLERS are the only personnel who will provide information to the PLAYERS.CONTROLLERS will also serve as FPL EVALUATORS.

C.EVALUATORS:

FEDERAL EVALUATORS from the Nuclear Regulatory Commission (NRC)will be evaluating the performance of FPL participants in accordance with the exercise scenario objectives.

FPL EVALUATORS and CONTROLLERS designated by FPL will provide documentation and assessment of the exercise activities for the purpose of the internal selferitique.

EVALUATORS serve a passive function (when not a Controller/Evaluator) and will only note actions taken by PLAYERS.These personnel may have specific areas to consider in their evaluation.

EVALUATORS may ask questions to clarif'y actions taken or procedural concerns but should not interfere with the flow of events.FPUPSL Rev.2 2.3-1 01/30/92 92EX

2.3 RULES

iContinued)

D.OBSERVERS:

Personnel who serve no evaluation, control or participatory function in the exercise.These people may be from Turkey Point Nuclear Plant (PTN), the FPL Miami General Office, Juno Beach (JNO)office or another utility, OBSERVERS should not interfere with EVALUATORS, and particularly, PLAYERS.Questions from OBSERVERS should be directed to a CONTROLLER.

E.VISITORS: Personnel who serve no function related to the exercise activities.

These people only enter a facility for a short time to perform non-exercise related functions.

This group of people may be from PTN.JNO, the FPL Miami General Office or other organizations.

Visitors shall not interfere with PLAYERS, CONTROLLERS, EVALUATORS or OBSERVERS.

Identification of the different groups of personnel will be accomplished by the use of badges.These identification badges are worn in addition to normal security badging and will be provided to all participants'during the meetings prior to the exercise.Badges are to be marked with an erasable marker to show the participant's name (and position filled, if a Player).The four groups are identified by the following colors: PLAYERS CONTROLLERS EVALUATORS OBSERVERS Green Pink Blue White 2.Personnel will be assigned as controllers at all functional areas to monitor and control exercise activities.

In addition, they will accompany radiological monitoring teams, plant health physics personnel, maintenance, repair and rescue teams.3.Message forms will be the mechanisms used to initiate, orchestrate, modify and complete the events comprising the overall scenario.Controllers will use the message forms to initiate scenario events and trigger responses from the involved personnel.

Some messages which deal with plant operations activities are used only in the Unit Control Room simulation of operations.

4, Each controller will have time-related plant and radiological parameters for the exercise scenario.This information will be issued when necessary or upon request from the appropriate players.FPL/PSL Rev.2 2.3-2 01/30/92 92EX

5.2.3 RULES

(Condnned)

Controllers will NOT provide information to the participants regarding scenario development or resolution of problem areas encountered.

Participants are expected to obtain information through their organizations and exercise their judgement in determining correct response actions and problem resolution.

6.Scenario data will be provided in at least 15-minute intervals.

Data for the time period between the updates and any future times are not available to the participants.

Participants should request from the controllers data which they feel is necessary for the performance of their function.7.Some participants may insist that certain parts of the scenario are unrealistic.

The controllers have the authority with the approval from the Exercise Controller to clarify any questions regarding scenario content.In some cases, it may be necessary to exercise"controller's prerogative" of countermanding participant actions to preserve the continuity and objectives of the exercise.Participants must accept the controllers word as final and proceed.Inappropriate actions can delay or speed-up the entire scenario timeline and impact other groups.8.Scenario events are hypotheticaL Any portions of the scenario depicting plant system operational transients are simulated events.NO scenario actions shall involve operation of plant systems or affect generation capability.

To help delineate such actions, all exercise scenario messages must be preceded and followed by the words: "THIS IS A DRILL"!9.Postulated accident conditions will result in a simulated radiological effluent release which may necessitate the consideration of protective actions for the general public.10.All FPL onsite and off-site emergency response facilities will be manned and perform their prescribed functions as appropriate to the development of the exercise scenario.Participation of FPL onsite personnel directly involved in responding to an emergency should be camed out to the extent necessary to meet the scope and objectives, including the deployment of radiological monitoring teams, emergency repair/damage control teams and other emergency workers.All actions are to be played out, as much as possible, in accordance with the emergency plan and procedures as if it were an actual emergency.

Actions should be identified to the controller for guidance as to whether to play them out or simulate them.FPL/PSL Rev.2 2.3-3 01/30/92 92EX

2.3 RULES

(Continued) 12.Certain events and activities may be simulated rather than utilize the actual deployment of the resources.

Simulation

-Involves identification and utilization of requirements and procedures short of actual deployment.

Actual-Involves movement of resources and/or physical implementation for this exercise.13.Exercise participants, controllers, evaluators and observers should not take any action which would preclude maintaining emergency readiness of the organization and community.

If an actual situation occurs thai requires a group to teiminate its participation in the exercise, they should notify the Exercise Controller.

All messages concerning actual events must be preceded with"THIS IS NOT I REPEAT, NOT A DRILL MESSAGE".In the event of an actual situation during the exercise or other unforeseen contingencies, contact: Exerdse Controller, pager no.340-9327.14.Communications between all exercise participants shal1 occur in accordance with the procedures of applicable emergency response plans.All communications, including initial telephone conversations, radio transmittals and loudspeaker announcements must begin and end with"THIS IS A DRILL"!15.Intentional violation of laws is not permitted during the exercise.Participants, controllers, evaluators and observers should comply with all federal, state and local legal restrictions.

All local traffic laws, specifically speed limits, shall be observed.16.Exercise participants, controllers, evaluators and observers should avoid the endangering of public and private property.17.It is not the intent to inconvenience or alarm the public during the conduct of the exercise.All communications, articularl in the ublic relations area must begin and end with"THIS IS A DRILL"!18.At the appropriate point in the exercise scenario, the Exercise Controller will initiate termination of the scenario.The Exercise Controller will ensure notification of off-site points of contact to advise them that the exercise is being terminated.

FPL/PSL Rev.2 2.3-4 01/30/92 92 EX

2.3 RULES

(Condoned) 19.All exercise participants will take part in a critique session in their emergency response facility immediately upon termination of exercise activities.

20.All Evaluators and Controller/Evaluators should complete their evaluation materials and provide them to the Emergency Preparedness Department at the FPL Controller/Evaluator Critique following the exercise.I~tP~~1~I t~II~"pl 4 t\FPL/PSL Rev.2 2.3-5 01/30/92 92EX

CONRDENTlAt.

FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS

~EVALUATED EXERCISE FEBRUARY 12, 1992 3.0 SCENARIO This section contains the following information:

Section 3.1 Section 3.2 Section 3.3 4 NARRATIVE

SUMMARY

-Describes in detail activities and events which occur during the scenario along with appropriate and anticipated corrective actions.SCENARIO TIMELINE-Provides a relationship between scenario events, real time and scenario time.SEQUENCE OF EVENTS TIMELINE-Provides a relationship between scenario activities and expected actions from the Emergency Response Organizations (ERO)s.FPIJPSL Rev.1 CONRDENTNl 3.0-1 01/30/92 92EX CONFlOENTIAI.

FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 3.1 NARRATIVE

SUMMARY

3.1.1 Brief

Narrative The scenario begins with a fire occurring in the"1BS" 480 Volt Motor Control Center (MCC)in the Unit 1"B" Switchgear Room (Unit 1 Reactor Auxiliary Building fRAB}).As a result of the fire uncontrolled for greater than 10 minutes, a NOTIFICATION of UNUSUAL EVENT (NUE)should be declared.Due to inoperative equipment and valves associated with the"1BS" MCC, operators begin a reactor power reduction.

Difficulty in extinguishing the fire prompts a request for off-site fire assistance (simulated) which should produce a declaration of ALERT.A radwaste worker in the Unit 1 Drumming Room is injured and contaminated.

The severity of the injury requires transport to the off-site medical treatment facility (Martin Memorial Hospital).

A flexible bellows assembly in the Unit 1 condensate pump suction header fails, dumping condenser hotwell contents and breaking vacuum in the main condenser.

The reactor and turbine are tripped and steam is dumped through the Atmospheric Dump Valves (ADVs).Heat damage to the"1B3" 4160 Volt Switchgear caused by the previous fire in the adjacent"1BS" 480 V.MCC causes a loss of the"1B3" 4160 V.Switchgear.

Reduced output on the"1C" Auxiliary Feed%Pater (AFW)Pump causes a decreasing Steam Generator (S/G)level.The"1C" AFW Pump fails, resulting in total loss of feed to the S/Gs.When operators establish once-through cooling on the one operable High Pressure Safety Injection (HPSI)pump and Power Operated Relief Valve (PORV), a SITE AREA EMERGENCY (SAE)should be declared.Failure of the HPSI pump results in loss of once-through cooling and should produce a declaration of GENERAL EMERGENCY (GE).The lack of Reactor Coolant System (RCS)feed and steaming down through the PORV uncovers the core and causes fuel damage.Recovery of the"1A" AFW pump allows restoration of feed to the"1A" S/G.The addition of cold feed water to the dry generator causes tube ruptures and a release of contaminated steam to the environment through a failed open ADV.RCS reflood, cooldown, feed up of the S/G and closure of the ADV isolation valve terminate and contain the radioactive release, FPUPSL Rev.4 CONROENTIAL 3.1-1 01/30/92 92 EX CONRDENTIAL

3.1 NARRATIVE

SU1NM'ARY (Continued)

3.1.2 Detailed

Narrative Initial conditions establish Unit 1 operating at 100%power, in the middle of core life.Power history has been full power operation for the last 180 days.Unit 2 is in day 12 of a 30 day scheduled maintenance outage.The"IA" Auxiliary Feed Water (AFW)Pump is tagged-out for motor bearing replacement.

The pump motor has been lifted from the baseplate and the end bells and bearing housings disassembled.

The"1A" AFW Pump was taken out of service at 1600 on February 11, 1992, starting the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Limiting Condition for Operation (LCO)clock at that time, and is anticipated to be restored to service in another 6 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.Demand on the system is moderate with an anticipated peak of 12,000 MWe.Service area conditions are noimal.Weather has been sunny and mild for the lasts,eek with occasional late afternoon and evening showers.Forecast is for*partly cloudy skies, temperatuies'n the upper 80's and occasional showers for the next four days.Current temperature is 78'ith winds from the East at 4-8 mph.At 0800, fire alarms at Delta 1.07.01 and 1.07.02 (Unit 1 Zone¹7 A&B)occur.Trouble alarms occur for the"1B5" 480 Volt Motor Control Center (MCC).The"1B5" MCC trips.The Fire Team responds and fights the fire.The Senior Nuclear Plant Operator (SNPO)is dispatched to investigate the alarms.Within minutes, the SNPO reports verification of fire and smoke in the Unit 1 Reactor Auxiliary Building (RAB)43'levation in the"B" Switchgear Room.The Fire Team responds and sets up to fight the fire in the"1B5" MCC.Due to a lack of fixed fire suppression and fire burning in the overhead cable trays uncontrolled for greater than 10 minutes, a NOTIFICATION of UNUSUAL EVENT (NUE)should be declared in accordance with Emergency Plan Implementing Procedure (EPIP)No.3100022E, Classificarion of Emergencies, EVENT/CLASS UNUSUAL EVENT 3.FIRE Uncontrolled fire within the lant lastin more than~1minutey, Operators should have evaluated the consequences to the electrical system and operational status utilizing Off-Normal Operating Procedure (ONOP)1-0910054, Loss of a Safery Related A.C.Bus, and begun a down-power of the reactor utilizing boric acid feed to the Volume Control Tank (VCT).FPUPSL Rev.4 CONFlDENTlAL 3.1-2 01/30/92 92EX CONFIDENTIAL 3.1-NARRATIVE SMmARY (Continued)

The Fire Team submits a request for off-site fire assistance (to be simulated).

This should result in a declaration of ALERT in accordance with Emergency Plan Implementing Procedure (EPIP)No.3100022E, Classijication of Eniergencies, EVENT/CLASS ALERT 3.FIRE~~>>g+i I>>>>,~ti Uncontrolled fire 1.Potentially affecting safety systems.AND~~2.Requiring off-site support in the opinion of the NPS/EC.A radwaste operator (simulated medical emergency volunteer victim)working in the Unit 1 Radwaste Building Drumming Room is injured severely when a B25 box lid falls on the victim.A coworker (Medical Controller) carries the injured person out of the Drumming Room and makes a report to the Unit 1 Control Room.The First-Aid Decon Team is dispatched to the scene.The injured individual is verified to be contaminated and the severity of the injury requires rapid transport to the off-site treatment facility (Martin Memorial Hospital).(Due to the levels of simulated contamination and the life-threatening nature of the simulated injuries, the patient wiH be transferred to the off-site facility still simulated to be contaminated.)

The ambulance is ordered, the victim is given initial care and prepared for tramport.The simulated arrival of the off-site fire assistance team will provide the final step to extinguish the fire in the"1BS" 480 V.MCC.Fire cleanup and appraisal of damages in the"B" Switchgear Room will begin.A sudden failure of a flex joint in the condensate header upstream of the pumps in Unit 1 results in the rapid loss of main condenser hotwell inventory and vacuum.Hot water fills the pump pit area under the Unit 1 Turbine Deck.The turbine and reactor are tripped due to rapidly decreasing vacuum.The condensate and main feed pumps trip on low suction pressure.%hen the Auxiliary Feed Actuation Signal (AFAS)occurs, the"1B" AFW pump autostarts.

Heat damage as a result of the previous fire in the adjacent"1B5" 480 V.MCC causes the"1B3" 4160 Volt switchgear to fail.The instabilities in affected control relays that tripped the"1B3" switchgear prevent it from being reenergized.

Loss of the"1B3" switchgear also causes the temporary loss of the"1AB" 4160 Volt and 480 Volt loadcenters until they are realigned to the"A" side 4160 Volt and'480 Volt supplies.%hen the"lC" APV pump is started, the controller only brings the pump turbine up to 3000 rpm, providing only about 100 gpm of feed to the S/Gs.Operators stabilize the plant and begin cooling down on the S/G Atmospheric Dump Valves (ADV)s.The injured person should have been loaded and transported off site in the ambulance by this time: FPIJPSL Rev.4 CONFIDENTlAL 3.1-3 01/30/92 92EX CONROENTIAL

SUMMARY

(Continued)

The"1C" AFW pump has been losing oil'since starting up and the turbine seizes.The lack of feed to the S/Gs being utilized for heat rejection begins to steam down S/G level.When the S/G levels reach 15%wide range, operators begin once-through cooling of the RCS utilizing the one operable High Pressure Safety Injection (HPSI)Pump and the one available Power Operated Relief Valve (PORV).Upon the opening of the PORV, a SITE AREA EMERGENCY (SAE)should be declared in accordance with Emergency Plan Implementing Procedure (EPIP)No.3100022E, Classification of Emergencies, EVENT/CLASS SITE AREA EMERGENCY 1.C.LOSS OF SECONDARY'COOLANT TLOF with once-throu h coolin initiated 2.No main or auxiliary feedwater fiow available.

PORV(s)have been opened to facilitate core heat removal.The one operating HPSI Pump bearings fail and the pump locks up, stopping once-through cooling.RCS temperature and pressure increase as a result of the lack of heat removal.The open PORV continues to blow down RCS inventory to the containment through the Quench Tank.A GENERAL EMERGENCY (GE)should be declared based upon Total Loss of Feed (TLOF)followed by failure of once-through cooling in accordance with Emergency Plan Implementing Procedure (EPIP)No.3100022E, Cktsstfication of Emergencies, EVENT/CLASS 6.A.IN REA ED AWARENE OF POTENTIAL CORE MELT GENERAL EMERGENCY Emer nc oordina or's'ment that lant condition exist that make rele of lar e amounts of radioactivi in a hort riod a ar ossible or~tikel.(Any core melt situstton.)

3.Total loss of feedwater followed by failure of once-through cooling (ECCS), to adequately cool the core.Protective Action Recommendations (PARs)should be generated based upon plant conditions.

FPL/PSL Rev.4 CON RDENTlAL 3.1-4 01/30/92 92EX CONRDENTlAL 3.1 NARE&TIVE

SUMMARY

(Continued)

The lack of sufficient heat removal and feed to the RCS causes reactor vessel level to decrease until the core is uncovered as indicated on the Reactor Vessel Level Monitoring System (RVLMS).Uncooled and uncovered fuel begins to release gas gap activity and fuel overheat begins to cause zirconium-water reaction, liberating hydrogen.Containment High Range Radiation Monitors (CHRRMs)increase sharply.When CHRRM readings have exceeded 4.2X19'/hr, PARs should be upgraded based upon plant conditions.

The"1A" AFW pump is reassembled and restored for feed to the S/Gs.The failure of feed valve controllers caused by the previous electrical casualties necessitates feeding of the"1A" S/G.When the cold auxiliary feedwater is admitted to the hot and dry"IA" S/G, approximately 50 U-tubes rupture.RCS equalizes into the S/G and the release of contaminated steam begins through the open ADV on the"1A" S/G.(NOTE if operators attempt to close the ADV,, the ADV controller has failed"as is" and may not be operated remotely.)

The current system availability and the need to remove heat from the RCS necessitates steaming the damaged S/G to the atmosphere and releasing radioactive materiaL The flooding up of the affected S/G with AFW covers the ruptured tubes, dilutes and partitions the release.Release radiation readings decline.Cool down and depressurization of the RCS reduces the primary to secondary flow.Repair and recovery team activities continue to stabilize the plant.Field monitoring teams track and monitor the release from the S/G ADV.Cool down and the establishment of long-tenn cooling allow the closure of the affected S/G ADV isolation valve, terminating the release.Field monitoring activities continue on the plume in the environment.

Repair and recovery teams and discussions are continuing in the Emergency Response Facilities.

The exercise is terminated.

FPL/PSL Rev.4 CON FlDENTIAL 3.1-5 01/30/92 92EX CONRDENTIAl FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 TME 3,2 SCENARIO TIMELINE EVENT 0730 Initial conditions establish Unit 1 operating at 100%power, in the middle of core life.Power history has been full power operation for the last 180,days, Unit 2.is in day,.12.,of a 30 day scheduled maintenance outage.The"1A" Auxiliary Feed Water (AFW)Pump was placed on a clearance for motor bearing replacement at 1600 on February 11, 1992, starting the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Limiting Condition for Operation (LCO)clock at that time.Demand on the system is moderate with an anticipated peak of 12,000 MWe.Service area conditions are normal.Weather has been sunny and mild for the last week with occasional late afternoon and evening showers.Forecast is for partly cloudy skies, temperatures in the upper 80's and occasional showers for the next four days.Current temperature is 78'ith winds from the East at 4-8 mph.0800 A fire occurs in the"B" Switchgear Room of the Unit 1 Reactor Auxiliary Building (RAB)in the"1B5" 480 Volt Motor Control Center (MCC).0805 Senior Nuclear Plant Operator (SNPO)verifies fire.Fire alarm is sounded and Fire Team is dispatched.

0815 0830 Fire fighting efforts are hindered by the lack of fixed suppression system and difficulties experienced by the Fire Team, The fire burns greater than 10 minutes, affecting safety equipment.

Due to difficulties experienced in fighting the fire, a request for off-site fire assistance (simulated) is made by the Fire Team.A NOTIFICATION OF UNUSUAL EVENT should be declared.FPIJPSL Rev.5 CONRDENTIAL 3.2-1 02/10/92 92 EX CONRDENTNL 3.2..SCENARIO TIMELINE (Continued)

TIME EVENT 0835 Operators start a down power by injecting boric acid into the Volume Control Tank (VCT).0840 The off-site fire assistance is simulated to arrive at the East Gate by Security Controller message.0845 An AL,ERT should be declared based upon the request (simulated) for off-site fire assistance

.0845 (Approx.)Upon arrival and setup (simulated) of the off-site fire assistance team, the fire is out.0900 The off-site fire assistance team is simulated to have departed site by Security Controller message.0905 A person is reported to be injured in the Unit 1 RAB Drumming Room.a Player or Controller makes notification of the injury.0910 (Approx.)The First-Aid Decon team is dispatched to the injury scene.The injured person is examined by the First-Aid Decon Team, triage and radiological assessment is performed.

Off-site medical assistance is required and the individual is contaminated.

Off-site medical facility is informed, ambulance ordered and injured individual prepared for movement to the off-site treatment facility.0930 A fiexible joint fails on the suction header of the Unit 1 condensate pumps resulting in a large leak of condensate.

A rapid loss of condenser vacuum caused by the damaged suction header and loss of hotwell inventory causes the operators to trip the turbine and reactor.Both main feed pumps trip on low suction, The"1B" AFW Pump autostarts on the Auxiliary Feed Actuation Signal (AFAS)and heat damage causes the"1B3" 4160 Volt switchgear to fault.The"1B3" 4160 Volt switchgear trips as a result of the previous fire in the adjacent"1B5" 480 V.MCC.The"1C" AFW Pump controller only brings the turbine up to reduced rpm, producing minimal feed to the Steam Generators (S/G)s.The severely reduced feed to the operating S/Gs begins to steam down the S/Gs.FPL/PSL Rev.5 CONFIDENTNL 3.2-2 02/10/92 92 EX CONFlDENTlAt.

TIME 3.2.$CENARIO TIMELINE (Continued)

EVENT 0945{Approx.)The injured individual has been transported to the off-site medical facility{Martin Memorial Hospital)by ambulance.

0945 The operators establish cool-down on the Steam Generator Atmospheric Dump Valves (ADV)s.The"1C" AFW Pump turbine experiences a loss of lubricating oil and locks up.1015 When S/6 levels reach 15%Wide range, operators begin once-through cooling on the one available High Pressure Safety Injection (HPSI)pump and the available Power Operated Relief Valves (PORV)s.1030 A SITE AREA EMERGENCY should be declared as a result of the loss of feed and initiation of once-through-cooling by opening of the PORV.1100 1115 The one operable HPSI pump fails, stopping once-.through cooling.The lack of heat rejection causes Reactor Coolant System (RCS)temperature and pressure to increase.The PORVs blow down excess pressure to the Quench Tank and containment.

A GENERAL EMERGENCY should be declared based upon total loss of feedwater followed by failure of once-through-cooling.

Protective Action Recommendations (PARs)are generated on plant conditions.

1130 The lack of heat removal in the RCS and decay heat causes full voiding and the core uncovers as indicated on the Core Exit Thermocouples (CET)s.Uncooled and uncovered fuel begins to release gas gap activity and fuel overheat begins to cause zirconium-water reaction, liberating hydrogen.Containment High Range Radiation Monitors (CHRRM)s increase sharply.Containment hydrogen increases.

1145 CHRRMS have exceeded 4.2X10'/hr.

Protective Action Recommendations (PARs)are upgraded based upon plant conditions.

FPL/PSL Rev.5 CONRDENTIAL 3.2-3 02/10/92 92EX

CONRDENTIAL 3.2..SCENARIO TIMELINE (Continued)

TIME EVENT 1200 The recovery of the"1A" AFW Pump allows the feeding of the"1A" S/G and resumption of heat rejection through the"1A" S/G and atmospheric dumps.The addition of cold feed water to the hot and dry"IA" S/G results in the rupturing of approximately 50 U-tubes in the"1A" S/G.The necessity of rejecting heat mandates utilizing the one available leaking S/G to release contaminated steam.On the initiation of feed to the dry S/G, the open atmospheric dump valve{ADV)fails as is, preventing the remote closure of the ADV.Off-site release rates increase sharply.PARs are upgraded based upon plant conditions.

1400 Cooldown of the RCS has reduced primary pressure and reduced the primary to secondary flow in the S/G being utilized for cooldown.Auxiliary feed has refilled the"lA" S/G covering and partitioning the tube ruptures.Release radiation readings begin to decline.Field monitoring activities continue.The emergency response teams continue to stabilize the reactor, verify safe shutdown and evaluate system integrity.

Discussions of recovery and reentry should begin as the release rate continues to decline.1500 Termination of Exercise Play.FPUPSL Rev.5 CONFlOENTlAL 3.2-4 02/10/92 92EX CONRDENTlAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLAÃr 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 3.3 SE UENCE OF EVENTS TIMELINE TIME: 0730 EMERGENCY CLASSIFICATION:

NONE SCENARIO EVENT: Initial Conditions:

Initial conditions establish Unit 1 operating at 100%power, in the middle of core life.Power history has been full power operation for the last 180 days.Unit 2 is in day 12 of a 30 day scheduled maintenance outage.The"1A" Auxiliary Feed Water (AFW)Pump has been placed on a clearance for motor removal and motor bearing replacement.

The motor has been disconnected electrically and mechanically, lifted from the baseplate and end bells removed for bearing removal.The AFW pump work places Unit 1 in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Limiting Condition for Operation (LCO)started at 1600 on February 11, 1992.The work is anticipated to require another 6 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.Demand on the system is moderate with an anticipated peak of 12,000 MWe.Service area conditions are normal.Weather has been sunny and mild for the last week with occasional late afternoon and evening showers.Forecast is for partly cloudy skies, temperatures in the upper 80's and occasional showers for the next four days.Current temperature is 78'ith winds from the East at 4-8 mph.ANTICIPATED ACTION: Unit 1 Control Room (Exercise Player)Operations staff receives initial conditions turnover.FPL/PSL Rev.S CONFlDENTlAL 3.3-1 02/10/92 92 EX CONFlDENTIAI.

3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: 0800 EMERGENCY CLASSIFiCATION:

NONE SCENARIO EVENT: Fire alarms at delta point numbers 1,07.01 and 1.07.02 (Unit 1 Zone 07 A&8)occur.ANTICIPATED ACTION: Senior Nuclear Plant Operator (SNPO)is dispatched to investigate the alarms.TIME: EMERGENCY CLASSIFICATION:

NONE SCENARIO EVENT: SNPO verifies the fire alarm.ANTICIPATED ACTION: Sound fire alarm.make announcements, dispatch Fire Team.Nuclear Plant Supervisor

{NPS)should refer to Emergency Plan Implementing Procedure (EPIP)No.3100022E, Classification of Emergencies, EPIP No.3100025E, Fire Emergencies, and Administrative Procedure No.1-1800023, Unit I Fire Fighting Strategies.

FPIJPSL Rev.5 CONFJDENTlAL 3.3-2 02/10/92 92 EX CONRDEN7IAI 3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: 0810 EMERGENCY CLASSIFICATION'.

NONE SCENARIO EVENT: Fire Team responds to the"B" 4160 Volt Switchgear Room on the 43'levation of the Unit 1 Reactor Auxiliary Building (RAB).The"1B5" 480 Volt MCC is isolated for firefighting purposes.ANTICIPATED ACTION: Operators should enter Off-Normal Operating Procedure (ONOP)No.1-09 10054, Loss of a Safety Related A.C.Bus.TIME: EMERGENCY CLASSIFICATION:

NONE SCENARIO EVENT: Fire Team continues firefighting action on the 43'levation of the Unit 1 RAB.ANTICIPATED ACTION: Continue in ONOP No.2-0910054, evaluate the consequences of the loss of the"1B5" 480 Volt MCC.I NPS/EC: A NOTIFICATION of UNUSUAL EVENT (NUE)should be declared in accordance with EPIP No.3100022E, Classification of Emergencies, EVENT/CLASS 3.FIRE UNUSUAL EVENT Uncontrolled fire within the lant I tin more than 10 minutes.Complete Fire or Ex losion Emer enc Checklis Unusual Event Checklist and perform notifications in accordance with EPIP No.3100021E, Duties and Responsibilities of the Emergency Coordinator.

FPL/PSL Rev.5 CONFIOENTlAL 3,3-3 02/10/92'2EX CONR DEN TlAL 3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME;0830 EMERGENCY CLASSIFICATION; NOTIFICATION OF UNUSUAL EVENT (NUE)SCENARIO EVENT: Difficulties experienced in fighting the fire in the"IB5" 480 Volt MCC and the overhead cable trays in addition to the lack of fixed suppression systems in that area lead to a request from the Fire Team for off-site fire assistance.(NOTE: Off-site fire assistance will be simulated.)

ANTICIPATED ACTION: NPS/EC: In accordance with EPIP No.3100021E, Duties and Responsibilines of the Emergency Coordinator, complete another Fire or Ex losion Emer enc Checklist and notify the off-site fire assistance organization (simulated call).Declare an ALERT in accordance with Emergency Plan Implementing Procedure (EPIP)No.3100022E, Classt Ji cation of Emergencies, EVENT/CLASS 3, FIRE ALERT Uncontrolled fire 1.Potentially affecting safety systems.AND 2.Requiring off-site support in the opinion of the NPS/EC.Complete Alert Checklist and perform notifications in accordance with EPIP No.3100021E, Duties and Responsibi lines of the Emergency Coordinator.

Technical Support Center (TSC): Begin activation Operational Support Center (OSC): Begin activation FPIJPSL Rev.5 CONFIOENTlAL 3.3-4 02/10/92 92 EX CONFIDENTIAL 3.3 SE UENCE OF EVENTS TlMELINE (Continued)

TIME: 0835 EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: The loss of AFW feed isolation valves due to degraded electrical condition in conjunction with the inoperative "1A" AFW pump causes operators to begin a power reduction (approximately 5 Megawatts per min)by injecting boric acid into the Volume Control Tank,(VCT).(NOTE: VCT injection chosen because Boron Load Control Valve, V-2525 is deenergized by the loss of the"1B5" 480 Volt MCC.)ANTICIPATED ACTION'perators:

Commence Reactor power reduction.

TIME: 0840 EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: The off-site fire assistance group is simulated to have arrived at the site by a Security Controller Message to the Security Officers at the East Gate.ANTICIPATED ACTION'ecurity makes notification of the arrival of the simulated off-site fire team and simulates escort to the fire scene.FPL/PSL Rev.5 CONFIDENTlAL 3.3-5 02/10/92 92 EX CONFlDENTIAl 3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: 0845 EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: The simulated off-site fire assistance has arrived and joined the Fire Team at the"B" Switchgear Room in the Unit 1 RAB.The fire in the"1B5" 480 Volt MCC and overhead cable trays is out.ANTICIPATED ACTION:~g Fire Team: Complete firefighting activities in the"B" Switchgear Room.Perform initial damage appraisal, TIME: EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: The off-site fire assistance group is simulated to have departed the site by a Security Controller Message.ANTICIPATED ACTION: Security makes notification of the departure of the simulated off-site fire team.FPL/PSL Rev.5 CONFlDENTIAL 3.3-6 02/10/92 92 EX CONflDEN7lAL 3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: A Radwaste operator (medical drill volunteer victim)working in Drumming Room of the Unit 1 RAB is injured when a B25 box lid falls and strikes the worker.The injured person has sustained a gash on the arm and a blow to the head.Another worker (or exercise medical controller) is simulated to have moved the semi-conscious victim outside of the Drumming Room and makes telephone notification of the injury.ANTICIPATED ACTION'PS/EC:

The First-Aid/Decon Team is requested by the Unit 1 Control Room.TME: 0910 (Approximate)

EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: First-Aid/Decon Team responds to the scene of the injury in the Unit 1 RAB.ANTICIPATED ACTION: The First-Aid/Decon Team arrives on the scene.Triage is performed.

The victim is determined to be contaminated, Initial medical appraisal indicates serious injuries.Off-site medical assistance is necessary and an ambulance is requested.

NPS/EC: Complete Medical Emer enc Checklist in accordance with EPIP No.3100021E, Duties and Responsibilities of the Emergency Coordinator.

Call for the off-site ambulance.

FPVPSL Rev.5 CONflDENTlAL 3.3-7 02/10/92 92 EX CONRDENTlA1 3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: A sudden failure in a flexible pipe joint in the suction header of the Unit 1 Main Condensate Pumps results in a rapid loss of condenser vacuum and loss of hotwell inventory.

Condensate Pumps and Feed Pumps trip, Hot water inundates the pump pit area under the Unit 1 Turbine Deck.When the Auxiliary Feed Actuation Signal (AFAS)autostarts the"IB" AFW pump, the"IB3" 4160 Volt bus faults and trips, Heat damage and instabilities in the"1B3" switchgear caused by the fire in"1B5" MCC prevent it from being utilized for the remainder of the exercise.The phase differential lockout of the"1B3" switchgear also deenergizes the"1AB" 4160 and 480 Volt loadcenters normally aligned to the"B" side until they are realigned to"A" side sources.When the"1C" AFW pump starts, a failure in its turbine controller only brings its turbine up to 3000 rpm, producing only about 100 gpm Steam Generator (S/G)feed.The S/Gs begin to steam down due to lack of feedwater.

The OSC and TSC should have been activated.

ANTICIPATED ACTION'perators:

Trip the turbine/reactor manually due to low condenser vacuum.Enter Emergency Operating Procedure (EOP)1-EOP-01, Standard Post Trip Actions.Reject heat through the Atmospheric Dump Valves (ADVs).Respond to the loss of the"1B3" 4160 Volt bus in accordance with ONOP No.1-0910054, Loss of a Safery Related A.C.Bus.Transfer the"1AB" 4160 and 480 Volt loadcenters to the"A" side supplies.Investigate the"1C" AFW pump minimal output.'SC; The Emergency Coordinator in the TSC should have relieved the NPS/EC of his Emergency Coordinator responsibilities.

TSC should have assumed notification and communication responsibilities.

Off-site treatment Facility (Martin Memorial Hospital)should be notified.Ambulance should be ordered and Security alerted for ingress on arrivaL Respond to the loss of 4160 Volt Emergency bus, minimal AFW feed and condensate leak.OSC: The OSC should have been activated by this time and offered electrical maintenance team support to the damage assessment in the"B" Switchgear Room.Dispatch teams as requested to the"1C" AFW pump, condensate leak and loss of"1B3" 4160 Volt bus.FPL/PSL Rev.5 CONHOENTIAL 3.3-8 02/10/92 92 EX CONFIOENTIAI.

3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: 0945 (Approximate)

EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: The injured person is transferred to the ambulance.

ANTICIPATED ACTION: I~~'r p r I I~I~//~Security expedites the ingress of the ambulance.

The ambulance is prepared to receive the contaminated victim.Ambulance attendants are given dosimetry and briefed on the condition of the patient.The victim is packaged and moved out of the Radiation Control Area into the ambulance with minimum delay.A Health Physics (HP)Technician accompanies the victim in the ambulance and goes to the hospital to provide Health Physics support..Security expedites the egress of the ambulance.

TIME: EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: "1C" AFW pump has been losing oil since startup.The"1C" AFW pump turbine experiences bearing lockup due to lack of lubrication.

ANTICIPATED ACTION: Operators:

Stabilize the plant, enter Emergency Operating Procedure (EOP)No.1-EOP-06, Total Loss of Feedwarer.

Begin to cool down on the ADVs and monitor S/G levels.TSC: Investigate the loss of the" 1C" AFW pump.Evaluate the possibility of expedited recovery of the"1A" and"1B" AFW pumps, OSC: Field teams as requested to respond to the ongoing equipment casualties.

FPIJPSL Rev.5 CONRDENTIAL 3.3-9 02/10/92 92 EX CONRDENTlAt.

3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: 1015 EMERGENCY CLASSIFICATION:

ALERT SCENARIO EVENT: S/Gs have reached 15%wide range level.ANTICIPATED ACTION: Operators:

Enter 1-EOP-15, Functional Recovery.Begin once-through cooling on the one available High Pressure Safety Injection (HPSI)pump ("1A")and the available Power Operated Relief Valves (PORV)s.TSC: EC should declare a SITE AREA EMERGENCY on the opening of the PORV in accordance with EPIP No.3100022E, CIassijication of Emergencies, EVENT/CLASS

~~1.C.LOSS OF SECONDARY COOLANT SITE AREA EMERGENCY TLOF with once-throu h coolin initiated 2.No main or auxiliary feedwater flow available..

AND PORV(s)have been opened to facilitate core heat removal.EC should complete the Site Area or General Emer enc Checklist and the TSC should perform notifications in accordance with EPIP No.3100021E, Duties and Responsibilities of the Emergency Coordinator.

Continue to evaluate plant conditions and respond to the lack of S/G feed.OSC: Field teams as required to respond to the ongoing equipment casualties.

Emergency Operations Facility (EOF): Begin activation (if the Emergency Control Officer[ECO]had not determined to activate earlier).FPIJPSL Rev.5 CONFIDENTlAL 3.3-10 02/10/92 92 EX CONFIDENTIAI.

3.3 SE UENCE OF EVENTS TMELINE (Continued)

TIME: 1100 EMERGENCY CLASSIFICATION:

SITE AREA EMERGENCY (SAE)SCENARIO EVENT: The"IA" HPSI pump begins to experience high vibration and the bearings seize.The loss of once-through cooling causes Reactor Coolant System (RCS)inventory to decrease, temperature and pressure to increase.The open PORVs continue to blow down RCS inventory to the containment'through the Quench 7ank'Core Exit Thermocouples (CET)s'begin'o increase.ANTICIPATED ACTION'perators:

Evaluate the consequences of the loss of once-through cooling.Monitor RCS inventory and CET temperatures.

TSC: A GENERAL EMERGENCY (GE)should be decided based upon Total Loss of Feed (TLOF)followed by failure of once-through cooling in accordance with Emergency Plan Implementing Procedure (EPIP)No.3100022E, Classification of Emergencies, EVENT/CLASS 6.A.INCREASED AWARENESS OR POTENTIAL CORE MELT I GENERAL EMERGENCY Emer enc Coordinator's

'ud ement that lant conditions exist that make release of lar e amounts of radioactivi in a short riod a ar ossible or~tikel.{Any core melt situation.)

3.Total loss of feedwater followed by failure of once-through cooling (ECCS)to adequately cool the core.The EC should complete the Site Area or Gen ral Emer enc Checklist and the TSC should perform notifications in accordance with EPIP No.3100021E, Duties and Responsibilities of the Emergency Coordinator.

Protective Action Recommendations (PARs)should be generated based upon plant conditions.

OSC: Continue to provide teams and support as requested to respond to the situation.

FPUPSL Rev.5 CONRDENTlAL 3.3-11 02/10/92 92 EX cONRDENTIAL 3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: 1130 EMERGENCY CLASSIFICATION:

GENERAL EMERGENCY (GE)SCENARIO EVENT: RCS isolation with no heat removal and no Emergency Core Cooling System (ECCS)feed has caused reactor vessel level to steam down.Core Exit Thermocouples (CET)s indicate core voiding and fuel uncovery.The uncovered upper fuel region of the core begins to release gas gap activity.and fuel, overheat, begins to cause zirconium-.water reaction, liberating hydrogen.Containment High Range Radiation Monitors (CHRRMs)increase sharply.Containment hydrogen increases.

ANTICIPATED ACTION: Operators:

Continue efforts to restore ECCS and AFW.Monitor the increasing containment hydrogen and radiation readings.Monitor CET temperatures.

TSC: Evaluate and take precautions against the increasing radiation fields associated with the containment and systems.Monitor and analyze for potential effluent releases.Perform dose projections based upon containment monitor readings.OSC: Continue to provide teams and support to mitigation efforts.Monitor teams in the field and ensure the changing radiological conditions are disseminated to emergency response personnel, EOF: Should have been activated by this time.Perform dose assessment and establish communications with State and Local Government.

FPL/PSL Rev.5 CONFIDENTIAL 3.3-12 02/10/92 92 EX CONFIDENTIAL 3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: 1145 EMERGENCY CLASSIFICATION:

GE SCENARIO EVENT: Fuel damage has peaked at approximately S0%of gas gap release and 25%of fuel overheat.CHRRMS have exceeded 4.2X10'/hr.

ANTICIPATED ACTION: Operators:

Continue attempts to recover ECCS and AFW.TSC: Continue to track increasing radiation levels and take precautionary actions.Perform dose projections on potential releases based upon source term in containment.

OSC: Continue to provide emergency response teams as capable.Monitor and control emergency response personnel exposure.Perform dose projections and continue to maintain communications with State and Local Government.

Make Protective Action Recommendations (PARs)based upon plant conditions.

FPL/PSL Rev.5 CONRDENTIAL 3.3-13 02/10/92 92 EX CONRDENTIAL 3.3 SE UENCE OF EVENTS TIMELINE (Continued)

TIME: 1200 EMERGENCY CLASSIFICATION:

GE SCENARIO EVENT: Emergency team(s)have succeeded in remounting and aligning the"1A" AFW pump.The"1A" AFW pump is started and the"1A" S/G is fed.The shock of cold water from the Condensate Storage Tank (CST)on the hot and dry S/G tube bundle causes approximately 50 U-tubes to rupture.The open ADV on the affected S/G has failed"as is" and cannot be moved in either direction remotely.The resulting sluice of fuel-damaged primary coolant releases almost pure primary steam from the ADV until the AFW feed can cover and dilute the tube leakage.Main steam line monitor readings, ambient radiation readings around the Steam Trestle and field readings spike as a result of the release of radioactive material to the environment.

ANTICIPATED ACTION: Operators:

Feed up the affected S/G with AFW to cool, partition and dilute the primary to secondary leakage.TSC: Take precautionary actions onsite for dramatically increased building radiation fields and release rates.Perform dose assessment on the release.Make onsite notifications of changing plant conditions.

OSC: Take precautionary actions for teams in the field.Monitor and evaluate increased radiation readings as a result of the release in progress.EOF: Perform dose assessment on the release.Upgrade PARs and make off-site notifications of changing plant conditions.

FPL/PSL Rev.5 CONFlDENTlAl 3.3-14 02/10/92 92 EX CONRDENTIAL 3.3 SE UENCE OF EVENTS TIMEI INE (Continued)

TIME: EMERGENCY CLASSIFICATION:

GE SCENARIO EVENT: Cooldown, depressurization, Safety Injection Tank (SK)and Low Pressure Safety Injection (LPSI)feed has refiooded the core.Offsite and Steam Trestle radiation readings have declined as primary to secondary fiow has equalized and stopped, AFW has flooded and contained the leakage and RCS depressurization has allowed LPSI floodup.The release of contaminated steam has nearly ceased and manual isolation of the stuck ADV may be performed on the Steam Trestle.ANTICIPATED ACTION: Operators:

Continue stabilization and cooldown of the primary system.TSC: Continue dose assessment and projection.

Continue core damage estimates, mitigation support activities, long-term safe shutdown and recovery strategy development.

OSC: EOF: Continue repair and monitoring team activities as capable.Continue dose assessment and projection.

Review projections and continue to make PARs to state and local authorities.

Continue core damage estimates, mitigation support activities, long-term safe shutdown and recovery strategy development.

FPL/PSL Rev.5 CONROEHTIAL 3.3-15 02/10/92 92EX CONRDENTIAL 3.3 SE NCE OF EVENTS TIMELINE (Continued)

TIME: 1500 EMERGENCY CLASSIFICATION:

GE SCENARIO EVENT: The primary system has been cooled-down, depressurized and stabilized.

Radiation readings onsite indicate virtually no release of radiation.

The plume has been tracked, monitored and analyzed by field teams.ANTICIPATED ACTION'he exercise is terminated.

A facility critique will be held in all key facilities with the Lead Controllers and the participants.

FPUPSL Rev.5 CONFlDENTlAL 3.3-16 02/10/92 92 EX

CONRDENTlAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 4.0 MESSAGES This section contains the following information:

Section 4.1 CONTROLLER MESSAGES-This section contains messages which are used to control the scenario.Section 4.2 MEDICAL SCENARIO and MESSAGES-This section contains all information needed for the medical exercise.Section 4.3 MINI-SCENARIOS

-This section contains detailed mini-scenarios for specific activity areas within the main scenario.FPIJPSL Rev.1 CNRDENTlAL 4.0-1 01/31/92.92EX

CONTROLLER MESSAGE To: Unit 1 CR RCO/NPS From: CR Controller Number: 002 Time: 0800 eeeeeeee4448e8e48844444444444444444444444444444844444444444444844444444444t444 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: The following alarm(s)have just come in on the Master Fire Panel: Delta point number 1.07.01, Unit 1 Zone 7 A Delta point number 1.07.02, Unit 1 Zone 7 B THL'>IS A DRILL FPL/PSL Rev.4 CONFtOENmai.

4.1-2 02/10/92 92 EX CONTROLLER MESSAGE To: Senior Nuclear rator SNPO From: Fire Controller Number: 003 Time: 0805{Approximate]

eeeeeeeeee44eee444448444444444444444444t44444444444444444444404t44444444444444 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations eeeeeeee444444444c444844444444444444444444444044444444444c44484444444444444444 Message: You find the following conditions on the 43'levation of the Unit 1 Reactor Auxiliary Building (RAB): Thick black smoke is emanating from the door to the 4160V"B" Switchgear Room.THIS IS A DRILL FPL/PSL Rev.4 CONR0ENTlAL 4.1-3 02/10/92 92 EX CONTROLLER MESSAGE ti I To: Fire Team Leader From: Fire Controller Number: 004 Time: 0810[Approximate]

eeeweeeew0eeW4W4e4444e44C844444444444t444484444844484444tww088448ww444444w4w THIS LS A DRILL DO NOT initiate actions affecting normal plant operations 0'4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4'4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 Message: Controller Note: P id U fll ig~if'U F'I d~i pd d U 43'levation of the RAB in the 4160V"B" switchgear (SWGR)and simulated firefighting activities performed.

Inside the 4160V"B" SWGR Room: There is a thick layer of black smoke on the ceiling.There is a very strong odor of burnt insulation.

There are several cubicles in the"1BS" 480 Volt Motor Control Center (MCC)that have their access panels blackened and soot covered.The top portions of the"1B5" MCC panels are blackened with soot and thin streams of blacksmoke are escaping from several areas, There is a smoldering fire in the cable tray over the"1BS" MCC still producing black smoke.YHL'>IS A DRILL Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q Q gl 4 Q Q 4 4 4 4 4 4 4 4 4 4 0 4 4'4 4 4 4 4 4 FPL/PSL Rev.4 CON FlDENTtAL 4.1-4 02/10/92 92 EX CON'HNGENCY MESSAGE To: Unit 1 CR Nuclear Plant Su rvisor NPS From: CR Controller Number: C-001 Time: 0830 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations 444ee444444444444488444e444e4444444444844444444444484444444ee444e4444e44444444 Message: UNUSUAL EVENT ncontrolled fire within the lant lastin more than 10 minutes.If not already done so, declare a NOTIFICATION of UNUSUAL EVENT (NUE)at this time in accordance with EPIP No.3100022E, Classification of Emergencies, EVENT/CLASS 3.FIRE W4440444444444444444440444C44488444W4444W4444848444444W84t44444444444444444eW4 THIS IS A DRILL FPIJPSL Rev.4 COHROENTlAL 4.1-5 02/10/92 92 EX CONTINGENCY MESSAGE To: Fire Team Leader ti~From: Fire Controller Number: C-002 Time;0830 Message: THIS IS A DRILL DO NOT initiate actions affecting normal plant operations If not already decided to do so, request off-site fire assistance at this time.THIS IS A DRILL FPUPSL Rev.4 CON ROENTIAL 4.1-6 02/10/92 92EX CONTINGENCY MESSAGE To: Unit 1 CR Nuclear Plant Sii rvisor NPS From: CR Controller Number: C-003 Time: 0830 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: Off-site fire assistance is to be SIMUL4TED.

DO NOT CALL OFF-SITE FIRE.Make all other responses as if off-site fire assistance has been called at this time.THIS IS A DRILL FPL/PSL Rev.4 CONFIDENTlAL 4.1-7 02/10/92 92 EX CONTINGENCY M%CAGE To: Unit 1 CR Nuclear Plant Su rvisor NPS From: CR Controller Number: C-004 Time: 0835 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations 4884440004444444W44440444444444444444444444444444444444444444884444444te44444 Message: If not already done so, you have begun a controlled reactor shutdown at 5 MWe/min by injecting Boric Acid to the Volume Control Tank (VCT)at approximately 10 gpm due to the loss of 2 out of three AFW paths.THIS IS A DRILL FPL/PSL Rev.4 CONFlDENTlAL 4.1-8 02/10/92 92 EX CONTROLLER MESSAGE 7:~EG S I': S~Cll Time: 0840 Number: 005 Message: THIS IS A DRILL DO NOT initiate actions affecting normal plant operations The off-site fire company has arrived at the East Security Gate.Make all notifications as if the off-site fire company were actually here.THIS IS A DRILL F PL/PSL Rev.4 CONFIDENTIAL 4.1-9 02/10/92 92 EX

CONTROLLER MESSAGE To:~Securi F S~CII Number: 007 Time: 0900 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: The off-site fire company has departed through the East Security Gate, Make all notifications as if the off-site fire company had actually left through the gate.THIS IS A DRILL FPUPSL Rev.4 CONFIDENTIAI.

4.1-12 02/10/92 92 EX CONTROLLER MESSAGE To: Unit 1 Control Room From: Conscri ted Pla er/Medical Controller Number: 008 Time: 0905 8444444444444444t4444444444444444444444444444444444444444448844444444e4e444444 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: Controller Note: The remainder of information for the medical emergency scenario will be provided from the Medical Emergency Mini-Scenario, Section 4.2.A worker has been injured in the Drumming Room of the Unit 1 Radwaste Building.The victim is semi-conscious and bleeding outside the Drumming Room.We need immediate medical assistance.

THIS IS A DRILL 44444444444444444444444444444444444444t44444444444444444444444444t444t4444e444 FPL/PSL Rev.4 CONRDENTlAL 4.1-13 02/10/92 92EX CONTROLLER MESSAGE To: Unit 1 Control Room From: OSC Lead Controller Number: 009 Time: 0930 eeeeeeweeeee44e44e444444444444t444e444444444444444444444e44e44444t4444444e4e44 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: Controller Note: Provide the following information to any and all personnel in the immediate vicinity of the Unit 1 Turbine Mezzanine and Ground Floor at this time.If there are no players in the immediate vicinity, phone the information in to the Unit 1 Control Room yourself and provide the message to any responding or passing players.There is hot steamy water flowing in the pits under the Unit 1 Turbine Deck.The condensate piping and pump pits are filled with hot water.THIS IS A DRILL FPIJPSL Rev.4 CONFlDENTlAL 4.1-14 02/10/92 92 EX CONTROLLER MESSAGE To: Re air Team Leader From: Re air Team Controller Number: 010 Time: 0930 4e44888448444488444444444444448444444444488484888884444WW4eeW88444t44C84444444 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: Controller Note: Provide the following information to any and all personnel in the immediate vicinity of the Unit 1 RAB 43'levation"B" Switchgear Room at this time.If there are no players in the immediate vicinity, phone the information in to the Unit 1 Control Room yourself and provide odor and visible portion of the information in the message to any responding or passing players.Several breakers and relays slammed in the"1B3" 4160 Volt Switchgear.

There was a loud arcing noise in the vicinity of the"1B3" 4160 Volt Switchgear.

There is the strong odor of burnt rubber, ozone and hot metal.There is no visible smoke or fire.4444444e44444444444444t44444444444448444488444444444844444e4e44444444444ee4444 THIS IS A DRILL FPL/PSL Rev.4 CONFlDENTIAL 4.1-15 02/10/92 92EX CONTROLLER MESSAGE t t~To: Re air Team Leader From: Re air Team Controller Number: 011 Time: 0945 (Approximate) 444448884444804884444444444444444444444444tt44444444444444444eee44444444444448 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: Controller Note: Provide the following information to any player personnel dispatched to investigate the loss of the"1C" AFW pump.There is a hazy cloud of oily vapor in the"1C" AFW pump area.The pump base is shiny and wet with oil.There is a strong odor of burnt oil and hot metal.The turbine bearing housings are smoking slightly and are too hot to be touched.THIS IS A DRILL FPUPSL Rev.4 CONFlDENTIAL 4.1-16 02/10/92 92 EX

COYIROLLER MESSAGE To: RCO From: CR Controller Number;012 Time: 1100 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: Controller Note: Provide the following information to operations players in the Unit 1 Control Room to indicate the loss of the"lA" HPSI pump.The"lA" HPSI pump has a green light.There is"0" amps and"0" flow."1A" HPSI pump has tripped.The"lA" HPSI pump will not restart from the Control Room.THIS IS A DRILL FPL/PSL Rev.4 CONRDENTIAL 4.1-18 02/10/92 92EX tt CONTROLLER MESSAGE To: Re air Team Leader/SNPO Frotn: Re air Team Controller Number: 013 Time: 1100 (Approximate)

THIS IS A DRILL DO NOT initiate actions affecting normal plant operations 444444444444444444444444t4444444444444440440444W0088CC888eeeeee8weeeee444W4400 Message: Controller Note: Provide the following information to any player personnel dispatched to investigate the loss of the"1A" HPSI pump.At the Pum Breaker.The instantaneous overcurrent flags are showing on all three phases.In the HPSI Pum room;There is a strong odor of burnt oil and hot metal.The pump bearing housings are smoking slightly and are too hot to be touched.44444444444444444444444444444444444444444e44444444444444444444444444444444W4WW THIS IS A DRILL 7 FPL/PSL Rev.4 CONFIDENTIAL 4.1-19 02/10/92 92 EX CONTINGENCY MESSAGE To: Emer enc Coordinator From: TSC Controller Number: C-007 Time;1115 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations 44444444444sit444044t444444tit44444444tit44tit4444444444sit444444484sit44t4444444444444444 Message: Controller Note: Deliver the following message if a GENERAL EMERGENCY has not been declared by this time and with the prior approval of the Exercise Controller.

A GENERAL EMERGENCY should be declared IAW EPIP No.3100022E, Classificanon of Emergencies, EVENT/CLASS 6.A.INCREASED AWARENESS OR POTENTIAL CORE MELT GENERAL EMERGENCY Emer enc Coordinator's

'ud ement that lant conditions exist that make release of lar e amounts of radioactivi in a short riod a ar ossible or~tikel.(Any core meit situation.)

3.Total loss of feedwater followed by failure of once-through cooling (ECCS)to adequately cool the core.THIS IS A DRILL FPL/PSL Rev.4 CONRDENTIAL 4.1-20 02/10/92 92 EX CONTINGENCY MI3SAGE T: Q~SC~From: OSC Lead Controller Number: C-008 Time: 1130 e884eW8eC4488eCC844444444444444444444444444444444444844444444444C4444444444444 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: Controller Note: Deliver the following message if team play at the"1A" AFW pump has not occurred or is not proceeding at sufficient pace to simulate recovery with the prior approval of the Exercise Controller.

The team(s)working on the"1A" AFW pump have remounted the motor and reconnected the~~motor leads, After"bumping" to test rotation, the pump will be ready to run in about ten minutes.THIS IS A DRILL FPL/PSL Rev.4 CONRDENTlAL 4.1-21 02l10/92 92EX CONTINGENCY MFSSAGE To: RCO From: CR Controller Number: C-009 Time: 1155 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations Message: Controller Note: Deliver the following message if team play at the"1A" AFW pump has not occurred or is not proceeding at sufficient pace to simulate recovery with the prior approval of the Exercise Controller.

The team(s)working on the"1A" AFW pump have remounted the motor and reconnected the motor leads.After"bumping" to test rotation, the pump will be ready to run in five minutes.THIS IS A DRILL FPL/PSL Rev.4 CONFIDENTIAL 4.1-22 02/10/92 92EX CONTROLLER MESSAGE To: ALL PARTICIPANTS From: ALL CONTROLLERS Number: 014 Time: 1500 THIS IS A DRILL DO NOT initiate actions affecting normal plant operations 4444~4e4444441wwkr a84~r 4a4~40~441 t4441 a44441 r r atr 4~444r r4r asge4e1 444e4404e44se Message: The Emergency Preparedness Evaluated Exercise is Terminated.

Restore all emergency facilities and equipment to a readiness condition.

Collect all logs, data sheets and notification forms and ensure they are given to the facility lead controllers.

Lead Controllers hold an in-place critique with all participants in all facilities.

Facility Managers and Key Participants ensure that all participants have completed attendance and critique documentation.

4tgt4tgttgttgt444sgg 44tgttgttgt88tgt4sg tgtrgt444tgttgt84484tgte444844sg484tgttg tg tgtetg tgttgt84tgt444tgt4444444444444eeg 44 THIS IS A DRILL FPIJPSL Rev.4 CONFlDENTIAL 4.1-23 02/10/92 92 EX CONFIDENTlAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR POWER PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 4.2 MEDICAL SCENARIO AND MESSAGES-NOTE-This Section contains data on the simulated contaminated injury including:

inplant, transport and treatment at the off-site medical treatment facility (Martin Memorial Hospital).

~NTHNT Scenario and anticipated actions Messages FPL/PSL Rev.2 CONFlDENTIAL 4.2-1 01/31/92 92EX CONFlOENTIAL

4.2.1 SCENARIO

AND ANTICIPATED ACTIONS: GENERAL SCENARIO: A Radwaste Operator (simulated by a volunteer victim)was working in the Drumming Room of the Unit 1 RAB when a lid on a B25 box slipped from the top of the box where it was sitting loosely and knocked the worker to the floor.As the lid fell, it knocked the victim over and the corner of the lid ripped open the right sleeve of the victim's protective clothing, gashing the right outer forearm between elbow and wrist.The victim was bowled over by the falling lid, striking their head soundly on the floor and was knocked semi-conscious.

The victim is stunned and bleeding and a coworker (simulated by the Medical Controller) helped the worker out of the Drumming Room where the victim slumped to the floor and the medical emergency scenario begins with a notification telephone call to the Unit I Control Room.FPL/PSL Rev, 2 CONROENTtAL 4.2-2 01/31/92 92EX't CONRDENTlAl DETAILED SCENARIO AND ACTIONS: SCENARIO ACTIONS The medical scenario begins with the volunteer victim lying on their side in the Unit 1 RAB outside the Drumming Room.The victim is wearing protective clothing, The victim is semiconscious and bleeding from the right forearm.Bleeding is apparent through the PC sleeve.y it" Initial condition The Medical Controller or a conscripted Player will call in the injury information to the Unit 1 Control Room, initiating the medical emergency scenario.The victim is semi-conscious and unresponsive to inquiry.Respiration:

Pulse: 24 85 Skin: Pale, and wet with perspiration.

Pupils: Dilated FPIJPSL Rev.2 CONFlOENTIAL 4.2-3 01/31/92 92EX CONFIDENTlAL DETAILED SCENARIO AND ACTIONS: (Continued)

SCENARIO ACTIONS Respiration:

Pulse: B/P: 24 SS"III~I I 140/96 Plant First-Aid/Decon Team Arrival Comtnunications are established.

Vital signs and patient condition are assessed.Protective clothing is removed to facilitate treatment of the wound.A pressure dressing is applied to the laceration.

The victim is kept in.a supine condition and remaining protective clothing is cut away.Psychological support is given.Skin: Pale and wet with perspiration.

Pupils: EquaL The Patient is conscious, but is weak, dizzy and unable to sit up.The victim complains of headache, a feeling of vertigo and nausea.There is copious bleeding from the tom right forearm.FPL/PSL Rev.2 CovplOnmai.

4.2-4 01/31/92 92EX CONFIGENTIAL DETAILED SCENARIO AND ACTIONS: (Continued)

Radiolo ical evaluation:

General area radiation levels: At Drumming Room door threshold (door open): 2 mr/hr airborne: While triage is being administered to the patient, Health Physics Technician should be assessing the general area radiological conditions and evaluating the contamination levels of the victim.smearable: (door closed): airborne: smearable:

Patient's SRD: ADA l 0~5000 cpm>Bkg 1 mr/hr ADA 5000 cpm>Bkg 10 mr FPL/PSL Rev.2 CONFIDENTIAL 4.2-5 01/31/92 92EX CONFlDENTIAl DETAILED SCENARIO AND ACTIONS: (Continued)

SCENARIO ACTIONS Radiolo ical Evaluation:(Continued)

When moved to a lower background area: Patient: In general, radiation, contamination and airborne activity outside of the immediate pumproom area will be AS READ.PC's (general):

right sleeve: Gloves: After PC removal: 5000 cpm>Bkg 3000 cpm>Bkg 5000 cpm>Bkg<Jl y+r~~I~i4~wly~i~g~Right forearm, wound area: 2500 cpm>Bkg Face, left cheek: Right Hand: Left Knee: 1000 cpm>Bkg 5000 cpm>Bkg 2000 cpm>Bkg FPUPSL Rev.2 CONFIDENTlAL 4,2-6 01/31/92 92EX

CONFlDENTtAL DETAILED SCENARIO AND ACTIONS: (Continued)

SCENARIO ACTIONS During the initial treatment and preparation for transport:

Respiration:

36, shallow,.irregular..

Pulse: B/P: Skin: Pupils: 110 148/98 Pale, cool diaphoretic Equal Initial Treatment: (Continued)

Notification of patient condition and contamination should be made to the Control Room and the Emergency Coordinator.

Due to the possibility of a cranial injury, notification to off-site treatment facility should be made and preparations for ambulance, transportbegun.

The patient should be transported by stretcher to meet the ambulance and contamination control appropriate to the medical priorities should be exercised as the patient crosses the Radiation Control Area (RCA)line.Patient is still complaining of headache and dizziness, is becoming less lucid, less responsive.

FPI/PSL Rev.2 CONFlOFNTIAL 4.2-7 01/31/92 92EX

, CONFIDENTIAL DETAILED SCENARIO AND ACTIONS: (Continued)

SCENARIO ACTIONS Radiolo ical Evaluation: (Continued)

After initial decon attempts: Right forearm, wound area: 1500 cpm)Bkg The initial decontamination attempts performed either in the RAB or in the ambulance will reduce the patient contamination levels to those indicated.

These levels will remain unchanged until the patient reaches the off-site treatment facility.'ace, left cheek: Right Hand: Left Knee: 100 cpm>Bkg 100 cpm>Bkg Background Respiration:

Pulse: B/P: Skin: Pupils: 38, irregular.

110 186/100 Pale, clammy, moist.Equal, responsive.

Sec nd Treatment: (Martin Memorial Hospital)Medical evaluation finds the forearm laceration to be approximately 18 cm in length and not deep.There is considerable venous bleeding.no apparent tendon/muscle damage.The patient is becoming more reactive to inquiry and stimuli, there is the possibility of a subdural hematoma as a result of the head.impact upon falling.Blood loss is controlled.

Patient is still disoriented, is getting stronger and more responsive.

FPIJPSL Rev.2 CONFIDENTIAL 4.2-8 01/3 1/92 92EX CONFID ENTlAL C DETAILED SCENARIO AND ACTIONS: (Continued)

SCENARIO ACTIONS Second Treatment: (Off-Site Medical, Continued))

Contamination levels: Wound: 1500 cpm>Bkg.In the Hospital, the patient's remaining clothing is removed.Appropriate medical and nursing tteatment are initiated.

As determined by the Physician, radiological surveys are performed and samples collected.

All surveys should be correctly documented, all samples properly-labeled.Face and Cheek: Right hand: After 1st Decon: Wound: 100 cpm)Bkg.100 cpm)Bkg.500 cpm)Bkg.Priorities are established for decontamination.

Appropriate techniques are utilized for decontamination.

Surveys are performed and.documented during the decontamination process.The Health Physics Technician makes recommendations and properly maintains control of waste.Area background levels are maintained as low as possible.Face and Cheek: Right hand: Background.

100 cpm>Bkg.FPI/PSL Rev.2 CONFlDENTIAL 4.2-9 01/31/92 92EX CONFIDENTIAL DETAILED SCENARIO AND ACTIONS: (Continued)

SCENARIO ACTIONS After 2nd Decon: Wound: 200 cpm>Bkg.After 3rd Decon: During the treatment, the wound will continue to exhibit measurable radiation readings in spite of decontamination efforts until the third simulated decontamination attempt.The removal of this contamination essentially completes'he treatment and decontamination phase of the scenario.W.ound: Background.

FPUPSL Rev.2 CONFIDENTIAL 4.2-10 01/31/92 92EX MEDICAI EMERGENCY MESSAGE FORM THIS S A DRILL TO: First-Aid/Decon Team MESSAGE NQ,'~I SME:~9999 A LOCATION: Unit 1 RAB Druinmin Room Entrance MESSAGE: G II N: 9 IS I~II I I~le I I'SSIS members as they earn it by performing the appropriate action.Vitals: Respiration:

Pulse: B/P: Skin: Pupils: 24 85 140/96 Pale and wet with perspiration.

Equal.Survey results of injured Operator.PC's (general):

Right sleeve: Gloves: SRD: After PC's are removed: 5000 cpm)Bkg 3000 cpm>Bkg 5000 cpm)Bkg 10 mR Right forearm, wound area: Face, left cheek: Right hand: Left Knee: 2500 cpm)Bkg 1000 cpm)Bkg 5000 cpm>Bkg 2000 cpm>Bkg FPL/PSL Rev.2 CONFlDENTlAL 4.2-11 01/31/92 92EX 0

MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: First-Aid/Decon Team MESSAGE NG.: M~I FME:~tl9I 9 LOCATION: Unit 1 RAB MESSAGE: C II N: 9 IS 9 fll ISIN E N 9 9'AlffG members as they earn it by performing the appropriate action.Vital Signs while preparing for transport:

Respiration:

Pulse: B/P: Skin: Pupils: 36, shallow, irregular.

110 ,148/98 Pale, cool and diaphoretic Equal, responsive Patient is still complaining of headache and dizziness, is becoming less lucid, less responsive.

FPL/PSL Rev.2 CONFlDENTIAL 4,2-12 01/31/92 92EX~V Mfa 9<<%~MA,'NA tS.a PCS%PE%.~~~M MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: First-Aid/Decon Team MESSAGE NG:.M~3 TIME:9~95 A LOCATION;Ambulance Loadin Point MESSAGE: Controller Note: Provide the following information onl to the First-Aid/Decon team members as they earn it by performing the appropriate action.Initial decontamination efforts (if performed) yield the following results;Right forearm, Wound area: 1500 cpm>Bkg Left Knee: Face, left cheek: Right hand: Background 100 cpm)Bkg 100 cpm>Bkg FPIJPSL Rev.2 CONRDENTlAL 4.2-13 01/31/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Ambulance Medical Team MESSAGE NG,'.OME:~IOOII A LOCATION: Ambulance Loadin Poin Enroute to Martin Memorial MESSAGE'hen the patient is examined and evaluated by Ambulance Medical Team and the entire I d M'Nll Sl I,O Id d Ell idl~lll M II d by the ambulance medical team's actions: Vitals: Respiration:

Pulse;B/P: Skin: Pupils: 43, irregular.

116 186/100 Pale, clammy, moist Equal, responsive Patient is still disoriented, is responsive to painful stimuli but unable to communicate lucidly.Wound: There is a shallow laceration outside the right forearm between elbow and wrist approximately 18 cm in length.There is considerable venous bleeding and no evidence of any possible tendon/nerve damage.FPL/PSL Rev.2 CONFlDENTlAL 4.2-14 01/31/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Health Ph sics Technician MESSAGE NG.: M-I TIME:~ltl3II A LOCATION: Martin Memorial Hos ital MESSAGE;After the transfer of the patient from the ambulance into the treatment area, clearing of ambulance protective coverings and proper removal of protective clothing by ambulance personnel-survey/status of the ambulance and attendants is: Ambulance:

Transfer Route: All Areas Background All Areas Background Ambulance Team Members: All Areas Background FPL/PSL Rev.2 CONFlDENT1AI.

4.2-15 01/31/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Medical Team MESSAGE NG,'~6 TME:~030 LOCATION: Martin Memorial Hos ital MESSAGE: When the patient is examined and evaluated by Medical Team: Vitals: Respiration:

Pulse: B/P: Skin: Pupils: 38, irregular.

110 186/100 Pale, clammy, moist Equal, responsive Patient is still disoriented, is getting stronger and more responsive.

Wound: There is a shallow laceration outside the right forearm between elbow and wrist approximately 18 cm in length.There is considerable venous bleeding and no evidence of any possible tendon/nerve damage.The patient is becoming more reactive to inquiry and stimuli and there may be an injury to the head caused by the fall.FPI/PSL Rev.2 CONFIOENTIAL 4.2-16 01/31/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Medical Team MESSAGE ND,'-TME:~05 LOCATION: Martin Memorial Hos ital MESSAGE: Additional patient status during examination:

Vitals: Pulse: Respiration:

B/P: Skin: 100 28 160/104 Pale, clammy, moist Patient is weak, slightly disoriented, but responsive and can answer inquiries.

FPUPSL Rev.2 CONFlDENllAL 4.2-17 01/31/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Health Ph sics Technician MESSAGE NG, M~I TME:~I050 LOCATION: Martin Memorial Hos ital AS MESSAGE: C II N'I IS I III ISde I I'AISIC members as they earn it by performing the appropriate action.Additional radiological survey results: Face and cheek: Right hand: Wound: 100 cpm)Bkg 100 cpm>Bkg 1500 cpm)Bkg FPL/PSL Rev.2 CONFlDENTtAL 4.2-18 01/31/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Health Ph sics Technician MEEEAGENG:.M

~I TEIEIIMII*A LOCATION: Martin Memorial Hos ital I MESSAGE: Post-Decon radiological survey results after the first decon: Face and cheek: Right hand: Wound: Background 100 cpm>Bkg 500 cpm>Bkg FPUPSL Rev, 2 CONFlOENTlAL 4.2-19 01/31/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Health Ph sics Technician MESSAGE NG,'.ll TIME:~Ill l LOCATION: Martin Memorial Hos ital MESSAGE: Post-Decon radiological survey results after the second decon: Right hand: Wound: Background 200 cpm>Bkg FPIJPSL Rev.2 CONFIDENTIAL 4.2-20 01/3 1/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Health Ph sics Technician MESSAGE NG:.M~II TIME:~ISS LOCATION: Martin Memorial Hos ital MESSAGE: Post-Decon radiological survey results after third decon: Wound: Background FPL/PSL Rev.2 CONFIDENTlAL 4.2-21 01/3 1/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Medical Team MESSAGE NG:.M~ll SME:~IIIII A LOCATION: Martin Memorial Hos ital MESSAGE: ENE L The third wound irrigation completes decontamination of the patient.All surveys now indicate Background.

You may now evaluate release of the patient to conventional treaunent areas.FPIJPSL Rev.2 CONFlDENTIAL 4.2-22 0 1/31/92 92EX MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Health Ph sics Technician MESSAGE NQ,'.IS TME:~I5tl LOCATION: Martin Memorial Hos ital MESSAGE'fter the transfer of the patient, proper exit and removal of protective clothing by Medical personnel-survey/status is: Patient: Stretcher:

Medical Team Members: All Areas Background All Areas Background All Areas Background FPIJPSL Rev.2 CONFIDENTIAL

~4.2-23 01/3 1/92 92EX

MEDICAL EMERGENCY MESSAGE FORM THIS IS A DRILL TO: Medical Team MEEEAGE NG:.M~4 TIME:~IEE*LOCATION: Martin Memorial Hos ital MESSAGE: The Radiological Medical Emergency Drill is terminated.

An in-place critique and discussion will take place.FFUPSL Rev.2 CONFlDENTlAL 4.2-24 01/31/92 92EX~M~E M MM, 4+4PMVIOVh N i%I MANIA'tk%4~~

CONRDENTIAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLAN'r 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 4.3 MINI SCENARIOS This scenario section contains detailed mini-scenarios for the following events: 4;3.1 4.3.2 4.3.3 4.3,4 Fire in the".1B5" 480 Volt Motor Control Center/Loss of the"lB3" 4160 Volt Switchgear "1A" AFW Pump Maintenance and Recovery Cross-Feed of the"1B2" 480 Volt Bus Public Information/Media Mini-Scenario FPIJPSL Rev.3 CONROENTIAL 4.3-1 01/31/92 92EX CONROENTlAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR'PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 4.3 MINI SCENARIOS GENERAL REPAIR TEAM CONTROLLER INFORMATION

'DO'NOT'ALLOW PL'AYERS'TO

>PHYSICALLY MOVE/CHANGE VALVES SWITCHES OR COMPONENT STATUS IN RESPONSE TO SIMULATED SCENARIO EVENTS.The actual movement or alteration of equipment and controls will affect Unit safety and operation and shall not be allowed in response to simulated scenario events.Players should indicate components to be altered and actions to be taken and then given information as to the response to the simulated action.Do not allow players to over-simulate response actions or skip over time required for response.If component disassembly is to be simulated, the necessary tools must be obtained in order to proceed with the simulation.

If replacement of parts is to be simulated, the actual procurement of the replacement part from stores should be accomplished in order to proceed with the simulation.

The following specific task information packages are designed to allow repair team controllers to provide sufficient feedback to players responding to simulated equipment casualties in the Exercise scenario.Provide information from the appropriate section to p'Eibypd'g'g 4 thh'g.not allow the Players to"over simulate" their response actions and thereby drastically reduce the time required for actual performance of the simulated task.Be sensitive to the frustration of the players common in situations of excessive simulation and try to avoid the loss of drillsmanship as a consequence of this impediment to their efforts.FPL/PSL Rev.3 CONR0ENTNL 4.3-2 01/31/92 92EX CONRDENTNL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 4.3 MINI SCENARIOS This scenario section contains detailed mini-scenarios for the following events: 4.3.1 4.3.2 4.3.3 4.3,4 Fire.in the".1BS" 480 Volt Motor Control Center/Loss, of the"1B3".4160 Volt Switchgear "1A" A&V Pump Maintenance and Recovery Cross-Feed of the"1B2" 480 Volt Bus Public Information/Media Mini-Scenario FPIJPSL Rev.4 CONR DEN'nAL 4.3-1 02/10/92 92EX CONFtDENTIAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 4.3 MINI SCENARIOS GENERAL REPAIR TEAM CONTROLLER INFORMATION DO NOT ALLOW PLAYERS TO.PHYSICALLY MOVE/CHANGE VALVES SWITCHES OR COMPONENT STATUS IN RESPONSE TO SIMULATED SCENARIO EVENTS.The actual movement or alteration of equipment and controls will affect Unit safety and operation and shall not be allowed in response to simulated scenario events.Players should indicate components to be altered and actions to be taken and then given information as to the response to the simulated action.Do not allow players to over-simulate response actions or skip over time required for response.If component disassembly is to be simulated, the necessary tools must be obtained in order to proceed with the simulation.

If replacement of parts is to be simulated, the actual procurement of the replacement part f'rom stores should be accomplished in order to proceed with the simulation.

The following specific task information packages arellesigned to allow repair team controllers to provide sufficient feedback to players responding to simulated equipment casualties in the Exercise scenario.Provide information from the appropriate section to U p'UEAltNi bypd g'g'bl h'g.D not allow the Players to"over simulate" their response actions and thereby drastically reduce the time required for actual performance of the simulated task.Be sensitive to the frustration of the players common in situations of excessive simulation and try to avoid the loss of drillsmanship as a consequence of this impediment to their efforts.FPL/PSL Rev.4 CONROEHTIAL 4.3-2 02/10/92 92EX

~~CONRDENTIAL 4.3.1 FIRE IN THE"1B5'-'80 VOLT MOTOR CONTROL CENTER/LOSS OF THE"1B3" 4160 VOLT SWITCHGEAR i.~Descri tion A short-circuit condition occurring in the"1BS" 480 Volt Motor Control Center (MCC)in the"B" Switchgear Room of the Unit 1 Reactor Auxiliary Building (RAB)results in the simulated discoloration of MCC cubicles, severe damage to MCC cabling and bussing and a fire burning within the cubicles and overhead cable trays.The initial grounding and arcing condition disrupts and severely damages the MCC and its internals.

As a result of the fire, cabling and insulation in the.overhead conduits and cable trays are burnt and produce heavy black smoke.The initial fire in the"1B5" MCC damages only the"1B5" and its load wiring.However, as a result of heat and firefighting efforts in close proximity to the"1B3" 4160 Volt Switchgear, a subsequent faulting and loss of the"1B3" switchgear will occur at 0930.II, Initial Conditions The fire controller should be standing by in the vicinity of the"1B5" 480 Volt MCC in the Unit 1"B" Switchgear Room in order to provide as-found conditions to the Fire Team upon their arrival.The scenario will begin with the presentation of fire alarm signals to the Nuclear Plant Supervisor (NPS)in the Unit 1 Control Room indicating the presence of smoke and heat in the Unit 1"B" Switchgear Room in conjunction with the loss of the"1BS" 480 Volt MCC and supplied loads electrically

.FPUPSL Rev.2 CONFIDENTIAL 4,3.1-1 02/10/92 92EX

CONROEHTIAL 4.3.1 FIRE IN THE"1B5" 480 VOLT MOTOR CONTROL CENTER/LOSS OF THE"1B3" 4160 VOLT SWITCHGEAR III.Scenario Time: Event: 0800 Fire alarms given in the Unit 1 Control Room (given by Controller message, Master Fire Panel Delta point number 1.07.01, Unit 1 Zone 7 A, and Delta point number 1.07.02, Unit 1 Zone 7 B)indicating heat and">.sm'oke'in'the area of the"B" Switchgear Room, Unit 1 RAB.Loss of the"1BS" 480 Volt MCC electrically.

Not~Operators should dispatch Senior Nuclear Plant Operator (SNPO)to investigate the alarms.Fire Controller should be staged at the vicinity of the 1BS Motor Control Center in the"B" Switchgear Room of the Unit 1 RAB to meet responding SNPO/Fire Team.An Electrical Maintenance Controller may be staged in the Operations Support Center (OSC)in order to respond with any Player maintenance teams dispatched, Electrical Maintenance Controller could support the Fire Controller onscene to cover the assessment actions taken after the fire is ouL 0805 (Approx.)SNPO should have responded to the"B" Switchgear Room on the 43'levation of the Unit 1 RAB and discovered heavy black smoke in the room caused by the"1BS" Motor Control Center.Notes: The responding Player will find heavy black smoke, Fire is burning primarily in the cable tray above the motor control center.The fire in the cable tray is reluctant to firefighting activity until the simulated request for off-site fire assistance at 0830.The last remaining slow-fire sources in the cable insulation will be out with the simulated arrival and support of off-site fire assistance by approximately 0845.As the Fire Team sets up agents and makes entry, the smoke will begin to lift and be primarily ceiling coverage, A search and rescue sweep of the room will find no lost or injured personnel in the fire area.0845 (Approx.)Any application of fire fighting agent by this time will have extinguished the fires.FPL/PSL Rev.2 CONROENTIAL 4.3.1-2 02/10/92 92EX

CONROENTNl 4.3.1 FIRE IN THE"1B5-" 480 VOLT MOTOR CONTROL CENTER/LOSS OF THE"1B3" 4160 VOLT SWITCHGEAR IO.Scenario (Continued)

Time: Event: 0930 Auxiliary Feed Actuation Signal (AFAS)attempts to start the"1B" Auxiliary Feed Water (AFW)Pump.As a.result of heat and firefighting efforts in the nearby"1B5" MCC, faulted relays and damaged current transformers (CTs)cause.the loss of the."1B3",4160 Volt Svyitchgear.

Initial Evaluation of Dama es: Cubicles in the"1BS" 480 Volt MCC are discolored, soot covered and severely burnt.There are doors and access panels blackened by smoke on the MCC in several locations on both sides.There is internal fire damage and conductor loss in several cubicles.The entire overhead cable tray is destroyed by fire, All the cabling and insulation is charred and useless.The damages to the"1B5" MCC are anticipated to prevent recovery of"1BS" loads for the duration of the exercise.Heat damage and exposure to fire fighting activities in the switchgear and cable trays adjacent to the"1B3" 4160 Volt Switchgear has resulted in damage to the degraded grid/undervoltage relays.When the"1B" AFW pump attempts to start on the AFAS signal, it trips on differential action.The"1B" Emergency Diesel Generator (EDG)autostarted on low voltage on the"1B3" bus, but never closes onto the bus.Failed Current Transformers (CTs)in the diesel cubicle and bus degradation are anticipated to prevent recovery of the"1B3" 4160 Volt bus for the duration of the exercise.FPIJPSL Rev.2 CONROENTIAL 4.3.1-3 02/10/92 92EX

~~CONRDENTIAl 4.3.1 FIRE IN THE"1B".480 VOLT MOTOR CONTROL CENTER/LOSS OF THE"1B3" 4160 VOLT SWITCHGEAR Detailed Evaluation of Dama es: "1B5" 480 Volt MCC: The fire in the"1B5" MCC has originated in several load modules near the center of the MCC.These controllers are destroyed.

Fire has spread along insulation and other conductors damaging them and the internal wiring before spreading to cable trays above the MCC.The cable trays are filled with burnt and carbonized insulation.,Conductors are bare of insulation, discolored and twisted."1B3" 4160 Volt Switchgear A multiple failure of the degraded grid/undervoltage relays is producing a complex fault condition.

A differential action has occurred on the startup of the"1B" AFW puinp as a result of heat damage to the"1B" diesel CTs in the end of the switchgear most closely exposed to the"1BS" fire.The multiple failures of contaminated and heat~aged circuitry in the switchgear has resulted in loss of stability and inability to reenergize the"1B3" 4160 Volt Switchgear or its individual loads.FPL/PSL Rev.2 CONFIDENTIAl 4.3.1-4 02/10/92 92EX CONFIOENTIAL 4.3.2"IA" AUXILIARY FEED WATER PUMP MA3ÃI'ENANCE L~Descri tion Ongoing maintenance on the"1A" Auxiliary Feed Water (AFW)Pump is postulated to be occurring at the beginning of the Exercise scenario.The subsequent unrecoverable loss of the"1B3" 4160 Volt Switchgear renders the"1B" AFW Pump powerless.

The lockup of the turbine bearings on the"1C" AFW pump disables it.As a result, the recovery of the"1A" AFW pump is not only important to the restoration of Steam Generator (S/G)feed,.but is mandated by scenario events and will occur at 1200 by Contingency Message if necessary.

The anticipated recovery attempts are considered to be: 1.Reassemble and remount the"lA" AFW Pump Motor.2, Cross-Over power from the"1A" AFW Pump to the"1B" AFW Pump.3."Rob" the"1B" AFW motor and mount it on the"1A" AFW baseplate.

II.~IMAM C Ch'he"1A" AFW Pump is simulated to be undergoing motor bearing replacement.

The motor was tagged-out, disconnected mechanically and electrically and lifted from the pump baseplate.

Both endbells have been removed and the couplingwnd bearing has been pulled.Due to the maintenance in progress, it may be assumed that all rigging and mounting/demounting tools are in the pumproom.However, any additional tools or materials that the Players wish to utilize in the recovery actions should be actually obtained and transported to the area real-time.

FPL/PSL Rev.3 CONRDENTIAL 4.3.2-1 02/10/92 92EX CONRDENTIAL 4.3.2"1A" AUXILIARY.

FEED WATER PUMP MAINTENANCE III, Scenario TIme: Event: 0730 The"1A" AFW Pump has been tagged out and disassembly begun since 1600, February 11, 1992, when the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO clock began.0930 Major break in the condensate suction header causes loss of Main Condensate Pumps and Main Feed Pumps.Auxiliary Feed Actuation Signal (AFAS)attempts to start the"1B" Auxiliary Feed Water (AFW)Pump.As a result of heat and firefighting efforts in the nearby"1B5" 480 Volt MCC, damaged and faulted relays cause the loss of the"1B3" 4160 Volt Switchgear that supplies power to the"1B" AFW Pump.0945 Loss of oil in the operating"1C" AFW pump causes the pump turbine bearings to lock up, Total Loss of Feed (TLOF).1000 (Approx.)As a result of the TLOF, repair team(s)should be dispatched to attempt and recover the"lA" AFW pump or to investigate restoration of the"1B" AFW Pump, 1145 A Contingency Message will be given (if required)that repair attempts on the"1A" AFW pump are successful and the pump will be available by 1200.1200 The"1A" AFW pump begins feeding the dry S/G.FPL/PSL Rev.3 CONFlDENTlAL 4,3.2-2 02/10/92 92EX

CONFlDENTlAL 4.3.2"1A" AU3GLIARY.FEED WATER PUMP MAJÃI'ENANCE IV.Detailed Controller Guidance The recovery of the"1A" AFW pump is crucial to scenario data fidelity and must occur at 1200.However, the efforts of repair team(s)assigned to the task may warrant the use of simulated delay or the Contingency of accelerated repair.Whether Players choose to reassemble the"1A" motor, crosswonnect the"lA" power to the"1B" pump motor or"rob" the"1B" motor, ensure that the simulated activity is performed as realistically as possible and simulation of obtaining parts, tools and work tasks is minimized (with the exception of lifting and slinging equipment which is assumed to be present.)In'this regard, any or all"of'the following items might be utilized for controlling the time interval for recovery: A baseplate bolt has stripped-out and must be retapped or helicoiled before the motor may be remounted and aligned.Coupling aligning tools and shims must be actually obtained and brought to the scene.The coupling lock screw(s)and key on the motor are damaged and must be repaired/replaced before the motor can be recoupled and aligned.If the Players attempt to energize the"1B" AFW pump from the"1A" pump power feeds, the AFW isolation valves on the"B" side (unpowered as a result of the loss of the"B" side power)may~nt be opened manually.The motor operator(s) are hydraulically locked by grease in the bellville washer assembly and the motor operator will not declutch.If further action is taken, the valve disk is wedged tight into the seats and cannot be moved.FPL/PSL Rev.3 CONR0ENTIAL 4.3.2-3 02/10/92 92EX CONHDENTIAL

4.3.3 Cross

Feed of the"1B2" 480 Volt Bus Summa~: The lockout and loss of the"1B3" 4160 Volt bus results in the loss of feed to the"1B2" 480 Volt bus and its associated loads.The loss of the"B" side of 480 Volt AC is an important loss due to the many loads associated with it.There is a method of"cross-feeding" the"1B2" 480 Volt bus from the"1A2" 480 Volt bus utilizing the"lAB" bus as a bridge.The recovery of the"1B2" bus and loads is not anticipated during the duration of the scenario and must be prevented in order to maintain scenario data integrity.

The Controller providing information to the team(s)simulating repair actions on this action should provide data in accordance with the following guidelines to allow the Players to perform play action relevant to the scenario.UIDANCE Initial Inspection:

The"1AB" bus supply cabling to the"1B2" 480 Volt Loadcenter is damaged by the recent fire in the nearby"1AS" 480 Volt Motor Control Center.All attempts to jumper and close the bus onto the"1AB" bus will result in an immediate protective action trip.There is heat-damaged and burnt insulation in the"1B2/1AB" connecting cables and breakers.Anticipated Actions: 1.Attempt to jumper and cross-feed the"1B2" and"1A2" 480 Volt busses through the"1AB" bus.2.Inspect and test the"1B2/1AB" breakers and supply circuits.FPUPSL Rev.1 CONRDENTlAL 4.3.3-1 02/10/92 92 EX CONRDENTNL

4.3.3 Cross

Feed of the"1B2" 480 Volt Bus Response to Actions: 1.The actual manipulation of the"1A2, lB2 and lAB" breakers SHOULD NOT BE PERFORMED; however, the actions required to perform this step should be simulated in a realistic fashion.The conductors and breakers between the"1B2" and the"1AB" 480 Volt busses will trip free.The breakers may not be reclosed without an immediate retrip.2.Once the proper tools are assembled for simulated opening and testing of the breaker housings and control circuits, the following conditions are found: There is a hard ground on all three conductors on the"1B2" side of the connections.

Continue to provide information and guidance to the team(s)as required, The"1B2" 480 Volt bus is not anticipated to be recovered during this scenario and may not be recovered in order to maintain scenario data fidelity.FPL/PSL Rev.1 CONRDENTlAL 4.3.3-2 02/10/92 92 EX CONRDENTlAL

4.3.4 Public

Information/Media Mini-Scenario I.Summary: The fire occurring in the Unit 1"B" Switchgear room causes media attention as a result of the call for offsite assistance being overheard on scanner.The station has begun making calls to the Corporate Communications Duty Officer requesting information to cover the event.Media Control"cell" simulating the news desk of the TV station should aggressively seek information from the Corporate Communications Duty Officer by phone.II.Guidance Initial Action: The simulated arrival of the off-site fire assistance group at 0840 should be followed shortly by phone calls requesting information on the event.By 0845, the Media Controller"cell" should be calling the General Office (GO)Corporate Communications Officer requesting information on the situation and activities at the site.At 0905, an actual call for offsite ambulance will occur in response to the emergency medical scenario and this should fuel the media demands for information on the events in progress.Anticipated Actions: Media Controller"cell" begins calling the Media information line in the GO requesting immediate details on the fire in Unit 1 from the Corporate Communications Duty Officer.FPIJPSL Rev.2 CONRDENTIAL 4.3.4-1 02/10/92 92EX CONRDENTIAL

.4.3.4 Public Information/Media Mini-Scenario IIL~Messa es: The Media Controller"cell" should begin calling the GO Corporate Communications Officer at 0845 and relaying the following messages at the following numbers: (305)552-3894 (305)552-3895¹1: THIS IS A DRILL, This is the Channel 5 newsdesk.We hear that there has been a fire or'explosion or something out there at the St.Lucie Site.There is a fire company responding and we may want to roll a helicopter or mobile crew to get some video of this event.Will you confirm and detail the events in progress?THIS IS A DRILL¹2:~..THIS IS A DRILL, This is Channel 5 news again.What exactly is the problem?Is there a radiation leak?Why did the problem require outside fire help?We hear that there is a declared emergency of some sort.What public protective measures are being taken?THIS IS A DRILL¹3: THIS IS A DRILL, This is Channel 5.We may want complete access for crews so that we can provide full and live public information on this event.Are you going to allow our mobile crews into your Plant emergency facilities to provide this public information if we dispatch them out there?THIS IS A DRILL¹4: (After 0910)THIS 1$A DRILL, This is Channel 5.There's an ambulance ordered for radiation injuries.How many people are injured?Is there a major radiation leak?Are people in danger?.Why haven't you provided this information on a serious problem with exposed and injured workers to the public yet?We are ready to disseminate the information if you will only cooperate.

THIS IS A DRILL FPIJPSL Rev.2 CON ROENTlAL 4.3.4-2 02/10/92 92 EX CONRDENTIAL

4.3.4 Public

Information/Media Mini-Scenario

¹5'PIS IS A DRILL, This is Channel 12.We hear that there is a major radiation accident out at the St.Lucie Plant with dead and injured personnel.

We also hear that you are"scooping" this incident to Channel 5.We demand full and equal information.

THIS 1$A DRILL FPL/PSL Rev.2 CONFIDENTIAL 4.3.4-3 02/10/92 92 EX CONROENTNL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLA'NT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 5.0 PLANT PARAMETER DATA This Scenario Section Contains the Following Information:

Section 5.1 Section 5.2 Section 5.3 PLANT PARAMETER DATA

SUMMARY

-A listing of all pertinent plant parameters generated on the PSL simulator for the postulated scenario events.PLANT PARAMETER DATA CARDS-The above pertinent plant parameters broken down by time interval for presentation to the Players in the Control Room.ANNUNCIATOR MIMIC SHEETS-Mimics of annunciators associated with the plant parameter data timed for concurrent presentation with the Plant Parameter.

Data Cards.FPIJPSL Rev.0 CONFIDENTtAL 5.0-1 12/06/91 92EX

5.1 PLANT

PARAMETER DATA

SUMMARY

St.Lucle Nuclear Plant 1992 Evaluated Exercise~TIME 07:45 08:00 08:05 NUCLEAR INSTRUMENTATION REACTOR POWER (%)LINEAR RANGE 100.9 100.9 100.9 LOG WIDE RANGE 100.2 100.2 100.2 08:10 08:15 100.9 100.9 100.2 100.2 08:30 08:35 08:40 08:45 09:00 100.3 98.7 96.5 94.6 87.3 99.6 98.0 95.9 94.0 86.8 REACTOR COOLANT SYSTEM (RTGB/QSPDS)

TAVE (F)T COLD (F)T HOT (F)LOOP A LOOPB LOOP A1 LOOP A2 LOOP B1 LOOP B2 LOOP, A LOOP B 573.5 573.5 573.5 573.5 573.6 573.6 573.6 573.6 549.0 549.0 549.0 549.0 548.7 548.7 548.7 548.7 549.0 549.0 549.0 549.0 549.0 549.0 549.0 549.0 598.2 598.2 598.2 598.2 598.3 598.3 598.3 598.3 573.5 573.3 572.8 572.6 573.6 573.4 572.9 572.8 549.0 548.8 548.7 549.0 548.7 548.6 548.4 548.8 549.0 548.9, 548.8 549.1 549.0 548.9 548.8 549.2 598.2 597.9 597.1 596.4 598.3 597.9 597.1 596.4 572.4 567.3 572.5 567.4 549.3 545.7 549.0 545.4 549.3 545.8 549.4 545.8 595.6 589.0 595.7 589.1 RCS PRESSURE (PSIA)LOOP FLOW (dp)LOOP A1 LOOP A2 LOOP B1 LOOP B2 71.3 71.3 71.3 71.3 71.3 71.3 71.3 71.3 71.8 71.8 71.8 71.8 71.4 71.4 71.4 71.4 71.3 71.3 71.3 71.3 71.3 71.3 71.3 71.3 71.8 71.8 71.8 71.7 71.4 71.4 71.4 71.4 71.3 71.4 71.3 71.4 71.7 71.8 71.4 71.5 2239.1 2235.3 2235.1 2235.0 2234.8 2251.1 2249.0 2250.0 2250.0 2249.9 PZR LEVEL (%)PZR TEMP (F)63.3 63.3 63.3 63.3 652.1 651.8 651.8 651.8 63.3 63.9 63.4 63.9 651.8 652.8 652.7 652.7 64.1 59.0 652.8 652.8 QUENCH TANK LEVEL (%)QUENCH TANK TEMP (F)QUENCH TANK PRESS (PSIG)63.1 63.1 90.6 90.6 5.6 5.6 63.1 63.1 90.6 90.6 5.6 5.6 63.1 63.1 90.6 90.6 5.6 5.6 63.1 63.1 90.6 90.6 5.6 5.6 63.1 63.1 90 6 90.6 5.6 5.6~=UNPOIVEEED/INVALID DATA POINT FPIA'SL Rev.1 5.1-1 02/10/92 92 EX St.Lucie Nuclear Plant 1992 Evaluated Exercise~TIME 05i45 CHEMICAL&VOLUME CONTROL SYS LETDOWN FLOW (GPM)VCT LEVEL (%)CHARG.FLOW (GPM)CHRG PUMP (ON/OFF)A B C BORONOMETER (PPM)08:40 08:45 09:00 38.9 37.6 38.8 56.7 56.7 56.7 44.0 44.0 44.0 76.5 70.2 76.7 57.1 58.2 58.7 87.9 87.9 87.8 38.4 38.1 56.7 56.7 44.0 44.0 78.4 64.S 59.6 36.2 87.9 87.9 ON ON ON ON ON OFF OFF OFF OFF OFF OFF OFF OFF OFF OFF 668.5 668.5 668.5 668.5 668.5 ON ON ON ON OFF OFF 673.7 680.8 ON ON ON ON ON ON OFF OFF OFF 669.2 670.3 671.8 08:00 08:05 08:10 08:15 08:30 08:35 CORE COOLING (QSPDS)SUBCOOLED MONITOR (F)A 53.7 B 53.7 CORE EXIT THERMOCOUPLE (F)HIGHEST CET A 600.4 B 600.7 REPRESENTATIVE CET A 612.2 B.612.1 RX VESSEL LEVEL (%)A B 54.8 55.5 56.3 57.0 63.6 54.8 55.5 56.3 57.0 63.6 53.5 53.4 53.5 53.4 53.5 53.5 53.5 53.5 598.6 598.3 591.3 598.8 598.1 591.4 610.2 610.2 602.7 610.2 609.8 602.6 600.8 600.9 600.8 600.8 600.7 600.7 600.9 600.2 599.4 600.9 600.5 599.6 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 100 612.1 612.5 612.4 612.2 611.7 610.8 612.1 612.6 612.6 612.5 611.9 611.0 CONTAINMENT PRESSURE (PSIG)TEMP (F)SUMP LEVEL (FI)WIDE RANGE NARROW RANGE 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 99.8 99.4 99.3 99.2 99.1-98.9 9S.8 98.7 98.7 9S.5-1.0-1.0-1.0-1.0-1.0-1.0 ,-1.0-1.0-1.0-1.0-6.3-6.4-6.4-6.4 6.5 6.5 6.6 4.6-6.6-6.7 CONT.H2 (%)0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0~=UNPOWEEED/INVALID DATA POINT FPL/PSL Rev.1 5.1-2 02/10/92 92 EX

4 St.Lucle Nuclear Plant 1992 Evaluated Exercise~TIME 07:45 ENGINEERED SAFETY FEATURES HPSI LOOP FLOW (GPM)Al 0 A2 0 BI 0 B2 0 LPSI LOOP FLOW (GPM)AI A2 Bl B2 CONT.SPRAY PUMP FLOW (GPM)A B 0 0 0 0 0 0 0 0 0~0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 SIT LEVEL (%)08:00 08:05 08:10 08:15 08:30 08:35 08:40 08:45 09:00 AI BI B?SIT PRESSURE (PSIG)AI A2 BI B2 86.0 86.0 86.2 86.2 86.2 86.2 86.2 86.2 86.0 86.0 86.0 86.2 86.2 86.2 86.2 86.2 86.2 86.2 86.2 86.2 213.5 213.5 213.5 213.5 213.5 215.6 215.6 215.6 215.6 215.6 213.8 213.8 213.8 213.8 213.8 214.1 214.1 214.1 214.1 214.1 86.0 86.0 86.0 86.2 86.2 86.2 86.2 86.2 86.2 86.2 86.2 86.2 213.5 213.5 213.5 215.6 215.6 215.6 213.8 213.8 213.8 214.1 214.1 214.1 86.0 86.0 86.2 86.2 86.2 86.2 86.2 86.2 213.5 213.5 215.6 215.6 213.8 213.8 214.1 214.1~i,:::,.:':

'=UNFOWEEEDENVALID DATA FOINT FPL/PSL Rev.I 5.1-3 02/10/92 92 EX STEAM GENERATORS SG LEVEL WR (%)St.Lucle Nuclear Plant 1992 Evaluated Exercise~TIME 07:45 08:00 08:05 08:10 08:15 08:30 08:35 08:40 08:45 00:00 SG LEVEL NR (%)A B A B SG PRESSURE (PSIG)A B FEED FLOW (LB/HR)A B STEAM FLOW (LB/HR)A B SG BLOW DOWN FLOW (GPM)A B 58.8 58.8 58.8 58.6 58.6 58.6 58.8 58.6 63.1 63.1 63.4 63.4 63.1 63.4 63.1 63.4 858.1 858.2 858.1 858.2 858.1 858.1 858.2 858.2 58.8 58.4 58.6 58.4 63.1 61.4 63.4 62.7 858.1 858.5 858.2 858.7 58.8 59.2 59.1 59.3 58.9 59.2 59.1 59.3 63.2 64.5 64.0 64.4 65.6 65.2 63.7 64.9 858.4 858.5 863.9 864.0 868.3 868.4'848.9 849.0 10 15 10 10 15 15 10 15 10 10 10 10 10 10 15 15 15 15 15 15 5830250 5830460 5829920 5830110 5830620 5807810 5729040 5583050 5442340 5040900 5843530 5843300 5843550 5843680 5844560 5821470 5745250 5596310 5455480 5055520 5809590 5809700 5809710 5809700 5809700 5759990 5676400 5538910 5417740 5008040 5823220 5823300 5823340 5823330 5823340 5774020 5690260 5553080 5431590 5021370 CONDENSER BACK PRESS (in.'.2.6 2.6 2.6 ELECTRICAL PLANT EDG LOAD (MW)2.6 2.6 2.6 2.6 2.5 2.5 2.4 A B 4160V VITAL BUS (VOLTS)1A3 1B3 68KV SWGR (VOLTS)1A1 1B1 0 0 0 0 0 0 0 0 4126.3 4126.2 4125.5 4127.1 4125.5 4126.9 4128.3 4133.4 4133.2 4135.2 4135.2 4135.1 4134.1 4136.4 6966.4 6966.3 6966.3 6966.4 6966.2 6968.8 6972.8 6967.1 6967.1 6967.2 6967.2 6967.2 6969.5 6973.7 4132.3 4136.7 4146.6 4140.3 4143.8 4154.7 6979.7 6985.8 7004.4 6980.6 6986.6 7005.3~=UNPO7VERED/INVALID DATA FOINT FPL/PSL Rev.1 5.1Q 02/10/92 92 EX St.Lucle Nuclear Plant 1992 Evaluated Exercise AUXILIARY SYSIXMS AFW FLOW (GPM)TANK LEVEL RWT (FT)CST (FT)PWT (FT)BAMT (%)~TIME 07:45 08:00 08:05 08:10 08:15 08:30 08:35 08:40 08:45 00:00 A B C 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 26.2 26.2 26.2 26.2 26.2 26.2 26.2 26.2 26.2 26.1 19.8 19.8 19.8 19.8 19.8 19.8 19.8 19.8 19.8 19.8 A B 91.9 91.9 92.4 92.4 91.9 91.9 91.9 90.9 90.4 89.9 89.4 87.9 92.4 92.4 92.4 92.4 92.4 92.4 92.4 92.4 COOLING WATER CCW HEADER (GPM)A B ICW HEADER (PSIG)A B 41 41 41 41 41 41 41 41 41 41 41 41 41 41 41 41 42 42 43 43 6551 6542 6536 6531 6573 6559 6564 6549 6549 6545 6978 6980 6979 6952 6976 6977 6986 6982 6990 6973 CONDENSER HOTWELL LEVEL (FQ 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7~=DNPOWERED/INVALID DATA POINT FPL/PSL Rev.1 5.1-5 02/10/92 92 EX MINIE NUCLEAR INSTRUMENTATION REACTOR POWER (%)LINEAR RANGE LOG WIDE RANGE St.Lucie Nuclear Plant 1992 Evaluated Exerche 09:15 09:30 09)35 09:40 09:45 09:50 09:55 10:00 10:15 10:20 75.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0.0.74.9 4.0 4.05E-03 8.84E-QS 2.10E46 1.13E-07 6.79E4)8 6.61E48 6.58E-08 5.57E4)8 5.07E-08 REACTOR COOLANT SYSTEM (RTGB/QSPDS)

T AVE (F)T COLD (F)T HOT (F)LOOP A LOOPB LOOP A1 LOOP A2 LOOP B1 LOOP B2 562.1 545.5 536.9 531.1 536.3 529.7 523.4 562.2 545.7 537.1 531.2 536.8 53Q.1 523.7 543.1 545.0 536.3 530.0 524.9 519.7 513.7 542.8 544.7 536.0 529.9 527.3 520.6 514.7 543.2 545.1 536.4 530.2 5249 519.7 513.7 543.2 545.1 536.5 530.2 527.4 520.7 514.7 517.5 445.4 425.6 517.8 445.8 427.0 507.9 428.9 411.0 508.8 428.7 409.7 507.9 429.6 412.6 508.9 429.4 412.8 LOOP A LOOP B RCS PRESSURE (PSIA)LOOP FLOW (dP)LOOP A1 LOOP A2 LOOP B1 LOOP B2 PZR LEVEL (%)PZR TEMP (F)QUENCH TANK LEVEL (%)QUENCH TANK TEMP (F)QUENCH TANK PRESS (PSIG)581.2 546.2 S37.7 532.2 546.5 S39.3 532.6 526.7 462.0 440.9 581.2 S46.3 537.9 532.2 547.4 540.0 533.2 527.2 462.0 441.3 2250.0 2199.5 2111.7 2113.3 1880.3 1659.5 1467.5 1298.2 502.8 389.3 71.4 70.8 71.0 5.3 O.Q 0.0 0.0 0.0 0.0 71.4 70.8 71.0 5.4 0.0 0.0 0.0 0.0 0.0 71.8 71.2 71.4 5.5 0.0 0.0 0.0 0.0 71.5 7Q.9 71.1 5.3 0.0 0.0 0.0 0.0 0.0 55.3 42.2 34.4 29.9 36.6 35.9 35.1 34.4 100.0 100.0 652.8 649.3 644.0 642.4 628.3 610.8 594.2 578.1 469.9 447.7 5.6 5.6 5.6 5.6 5.6 5.6 5.6 5.6 1.4 3.0~i::i::.i.i:i..::::.::

=UNPOVIEEED/INVALID DATA POINT FPL/PSL Rev 1 5.1-6 02/10/92 92 EX

~TIME 00:15 00:50 St.Lucle Nuclear Plant 1992 Evaluated Exercise 09:35 09:40 09:45 09:50 09:55 10:00 10:15 10:20 STEAM GENERATORS SG LEVEL WR (%)SG LEVEL NR (%)A B 59.5 50.3 59.6 50.0 45.3 39.5 35.7 31.1 26.7 22.7 7.5 44.8 38.5 35.4 31.0 26.9 22.9 8.0 2.3 2.8 0.0 0.0 0.0 0.0 0.0 0.0 63.0 33.0 13.0 0.0 64.2 32.0 11.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 A B SG PRESSURE (PSIG)A B FEED FLOW (LB/HR)A B STEAM FLOW (LB/HR)A 4244660 B 4256520 SG BLOW DOWN FLOW (GPM)A 10 B 15 845.0 972.5 897.0 866.1 829.4 787.0 746.9 708.2 845.1 972.6 897.0 866.1 841.7 793.7 753.6 7 14.1 4287670 0 4299090 0 415.7 2'78.6 414.8 280.0 CONDENSER BACK PRESS (in..2.1 15.0 25.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 ELECTRICAL PLANT EDG LOAD (MW)A B 4160V VITAL BUS (VOLTS)1A3 1B3 69KV SWGR (VOLTS)1A1 1B1 0 0 4167.3.4248.6 4249.0 4251.8 4257.1 4257.2 4257.9 4258.2 4252.9 4253.9 4174.3 00 00 00 00 00 0.0 00 00 00 7037.5 7017.9 7018.6 7022.4 7024.5 7024.5 7024.8 7024.9 7022.3 7022.7 7038.3 7032.8 7033.2 7035.6 7035.7 7035.7 7035.7 7035.7 7035.3 7035.3~i:::::::::::::::'::::

=UNPOWEEED/INVALID DATA POINT FPL/PSL Rev.1 5.1-9 02/10/92 92 EX

St.Lucle Nuclear Plant 1992 Evaluated Exercise~TIME 10:25 10:30 10:45 NUCLEAR INPIRUMENTATION REACTOR POWER (%)LINEAR RANGE 0.0 0.0 0.0 LOG WIDE RANGE 4.69E-08 4.45E-08 3.99E4)8 11:00 11:05 11:10 11:15 11:30 11:35 11:40 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3.85E4)8 3.86E-08 3.85E-08 3.82E-08 3.70E-08 3.65E-08 3.61E-08 REACTOR COOLANT SYSTEM (RTGB/QSPDS)

TAVE(F)LOOP A 414.9 413.2 404.9 LOOPB 415.7 413.7 407.0 T COLD (F)P 402.3 406.0 425.5 431.9 405.1 408.9 428.3 434.8 446.1 450.2 454.2 448.9 453.0 457.0 T HOT (F)LOOP A1 LOOP A2 LOOP B1 LOOP B2 LOOP A LOOP B 390.4 388.6 376.6 376.1 383.6 391.1 398.6 390.6 388.3 376.3 375.8 383.3 390.8 398.3 391.3 389.5 380.5 382.0 389.5 397.0 404.5 392.0 388.8 379.8 381.3 388.8 396.3 403.8 439.4 437.9 433.4 428.6 428.6 460.0 465.4 439.8 438.3 433.8 428.6 428.6 460.0 465.4 421.1 428.6 436.1 420.8 428.3 435.8 427.0 434.5 442.0 426.3 433.8 441.3 471.2 471.9 472.4 471.2 471.9 472.4 RCS PRESSURE (PSIA)LOOP FLOW (dp)LOOP A1 LOOP A2 LOOP B1 LOOP B2 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0" 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 388.1 426.4 437.2 376.2 376.2 479.2 400.7 413.9.420.0 374.9 PZR LEVEL (%)PZR TEMP (F)QUENCH TANK QUENCH TANK QUENCH TANK 100.0 100.0 100.0 100.0 100.0 100.0 100.0 100.0 100.0 100.0 451.0 452.4 449.8 444.0 447.8 450.1 451.3 454.5 455.2 455.6 LEVEL (%)'-,:.:-,::::.43'.Il',-:::,":::::,-':.:::::.:::::63 I::::::.."::'P';:.:1:':-,::::,::.::,::.:,::::53:;:I:'::,":-:',::

PRESS (PSIG)8.9 11.1 13.9 5.3 5.9 11.0 4.8 11.1 12.5 13.4 r~i:::::::::::::::::':::::::::::,:

=DNPO2VEEED/INVALID DATA POINT FPL/PSL Rev.1 5,1-11 02/10/92 92 EX

STEAM GENERATORS SG LEVEL WR (%)St.Lucle Nuclear Plant 1992 Evaluated Exercise~TIME 10:25 10:30 10:45 11:00 ll:05 11:10 11:15 ih30 II:35 ll:40 SG LEVEL NR (%)A B 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 A B SG PRESSURE (PSIG)A B FEED FLOW (LB/HR)A B STEAM FLOW (LB/HR)A 0 B 0 SG BLOW DOWN FLOW (GPM)A 0 B 0 0 0 0 0 0 0 0 0 0 0.0 0 0 0 0 0 0 0 226.8 87.1 13.5 13.5 13.5 13.5 13.5 13.5 13.5'13.5 227.3 95.9 14.1 14.1 14.1 14.1 14.1 14.1 14.1 14.1 CONDENSER BACK PRESS (ln.H 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 ELECTRICAL PLANT EDG LOAD (MW)A B 4160V VlTAL BUS (VOLTS)lA3 1B3 6.9KV SWGR (VOLTS)1A1 1B1 4252.1 0.0 7022.0 7035.3 0 0 0 0 0 0 0 0 0 0 4252.1 4253.9 4257.0 4258.1 4258.1 0.0 0.0 0.0 0.0 0.0 7022.0 7022.7 7023.9 7024.3 7024.3 7035.3 7035.3 7035.4 7035.4 7035.4 4257.1 4257.0 0.0 0.0 7D23.9 7023.9 7035.4 7035.4 0 0 0 0 4258.1 4257.0 0.0 0.0 7024.3 7023.9 7035.4 7035.4~i::::,:i::ii:,::i::::::,:::,::::::::

=UNPOWEEED/INVALID DATA POINT FPL/PSL Rev.1 5.1-14 02/10/92 92 EX

0-5.2 2.0-5.2 2.0-2.3-2.3 440.8 438.4 437.5 425.8 417.3 440.8 438.4 437.5 425.8 417.3 1463.0 1485.0 1484.0 1477.0 453.1 1464.0 1486.0 1485.0 1476.0 453.1 0 0 0 0 10 20 40 40 70 80 0 0 0 0 10 20 40 40 70 80 St.Lucle Nuclear Plant 1992 Evaluated Exercise~TIME 11:45 12:00 12:05 12:10 12:15 12:20 12:25 12:30 12:45 13:00 CHEMICAL 8r, VOLUME CONTROL SYS LETDOWN FLOW (GPM):-::::.-:-:.,-.:94+'.'-..

,:::::-':,::94.:8:::::.::,::-::::.::::::.:,'::94'.:8.::".::,:,-'.::::::,:,'941:

VCT LEVEL (%)CHARG.FLOW (GPM)79.8 80.2 80.2 80.2 80.2 80.2 80.2 80.2 80.2 80.2 CHRG PUMP (ON/OFF)A ON ON ON ON ON ON ON ON ON ON B OFF OFF OFF OFF OFF OFF OFF OFF OFF OFF C ON ON ON ON ON ON ON ON ON ON BORONOMETER(PPM)

CORE COOLING (QSPDS)SUBCOOLED MONITOR (Fj A-29.5 0.2-1.7-0.8 2.5 4.5 2.2 B-29.5 0.2-1.7 4).8 2.5 4.5 2.2 CORE EXIT THERMOCOUPLE (F)HIGHEST CET A 1447.0 1473.0 1474.0 1465.0 443.1 B 1446.0 1473.0 1473.0 1464.0 443.1 REPRESENTATIVE CET A B RX VESSEL LEVEL (%)A B CONTAINMENT PRESSURE (PSIG)TEMP (F)SUMP LEVEL (FT)WIDE RANGE NARROW RANGE CONT.H2 (%)5.7'.4 6.5 6.5 160.2 170.8 170.9 171.1 6.6 6.6 6.7 6.7 6.9 7.0 171.2 171.3 171.5 171.6 172.0 172.3 4.9 5.5 5.7 5.8 6.0 6.1-6.3 6.4 6.9 9.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1.4 1.8 1.8 1.8 1.8 1.8 1.8 1.8 1.8 1.8~i'::::::.:','::::::'::,:.::..:::::::

=UNPOIVEEED/INVALID DATA POINT FPL/PSL Rev.1 5.1-17 02/10/92 92K X St.Lucle Nuclear Plant 1992 Evaluated Exercise~TIME I I:45 ENGINEERED SAFETY FEATURES HPSI LOOP FLOW (GPM)A1 0 A2 0 B1 0 B2 0 LPSI LOOP FLOW (GPM)A1 A2 B1 B2 CONT.SPRAY PUMP FLOW (GP A B 12:00 12:05 12:10 12:15 12:20.12:25 12:30 12t45 13:00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 SIT LEVEL (%)Al A2 B1 B2 SIT PRESSURE (PSIG)A1 A2 B1 B2 0 225 300 400 475 500 825 1000 0 225 300 400 475 500 825 1000 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M)0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 86.0 86.0 86.0 78.0 74.0 71.0 70.0 64.0 47.0 32.0::.::.::.:'.::.86/:,::.::.::.::.::.

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86.2 86.2 86.2 80.0 75.0 72.0 70.0 65.0 43.0 30.0 213.5 213.5 213.5 199.7 194.7 189.7 184.7 182.7 159.7 144.7'.:::".:: P 1$'5.::,::.:.::.::215,'6,.::::".

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214.1 214.1 214.1 199.7 194.7 189.7 184.7 182.7 159.7 144.7~=UNPO5VEEED/INVALID DATA POINT FPL/PSL Rev.1 5.1-18 02/10/92 92EX SI EAM GENERATORS SG LEVEL WR (%)St.Lucle Nuclear Plant 1992 Evaluated Exercise~TIME 11:45 12200 12:05 12:10 12:15 12:20 12:25 12:30 12:45 13:00 SG LEVEL NR (%)A B 0.0 10.0 20.0 30.0 35.0 38.0 40.0 45.0 61.0 63.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 A B SG PRESSURE (PSIG)A B FEED FLOW (LB/HR)A B STIR%M FLOW (LB/HR)A B SG BLOW DOWN FLOW (GPM)A B 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 12.0 68.0 70.0 0.0 0.0 0.0 13.5 100.0 150.0 14.1 14.1 14.1 185.0 180.0 175.0 170.0 14.1 14.1 14.1 14.1 168.0 145.0'130.0 14.1 14.1 14.1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0~0 0 1 0 0 0 0 0 0~0 0 0 0 0 0 0 0 0 I 0 0 0 0 0 CONDENSER BACK PRESS (ln.H 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 ELECTRICAL PLANT EDG LOAD (MW)0 0 0 0 0 0 4256.2 4256.2 0.0 0.0 7023.6 7023.6 7035.4 7035.4 4256.2 0.0 A B 4160V VH'AL BUS (VOLTS)1A3 4257.8 1B3 0.0 69KV SWGR (VOLTS)1A1 7024.2 7023.6 1B1 7035.4 7035.4~=UNPOIVEEED/INVALID DATA POINT 0 0 4256.2 4256.2 0.0 0.0 7023.6 7023.6 7035.4 7035.4 4256.2 4256.2 4256.2 4256.2 0.0 0.0 0.0 0.0 7023.6 7023.6 7023.6 7023.6 7035.4 7035.4 7035.4 7035.4 FPL/PSL Rev.1 5.1-19 02/10/92 92EX

SI EAM GENERATORS SG LEVEL WR (%)~TIME I3: I5 13:30 St.Lucle Nuclear Plant 1992 Evaluated Exercise 13:45 14:00 14:15 14:30 14:45 15:00 SG LEVEL NR (%)A B 63.0 63.0 0.0 0.0 63.0 63.0 0.0 0.0 63.0 63.0 63.0 63.0 0.0 0.0 0.0 0.0 A B SG PRESSURE (PSIG)A B FEED FLOW (LB/HR)A B STEAM FLOW (LB/HR)A.B SG BLOW DOWN FLOW (GPM)A B 115.0 100.0 95.0 14.1 14.1 14.1 93.0 88.0 85.0 80.0 75.0 14.1 14.1 14.1 14.1 14.1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 70.0 70.0 70.0 70.0 70.0 70.0 70.0 70.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 CONDENSER BACK PRESS (ln.H 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 ELECTRICAL PLANT EDG LOAD (MW)A B 4160V VITAL BUS (VOLTS)1A3 1B3 68KV SWGR (VOLTS)1A1 1Bl 0 0 4256.2 4256.2 4256.2 4256.2 4256.2 4256.2 4256.2 4256.2 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 7023.6 7023.6 7023.6 7023.6 7023.6 7023.6 7023.6 7023.6 7035.4 7035.4 7035.4 7035.4 7035.4 7035.4 7035.4 7035.4~=DNPOIVEEED/INVALID DATA POINT FPL/PSL Rev.1 5.1-24 02/10/92 92 EX

5.2 PLANT

PARAMETER DATA CARDS This Data to be Provided Later 59 ANNUNCIATOR MIMIC SHEETS This Data to be Provided Later CONRDENTtAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLA'NT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 6.0 METEOROLOGICAL PARAMETERS This Scenario Section Contains the Following Information:

Section 6.1 METEOROLOGICAL FORECAST DATA-A simulated weather forecast for the time period affected by the postulated scenario events.Section 6.2 Section 6.3 METEOROLOGICAL DATA

SUMMARY

-The postulated meteorological conditions for the scenario in summary.METEOROLOGICAL DATA CARDS-Mimics of screens presenting meteorological data timed for presentation to the drill participants.

FPI/PSL Rev.0 CONRDENTIAL 6.0-1 12/06/91 92EX

FLORIDA POWER AND LIGHT COMPANY~ST.LUCIE NUCLEAR PLANT f992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 6.1 METEOROLOGICAL FORECAST DATA U.S.WEATHER SERVICE FORECAST DATA 02/12/92 0700 EDT Forecast from the National Weather Service Station at Palm Beach International ort for the Palm Beaches and vicini A weak high pressure system over the Atlantic is pushing a slow-moving cold front westward towards the Florida Coast.Air ahead of this front is partly cloudy and warm as a result of a stationary high centered offshore east of southern Florida.Cloudy and warm conditions will prevail for the next 8-12 hours until the air mass is pushed into a cold front stretching north and south over central Florida.Contact with this stationary front will produce increased cloudiness and showers by evening.Present conditions are fair and warm, temperature 78 degrees Fahrenheit with an anticipated high in the low eighties.Moderate scattered clouds with increasing cloudiness towards evening.Winds are mild from the east at 4 to 6 miles per hour continuing predominantly easterly throughout the evening.Probability of precipitation is 30%through Thursday morning.Marine conditions are: moderate seas, 3-5 feet.Winds from the east at 3-5 knots, visibility 15 miles.Water temperature 68 degrees at Jupiter Inlet.FPL/PSL 6.1-1 91EX 6.2 METE ROLOGICAL DATA

SUMMARY

St.Lucie Nuclear Plant 1992 Exercise PARAMETER UNITS TIME 07:30 07:45 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 10:00 10:15 10 METER 15 Min Avg.mph 3.7 4.4 4.3 4.4 5.1 4.9 4.5 3.9 5.2 4.4 3.8 5.2 Wind Speed Knots 3.2 3.8 3.7 3.8 4.4 4.3 3.9 3.4 4.5 3.8 3.3 4.5 15 Min Avg.Deg 88 89 90 94 95 96 96 95 93 94 96 97 Wind Direction Current Temp Deg F 78 77.8 77.9 78.1 78.3 78 78.2 78.3 78.4 78.4 78.5 78.4 60 METER 15 Min Avg.MPH 4.3 5.2 4.7 5.4 5.2 4.8 5.6 4.3 4.4 5.6 5.3 5 Wind Speed 15 Min Avg.Deg 95 96 Wind Direction 94 93 95 91 96 94 97 93 97 95 Current Temp Deg F 79.2 78.7 79 79.1 79 78.9 78.7 78.8 79.3 79.2 79 79.3 15 Min Avg.Deg F-1.2-0.9 DNerential Temperature

-1.1-1 W.7 W.9%.5-W.5 N.9%.8 4.5%.9 Stability Class D D D D D'D D D D D D FPL/PSL Rev.0 6.2-1 12/1 0/1 991 92EX St.Lucie Nuclear Plant 1992 Exercise PARAMETER UNITS TIME 10:30 10:45 11:00 11:15 11:30 11:45 12:00 12:15 12:30 12:45 13:00 13:15 10 METER 15 Min Avg.mph 5.2 5.1 4.4 3.9 3.8 4.1 4.3 4.4 4.3 4.1 5.0 4.8 WindSpeed Knots 45 44 3.8 3.4 33 36 37 3.8 3.7 36 4.3 4.2 15 Min Avg.Deg 95 96 94 97 98 95 96 97 Wind Direction Current Temp Deg F 77.9 78.2 77.8 78 78.2 78.4 78.6 78.9 78.3 78.5 78.4 78.3 60 METER 15 Min Avg.MPH 5.2 4.9 5.4 4.8 5.1 5.4 5.2 5.4 Wind Speed 4.9 5.1 5.4 5.3 15 Min Avg.Deg 94 96 92 94 95 97 95 95 Wind Direction 94 93 92 91.Current Temp Deg F 78.9 79.4 78.8 79.2 79 79.1 79.3 79.8 79.1 79.4 79.2 79 15 Min Avg.Deg F DNerential Temperature 1.2-1-1.2-0.8 47 47 49 48 49 4.8 4.7 Stability Oass D D D D D'D D D D D FPIJPSL Rev.0 6.2-2 12/1 0/1 991 92EX St.Lucie Nudear Plant 1992 Exercise PARAMETER UNITS TIME 13:30 13:45 14:00 14:15 14:30 14:45 15:00 10 METER 15 Min Avg.mph 4.9 4.7 5.1 5.3 5.4 4.7 5.0 Wind Speed Knots 4.3 4.1 4.4 4.6 4.7 4.1 4.3 15 Min Avg.Deg 95 97 Wind Direction 98 95 92 92 92 Current Temp Deg F 78.8 78.7 79 78.5 78.5 78.4 78.4 60 METER 15 Min Avg.MPH 4.8 4.7 Wind Speed 5 5.3 5.3 5.2 5.2 15 Min Avg.Deg 93 94 Wind Direction Current Temp Deg F 79.6 79.8 79.9 79.6 79.3 79.2 79.2 15 Min Avg.Deg F+.8-1.1 DNerential Temperature

-0.9-1.1 W.8%.8 4.8 Stability Class D D D D D'D FPUPSL Rev.0 6.2-3 12/1 0/1 991 92EX 63 METEOROLOGlCAL DATA CARDS This data to be provided later

CONRDENTIAL FLORIDA POWER AND LIGHT COMPANY ST, LUCIE NUCLEAR PLAN'I'992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 7.0 RADIOLOGICAL DATA This Scenario Section Contains the Following Information:

Section 7.1 REACTOR COOLANT SYSTEM RADIOLOGICAL DATA-simulated chemistry and radiochemistry data resulting from the postulated scenario events.7.1.1 Coolant Radiochemistry Summary 7.1.2 Coolant Radiochemistry Data Cards 7.1.3 Coolant Chemistry Data 7.1.4 Containment Atmosphere Summary 7.1.5 Containment Atmosphere Sample Cards 7.1.6 Containment Sump Activity Summary 7.1.7 Containment Sump Sample Cards 7.1.8 Steam Generator"1A" Sample Activity Summary Section 7.2 PROCESS RADIATION MONITOR DATA-Process radiation monitor data for the postulated scenario events.7.2,1 Process Monitor Summary 7.2.2 Process Monitor Data Cards Section 7.3 AREA RADIATION MONITOR DATA-Area radiation monitor data for the postulated scenario events.7.3.1 Area Radiation Monitor Summary 7.3.2 Area Radiation Monitor Data Cards Section 7.4 ONSITE RADIOLOGICAL DATA-Simulated radiation levels in and around onsite buildings as a result of postulated scenario events.7.4.1 Inplant Area Maps 7.4.2 Onsite Plume Map Section 7.5 OFF-SITE RADIOLOGICAL DATA-Simulated radiation levels off-site as a result of postulated scenario events.7.5.1 Off-Site Monitoring Data 7.5.2 Off-Site Plume Map FPIJPSL Rev.1 CONFIDENTIAL 7.0-1 02/10/92 92 EX CONflDENTNL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 7.1 REACTOR COOLANT SYSTEM RADIOLOGICAL DATA This Scenario Section Contains the Following Information:

Section.7.1.1 Section 7.1.2 Section 7.1.3 Section 7.1.4 Section 7.1.5 Section 7.1.6 Section 7.1.7 Section 7.1.S COOLANT RADIOCHEMISTRY

SUMMARY

COOLANT RADIOCHEMISTRY DATA CARDS COOLANT CHEMISTRY DATA CONTAINMENT ATMOSPHERE

SUMMARY

CONTAINMENT ATMOSPHERE SAMPLE CARDS CONTAII&fENT SUMP ACTIVITY

SUMMARY

CONTABAfENT SUMP SAMPLE CARDS STEAM GENERATOR"1A" SAMPLE ACTIVITY

SUMMARY

FPL/PSL Rev.1 CON flDENTIA 7.1-1 02/10/92 92 EX

7.1.1 COOLANT

RADIOCHEMISTRY

SUMMARY

St.Lode vaclcar PLant 1992 Excrcsse Reactor Coolant Systcta hcrlctty Data Sommary aCLhal ISOTOPE KANS Kr$5 Kr 87 Kr 8$Xe L3Ita Xe.133 Xe 135 1.131 I-132 1.133 1.134 1.135 Cr SI o54 Fe 55 Fe.S9 Cof 8 Co@0 Rb 8$Sr 89 Sr 90 Y.90 Sr 91 Y.glja Y.91 Zc 95 Nb-95 Mogg Tc ggta RN 103 Ra.106 Tc-L29ta Te.129 Te.131ta Te-131 Te-132 Cs-136 Cs.137 Cs.13$ILa~140 La.140 Ce-143 Pr 143 Cc-144 Pr.144 08t00 4.71843 2.20843 8.90843 9.92843 1.96842 3.86842 3.87E.OZ 4.32843 2.18E42 1.94842 3.79842 2.828 02 2.60844 9.03844 2.20844 1.40844 1.82843 2.80844 1.20E+00 4.80845 1.40846 1.50841 7.0084$3A0845 8.80846 820~5.96844 1.10842 5.00843 6.20846 1.40846 1.90844 1.5084f 3.00844 1.00844 330844 8.35844 1.90843 7.65844$.87842 3.00845 1.90845 4.90846 6.80846 430846 3.10846 IIt30 2.7 LE+04 1.62E+03 2.398~6.178+04 5.7$E+02 Z.IZEc05 1.57E+0$1.088+05 6.758+04 1.97E+0$4.62Ec04 1.50E+05 4A7843 7A0844 3.79843 2A 1843 3.83&02 4.82&03 5.7SE+02 8328+04 5.958+03 6.118+03 9.07E+04 1.1$8+04 L.l IE+05 I848+05 IPSE+05 1.648+0$1.158+05 ldlE+0$4.268c04 1.89E+03 8.33E+03 1.328+04 2.79E+03 1.298+05 1.748c04 4.SSE+03 7.98E+03 1.19E+04 1.608+0$1.60E+05 1.338+05 I368+OS 1.098+05$.96E+02-1.258+04 8.098+02 9.078+03 2.738+04 2.878+02 1.06E+05 7358+04$.388+04 2.908 c04 9.708+04 I368+04 7.128+04 2.23843 3.70844 1.89843 120843 1.92842 2.41843 8.938cOL 4.268c04 2.97E+03 3.04E+03 4.388+04 3.$28+03$3$8+04 7.728 c04 7.77E+04 8.188+04 fA4E+04 7.$38+04 2.138+04 3.958+03 3.05E+03 M48c03 6.038+02 6.428+04 8.708+03 ZAZBc03 3.998c03 3.IIEc03 7.988c04 1.928+04 6388c04 6.788+04 5.478+04 1.348+02 12:30 f.788+03 4.04E+02 3A5E+03 1208+04 IA3E+02 5.278+04 3.638+04 2.68E+04 1.2SE+04 4.77E+04 f.258+03 3.388+04 1.12843 1.85844 9.47844 987843 1.21843 1398+01 2.13E+04 IA 98+03 1.518 c03 2.11Ec04 1.268+03 2.778+04 3.86M'.888+04 4078c04 L578+04 3.7dE+04 1.068 c04 1.978+03 1.12E+03 3.238+03 1.308+02 3.208c04 4358+03 1.218+03 1.998+03 S.ISEcOZ 3.998+04 3.938c04 3.26E+04 3.38E+04 2.74E+04 2.028c01 L3t00 2.$98c03 2.02E+02 1.73E+03 6.02E+03 7.178cOL 2.64E+04 1.828 c04 1.348+04 6.23E+03 2.398c04 2.638+03 1.69E+04 f88844 9.2d84$4.74844 3.01844 4.19843 6.03844 6.958+00 1.07Ec04 7.448+02 7858+02 1.068+04 631E+02 L398+04 1.938+04 1.948c04 2.038+04 1.288c04 1.888c04 5.328c03 9.$78+02 5.608+02 I.628c03 6328+01 1.608c04 2.178+03 6.048+02 9.978+02 4.088+02 1.99E+04 1.968c04 1.638+04 1.698+04 1.37E+04 1.018+01 13t30 1.448+03 I.OIE+02 8.638+02 3.018+03 3398cOI 1.32Ec04 9.088c03 6.71Ec03 3.128+03 1.198+04 1.31E+03 8A48+03 2.79844 4.63845 2.37844 130844 239843 3.01844 3.478+00$.338+03 3.728+02 3.78E+02 5.288+03 3.1$EcOZ 6.938+03 9.648c03 9.718+03 1.028+04 6AZBc03 9AIEc03 2.668+03 4.938 HQ 2.80E+02 8.09E+02 3&8+01 1.99E+03 IASE+03 3.028c02 4.998+02 2.048+02 9.978+03 9.828+03 8.148+03 8A68+03 6.848+03 5.0f 8+00 14t00 7.228+02 5.068cOL 4.3 LE+02 IDLE+03 1.798+01&98+03 4348+03 3.36E+03 I36E+03 5.968+03 4.228+03 IAOB44 231845 l.18844 732845 I.ZOE43 131844 1.74E+00 2.66E+03 1.868+02 1.898+02 2.648+03 LASE+02~3A7E+03 4.828+03 4.85E+03 f.088+03 3.218+03 4.10E+03 1.338+03 2.478+02 LAOE+02 4.04E+02 1.638cOI 4.008+03 5A48+02 1318+02 2A 98+02 1.028+02 4.988+03 4.91E+03 4.078+03 4.23E+03 3.42E+03 2528+00 I4t30 3.618+02 2338cOI 2.168+02 733 E+02 8.97EHS 3.308+03 2.27Ec03 1.68E+03 1.198c02 2.98E+03 3.2SE+02 2.11E+03 6.988-05 1.16F 05 f.92845 3.76845 5.98844 7.54845 8.68841 1.33E+03 9.298cOL 9A4E+Ol 1.32E+03 7.89E+Ol 1.13E+03 2AIE+03 2.438c03 2.S48+03 1.60E+03 2.358+03 6.658+02 1.238+02 7.008+01 2.02E+02 8.15E+00 2.00E+03 2.728 cOZ 7.5f 8+01'.258+02 5.098+01 2.498+03 2.458c03 2.03E+03 2.12E+03 1.71E+03 1.26E+00 15:00 I.SLE+02 1.26E+Ol 1.088+02 3.76E+02 4ASE+00 1.6$E+03 1.148+03 8.39E+02 3.90E+02 1.498+03 1.64E+02 1.068+03 3.498.05 5.78846 2.96845 1.8884S 2.998-04 3.77845 4.34841 6.66E+02 4.658+01 4.72E+O1 6.60E+02 3.948+01 8.66E+02 1.21E+03 1.21E+03 1.27E+03 8.02E+02 1.188+03 3.33E+02 6.178+01 3.508+01 L.OIE+02 4.088+00 9.99E+02 1.36E+02 3.78E+01 6.23E+Ol 2.SS E+Ol 1.258+03 1.23E+03 I.OZEc03 1.06E+03 8.55E+02 6.31841 IZ TOT PhRT TOT TOThL 1.131 DEQ 1.23841 1.12E.OI 1.2S 8+00*Ld IE+00 1.34842 5.698+0$3.0$E+06 2.678+05 9.838+05 IA 88+06 8.748+04 1.118+0$1.268+05 4.86E+05 1.23E+0$4.318+04$348+04 6.308+04 2.438+05 3.628+05 2.16E+04 2.77E+04 3.158+04 1.22E+05 I.SIEc05 1.088+04 1398+04 l8 88+04 6.088+04 9 048+04 539 E+03 6.938+03 7.888+03 4.528+04 2.708+03 3A7Ec03 3.94E+03 1.$28+04 2.268c04 1.35E+03 Rec.1 02I03J92 92EX 7.1.2 C OLANT RADIOCHEMISTRY DATA CARDS This Data to be Provided Later 7.13 COOLAXF CHEMISTRY DATA ST.LUCIE NUCLEAR PLANT 1992 EXERCISE REACTOR COOLANT CHEMISTRY DATA

SUMMARY

CHEMISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: PARAMETER UNITS 07:30 TO 11:30 12:00 12:30 13:00 13:30 14:00 14:30 15:00 7.10 8.50 8.50 Dissolved 02 Dissolved H2 Conductiv'0.1 cd 25.00 umhos 10.00 1.30 150.00 150.00 150.00 1000.00 1200.00 1200.00 Chhrides<0.15 150.00 180.00 7.1.3-1 92EX ST.LUCIE NUCLEAR PLANT 1992 EXERCISE CHEMISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: PARAMETER UNITS 07:30 7.10 Dhsolved 02 Dhsolved H2 Conductiv Chio rides<0.1 cctk 25.00 wnhos 10.00<0.15 FPUPSL 7.1.3-2

ST.LUCIE NUCLEAR PLANT 1992 EXERCISE CHEMISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: UNITS 11:30 7.10 Dhsolved 02<0.1 Dhsolved H2 25.00 10.00<0.15 FPLJPSL 7.1.3-3 92EX

ST.LUCIE NUCLEAR PLANT 1992 EXERCISE CHEMISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: PARAMETER UNITS 12:00 Dissolved 02 Dhsolved H2 Chlorkke FPLlPSL 92EX ST.LUCIE NUCLEAR PLANT 1992 EXERCISE CHEMISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: UNITS 12:30 DIssoIved 02 DIssolved H2 Conductlv'hIorkhs FPL/PSL 7.1.3-5 92EX

ST.LUCIE NUCLEAR PLANT 1992 EXERCISE CHEMISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: PARAMETER UNITS 13:00 Dissolved 02 Dissolved H2 FPL/PSL 7.1.3%92EX

ST.LUCIE NUCLEAR PLANT 1992 EXERCISE-CHENISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: UNITS 13:30 DIssolved 02 Chiarides P FPQPSL 7.1.3-7 92EX ST.LUCIE NUCLEAR PLANT 1992 EXERCISE CHEMISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: UNITS 14:00 DIssolved 02 umhos 1200.00 Chhrides Boron FPLlPSL 7.1.3W 92EX ST.LUCIE NUCLEAR PLANT 1992 EXERCISE CHEMISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: UNITS 14:30 DIssoIved 02 1.00 DIssoIved H2 umhos FPL/PSL 7.1.3-9 92EX ST.LUCIE NUCLEAR PLANT 1992 EXERCISE CHEMISTRY RESULTS ON REACTOR COOLANT SAMPLES TIME OF SAMPLE: PARAMETER UNITS 15:00 Dissolved 02 DIssolved H2 FPL/PSL 7.1.3-10 St.Lucle Nuctear Plant 1992 Exercise Containment Atmosphere Data Summary oCVce 1$OTOPK Kr4Sea Kn85 Kr$7 Ks 8$Xe.13 ha Xe-L33 Xe.D$I 131 I.D2 1-133 1.134 1.135 Cr 51 Ma-$4 Fe.5$Fe.59 Co-5$C~Rb 8$Sc 89 Sr 90 Y-90 Sr 91 Y.9ba Y-91 Zc 95 Nb9$Mo 99 Tc.99aa Ra 103 Ra 106 Te.t29as Te 129 Te Dha Te-DI Te 132 Cs-D4 Cs.136 Cs-137 Cs.L3$Be.140 Lei 140 Ce 143 Pr 143 Cc-144 Pr 144 INITIhL 330847 4.00848 1.90841 6.30847 8.90E48 2.20E-OS I.OOE 06 7.50845 1.60846 6AOE 06 7.88847 1.70846 5.20849 1.30849 4A0849 3.20849 4.50848 5.70849 1.20848 1.30849 O.OOE+00 0.008+00 7.00F 10 4.608 10 1.90F 10 1.90F 10 1.908-11 2.40E47 3.80847 1.308 10 3.20F I I 3.90849 9.00849 4.60849 7.70849 6.10848 7.9084$3A0848 5.30848 O.OOE+00 6.00E 10 6.90E-IO 0.008+00 1.308.10 1.30F 10 3.10E 10 LOt IS$.77847 IA6FA7'.18847 1.11846 1.03FA6 2.39845 2.868.06 7.11845 2.65846 7.338 06 2.61846 3.06846 1.778.08 4A784$1.50848 9.94849 1.33847 1.92848 5.76845 3.61E49 6.748 I I 7.22F 12 4.07849 2.10849 6.13F 10 5.85F 10 2.87848 7.69FA7 6.21E47 4.28F 10 9.94F 11 1.3084$9.72849 1.9084$1.25848 7.7884$1.19847 1.25847 8.9884$2.82845 1.60849 L36F 10 4378 10 3A7E 10 439 E-10 Uh30 4.13846 1.80E46 7.33845 888FA6 I3884$f.30FA$3.2084$1.1084$1.9IE45 2.20845 3.1284$2A3845 2.14847 1.25847 I.8IPA7 1.1$847 1.50846 2.30847 9.59844 3.9884$1.12849 IMP 10$.68848 2.77848 1.2S849 6.77E49 4.78847 9.06846 439 FA6 S.LOFA9 I.ISFA9 186847 2.10E4$2A 5847 8.7984$3A2847 7A 9847 I86PA6 6.6d 847 4.7184$2A784$Id984$3.93849$88849 3.74E49 2.80E49 7.908 06 337846 1.45845 1.65845 3.1584$8.39845 6.31FA5 IA4FA$3.66845 3.75845 6.16845 4.69845 4.22847 IA5846 337847 228847 2.96845 435PA7 1.92843 1.8384$225849 2AIE 10 1.13E47&0848 1.43E4$1.33E4$986PA7 1.79E45 8AOPA6 I.OIFAS 2.28849 3.09847 3.3184$4.86847 I.68607 6.22E47 IA2E45 3.08845 128846 9A 1845 4.$784$3.1284$7.86849 1.10848 1.35E49 5.28849 Ih00 1.17E45 5.33846 2.ldFA5 2A 5845 4.72IAS 1.15844 9A184$1.79PA5 SA084$S.31E4$9.20845 6.9584S 6.31847 2.17846 534847 3A0847 4.42E45 5.19847 2.88843 1.17847 3.37FA9 3.61F 10 1.69847 8.22848 2.1484$1.9984$LA3PA6 2.67IAS 1.24PAS I30848 3.40849 4.61847 43184$7.26847 2A 8847 9.03847 2.09605 4.60846 1.89IA6 IA 1844 7.28E4$4.6484$1.18848 1.65PAS 1.10848 7.16849 lh15 3.938~L3$841 3A68+00 8.96E+00$.35842 3.088+01 2.288+01 1.568+01 9.80E+00 2.868+01 6.71E+00 2.18E+Ol 9.64847 1.19846 8.17847'.20847 1.778 06 1.04E46 SA 8842 1.24E+Ol 8.63E41 8.$6841 1.32E+Ol 1.588~IAIE+Ot 2248+01 L26 8+01 2.398+01 1.67E+01 2.19E+Ol 6.188~1.15E+00 1.21E+00 I.928~4.05E41 1.$78&1 2528+00 7.03841 I.16&00 1.728+00 2328eOI 2328&1 1.93E+01 1.978+01!398+01 1.30IAL lh30 1.858+00 4.70841 6.938+00 I.798&1 1.67E41 6.168+01 435E+Ol 3.138+01 1.96E+Ol 5.73E+Ol 1.348+01 4.36E+Ol 1.30845 2.ISLA7 I.IOFA6 5.99847 1.11845 IA0845 1.57841 2A7E+Ol 1.73E+00 1.77E+00 2.63'3.358+00 3.228+01 4ASE+01 4318+01 4.778+01 3.348&1 4.378+01 1.24&01 2.298+00 2A2E+00 3.84E+00 8.10841 3.758+01 5.058+00 I A 18+00 2.328+00 3A4 8+00 4.648+01 4.64E+Ol 3.868+01 3.948+01 3.18E+Ol 2.60841 lh4$5.668+01 3328~4338&1 1.268+02 1.258+00 4.61E+02 3.3fEHB 2.348+02 1.368+02 4.26&02 8.268+01 3.188+02 9.73845 1.61846 8.25846 f.24846 8.3484$1.05845 6.98841 1.868+02 1.308+01 1.33&01 1.94E+02 2.048+01 2.42E+02 3.368+02 3.38E+02 3378+02 2.44E+02 3.28E+02 9.27E+Ol 1.728%I 1.55E+Ol 2.81E+Ol 4.00E+00 2.808+02 3.798+01 1.05E+Ot 1.74E+Ol 1.$7E+Ol 3ASB+02 3.46E+02 2.888+02 2.9f EHQ 2.38E+02 1.07E+00 7.088+01 4AOE+00$.66E+Ol I.SSE+02 136 E+00 5.76E+02 4.198+02 2.938+02 1.10E+02 f.32E+02 1.03E+02 3.98E+02 1.228.05 2.028.06 1.03FA5 635845 L.04844 1.31845 8.72841 2.32E+02 1.52E+Ol 1.66E+Ol 2.43E+02 235E+Ol 3.02E+02 4.20E+02 4.238+02 4.46E+02 3.04E+02 4.10E+02 1.168+02 2.15E+Ol 1.948&1 3.58E+Ol 4.998+00 3.508+02 4.73E+Ol 1.32E+Ol 2.17E+Ol 2.348+01 4.358+02 4.33E+02 3.608+02 3.698+02 2.988+02 1.34E+00 8.14&01 5.068+00 6.5 LE+01 1.828+02 1.80E+00 6.538+02 4.81E+02 3.37E+02 1.96E+02 6.12E+02 l.L9E&2 4.58E~IAOE4$2.32E-06 1.19845 7.54E.05 1.20E44 1.5 IE.OS 1.00E+00 2.678+02 I.868+01 1.9LE&l 2.79 8+02 2.94E+01 3.478+02 4.838+02 4.868+02 5.13E&2 3.50E+02 4.1 LEi02 1.338+02 2A78+Ot 2.238&1 4.12E+Ot 5.748i00 4.03E&2 5.44E+Ot I.f 2E+Ot 2.5 08+01 2.698+01 5.008+02 4.98E+02 4.L48+02 4.248+02 3.43E+02 I.f 48+00 12:00" Lh I 5 12 TOT PhRT TOT I.DI DEQ 2A3F 0$1.80F Of 9.S4 847 4.32845 9.45846 3.02845 2.34845 6.25845 1.16844 1.0184$1.03E43 1.26843 2.02845 2.2IE44 1.97844 2.05843 2.47843 3.09845 3.19E44 2.8dIA4 3.08843 3.68843 4.16845 7.028&1 8.2d ECOL 4A28472 2378+01 1.658+02 5.798+02 8.858+02 5.138+01 1.03E+03 1.20E+03 4.31E+03 6348+03 3.82E+02 1.29E+03 1.508+03 S.39E+03 8.178+03 4.78E+02 IASB+03 1.72E+03 6.208&3 9AOB+03 S.S OB+02 Rer, 2 7.1A I 02/03@X 92EX St.Lucte Mudear Hant 1992 Exerctse Contatnment Atmosphere Oata Summary oCVcc ISOTOPE Kr Sfra Kr4$Kr 81 Kr 88 Xe 13ba Xe L33 Xe 13$I.D]I 132 1.133 I D4 I0 DS Cr$1 Mn.$4 Fe$$Fe.59 Co$8 Co%0 Rb 88 Sr 89 Se 90 Y.90 Sr 91 Y.9ba Y 91 Zr 9$ilb9$Mo 99 Tc 99ar Ru.103 Ru-L05 Tc]29ea Tc-129 Tc Dba Te Di Tc 132 Cc 134 Cc 136 Cc 131 Cc 138 Ba~]40 Qo]40 Ce.]43 Pr 14$Ce.]44 Pr]44 IMO 8.14E+Ol 5.06E+00 6.51E+Ol 1.828+02 l.80E+00 6.63E+02 4.81E+02 3.378+02 1.96E+02 6.128+02 1.198+02 4.588+02 IA0845 2.32846 1.19845 7.54845 1.20844 1.51845 I.OOE+00 2.67E+02 1.868+01 1.918+01 2.798+02 2.948+01 3.47E+02 4.$3E+02 4.868+02$.13E+02 3808+02 4.71E+02 L33E+02 2.478+01 2.23E+Ol 4.128+01 5.14E+00 4.03E+02 5A4E+Ol 1.52E+Ol X508+Ot 2.698+01 5.008+02 4.988+02 4.148+02 4.248+02 3.43&02 ld48+00 12:4$8.148+01 5.06&mt MLE+OL I.SZE+OZ I.SOE+00 5.63E+02 4.818+02 3.378+02 1.96E+02 6.128+02 1.198+02 4388+02 1.40845 2.32845 1.1984f 734846 I.20844 ldt845 I.OOE+00 2.678+02 1.86&01 1.91E+01 2.798+02 2.948+01 3A78+02 4.83E+02 4.868+02$.138+02 3308+02 4.718+02 1.338cOZ 2.478+01 2.23E+Ol 4.12E+Ol S.74E+00 4.038+02 SA48&t 1328+01 2.508+01 2.69E+Ol 5.008+02 4.98&02 4.148c02 424&02 3A38+02 184E+00]3>00 8.14&01 5.068+00 63 LBcOI I.S28+02 I.SOB+00 6.638+02 4.818+02 3.378c02 1.96E+02 6.12&02 1.198+02 438 E+02 IA0845 2.32845 1.1984f 784845 1.20844 L31845 I.OOE+00 2.678+02 1.86&01 1.918+01 2.798c02 2,94&01 3A78cOZ 4.83E+02 4.868+02 5.13&02 3.508+02 4.718+02 1338c02 ZA78cOL 2.23&01 4.128+01 5.748+00 4.038+02 SA4&01 132&01 L508cOL 2.69&01 5.008+02 4.98&02 4.14&02 4.24&02 3.438+02 L838+OO]3r]$S.I48cOL 5.06E+00 6318&I L.SZE~1.808+00 6.63E+02 4.$1E+02 3.378+02 1.96&02 6.128+02 1.198+02 4.588MB IA0845 2.32845 l.l984f 7.54846 1.20844 I.S1845 1.008+00 2.578+02 1.868+01 1.918+01 2.798+02 2.94&01 3A78c02 4.838c02 4.868+02$.13E+02 3808+02 4.718+02 1338+02 ZA7E+Ol 2.238+01 4.128+01$.74&00 4.03E+02$A4&01 1328+01 L50E+Ot 2.69E+Ot$.008+02 4.98&02 4.148+02 4.24E+02 3.438+02 L8384$1%30 8.148&1 5.06E+00 6318+01 1.8ZE+02 1.8OE+00 6.63E+02 4.81E+02 3378+01 1.96E+02 6.12E+02 1.19E+02 4388+02 IA0845 232845 I.I984f 734846 1.20844 1.51845 1.008+00 2.678+02 1.868+01 1.91E+Ol 2.798+02 2.94E+Ol 3.47E F02 4.838+02 4.86&02 S.L38e02 3308+02 4.7IE+02 1.338+02 2.478cOI X238+Ol 4.128+01 5.74&00 4.03E+02 SA4 8+01 LDZB+Ot 2308+01 2.69E+Ol 5.008+02 4.98E+02 4.148kB 4248+02 3.43E+02 l33E+OO IS>4$8.148+01 5.068+00 6318+01 L.SZBcOZ 1.808+00 6.638+02 4.818~3.378+OZ 1.96E+02 6.12E+02 1.198MB 4.5884'.40845 232846 I.1984$7.54846 1.20&04 ldt845 I.OOE+00 2.678+02 1.868+01 1.91&01 2.79E+02 2.948+01 3A78+02 4.83E+02 4.868+02 S.138c02 3808c02 4.7LEHR 1.338+02 ZA7E+Ol 2238+01 4.128+01 f.738+00 4.038+02 SA4&01 tdZEcOL 2308+01 2.688+01 5.008+02 4.988+02 4.14&02 4.248+02 3.438~td38~L4>00 8.14 8+0 t f.068+00 6.518+01 I.SZE+02 I.SOE+00 5.63E+02 4.818+02 3.37E+02 1.96E+02 6.128+02 1.198+02 4.588+02 IA0845 2.32846 1.19E45 734846 l.20E44 tdlE45 I.OOE+00 2.678+02 1.86E+Ol 1.918+01 2.798+02 2.938cOL 3A7E+02 4.$3E+02 4.868kB S.138+02 3308+02 4.118+02 1338+02 2A78+Ol 2.238+01 4.128+01 S.73E+00 4.038+02$A4&OI 1328+01 2308+01 2.688+01 5.008+02 4.988c02 4.L48+02 4248+02 3A3 8+02 I 338+00 L4s]$8.148+01 5.068+00 631E+Ol 1.$2E+02 1.808+00 6.63E+02 4.SIE+02 3.37E+02 l.968+02 6.12E+02 L.198+02 4.588@72 1.40845 232845 I.I9845 7.54846 l.20844 1.51845 I.OOE+00 2.67E+02 1.868+01 1.91E+Ol 2.19E+02 2.93E+Ol 3.47E+02 4.S38+02 4.868+02 5.138+OZ 3.508+02 4.718+02 1.33E+02 2.478+01 X23E+Ol 4.1ZE+Ol 5.73E+00 4.038+02 S.44E+Ol 1.528+01 2808+01 2.68E+Ol 5.00E+02 4.988+02 4.148+02 4.Z4E+02 3A3E+02 1338+00 1400, 8.t48+Ol 5.06E+OO 6.518+01 I.8IE+02 L.SOB@%6.63E+02 4.818+02 3.378+02 l.968+02 6.12E+02 1.198+02 4.588+02 1.40E45 2.32846 1.19845 7.54846 l.20844 13 1845 1.008+00 2.67E+02 1.868+01 1.918+01 2.798+02 2.938+01 3.478+02 4.83E+02 4.86E+02 S.13E+02 3.SOB+02 4.7 LE+02 1.33E+02 2A7E+Ol 2.23E+Ol 4.12E+Ol 5.738+00 4.038+02 5.44E+Ol 1.52&01 2.SOB+01 2.6SE+Ol 5.00E+02 4.98E+02 4.14E+02 4.24E+02 3A3E+02 1.53E+00 L4;45 8 148%1 5.05&00 6.518+01 I.8 LE+02 l.808+00 6.63E&2 4.$18+02 3.378+02 1.968+02 6.I 28+02 1.198+02>.588&2 1.408 05 2.32E 06 1.19E-05 7.fcE46 I.ZOE.O4 l.5 IF 05 9.99F Ol 2.678+02 1.868+01 1.9 LB+01 2.798+02 2.938iOL 3.47Ec02 4.838+02 4.868&2 S.I3 8+02 3.508+02 4.7IE+02 1.338i02 2.478+01 2.238&1 4.128+01 5.738+CO 4.038+02 5 A48iOI 1.52Ecol Z.SOB+OI 2.688+01 5.008%2 4.988+02 4.148+02 4.248c02 3 438iOZ I.S38iCO lI/G TOI'2 TQI'hRT.TOT.TOThi, I.]31 DBQ IASE+03 l.728+03 6.208+03 9AOE+03$.50E+02 I ASE+03 I ASE+03 1.48E+03 I.72E+03 I.728c03 L.728 c03 6.208+03 6.208+03 6.208+03 9.408+03 9AOE+03 9AOE+03 f DOE+02 5.508+02 5308+02 1.488+03 1.72E+03 6.208+03 S.SOEe02 LASEc03 5.208e03 S.SOB+02 LA 88+03 1.728+03 6.208+03 9AO&03 5308+02 I ASEt03 1.72E+03 6.20E+03 9AOE+03 5.508+02 1.48E+03 1.128+03 6.20E+03 9.408+03 f308+02 I.488+03 I.72Ec03 6.208+03 9A 08+03 S.SOEi02 Rer.2 1.]A 2 02/03/92 9]EX St.Lucle Nudear Pfant 1992 Exercise Containment Atmosphere Data Summary a Clice ISOTOPE 15<00>>>>'v Kr45ae Kr45 K~Ke48 Xe 131ae Xe.133 Xe.135 I.131 I.I32 1.133 1.134 1-135 Cr 51 Ma 54 Fe 55 Fe.59 Co5$Co40 Rb.8$Sr49 Sr 90 Y.90 Sr 91 Y-9lja Y-91 Zr 95 Nb95 Mo 99 Tc 99aa Ra 103 Ra 106 Te.l29ae Te 129 Te 131m Te 131 Te.132 Ce 134 Ce-136 Ce.137 Ce 13$84 140 La.140 Ce.143 Pr 143 Ce 144 Pr 144 8.14E+Ol 5.06E+00 6.518+01 l.8lE+02 l.808+00 6.63E+02 4.818+02 3.378+02 l.96E+02 6.128+02 l.198+02 4.588+02 IAO&05 2.328 06 l.l9845 7.54FA6 l.20FA4 l31845 9.99841 2.678+02 1.868+01 l.91E+Ol 2.798+02 2.938+01 3A78+02 4.838e02 4.868+02 5.138+02 3808+02 4.718+ID 1.338+02 2A7E+Ol 2238+01 4.l28+Ol 5.73E+00 4.038+02 5A48+Ol 1.528+01 2.508+01 2.68E+Ol 5.008+02 4.98E+02 4.14E+02 4.24840 3.438+02 1838+00>>g>>NG TOI'.48E+03 12TQI'.728+03 PhRT.TOT.6.208+03 TOThL 1-131 DEQ 5308+02 Res.2 1.1A 3 OZ/OK@91 EX

7.1.5 CONTAINMENT

ATMOSPHERE SAMPLE CARDS This Data to be Provided Later 7.1.6 C NTAINMENT SUMP ACTIViTY

SUMMARY

Sc.Lode.'caetear Plaac 1992 Eialoaced Excrctse C~cabuocac Scsap Data Sammael aCLhal LSOTOPE I 131 I le L 133 1.134 1.13$Cc 51 Mn.54 Fe 5$Fe 59 Co 5$Co40 Rb$$Sc$9 Sc 90 Y 90 Sc 91 Y.9tccc Y.91 Zc 9$Nb9$Mo 99 Te 99m Ro 103 Rcc L06 Te.t29aa Te L29 Tc.tf ta Te 131 Te.132 Cs.134 Cs 136 Cs 137 Cs L3$Sa.L40 La~140 Cc L43 Pc 143 Ce 144 Pt 144 1.60E45 6AOE44 7.88FA6 1.70845 5.20847 t.70847 4.40847 3.20FAl 480846 S.70847 1.208.06 1.30847 0.008+00 0.008+00'.00848 4.60E48 1.9084S 1.90FAS 1.9084$2.4084$3.80E4$l.3084$3.20849 3.90847 9.00E47 4.60M7 7.70847 6.10E46 7.90846 3.40846 5.30846 O.OOE+00 6.0084$6.9084$O.OOE+00 1.3084$1.30FAS 3.10848 1.25E43 1.70843;2.15843 1.61843 L3284$5.1384$l.29FA$8.23846 1.07844 I.6484$6.77842 2.848-06 7.92848 SA 9849 4.03FA6 1.97FAd 5.16847 4.82847 3.38845 6ASPA4 3.19844 3.63847 8&848 1.1184$1.70846 1.7484$639806 28684$SA7FA$1.11844 4.83FA$3.32843 1.75846 I.I4~2.77847 3.97847 2.67EO7 2.05847 3.04843 3.15E43 5.28843 3.93843 3.65845 1.26844 3.09845 l.97FAf X56844 3.9384$1.66841 6.77FA6 1.95847 2.09848 9.79FA6 4.76846 1.24PA6 1.15846 8.2984$135843 7~8.72841 1.97847 567845 2.73&06 421FA5 IA584f 5 30845 I~2.67844 1.10844 8.16&03 4.22846 6.81847 985&07 6.35847 483847 LOc1 5 LOc30 3.15844 684FA4 11:00 7.66844 3.71FA3 3.57E43 6.43843 4.79843 4A3845 133844 3.75&05 23984$3.11844 4.78845 2.03841 8.20846 2.38847 234848 1.1984S 5.79846 IAOFA6 1.40846 I.OIPA4 1.88843 8.65844 1.06846 X39847 32484$2.94846 5.1184$1.73845 6.21845 IA5844 3.24&0'32844 9.9$FA3 f.12846 3.25846 8.31847 1.16PA6 7.69847$.39847 Lh30 7.13844 332843 3.27843 6.11FA3 43S843 4.2084$1.46844 386845 2.2684$2.94844 4.53845 1.93 PAL 7.77846 2.26847 2.42848 1.13845 SA 9846 1.42846 1.33FA6 9.61845 1.78843 8.15844 1.00846 226847 3.07FA5 2.62846 4.$5845 1.6384$5.78845 I36844 3.07844 IMB44 9A6 843 4.85846 3.08846 7.90841 1.10E46 7.28847 5.06PA7 f.388+02 2.908+02 9.708+02 tddE+02 7.128~2.23E4f 3.70846 1.89E45 1.2084$!.92LA4 2A 1845 8.93841 4.268+02 2.97E+Ol 3.048+01 4.388+02 3.828&1$358+02 7.728 F02 7.778+02$.188+02 5.44E+02 7838s02 2.138e02 3.958&1 3.058+01 6848+01 d.038+00 6A28~8.708+01 2A28eOL 3.998eOL 3.118+01 7.988+02 7.92&02'388e02 6.788e02 5A78+02 1.348e00 2.688+01 1.258+01 4.778~1 5.258+00 338&01 1.12846 1.85847 9A 7847 6.02847 937846 l.21846 1.39842 2.13E+Ol IA9E+00 1.518+00 2.11E+Ol 1.26E+00 2.778&1 3.868+01 3.888+01 4.078+01 2578+01 3.768+01 1.068+01 1.978+00 1.128+00 3.238+00 I3084L 3.20E&t 435EHR IDLE+00 1.99E+00 S.IS841 3.998+01 3.938&1 3.26&01 3.38&01 2.748+01 2.02842 13c00 2.688+01 1.078+01 4.69E+Ol 334E+00 3.20E+Ol I.12846 1.$5847 9.47847 6.02847 9.57846 1.21846 4.32843 2.13E+Ol 1.498+00 I SOE+00 2.048+01 8.35E-OI 2.77E+Ol 3.86E+Ol 3.88E+01 4.058+01 2A2E+01 3.76E+Ol 1.068+01 1.978+00$21841 3.20E+00 5.64FAQ 3.18E+Ol 4.35E+00 1.21E+00 1.99E+00 427841 3.98E+Ol 3.898+01 3.22E+Ol 3.38E+Ol 2.748+01 6.06843 Lf c30 2.67E+00 9.21841 4.6 LE+00 239841 3.048+00 1.11847 I.SS84$9.4784$6.0184$9.57847 I 2IFA7 1.34844 2.138+00 IA98 Ol 1.49841 1.97E+00$328 02 2.77E+00 3.868+00 3.88E+00 4.038+00 2.298+00 3.768+00 1.06E~1.97841 6.02842 3.16841 2.44E43 3.17E+00 4.35841 1.21F Ol 1.99841 2.24842 3.98E+00 3.868+00 3.19E+00 3.388+00 2,748+00 1.$2844 1400 2.67E~7.92E41 4.548+00 1.61841 2.898+00 1.11847 I.S584$9.47848 6.0IE 08 9.57E-07 1.2IE 07 s.I88-Of 2.138~1.498.01 IA9E 01 1.908+00 3.65E 02 2.778~3.85 8+00 3.888+00 4.00E+00 2.16E+00 3.768+00 1.06E+00 1.97841 4AIFA2 3.12FAI 1.0f E-03 3.168+00'.358.01 L.20E.OL 1.998.01 t.l7E.O2 3.978~3.838+00 3.158+00 3.378+00 2.748+00 5A68 05 12 TOT 7.56844 I.dlPA2 1.93842 1.82842 I.I LE+02 1.03E+01 9.978+00 PhRT TOT 9.5484S 1.7$PAI 2.17841 2.06841 2.678e03 1.268+02 1.208+02 I.ISE+Ol I.108+0 l TOTAL 8.51844 1.94841 256841 2.24841 9.$38+03 4.828+02 4.78E+Ol 4.74EiO I 1.131 DEQ 9.93844 2.21E43 IA$8+04 7.088+02 6.95E+Ol 6.848+01 Rev.I 7.1.6.1 0203192 92EX

SC I.ucSe Itacleer Pleat 1992 Crelastis Exercise Coaaatccccecat Saccctc Deca Sacacaacy aClhcct ISOTOPE 1.131 I.132 I.L33 I.L34 I 135 Cr 51 Mcc-54 Fe-55 Fe 59 Co 5$CodO Rb.$$Sc$9 Sc 90 Y 90 Sc 91 Y.9tccs Y.91 Zc 95 Vb 95 Mo.99 Tc.99as Ru.t03 RN 105 Te 129ea Te.129 Te L3tmc To 131 Te.132 Cs L35 Cs.135 Cs.137 Cs.l3$Ba.HO La.t40 Ce L43 Pc L43 Ce.14 Pr 14 1430 2.67E F00 6.$1PAI 4A58e00 L.09841 2.74E+00 I.l IE-07 l.$58-0$9A784$6.0184$937847 l.2I847 l.30845 2.138+00 IA 9841 IA$841 1.$3E+00 2A18.02 3.$5E+00 3.$$E+00 3.9$8+00 2.048+00 3.768+00 1.068+00 l.97841 3.2l842 3.09841 486844 3.148+00 4.35841 1.20841 l.99841 6.L6843 3.97E+00 3.798+00 3.12E+00 3.37E+00 2.74E+00 I.64845 L5c00 2.66EHN 5,$5E41 4398 e{N 7.34842 2.60E+00 I.I IE47 t.$584$9A 7848 6.0184$9.56847!.21847 4.04846 2.138+00 I A 9841 IA7841 1.778+00 1.60842 3.$5E+00 3.$78+00 3.958+00 1.938+00 3.76E+00 l.0584$!.97841 237842 3.05841 1.97844 3.I3 8+00 4.35PAI L.20IAL I.99841 3.23843 3.96E+00 3.76E+00 3.098+00 3.37E+00 2.748+00 4.93845 12 TOT.9.39E+00 PhRT.TOT.1.07E+01 1.038+01 TOThl 4.7LE+OL 4.678cOL 1.131 DKQ 5.748+01 6.648+01 Rcv.I 7.1A-2 0>03)92 9LCX

7.1.7 CONTAINMENT

SUMP SAMPLE CARDS This Data to be Provided Later

7.1.8 STEAM

GENERATOR"1A" SAMPLE ACTlVITY

SUMMARY

SL La<le Isedsec Flees IS92 Re<eche Qeas Quotas"A" Act!AJ Dose Sasaarf aCVssl I2 15 14(SO Kr45s K+45<<F47 Kn4$Xo Uls Xo LU Xo l)S I Ul I 02 10)I U4 I 05 Cc41 hie 54 Pe 55 P+59 Co.5$C~RES!Ss 9$Y 90 Ss$1 Y Sls Yi91 Zs 95 IIIs 95 Mo 99 Tc-99so Ra Ii)Ra 195 Te.l)9s To.l)S To.0 la To Ul To 02 Cs.04 Cs.Ui Cs 01 Cs.0$be I45 Lo IN Co 143 Pt.li)Cs.144 Ps 144 cMDA<MDA cMDA cMDA cMDA cMDA cMDA cMDA cMDA<MDA<MDA<MDA cMDA cMDA cMDA cMDA cMDA<<MDA chlDA cMDA<<MDA cMDA cMDA cMDA cMDA<<MDA cMDA<<MDA cMDA cMDA<<MDA<<MDA cMDA cMDA cMDA<<MDA cMDA<<MDA cMDA cMDA cMDA cMDA cMDA cMDA cMDA cMDA I~L00$s00 947$sOI 2.7)Bs02 2.S 78<00 1.068+0)7358o02 5.)SBs02 2.908s02 0.708+02 1.568t02 7.128<02 2.2)FA5 L10PA6 IA0 845 1.20845 1.92844 L41 845 L93PAI 4268<02 LOTSsOI M4$sOI*Sdbs02 L$2SIOI S.55$s02 7.72$s02 7.778<02$.1$8sO)SA48s02 7.53$s02 2.1)Bs02 3.958<01 L058+Ol 6.548sOI 6.038~6A)Bs02$.708s01 L428sO I 3.008<OI 3.118sOI 7.0$$s02 7.928@02 6.5$$s02 6.7$$s02 5ATSs01 I~1.258sOO S.N842 OAl7841 2.738s00 1.$7842 1.068+01 7.558+00 5 JS&40 L908sOO 9.708s00 1.558+00 7.128+00 L2)847 S.7084$uOPAT 1.20847 1.92845 2AI847 L93 PA)*26 8s00 2.97PAI)A%341 382841 5858s00 7.728400 7.778<00 S.ISSsOO 5A4$t00 7838tOO 2.138s00).05PAI L05E41 6.54PAI 6.0)FA2 6A)8<00 L 70841 2A)SO I 3.90S41 3.11841 1.0$$s00 7.02$sOO 6,7$$sOO 5 ATE<00 134842 I~S.N844 0.07843 2.73 PA)L$7844 1.06841 1.55842 5.35842 L 90842 9.70S42 1&842 7.12842 2.2)S40).708 10 IA0849 IWFAO 1.0)PAS)A1849 LO)PA5 426842 2.97$4S)44843 43$FA)3~SS5$42 1.72842 1.77841 ai$842 5A4PA)783842 2.1)842 S.9SE43 3 05843 6.S4$43 6 03844 6A2842 a70$45 2A2843 3.99843 3.11843 7.05842 1.92842 6.1$FA2 5ATS41 134844 1.2$844 S.N845 0AO845 2.7)PA4 LSTPA5 1.06843 7.55PA4 5.3$$04 2.90844 9.70844 1.56844 7.12FA4 1.238 I I 3.708.12 1.$08-11 1.208 Il 1.028 10 2AIB 11$.93847 1.97S45 3.04$0$L)$844 A%45 535844 7.72PA4 7.77844$.15844 5A4844 7.5)844 2.1)PA4).95845 3.05845 6,54845 LO)$46 6AK44 a10$4$2A2845 L99$45 3.11PA5 7.05844 7.0%44 L5$844 6.11844 5A7844 134845 1.25PA5 LNFA$0.07PAT 2.73846 LSTPAS 1.05845 1.55846 5.16846 LSOS45 9.70PA6 1 86846 7.12FA6 L238 IS 3.708 li I@08 13 1.208 I)I.028 12 2AIB IS a9)840 a)6846 2.97847 3 ANDI)a)$846 SA)847 585845 7.72845 7.71845 L ld845 5A4846 1.53S46 2.1)845 3.9$PAT 3.05847 6.54847 6.0384$6A2PA6 L70841 2A 2847 3.09847 LIIPAT 7.9$8.06 1.92PA6 5.5SPA6 6.7S846 5.47846 13l845 l~LNPA9 9AO84$L7)PAT LSTPA8 1.06FA5 735FAT 53$847 1.90847 0.70847 I%FAT 7.12847 L138 14).108 15 IA08 14 I.208.14 1.928 13 1AIE 14 LO)s.IO 4,)SPAT 2.97845 3.04845 4)S SOT W)PAS 535847 7.7%47 1.77847$.15847 5A4847 7.53847 Ll)$47 S.9584$).OSE4$6.5484$6.03849 6A2S47 L 70845)A2$4$3.9984$3.1184$1.05847 7.92841 a)$847 5.71847 SA1847 134840 12584$LNB 10 9.07840 2.73FAS LSTE-10 1.06841 73584$5.3SFAS 2.90PAS 0.70E4$1.5684$1.11PAS L23F 15 3.10P 16 IA08 IS 1.208 iS 1.92E.14 L418 15 L9)E ll 4.26PAS 2.97840 3.04$4!l 434845 342&8 585E4$7.7284$7.7184$$.15845 5A484$7.5384$Ll)84$S.9$840).0$840 L54840 6.0)B 10 6A284$L 70840 2A2840).90PAO S.I ISN 7.95845 7.0284$a$$$4$6.15845 5ATFAS 1348 10 I~S.NB.I I 0.078-10 2.73840 LSTE-11 1.0684$1.55840 5.)$840 L SOFAS 0.70PA9 186FA0 7.12840 2.238-16).TOE 17 IA9$16 1.208 15 1.928 IS L418 16$.938 ll 4.26PAO 2.978.10 S.048.10 a)$840 SA)8 10 535PA9 7.7)PAO 1.77PA9$.15849 5A4849 7.538 09 r 2.13PA9).958 10).058 10 6.S48 10 aO)B.I I 6A2PAO$.708-10 2A28 10 3.008.10 3.118 10 1.0SPAO'1.91840 LSSFA0 6.7$E40 5A7849 1.348 ll 1.258 10$.09E ll 0.078.11 2.738.10 LSTE 12 1.06849 7.5$8 10 5)SE 10 L908.10 9.70E 10 I.S6E.IO 7.128 10 2.2S8.IT 3.108 IS 1.$08 IT 1.208 11 1.028 16)AIE 11 L9)8 13 4.268 10 LOTS.I I 3.048 ll*318.10 3.$28 II 5858.10 7.728 10 T.TTB 10 ald8.10 SA48.10 1.538.10 2.138 10).05E.II).058 li 6.S48.11 6.03E.12 6A)8 10 L708.11 2A28-I I 3.998 11 S.I IB I I 7.9$8.10 7.928.10 6.5$8.10 6.1$8 10 SATB 10 1348-12 TIIG TOT cMDA I)TOT<MDA PART TOT cMDA 1.01 DE@134842 L)18<41 2.678sOI 9.$SSt01 l)1841 2.31843 2.)I S45 2,31845 LS I PAT 2.67841 L67$03 2.67S45 2.67846 L57847 043841 MSS43 9.$3845 9ASPA6 9A)847 IASS<OO IA$842 I ASS 04 I AS845 I ASPA6 L14842 L74844 L74A6 L14847$.1484$L)i84$L 67845 2.3 IFAO 2.67840 iASE 0$$.748 10 Ros.~T.LLI~I/2$I92 CONFIDENTIAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLAN'I'992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 7.2 PROCESS RADIATION MONITOR DATA This Scenario Section Contains the Following Information:

Section 7.2.1 Section 7.2.2 PROCESS MONITOR

SUMMARY

PROCESS MONITOR DATA CARDS FPIJPSL Rev.0 CONFIDENTIAL 7.2-1 12/06/91 92 EX 7.2.1 PR CESS MONITOR

SUMMARY

THIS 1$h DMLL ST.LUCIE EVALUATED EXERCISE FEBRUARY 12, 1992 PROCESS MONITORING SYSTEM MONll'OR DESCRIPTION UNITS 07:30 08:00 08:15 08:30 08:45 09:00 09:15 09:30 09:45 PLANT VENT SYSTEM GASEOUS ACTIVITY IODINE ACTIVITY PARTICULATE ACfIVITY uCi/cc 2.03E46 2.03E-06 2.03E46 cpm IA4E&I 1.44E&I IA4E&I cpm 1.79E&I 1.79E&l 1.79E&1 2.03E46 IA4E&I 1.79E&I 2.03E-06 2.03E46 2.03E46 2.03E-06 2.03E-06 1 A4E+OI I A4EtOI 1.44E&I 1.44E+Ol 1.44E&1 1.79E+0 1 1.79Et01 1.79Et01 1.79E+01 1.79E&I CONTAINMENT ATMOSPHERE GASEOUS ACI'IVITY IODINE ACI1VITY PARTICULATE ACflVITY cpm 2.53EtOI 2.53E+Ol 2.53E&I cpm 3.47EtOI 3.47E&I 3.47E&I cpm 7.87EtOI 7.87E&I 7.87EtOI 2.53E+Ol 3.47E&I 7.87E&I 2.53E&1 2.53E&1 2.53E&1 OOS OOS 3.47Et01'.47E&1 3.47E&1 OOS OOS 7.87'7.87'7.87E&1 7.87Et01 7.87 ENVOI ECCS EXHAUST-A ECCS EXHAUST-B uCi/sec 1.33E47 1.33E47 1.33E47 uCi/sec 1.33E47 1.33E47 1.33E47 1.33E47 1.33E47 1.33E47 1.33E47 1.33E47 1.33E47 1.33E47 1.33E47 1.33E47 1.33E47 OOS OOS FUEL HANDLING BLDG EXHAUST GASEOUS ACflVITY uCi/cc IODINE ACflVITY cpm PARTICULATE ACTIVITY cpm 2.53E46 2.53E46 3.47E&I 3.47E&I 7.87EtOI 7.87E&I 2.53E46 3.47E&l 7.87E&I 2.53E46 3.47E&I 7.87E&1 2.53E46 2.53E46 2.53E46 3.47E&1 3.47E&1 3.47EtOI 7.87 ENVOI 7.87'7.87EtOI OOS OOS OOS OOS OOS OOS MAIN STEAM LINE-IA MAIN STEAM LINE-IB 9.05E41 9.05E41 1.59E~1.59E~9.05E41 1.59E~9.05E41 1.59EKO 9.05E41 9.QSE41 9.QSE41 9.05E41 9.05E41 1.59E~1.59E~1.59E+00 1.59Et00 1.59EKO COMPONENT COOLING WATE cpm COMPONENT COOLING WATE cpm 2.50E~250Et02 2.50Et02 2.50Et02 CONDENSER AIR EJECfOR cpm I.OOEt02 I.OOE&2 I.OOE&2 2.50E&2 2.50Et02 I.OOE&2 2.50E&2 2.50E&2 I.OOE&2 I.OOEt02 I.OOEt02 1.00E&2 I.OOE&2 2.50E&2 2.50E&2 2.50E&2 2.50E&2 2.50E+02 2.50E&2 2.50E&2 2.50Et02 OOS OOS Sl'EAM GEN A BLOWDOWN STEAM GEN B BLOWDOWN GASEOUS RADWASTE cpm 9.00E&2 9.00E&2 9.00Et02 cpm I.OOE&3 I.OOE&3 1.00E+03 cpm I.OOE+04 I.OOE~I.OOE+04 9.00E&2 I.OOE&3 9.00E&2 9.00Et02 9.00Et02 9.00E&2 9.00Et02 1.00Et03 I.OOEt03 1.00E&3 OOS OOS I.OOE~I.OOEt04 I.OOE~1.00E+04 I.OOE~LIQUID RADWASTE OOS=Out of Service FPI JPSL cpm 5.90E&I 5.90E&I 5.90E&I Rev.3 5.90E&I 7.2.1-1 5.90E&I 5.90E&1 5.90E&I OOS OOS 02/10/92 92EX THIS IS h DRILL ST.LUCIE EVALUATED EXERCISE FEBRUARY 12, 1992 PROCESS MONITORING SYSTEM MONffOR DESCRIFf ION UNITS 10:00 10:15 10:30 10:45 11:00 11:15 11:30 1 1:45 12:00 PLANT VENf SYSTEM GASEOUS ACf IVITY IODINE ACTIVITY PARTICULATE ACTIVITY uCi/cc 2.03E46 2.03E46 2.03E46 cpm IA4E&I IA4E&I 1.44E&I cpm 1.79EtOI 1.79E+OI 1.79EtOI 1 2.03E46 2.03E46 2.03E46 2.03E-06 2.03E46 2.03E46 1A4E&I 1A4E&I I A4EtOI 1.44E&1 1.44E&1 1.44EtOI 1.79E&1 1.79Et01 1.79E&1 1.79E&1 1.79 Eel 1.79E&1 CONTAINMENT ATMOSPHERE GASEOUS ACTIVITY cpm OOS OOS OOS OOS OOS OOS OOS OOS OOS IODINE ACflVITY cpm OOS OOS OOS OOS OOS OOS OOS OOS OOS PARTICULATE ACfIVITY cpm 7.87EtOI>I.OOE+06>I.OOE~>I.OOE~>1.00E+06>I.OOEt06>I.OOEt06>1.00E+06>I.OOE~ECCS EXHAUST-A ECCS EXHAUST-B uCi/sec 1.33E47 2.OOE47 3.00E47 uCi/sec OOS OOS OOS 3.00E47 3.00E47 3.00E47 3.00E47 3.00E47 3.OOE47 OOS OOS OOS OOS OOS OOS FUEL HANDLING BLDG EXHAUST GASEOUS ACTIVITY uCi/cc IODINE ACTIVITY cpm PARTICULATE ACI'IVITY cpm OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS MAIN SfEAM LINE-lA mR/hr MAIN STEAM LINE-IB mR/hr 9.05E41 9.05E41 159E~1.59E~CONDENSER AIR EJECTOR cpm I.OOE~I.OOE~9.05E41 1.59E~I.OOE&2 9.QSE41 1.59E+00 I.OOE&2 9.QSE41 9.05E41 9.05E41 9.05E41 2.40Et03 1.59E~1.59E~1.59E~1.59E~3.00Et00 1.00Et02 I.OOEt02 1.00E&2 1.00E&2 1.00Et02 COMPONENT COOLING WATE cpm COMPONENT COOUNG WATE cpm 2MEt02 2ME&2 2.50Et02 2MEt02 2.50E&2 2.50Et02 2.50Et02 2.50E&2 2.50E&2 OOS OOS OOS OOS OOS OOS OOS OOS OOS STEAM GEN A BLOWDOWN STEAM GEN B BLOWDOWN GASEOUS RADWASTE cpm 9.00E&2 9.00E&2 9.00E&2 cpm OOS OOS OOS cpm I.OOEt04 1.00E+04 1.00E+04 9.00Et02 9.00E&2 9.00E&2 9.00Et02 9.00E&2>I.OOE+06 OOS OOS OOS OOS OOS OOS 1.00E+04 I.OOEt04 I.OOE~I.OOE~1.00E+04 I.OOEt04 LIQUID RADWASTE OOS=Out of Service cpm OOS OOS OOS OOS OOS OOS OOS OOS OOS I'PUPSL Rev.3 7.2.1-2 02/10/92 92 EX THIS IS h DRILL SL LUCIE EVALUATED EXERCISE FEBRUARY 12, 1992 PROCESS MONITORING SYSTEM C MONITOR DESCRIFf ION UNITS 12:15 12:30 12:45 13:00 13:15 13:30 13:45 14:00 14:15 PLANT Vlf SYSTEM GASEOUS ACTIVITY IODINE ACI1VITY PARTICULATE ACflVITY uCVcc 2.03E46 2.03E46 2.03E46 cpm IA4E&I IA4E&l 1.44E&l cpm 1.79E+Ol 1.79E+OI 1.79E&1 2.03E46 lA4E&I 1.79E&1 2.03E46 2.03E46 2.03E-06 2.03E46 2.03E-06 I A4E&1 1A4E+Ol 1A4E+Ol I A4E&I 1 A4E&1 1.79E&I 1.79E&1 1.79E&1 1.79Et01 1.79E&1 CONTAINMENT ATMOSPHERE GASEOUS ACfNITY cpm OOS OOS OOS OOS OOS OOS OOS OOS OOS IODINE ACflVITY cpm OOS OOS OOS OOS OOS OOS OOS OOS OOS PARTICULATE ACfIVITY cpm>I.OOE~>I.OOE~>I.OOEt06>I.OOE~>1.00E+06>I.OOEt06>I.OOEt06>I.OOE~>1.00E+06 ECCS EXHAUST-A ECCS EXHAUST-B uCi/sec 4.00E46 5.00E47 6.00E47 uCi/sec OOS OOS OOS 6.00E47 OOS 6.00E%7 6.00E%7 6.00E47 6.00E47 6.00E-07 OOS OOS OOS OOS OOS FUEL HANDLING BLDG EXHAUST GASEOUS ACI1VITY uCi/cc IODINE ACI1VITY cpm PARTICULATE ACflVITY cpm OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS OOS MAIN STEAM LINE-IA MAIN STEAM LINE-1B mR/hr 1.10E+03 2ME+02 6.00E&l mR/hr 3.00E+00 3.00E+00 3.00E+00 9.20E~3.00E~2.20E+00 5.30E41 5.IOEA1 5.00E41 5.00E-Ol 2.50E+00 I.OOEt00 1.00E+00 I.OOE~1.00E+00 CONDENSER AIR EJECI'OR COMPONENT COOLING WATE COMPONENT COOUNG WATE STEAM GEN A BLOWDOWN STEAM GEN B BLOWDOWN GASEOUS RADWASTE cpm 1.00E+02 I.OOE&2 I.OOE&2 1.00E&2 I.OOE&2 I.OOEt02 1.00E+02 1.00E+02 I.OOE&2 cpm 2.50E&2 2.50E&2 2.50E&2 2.50E&2 cpm OOS OOS OOS OOS 2.50Et02 2.50Et02 2.50Et02 2.50Et02 2.50E&2 OOS OOS OOS OOS OOS cpm I.OOEt04 I.OOE~I.OOE~I.OOE~1.00E~I.OOE~I.OOE~I.OOE~cpm>1.00E~>I.OOE~>I.OOEt06>I.OOEt06>I.OOEt06>I.OOE~>I.OOE~>1.00E+06>I.OOE~cpm OOS OOS OOS OOS OOS OOS OOS OOS OOS UQUID RADWASTE OOS=Out of Service cpm OOS OOS OOS OOS OOS OOS OOS OOS Il'UPS L Rev.3 7.2.1-3 02/lO/92 92EX THIS IS A DRILL ST.LUCIE EVALUATED EXERCISE FEBRUARY 12, 1992 PROCESS MONITORING SYSTEM MONITOR DESCRIPI'ION UNITS 14:30 14:45 15:00 PLANT VENr SYSTEM GASEOUS ACTIVITY IODINE ACllVITY PARTICULATE ACI IVITY uCi/cc 2.03E46 2.03E46 2.03E46 cpm IA4EtOI I A4E&I 1.44E&1 cpm 1.79E&I 1.79E&l 1.79'CONTAINMENT ATMOSPHERE GASEOUS ACI1VITY cpm OOS OOS OOS IODINE ACllVITY cpm OOS OOS OOS PARTICULATE ACllVITY cpm>1.00E~>I.OOE~>I.OOE+06 ECCS EXHAUST-A ECCS EXHAUST-B uCVsec 6.00E47 6.00E47 6.00E47 uCi/sec OOS OOS OOS FUEL HANDLING BLDG EXHAUST GASEOUS ACTIVITY uCi/cc OOS OOS OOS IODINE ACTIVITY cpm OOS OOS OOS PARTICULATE ACIlVITY cpm OOS OOS OOS MAIN STEAM LINE-IA MAIN STEAM LINE-IB mR/hr 5.00E41 5.0OE41 5.0OE-01 mR/hr I.OOE~I.OOE~I.OOE~CONDENSER AIR EJECI'OR cpm I.OOEt02 I.OOE~I.OOE&2 COMPONENT COOUNG WATE cpm 2.50E&2 2MEt02 2.50E&2 COMPONENI'OOLING WATE cpm OOS OOS OOS STEAM GEN A BLOWDOWN STEAM GEN B BLOWDOWN GASEOUS RADWASTE LIQUID RADWASTE OOS=Out of Service cpm>I.OOE~>I.OOE~>I.OOE+06 cpm OOS OOS OOS cpm I.OOE~I.OOE~I.OOE+04 cpm OOS OOS OOS Il'IS'SL Rev.3 7.2.1-4 02/1082 92EX 7.2.2 PR CESS MONITOR DATA CARDS This Data to be Provided Later CONFlDENTIAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 7.3 AREA RADIATION MONITOR DATA This Scenario Section Contains the Following Information:

Section 7.3.1 Section 7.3.2 AREA RADIATION MONITOR

SUMMARY

AREA RADIATION MONITOR DATA CARDS FPI/PSL Rev.0 CON RDENTIAL 7.3-1 12/06/91 92EX ST.LUCIE NUCLEAR PLANT EVALUATED EXERCISE AREA RADIATION MONfl'OR DATA

SUMMARY

MONITOR¹, MONITOR DESCRIPTION TIMEI 07:30 07:45 08:15 08:30 08:45 09:15 RE-I RE-3 REM RE-5 RE-6 RE-7 RE-8 RE-9 RE-10 RE-11 RE-12 RE-13 RE-14 RE-15 RE-16 RE-17 RLJ 18 RE-19 RE-20 RE-21 RE-22 RE-24 RE-25 RE-26 RE-27 RE-36 RE-37 RE-38 RE-39 RE-52 RL'-53 kE-58 kl.'-59 CONTROL ROOM AREA CIS...A 0 DEGREES CIS...B 270 DEGREES CIS...C 180 DEGREES CIS...D 90 DEGREES SPENT FUEL POOL SPENI'FUEL POOL SPENT FUEL POOL BORIC ACID PRECON.FILT.WASIE FIL'KR MON.LAUNDRY FILTER WASK GAS COMPRESSOR CfuLRGING PUMP AREA IIOLD UP DRAIN PUMP AREA SAMPLE ROOM AREA ION EXCH.CORRIDOR ION EXCH.VALVE GALLERY DRUMMfNG STATION AREA PURIFICATION HLTER AREA SPENT RESIN CORRIDOR REACTOR DRAIN PUMPS AREA HVAC EQUIPMENT ROOM AREA CHEMICAL DRAIN PUMP AREA VOL CONTROL TK CORRIDOR LETDOWN HEAT EXCH.FUEL POOL NEW FUEL STORAGE AERATED WAS'TORAGE BORIC ACID CONCENTRATOR POST LOCA A POST LOCA B CfuNM A CfllNM II mR/hr udUhr mR/hr mR/hr mR/hr udUhr mR/hr mR/hr mR/hr udUhr mR/hr mR/hr udUhr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mIUhr mR/hr mR/hr mR/hr mR/hr udUhr mR/hr mR/hr mR/hr ulR/ht R/hr R/hr 1.908 Ol 2.34Et00 6.98E+00 4.14E+00 I.07Et00 1.248t00 IPSE Ol I.SSE+00 5 JOE.0I 2.078+00 2.07E400 1.50E+00 1.$28+00$$9FAL 6.458~4.948.0L IAMB-Ot 1.29E+00 2.33EHQ 249&01 1.89E+00 I.$4&01 7.29F Ol 1.608-01 2.338+00 3.03E+00 1.60E-OI LDSF Ol 2JL9F Ol IDSB.OI 2.698-01 1.048o UU 1.298'U 1.90F Ol 2.34E+00.6988t00 4.14E+00 1.07E+00 1.248t00 LSSSOI L USE+00 5Xi9BOL 2.07E+00 2.07E+00 1~F00 1.828+00 5JL9~I 6458+00 4.94E4L 1.60&01 I29E+00 2.33E+00 289EOI 1498+00 1.$4EOI 7.29841 1.60F Ol 2.338+00 3.03E+00 IAAF Ol 1.5SB-OI 249BOI 1.55E-OI X69BOI I.048+00 1.29Et00 I.908.01 2.348t00 6.9$8t00 4.14ERS 1.07'0 I.248t00 IASB.OI LDSE+00 SJI9801 2.07E 100 2.07&00 1.508 F00 I.$28t00$.69F Ol 6 458t00 4.94FAI I.60BOL l&Et00 2.338AM 249&01 1498~1.$4801 7.29801 I.60641 23384M 3.0384$L.608-0I 1.55E41 2.69641 I.S5E.OI 2.69F Ol I.OIEi00 J.298100 1.90E.OI 2.348'0 6.988+00 4.148e00 I.078t00 I.248t00 1.68E.OI L.SSEo00 S.69F Ol 2.078t00 2.078'0 L.SOEt00 I.$28t00 5.698 Ol 6 458+00 4948.0I L.60FAI t.29&00 233 8t00 289&11 1.$98t00 I.84BOI 739801 I SOFA)I 2.33&00 3.038t00 1.608 Ol I.SSF Ul 2.69E 01 1.55E-OI 2.698-01 L.UIEtUO 1.29LiUU 1.9UE-OI 2.348+00 6.9SEt00 4.148t00 1.078+00 1.248+00 1.6$F Ol L.SSEi00 SJL9F Ol 2.078'0 2.07E~I.SOEt00 I.$28tUO S.69F Ol 6 45&00 4.94E-OI 1.608 01 1.298+00 2.338t00 2.69F Ol 1.$9E+00 1.848 01 7.29F 0 I 1.608 01 2.33E>00 3.038t00 1.608 01 I.SSh Ol 2.69E.OI 1.$5E-OI 2.69L Ul L.U48tUO J.29htUU 1.9UL'.Ul 2.34L'iUU 6.9$1 tUU 4.148i00 1.07L<00 I.24ht00 1.6$E-OI I.SSE+00 5.69EMI 2.078t00 2.078'0 I.SOEt00 1.$28t00 5.698-01 6 45E+00 4.94~1 1.60h.01 1.298+00 2.338tOO 2.69E-OJ 1.$9E+00 I.$4E4L 729F Ol 1.60F Ol 2.33E+00 3.038i00 1.6UE-OI 1.558.01 2.698 Ol 1.55F 01 2.691: OI I.048i00 t.298'U L.90h.UI 2.348'U 6.988t00 4.148t00 I.07&00 1,24ht00 1.6$F Ol I.SS&00 S.69E.UI 2.078i00 2.078'0 I.SOEr00 L.$28i00 S.69E-OL 6 458e00 4.94E.OI 1.60E-UI I.298'0 2.338 F00 2.698-01 I.$98+00 I.S4E-OI 7.298 01 I.60641 2.33Et00 3.03E+00 1.60E-OI I.SSBOL 2 69841 I.S58 Ol 2 698-01 L.048iOU J.29htUU 1.9UL'l 2.348eUU 6.9$h'+UU 4.148tUU J.07h DUO L.24L'tUU I.b$8-01 I.SSEi00 5.69h-UL 2.078'U 2.07ht00 I.SOEt00 I.$2he UU S.69h.U I 6 458o00 4.948.01 L.608.01 I.298tUU 2.338oOU 2.6984JI I.$98t00 1.$4E-OI 7.298.01 I ANU Ul 2.338tUU 3.038iUU I.OUI0 I 1.55L UI 2.698 Ul L.SSh.UI 2.698 Ul I.U4 h'e UU J.29LeUU I'I'I.II".il.

Itcv.2 CX>8=()IJl'l'I!k VI(.'I l 7.I I-I 02/0 I/92 ST.LUCIE NUCLEAR PLANT EVALUATED EXERCISE AREA RADIATION MONITOR DATA

SUMMARY

MON ffOR¹MONITOR DESCRlP11ON TIME: UNITS 09:30 09:45 10:00 10:15 10:30 10:45 I I:OO I I:15 RE-I RE-3 REQ RE-5 RE%RE-7 RE-8 RE-9 RE-10 RE-I I RE-12 RE-13 RE-14 RE-15 RE-16 RE-17 RE-18 RE-19 RE-20 RE-21 RE-22 RE-24 RE-25 RE-26 RE-27 RE-36 RE-37 RE-38 RE-39 RE-52 RL'-53 RL-58 RI!-59 CONfROL ROOM AREA CIS...A 0 DEGREES CIS...B 270 DEGREES CIS...C 180 DEGREES CIS...D 90 DEGREES SPENf FUEL POOL SPENT FUEL POOL SPENT FUEL POOL BORIC ACID PRECON.HLT.WASTE FILTER MON.LAUNDRY FILTER WAS%GAS COMPRESSOR CHARGING PUMP AREA)fOLD UP DRAIN PUMP AREA SAMPLE ROOM AREA ION EXCH.CORRIDOR ION EXCH.VALVE GALURY DRUMMING STATION AREA PURIFICATION FIL'IER AREA SPENf RESIN CORRIDOR REACI'OR DRAIN PUMPS AREA HVAC EQUIPMEÃf ROOM AREA C)IEMICAL DRAIN PUMP AREA VOL CONTROL TK CORRIDOR LEIS)OWN HEAT EXCH.FUEL POOL NEW FUEL STORAGE AERATED WASTE STORAGE BORIC ACID CONCENlRA'IOR POST LOCA A POST LOCA 8 CH)lRM A CIIIIRM B mR/hr mR/hr nIR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr aIR/hr R/hr R/hr I.90E4I 2.348too 6.988+00 4.14E+00 1.07&00 1.248too S.69FAI OOS 1.508+00 1.82E~6 458+00 4.94841 OOS 2338+00 1.89E+00 OOS 7.29EOI 1.60641 OOS 008 OOS 1.55E41 2.69L'-01 6.OI8-UI 6.UUL.U I 1.90E.OI 2.348too 6.9$8too 4.148+00 1.078too 1.24E+00 OOS 008 5ABE4I OOS OOS I.SOEtoo 1.$2E+00 OOS 6 458t00 4.94 M I OOS OOS 2.33E too OOS 1.$98too OOS 7298.01 1~1 OOS OOS 008 OOS 008 1.55F Ol 2.69E-OI 6.OIF Ol a.ooE,ol 1.90F:Ol 2.348'o 6.988~4.148too 1.078too 1.248too OOS 008$.698411 OOS OOS I.SUE+00 1.82E+00 008 6.458+00 4.948411 OOS 006 2.338too OOS 1.$98+00 008 7.29801 1.60E-OI 008 008 OOS OOS 008 1.55F Ol 2.69L'.01 6.04E.OI 6.0OL'-01 1.90E-OI 2.308'l 2.30E+O1 2.308&1 2.308tol 1.24E+00 008 S.69E.OI OOS I.SUE+00 1.$2E+00 OOS 6 458too 4.94E-OI 008 OOS 2.33E+00 1.$9E+00 7.29E Ol I.bOLOI OOS OOS 008 OOS I.SS&OI 2.69L'01 6.048.0I 6.UUE.UI I.908.01 4.1$8tol 4.1$8tol 4.1$8tol 4.1$8tOI 1.248100 OOS 008$.69F Ol 008 OOS 1.$08+00 1.$?Etoo OOS 6 458+00 4.948.01 OOS 008 2.338tuo OOS I.$98100 OOS 7.298-01 1.60E4I OOS OOS 008 1.$58.01?.a9L'.ul 6.048 0 I 6.UUL'I 1.JUL ul 3.UUI otl?3.UUL'iu2 3.UUL'02 3 UUL'tu2 1.24L't Uu$.69E.OI I.SOEtoo I.$?Etuu 6 458+00 4.94E.OI 2.338tuo 1.$98tuu 7.29E.UI 1.608 tll 008 OOS I.SSL'Ol 2.69L'.Ul 6.048.01 6.UUL UI 1.9UF:Ol 1.$0&03 I.$08t03 1.808+03 I.$08103 1.248too 008 S.69E-OI OOS 008 I.SOEtoo 1.$28too 008 6 4$E+00 4.94841 OOS 2.338ioo 008 I.$98+00 008 7.29841 1.60E41 OOS 008 008 OOS 00b 1.5$F Ol 2.698-01 1308100 I.3UE+Ou 3.0UL'-tl1

>I.OUL'e US>I.UOEeus>I.OOEeus>1.00&US>I.OUEt Ui OOS 008$.698.0I 008 I.SOEtuo I.$2&00 OOS 6 458ttN 4.94E Ol 4.OUEtou OOS 3.008tol 008 7.29&01 1.608-01 008 OOS OOS OOS?.uu&03?.UOL'e tl3?.auLeu4?.auL't U4 II/Phl (X)S=()Ul')I'ill(V ICI!I(<<v, 2 7.3.I.2 02/03/92 92)tX Sl'.LUCIE NUCLEAR PLANT EVALUhTED EXERCISE hREA RADIATION MONfl'OR DATh

SUMMARY

MONITOR¹MONITOR DESCRPHON TIMEI UNITS 11:30 11:45 12:00 12:15 12:30 12:45 13:00 13:15 RE-I RE-3 RE4 RE-5 RE%RE-7 RE-8 RE-9 RE-10 RE-I I RE-12 RE-13 RE-14 RE-15 RE-16 RE-17 RE-18 RE-19 RE-20 RE-21 RE-22 RE-24 RE-25 RE-26 RE-27 RE-36 RE-37 RE-38 RE-39 RE-52.RE-53 RL-58 Rli-59 CONfROL ROOM AREA CIS...A 0 DEGREES CIS...B 270 DEGREES CIS...C 180 DEGREES CIS...D 90 DEGREES SPENT FUEL POOL SPENI'UEL POOL SPENf FUEL POOL BORIC ACID PRECON.FILT.WAS%FILTER MON.LAUNDRY FILTER WASK GAS COMPRESSOR CHARGING PUMP AREA HOLD UP DRAIN PUMP AREA SAMPLE ROOM AREA ION EXCH.CORRIDOR ION EXCH.VALVE GALLERY DRUMMING STATION AREA PURIFICATION FILTER AREA SPENf RESIN CORRIDOR REACfOR DRAIN PUMPS AREA HVAC EQUIPMENf ROOM AREA CHEMICAL DRAIN PUMP AREA VOL CONIROL TK CORRIDOR LETDOWN HEAT EXCH.FUEL POOL NEW FUEL STORAGE AERATED WAS'TORAGE BORIC ACID CONCENIRATOR POST LOCA A POS'f LOCA B CHHRM A CIIHRM 8 mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr mR/hr aIR/hr R/hr R/hr 8.00E.OI>I.OUE405>1.00E<05>1.00E+0$>1.00E+0$>1.008+%OQS 008$.69E.01 OOS OQS 1.50E+00 1.428too OQS 6A5E+00 494 E41 OOS OQS I.OOE+00 008 7~ioI 008 7.29841 IAS&OI 008 008 OOS OOS OOS S.OOE403 S.UUEto3$.008tu4 S.UUEtu4 2.00801>I.OOPS>IASEAS>I.OOE405>1.00885>1.008M OGS OGS 549F 01 008 OOS l~I.I28t00 008 6A5E+00 4.94EOI OOS OOS BASE+00 OQS 7~&1 OOS 7.29841 1.60601 008 OQS 008 OOS OGS$.008103 S.UOEt03 S.UOE404$.008i04 1.908-01>I.OOEtos>I.OOEtos>I.OOE40$>1.008tos>I.00&04 008 OOS 5.698-01 OOS OOS 1.50E+00 1.$28~OOS 6A5Etoo 4.94&01 OOS OOS I238tol OQS I.OOEAC OQS 729641 I~I 008 OQS 008 008 008 7.008t03 7.008+03 6.758t04 6.758'4 1.90L-OI>I.OOEt05>1.008tos>1.008tos>1.008tos>IAOEt04 OOS 008 5.69E-OI OQS 008 1.50E+00 I.S28+00 OOS 6A5E+00 494 E41 OOS OQS 1.13E+01 OQS 9.008tol OOS 7.29801 1.60641 008 008 OOS OOS OOS 6.$08>03 6.50Li03 6.508e 04 6.$UL'F 04 1.908 ol>1.00E+0$>I.OO&US>I.OOE+0$>1.008tos>I.00&04 008 OOS$.69F 01 008 OOS 1.$08too 1.428+00 OOS 6A58i00 4.94E-OI OQS 008 I.138&1 OOS 9.00Etol 008 7.29&01 I X48 01 008 OOS OOS 008 6.UOE+03 6.008tu3 6.SUL'e 04 b.SUEt 04 1.9UL'Ul>I.OULt Us>I.UUEo US>I.UUL't US>I.UUEiuS>I.OUEt04 OOS OQS$.698-01 008 OQS I~too 1.428tuo OOS 6A5E+00 4.948411 OQS OQS 1.138tol OQS 9.008tol OQS 7.29841 I.~l OGS 008 OGS OGS OGS b.uuE+03 6 UULtU3 6.5UL'F04 6.5UL+04 1.908.01>I.UOEios>I.OOEt0$>1.008tos>I.OOE+0$>1.008+04 OOS OOS 5.698-01 008 OGS 1.$08+00 1.528tou OOS 6A58+00 4.94E.OI OGS 008 1.138+01 OQS 9.008+01 OQS 7.298-01 1.60E4I OGS OOS OOS OOS OOS 6.008y03 6.008'3 6.$0Lt04 e.SUE<04 1.9UE.OI>I.OUEt 05>I.UUEtos>I.OO&0$>1.008t05>I.OOEt04 008 008 569841 OQS OQS 1.5UE too 1.428+00 OGS 6A58tou 4 948-01 OOS OOS 1.13E&I OOS 9.008&1 OOS 7.29801 IAAF 01 OQS OOS OOS OOS 008 6.00L't03 e.uu&U3 6.5ULiu4 6.5UI:eu4 1'I'I JP!SL Rcv.2 ()OS=OlJI'Ol'l!

RVICL 7.3.1-3 02/03/92 92l:X b f.LUCIE NUCLEAR PLANT EVALUh fED EXERCISE AREA RADIA f ION MONffOR DATA

SUMMARY

MONITOR¹MONITOR DESCRIPTION TIMEI 13:30 13:45 14:00 14:15 14:30 14:45 15:00 RE-I RF:3 RE4 RE-5 RE<RE-7 RE-8 RE-9 RE-10 RE-11 RE-12 RE-13 RE-14 RE-15 RE-16 RE-17 RE-18 RE-19 RE-20 RE-21 RE-22 RE-24 RE-25 RE-26 RE-27 RE-36 RE-37 RE-38 RE-39 RE-52 RL-53 RF-58 RE-59 CONTROL ROOM AREA CIS...A 0 DEGREES CIS...B 270 DEGREES CIS...C 180 DEGREES CIS...D 90 DEGREES SPENT FUEL POOL SPENT FUEL POOL SPENI'UEL POOL BORIC ACID PRECON.FILT.WAS1E FILTER MON.LAUNDRY FILTER WASTE GAS COMPRESSOR CHARGING PUMP AREA HOLD UP DRAIN PUMP AREA SAMPLE ROOM AREA ION EXCH.CORRiDOR ION EXCH.VALVE GALLERY DRUMMING STATION AREA PURIFICATION FIL'KR AREA SPENT RESIN CORRIDOR REACI'OR DRAIN PUMPS AREA HVAC EQUIPMENf ROOM AREA CHEMICAL DRAIN PUMP AREA VOL CONTROL TK CORRIDOR LETDOWN HEAT EXCH.FUEL POOL NEW FUEL STORAGE AERATED WASTE STORAGE BORIC ACID CONCENTRATOR POST LOCA A POST LOCA B CIIHRM A CHHRM B mR/hr mR/hr aIR/hr mR/hr mR/hr mR/hr mlUhr mR/hr mR/hr mNhr mR/hr mR/hr mlUhr mR/hr mNhr mR/hr mlUhr mR/hr mNhr mR/hr mR/hr mlUhr mIUhr mNhr mR/hr mNhr mR/hr mR/hr mR/hr mNhr mNhf Nllr R/br 1.90E.OI>I.OOEi0$>I.OOEt05>I.OOEt0$>I.OOEt0$>I.OOE+04 OOS$.69841 6A5E+00 494 E4I OOS OOS 1.13&01 OQS 9.00E+Ol OOS 729801 1.60801 OOS OOS OOS OOS OOS 6.0OEt03 6.00&03 6.508eu4 6,50&04 1.90E4I>I.OOPS>1.008+0$>I.OOE+0$>I.OOE+0$>I.OOE+04 OOS OOS$.69801 OOS OQS 1~+00 1.$2E+00 OOS 6A58+00 4.94E-OI OOS OOS I.138&1 OOS 9.00Etol OOS 7.29FAI I.Q&OI OOS OOS OOS OOS OOS 6.008+03 6.00E403 6.50Et04 6.50E+04 1.90E-OI>1.008+0$>1.00&05>I.OOE+0$>IISEeOS>I.OOEt04 OQS OOS$59&01 OOS OQS 1~+00 1.$28ioo OOS 6ASE+00 4.94&01 OOS OOS 1.13E+Ol OOS 9.00E+Ol OOS 7.29FAI 1.60641 OOS OOS OOS OOS OOS 6.008'3 6.00&03 6.50&04 6.$0&04 1.90E41>I.UOEt0$>I.OOEtoS>I.OOE 405>1.008t05>I.OOEt04 OOS OOS$.69801 OOS OOS 1.$0&00 I.82&00 OOS 6A58tuo 4.94641 OOS OOS 1.13E+01 OOS 9.0088)I OOS 7.29F Ol I ME41 OQS OOS OOS OOS OOS 6.008103 6.00&03 6.50&U4 6.5ULou4 1.9UE-ol>I.OOEtOS>I.OOEiOS>I.OOEt0$>I.OOEt0$>1.00&04 OQS OOS$.69EOI OOS OQS 1.5OEtoo I.828ioo OOS 6ASE+00 4.948.01 OOS OOS 1.138+01 OOS 9.008tol OQS 7.29E-OI 1.60E.OI OOS OOS OOS OOS OOS 6.00&03 6.00Lt03 6.5OLi04 6.50&04 1.908 ul>I.ouli e 05>I.UUL'e 0$>I.OOL'o U$>I.UUL'tUS

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7.3.l-4 02/03/92 7.3.1 AREA RADIATION MONITOR SUhCVIARY 7.3.2 AREA RADIATION MONIT R DATA CARDS 0

This Data to be Provided Later COHRDEHTNL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLAN'1 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 7.4 ONSITE RADIOLOGICAL DATA This Scenario Section Contains the Following Information:

Section 7.4.1 Section 7.4.2 INPLANT AREA MAPS ONSITE PLUME MAP FPIJPSL Rev.0 CONRDENTIAt.

7.4-1 12/06/91 92EX i

7.4.1 INPLANT

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7.4.2 ONSITE

PLUME MAP 1l%Cl<ho lO

~aoas assaaa~stO/%llllllHIIHlltlllllllb Caoaa 0 (Y 0-~ts s a N gk 5~~I O OA~O\/OS Oa~sso~~~ata~'aao.~oao~t<<,~tta~<<a~aaa~mO~aaa~saa s<<~aso s<<~tost<<t S.<<<<N~Ql~[ssssa E~it 6 e~4 eW I<<<<as OsssLf~14.6 1~J~'so I tM OIS SOOI~I I~as~COO sa C3~ts~OOO 6~otsso Cao<<to..iuuua L~I%~sao 5~LL.'E gn)~L-s~aaaa C~/~O~/'<<aatt s~I Stosl sossl sal I lsslal IUAsota ssl Isas1~Iso os sssst saass bl I C ST.LUCK NUCLEAR PLANT ONSITE PUSH OATA CNSJSS EXERCISE LUDLUM 221$BKG 100 001 LUDI.UM 221$EFF FRISKER EFF.AIA SAMPLE VOL 10 Ws Yo cube loot LIKES fAOM SOUACE PAEFLTEA GA06$COLSITS CAAT.GA068 TOTAL CNTS 6 QSI 0.4 0.$02 791075 0.1 N cART.GA088 ToTAL cNTs I Iw OQU848 e.ooE47 aooE45 a::I:::::.:::.::;1:.:::

441752 M4E46%$6E46 2976 7~1355145 (3 S C AlcA.l)OSE EAWS C~+/NL)C~rkw II R.IN.ES f A044 SOUACE 05 0.4 0.$0.2 l.O COFI6uaCWS 8)Q jOOO COLIang O~gy, lq A~L hCTLIi L PAEFLTEA GA068 COLNTS CAAT.GA06S TOTAL CNTS.6 1481 OPEN WSCXM 0 HEA)HT.CL06EO WSCXM 0 HEA)HT CAAT.GA068 TOTN.CNTS I 14SI GA0LSXI DEPOSITION SLKAAARE FIFTH4ATKXI sAhr 1$.4 13195 131565 396643 4:::.11$$.00E45 4.99E45 S$6.0 402.0 230941 492423 1.55E46 2.01E46$719 4453 Not~g.I FOQ jC g O~Qa, Q.~os+)SO~gagtaeaacf J o R C e+O0 CT'kg aDA b~g g hczlL4L, Acyl,L+L IV SCauICF IN.ES FAGS SOLXICE PAEFS.TEA GAOSS COL84TS CART.GAOSS TUB.CNTS 6 1484 KXQK ASXIOQK 1XXIC.OPel WOW 0 HEIO Hl'.CLOSEO~0 HBQ HT.0.6 0.4 e.ooE49 4.00Ea 0.$4.0OE47 bi+7, C,~~.S IO boSK 44M CaaC/)>OO 2 CICI CAAT.GA06$TOThL CNTS.I QN Capue OEPOSITION uOlaeu 1.34E47 1.34E45$.35E45 SQEPBhBLE CONTAI&IATION I$0 2IXI 744 NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS i BACKGROUND ON IODINE CARTRIDGE~6 MIN WITH 35 CUBIC FOOT SAMPLE BACKGROUND COUNT ON LUDLUM 2215~500 GROSS COUNTS.5 MIN.COUNT.100 CPM.AN SAMPLE FLOW~7 CFMFOA 5 MIN.~35 CFM/)PQ C Lw'5a L)g5'~~

TIKI 1?1$ST.LUCK IRJCLEAR PLANT OIIQTE PUNK DATA~2A2IS2 EXEACQK LUDLUM 2218 BKG 100 0 O'I LUDLUM 2218 EFF FRISKEA EFF 10@LES FAO61 SOUACE 0.4 02 0.1 PAEFS.TEA OAOSS COLSITS 16700&27387 701076 1318450 OPEN WSQON~HEAD HT.CLOSED WORE 0 HEAD HT afQIT:.I':..:'.:'.I'I.:i.:':,',1:i:i:.!I!1 A'ate 2880 635.1 Mi.1'IS60.1 CAAT OAO68 TOTAL CNTS I ISI OSLS8S 451782 823654 1%6 N5 2308610 abase TA7E45 4.02E46 7.37E46 1.07E46 3273 SiQ&15383 2SMT CART.OAO6S TOTAL CHTS 6 1LH OOLRh uQAe 5.00E48 1.20E45 1.80E46 SOOE46 4518020 2.58E46 QSC~5 Csun'TTLILA 4 1R, CA a/&)0%).0 (O~SClOM)C jOOO Cta.OAEE.iH.IQ~ES FAQLA SOUACE SECTOA PAEFS.TEA OA06S COLSITS CAAT OAOSS TOTAL CHTS 6LNI OPEN WIDOW~HEAD HT CAAT.OAOSS TOTAL CNTS I QSI OAOLSXI DEPOSIDON SLKARAkLE TXSFTN&iATXSL 131855 0.4 651782 2.01E46 0.3 8181 02 570.1 1166306 1'IMO Naanc CWgmaW Tq)~~~A-Crm<~u~Qu18AAISg g, g@en)~(>A+c~)~SraLFLCC" her 5-T.T r~NEST~MES FIX%I SOLSICE PIKFSTEA OIX%$COLSTTS CART.DROSS TOTAL CNTS 6 QSI~ASISOfWE CC%C.OPEN WSCIOW~HEAD HT.0.4 OS 79118'br'~~v 5 JQ boCr a ef'AAO/ill)5'TR.30 cy j 00~l hirJ~CAAT OAO6S TOTAL CHTS.I QSI GAOL%0 DEPO6ITIOH 7.37E46 1.47E45 QJEAAAELE CONTAMINATION E~~C./~CC I:XS.IQ.'(PC.AA 5)NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS~SAC NERO U NO ON IOOINE C ARTS I ORE 0 5 MIN WITH 55 C URIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 22 IS~500 GROSS COUNTS.5 MIN.COUNT.IOO CPM.AIA SAMPLE FLOW m 7 CFM FOA 5 MIN~35 CFM EI If.'IPJ:5 I 1M': TRX ST.LUCIE NUCLEAR PLANl'NQTE PLUiK DATA 02tl2JS2EXERCISE LUDLUM 2218 8KG 100 001 LUDLUM 2218 EFF FRISKER EFF Sle cube Qol@LES FAOQ SOUACE 6ECTOA PAEFLTEA GAOSS COL%F6 O.i 270N1 0.$02 (I::-::.:ii'l.:':i:::.."N i05206 87533i 0.1 CART.GA068 TOTN.CNTS 6LLS1 OSLSIIS OP84 WIDOW 0 HElD HT MLES fMLL SOURCE SECTOA PAEFS.TEA OAOSS COLNTB CAAT GAQ6S TOTAL EWZS 6 LLSL IOONE AHSOISLE CONC.OPel WHOOW~HEA)HT.CLOSEO WWOW 0 HEID HT.CAAT.GAOSS TOTIL i&$8.1 QS1 05 saRIs 718)CAAl'AOBS TOTiL 1$FI8 1 IW OOUAIB 238580 TcQEETS 2.18E45 4.1iE44 710.0 700640 1182i60 0.60E46 l.iSE4i 21M2 Sld82 O.i 05 13507d 202IMO 02 N$.07E48 i.8 1E48 1420 21$.0 235580$6i820 021E45 1.54E46$.07E46 N20.0 O~c JOSEF'M~4~r~>~Cn bc'~(.BAZOO era m a~I<)(fbi~A~~CS~0 E Sqg 5.CEELl4kaigf

(~Q Qcl~ecg~~)

CgOESO CVS)fVF~~r m~+QUES FAOQ SOLNCE 0.6 O.i 0.$2.72E46 i.75E46 40%I 10645 7.NE46 15861 sr.Q~Cte r 405'<447TL (~y~g 5 So PAEFR.TEA OAOSS COLSIITS CART.OAOBS TOTAL 6 QN 1S51b 27CQS i0531 S.07E47 4.NE47 0.21E47 ii?TO li2 2b.i CART GA068 TOTAL CNTS.1 QSL GRXNO OEPO6%0N SNEAAhKE OONTALWLAMH 2.'ISE45 5.44E45 0.5OE45 PA+/FHZ (6 EELFA.8!'LL)/OD 1$8 21IS NOTES: CAllI GROSS TOTAL COUNTS IS TOTAL COUNTS~SACKGRO UN CON IOOINE C ART RIOGE~6 MIN WITH 66 C USIC FOOT SAMPLE.SACKGROUND COUNT ON LUDLUM 221S~500 GROSS COUNTS.5 MIN.COUNT.100 CPM.AIR SAMPLE FLOW~7 CFM FOR 5 MIN.M 35 CF M 7 4'F'6 0 11'3l'JSF VL't X ST.LUCK NJCLEAR PLANT OICSAE PLUS%QATA e2FI2N2 EXERCISE LUDLUll 221$BKG 100 001 LUPLUM 221 6 EFF.FRSKEA EFF.10 cube leal@LES FIKXl SOLSTICE 04 02 0.1 PAEFLTEA OAOSS COISIT6 CART OAOSS TOTAL ISITS 6 QSI 1M016 154857 274770 CART.OMSS TOTN.ISFIS 1 i&i aAEIF i:!i:i!aha 599 1104 179.7 451155 1.55E44 5161$Msc w~~I C.g~l~'1 O5C~3 (OhsaJ~Caa5va)(1$00 c.r5 W Cw<4)QLES FROM SOUACE 0.4 0.$02 hJ.~Ter SECTOR PAEFLTEA OA066 COLIITS CAAT.OA06S TOTIL CNTS 6 QSI cau181~ARSO&1E IXWC.OPEN Wt4OOW 0 HFAD Ht.CLO6EO NORCN 0 HGO HT 27465 52440 1$7$01 1.57E45$.12E45:.i.:ISE-'!ii::i:::.

1494%.~~cf (CS64~)CART.GROS&TOTAL CNTS 1 QSI MLES FIRM SOLSTICE SECTOR PAEFLTEA GROSS ORNTS CAAT OAOSS TOTAL 6 QSI~ASISOISIE IXNC.OPEN~0 HEAD Ht.CLO6EO WNXIW 0 IRAQ HT CART GROSS TOTAL CHTS.I QN SQEAAAR.E CONTAQWLTION uQkc 125E47 12.0 1341 2405$$520E45 7.8SE46 115lS 1760$0$S.75E47 18.0 1.04E46 Qo~M~6 Ga'Il l nJ CTlvll+45 o CCVWI ACIO g.V.M(g~(<a'>-.6 P'~)NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CAATRIDGE 0 5 MIN.WITH 35 CUBiC FOOT SAMPLE" BACKGROUND COUNT ON I UDLUM 22IS 500 GROSS COUNTS.5 MIN.COUN T.100 CPM.AIR SAMPLE FLOW i 7 CFll FOR 5 MIN

ST.LUCIE NUCLEAR PLANT ONSTTE 1$LLQK DATA 02li2JS2 EXERC1&E LUDLUM 2218 EFF.FRSKER EFF.AlR SAMPLE VOL 10 LUDLUM 2218 BKG l00 001 Yo ca4e leal@LES FAOQ SOURCE 04:N 0.$02.N.0.1 O>c S7574 uCHoo-2$1E417&.74E47 4.81E47 afar 144 288 42.0 CAAT.GAOSS TOTIL CNTS 1@el SQkEat 2.&SEN0&8.14E46 I.OWN&872 1472&24582~TEAGAOSSCaaTS CART.GROSS TOTlL CNTS.6QH COLRll 83118 1.43E40 2.87E40'm'.:::m'.:

T4;&i:i 71.&142.0 1.81EOi S.78EOI 46794 834SS bos-a~-(PN8 I N8$o l C+tm i aOS,+3 (Sac~Q~~QI.ES F RON SOUACE PAEFLTER GAOSS COLNTS CART GAOSS TOTAL CNTS, 6 Qel OPEN WNOOW 0 HEAD HT 0.5 ehkr 72 0.4 287EO7 143 4.40E+7 214 02 31584 7.17EO7~l (aver,b S Ei4TIISEE464

~Q (iooa~)CART.GAOSS TOTAL CNTS 1 QN~ES RKSI%ENCE NSkea 1SSE4$SCSEM ESTER$0$E4$2838 SM2 11741 17MO/0.4 8~T bear p4eC C~/4~)dao hJ SgrrV s~SECTOR erma TER aaaa COLSTTS CART.GROSS TOTAL CNTS 6@el~ASOOfIK CONC.OPel WIDOW 0 HEAD HT.1274 4.8 IO cQ60 CART GROSS TOTAL CNTS 1@el NOTES: 8.1SE4b TS72 CART.GROSS TOTAL COUNTS is TOTAL COUNTS~BACKGROUND ON lODlNE CARTRlDGE 0 6 MlN.WlTN 35 CUBlC FOOT SAMPLE BACKGROUND COUNT ON LUDLUM 2218~500 GROSS COUNTS, 5 MIN, COUNT.100 CPM.AlR SAMPLE FLOW~TCFMFOR 5MlN.~35 CFM~\~0 If$.'VJL' QR 13:14 ST.LUCIE NUCLEAR PLANT OHETTE PlLNK DATA 42f12I82 EXERCISE CENTERlNE LUDLUM 2218 BKG LUOLUM 2218 EFF.FRSKER EFF.AIR SAMPLE VOL.001 10 MLES f AOM SOUACE ClAT.OAOSS TOT@.CHTS.6 MSI OPEN NOCRW 0 HEAD HT.CLOSED~0 HEAD HT CART.DROSS TOTIL CNTS 1 I%I 04 i:i'::I:i:::.':N S746 uOAe 424EO4 4.4QEO4 4.4 02 H:.':I:'.::::i.:Ii'::N 5410 Q342 127EO7 2.12EO7 11.0 0.1 18571 4.24EO7 21.9 Dam Aa mg t'a,Z>AC.Q P eau~~6 ORDISK)DEIIOSITXSI SIKAAIIS.E OQ4TNQQLTKSI 420EO5 1.08EO4 1.42EOi$.77EOi 1$77$23435$5421 4374S MLES f RLI SOUACE SECTOR 0.5 0.4 0.$0.2 PAEf@TEA OA06S COLNT S CART.OAOSS TOTIL CHTS.6 MSI IQONE NABOISIE IX'.OPER WSSIOSI~HElD HT.CART.DROSS TOTAL CHTS 1MSI OAOISKI DEITOSIMH UCUoc 2.12EOS 1878 2811 4877 424EOS 4~OS 1.08EO7$.10EO6 6.$2EO6 8.0QEOS 4447 11414 17481 IL PE,EF UDAFAI N, 5aM ll I CC-QQQ(y~04'me.l wC.>~tVe~MLE8 fROM SOLNCE SECTOR PI%$MER OAOSS COLSITS CART.DROSS TOT%.tWTQ 6 MSI OOLnka 0.6 424EOQ 0.4 QO 1+6 CARl OA068 TOTAL CHTS, l MSI OOUAka OAOUND DEPOSITION SMEAAAR.E IXSITAMSIATIOH 02 2.67EOS 0.4 1377 0.7 (5D Or/g J iM~I~FTAD (C L'-L NOTES: CART GROSS TOTAL COUNTS IS TOTAL COUNTS t SACKGROUNDON IODINE CARTRIDGE~6 GIN.WITH 66 CURIO FOOT SAllFLE BACKGROUND COUNT ON LUOLUM 2218~500 GROSS COUNTS, 5 MIN.COUNT.100 CPM.AIR SAMPLE FLOW~7 CFM FOR 5 MIN.~35 CFM~~~6 OIIJ JPJ2 lJSI X ST.LUCK NJCLEAA PLANT ONSITE PLUME DATA 02II2N3 EXERCISE LUDLUM 221S BKG LUDLUM 221S EFF FRISKEA EFF 100 001 10 QUES FAOQ SOLSLCE SECTOIL PAEF S.TEA OALXIS COLNTS CART OAOSSTOTlL CNIS 6QN lOONE lLSLSOINE CHIC.CAAT OAOSSTOTIL CNTS I i&i O.S 03 1.5 0.2 2.6 0.1 A L(AMm S, Aalu~c/g g A Sgg.~~~021 E45 1.07E4i 5 HALF CElfKRLSK QLES FADE SOUACE 06 OS 02 SECTOR PAEFSTEA CROSS COLNTS CAAT OAOSSTOTN.

CNTS SUN OPEN WMXM 0 HEAD HT 4.92E-10 Q.S4E-IO 0$O.d@IlT.(rl557 55 hJ SeeuICEb'LbS.

~4'k~CART OKXLS TOTiL CNTS 1 IXI ORXSSI OEPOSITXSI

%KARAKE CCNTNHLATXN 12SE45$.10E46 2861 6.$3E45.IIS25 5.10E46 HLES FMQ SOLSLCE SECTOR PAEFLTEA OAOSS COLNTS CART.OJKOS TOTN.CNTS S QN COLllll 06 0.1 0$I&l 35 uQke<<$.$0E-1&.$0E-I$0E-I OPEN~O HEIe HT.CLOSED WMXM 0 HEILD HT sacr 0.1 0.1 02 Ac qua<SUEAAh8L E CONTISNIILTION EcnaETS 2.57E46 6.21E46 1379 1.07E45 NOTES: CART IUKISS TOTAL COUNTS IS TOTAL COUNTS~SACKGROUNC ON IOOINE CARTRICGE 0 5 MIN.WITN 55 CUBIC FOOT SAIIFLE BACKGROUND COUNT ON LUDLUM 221S~500 GAOSS COUNTS.5 MIN.COUNT, 100 CPM, HA SAMPLE FLOW 7 CFMFOA 5 MIN.a 35 CPM/TBE'55~~~~>5 V TNJEI ILW ST.LUCK NJCLEAA PLANT OI4SITE PLINY DATA 02tl2I82 EXERCISE LUDLUM 2218 BKG 100 001 LUDLUM 221S EFF FALSKEA EFF HA SAMPLE VOL.10 ULES FAOLI SOLSICE 6ECTOA PAEFS.TER ONES COLSITS CART.GA068 TOTAL CNTS 6 QSI 0.6 0.4 0.$02 0.1 113<<$$0E.4.5SE-IO 6.87E-IO 1.14E40 CART GROSSTOTAL ISIT8 II%I GIKXSKI OEFOSITX81

~AIWS.E IXWTNWATNN 2.67E4S 421 BS 6704 1~0.4'l.07EO4 0.6 1.$83816 AL L~~M A~~@LES f AOQ SOLSTICE 0.5 0.4 0.$02 PAEFLTEA GAO68 COLM%8 CAAT GAOSS TOTAL CNTS 6 QSI 17 uQ!oc<<$.$0E-I ALAOI 0.1<<S.SOE-1 0.1$.43E-10 6.72E-10 02 Se1.0~7~KI.Se~ic QLhg+46~llf (~/I~)CART.GAO6$TOTAL CNT8 I QSI GAOLSCI OEPOSITX81 S.I IE46 6~46 S.IOE46 11828 17979~ES FIKXI SOLNCE SECTOR PI%F8.TEA GAO88 COLSITS CAAT GROSS TOTAL CNN SQSI LOOSIE ASSILXSIE IX'.OPEN WMXW 0 t&IO HT.1$0.4 14<<S.SOE-1<<$.$0E-1 30 0.0 0.0 0.0 CART.GA068 TOTAL CNTS, I QSI GAOL8IO OEFOSITQN SQEAAAfLE CONTANSIATLON 6.21EOS 1.07E~1379 2368 (Lm'4'<=OP>.'NOTES: CAAT.GROSS TOTAL COUNTS IS TOTAL COUNTS i BACKGROUND ON IODINE CAATAIDGE~6 MIN.WITII 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 221S~500 GROSS COUNTS, 5 MIN, COUNT, IOO CPM.HA SAMPLE FLOW~7 CFMFOA 5 MIN.~35 CFM S ui nii;L Aoav I 7428 0 If23PJ2 O'I X ST.LUCIE NUCLEAR PLANT OHSNE PLLQK OATA 82IT2I82 EXERCISE LUDLUM 221$BKG 100 0OI LUDLUM 221$EFF FRISKER EFF.AIR SAMPLE VOL 10 MLES FAOQ SOUACE SECTOR PAEFLTEA GAOSS COIJITS CART.GAO68 TTTTAL CHITS 6 QSI Oi$1 02 0.1 i27E-10 d.iIE-TO 1.07E40 0,1 O.i 12 CaRT.GI'S ITlL CNTS I QSI d2IE45 1.07E44 1.d2E4i 15791 2$1$6054@LES f AOQ SONICE SECTOR PAEFLTEA GAO68 COLIITS CaRT GA068 TOTaL CNTS 6 QSI IQONE ASIIIOISIE CONC.CLO6ED WINOS 0 HEaD HT.CaRT.GAOSSTOTaL CÃTS IIJN GRXJCI DEPOSITNN RKIAIISE IXWTNRIAMN 0.6'I7 uCVoc<<$.$0E-T aRkr 0.1 O.i 0.1$.11E46 0.$02 0.$5.$$E46$.10E46 11 aM)17IST2<<$.$0E-1 5.34E-IO Sc~~~T~M S~i<<4 4OSS A4t$C~~~~ES FAQQ RXHKE SECTOR~TER GROSS COISITS CAAT.GAOSS TOTAL CNTS 6 Qel OONlle 1$O.i 3d'a%MIDIS%CONC.WSNOW 0 HEID HT.CLOSED WOKEN~HEAD HT CaRT GAO6$TOTAL CNTS I lkeI<<$.$0E-T<<$.$0E-I 0.0 257E48 d 21E4S 1370<<$.$0E-10 0.0 1.07E46 r C'Og g~NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS i BACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUBIC FOOT SAMPLE BACKGROUND COUNT ON LUDLUM 22 IS 500 GROSS COUNTS, 5 MIN COUNT, 100 CPM.AIR SAMPLE FLOW+7 CFM FOR 5 MIN.~35 CFM TRKI 14:16 ST.LUCIE NJCLEAR PLANl'NQTTE PLLNK DATA CVI2ISSEXEACNE LUDLUM 2218 BKG RO-2 BKG LUDLUM 2218 EFF.FRISKEA EFF 001 10 Cuba loot@LES FROW SOLACE SECTOR PAEFS.TEA OAOSS COLSITS CART.OA068 TOtlL CNTS I QSI OOLRIS 0.4 0.$0.1 IODSIE ASNOISIE CCSIC.OPEN~0 HEAD HT CARY.OAOSS mt%.ISITS I INI 4.01E-10 0.1 02 uOkaO 2.67E46 42IE46 6707 1NQS 1.01E-10 0.4'1.OOE40 2.OOE4Q 0.6 1.62E44$.78E4I$6071 83841 ALL, JL4bA4 S A~M~&iEhh g J~~~~@LES FROW SOLSTICE SECtOR PREFLTEA GA068 COLSITS CAAT OA068 TOTN.CHTS I F81 XBPIE ASISLXAE lXAC.OPEN WNOQN~HEA)HT CART OAOSS TOflL I&I%I QSI OOUAh c3.$OE-I 0.1 0.4 0$21 4.$OE-1 cS.SOE-1 0.1 02$.11E46 6.$3E46~897 15832 02 N 6.01E-10 0$0.1OE46 gaMSM~P~.Q~7 m~, g~rgy(~@Ling@os@~IN'~CTOA L 0.6 0.4 0$PAEFLTEA OfKSS COLSITS CJLAT.OADSS Tare.anS SSSI GMK AESIOf5%ITIC OPEN WING 0 HEAD HT.CLOSED~0 IKAO Ht 1$uQkc cS.SOE-I SLRkt 0.0 0.0 0.0 cS.SOE-1 cS.SOE-1 CART OA068 TOTAL CNTS I QSI 0AOLND DEIOSftX%SQEARAR.E CXWtNHIATKN NOTES 621 E48 1.07E46 1379 2386 ChAT.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE~6 MIN.WITH 35 CUBIC FOOT SAMPLE BACKGROUND COUNT ON LUDLUM 22 IS~SOO GROSS COUNTS.5 MIN COUNT.100 CPM.AIA SAMPLE FLOW a 7 CFM FOR 6 MIN+35 CFM 1 u~II~I~742 LO Ll If<<'.VJX TNE: 1~ST.LUCK NUCLEAR PLANT ONSTTE~DATA~2fl2IRk EXERCISE LUDLUM 2218 8KG 100 001 LUDLUM 2218 EFF FRISKER EFF.AIR SAMPLE VOL.10 LR.ES FAOQ SOUACE SECTOA 04 0.$02 0.1 RKFLTER OAOS8 COLNTS CARl'ADSS TOThL CNTS 8 INI IOOSIE hSI80NIE IXXOC.OOLSQS IT IT, uCVoo 4'.6SE-10 6.48E-TO 9.16E-10'I.SSE40 02 0.$O.Q CART DROSS TOThL CNTS I QSI 421 E46 1.07E44 1.82E44$.78E44 ALE Ao.ek'S Q c gAc~Sgg~~~QLES FAOU SOUACE SECTOR PAEFLTEA OAOSS COLNTS ChAT DROSS TOThL CNTS 5 QN OOLÃSS 0.6 18 0.4 IQOOK hSISORLE CONC.OPBi W~0 HEhD HT.CLOSED~0 HEAD HT UCVoc 4.$0E-1 4.$0E-1 aLRkt 0.1 0.1 CART.DROSS TOThL CNl8 I I%i OOLO88 EEaaEES 12QE46$.11E46 0.$4.$0E-1 0.1 118$4 02 4.68E-10 02 8.10E46 6BW.P~u T'.hl, SMSLLTTCS TF5LbIE~F 44llfJ QhhFS.I ua)CreNI~~4~x SECTOR PI%F8.TEA OAOSS COLSITS ChRT.ORISS TOTAL CNTS 8 QN 0.6 1$0.4 14 0.$14 OPBI~0 HEhD HT.CLOSED liOCXW 0 HElD HT 4SDE-1 0.0 4.$0E-1 4.$0E-1 0.0 ChAT DROSS TOThL CNT8.1 QN OAQUHO DEPOSITION 2.57E48 8.21E48 1.07E46 NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS~BACKGROUND ON IODINE CARTRIDGE 0 6 MIN WITH 35 CUBIC FOOT SAMPLE 8ACKGROUND COUNT ON LUDLUM 221S~500 GROSS COUNTS, 5 MIN COUNT.100 CPM.AIR SAMPLE FLOW~7 CFM FOFI 5 MIN.a 35 CFM 1%%1'lSAS ST.LUCK IIICLEAR PLANT ONSTTE PUNK DATA 82fl2I82 EXERC18E LUDLUM 2218 8KG LUDLUM 2218 EFF.FRISKER EFF.001 10~ES FA061 SOLSTICE PAEFLTER 0$KXS COLNT8 CART.GROSS TOTAL CNTS 6 QN~AMOFNE CXNC.OP84~0 I%K)HT.CLOSED NMXW 0 HEAD HT as 0.1 0.4-N HS.SOE-1 4.12E-10 02 02 8.87E-10 OA 0.1 ChAT.GROSS TOThL CNT$1 QN OOLNIS 821E45 1 07E44 lm97 2SNO~ES f A061 SOLSTICE SECTOR PAEFLTEA GAO66 COLNTS ChRT GA06$TOThL CHTS.6 QN 0.6 15 0.$18 OS 21 02%0k~~.CTIvLT AS INF.Sg+UIEAF ALLI6, IOONE hSLSOINE CONC OPEN WNOOW 0 HEhD HT.CLO6ED VWNOW 0 HEAD HT CAAT.GAO6$TOTll CNTS I I%I uCkc NS.SOE-1 aRELI 0.0 NS.SOE-1 0.1 S.11E45 0.1 02 S.SSE45 8.10E45 11885 17NO d.SOE-1 S.OE-10~4 GOO QaeA 1 W$A 1 AL uLES FRQQ SCONCE SECTOR PfKFLTEA 0$Ã%$COLNTS CART.GAO6$TOTIL CNTS 6 16N 1S OA OS uCVce cS.SOE-1 HS.SOE-1 4$SSE-1 ChAT GA06S TOTAL CHTS I QN GAQLND OEPOSIN 1$fQS 0.0 0.0 FcELEEgLT 2.57E48 8 21E48 0.0 1.07E46 (g>0 HOTES: CART, GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE~E ITIN.WITH SS CUBIC FOOT SAMPLE BACKGROUND COUNT ON LUDLUM 2218~500 GROSS COUNTS, 5 MIN.COUNT.100 CPM.AIR SAMPLE FLOW a 7 CFMFOR 5 MIN.a 35 CFM I Il\II~'C I.~74'F TP 9'I X ST.LUCIE NUCLEAR PLANT OI4SITE PLLNK DATA CV11IS2 EXERCISE LUDLUM 2218 8KG RO-2 8KG LUDLUM 2218 EFF.FRISKER EFF.DOS IO~ES FADE SOUACE 6ECTOR PAEFS.TEA GAOSS COLSITS 0.4 0.$0.2 0.1 N:-:,:::::::::::::.:.::::14 CART.GA06$TOTAL 4$4TS 6 QSI~HQÃXSIE CONC.OPBI WMCN 0 HM)HT.<<S.SOE-1<<S.SOE-1 4.5SE-10 0.15E-10:".::!D i'il'l'i:i.'i'i:.i'.:.i:

'06'i'-iI':

-'i i:Til'i.:: 0.1 02 02 0.4 07 CART.GA06$TOTN.I QSI 422E46 1.07E44 1.52E44$.78E44 1$7QQ 2$$7$$5054 fMbb M.ES F804 SOUACE SECTOR PAEFLTEA GA068 COISITS CHIT.GA068 TOT%.CHTS 6 QSI XKNE ASISOQIE OONC.OPBI WAXY 0 HEAD HT.CLO6ED WQM 0 IDIO HT 0.5 14 UCVoc<<S.SOE-1 0.4 16<<S.SOE-1 0.1 0.$18<<S.SOE-S 02<<S.SOE-S 02 S~.+<~T 4 hJ Ca.teide/Lb'HIT.GA06$TOTlL CNTS I QSI uGaau 12SE45$.11E46 6~45 8.1OE46 2855~118$5 17N2 maTT4 CENTER+0.4 OS PAEFLTER GROSS COLSITS CHIT.GA06$TTTTIL CNTS 6 QSI OOUAh 12 1$1$~AETIO~CONC.OPEN WMKW 0 IKJS HT.CLOSED WOW 0 i%AO HT<<S.SOE-1<<S.SOE-T 0.0<<S.SOE-t 0.0 CHIT GROSS TOTAL Q4TS I 1484 CSNAKES 1.07E46 CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+8ACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUBIC FOOT'AMPLE.

8ACKGROUND COUNT ON LUDLUM 221$~500 GROSS COUNTS.5 MIN.COUNT, 100 CPM.HR SAMPLE FLOW s 7 CFM FOR 5 MIN.a 35 CFM n~74'P 1'I Olfa3lu O.'l,x TSIEL 16:16 Sr.Luce IaCLEAR~T OIIQITE PLLNK DATA 03II2N2 EXERCISE LUDLUM 221$BKG 100 001 LUDLUM 2218 EFF FRISKER EFF 10 PAEFB.TEA OA068 CONITB CAAT.OAO&8 TOTAL CNTB 6 INI 0.6 OOLBLIB.::.:":.::

':.1".0.4:.N 03 02 16 22 0.1<<3.30E.1<<S.SOE-1<<3.30E-1 4.66E-10 IARNLT a1 ai 02 0.3 0.6 CAAT.OA068 TOTAL CHTB I INI OfeLBB)OEPO&fR%~22E46 1.07E4i 1.62E4i S.78E44 13600 23N5 35687 63676 S,~~lc5Q~pA~T LH.ES FAOLI SOLACE SECTOA PAEFN.TEA OA06&COLNTB CART.OA068 TOTAL CHTB 6 QBI OOUAS'13 0.1 14 0$16 17 IOOHE NABOfWE CONC.OPEN WNOOW~HEAD HT.CLOSEO WWOOW 0 HEAOHT CART OA068 TOTAL CHTB I@BI CeUAkS OAOLJBI OEIOSITL011 SQEAAAKE EXBITAIWIATXBI

<<3.30E-I 0.0<<3.30E-1<<3.30E-1<<S.SOE-1 0.1 ai S.11E46 6~46 6.11E46 11837 17806 TEIITII CEIITEILSK

,5 os i CAIRN (~lan.g LN.EB FAHI BOLNCE 6ECTOfl PAEFLTEA OAOBB COL&IT&CAAT.OAOBB TOTAL CHTB 6@BI 0.6 12 O.B 12 0.3 13~ABLBOIWE IX'.OPEN WBNOW 0 HEAD HT.CL06EO~0 HEAOHT 0.0 0.0<<3.30E-1<<3.30E-1<<3.30E-1 0.0 CART OA06S TOTAL CNTB, I IABI OOLaka 257E46 6.22E46 1.07E46 NOTES CART.GROSS TOTAL COUNTS IS TOTAL COUNTS BACKGROUND ON IODINE CARTRIDGE~6 MIN.WITH 35 CUBIC FOOT SAMPI E BACKGROUND COUNT ON LUDLUM 2218~500 GROSS COUNTS.5 MIN.COUNT.100 CPM.AIR SAMPLE FLOLtIf~7 CFM FOR 5 MIN.~35 CFM~~~~W~~1 4 2 14 0 I l~3I'JB ST.LUCIE ISJCLEAR PLANT ONSITE PllNK DATA 02f12f82 EXERCSR LUDLUM 221S BKG IOO 001 LUDLUM 221 S EFF.FRISKER EFF 10 cLSIIc foot QLES FAOLI SOLNCE 0.4:N O.S 02.N.O.I IQONE AIISGfNE CHIC.OPEHHOOCW 0 HEA)HT.CLOSEO WSSXW 0 HEAOHT uOko ckS&I cS.SOE-1 cS.SOE-1 aMr'.::I.!-::i::..::::.i:.:IO 02 CART.OM6$TOTN.CHTS I QSI uObat 267E46 I22E46 1APE44 6711 IW)1 22677 PAEFLLTEA OAOSS COLSITS CreT.OAOSS TOTAL arTS KAHN aOWa I.".:!I OS 0.6 1.02E44 S.TSE46 SQS I SSSS2 cS.SOE.I S.ME-IO a~a kl L-HE~S jvl~M)@Pm~~IN.ES FACY SOLNCE SECCTOA PAEFLTEA OAO6$COLNTS CART GROSS TOTAL CHTS 6ILN IOONE AIRSOfNE CONC.OPBi WNOOW 0 HEII HT.CLOSEO 1NRCN 0 HElO HT CART.OAOSS TOTN.CHTS I I%I OROLSS)OEPONTXIH~ARNE EXWTNNIATXN uCVoc cS.SOE-I cS.SOE-1 0.0 aQSEo$12SE46 S.11E46 02 15'I7 cS.SOE-I cS.SOE.I 0.1 02 6.SSE46 6.11E46 1ISSS 17%6 WRENLT~QCT', Q'fIUL Y m.hJ.ZETEATICA:

4I.5355~ygE gA~g~/uL)~ES FACY SOLNCE 6ECTOR RKFLTER OAOSS OLXSFTS CART.OA06$TOTN.CHTS 6 QN 0.1<<S.SOE-I 0$cS.SOE-I CLO6EO WSEIOW 0 HEIO HT.CART.OA06S TOTAL CHTS I QN SuEAAhK 6 COHTAIQALTIOH NOTES: 0.0 571 0.0 0.0 1.07E46 CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+SACKGIKIU NO ON ISO INE CAR TRICGE 0 5AIIN.WITH 35 CU SIC FOUI SAllP LE BACKGROUND COUNT ON LUDLUM 2216~500 GROSS COUNTS.5 MIN.COUNT.IOO CPM.HR SAMPLE FLOW RA 7CFM FOR 5 MIN As 35 CFM 3~)~K 0 If~3PJ2 AJ'k X 75%I 1LlC BT.LUCK NUCLEAR PLANT OKSAE PLlQK OATA~Stl282 EXERCISE LUDLUM 2215 BKG 100 001 LUDI.UM 22lb EFF.FRISKER EFF 10 iilES f AOQ SOLNCE 0.4;K.0.$02 0.1 CART OA066 TOTN.CNTS 6 QN IOONE ASISOI5%ITIC QPEH WPXXW 0 HEAD HT.I2QSEO NOCXW 0 I%K)HT.CNLT.OAQSS TOTN.l IXI GAOL')OEPOSffÃSI RKAANLE OISffNNIATXXi ai a1 cS.SOE-T 02 cS.SOE-1 OS 4.55E-TO O.e~~SOP~~T5 IN.ES f ACSI SOLSICE SECTIXL 0.4 OS 02 PAEfSTEA GIXXIS COLNTS CART OAOSS TOTAL 13ITS 6 QSI OPEH WSIOW 0 HBIO HT.CLOSEO~0 HGO HT CAAT.OAOSS TOTN.CHTS l LW OAOLSCI OEPOSTIXIl 14 17 0,0$.1'lE46 62$E45 6.11E46 2656 OÃIT 11640 17QI7 cS.SOE-1 cS.SOE.1 cS.SOE-1 cS.SOE-1 QDkb&RLI QA~UETULI.

@~1.TAL~.isTEIPSIF SLDAL~ggr gaza%(~Isa g A I~~ES fAOQ SOLSICE 0.4 0$CAAT.OAOSS TOTN.CHTS C il 12 12 1$OPEN WSSXIW 0 l%IO HT.Q.OSEO'NORM 0 l%JO HT uNe cS.SOE-T aRIIr 0.0 cS.SOE-cS.SOE-T 0.0 CAAT OAOSSTOTN.CSITS li&i OOPS 622E45 1.07E45 13M 2MS NOTES: CART EROSE TOTAL COUNTS IS TOTAL COUNTS~SACNQROUNO ON IOOINE CARTRI USE~S MIN.WlTN SS CUBIC FOOT SAMPLE BACKGROUND COUNT ON LUDLUM 22 IS ss 500 GROSS COUNTS, 5 MIN COUNT.100 CPM.AIR SAMPLE FLOW As 7 CFM FOR 5 MIN.~35 CFM'F~I 0 IL23/92 AJ't X

CONRDENTlAL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 7,5 OFF-SITE RADIOLOGICAL DATA This Scenario Section Contains the Following Information:

Section 7.5.1 Section 7.5.2 Section 7.5.3 FPL OFF-SITE MONITORING DATA OFF-SITE PLUME MAP STATE OF FLORIDA OFF-SITE MONITORING DATA FPL/PSL Rev.0 CONFIDEHTlAL 7.5-1 12/06/91 92EX 7.5.1 FPL OFFWITE MONITORING DATA ST.LUCIE NUCLEAR PtANT 02/$2IQ2 EXERCISE PLUME DATA LUDLUM 2218 BKG 001 TIQEI 12:15 MI.ES FROM SOURCE 05 3 CENTERUNE LUDLUM 2218 EFF FRISKER EFF.AIR SAMPLE VOL'0 10 PREFLTEA GA06S COlÃtS CAAT.GROSS TOTAL CNT8.6 MN CCUAIS 210862 12 12 12 12 12 12 12 12 12 IOONE NA801NE CONC.OPEN WNOOW 0 HEAD HT 4.80E45<<3.30E-1 c3.30E-10 M:i.:!I!:.!IO.

':.i.:I'.:'II!00::::Ii:i c3.30E-10 c3.30E-10 c3.30E-10 c3.30E-10 c3.30E-10 0:O.'.:'-:I

'.:'..:OQ:

'.i'.::I:.i:'O.O:.'-i:iI

'::.i::":0.0 c3.30E-10 4.0 c3.30E-10 0.0 CAAT.GA066 TOTAL CNT8 1 MN OOUAS 258.0 451782 214.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HALF CENTERED MI.ES FROM SOURCE SECTOR PAEF6.TEA GA06S COINTS CAAT.GROSS TOTAL CNTS.6 MN 0.5 1 2 N: '":::: ':i::Hi:I:i:I:

I:.i.:IN 131856 105487 12 3 12 12 12'12 12 8-N 12 12 10 12 GONE NASOANE CONC UCUcc 3.00E45 2.40E4b<<3.30E-1 c3.30E-10 c3.30E-10 c3.30E-10 c3.30E-10 c$.30E-10 c3.30E-10<<3.XE-10 c3.30E-10 OPEN WNOOW 0 HEAD HT.CL06ED WNOOW~HEAD HT.CAAT.GA06S TOTAL CNTS.l MN mRlhr 134.0 1072 0.0 oaata 2X841 164773 0.0 mRjhr iii 20't'ai:-I::.!I'!18Oi!i i:i:ii4FD:ii:..'I:.i!i:.!Dj0:

0.0 0.0 0.0 0.0 0.0 0.0 0.0 MLES FROM SOURCE 0.5 TENTH CENTERUNE 10 PAEFS.TEA GA06S COATS CART.GA06S TOTAL CNTS, 6 MN 21107 12 12 12 12 12 12 N 12 12 12 IOONE NRSOfNE CONC.OPEN WNOOW~HEAD HT CL06EO W66ICW 0 HEAD HT.CART.GAOSS TOTAL CNTS.1 MN UCVcc 5.00Ed7 4.80E+7 21.5<<$.30E-10 0.0 c3.30E-10 0.0 0.0 0.0 0.0 c3.XE-10 c3.XE-1 c3.30E-10 c3.30E-10<<3.30E-10<<3.30E-10::i:.i::OQ'i'i:

"-'i':OO!:i'i i'00 I"': 00 0.0 0.0<<3.30E-10 0.0 00 NOTES: CART GROSS TOTAL COUNTS IS TOTAL COUNTS~DBACKGROUND ON IODINE CARTRIDGE G 5 MIN.WITH 55 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 2218 GS 500 GROSS COUNTS, 5 MIN.COUNT.100 CPM.AIR SAMPLE FLOW NS 7 CFM FOR 5 MIN.35 CFM FPIJPSL Rev I 7.5 1.)0 I/23I92 92EX

TlQE: 12:45 Ma.ES FAO61 SOURCE ST.LUCIE NUCLEAR PlANT 02I$2IQ2 EXERCISE PLUME DATA CENTERUNE N LUDLUM 2218 BKG LUDLUM 2218 EFF FRISKER EFF.AIR SAMPlE VOL 0.01 10 10 PAEFLTEA GAO6S COLNTS CAAT.GAOSS TOTAL CNTS, 6 MN 43973 39474 12 12 12 12 12 12 12 1.00E~6.97'3.30E-10

<<3.30E-10<<3.30E-10 c3.30E-1 c3.30E-10 c3.30E-10 c3.30E-10'O.Q 479 0.0 0.0 0.0 0.0 0.0 0.0 0.0 CAAT.GA066 TOTAL CHTS.1 QN uLES FAO61 SOURCE SECTOR 0.5 HALF CENTERLINE N-':.i:.ii':.I:.:.:I:.'N:tt:.::I

'I: i.'i: N 10 PAEFI.TEA GAO6S COINTS CAAT.GAOSS TOTAL CHTS, 6 QN COUIIIS 21993 19743 12 12 12 12 12 12 12 IOONE AIABOFNE CONC.OP EH WNOOW~HEAD HT.CLO6ED VORQN~HEAD HT.e25Ea7 240 214 5.00E47 4 49E47 212 0.0 5.01E<7 c3.30E-10 0.0 0.0 c3.30E-10<<3.30E-TO c3.30E-1<<3.30E-10 c3 30E-10:!Iles'OQ: '-i.-: '.ilia 00!i:i.-'":"t-'::IO.O::

'I:: 0.0 0.0 0.0 c3.30E-10 OQ 0.0 CAAT.GA06S TOTAL CHTS, 1 LIN Caufke uLES FAOLI SOUACE SECTOA PAEFLTEA GAO6S COLNTS cAAT.GADSBTDTALans,SNN counh.::::"4807.

N 3966 4414 12 N 12 12 12 N:.:::"..-t."-.'IN 12 10 12 IOONE AlABOQIE COHC.OPEN WSEIW 0 HEAD HT macr e.o i.e uCVcc 125E47 1.00EO7 e.97E4S 1.DOE+7 42 c3.30E-1 OP 0.0 c3.30E-10 0.0 c3.30E-10 0.0 c3.30E-10 c3.30E-10 c3.30E-10<<3.30E-10:.:i:i:4Q:.i:.:::.'.:i'.:::.::0.0.'::.'.

I i:::t0.0":-."-':-'.::0,0'-':.:-'.0 0.0 0.0 0.0 CAAT.GAO6S TOTAL CNT6.1 QN COUhl3 NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 6 MIN.WITH 35 CUBIC FOOT SAMPLF.BACKGFIOUND COUNT ON LUDLUM 2218~500 GROSS COUNTS.5 MIN.COUNT, 100 CPM.AIR SAMPLE FLOW~7 CFMFOR5MIN.

~35 CFM FPUPSL Rev 1 7513 01/23PJ2 92EX ISLES FROM SOUACE 05 ST.LUCIE llUCLEAR PLANT 02'I92 EXERCISE PLUlK DATA CENTERLINE LUDLUM 2218 BKG RO 2 BKG LUDLUM 2218 EFF FRISKER EFF.AIR SAMPLE VOL.0.01 10 10 PRESTER GAOSS COPIES CART.GAOSS TOTAL CNTS.6 QII OOUAIS 1283310109 27527 21107 12 12 12 12 12 lODNE AIASOINE CONC.OPEN WNDOW~HEAD HT.CLOSED WOW~HEA)HT.uCVcc 2.87E47 2.$0E47 mph 1i3 3.66E47 182 6.13E47 8.26E47 4.80E47<<3.30E-10 i:i.'!435:.:.'::

i:i:!321:::i:.:::.:i:.I:.:'40:i:.:::.I 29.0 216 0.0 c3 30E-10 0.4 0.0<3 30E-10 0.0 0.0 0.0<3.30E-10<3 30E-10 CART.GAOSS TOTAL CNTS.1 UN COUOte HALF CENTERLIiE ULES FAOLI SOUACE SECTOR PAEFLTER GROSS COLIITS CART.GRAS TOTAL CNTS, S ilPI 0.5 uCVcc 1A3E47 1.15E47 3 80l0 11287 1.83E47 2.68E47 13770 3.13E47 N N'.:.:"-:.i.:'"::.:N 12 12 c3.30E-10 c3.30E-10 10 N'l:iii'..:.'i.'N::::.::::

LN 12 12 12 c3.30E-10 c3.30E-10<3.30E-10 OPEN WHEW~HEA)HT 112 10.7'4A-::i::i-

.i-'i!40 0.0 0.0 0.0 0.0 0.0 GAAT.GAoss TDTAL cNTs.I LQI coute MLES FAOM SOUACE SECTOR 0.5 N N:.iii:i':::i'.

N':i:.!E':i;:::N 10 PAEFLTEA GROSS COISITS 1274 1022 1818 2267 276l 2122 12 12 12 12 12 I CART.GAOSS TOTAL CNTS.S QN OPEN WOW 0 HEAD HT 230E48 3.66E48 5.13E4S S.26E4S i.SOE48 c3.30E-1 c3.30E-10 c3.30E-10 c3.30E-10<3.30E-10'4.0 12 2.9 2.2 00 0.0 0.0 0.0 00 CART.GAOSS TOTAL CNTS.I QI4 NOTES CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 6 MIN.WITH 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 2218 m 500 GROSS COUN I S, 5 MIN.COUNT.100 CPM.AIR SAMPLE FLOW~7 CFM FOR 5 MIN.~35 CFM FPUPSI.Rev I 75 l.c 0 I/23J92 92EX TIMEI 13:16 MLES FROM SOURCE SECTOR ST.LUCIE NUCLEAR PLANT 02/12/S2 EXERCISE PLUME DATA CENTERUNE LUDLUM 2218 BKG RO.2 BKG LUDLUM 2218 EFF FRISKER EFF.0.01 10~le cubic Owl 10 PAEALTER GAO6S COUNTS 1878'1506 9187 14108 10817 12'12 12 12 CAAT.GAOSS TOTAL CNT6, 6 LIN IOONE AIISOINE CONC.uCI/oc 424E48$.39E48 17.:::.:::.:::.1'.00E47 3.20E47$.56E47 c3.30E-10 c3.30E-10 c3.30E.10 c3.30E-10 OPEN WNOOW~HEAD HT.CLO6ED WNOOW~HEAD HT 1b 4.4 15.4 11.4 0.0 0.0 ILO:..:i:i.:i:.i.:!

0:0 0.0 0.0 CAAT.GMSS TOTAL CNTS, I LIN MLES FAOLI SOURCE SECTOA PAEALTEA GRO6S COINTS 0.5 HALF CENTERLIIE Sl15 8 7 8 9 10 N:: i..:".:::m:.i N-".:.i:.::

'.:::i.'".N

'.m'i':-'i:i-'N: i'::::: N'.'-'-'2 12 12 12 CAAT.GAOSS TOTAL CNTS.6 MN IOONE A&BORNE CONC.OPEN WNOOW~HEAD HT.2.12E4S 1.70E48 4.19E48 1.0lE47 1.80E47 1.23E47 1.77E47 c3.30E-10 c3.30E-IO c3.30E-1 i:.i.:'122:i.:'::i:.!40::::.

i:i.:.:'OO:.!i I'.:!.:'OOI!:

c3.30E-IO 0.0 CLO6ED WNOOW 0 HEAD HT 47 7.7 82 0.0 0.0 0.0 0.0 CAAT.GAO6S TOTAL CNTS.I LIN MLES FAOll SOUACE 0.5 TENTH CENTERLbIE N::i': "i:.:Ii'N 10 PREFLTEA GAO6S COINTS CART.GA066 TOTAL CNTS 6 NN couoII 181 1421 1093 1571 12 12 12 12 3.39E40 8.38E40 2.00E4S 3.20E48 2 48E48 3.65E48<<3.30E-IO c3.30E-10 c3 30E-10 c3.30E-10 OPEN WNOOW 0 HEAD HT.CLOSED WNOOW 0 HEAD HT 02 0:i:::i i!Ok 0.4 02'1.0 1.6 lb 0.0 Oy::.:::.:::::::.::..::.qo 0.0 0.0 0.0 0;0 CART.GROSS TOTAL CNTS.I llN OOUAtS NOTES CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 2218 500 GROSS COUNTS.5 MIN.COUNT.100 CPM.AIR SAMPLE FLOWa 7CFMFOR5MIN.

a 35 CFM f PIJPSL Rev.l 751.5 0 I/2362 92EX ST.LUCIE NUCLEAR PLANT 02tl2IS2 EXERCISE PUIiK DATA LUDLUM 2218 BKG 0.01@LES FAOLI SOURCE SECTOR CENTERUNE LUDLUM 221S EFF FRISKER EFF AIR SAMPLE VOL N 10 10 8::":i.'i::

i.'".N CYGNE NRSO&lE CONC.OPEN WHO'HEAD HT uCVoc 9.84E-IO PAEFLTEA GAO6S COLNTS CART.GR068 TOTAL CNTS.6 MN CaulQS 47 7.87E-10 2119'::50898::i:

': '-88985-i:::-:::::".: 1.30E47'I.OOE47 1.82E47 2910 2.92E47 12 c330E-1 12 12 c3.30E-IO c3.30E-IO 0.4 0.7 4.8 8.7 130 0.0 0.0 0.0 chAT.GA06s ToTAL cNT8 1 MN 00ur86 MLES FROM SOURCE 0$HALF CENTERUNE 10 PAEFN TEA GAO6S COUNTS ChAT.GAOSS TOTAL CNTS 6 MN N::i:i'-::i:"-.i.:8!:!I'.:i:i:i'.I:.';N--i'i'.-i:

i: i:W':.i ii:i:.8 N 2210 4005 N N 12-12 12 IOONE h&80fNE CONC.OPEN WNOOW~HEhD HT.CLO6ED WNOOW~HEhD HT UCIicc 4.92E-10 3.94E-10 520E49 2.40E48 S.52E4S mar::::-::!IO'A':..:'::"::::::".:.0>,:i;::.I:.i.:i:;!4$

,.i-:,i.:;:I::::.,4g::::::.::.:.:-:::.:

-:..::4g;:::i:;

mRIhr 03 02 08 S.OOE48 9.08E4S 1.46E47 0.0 0.0 c3.30E-IO c3.30E-10 c3.30E-10 0.0 CAAT.GAO6S TOTAL CNTS.1 MN@LES FROM SOUACE PAEFLTEA GAO6S COINTS 0.5 15 15 TENTH CENTERS 811 N N:I'::i"::-i'-

N 12 10 12 ChAT.GA06S TOTAL CNT8.6 MN c3.30E-10 c3.30E-10 0;I'::.I::ii:::-I-.":0$

124E49 4.79E49 1.30E4S 1.00E4S DIE:";:"::-:.:::11741:::.::..::-:.::

500 1.82E48 2.92E4S<<330E-10 I:::.::::.yA;::.:::.::I:.:.:'.:-0:.::::.'I::..:I'.0.0:::.'::

c3.30E-10 00 c3 30E-10 0.0 0.1 0.1 0.1 02 0.7 0.5 0.0 0.0 0.0 ChAT.GAOSS TOTAL CNTS.$MN NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 2218~500 GROSS COUNTS, 5 MIN.COUNT, 100 CPM.AIR SAMPLE FLOW a 7 CFMFOR 5MIN.35 CFM FPL/PSL Rsv.l 7,5 14.OIQ3$2 ST.LUCIE NUCLEAR PLANT 02I1202 EXERClSE PLUME DATA LUDLUM 2218 BKG 100 0.01 13A5 LUDLUM 2218 EFF.FRISKER EFF.AIR SAMPLE VOL 10 Vo cubic Set LltES FROM SOURCE SECTOR PAEA.TEA GR06S COINTS CAAT.GAOSS TOTAL CNTB, 6 MN IOONE ASBOINE CONC.OPEN WNDOW~HEAD HT<<S.SDE-1 cS.SOE-1 cS.SOE-10 7.08E49 1.50E47 N 10101 12 2.29E47 c3.30E-10:.:::::.:18;8::.::::::.::::I::.:::Oa:.::::I:::

10 12 c3.30E-10 00 0.1 0.1 02 0.4 1.8 S.7 10.9 0.0 0.0 CAAT.GA06S TOTAL CNTS, 1 MN MI.ES FAOM SOUACE SECTOR PAEFS.TEA GA06S COLNTS 0.5 17 18 18 HALF CENTERUNE N 517 1837 3301 N 12 10 12 CAAT.GRAS TOTAL CNTS.6 MN IOONE AIABOINE CCRC.OPEN WNOOW~HEAD HT.c3.30E-10 c3.30E-1 3.54E49 1.50E48 1.15E48 3.89E48 7ASE48:.i:0.9-:iii:

'::iI:i!!k7 iii:i:ii:i!IITR i::,: 1.15E47<<3.30E-10 c3,30E-10'0;0 CAAT.6$K68 TOTAL CNTS.I MN ccuRIS 0.1 0.1 0.1 02 0.8 0.8 1.8 3.5 0.0 0.0@LES FROM RIuRCE SECTOR PREFI.TEA GA06S COLNTS 0.5 13 13 13 N 113 1021 12 10 12 IOONE ASBOINE CONC.OPEN WNDOW 0 HEAD HT uCVce c3.30E-1 mRIhr 0.0 CAAT.GAOSS TOTAL CNTB, 6 MN CCuRIS i I!l 500 0.0 0.0 cS.SOE-1 cS.SOE-10 7.08E-10 0.0 02 0.1::-'::1850 i.:i: i':i-:!1884:::iI 29QE49 2.30E49 7.3QE49 1.5OE4S 229E48-:.i:i:" Id:::i.:i'I

'I':i'::b4".:.I:i

..:.'T4::i'..:':.

0.7 OA c3.30E-10 c3 30E-10 00-':.:--:.:0;0 0.0 0.0 cAAT.GA068 TQTAL cNTB.I MN ccuht6 NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 221S~500 GROSS COUNTS, 5 MIN.COUNT.100 CPM.AIR SAMPLE FLOW a 7 CFMFOR 5MIN.35 CFM FPLJPSL RIIv, I 751-7, 0 li23/92 92EX

ST.LUCIE NUCLEAR PLANT 02IT2IQ2 EXERCISE PLUME OATA LUDLUM 2218 BKG 100 001 TTNE1'I4AO CENTERUNE LUDLUM 2218 EFF FRISKER EFF.AIR SAMPlE VOL 10 LQ.ES FROQ SOUACE SECI'OR PAEFLTEA GA068 COINTS cART.GAOss Tote.cHts,asm oounh uCUcc<<S.SOE-10<<S.SOE-1<<S.SOE-1<<3.30E-10 181 4.43E40 3.30E40 L70EO8 5180 8817!4P4l'i::.58f:: 1.18E+7 2.00EO7 10 7441 1.69E+7 mRJhr 0.1 0.0 0.1 02 02 0.9 5.8 7.9 cART.GA06s TDTAL cHTs 1 QN oouIl4$HALF CENTERUNE@LES FAOLI SOUACE SECTOR PREFS.TEA GA06S COLNTS CART.GA06S TOTAL CHTS 6 QN IOONE AIRSOINE COHC.OPEN WNDOW 0 HEIO HT 0.5 N::ilia:"-

iiiiii:8:':i!I!i ilia i N 17 18 13<<3,XE-10<<3.30E-10<<S.SOE-1<<S.XE-10 N 1350 2598 4414 2.21E40 1.70E40 8.48E40 3.04E4S 5.88E4S 1.DOE+7 0%.: i iii!01: ii::.:ii.-:

07 i::::22::-':::4.'S::i:-'i::

':::::::70 10 SX18 0.1 0.1 0.0 0.1 0.1 0.1 0.4 2.9 4.7 CAAT.GAOSS TOThL CHTS.1 iQ4 CXISI@LES FROCK SOURCE SECTOR 0.5 N TENTH CENTERl%IE N 10 PREFI.TER GA066 COINTS CAAT.GAOSS TOTIL CNIS, 6 QN 13 13 uCVoc<<S.SOE-10<<S.SOE-10 12 13 31<<S.XE-10<<3.XE-10 4.43E-10 3.30E-10 1.70E4Q 8.08E40 1.18E4S 2.00EOS 1.69E48 OPEN WNOOW 0 HEAD HT.CLOSED WNOOW 0 HEAD Ht mRIhr 0.0 0.0 0.0 0.0 Op 0.0 0.0 0;1 i'.I:'i':::-'::-44 0.3 0.1 0%D.e 0.9 D.e CAAT.GA06S TOThL CHTS.1 QN NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 2218~500 GROSS COUNTS, 5 MIN.COUNT, 100 CPM.AIR SAMPLE FLOW a 7 CFM FOR 5 MIN.35 CFM FPUPSL 7,5.1 8 0 I/2362 92EX ST.LUCIE NUCLEAR PLANT 02II2I92 EXERCISE PLUME DATA LUDLUM 2218 BKG 0.01 TIMEt'l4:15 Mi.ES FROM SOURCE SECTOR PAERLTER GA06S COLSrrs 1Q CENTERUNE 17 LUDLUM 2218 EFF FRISKER EFF.AIR SAMPLE VOL 827 2114 10 cubic lect 10 CART.GAOSS TOTAL CHTS 6 MN IOONE ASSOIL CONC.OPEN WNOOW 0 HEAD HT.CLOSED WMIW~HEAD HT UNcc<<SSOE-1<<S.SOE-1 mFUhr 0.1 c3.3OE-1 0.0<<S.SOE-IO 0.0 c3.3OE-10 0.1::"=:: 500'-F::"::1488::..

':.'58IO:.:

I'.:18908':::

cS.SOE-1 2.51E40 1 4OE4S 4.78E4XI'0$:::i:.i:'-.:":!I'.:I02:i:i-:i i.:i.:i: 'Ai:!I!i:.i i:8lF." 0.1 0.1 0.7 5.0 42:.IS9982:.:.::::I:83813

=LOSE+7 8 65E48 CAAT.GA06S TOTAL CHTS.I AN MLES FAOM SOURCE PREFAB.TER GA06S COL%vs CAAT.GAOSS TOTAL CNTS, 6 MN 0.5 18 13 14 N HALF CENTERLIIE N 31Q N 41 10 I915 OPEH WNOOW~HEAD HT UCVcc c3.30E-1 cS.SOE-1<<S.SOE-1<<3.8OE-1<<3.3OE-10 Dt::.:!'."-:'::::I::::OO'::=:.:I:::::::.::::00::::::::::I::::.::-:0>

c3.30E-10 mRkr 0.1 0.1 0.0 0.0 0.0 0.0 0.1 0.4 25 2.1 ChAT.GROSS TOTAL CHTS.1 MN coUnts I Mi.ES FROM SOURCE SECTOR PREALTEA GA06S COINTS 0.5 13 12 12 12 N 10 CART.GA068 TDTAL cNts.6MN counts.'.':.:.:500::.::"I:.:::.:":80 UCUoc<<S.SOE-10 c3.30E-10 c3.3OE-1<<3.30E-10 c3.3OE-10 c3.3OE-10 c3.30E-10 1 40E40.'i 2341!I!I.".: 4448."': I383I: 4.78E4XI 1.03E4S 8 65E49 OPEN WNOOW~HEAD HT CLOSED WNOOW~HEAD HT 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.1 0.4:!I!:i':'08:.:.':::0.6 04 0.5 0.3 CART.mess TOTAL CHTS.I MN counts f(6 NOTES: CART QRQSS TOTAL CQUNTS IS TOTAL COUNTS BACKGROUND ON IODINE CARTRIDGE 0 6 MIN WITH SS CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 2218 ss 500 GROSS COUNTS, 5 MIN.COUNT.100 CPM.AIR SAMPLE FLOW a 7 CFM FOR 5 MIN.35 CFM FPuPSL Rev I 7519 0 II23$2 92E X ST.LUCIE NUCLEAR PLANT 02ISSIQ2 EXERCISE PLUME DATA LUDLUM 2218 BKG 0.01 TWE: fit LUDLUM 2218 EFF FRISKER EFF.AIR SAMPLE VOL 10 MLES FADE SOURCE SECTOR PAEFLTER GA06S COINTS CAAT.GAOSS TOTAL CHTS.5 QN 05 18 15 N 13 13 18I7 10 cS.SOE-10 cS.SOE-10 c3.30E-10 c3.30E-1 c3.30E-10 cS.SOE-10 2.07E49 1.10E48 4.17E48 3.52E48 OPEH WNOOW 0 HEAD HT.CLOSED WNOOW 0 HEAD HT 0.1 0.1 0.0 0.0 0.0 0.0 0.0 0.1 O.e 2.1 1.8 CAAT.GROSS TOTAL CHTS I QN OOUfA ua.ES FAOu SOUACE SECTOR PREFLTEA GAO66 COLNTS CAAT.GAOSS TOTAL CHTS 6LIN IQONE ASSOAHE COHO.OPEH WNDOW~HEAD HT OS 18 c3.XE-10 15 cS.XE-1 13 c3.30E-10 13 c3.XE-10 13 c3.XE-1 12 13 c3.30E-10 c3.30E-1 1 OSE40'0:0!i:.-':.::i.:i-:

04::i:iI:ii:!

01 SAQE49 10 N 1.78E48 0.1 0.0 0.0 0.0 0.0 0.0 0.0 0.1 0.9 CAAT.GAOSS TOTAL CHTS,)MN QLES FAOQ SOUACE SECTOR PREFLTEA GA06S COLNTS CAAT.GROSS TOTAL CHTS.6 QN OS 13 13 12 12 12 12 12 10 21 50: ii: '::ll;928:.:i:

'::.:l2)08

-"':-." 1855 c3.30E-1 c380E-10 c3.80E-10 cS.SOE-10 c3.XE-10 c3.30E-10 c3.30E-10 00:::";::.

'.::'-i'..::

0:.:::::'-.::

'..:':i'::O:0':.:-:"i.

.:.i-::'-00 c3.30E-10 1.10E49 4.17E49 3.52E49 40::::..:.:-:::.:":0:f:::.::::::::-:::

OLS:::.::I

"'-:::0;8 0.0 0.0 0.0 00 0.0 0.0 0.0 0.0 0.1 02 02 CAAT.GROSS TOTAL CHTS.I QN NOTES.CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 2218 500 GROSS COUNTS, 5 MIN.COUNT, 100 CPM.AIR SAMPLE FLOW+7 CFM FOR 5 MIN.e 35 CFM FPLJPSL Rev I 751~10 OI/23$2 92EX

TQ4E: 16I16 c ST.LUCIE NUCLEAR PLANT 02lf 2I$2 EXERCISE PLUlK DATA LUDLUM 2218 BKG RO-2 BKG LUDLUM 221$EFF.FRISKER EFF.AIR SAMPLE VOL OOI 10 MLES FROM SOUACE SECTOR PAERLTEA GA06S COINTS CAAT.GAOSS TOTAL CNTS.6 MN 0.6 13 13 13 13 13 12 N 12 13 10 13 cS.SOE-1<<SXE-I c3.30E-10 c3.30E-IO c3.30E-10 c3.3OE-1<<3.30E-IO<<3.30E-IO c3.30E-10 c3.30E.10 c3.30E-IO OPEN WNOOW 0 HEAD HT.CLOSED WNOOW 0 HEAD HT 0.1 0.1 OD 0;0:.i:.i:i.:i.:i.:i:DAI 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q6:i:-'i:iI eQ 0.0 00 CAAT.GA06S TOTAL CATS 1 MN Ml.ES FAOM SOUACE SECTOR PAEFILTEA GA06S COUNTS CART.GAOSS TOTAL CNTS, 6 MN IOONE AIASOINE CONC.0.5 N'::i:::ii'.:!liiiii8!i'ilia iiiiiii:N'iiiiiii i:iiii:i'N 13 13 13 13<<S.SQE-IO c3.30E-IO<<3.3OE-I c3.30E-IO 12 c3.30E-10 12 12 12 c3.30E-10 c3.3OE-IO 4.30E-IO N 12 13 c3.30E-IO c3.30E-10 10 13 c3.30E-I 0 OPEN WNOOW~HEAD HT.CLOSED WNOOW~HEAD HT OA)0.0 0.0 0.0 0.0 0.0!:ii..i'i::::::OA}..'.':'.::

.'.'::40 0.0 0.0 0.0 0:Di i::i':i-i':QO 0.0 0.0 0;Q 0.0 CAAT.GROSS TOTAL CNT6.I MN OOISIIB MLES FlKM SOURCE SECTOR PAEFLTER GA066 COINTS OS 12 12 12 12 12 N 12 12 12 N 12 12 10 12 CART.GAOSS TOTAL CNTS, 6 MN OOUAtS:i:.500 uCVoc 430E-10 cS.SOE-1 cS.SOE-10 c3.30E-10 c3.30E-10 c3.30E-IO<<S.SOE-IO c3.3OE-10 c3.30E-IO c3.30E-IO c3.30E-IO OPEN WNOOW~HEAD HT.CLOSED WNOOW 0 HEAD HT IIIfNr 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 QO i:i::: '00 0.0 00 cAAT.GAoss TQTAL cNTs.I MN eels NOTES CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 6 MIN.WITH 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 2216~500 GROSS COUNTS.5 MIN.COUNT, 100 CPM.AIR SAMPLE FLOW+7 CFM FOR 5 MIN.+35 CFM FPIJPSL Rev.I 751.13 0 I/2362 92EX TIME: 1600 ST.LUCIE NUCLEAR PLANT 02fl2f82 EXERCLSE PLUlK DATA RO.2 BKG LUDLUM 2218 EFF FRISKER EFF.AIR SAMPLE VOL 0.01 10 LUDLUM 2218 BKG 100'/o Vo cubic feeI iQ.ES FAOM SOURCE SECTOR PREFS.TER GA06S COUNTS CAAT.GAOSS TOTAL CNTS.6 MH 13 13 N:.:::.:i::.:'::::::i:-.::i:

'-'.::IN::i.:i:":,:::::i':N:.::,:::,:.I::.::i:::N 12 12 12 12 13 12 10 N 12 OPEN WHDOW 0 HEAD HT.CLOSED WHOOW~HEAD HT cS.SOE-1 cS.SOE-1 c3.30E-10 c3.30E-10 Dih'i il'::.i:i.:iTl'.i'.ll i'.!I!i'O.::i:ill:i:i IDN 0.0 0.0 0.1 0.1<<3.30E-10 c3.30E-10 c3.3OE-10 c3.30E-10 c3.30E-10<<3.30E-10 DD:..:i.:':

':.';:.',:.'0D:.;:.:'.:';:.';:.i:.:;00'i:.i:i:i:.'.:!0':.';.:'.

i:.'.:';!00:.';I:":.i:.i'0 0.0 0.0 0.0 0.0 0.0 0.0 c3 30E-10 oa 0.0 CAAT.GA06S TOTAL CHTS.1 MH MAES FROM SOUACE SECTOR PAEFS.TEA OAO6S COIHTS CAAT.GA068 TOTAL CHTS, 6 MH IOOHE luRSOfHE CONC.OPEN WHOOW~HEAD HT 0.5 13 c3.30E-10 Dii 13 c3.3OE-10 N 12 cS.30E-1 12 cS.SOE-10'12 c3.30E-10 12 c3.XE-10'0'.0 12 c3.30E-10 12 N 12 12 10 12 c3.XE-10<<3.30E-10 c3.30E-1<<3.30E-10 40!:.i i.:i:i.:00:.i.:i:.':ii:.i:::00:i:i::.::"IO;Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 CAAT.GROSS TOTAL CNTS.I LIH ccIIIIL TENTH CENTERLIIE MLES FROM SOUACE SECTOfl PREFKTEA GAO6S COLHTS 0.5 12 12 12 3 12 12 12 12 12 10 12 cAAT.GAoss TDTAL cNTs.6 MH cotNh.:.:i:i 500 UCifcc cS.SOE-10 cS.SOE-10 c3.30E-10 c3.30E-10 c3.XE-10 c3.XE-10 c3.30E-10<<3.XE-10 c3.30E-10 cS 30E-10 c3.3OE-10 OPEN WHOOW 0 HEAD HT.CLOSED WHDOW~HEAD HT abbr 0.0 0I:::I::::;:::.::.::::I::0:a 0.0 0.0 0.0 0.0 0.0 0.0 0.0 OO 0.0 00'" 0.0 0.0 CAAT.GAOSS TOTAL CHTS.I LIH Ceufs NOTES CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 2218~500 GROSS COUNTS, 5 MIN.COUNT.100 CPM.AIR SAMPLE FLOW a 7 CFM FOR 5 MIN.a 35 CFM f PUPSL Rev I 751~Io 01/23'2EX

TILlEI 16A6 MLES FROM SOURCE 0$ST.LUCIE NUCLEAR PLANT 02/12/82 EXERCISE PLUME DATA CENTERUNE N LUDLUM 2218 BKG RO-2 BKG LUDLUM 2218 EFF FRISKER EFF.AIR SAMPLE VOL NI:.3:.'::-'I:'2 N 001 10 10 PAEFS TEA GA06S COINTS 13 12 12 12 12 12 12 12 12 ChAT.GAOSS TOTAL CHTS.5 MN IODNE hlASOAHE COHC.cS.SOE-I cS.SOE-IO c$.30E-IO c3.30E-IO c3.XE-IO<S.XE-IO c3.30E-IO c3.30E-IO<3.30E-IO c3.30E-IO<3.30E-I 0 OPEN WNOOW 0 HEAD HT.CLO6ED WMXNf~HEAD HT Oil 0.1 0.1 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Oh:::::::::::::::::.:I:O.O::.:::.:::::::.:I.:::Fo'.O O.a 0.0 O.Q 0.0 CAAT.GA068 TOTAL CHT8.I MN OOURIS MI.ES FROM SOUACE SECTOR PAEF1.TEA GA068 COINTS ChAT.GAOSS TOThL CNTS 6 MN lOONE hlASOANE COHC.OPEN WNOOW~HEAD HT.CLOSED WNOOW~HEhD HT.ChAT.GROSS TOThL CHTS, I MN 05 13 UCI/CC c3.XE-I mR/hr:.::::.':DA:.-'..:I-mR/hr 0.0 N:;il:i: i'::ilia:N 13 12 0.0 0.0<<S.XE-IO c3.30E-IO 3 N 12 12 N 12 12 c3.XE-IO c3.30E-I N.XE-IO c3.30E-IO:iii:i'DO::i::I::::i'::.:Ol'I::-.:':::

i i:.'00!i::i

.i-'":DA):.:.'i 0.0 0.0 0.0 0.0 N 12 c3.XE-IO 0.0 N 12 12 c3.30E-IO<<3.30E-IO'00-:':-':::.

'.o 0.0 0.0 10 N 12 c3.XE-IO 0.0 MLES FAOM SOUACE 0.5 TENTH CENTERUNE 10 SECTOR PAEFILTER GA068 COINTS ChAT.GA06S TOTAL CHTS, 6 LIN 12 12 12 12 12 12 12 12 12 12 IOONE NASOINE CONC.OPEN WNOOW 0 HEAD HT 0.0 00 c3.30E-I cS.SOE-IO c3.30E-IO 0.0 c3.30E-IO 0.0 c3.XE-IO 0.0 c3.XE-IO'0:0 0.0 c3.30E-IO 0.0 c3.30E.IO c3.30E-IO c3.XE-IO<3.30E-IO.:.::.::::.o.a:::::::::.'::::..:O.o:::.:::::

":::::Qo::::::-::::::.o.o:::::":

0.0 0.0 0.0 0.0 chRT.GAoss TDThL cHTs.1 MN caUAIe NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+BACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUBIC FOOT SAMPLE.BACKGROUND COUNT ON LUDLUM 22 IS 500 GROSS COUNTS, 5 MIN.COUNT, 100 CPM.AIR SAMPLE FLOW a 7 CFMFOR 5 MIN.a 35 CFM FPL/PSL Rev I 7.5.1~15 0 I/23/J2 92EX

ST.LUCIE NUCLEAR PLANT 02/12IQ2 EXERCISE PLUME DATA LUDLUM 2218 8KG 100 0.01 TIQEf 1440 LUDLUM 2218 EFF FRLSKER EFF.AIR SAMPLE VOL 10 Mt ES FAOLI SOUACE SECTOR PAEFILTEA GROSS COLNTS chAT.GAoss TDThL cffTS.6 MN CNmte 13 12 12 12 12 12 12 10 12 GONE hIABOfNE COHO.OPEN WNDOW~HEho HT uCVcc<<S.SOE-1 mfMr:.i:i:.!

OiI:.I I cS.SOE-1 c3.30E-10<<3.30E-10 c3.30E-10 c3.3OE-10;::.::::,oo:;::::;:::::::::::.::;:ba:::.:::::::::.:::.::IO'.o:".;:-::F c3.30E-10 c3.3OE-10 c3.30E-10<<3.30E-10 c3.30E-10:.i:i:0.0.::-:::::::

O.Q'i.:::I

..".0:O'.:: mRIhr 0.1 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 CART.GAOSS TOTAL CHTS.I MN counts MLES FAOM SOUACE SECTOR PAEFILTEA GAOSS COLNTS 0.5 13 13 i12 12 12 12 12 12 N 12 10 N:::::.:N 12 12 ChAT.GROSS TOThL CffTS.4 MN IOONE hIABOfNE COHO.OPER WNOOW~HEAD HT c3.30E-10 c3.30E-1 c3.30E-10 cS.XE-10 O;I:'ll::i:::

':i::i-".Nl::

ii::::i::-::::40::iii.::::ii::i:OIO':

c3.30E-10 c3.XE-10'0:0 c3.30E-10 c3.30E-10 c3.30E-10 c3.30E-10 c3.30E-10 o.o:.:.::.:::.

-:::.:Ioa 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 00 ChAT.GROSS TOTAL CHTS.1 MN CCurIIN TENTH CENTERUNE MLES FROM SOUACE SECTOR PAEFILTEA GROSS COLNTS 0.5 12 12 12 12 12 N'i:I:i".'i:iI'i.:II 12 12 12 12 12 10 12 ChAT.GROSS TOThL CIITS, 4 MN IOONE hIABOINE CONC.OPEN WNOOW~HEAD HT mRfhr 0.0 0.0 uCVcc c3.30E-10 c3.XE-1<<S.SOE-IO<<3.30E-10 c3.30E-10 c3.XE-10 c3.30E-10 c3.30E-10 c3.30E-10::.:::-:::

Oa:::::.:::.:':":::.:O:O::I::::::::::.:::.:::.On I::.::::.I:.:::.:::.::O.O:::::::.::I:..::::.:'.:O.O::.:::.::-

.00 0.0 0.0 0.0 0.0 0.0 0.0 c3.30E-10 oo 0.0 c3.30E-10 O.O 0.0 ChAT.GAOSS TOTAL CHTS.f MN NOTES: CART.GROSS TOTAL COUNTS IS TOTAL COUNTS+8ACKGROUND ON IODINE CARTRIDGE 0 5 MIN.WITH 35 CUSIC FOOT SAMPLE BACKGROUND COUNT ON LUDLUM 2218~500 GROSS COUNTS, 5 MIN.COUNT, 100 CPM.AIR SAMPLE FLOW a 7 CFM FOR 5 MIN.a 35 CFM FPLJPSL Rev.f 7 5 1-16 0 II23$2 92EX

7.5.2 FF-SITE PLUME MAP

'o ST LUCIE 8LyO'I~~p fl OP v<AQWw Avt IKRCE Z BELC)%II CANAL f+~5 C<+o ORANOE AyE NllCl watT I ill~TIANTIC DCEAN p S~O Ogk h S MILES IIIOWAY AO 2 MILES T LUCIS 4 LEAR ASLANT NI t Q j A T NR A All 2~A EeyO la Vl I C 7fg RT>y U Jtldlll ltkCH 10 Ql\MARTIN OOWNS QV MARTIN HWY IQ CONFlDENTNL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAIKDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 8.0 MISCELLANEOUS This Scenario Section Contains the Following Information:

Section 8.1 Section 8.2 Section 8.3 EVALUATION MATERIALS-Forms and record sheets to be utilized by the FPL Evaluators in recording and evaluating the performance of the participants.

REFERENCES

-Pertinent scenario data references.

ACRONYMS AND ABBREVIATIONS

-An alphabetical listing of many acronyms and abbreviations utilized in the scenario text and at the St.Lucie Nuclear Plant.Section 8.4 SITE LAYOUT DATA-Reference data on the St.Lucie Nuclear Plant location, key facilities, access routes, etc.FPL/PSL Rev.0 CONFIDENTlAL 8.0-1 12/06/91 92 EX

8.1 EVALUATION

MATERIALS This Data to be Provided Later 82 REFERENCES MAIN POWER OISTRIBUTION SYSTEM UNIT 1 FIGURE 1 NUTCIO>>ON ISANl atl>>WIXN STATIC WTCAY S WICAY t NOWAY I~O>>,Ir>>~AY~MTS SAT S~OSI tkST I>>SV SUS~AT I IA STMT US ITIN U>>T S~4>>>>EATON NNN~lk lt A I~lkk M IAI ISNT~OCIESATEN SS Itl*I~1kk~.I~IAS A>>IAS RSII~.I~IM~.IS ISS~I k'I~Ill~US UIII I*IIII<<SUS U>>T 2 IAI CL lk atSA I AS Lt I SS CC IS I LL 4C, lkl WU I C IAS WY.I C lkt w v.I C.ltl AICT.sawAxx SOOTY WC IAO AEAOTON AWA WC 1k 1 TUSL MEA WC I AS SAIL rkSTE WC I AS~ITAKE AWA WC Ikk re T SEA TIWIT SIANT~S I Ik W>>WCIAS TUA NANISNO WC I AT atSA Aktk WC lkk ktkOTON Mtk WC Ilk AEAOTON Mtk WC ISA W>>IUA IMINLNO WC 1 ST atSAAASA WC ISO A tACTOO MEA ICC ISA k EACTOO MEA AUTO SUS TSANSES IU~IH~IUA L AAEA WC 1tl llew kAtA WC I!I AAL rkklt ICCISS r Tkktkktk WCI 4 rTS, lt EATICNT IIAN T ICC I~11 NIL MILCI ICCI~>>CONOENSATE JOUTNTS 0311016, Rev.2 20 01/1 4/91 1992 Exercise Main Steam Line Monitors 1.00E+04 1.00E+03~MSI.'A'MSL'B'.00E+02 E 1.00E+01 1.00E+00~-a~a 1.00E-01 I~I aA o aA ca aA cI aA aD IA aD aA D aA o aA O aA D IA CI<)D aA D IA D aA n CI e-n W CI r n W aD~-n W CI e-Y)W D~n W D~n~D~n~CI ca ra ca cxi oi w oi ai ci ci ci o-" cv cv ri ri n Yi n n v: v'D D D CI D aD O D r w~e e~r w~a~e~w e e r~

1992 Exercise CHRRNS 1.00E+05: Q-:Q~Q.:-Q-:Q=XE-.0 1.00E+04 1.00E+03$.1.00E+02 1.00E+01 1.00E+00 1.00E-01 CD CD CD lA C'D lA CD C)CI CD IA C)cn C)C)C)C5 lfi a~n v.CS CD~v~~lA Y)lt~~r~I-I-I-I-H~~~l f I Y)CV CV CV e~~CD~i~~'=--I-t-t&-I-I CA M lA CD ali C>V'~CA V O~i n V VC WC VC lCi~V~~~

1992 Exerctse Contatnment Chemistry Summary 1.00E+07 1.00E+06 1.00E+05 1.00E+04 1.00E+03 1.00E+02 I 4 I~~}I I I I I I I I I I I 4 I I I I I I I I I I I i I I I I I I I I}I I}j 4 I)I I I I}I II I 1 I I I I I I!I I l.I I 4 t t I 4 t~I I I~I 4 I II I ill I!ill 4 4 4 1 1 4.t I 1 I'-I 4 1 4 1 I I 1 4}~}4 4}t~~I I 1}I 1}}I t 1 4 I I t t t I I}1~l g}C'.=I i i}~1 1}I}!!4}~~~}I}=: i i I i i E~1.00E+01 I 1 I I I I I!ll!I I!I 4 I I t 1 I I I 4 I 1 4 4}}4~~i t 4~1.00E+00 1.00E-01 1.00E42 I I I I I I I I 4 I I I I I i I I I I I 4 I I I I I 4 4!Ijl ill I jl I I jll I ll I I 1 I I I I I i I I I}I i I}}f}I I lillli i I I I I I I I I i i i i I I i I I IIIII IIII I Illillillilllllll IIII ill I i i i i}f i 4}}}ljlii 1.00E-03-I I I 4 4 4 t~~I 4 4~I I f I~I 1 I}I}4 I 4 4 t 4 4}I 1.00E-04 t 4 I t 1~4}1 I I I I I I}4 f~4 I 1 t l 4 1 1}}}}I 1 t I l 4 t~1}1.00E-05 10:00 10:30 11:00 11:30 12:00 12:30 13:00 13:30 14:00 14:30 15:00~ACS TOTAL~CNT ATM TOTAL-'CNTSMP TOTAL

1992 Exercise SlG A Concentration 1.00EA5 1.00E+04 1.00EA3 1.00E+02 1.00EA1 I I IIIII~I II I I I I I I I I I I I I I Illlltllllljllllllllllll ltttlltlflllftttffftttft tftfttttlftltfttlllfflff !Illllllllllllllllllllll I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I llllllllllll!Il I I I I I I!Ill}1 I I ll f}1}}I a f f aa 1 a a a a a!f11 N/G TOT'lfjj<<a l2 TOT fttj a I t I t I a I I I a I I I ia-'PART TOT llll tffttttfffttftfttff 1.00EAO 1.ME-01 1.00E-02 t I I tb tlf flllII)I I I I I}I I I I I I a a a a a a I I a I I I I Illlttfljlljtl I I I!if I f I I I II I I I t I I I I I I I I I~TOTAL I-131 DEQ I I I f I I I a a E 1.00E-03 c3 ,~1.00E-04 I I I I I I I I I}t I t I I t I I I llllllllllllllllllll jill Illlltlll I I I I I I I I I I I I!I I I I I I I lllllljjljlljll I I I I I I I a a a lll!l!1 1.00E45 IIIII}}}l}l}ttt}t}}t lilt lllllllllll I I}11 I I I I I I 1}I I 1.00E-06 fttfttlf fit tlltft t a'ttfjftfj 1.00E-08~I a i l af al I I I!I I I I I 1.00E-09~~i~I I I I I a iI t I 1.00E-07 I i I!I}!t I!I I I t!I I I I I t IIIIII ttlf I I I I I'l l'11 I!I I!jj}ajIlttl lllltlltllllllflfllfljtl f I I I I I I I I t I 1}1}I t I I)I 1.00E-10 1.00E-11 1.00E-12 I I I I I I I I I!I I I I I I I I I I I t I~I I I I I I I I I I I I I t I I I I I I I I I I I I I I I I I I I I t I I I I I I I I 1 I I I I I I I I I I I I I I I I I I I I I I I I I a I I I I I I 10:00 10:30 11:00 11:30 12:00 12:30 13:00 13:30 14:00 14:30 15:00 1992 Exercise Containment Sumps 1.00E+05 1.00E+04 1.00E+03 1.00E+02 1.00E+01 E~1.00E+00 3 3 Z j 1.00E-01 1.00E-02 1.00E-03-~l2 TOT~PART TOT-~-TOTAL~I-131 DEQ 1.00E-04 1.00E-OS 10:00 10:30 11:00 11:30 12:00 12:30 13:00 13:30 14:00 14:30 15:00 1992 Exercise Contatnment Atmosphere 1.00E~1.00E+03 1.00E~~A 4 I~I A~\I I\I A t I I I~~l I~L J I A A I j~~~4~~~I~I~~~I 4~j I j K 4 A I 4~1.00E+01 1.00E+00 1.00E-01 E c3 1.00E~~I x I 4 A I A I 4 j C A l L I~5~l I I~I~A A~~~I A~1\A I I~N/G TOT~12 TOT-'PART TOT A~A I L S j~z I T I z~TOTAL-i-1-131 DEQ 1.00E44~~~L l I R 4~l I t 4~~A~J t I l I A A~A~I I j l~I~A I~~~~~~'I~~~~I~~l~~I A~1 1.00E-05~t 1.00E-06 1.00E-07 10:00 10:30 11:00 11:30 12;00 12:30 13:00 13:30 14:00 14:30 15:00 1992 Exercise RCS Activity Summery 1.00E+07 1.00E+06 1.00E+05 1.00E+03 E c3 1.00E+02 1.00E+01 1.00E+00~N/G TOT~l2 TOT-o-PART TOT~TOTAL->-I-131 DEQ 1.00E%1 1.00E-02 10:00 10:30 11:00 11:30 12.'00 12:30 13:00 13:30 14:00 14:30 15:00

CQNRDENTNL FLORIDA POWER AND LIGHT COMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 8,3 ACRONYMS AND ABBREVIATIONS AC ADV AFAS AFP AFW ANPO ANPS ARC ARM ATWS AUX BAMT BALI'HB BOP Alternating Current Atmospheric Dump Valve Auxiliary Feedwater Actuation Signal Auxiliary Feedwater Pump Auxiliary Feedwater Auxiliary Nuclear Plant Operator Assistant Nuclear Plant Superintendent American Red Cross Area Radiation Monitor Anticipated Transient Without SCRAM Auxiliary Boric Acid Makeup Tank Battery Backup Heater Breaker Balance of Plant C-E CAS CAT CCAS CCW CEA CEDM CET CFMS CHRRM CIAS CNTMT COND Combustion Engineering Central Alarm Station Chemical Addition Tank Containment Cooling Actuation Signal Component Cooling Water Control Element Assembly Control Element Drive Mechanism Core Exit Thermocouple Critical Function Monitoring System Containment High-Range Radiation Monitor Containment Isolation Actuation Signal Containment Condensate (Condenser) FPIJPSL Rev.0 CONFlDENTNL 8.3-2 12/06/91 92EX

CONFlDENTNL FLORIDA POWER AND LIGEI'OMPANY ST.LUCIE NUCLEAR PLANT 1992 EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 12, 1992 8,3 ACRONYMS AND ABBREVIATIONS CONT CPIAS CPM CPS-CR CRAC CS CSAS CSS CST CIL CTPC CVCS DC DCS DE DECON DEM DER DHRS DNB DPM DPS EAL EBS EC ECCS ECO Controller Containment Purge Isolation Actuation Signal Counts Per Minute Counts Per Second Control Room Control Room Auxiliary Console Containment Spray Containment Spray Actuation Signal Containment Spray System Condensate Storage Tank Chemistry Team Leader Containment Temperature and Pressure Control Chemical Volume Control System Direct Current Duty Call Supervisor Dose Equivalent (eg: DE-I)3i)Decontaminate (Decontamination) Florida Division of Emergency Management Florida Department of Environmental Regulation Florida Department of Health&Rehabilitative Services Departure From Nucleate Boiling Disintegrations Per Minute Disintegrations Per Second Emergency Action Level Emergency Broadcast System Emergency Coordinator Emergency Core Cooling System Emergency Control Officer FPL/PSL Rev.0 CONF1DENTlAL 8.3-3 12/06/91 92 EX CONFlDENTlAL

8.3 ACRONYMS

AND ABBREVIATIONS (Continued) EDG EDT EIM EMT ENC EOC EOF EOP EPA EPIP EPZ ERDADS ERF ESC ESF ESM F-A FEMA FEOC FCV FPL FRERP FRMAP FSAR FT Emergency Diesel Generator Equipment Drain Tank Emergency Information Manager Emergency Medical Technician Emergency News Center Emergency Operating Center Emergency Operations Facility Emergency Operating Procedure U.S.Environmental Protection Agency Emergency Plan Implementing Procedure Emergency Planning Zone Emergency Response Data Acquisition and Display System Emergency Response Facility Engineered Safeguards Cabinet Engineered Safety Feature Emergency Security Manager First Aid Federal Emergency Management Agency.Field Emergency Operations Center (DEM)Flow Control Valve Florida Power and Light Company Federal Radiological Emergency Response Plan Federal Radiological Monitoring and Assessment Plan Final Safety Analysis Report Flash Tank GAC GAM GAR GDT GE GPM Governor's Advisory Committee Governor's Affairs Manager Governor's Authorized Representative Gas Delay Tank General Emergency Gallons Per Minute FPL/PSL Rev.0 CONFIDENTNL 8.3-4 12/06/91 92EX

CONFIDENTIAL

8.3 ACRONYMS

AND ABBREVIATIONS (Continued) HPSI HPT HR HRD HSCP HT HVAC HX IC I&C ICW IRS High Pressure Safety Injection Health Physics Technician Heat Removal Hot Ring-Down (Phone System)Hot Shutdown Control Panel Holdup Tank Heating, Ventilation and Air Conditioning Heat Exchanger Inventory Control Instrumentation and Calibration Intake Cooling Water Iodine Removal System JENC Joint Emergency News Center Potassium Iodide LCO LGR LOCA LOF LOOP LPRT LPSI LPMS Limiting Condition for Operation Local Government Radio Loss of Coolant Accident Loss of Feedwater Loss of Off-Site Power Low Pressurizer Pressure Relief Valve Trip Low Pressure Safety Injection Loose Parts Monitoring System MCA MCC MDA MERL MOV MPC MPH MSIS Multi-Channel Analyzer Motor Control Center Minimum Detectable Activity Mobile Emergency Radiological Laboratory (DEM)Motor Operated Valve Maximum Permissible Concentration Miles Per Hour Main Steam Isolation Signal FPUPSL Rev.0 CONFIDENTNL 8.3-5 12/06/91 92 EX

CONFlDENTNL

8.3 ACRONYMS

AND ABBREVIATIONS (Continued) MSIV MSLB MSSV NAWAS NEDO NC NPO NPS NRC NSSS NUE NWE Main Steam Isolation Valve Main Steam Line Break Main Steam Safety Valve National Warning System Nuclear Energy Duty Officer Natural Circulation Nuclear Plant Operator Nuclear Plant Supe'rvisor" U.S.Nuclear Regulatory Commission Nuclear Steam Supply System Notification of Unusual Event Nuclear Watch Engineer OSC PACB PAG PAR PASS PCs PIO PLCS PORV PPM PRM PROC PZR Operational Support Center Plant Auxiliary Control Board Protective Action Guideline Protective Action Recommendation Post-Accident Sampling System Protective Clothing Public Information Officer Pressurizer Level Control System Power Operated Relief Valve Parts Per Million Process Radiation Monitor Procedure Pressurizer QT Quench Tank RAB RAS RAT RC Reactor Auxiliary Building Recirculation Actuation Signal Resin Addition Tank Reactivity Control FPUPSL Rev.0 CONFIDENTNL 8.3-6 12/06/91 92EX

CONFIDENTIAL 8,3 ACRONYMS AND ABBREVIATIONS (Continued) 'CA RCC RCP RCS RDT RECS REP RM RO RPM RPS RRS RSO RT RTGB RTL RV RVLMS RWT Rx.Radiologically Controlled Area Reception and Care Center Reactor Coolant Pump Reactor Coolant System Reactor Drain Tank Radiological Emergency Communication Radiation Exposure Permit Recovery, Manager Reactor Operator Radiation Protection Manager Reactor Protective System Reactor Regulatory System Radiation Safety Officer Reactor Trip Reactor Turbine Generator Board Radiation Team Leader Reactor Vessel Reactor Vessel Level Monitoring System Ref'ueling Water Tank Reactor System SAE SAS SB SCFM SCS SE SEC SED SEOC SFSC S/G SIAS SIS SIT Site Area Emergency Secondary Alarm Station Station Blackout Standard Cubic Feet Per Minute Shutdown Cooling System Solenoid Valve Security Sequence of Events Diagram State Emergency Operating Center Safety Function Status Check Steam Generator Safety Injection Actuation Signal Safety Injection System Safety Injection Tank FPUPSL Rev.0 CONFIDENTIAL 8.3-7 12/06/91 92EX

CONFIDENTIAL

8.3 ACRONYMS

AND ABBREVIATIONS (Continued) SMM SMRAP SRO SRT STA SWGR SWP Subcooled Margin Monitor Southern Mutual Radiological Assistance Plan Senior Reactor Operator Spent Resin Tank Shift Technical Advisor Switchgear State Warning Point SYC TBV T.TCV TCW Th TO'ref TSC VCT Average Coolant Temperature Turbine Bypass Valve Cold Leg Temperature Temperature Control Valve Turbine Cooling Water Hot Leg Temperature Turbine Operator Turbine Control System Reference Temperature Technical Support Center Volume Control Tank XFMR Transformer FPL/PSL Rev.0 CONFIDENTIAL 8.3-8 12/06/91 92EX

V~8.4 SITE LAYOUT DATA~ries 5 lIIAP14<<t A 4 Y f41 8'44gL 4 For any emergency response, the Control Room of the affected unit serves the initial point of control.The Nuclear Plant Supervisor stations himself in the affected unit's Control Room when he assumes the role of Emergency Coordinator. The Emergency Coordinator can leave the Control Room if necessary, after a proper turnover to a qualified alternate Emergency Coordinator, to make a personal assessment regarding plant safety.The Control Rooms are designed to remain tenable under accident, conditions described in the Final Safety Analysis Report.All plant related operations are directed from the Control Room.Nuclear plant instrumentation, including area and process radiation monitoring system instrumentation, is provided in the Control Room to give early warning of a potential emergency and to provide for continuing indication of an emergency situation. The Control Rooms contain the controls and instrumentation necessary for operation of the reactor under normal and emergency conditions. A supply of radiological emergency equipment is maintained in the Control Room.Each Control Room contains the necessary communications equipment for notifying on-site personnel and offsite authorities in the event of an accident.This includes the State's Hot Ringdown telephone, National Warning System (NAWAS), Local Government Radio System, Emergency Notification System (ENS)to the NRC Operations Center (in Bethesda,- MD), commercial telephones, Florida Power and Light Company radio system, public address system, PAX telephone system, portable radio sets (walkie-talkies), and a radio paging system.These systems are used as defined by procedure to accomplish the necessary notifications and communications. The Company maintains an on-site Technical Support Center ta provide the Control Room and the Emergency Operations Facility with in-depth diagnostic and engineering assistance without adding to congestion within the Control Room.This assistance can help determine the operational decisions that would be appropriate to better control and mitigate the consequences of the emergency. The Technical Support Center is located in a block of rooms ad)acent to the Unit 1 Control Room.19 Activation of'he Technical Support Center vill be initiated hy the Emergency Coordinator in the event of an Alert, Site Area Emergency or General Emergency. Arrangements have been made to staff the Technical Support Center in timely manner.The Technical Support Center contains pertinent records and dravings.Xt has an emergency communications network similar to the Control Room, with the exception of NAWAS.The Company maintains an on-site Operational Support Center to serve as an assembly point for auxiliary operators, health.physics technicians, maintenance personnel, and other plant shift personnel available to support the emergency response.Required staff vill he assigned to appropriate activities hy the Emergency Coordinator or his designee.The Operational Support Center is located on the second floor of the Service Building in the large conference room.Equipment that can he used hy personnel dispatched from the facility is stored in the same building.Activation of the Operational Support Center will be initiated by the Emergency Coordinator. Xt vill be in operation for an Alert, Site Area Emergency or General Emergency and will be staffed in tim'ely manner.The Company maintains an Emergency Operations Facility from which evaluation and coordination of all FPL activities related to an emergency can be carried out and from vhich FPL can provide information to Federal, State, and local authorities. The Emergency Operations Facility is located at the intersection of State Road 712 (Midway Road)and X-95 approximately 10.5 miles vest of the St.Lucie Plant.The Emergency Operations Facility has sufficient space to accommodate the FPL response organization and designated representatives of Federal, State, and local government. 20 The Emergency Operations Facility has an emergency communications network including but not limited to Local Government Radio, commercial telephane lines, State Hot Ringdown phone, NRC ENS, and FPL Company Radio.Essential precalculated emergency data, UFSAR, T/S, Procedures, and selected drawings are available. Activation of the Emergency Operations Facility is the responsibility of the Emergency Control Officer and is required for a Site Area Emergency or General Emergency. Arrangements have been made for staffing in a timely manner.An Emergency News Center is provided to allow the news media access to information Crom the Emergency Operations Facility.The Emergency Znformation Manager will designate an individual ta supervise the Emergency News Center.The Center is co-located with the Emergency Operations Facility (Midway Road and Z-95). 1~4 Ficpxre 1: Travel Directions to Plant st.Lucie PWNT: ST.LUCRE uceeaa Fforfda Power 8 Ught Ca.I.ocATIQN: FL Pferoe, FL OI~IXO HIOII WCC'lJI~INIRINlOIQLI ThhS ee Attgtit~Iloii tS~e<<g Iloeg, lbrtt~egItg I%WH~10el<<tg pgeeeg o~gL lb'Note II ENI gl, Hlgfhwy 74 IO~NgleOy'I, tel%L4 I NOle'I l4+Iwey AIA I\ee ttgttL IlA4 O'IA 44II Ittgttg~eg e~~wgswop e<<t ttote Itohg 0%~II 0%Ow%<<eaxeoteo~~<<xwa~iS4nwa-.LUCIE I l40f TO OCJLi~$$$ALLOW OA4HEO IKQTS 4WeWe 44.PAUA BKACM AIRPORT 17

Figure 2: St.Lucie Plant Site Layout/On-site Emergency Response Facilities yQ 0 Q I fe 0 21 0 CI~[I 8 op$8'7 Figure 3: Unit 1 controL Room 6?.p>EI,.4-Enqineerea SafrOuaro LoOcc Caoanet 8-Enqineereo Safeguaro C Cheeacal volue~Contr=;0 oeactlvatv E-Reactor Coolant Svste~-Conoeneate CoolinO G bromine Generator RaO Hons torcnO Panels l-Reactor>~otect~v~Svs Coeeunccatxons Kcusome~K-EA0405 t.-Office Kgtchen N~TeChnlcal Suooct t Cen ti N 22 Figure 4 Technical Support Center COe~fg oncet tie WON TOC'PINQ4ggye tQ4'gkH AM.orna%TW Shht ref 4~Na%%IINl 23 Figure 5: Travel Oirectiona to the Emergency Qyerationa Facility and Neve Canter ST.LUC%POWSI Kf&T AfACOSztNC V.S.1~~~~0 IPcScl Rive'~~C OCam~~t~t j~~Rosa sa hag lan-A St hach She~~~~St.4eie Casey~~~~~~Mane Cavy~~~~~St.4cie 5 24

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