Latest revision as of 14:08, 4 February 2020

Text

Rev 8 to Emergency Plan Implementing Procedure 3100033E, Offsite Dose Calculations.
	ML17214A683
Person / Time
Site:	Saint Lucie
Issue date:	01/09/1984
From:	Schmidt A; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17214A680	List: ML17214A679; ML17214A681; ML17214A682; ML17214A683; ML17214A684;
References
	3100033E, NUDOCS 8402070388
	Download: ML17214A683 (96)
	v • d • e

~jP ~cga

~g 1 of 10 pp FLORIDA POWER & LIGHT COMPANY ST. LUCIE.PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E REVISION(:, 4

1.0 Title

ON-SITE SUP RT CENTERS 2.0 ~Aroval:

Reviewed by FP4ilit Revie~ Group /l l gr cfog > 4- l.5 19+~

Approved by / V. P Power. Resource Rev. 4 reviewed FRG 1982 Approved by 1982 3."0 ~Eco a:

3. 1 Purpose This procedure provides guideli es and responsibilities for activation .and use of the on-sit Technical and Operational Support Centers. This procedure d scribes interim facilities and shall be revised when permanent acilities are operational.

3.2 Discussion The activities of plant management, techn'cal and engineering /R4 support personnel are an important part of the overall site response to an accident, and must be proper defined and logistically supported. The need for additio al operational support personnel, other than those required a d allowed in the Control Room, is also recognized as vitally important in properly responding to an emergency.

The intent of, providing Technical and Operational Su ort Centers

,is to provide bases where post-accident emergency pl ning can be conducted and required operational support personn can assemble for potential duty. Both centers will be in ose communication with the Control Room via the PAX phone s tern, without disrupting, congesting, or confusing the activiti s in the Control Room by the physical presence of additional pe sonnel,

e Page 2 of 10 EHERGENCY PLAN IMPLEHENTING PROCEDURE NO. 3100032E, REV 4 ON-SITE SUPPORT CENTERS 3.3 Description 3.3.1 Technical Support Center (TSC)

The TSC's located in the training classroom area, adjacent to the Unit 81 Control Room. Emergency supplies available near the TSC are listed in Table 1. Documents and drawings available are listed in Table 2.

3.3.2 Operational Support Center (OSC)

The OSC is maintained in the first floor maintenance area of the Service Building.

3.3.3 Communications Equipment The Control Room contains necessary telephone and public address systems for communications within and outside the plant. The Control Room al" o contains NAMAS and Local Government Radio for communications with state and county ~

agencies. Use of these systems is described in the Appendix.

The*TSC contains necessary telephones to communicate with the Control Room, OSC, the General Office Emergency Center, the Emergency Operations Facility and. outside agencies.

It also contains an ENS dedicated telephone to the NRC Operations Center and the NRC Region XX Office. /R4 I

3.4 Authority This procedure implements the St Lucie Plant Radiological Emergency Plan.

4.0 Precautions

4.1 The TSC and OSC shall be activated upon the direction of the Emergency Coordinator or his designated alternate only.

4.2 Radiological conditions in the on-site Technical and Operational Support Center shall be monitored when required to be 'in use.

Radiation levels in the TSC should be monitored using available (control room) portable instruments. /R4 4.3 The Emergency Coordinator shall recommend a suitable location other than the designated areas such actions.

if radiological conditions warrant

1 I

0

Page 3 of 10 EMERGENCY PLAN ItPLEHENTING PROCEDURE NO. 3100032E, REV "

ON-SITE SUPPORT CENTERS 5.0 Res onsibilities:

5.1 The Emergency Cooxdinator is responsible for activating the TSC, activating the OSC, and arranging, for staffing through the Duty Call Supervisor.

5.2 The TSC Supervisor will be the most senior person available to remain at the TSC of the following:

Primary: Technical Supervisor Alternate Off duty Shift Technical Advisor (See 3100023E, Emexgency Roster)

He is responsible for supervising TSC activities, reporting to the Emergency Coordinator, and communicating with the Emergency Operations Facility.

5.3 Each department head or designated alternate is responsible for reporting to the TSC when called.

5.4 Those reporting to the Operational Support Center are responsible for being prepared to carry out support functions designated by.

the Emergency Coordinator.

5.5 The Emergency Coordinator has the overall responsibility for the conduct of emergency operations and activities and should work closely with the TSC to ensure all information is used in making accident recovery decisions.

5.6 The gC department is responsible for ensuring that records, documents, and prints are maintained in the TSC or are available for immediate use in the Document Control vault.

5.7 .Health Physics Dept shall provide a portable monitor -to the Technicial Support Center for radioiodine .monitoring. This monitor can also be used for'monitoring the control room.

6.0 References

/R4 6.2 E-Plan Implementing Procedure 3100021,"Duties of the Emergency Coordiantor".

6.3 E-Plan Implementing Procedure 3100033E, "Off Site Dose Calculations".

6.4 E-Plan Implementing Procedure 3100022E, "Classification of Emergencies".

7.0 Records

A record of actions taken at the TSC shall be maintained by the TSC Supervisor.

II, )

Page 4 of 10 EMERGENCY PLAN IIPL~r KNTING PROCEDURE NO. 3100032E, REV 4 ON-SITE SUPPORT CENTERS

8.0 Instructions

8.1 Activation The Emergency Coordinator shall activate the TSC and the OSC for an emergency condition classified as Alert, Site Area Emergency, or General Emergency.

8.2 Staffing The Emergency Coordinator shall arrange for staffing through the Duty Call Supervisor, Table 3 identifies the TSC staffing requirements.

J 8.3 Use of the Technical Support Center The TSC shall be used to provide plant management and technical support to plant operations personnel during emergency conditions. A primary task shall be to relieve the Emergency Coordinator of off-site communications to the state and local agencies, NRC and the FPL Off-Site Emergency Organization.

~

This task becomes the responsibility of the EOF when they are manned and fully operational. The TSC staff shall piovide technical support as requested by the Emergency Coordinator and shall /R4 direct itself toward determining current and projected plant status and providing in-depth diagnostic and engineering assistance, as required.

8.4 Use of the Operational Support Center The Emergency Coordinator shall assign available plant staff not needed in the TSC or Control Room to the OSC. The OSC Supervisor (Assistant Superintendent Mechanical Maintenance or designated alternate) shall maintain communications with the TSC and report as directed by the Emergency Coordinator or TSC Supervisor.

8.5 Deactivation It is the responsibility of the Emergency Coordinator or his designee to deactivate and secure the TSC and OSC when the emergency dondition no longer exists.

8.6 Alternate OSC In the event that the OSC becomes untenable, the Emergency Coordinator shall designate an alternate location.

NOTE: The Steam Generator Blowdown Building is outfitted to be an alternate OSC. /R4 l

1 Page 5 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 4 ON-SITE SUPPORT CENTERS TABLE 1 RADIOLOGICAL EKRGENCY EQUIPMENT ST LUCIE PLANT CONTROL ROOM STORAGE LOCKER (ALSO FOR TSC USE)

1. Coveralls

2. Hood

3. Gloves

4. Shoe Covers

5. Self Contained Breathing Apparatus

6. Full Face Respirators and Filters

7. Pocket Dosimeters

8. Dosimeter Chargers

9. TLD's

10. Portable Count Rate Instrumentation

11. Portable Dose Rate Instrumentation

12. Contamination Smears

13. Envelopes

14. Radiation Tape/Rope

15. Radiological Signs

16. Industrial First Aid Kit

17. Step-Off Pads

18. Plastic Bags

\

Page 6 of 10 EMERGENCY PLAN INPLEHENTING PROCEDURE NO. 3100032E, REV 4 ON-SITE SUPPORT CENTERS TABLE 2 EMERGENCY DATA, DRAWINGS AND,DOCEfENTS MAINTAINED AT THE TSC ST 1UCIE PLANT

1. Plant Technical Specifications C

2. Plant Operating Procedures

3. Emergency Operating Pro'cedures

4. Emergency Plan and Implementing Procedures

5. Final Safety Analysis Report

6. Drawings, Schematics and Diagrams

Page 7 of la EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 4 ON-SITE SUPPORT CENTERS TABLE 3 TECHNICAL SUPPORT CENTER STAFFING ST LUCIE PLANT TSC Supervisor Primary: Technical Supervisor Alternate Off duty STA (per 3100023E, Emergency Rost'er)

Operations Representative (Off duty Duty Call Supervisor or NPS)

Health Physics Supervisor (Radiation Team Leader) /R4 Chemistry Supervisor Reactor Engineering Supervisor Maintenance Superintendent Quality Control Supervisor Support Staff as determined by these supervisors

Page 8 of 10 K!ERGENCY PLAN IMPLFJfENTING PROCEDURE NO. 3100032E, REV 4 ON-SITE SUPPORT CENTERS APPENDIX CO~i ICATIONS EQUIPMEHT A. Use of the NAWAS System

1. The NAWAS is used for announcing the initial warning to the State Warning Point at the Bureau of Disaster Preparedness (BDP) and St. Lucie Disaster Preparedness Coordinator of all

.four Emergency Classes.

2. The NAWAS is a direct, protected telephone land line with the handset installed in the Control Room.

3. Picking up the handset from its cradle activates a response at the State Warning Point and St. Lucie and Martin County Disaster Preparedness Offices. The Nuclear Plant Supervisor (Emergency Coordinator) will advise the personnel on the other end of the system, in a coded message, of the conditions at the plant. He then places the handset back on its cradle, as this is the only use for it during an emergency. His message will activate the required state and local emergency teams.

4. The procedure for reporting an emergency via NAWAS is summarized in E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator, and described in detail below.

A. (1) "S'tate Warning Point Tallahssee, this= is St. Lucie aslant

'(State War'ning Point will give a go-ahead)

"State'Warning Point Tallahssee, this is St. Lucie Plant /R4

tBPRRt Time "Acknowledge, over."

(ALTERNATE METHOD) If NAWAS is unavailable-telephone State Warning Point at PHONE NO. 1-904-488-1320 or Florida Marine Patrol-Alternate, State Warning Point 1-904-488-5757.

State Warning Point will call via Phone to validate the notification. After validation, transfer the information on the State of Florida Fixed Nuclear Facility Notification Message Form via NAWAS or ALTERNATE METHOD. /R4 State Warning Point Message Validation Time

Announce the class as indicated by EPIP 3100022E "Classification of Emergencies"

Page 9 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV .4 ON-SITE SUPPORT CENTERS APPENDIX (cont)

A. Use of the NAWAS System (cont)

Classifications The classes of Radiological Emergencies are described in E-Plan Implementing Procedure 3100022E, Classification of Emergencies.

3, Plume Exposure Pathway A. The Plume Exposure Pathway will extend outward from-'each nuclear power plant for a radius of ten (lQ) miles, and /R4 shall be segmented into 22-1/2 arcs and will be lettered A through R (excluding I and 0) for the 360 of the compass.

B. Each area is divided into SECTORS beginning at the ce"ter and extending outward in mile increments One through ten. /R4 Contaminated area, extending outward from the nuclear plant, will be located and reported as discussed in E-Plan Implementing Procedure 3lQQQ33F;-"Off-Site Dose Calculations."

B. Use of the Local Government Radio (LGR)

1. The LGR is used, unless inoperative or unavailable, for maintaining communications with various state and local disaster preparedness personnel. Messages are transmitted and received on frequencies allocated by the state Bureau of Disaster Preparedness.

2. The LGR control unit is installed in the Control Room, and TSC.

C. Use of the ENS Telephone Network /R4

1. Within one hour of the, time that the Emergency Plan or any part of the Emergency Plan is implemented the NRC shall be notified and an open, continuous communications channel established using the NRC ENS circuit (red phone). The Nuclear Plant Supervisor (Emergency Coordinator) shall be responsible for assuring that this notification is made.

2. To initiate a signal to the NRC Operations Center, remove the handset from the receiver.

3. When the NRC Duty Officer answers, identify yourself as "Florida Power 6 Light, St Lucie Plant".

Page 10 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE HO. 3100032E, REV "4 ON-SITE SUPPORT CENTERS APPENDIX (cont)

C. Use of the ENS Telephone Network (cont) /R4

4. Make the notification.

5. Maintain the line open and manned until allowed to terminate the call by the NRC Duty Officer.

~i Cp

/

Page 1 of 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN DPLEMENTING PROCEDURE NO. 3100050E REVISION 6

l. 0

Title:

MAINTAINING EMERGENCY PREPAREDNESS EMERGENCY EXERCISES, DRILLS, TESTS, AND EVALUATIONS.

2. 0 ~Avovels:

Reviewed by Facility Review Group July 25, 19 75 Approved by K. N. Harris Plant Manager'uly 293 19~

Rev. 4 Review by FRG l~ t 19 P C Approved by V, P. Power Resources 19~

Rev. 6 Review v Facility Rev Group ~ca ~ e NV 19' Approved by Ms 3.0 ~Soo e:

3.1 Purpose This procedure provides instructions for conducting periodic emergency exercises, drills, and tests.

3.2 Discussion Periodic exercises and drills will be conducted in order to test the state of emergency preparedness of participating personnel, organizations, and agencies. Each exercise or drill will be conducted to:

1) Ensure that participants are familiar with their respective duties and responsibilities.

2) Verify the adequacy of the Emergency Plan and emergency procedures;

3) Test the communication network and systems.

4) Check the availability of emergency supplies and equipment.

5) Verify the operability of emergency equipment.

These exercises and drills will simulate emergency conditions and may be scheduled such that two or more exercises or drills are conducted simul-taneously. R6 The results of the exercises will form the basis for corrective action to eliminate identified deficiencies, and will be discussed during a post-exercise evaluation. R6

J

~

'=

a 4

C Page 2 of 6 FLORIDA POWER 6 LIGHT COMPANY'T.

LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100050E REVISION 6 3.0 ~Sco e: (cont'd) 3.3 Authority This procedure implements the St. Lucie Plant Radiological Emergency Plan.

4.0 Precautions

4.1 Every emergency alarm,or announcement shall be assumed to be true unless an announcement is made to the contrary.

5.0 Res onsibilities:

5.1 The FPL Emergency Planning Supervisor shall be responsible for planning, scheduling, and coordinating all major emergency drills or exercises involving off site agencies. When an exercise is to be conducted, the Emergency Planning Supervisor shall:

a) Schedule a date for the exercise in coordination with the Health Physics Supervisor- and the primary State and county emergency response agencies. R6 b) Request that the Health Physics Supervisor assign personnel to assist the Emergency Planning Supervisor prepare a scenario. -

R6 c) Coordinate all FPL efforts with other participating personnel, organizations, and agencies.

d) Obtain the approval of the Plant Manager.

e) Offer federal, state and local observers the opportunity to evaluate the exercise.

f) Discuss and evaluate the exercise with observers and principal participants. I for all identified deficiencies, corrective I

g) Ensure that measures are recommended.

h) Prepare and retain documentation for record keeping.

l i

'a t,

Page 3 of 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100050E REVISION 6 5.0 Res onsibilities: (Cont'd) 5.2 When an exercise or a major drill is to be conducted, the Health Physics Supervisor shall assure that the following is accomplished:

a) Assign personnel to prepare a scenario.

b) Coordinate through the Emergency Planning Supervisor all activities which involve off-site personnel organizations or agencies.

c) Schedule a date for this activity in coordination with the Emergency Planning Supervisor and assign observers.

d) Obtain approval of Plant Manager.

e) Review evaluations of exercise or drill with the observers and the Facility Review Group.

f) Ensure that deficiencies which are identified are addressed with corrective measures.

g) Prepare and submit documentation to the Emergency Planning Supervisor for record keeping.

6.0 References 6.1 St. Lucie Plant Radiological Emergency plan 6.2 NUREG 0654 7.0 Records and Notifications 7.1 Log Entries 7.2 Written evaluation to FRG, Plant Manager, and Emergency Planning Supervisor by the Health Physics Supervisor.

7.3 Consolidated exercise summary by the Emergency Planning Supervisor.

I

' ia

Page 4'f 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100050E REVISION 6 8.0 Instructions 8.1 The following emergency exercises, drills, and tests shall be conducted-at the frequency indicated:

a) Exercises (Inte rated Drills)

A major radiological emer'gency response exercise shall be conducted at least once every twelve (12) months (plus or minus three months)-to demonstrate the effectiveness of the Emergency Plan. This exercise shall be conducted as a Site Area Emergency or General Emergency and will provide for the coordination with and,participation of off-site emergency response personnel organizations and agencies including those of federal, state, and local governments. The emergency scenario shall be varied from year to year.

Provisions shall be made to start at least one exercise between 6:00 PM and midnight, and at least one exercise between midnight and 6:00 A.M., every six years. The "Affected Unit" in the exercise should be changed from year to year. R6 This emergency response exercise shall be critiqued by Florida Power & Light Company observers/evaluators and other observers as appropriate from federal, state, and local agencies. R6 b) Radiolo ical Monitorin 'rill A radiological monitoring drill shall be conducted at least once every twelve (12) months (plus or minus three months). These drills will include collection and analysis of sample media (e.g. water, air).

This drill should include testing of communications and understanding of communications between the RTL and the teams.

c) Health Ph sics Drills R6 Thc Health Physics Department shall conduct health physics drills semi-annually and one of the semi-annual"drills may be incorporated into the radiological monitoring drill.

d) Medical Emer enc Drill A medical emergency drill involving a-simulated contaminated individual, with provisions for activation of the plant First Aid and Personnel Decontamination Team and participation by local support services (i.e., ambulance and off-site medical treatment facility), shall be conducted at least once every twelve (12) months (plus or minus three months).

Page 5 of 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100050E REVISION 6 8.0 Instructions (cont'd) 8.1 (Cont'd) e) Fire Emer enc Drill Fire drills are conducted in accordance with Technical Specifications to test the operational readiness (personnel, equipment and procedures) to control and extinguish a fire onsite. The drills also serve to evaluate and document the response of onsite personnel and participating off-site agencies to varying fire situations. The communication links and notification procedures are tested at least semi-annually during fire emergency drills. A post-drill cr'itique is held after each fire drill completed to identify possible areas for improvement in equipment and/or procedures.

f) Communications Tests Communications with the Bureau of Emergency Management, Department of Health and Rehabilitative Services, and St.

Lucie and Martin County Disaster Preparedness Coordinators within the plume exposure pathway Emergency Planning Zone (EPZ) will be tested monthly.

8.2 Conducting Drills 8.2.1 The Nuclear Plant Supervisor (NPS) shall evaluate the plant conditions and ascertain that the drill will not adversely affect plant equipment or operations.

8.2.2 The Health Physics Supervisor shall designate specific members of the plant staff to act as controllers and evaluators during the drill. These controllers and evaluators shall be familiar with the procedures and proper actions to;be taken associated with their post during the drill. Additionally, briefings shall be, conducted to indicate what purpose the drill will service and what specific areas the controllers and evaluators should be concerned with.

These controllers and evaluators shall be posted throughout the plant area to observe and record the actions of plant personnel during the drill and to verify alarm audibility.

8.2.3 After receiving a signal of alarm indicating that an emergency condition exists, which has been initiated as part of the drill, the NPS shall take action as required by the Emergency Plan.

R6

I Page 6 of 6 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN Il'PLEHENTING PROCEDURE NO. 3100050E REVISION 6 8.0 Instructions (cont'd) 8.2 (cont'd) 8.2.4 At the termination of the drill, the NPS shall announce over the PA system that the drill is over. This shall be repeated along with any required instructions.

8.3 Evaluation of Drills and Exercises 8.3.1 Following a drill the Health Physics Supervisor shall R6 assimilate all information and data concerning the .

emergency procedure drill and hold a critique on the drill, and present a summary of the critique to the FRG. R6 The FRG shall recommend changes to the Emergency Plan Implementing Procedures as necessary. R6 8.3.2 Following an exercise, the Emergency Planning Supervisor, plant management, FPL controllers and evaluators and R6 principal participants in the exercise will meet to discuss and evaluate the exercise.

The evaluation shall be based on the ability of participants to follow emergency procedures, the adequacy of emergency procedures, and the adequacy of emergency equipment and supplies. Plant management shall be responsible for necessary changes in the Plant Emergency Procedures and for recommending and/or submitting changes in the Emergency Plan to the Emergency Planning Supervisor.

8.3.3 The FRG shall submit a written evaluation following an exercise.to the Emergency Planning Supervisor. These comments will be incorporated, with comments from other principal participants and controllers and evaluators, into a consolidated exercise summary. The summary will be dis-tributed as described in the "Duties and Responsibilities of the Emergency Planning. Supervisor" procedure. R6

/

I I

Page 1 of 30 FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE PLANT E>>PLAN IMPLEMENTING PROCEDURE NO ~ 3100033E REVISION 8

1.0 TITLE

Off-Site Dose Calculations 2.0 REVIEW AND APPROVAL:

Reviewed by Facility Review Group March 20 and 25 1981 Approved by A. D; Schmidt V.P. Power Resources March 26 1981 Revision 8 Revi by P. R G Approved by V.P. Nuc Energy 19++

3.0 SCOPE

3.1

Purpose:

3.1.1 This procedure provides a method for estimating'hole body and thyroid dose rates and integrated whole body and thyroid dose for the area surrounding the site out to 12 miles.

3 '.2 This procedure provides a method of comparing. dose estimates, release rates, and radiati'on levels in containment to Emergency Classifications Guidelines.

3.2 Discussion

3.2.1 This procedure is applicable to both Unit 1 and Unit- 2.

Provisions have been made to sum the releases from both Units should both be releasing radioactive materials during an emergency.

3.2.2 The Chemistry Department representative should use the computer dose calculation model, if available, for estimating off-site whole body and thyroid dose rates and integrated doses when releases of radioactive materials occur during an emergency. This model closely parallels this procedure.

This procedure provides the means for hand calculation of offsite dose rates and integrated doses.

'DR 8402070388 840202 PDR ADOCK 05000335 F

, !R,I

t 0

A

Page 2 of 30 ST ~ LUCIE PLANT .

E PLAN IMPLEMENTING PROCEDURE 3100033EP REVISION 8 OPF-SITE DOSE CALCULATIONS

3.0 SCOPE

(continued) 3.2 (continued) 3.2.3 The Emergency Coordinator will use these off-site dose estimates, release rates, and radiation levels in containment for emergency classification of off-site protective action recommendations. The'mergency Coordinator or his designee will perform these off-site dose calculations if the Chemistry Department representative is unavailalle to do so.

3 '.4 This activity may be duplicated by the dose assessment group.

in the EOF when it is manned and operational. This serves as a redundant/check for off-site dose data.

3.3 Authoritv

This procedure implements the St. Lucie Plant Radiological Emergency Plan.

4.0 PRECAUTIONS

None 5 ' RESPONSIBILITIFS:

5.1 The Emergency Coordinator or his designee shall assure that whole body and thyroid dose rates and integrated doses are calculated, following releases of radioactive material during an emergency.

5.2 The Chemistry Department representative shall make the estimates upon arrival at the Technical Support Center at the direction of the Emergency Coordinator or his designee.

6 ' REPERENCES:

6.1 St. Lucie Plant Radiological Emergency Plan 6.2 St. Lucie Plant Radiation Protection Manual 6.3 "Duties of the Emergency Coordinator," EPIP 3100021E 6.4 "Classification of Emergencies," EPIP 3100022E 6.5 "Bases for Accident Dose Calculations for St. Lucie Nuclear Power Plant" (Bases prepared by HMM Associates of Waltham, Massachusetts.)

6.6 "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,"

NUREG-0654, Revision 1 6.7 St ~ Lucie Unit 1 FSAR 6.8 St. Lucie Unit 2 FSAR

P:ge 3 of 30 ST ~ LUCIE PLANT E-PLAN IMPLEMENTING PROCFDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS 7.0 RECORDS AND NOTIFICATIONS:

The attached worksheets shall be retained as qualitv records.

Notifications are made per EPIP 3100021E.

Page 4 of 30 ST ~ LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100 )33E, REVISION 8 OFF-SITE DOSE CALCULAT:ONS 8 ' INSTRUCTIONS:

8.1 Upon the initiation of an event which has resulted in or could result in releases of radioactive material, the Containment High Range Radiation Monitors (if inoperable, use Post LOCA) reading should be compared to the Action Guidelines for supplemental classification of the event.

8.2 Determine the release rate for Noble gases and Iodines. If both Units are releasing radioactive material during an emergency, determine the release rates for both plants separately and add the results as requested.

Four methods for release rate determination are available. If Chemistry grab sample analysis data is available, METHOD A (Al for Unit 1, A2 for Unit 2) should be used. METHOD B (Bl for Unit 1, B2 for Unit 2) is used when grab sample data is not yet available and effluent monitors are operable. METHOD C (applicable to both Units), CHRRM method, is used if. METHOD B can't be used. As a default, METHOD D (applicable to both Units), Post LOCA monitors, may be used for release rate determination.

4 8.2.1 For the affected Unit(s), complete a RELEASE RATE'WORKSHEET using the appropriate method for release rate determination. /R8 8.3 Determine the current meteorological data using the, METEOROLOGY WORKSHEET. Three methods for meteorological data determination are available. METHOD A (Site Meteorology Tower) uses the 15 minute average met data from the Control Room met data recorders. Method A serves as the primary source of data. METHOD B (West Palm Beach NOAA or Vero Airport FSS) serves as a backup. Manipulation of data from these sources is handled in Appendix C. METHOD C (default) serves as the secondary backup source of data.

8.3.1 For the affected Unit, complete a METEOROLOGY WORKSHEET using the appropriate method (use only one method).

Page 5 of 30 ST ~ LUCIE PLANT E-PLAN IMPLLMENTING PROCEDURE 3'100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS

8.0 INSTRUCTIONS

(continued) 8.4 Calculate Off-site Doses using the POSE CALCULATION WORKSHEET 8.4.1 If both plants are releasing radioactive material during an emergency, total the Noble gas and Iodine release rates.

8.4.2 Multiply total NOBLE GAS RELEASE RATE (Ci/sec) by WHOLE BODY DOSE FACTOR (mRem/hr/Ci/sec) to determine WHOLE BODY DOSE RATE. /R8 NOTE: The whole body dose rate conversion factor is determined from Dose Factor Tables and is based on precalculated dose rates at 1, 2, 5, and 10 miles from the plant; meteorological conditions (stability and w.'.nd speed), and a 1 Ci/sec release rate.

8 ' ' Multiply TOTAL IODINE RELEASE RATE (Ci/sec) by THYROID DOSE FACTOR (nRem/hr/Ci/sec) to determine THYROID DOSE RATE. /R8 NOTE: The thyroid dose rate conversion factor is determined from Dose Factor Tables and is based on precalculated dose rates at 1, 2, 5, and 10 miles from the plant; meteorological conditions (stability and wind speed),

and a 1 Ci/sec release rate.

8.4.4 Enter the dose rate results in part 6A. Noting wind direction, record dose rate results in the i'ndicated sector and the adiacent sectors (on each side) in part 6B.

8.5 The Emergency Coordinator or his designee shall monitor release rates and meteorological conditions to determine how frequently to update the dose rate estimates. Dose rate estimates shall be updated if any of the'ollowing averages change by the amounts

.indicated below over a period not to exceed 30 minutes:

1. Release rates increase by more than 25T.

2. Wind speed decreases by two classes or more.

3.'tmospheric stability becomes more stable by more than one class (e.g., stability D to F).

4. Wind direction changes by more than 22.5 (i.e., plume centerline is more than one sector away from prior location).

In any case, the estimates shall be revised at least hourly for the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the accident unless it is determined that releases of radioactivity have been terminated.

Page 6 of 30 ST. LUCIE PLANT .

'- E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS 8 o INSTRUCTIONS: (continued) 8.6 The Emergency Coordinator or his designee shall track integrated thyroid and whole body dose once each hour for the duration of the event as follows:

S.d. 1 The average thyroid anB whole body Bose rates shell be determined for each sector from the DOSE CALCULATION WORKSHEETS completed for the hour of interest.

8.6.2 Update step 9 of the DOSE CALCULATION WORKSHEETS by adding the thyroid and whole body dose rate determined from 6.A for each applicable sector/distance block to the integrated dose from event initiation to the present for that sector/distance block. /R8 8 '.3 Doses for sector/distance blocks with zero estimated dose rate for the current hour remain unchanged.

8.7 Proiections of doses and dose rates should be made on the basis that the most recently estimated dose rates and their distribution will for two hours. Pro)ecting dose rates for periods othhr than 'ersist two hours should be made on an ad hoc basis using best available data on release rate estimates and subsequent meteorological conditions.

8e8 The results of TOTAL RELEASE RATE, DOSE RATES, and ACCUMULATED DOSE should be compared to applicable Table 3, Page 19 ACTION GUIDELINES. The Emergency Coordinator, if not performing the actual calculations, shall be informed of all dose estimates. The Emergency Coordinator shall evaluate the results and declare a new status as applicable. 'R8 8.9 Dose conversion tables for distances 1 to 12 miles, by 1 mile increments, are attached as Appendix A for calculations of dose at other than 1, 2, 5, and 10 miles.

Page 7 of 30 ST. LUCIEN PL'ANT .

-" "-E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET Al METHOD Al CHEMISTRY GRAB SAMPLE UNIT 1 NOTE: Read Unit 1 CHRRM and compare with ACTION GUIDE 1A, Page 19.

1. Date and Time of Data / /

2. Acquire sample assay data. Enter the gross Noble gas and Iodine-131 Deq concentrations in uCi/cc in the table below.

3. Determine pathway flow. If available, use the Unit 1 effluent monitor channel'hown. Alternatively, use the flow based on exhaust fan status, figured below. Default flows are listed if exhaust fan status is not available.

4. Calculate Release Rates.

FLOW CONVERSION CALCULATED Ci SEC I PATHWAY TYPE uC/cc X SCFM X VALUE NOBLE GAS IODINE I I I P ant No e Gas 4.72 E-4 Vent I Iodine Fuel Noble Gas 4.72 E-4 o ne S o le Gas 4 ~ 72 E-'4 A Iodine ECCS Noble Gas 4.72 E-4

! B o ne Total Total Noble Gas Iodine

5. Compare Noble gas release rate with ACTION GUIDE 2A, Page 19.

6. Take total Noble gas and Iodine release rates, in Ci/sec, to the DOSE CALCULATION WORESHEET; Page 14.

UNIT 1 PATHWAY FLOW DATA Plant Vent,'hannel 01-10 Fuel Building, Channel 04-10 Default 86050 SCFM Default 23800 SCFM Plant Vent by Exhaust Fan Status Fuel Building by Exhaust Fan Status Check fans that are "ON" Check fans that are "ON" 10A 74050 HVE 16A 10350 1 HVE 74050 1 HVE 16B 10350 1 HVE 10B 6A 6000 1

1 HVE 17 5000 1 HVE HVE 6B 6000 1 HVE 15 8450 1

HVE 8A 42000 1

1 HVE 8B 42000 Total Fuel Bldg. (SCFM)

.1 HVE 7A 500 1 HVE 7B 500 ECCS, Default Value is 30000 SCFM Total of "ON" Plant Vent (SCFM) ECCS-A Channel 02-10, 1 HVE 9A 30000 SCF1 ECCS-B Channel 03-10, 1 HVE 9B 30000 SCB

/R1

F Page 8 of 30 ST. LUCIE,PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OPP-SITE DOSE CALCUL'ATIONS RELEASE RATE WORKSHEET A2 METHOD A2 - CHEMISTRY GRAB SAMPLE - UNIT 2

'OTE: Read Unit 2 CHRRM and compare with ACTION GUIDE 1A, Page 19

/ /

Date and Time of Data 2~ Acquire sample assay data. Enter the gross Noble gas and Iodine-131 Deq concentrations in uCi/cc in the table below.

3. Determine pathway flow. If available, use the Unit 2 effluent monitor channel listed below. Alternatively, use the flow based on exhaust fan flow, figured below. Default flows are listed if exhaust fan status is not available.

4. Calculate Release Rates.

I GROSS FLOW CONVERSION CALCULATED Ci SEC I PATHWAY I TYPE uC/cc X SCFM X VALUE NOBLE GAS IODIN I P ant No le Gas 4.72 E-4 Vent Iodine I ECCS 'oble Gas 4.72 E-4-"'

! A o ne I

I B I o e Gas Iodine

'2 E-4

'Total Total Noble Gas Iodine

5. Compare Noble gas release rate with ACTION GUIDE 2A, Page 19.

6. Take total Noble gas and Iodine release rates, in Ci/sec, to the DOSE CALCULATION WQRKSHEET, Page 14.

UNIT 2 PATHWAY PLOW DATA Plant Vent, (Grid 5) Channel 421 or 431 (Redundant Samplers), utilize "PROC FLOW N" (SCFM)

Default 96500 SCFM Plant Vent by Exhaust Pan Status ECCS, no monitored flow rate Check Pans that are "ON" Default Value is 30000 SCFM 2 HVE 10A 84500 ECCS A, 2 HVE 9A 30000 SCFM 2 HVE 10B 84500 ECCS B, 2 HVE 9B 30000 SCFM 2 HVE 6A 6000 2 HVE 6B 6000 2 HVE 8'A 42000 HVE SB 42000 16A 10000 2

2 HVE 2 HVE 16B 10000 2 HVE 17 6000 2 HVE 15 9700 2 HVE 7A 2000 2 HVE 7B 2000 Total of "ON" Fans (SCFM) /RS

Page 9 of 30 ST. LUCIE PL'ANT

. E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISI01 8 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET Bl METHOD Bl - UNIT 1 EFFLUENT MONITOR NOTE- Read Unit 1 CHRRM and compare to ACTION GUIDE 1A, Page 19.

1. Date and Time of Data / /

2. Determine gross Noble gas concentrations via Eberline Control Terminal A or B.

i) Enable keyboard, turn keyswitch on.

Press HIST MIN. 'i) iii) Enter the applicable pathway channel number.

iv) Press ENTER.

v) Enter the next-to-last data point from the lowest non-'alarming range into the table below under monitor data.

3. Determine pathway flow via Eberline Control Terminal A or BE Alternatively use fan status or default figured on RELEASE RATE WORKSHEET Al, METHOD Al. Enter the flow, in SCFM, into the table below.

EBERLINE CONTROL TERMINAL CHANNEL DATA PATIMAY HI RANGE FLOW Plant Vent 0105 0107 0109 0110 ECCS-A 0205 0207 I 0209 02 10 ECCS-B 0305 0307 0309'409 0310 Fuel Bldg. 0405 0407 0410 Steamline A N/A 0501 N/A N/A Steamline B N/A 0502 N/A N/A 4~ Select IODINE FACTOR, use factors shown for pathway for accident type.

Enter in table below.

ACCIDENT APE WASTE FUEL PATHWAY LOCA SGTR MSLB GAP TR HANDLING CASK DROP Plant Vent 0 F 01 1.0 E-6 1.0 4 E-5 N/A N/A ECCS A, B 0.01 N/A N/A N/A N/A N/A Fuel Bldg. N/A N/A N/A N/A 0.0 1.3 Steamline A,B! N/A 1 ~ 0 E-3 N/A N/A N/A N/A

5. Calculate Noble gas and Iodine release rates for each pathway, then add up the, Noble gas and Iodine rates to get total release rates.

MONITOR X FLOW X FLOW 'NOBLE GAS X IODINE IODINE

! PAT1MAY DATA SCFM FACTOR Ci/SEC FACTOR Ci/SEC iPlant Vent I I 472E4 I iECCS-A I I 4.72 E-4 I I I ECCS-B I I 4.72 E-4 I I I

)Fuel Bld ! I I 4.72 E-4 I I iSteamline A 1 I 1.24 E-2 I

/Steamline B I 1 I 1.24E-2 ( I I Totals, Ci/sec Noble Gas Iodine

6. Compare the total Noble gas release rate with ACTION GUIDE 2A, Page 19 '

~ Take the total Noble gas and Iodine release rates, in Ci/sec, to the DOSE CALCULATION WORKSHEET, Page 14. /R8

Page 10 of 30 ST. LUC E PLANT E-PLAN IMPLEMENTING PROCF 3URE 3100033F., REVISION 8 OFF-SITE DOSF. CALCULATIONS RELEASE RATE WORKSHEET B2 METHOD B2 UNIT 2 EFFLUENT MONITOR NOTE: Read Unit 2 CHRRM and compare with ACTION GUIDE 1A, Page 19.

1. Date and Time of Data. / /

2. -Determine gross Noble gas release rate via the General Atomics Console for the applicable pathway.

i) Press GRID 4.

ii) Press the channel number shown in the table below.

iii) Press SEL.

iv) Press TREND 10 MIN.

v) Record the value, shown in upper right corner of CRT, into the table below under data.

3. Select Iodine factor for the pathway based on accident type. Fnter into table below under Iodine Factor.

ACCIDENT TYPE PATHWAY LOCA SGTR MSLB WASTE GAS FUEL HANDLING CASK DROP Plant Vent Fuel Bldg 0.01 1.0 E-6 1.0 4E-5 0. 04 1.3 ECCS-A or B 0.01 N A N A N A N A N A Steamline AorB N/A 1 ~ 0 E-3 N/A N/A N/A N/A 4~ Calculate Noble gas and Iodine release rates for each pathway, then add up the release rates to get total Noble gas and Iodine.

NOBLE GAS IODINE IODINE DATA Z CONVERSION Ci/SEC X FACTOR PATHWAY CHANNEL g Plant Vent 1E-6 Fuel Bld I ECCS A 604 lE-6 l ECCS B 614 1E-6 Steamline 2A Data ~ (CH 631) (CH 633) NET SL2A

)Steamline NET SL A 1.2 E-Steamline 2B Data (CH 632) (CH 633) NET SL2B jSteamline 2B NET SL2B 1 ~ 24 E-2 Totals, Ci/sec Noble Gas Iodine

5. Compare the total Noble gas release rate with ACTION GUIDE 2A, Page 19.

6. Take the total Noble gas and Iodine release rates to the DOSE CALCULATION WORKSHEET, Page 14.

/RS

~ I I~

' I I I ~ ~

~ I

~ 'I4 ~ ~ ~ Ie ~ II ~

~ ~

' ~ I It ~

I' ' ~ ~ I I ~ I

~ I '

I ~ I II ' ~ I ~ I I ~ I ~ I ~ I I I ~ I ~

I II ~ ~ ~ ~ ~ ~ ~ II NM55$

m%%%

5 5 R%8$

R%5$

~ %%5%EEE5555 5885LR55555

~ Ni%$RRUR

~ SLR~I~HR

&SSREa

~ 5555

~ ~ ~ ~ ~

I ~

~ o

~ ~

~ ~ ~ ~ ~ ~ II

Page 12 of 30 STe LUCIE. PLANT

. E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET D METHOD D POST LOCA MONITORS APPLICABLE TO UNIT 1 OR UNIT 2 1~ Read Post LOCA Monitor.

Circle values used:

TOTAL POST LOCA MONITOR NOBLE GAS RELEASE TOTAL IODINE RELEASE RATE (Ci/sec)

READING (mR/hr) RATE (Ci/sec) WITH SAFEGUARDS NO SAFEGUARDS

< 60 NEGLIGIBLE

> 60 to 100 l 2~0 0 03 0.1 I

> 100.to 1000 I 10.0 0.14 0.4 I 1000 40. 0 0. 60 1.6 NOTE: Post LOCA Monitor readings must be verified by HP survey.

2. Compare Post LOCA Monitor readings to ACTION GUIDE 1B, Page 19.

4

3. Take Noble gas and Iodine release rate to the DOSE CALCULATION WORKSHEET, Page 14.

0 Page 13 of 30 ST ~ LUCIE'LANT F.-PLAN IMPLEMFNTING PROCEDIJRE 31'00033E, REVISION 8 OFF-SITE DOSE CALCULATIONS METEOROLOGY WORKSHEET Date and Time of Data: / /

Meteorolo ical Data NOTE: Three methods are offered for use. Method A is preferred to all others and Method B is preferable to Method C. "

)

METHOD A )

Site Meteorology Tower NOTE: Unit 2 Control Room has to contact Unit 1 Control Room for this data.

Wind Speed mph) (Lo~~r Sensor, Upper Sensor ~ Alternate)

Wind Direction )Prom (Lower Sensor, Upper Sensor ~ Alternate)

Delta T F) (Strip Chart Recorder, Digital ~ Alternate)

Prom Table below, convert Delta T to stability class METEOROLOGICAL STABILITY CLASSES STEP 2 I DELTA T RANGES F STABILITY CLASS DEFINITION

< -1.6 Extremel unstable

-1 6 to

~ < -1 ~ 5 B Moderately unstable

-1.5 to < -1.3 Slightl unstable

-1 3 to

~ < -0 ' Neutral

-0.4 to < +1.3 E Sli htl stable

+1.3 to < +3.5 Moderately stable

) +3.5 G Extremely stable Take Stability Class and Wind Speed to the DOSE CALCULATION WORKSHEET, Page 14.

METHOD B )

West Palm Beach Airport NOAA Center Alt Vero Plight Service Station Go to Appendix C, Page 28.

METHOD C )

Default Values DAY NIGHT Wind Speed Stability Class Take Stability Class and Wind Speed to the DOSE CALCULATION WORKSHEET, Page 14.

Page j4 of 30 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033K, REVISION 8 OFF-SITE DOSE CALCULATIONS DOSE CALCULATION WORKSHEET

1. Date and Time of Calculation / /

2. Sum release rates. Enter release rates from the affected Unit(s).

~ Add, if applicable, to get total release rate from site.

I UNIT NOBLE GAS Ci SEC IODINE Ci SEC METHOD j 2

Total Enter totals in Dose Calculation Table below.

3. Fnter from the METEOROLOGY WORKSHEET the, MET Data.

Wind from Speed mph, Stability

4. Enter in the Dose Calculation Table the WB and THY Dose Factor (DF) for the Stability Class and Wind Speed group. The factors are listed on Pages 17 and 18. Dose factors for distances other than 1, 2, 5, and 10 miles are listed in Appendix A.

Check for Sea Breeze effect. If any one of the following conditions do 4

5.

not exist, the Sea Breeze Factor (SBF) is one (1), and go to Step 6.

Conditions:

1. Stability Class A, B, or C.

2. Time of day 6 am to 7 pm.

3. Wind is (from) between 0 and 180 .

4. Air temperature ) surface water temperature.

HISTORICAL MONTHLY AVERAGE SURFACE WATER TEMPERATURES, F JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 69 65 69 73 76 7 80 .81 81 79 7 . 71 Select the appropriate Sea Breeze Factor (SBF) and enter it into Step 6.

STABILITY SEA BREEZE FACTORS CLASS DISTANCE (MILES) 10 A 12 ~ 3 8.8 5.6 3.9 2.3 3~ 5 ' 3.9 C 1 ~ 2 1.6 2.3 3.0

/R8

Page 15 of 30 ST. LUCIE 'PLANT

, E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS DOSE CALCULATION WORKSHEET (continued) 6.A Complete Dose Calculation Table.

WHOLE BODY THYROID RANGE NOBLE GAS IODINE THY MILES CI/SFC (X) DF (X) SBF (~) MREM/HR CI/SEC (X) DF (X) SBF (~) MREM/HR I

2 5

IO 6.B ENTER DOSE RATE RESULTS FOR INDICATED SECTOR & ADJACENT SECTOR ON EACH SIDE:

WIND AFFECTED mRem hr WHOLE BODY (t MILE mRem hr THYROID 9 MILE FROM DIR SECTOR 10 10 168.5-191 ' ALPHA 191 '-213 ' NNE BRAVO 213 '-236.5 NE CHARLIE 236.5-258 ' ENE DELTA 258 '-281.5 ECHO 281 5-303.5 ESE FOXTROT 303.5-326 ' SE GOLF 326. 5-348. 5 SSE HOTEL 8

'- 11 33 '

'1 SSW JULIET KILO 56 '-

33.5- 56.5 78 '

78.5-101 '

WSW MIKE NOVEMBER 101.5-123 ' WNW PAPA 123.5-1 6.5 NW OUEBEC 1 6.5-168 ' NNW ROMEO

7. Compare the WB and THY dose rates with ACTION GUIDE 3A and 3B, respectively, Page 19.

8. Inform the Emergency Coordinator of the data and assist in including this data in the PLANT/RADIOLOGICAL CHECKLIST, EPIP 3100021E, Page 8.

9. On a form similar to Page 16, track the Dose Accumulation for Appropriate Sectors (half hour updates).

10. On a form similar to Page 16, track the Dose Projection for Appropriate Sectors.

/R8

Page 16 of 30 ST. LUCIE. PLANT E-PL'AN IMPLEMENT NG PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS DOSF. CALCULATION WORKSHEET (continued)

This is (check appropriate box) f J A Dose Accumulation Worksheet, Time of Applicability

[ ] A Dose Pro)ection Worksheet, Applicable to DOWNWIND WHOLE BODY mRem 8 MILES THYROID mRem 8 MILES DIRECTION 1 2 5 10 10 N ALPHA

)

NNE BRAVO NE CHARLIE ENE DELTA E ECHO I ESE FOXTROT I SSE GOLF SE HOTEL I S JULIET SSW KILO I SW LIMA WSW MIKE j W NOVEMBER

)

WNW PAPA I NW OUEBEC

)

NNW ROMEO

Page 17 of 30 ST. LUCIE PLANT

-,.- E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS DOSE FACTOR TABLES mRem/hr per Ci/Sec STABILITY CLASS A WIND SPEED GROUPS, MPH

>0 to 2 >2 to to 9 >9 to 18 >18 to 36 MILES WB THY WB THY WB THY WB THY WB 1 1.25 2990 .416 998 ) . 208 499 . 104 250 I .052 125 I I 2 )

.668 1600 .223 534 )

.111 267 .0556 134 I .0278 66.8 )

) 5 ) .360 863 I 120 288 I 0599 144 ) ~ 0300 71.9 I .015 36 l 1O) .360 863 .120 288 )

.0599 144 .03OO .015 STABILITY CLASS B

/

WIND SPEED GROUPS, MPH

>Oto 2 >2 to 4 to 9 >9 to 18 >18 to 36 MILES WB THY WB THY WB THY WB THY i 1) 8.9 21400 )

2.97 7120 I 1 ~ 48 3560 I .742 1780 .371'90 l 2.26 5410 )

.7S2 1800 ) .376 902 )

.188 451 ~ A94 226 l S I .388 932 l 129 311 )

.O6S 155 I .032 77.6 )

.O16 38.8,)

1O .360 ,863 I .120 288 I ~ 059 144 .030 71.4 ) .015 36.0 STABILITY CLASS C WIND SPEED GROUPS, MPH RANGE >0 to 2 >2 to to >9 to 18 >18 to 36 MILE$ WB THY WB THY WB THY WB THY I 1 I 22.5 54100 I 7.51 18000 ) 3.75 9010 1.88 '510 .939 2250 2 I 6. 54 15700 )

2. 18 5240 ) 1. 09 2620 I .545 1310 I 273 654 5 )

1.25 3000 .417 1000 ) .208 500 .104 250 ~ 052 125 I 10 ) .468 1120 ) .156 374 I .078 187 I ~ 039 93.6 ) ~ 020 46 ' I STABILITY CLASS D WIND SPEED GROUPS, MPH

>0 to 2 >2 to to 9 >9 to 18 >18 to 36 MILES TFY WB THY WB THY WB THY l 1 )

46.2 1.1E+5) 15.4 3.7E+4) 9.'14 2.2E+4) 5 '0 1 'E+4) 2.70 6480 I l 2 ) 18 ' 4 'K+4) 6.31 1.5E+4) 3.51 8410 I 1.96 4710 .982 2360

) 5 ) 5 ' 1.3E+4) 1 ~ 83 4400 I 964 2310 l .511 1230 .255 613 1O 2.1 5030 I ~ 70 1680 I ~ 36 863 ) ~ 186 446 ) ~ 093 223 I

Page 18 of 30 ST. LUCIE PLANT.

E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS DOSE FACTOR TALBES mRem/hr per Ci/sec (continued)

STABILITY CLASS E llew WIND SPEED GROUPS, MPH

>0 to 2 >2 to 4 >4 to 9 >9 to 18 >18 to 36 MILES WB THY WB THY WB THY WB , THY WB THY I 1 I 70.6 1.7E+5I 23.5 5 'E+4I 15.9 3 'E+4I 10 ' ' 'E+4l 5.1 1.2E+4I I 2 I 33 ' 7 'E+4I 0 2. 7E+4l 6 '3 1 6E+4l 4.05 9710 I 2.02 4860 I 11. 6 2 ~ 8E+4 I 3.87 9280 I 2 ~ 15 5150 I 1. 18 '840 I ~ 592 1420 I 10 5.07 1.2E+4I 4050 I .897 2150 .475 1140 I .237 570 STABILITY CLASS F WIND SPEED GROUPS, MPH

'ANGE >0 to 2 >2 to to 9 >9 to 18 >18 to 36 MILES WB THY WB THY . WB THY WB THY WB ~ THY I 1 I 125 3E+5 I 42 lE+5 I 31 7 ~ 4E+4 I 19 4.5E+4I 9.5 2.3E+4 I 2 I 64 1 ~ 5E+Sl 5.1E+4I 14.' 'E+4I 8.53 2E+4 4.3 1E+4 I 5 I 25 ' 6E+4 I 8 ' 2E+4 I 5 ' 1 ~ 2E+4I 2.9 '660 3330 10 I 12.1 2.9E+4I 4.0 9670 I 2.2 5300 1. 2 2840 I .60 1420 STABILITY CLASS G WIND SPEED GROUPS, MPH RANGE >Oto 2 >2 to to 9 >9 to 18 >18 to 36 MILES WB THY WB THY WB THY WB THY WB I 1 I 196 4.7E+5I 65.3 l. 6E+5 I 57 1.4E+5 I 31 '

'E+4I 15.4 3.7E+4I I 2 I 111 2.7E+5I 37 8.9E+4I 28 6.7E+4l 17 4 'E+4l 8' 2.0E+4I I 5 I 52 1.3E+5I 17 4 ~ 1E+4 I 11 2 ~ 7E+4 I 6 ' 1.5E+4l 3 ' 7540 10 27.5 6.6E+4I + I 5 ' 1.3E+4 2 ' 6980 I 1 5 3490

Page 19 of 30 ST ~ LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS TABLE 3 ACTION GUIDELINES In-Plant Systems A. Containment High Range Radiation (CHRRM)

INSTANTANEOUS READING EVENT CLASSIFICATION

< 7.3 E + 03 R hr No Emergency Classification

> 7.3 E + 03 R hr Site Area Emergency

> 1.47 E + 05 R hr General Emergency B. Post LOCA Monitors (Backup to CHRRM) Verified by Survey INSTANTANEOUS READING EVENT CLASSIFICATION

< 1000 mR hr No Emergency Classification

> 1000 mR hr General Emergency

2. Release Rates:

A. Noble Gas Releases INSTANTANEOUS READING EVENT CLASSIFICATION

< 0.083 Ci sec No Action Within Tech. Spec. Limits

> 0.083 Ci sec to < 0.83 Ci sec Unusual Event

> 0.83 Ci sec Alert

3. Dose Calculations A. Whole Body Dose Rate at 1 Mile:

INSTANTANEOUS 2 MINUTE HALF HOUR VALUE DURATION DURATION EVENT CLASSIFICATION Not applicable > 500 mRem hr > 50 mRem hr Site Area Emergency

> 1000 mRem hr Not applicable Not applicable General Emergency B. Thyroid Dose Rate at 1 Mile:

MINUTE HALF HOUR DURATION DURATION EVENT CLASSIFICATION Not applicable > 2500 mRem/hr > 250 mRem/hr Site Area Emergency C. Integrated Thyroid Dose at 1 Mile:

l ACCUMULATED DOSE EVENT CLASSIFICATION

> 5000 MREM GENERAL EMERGENCY

0 Page 20 of 30 STf LUCIE PLANT..

A '.E-PLAN IMPLEHENTING PROCEDURE 3100033Et REVISION 8 OFF-SITE DOSE CALCULATIONS APPENDIX A DOSE FACTORS FOR STABILITY CLASS A

'4 w oouY uvoc FCfa 3TttBILI7t'LA>vtt - (ai~cc)/rfa) t cd:.tt tt 1.v Ci/3EC E)ita3GaL~t tatttc

~ ~ 4 I<<\

1lnu f)I'ItlQM - RILE"

(%ri) f I~

A Ce A

Oo 't ~ Oo 74 IVe ll ~ I, ~

A A A A~ A At OVCVI A~ A ~ AP A ~

OVCVI A jot ~ A AP A~

Vl AP ~

G I OVC<<J

~

I A

JIOVC

~ At A~

Vl A ~ AP teel)VC I ~ C%'h)V 04OOC Vl 4ofQC Vl Oo DVCVI Oo Oo deoVC 01 Oe OVC A'lt A ~ ~ P a Deva A~

2. rX+1 1. &<I 1 ~ 2VC 61 I et I ~ CVC A

Vl

~

I~ 'CV'\ II PAP AIIP I IJCV I

~

Ae ~ AA I ~ ~ VC A~

Va

~

Io<<'C A~

Va

~

I ~

AAP

'L'C A~

Vl le<<<<J <<J.

Joliet Atr

' \KC ~ ~ ~

Vl I ~ I I CVI P A~ ttt I ~ JCC +A 54 TJC V2 54 f tC VJ. 5 ~ -cv". 54 JJC VC 54 1tC VC 54 7PCVI. Je tCVL AA uo ttc>>4Ii I

A PAP i<< A AAI At\ A +At A AAP AA OoVVCV'eWCVC A AA AA A AAP AA A AAP AA A AAP A IIIWC V.

7 10 1. v4Ev1 5.5/JEv2 3. ooEv2 Oo WCVC Oe WCVC 34 WCV2 OoWCVC OoWCVC Io-36 A P OC A A <<A Co /OCVJ'.

AA ~ AAt AA I ~ I iK Vl.

fjlt I ~ ijVCVC lA 1 ~ 54vc C42

~ fAI AA I 4 ijvc>>3c

~ PAP AA I ~ IJ4JC Va'.

I fit I ~ ejVC VC f jlP lA I ~ iVC J' CAP IA J444CVL 7noiu uv3E FaJR STttSILI7t'M tt - t'ai/ntt) t co 3EL jot tt a.v ~

I/3EC cNI33IBt FJITc w'Ittu A<< ~ tl At<<<<ert

~ ~ ~

LIVttttttlllu LoakttfOLC nlLCG (t n)

I~ Il ~ 't ~ 5. Oe I~

~

IVI C~

V i A Att O'\

Ct JoVVO I ~ OVEfVG

~ ~ ~ P ~ AA I ~ I actVO Il OIO<<K VC tr AA A ~ At AA A Ar AA OIO<<KML OIDGC VC OoojacV'lt l At AA DIG<<K+V@

A G ~ OGC jtt "' 44 s

tr .AA t at AA ox>>J o DK<<v' Dace'

~ A PAP AA A AAP Ajl A AAP AA A' AA AA AAP 'I J. Jocf02 54QcW<<347CE<2 2eooc~J2 <<o Doc+)2 2toocvL 24oocv2 L I ÃCNC e'. ~ OOC 1

L I 4GGCfVe'. DOC&<<' ~ OOC>J

~ A tetr Atl tl <<P AA f,t.c<<VL

~ ~

LIOICfVL I OJCfVL

~

Aft AA ~ ~I AA I ~ fwc<<VC',etc<<JL

~ ~ ~ ~ AA ~ ~ ~

a,w<<C<<J et I ~ <<C 'J

~ ~ ~ P AA ~

I ~

~ P AA

~cfeJ'of<<C ~ ~ ~ P AA V-I I ~

~ ~ P

<<Cf'JC A ~ act AA I 't<<CW'

~

~et

~

A A IO A feP

<JI A~ <<

~

~ AP,A ~

I I JCfVI

~ ~

I ITC Vl

~

t .A ~ ~ Aj I I JC<<VI

~

A~ <<

I~

~ At A ltcfjJI

~ ~ <<

4 ~

~ Ar A I CeVI

~

' ~ tt

'ZC Vl I'

~

I I'Ce"Ja

~ P A ~

"~

IAP A~

I.C<<'Jl I~

A a ~ C>>'I 4' t t ~ A

't~ ~ OtKfVI A~ A 4P I A A~ A 44 4<< ~ A A A~

I A t ~ 'I t I A I~

I . A Ae A ~ A IO I ~ C JC+eJX Oe DOC<<V1 )I OIJC>>JI Go OIJC<<VI jae OL'0 Vl Ge OVC<<VI ~ GVC<<VI IOVC Va ~ O'J Va ~ GVC J I G~ Gajc<<J

Page 21 of 30 ST LUCIE'L)NT .

E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS APPENDIX A DOSE FACI,'ORS FOR STABILITY CLASS B IVovLc evul a)vec ILA OliaoILII I QJ1303 8 - ii)IaEait IV%) s eiiecu o.n n l ~ v vll ci. caiaeeaaa hnlc iaaiau RQ4)I)au DISTriivc - ilILES P OAOO ~

)

tl 'I ~ I r lVI

~ ~

l ~ Ce eo 5. ~ Oo ~ lao aCI AI il A \

A to V C A AGE+A 2o 2ecW 1. GIEM 5.oeEv"a 3oeec Gl 3o evAEGI A

deeVC

~ AP A ~

Vl A

doOVC AP A ~

Vl A A el OVCVl el OVCVl eteVC

~ 'I

'il A

eteVC Al

'il A~

I tlAP 'I 2-4 A' APP+A IlC 7.52Ecv1 3.35EpGa l orc vl

~ Ioc~E-GI l

~

AAP CVC A~

Vl l

~

tsAP A ~

save Vl

~

l ~

AAI A ~

LVC Vl l

~

AAP Avc il A~ ~

l P'Vcoil

~

l ~

AAI P'VCV I A~

l

~

AA AVVC A~

4 l. 4eciGG 3. 7oE+I l.6ecCVC 5o rrcvc 5o orc vc 5.rrc i2 5.:rc i2 5e rrcvI.

A li li PAP *A AA 9-Io 7. 4u'P01 1 ~ Oec Vi A A~APGA

'ilPAP

~

ICC VC ls ~ I AA Oo C'ICVL 3.GGEv2 A AAP AP et WCVIa et VVCVC el A AAP AA WC' 0~ WC' et WC AA VC P Alt AIS JAP AA 0 AP Ale Ae ~

9.4C&)2 4.1$ Ev2 I.o iRCVI I.o2Ep02 1.5GEp02 1~ AAICVC l oPC~ V' ~ 5VC v2 l ~ 5VC li2 l

~

e SVCVC ittvID uvec Evaa STASILIa I'M 8 - i%%uiPR)i eiaecu i.n A a.v vaieci. Cnaeeavii RriTCE w'Ihu II FEED uvimQI)iD DISTrhm BILES iiii.al) l ~ Co li ee 5. ee I ~ lV ll ~ l'A

~

0 2 2 14Ei04 5 41&03 2 41Ei03 1 30ci00 r ~ Olci02 0 Oee+0' OAKpV2 0 OAKPi02 0 OoK I 0 OiK VC 0 Odcovc 0 00Ci02 A AA \P AA Al\ A Att AP 2-4 7. I cciGS 'l. oviiG3 8. 0%F2 4. 50ci02 3. I IEi02 2. oeci02 -"" ooci02 2. 00Ei02 2. OOEi02 CoNC VC CoNC VC aeeecV'

~ 3o iVcs03 I I PcciG2 4. v2Ei02 2. 270 i02 I . K<i2 I o 44"v2 I 44Ei02 ~ a . 44ci02 I . 4 ci02 l 44ci02

~ a ~ 44Ei02 a . 44ci02 A O~ A i 18 l 70'c&3

~ 4 ~ 51Ei02 2 GIEi02 1~ 1%iG2 s.70Ess01 I ~ lrci0l I ~ irciGi Te a ci01 = ~ I iGIi l llE~IGi

~

A ~ ~,AA ~ P \~ P AtsP A ~ A AI A Al A ~ A A A AP A A AI A~ I A~ A IA A~

AGAEiGAA I o se ~ P LOCiGL A ~

l ~ Vlcsoesf 5e 6CC'sua etsAOCWa ee Ov Va so ee OVCVa 0 ~ esiC+

al ~

ia re OVCVa coo'.IC'ova }IOVCVa I et.

Page 22 of 30 ST. LUCIE IMPLEMENTING PROCEDURE 3100033Et REVISION 8 PLANT'E-PLAN OPF-SITE DOSE CALCULATIONS APPENDIX A DOSE FACTORS POR STABILITY CLASS C ttn0LE o0uY DOoc r0n STADILIIt vtjtSS C - tmcn/mi t BAocu tot A l.v Ci/SEC cttioosvtt ItAtc tl l IQ

~or u0ittQIHD DISTrViCE - BILES wrrdi l ~

A lo Oo 't ~ 5. 6. I~

A Oo

~ A lve ll ~

A llo

~

0-2 2og~+01 6,54E& SoISEA Io87dw" Iocw<4 8.rrE<I oo80EP01 5o74cP01 5o iirVi 4e6oc Jl 4~ lrc vl 3 Icvi eAA A ~ AAo' 2-4 7eSIEt00 2o 18Et00 l 0eEM

~ 0 ~ 24Ep01 4. lIEvl 3.00EpDI ".2Icvi 1 ~ r IEADI I ~ 7lcvl l 5ocvl l

~

~ 'tOC Vl l

~

~ OCCVl<

~1 3o'lrEh4 1~ 0lct00 SolirFIII l ~

A lo A

Oo 5. Oo I~ Oo r ~

~

lVo ll ~ tho 5o4IE+04 IoSTCO I SOEt03

~ 4 41&VS Se00EHS 2 ICE+VS le RC VS I ~ OE+(3 l 24EC+IS

~ I llc VS l ~ VSE VS o '2CE%2 l 't A ~

l ~ 80'o 24EKS 2 e 52Et03 I 50E<3 1~ 00E 03 7o 1 rE<2 5. 44Et02 4 ~ 5 rEI02 4~ 12Et02, 3. 74EPoJ2 S. 4SEm*2 3. b cteJ2

't~ Ar A A rovicvo

~ AA l olc60 A ~ AP A ~ A~ P A I elocute

~ AP AA 7o'trctvl 5 eXcml AA A 0

PAP vrcvlA lI A

'l AP A l lrcvl l V6ctvl A AAP OA A A P AA l 0 I Ct'I o

~ OA

'e ILC l $41CVl

~

P A A A P A~ 'AD AAP A IIE&2 l OVER l I ~ l Sct02 l I l

~

r 10 4o SrlC 0et 1 ~ SlE&3 Oo30Et02 Se 2oSAJCWL ~ ~ ieoctVA2 ~ Vir+02 e erCC V Oov'OC Vl I roc&a

~

lo A A APP AA ColiC VO OoStcdlA

~o l

A

~

~ PP lSCEHl A ~ AAP AA loOIWl ~

~

App,oA A AAp A I lirterl Oorrc&l

~ Aht Oeovchll A tdo pep A ltcooJl ~ i5e IepCV A~ ~ AP h ~

'toOOCOVI

~ AAP A

'tel rc'Ovl~ A~

I C'tvl

Page 23 of 30 ST<<LUCIE PLANT ~

E-PLAN IMPLEMENTING PROCEDURE 3100033K, REVISION 8 OFF-SITE DOSE CALCULATIONS APPENDIX A DOSE FACTORS FOR STABILITY CLASS D tt)lVLE KIJY K% Fvra SIABILIIY G ttoo ae ilfP/)Itt)t SING i4t rt I V>> ~ IISEtt BIISSIQi /tetr C

<<IIIII Im)<<ir)I)iD Glott't)rX - BILES i>>rH)

A A t

+

ta Co Oo Oo I ~ Oo 1~

~

IV>> II ~

~

IC>>

Oc 4a 6CCIO1 Isa&I I ~ IOEVI 7>> 46EVO 5>> 50' ~ Cl dW Ss 45CVO 2>> OTHOV 2>> 4SEVO 2>> IVER< V I ~ I 6EVO'

~ AP OAP hh hh AA AP 6 o >>a I Ev0 AA c>>4rcM AA I s <<CCVV I I CP

~ ~ ~ h~ ~ A ~

~

I ~ 54coO 1 Oo OOCVV 1 ~ OaaCVV ~ alCVV 1>>55C Vl Oe IVC Jl O>>11C Vl 0>> IIC Vl 5>>OOC

~ A 1~ 14cK4 S.51&% i. 11' AAP AA I ~ >>ICCW>>V 1 ~ 04c Ol 7>>44C Ol 5>>1OC Jl 'I~ ~ At<<

r'ICVI h~ ~ ~ AP h ~

'to IOC Vl root'C JI hP h A

~

et h I I/O Vl

~ ~

0>> VCC Vl At tAt r-io 5.40'.96EKQ I ~ VOChl0 7>>O~rc vl 5. I1Ep01 S. r IEpOI Oo ICC Ol 2.57EP01 A

a' l lttCVI

~ h ~ ~ A ~ ~

I ~ OOC Vl I oac Vl I 5OCV I

~

h~

~

h<IOC Jp aeePgD IOAP PO<<hr@ILIP t ~atv 0 tgP>>ga) ~PAP<<<<ti ~

I h Ae>>APA P >>>AA>>ha <<Pe

'<<Iitl/

lt'CCIr

~

\g <<I<<A~a~ gts PA errril A A Cs Os 5. Oe I~ 1~ IV>> II

~ ~

~

IC>>

V h A 1 ~ I Iv&5 4>> WV<<2>> &/4 I ~ 7 1cV4 i occA I e e vocoder os cccvo 0>> ooww 5>> oatc~w Jo vocvo ~ ~

'to rCWJ hA ~

A~

AAP hA Astctv)

A ~

So IOE'hA 1~ 5IC~ Oo OCEKO 5>> 17EVat 4 ~ 'tVCHS ate 4CCHS 2>> I OCVS 2>> Crc+04 I ~ t 'tCVO I e OOCVS I ~ <<OCTO

~

~ ~~

I 't lcivaa

~~t hh PAP hA h >>AP IA A Ae ~, tl<< At P ht\ >>AP hh AA ahP AA l t iAP ho A t l A

Ce 1 Coopt Oo

~

<< I Eovet

~

4>> I I CVO lao Ioctvd Ce eaICV>>t

~

I ~ I tE>>'/lt

~

I ~ 't<<CVO

~

I ~ 1 ruat ~

I o VVCWO Os OaacoVC t ahVCVC

~ I ~ 'aC>/

AAP ho 'e>>P AA t\ tll hh 'Ah hA Aht AA P APP AA AP htl P htl <<Ah AA h A 'lh A 1 lo I aeVCov4

~

W IlctOO C>>OVB'lO I ~ /VCR I CAVO

~ ~ ~

~

~ ~ O.CVC I ~ e/OCPJC

~

0>>

~

IIC VC a/e V WC

~

<<o

~

>>C } 1CCt'VC I I<< t JC

~

At hA h At ~ AA Aht hhl A <<aI h<< AP hA s Ah AA A tP hA h hh<<.h<<Ac. Ore >>hP hA A PP tA

i. Areci.AAc V' th ze~r> o. m~vc o. Iocivc <<. I vcsc o. I.c~/c
~
~ 0 ro Oe <<Ocovr Ce aeOCVet a.
~ ~
o. Vtc~v /c ~ Jc~e/ I ~ Ql
'I Page 24 of 30 STo LUCIE PLANT IMPLEMENTING PROCEDURE 3100033Er '-PLAN REVISION 8 OFF-SITE DOSE CALCULATIONS APPENDIX A DOSE PACTORS FOR STABILITY CLASS E wM SGui uvoc FGn STASILII F vtjtSS E - FeE))JItt) t SAocu ~Xi A 1.0 CII'SEC c)i'xKAI 'll Iv'tlcE KitntiIQ uISTthvc - ifILES A
io A
Oo 'to 5. Oo I~ Oe o~ lVe ll ~ lieA hh At AA h IA oeP hh ~ h hh 0 7.0bE<f 3.31&01 2. fOE<f 1.5IE<f l. foe+01 r.35Et00 I I Oc'tvv
~
~
0 ~ tMCtVV 5e I Octvv A~ VICtvv
~ ~
'toIJtctvv 'toVO ~.AJI P AA AA tl A Oht Ah 2-4 2osroIc<f le fGERf os rrc 00, 5e 02cE~ oo 87EM 3o iC is IIICttIV hoilC W
~ ~
1 ~ riC~JV
~
1 ~ orc~JV 1 ~ INIC eJV i.o c JG.
4 9 1.5rEKI o.73EC~ 4.GIEMr 2.84'. 1%M 1.71E~ ~
1~ 't~ eP 1ctvv AA 1~
eA lrc w h ~ htP hh 1oviC'tVV A A P Oe rIC 'Jl t ~
I rOCV1
~
P he 9-i8 1. 0ic+Oi 4. G5c+00 2. 35'.5r Et00 1. 1 SEM r.SGEpGI 7. 59E~)I O.SoEp01 5. 45Ep01
'I.
4. I ~c J 1 4. 1 9' 3. 74c 'Ji lo 36 5e IGE+00 2oOictGO 1~ I/Vw 7o97E Gf 5o ric vl 4eolc vf Se I rc Ol >I loc vl i ~ ~ Itc vl 'ISIc vl 2e IGc IJf 1 ~ SI T)ttnOID uOOC FGR STASILITY CLASS E - (%9/M) t SAN@ Qi tt l.v vlIocv ct)lorlvtt ntttc oil)tu SFEED CQtittilitu DISTt't'tvE - ))ILES (t~r) ~ ~ A to ~
+ io 3o 'to 5. Oe I~ O~ r ~ lVs 11 ~ the 0-2 1.7GEt05 7,9mt04 5.03Et04 S.oft@ 2.7m&4 2.24E~ 'l.oIc "J4 1.5rcm4 i Soc'v4
~ i.chi J4 l.voc v4 r.i.ctv3 4 5o O~C t04 2e O5C+04 1 ~ Coct04 1 ~ 2VAEteJ4 r ioc+03
~ 7o 4OCt03 0~ '%43 5e 31EtGS 4eolc vS 'e ~ GSE+GS So OlEt JS Se iKtoJO A AOP At h 'P ~IA ht hh AAP hh A AP O&t AA A ~ hh ' tIC~JO tIA A ~ P AA Pt hh
~
Oic~ ~ ~ ~ ~
rlc'tVO
~
~
dsolc& I lc~rls
~
9 1 ~ 9e IOE OO O ~ Ohctvo 5o 1+4 VO to 1VCtvlt OoOOC VO ~ JO is'IOC ~ O 1 ~ 1 ~
loA io'IetPlcoePt A h~ A I ~ ItchA oo ~ ~
5 NX%O AP hA A AAP O OOC'tVAo IA A A~~
ioOlCtv)h tl i isa'tVO A AAP AA ~
1 AAP AA Oictvo
~
1 P P AA ACI JO 1~
As ~
OIVVIr AA 1 ~
~
o'tc Vo AA ~
1 ~
h VlC VO A A A O ~
~ AA Ct Ji I o~ hA PAP hh o hA P AA 1
AAP, eQC 04
~ ~ AsP
'toOOCtGO A A Ae ~,IIA isolC Vlt 1~
Ae ~,AA I tc+JO ~
1 otictv
~ AP hA ~ AP AA le iiC VO A
I ~
hl 1VC hei Vi I sKoP V hA Oo etC Ji Qe I'JC Vi 5o otOC AA Vo
~ ~
s Page 25 of 30 STe LUCIE'LANT ~
" '-PLAN IMPLEMENTING PROCEDURE 3100033EI REVISION 8 OFF-SITE DOSE CALCULATIONS APPENDIX A DOSE FACTORS FOR STABILITY CLASS F l
o=
a r
'ItnvLE"qquY-uvoc.Fvn" oittoiLIT'I LLnoo F.
- I~i'rp oft IIII lt I I'/ I"llKCc~fISSI".r" IIIITE II'inu DWEEB
- CQHli'IS: uISTI't}tot= HILES ~'"-"-
~ ~ s
~ A los A AAP hh 0 2 1~ 'js/Et02 6oOOCr0}'eMW} So@VCR} ' 54C10}s, Cev<c+0} le/Otru} I otrtr0}"'es7ocrv} lo2 C. Vl l VrcrSI} , ~ Orc~rV
~ Oh A Aha hh A S 4 }SE+01 P 2o l'~chtl-~is 4SCE<}--"1 e v7Er'0}:Oe 46E<st/- o. roErILsSe rear'Ihrv -5. IOC~4 -r'52Env r ~ e/aSSE'srt-~a OSEr've'I 'XPVV
'r lr hh 4-r 3 art<1 1~ 4}E 0}. oeorcr00 ~*." 4e SSrEchpy.. 4s 0VE~ Se Ssicr00. 2eo/ rIV 2o SVE~/0 2s2}E, VV h I ~ 7+C 'r/v s
~
I ~ I 7t&V l
a a" AP h~
9-}S }.OrEt0} LSOCW 5.2}E+00 P3'65EK6 2. r OE+00 Cesar;=}.OOCr'00-" }.56E~W I ~ s7s/C+/V 1 ~ } rcr0V l ~ vCC+Jv ~
~
rrc VI C
18-So 7~ 46Er'00 4o 26Er'00 2a 6VEr'00 la OS' 1 sorer'00 1 eErw r. bcp01 7. 7 ecp0I 6.74E<} So rocvl Sococ~/I re IA vl IIIIRID uvoc Fvn STltoILITI VLnoo F - lincH/tni ~ ottocu vt} tt l.v triicctr ci}iooiLri /VITE
~ lA Ii liiu ~
ol ccu (iinnl l ~ Ce alp 5. Oa I ~ Oe 7~
~ h lVe ll ~ I' h ri V C A PAP h 5
e QAP+h 1o vSEcrvAS = 7.67' AAP h 5 Vs7trV4 o ~ reh/C AAP h ~ Ir A O hP h Ivcrvr ~ h rtr h Autre'.'r
~
l 7VtrVr A har
~
h ~
~ ~
Olcrv
~ h Cs A
Oi c~/r h~ A P AA A hA Aa
r. r6cr'Irr'. }vEr'04 A ~ ~
2-4 a APE 2.56E+04 2 o Ooocrvr 1.6OCW }.42cE~ i. M+v4 I. vM~~ 7 e 0/CrVO 0~ I ItrVo / ~ I C~IO OP AA h OP rap aA Vt:CrvJ'al hh hA hh ~ hc h 4-7 I . rlc
~ AP h ~
rvr A AAP h ~ Oe OOCrur
~
2e }SCE+04 1 ~ Soc 0r le'1 rt 04 A 7 ~ OICrVO O Vrtrvoo O OCCro/O Oo de 4I.'CrVP re ostoV 7
~
hh hSP hah hA A Aerr AA 7-13 4. BE+04 }.2%M A APP+hh Oa I /C Vst Oo OocrVO hh 5 e Pic,rvo
~ AP hh 'I~ ~ rVCrvr ~ A P ~~
Oe I CrVO rcr .\wA
~
I, OrC V' ~ O P hA seCC Voo A hei h P hh A PAP ah A% AA AA ~ hl s rl A>> A l ~ hr I.. I VtrVO i
~ ~
2.2) EK4 l ~ v2cEr04 6 o 25CEf03 A+A L o COcrvos o Oi C~I) ~~ Olc VO I ~ ro,trVO ~ ~ pe crVI I C V
Page 26 of 30 ST+ LUCIE'PLANT ~
'-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OPP-SITE DOSE CALCULATIONS APPENDIX A DOSE PACTORS FOR STABILITY CLASS G t<<A <<<<Alt Ah>> <<0 Afshel ttht << lAh A - Irincriinnil trhrht t th tt ~ Ahtt htl h A~ thhh Aht ~ Atrr As>> ~
linus 000i kec rvn oitt8icaii virtoo u
~ ~ ~
ottocu 0n tt a.v
~
va/>>i cna)oat.tl cnic IIIIIII yEEB 6$ i%UIID DISTAt4X - BILE I FIIJ A r l ~ A js ot 5. Os I~ Ce
~ A aVs al ~ lIA ~ ~
A<<A js fl A A AAA he h A At roc>
~ ~ hldira l ~ ~ ~ AA h ~
ltac'tva
~ her't I ~ vlc>va A
r t~Kwv a Ah A A A Os OOCVV
~
I ~ or
<< 'lh ~ Att hh tehact'.Ar ~
2.8IEHI 1.8icvi i.oreV0 S. 73>>EVO S. 2I CV0 2. r 'I c Vit 2. 62EVV 2. 3 I cnÃ
~
lo A At sao 1 ~ 54' <<cW 5. 4I cQ 4e 0IE4 3e 14EV0 2e 5I Nl 2e I Ic+~r0 I ~ 8:dw I ~ 64E 'iY' ~ 4~K>w I ~ SIC+A 1 ~ l rc>A< Tnlnvlo uvoc Fvn STI'IIIILII ( CiM 0 " II~K/nn) I 8tthcu vn tt i.v I I/>>t". CnISSIiII Ivttc tt I ltITil St'cED 'aaretntitIO uISTnn7E - tiliES (nt nl r l ~ I. ~ 't ~ 5. Oe I ~ Oe
\A av ~ il ~ ~ ~ ah ~
0-2 4. 70E+05 2. o7E+05 i. r 1&05 i. 5IKm5 i. 24Ew5 l.vÃw5 9e 1I cd 8. i21 ~>4 7.. I cav4 n. 5rcv4 o. v2Em4 2-4 I e5ic<5 8. OrEW o.one*'.0IEhVe 4. aSEv4 3e 51&Pt St06Ev4 2 ~ 7lchII4 2.42Ev" " 0E~v4 '. vlEv4 i. 0 Kv4 4-9 1.Xc<5 o.74Et> 4.4%+v4 3.34E& 2.66Ev4 2.2vEm i.otciI4 a.63c~r4 i.~<<I4 a..ww4 i.ieEw4 h A ~ rA hA cht ~ I VC AA 9-18 I ~ earckl4 3s roc~ ce 6&rt I rstcM e I ~ 5ic+l4 I ~ ~hocv4 le V4cv4 oe 9nc&3 ~ shNKvd 0 ~ rocvo
~
0 ~ OCVO h Ic A A rA hr lo 30 3.ore<4 I.rrE~04 1.3IE~r4 r.o>>+v3 7.54BPs o.iicmS 5l2vEwS 4.4ncv3 >sr:c~a oe~SE~vo h~ a'tcVhh at O KVh
Page 27 of 30 ST. LUCIE PLANT IMPLEMENTING FROCEDURE 3100033E, REVISION 8
'-'LAN OFF-SITE DOSE CALCULATIONS THIS PAGE INTENTIONALLY LEFT BLANK
4 Page 28 of 30 ST ~ LUCIE PLANT'-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS APPENDIX B BACKUP METEOROLOGY WORKSHEET In the event data is unavailable from the meteorological "strip chart recorder, use the following procedure: A. Gather Data
1. Date: Time e

2. Phone the West Palm Beach Airport NOAA Center at 64-305'-684-3633 or (alternate) Vero Flight Service Station (Stuart f) 287-8021. /R8

3. Copy current weather:
Time of observation: Eastern (Standard) (Daylight) Wind Direction.'ind Degrees Speed: Knots Sky Condition: Clear or Scattered Broken Overcast *
If broken or overcast, copy ceiling height: ft.
4. If daytime (1 hour after sunrise to 1 hour before sunset) go to Section C (next page) ~
B. Nightime Calculations
1. Determine Solar Radiation Characteristics:
Sk Condition I OVERCAST I )I
~Cei 1 in < 7 000 I ~es )I Radiation NIL I BROKEN I WEAK LOSS I GLAR OR SCATTERED ) STRONG LOSS I
2. Choose Stability Category (D through G)
Solar Wind Speed (knots) Radiation 01 2,3 4 5 6 7 8,9 10 11 )11 Nil D D D D D D D D D Weak Loss F F E ~ E D D D D Strong Loss G F F E E E D D
3. Go to Section D.
I Page 29 of 30 P ST ~ LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 8 OFF-SITE DOSE CALCULATIONS APPENDIX B BACKUP METEOROLOGY WORKSHEET C. Daytime Calculations:
1. Determine solar altitude (angle of sun above horizon) using Graph C-l.

2. Determine Solar Radiation Characteristics: (Nil, Weak, Slight, Moderate or Strong).
SOLAR ALTITUDE Sky Condi tion Ceiling Ft. I < 15 15 < 35 35 60 > 60
< 7000 NIL NIL NIL 7K to 16K Weak Weak Slight >16000 Weak Weak Slight Moderate < 7000 Weak Weak Weak Slight "Broken" 7K to 16K Weak Weak Slight Moderate > 16000 I Weak Slight Moderate Strong I
"Clear or Scattered" N/A Weak Slight Moderate Strong
3. Choose Stability Category (A through D)
Solar Wind Speed (knots) Radiation 0,1 2,3 4 5 6 7 8,9 10 ll >11 Strong A A A B. B B C .C C Moderate A B B B B C C C D SliRht B B C C C C D D D Weak C C D D D D D D D Nil D D D D D D D D D D. Input to Dose Calculation System Take information to the DOSE CALCULATION WORKSHEET, Page 14.
1. Wind Direction (from Step A.3) degrees

2. Wind Speed 1.15 x (knots) mph

3. Atmospheric Stability (Circle One):
(From Step B.2 or C.3) A B C D E F G
ADRISrED FOR DAValaitr SOLAR ALTITUDEBY TIME OF DAY CORREClED EOII ST. LUCIE PLANT N AVIIIO rIME wolANT I WVICII T JNC ALT ~I Sl tltI40C 0 OCIOOSO IRIS IWl0 r LOIIQITIJOE COCCI TOO 0
<16 16'-36'~
10 10 36'0' I Tt 11 (h M g 12 i2 aw i ',I o rnnop+o I
'I I
I WWM a
'i.
sP nQ 40 I 2 I i I I Pfl M CO 35'- 40' M O CO 16'~ ~ 3 64 I I IO I!~,"I sAMW ni52I25 OlnIAkT 0 5 tOtS IIAncII I ZITIk .. IO I 20th S 5 202 Illf
', OIIheu 0 5202 AIIC 0 IS 2025 AAT C~lt Ugl. ILEhb T1HEI 0 I 20 25 NJQUSI 5 0 202 SIJII40III IO 20 25 oc I oLo 0 OI$ 102$
Hovl 4ul 0 I 5 1015 202$ Io cl Qol 0 O m
Page 1 of 13 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN DiPLEMENTING PROCEDURE 83100026E, REV. 9
1.0 TITLE
CRITERIA FOR AND CONDUCT OF EVACUATIONS
2.0 APPROVAL
Reviewed by Facility Review Group Jul 25, 1975 Approved by K. N. Harris Revision Approved by 5
'e iewe by Fac ity Review Group March 20 V.P. Pwr. Res. & 25 l~
19~8 Revision 6 R ed b Faci Review Group a 2. 8 19 8 l Approved by V.P. Pwr. Res. z 19&~ Revision 7 Rev ~ d by Facil 1 Review Group Z 1982. Approved by 1982. Revision 9 Revie 'y Faciiit Review Group. 5~Pl- 8 1982. Approved by .P., Nucl. Energy
3.0 SCOPE
3.1 ~Per ese This procedure provides criteria for determining if evacuation of a local area on-site or the Owner Controlled Area should be carried out. It provides instructions for effecting an ordered, rapid and safe evacuation of a local area or the Owner Controlled Area in order to prevent or minimize radiation exposure to personnel. It also provides instructions for personnel account-ability. 3.2 Discussion 3.2.1 Accurate classification of emergencies that may occur at the Plant is necessary to enable the Nuclear Plant Supervisor to take the proper corrective action and to know when to initiate the Emergency Plans. For those emergencies involving high radiation and/or the release of radioactive material to the environment, it is necessary to provide the Nuclear Plant Supervisor (Emergency Coordinator) with guidelines that will enable him to know when to order a local area evacuation or"evacuation of the Owner Controlled Area.
Page 2 of 13 FLORIDA POWER & LIGHT COMPANY'MERGENCY PLAN IMPLEMENTING PROCEDURE
//3100026E, REV. 9
3.0 SCOPE
Continued 3.2 Discussion Continued 3.2.2 'A local area evacuation or evacuation of the Owner Controlled Area may be necessitated by the occurrence /R9 of any of several events where evacuation of personnel would be necessary to minimize their exposure to radiation. An Owner Controlled Area evacuation will be conducted for any Site Area Emergency or General Emergency. This procedure implements the St. Lucie Plant Radiological /R9 Emergency Plan.
3.4 Definitions
The location to which evacuation personnel report. In a local evacuation, personnel evacuate and assemble in a location designated by the Emergency Coordinator. In an evacuation of the Owner Controlled Area, evacuating FPL personnel from the Protected Area go to the Site Assembly Station on Highway A1A near the north entrance to plant property, while non-FPL personnel and FPL personnel from outside the Protected Area assemble at Jaycee Public Park on Highway AlA, 7< miles north of the plant. If necessary, other assembly areas can be specified by the Emergency Coordinator. /R9 3.4.2 Escort An individual specifically assigned to accompany other persons who are required by the Security Plan or Health Physics Manual to be escorted. 3.4.3 Local Area Evacuation An evacuation of some portion of, but not all of, the Owner Controlled Area. It may include evacuation of a room, building, group of buildings, generating station area, or other portion of the Owner Controlled Area. I
Page S ol FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN DPLE>KNTING PROCEDURE
//3100026E, REV. 9
3. 0 SCOPE: Continued)
3.4 Definitions
Continued) 3.4.4 Owner Controlled Area That portion of FPL property surrounding and including the plant which is subject to limited access and control as deemed appropriate by FPL (indicated by the line on the attached Florida Power & Light property plan, Figure 1 of this procedure). 3.4.5 Owner Controlled Area Evacuation The evacuation from the Owner Controlled Area of all personnel except those required to place the plant in a safe condition, the emergency teams, and the guards necessary to fulfill their evacuation responsibilities. 3.4.6 Radiation Control Point Located in the Auxiliary Building, it is likely to be used as an assembly area during a local evacuation.
4.0 Precautions
4.1 Every effort shall be made to minimize personnel exposure to radiation. 4.2 Personnel who have been in the area of the emergency shall remain in a group, and shall not mix with the other personnel in the Radiation Control Point or other assembly area until they have been monitored for possible contamination, unless they are injured. Injured personnel shall be treated as discussed in E-Plan Imple-menting Procedure 3100021E, Duties of the Emergency Coordinator. 4.3 Except as discussed in 4.2 above, personnel reporting to the Radiation Control Point or other assembly area shall group according to departments in order to facilitate personnel accountability and monitoring. 4.4 When reporting to the assembly area, take the most direct route possible, but do not use any route or area that has been declared part of the emergency area, or that could result in excessive individual exposure or injury. 4.5 If an area or building is evacuated, any records regarding the persons in the area shall be removed and taken to the assembly area.
Page 4 ot 13 FLORIDA POWER 6 LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
//3100026E, REV. 9
4.0 Precautions
(Continued) 4.6 Health Physics personnel exiting the RAB as necessitated by an emergency condition of possible radiological nature shall pick up suitable portable radiation monitoring equipment which would be required for re-entry monitoring. 5.0 Res onsibilities: 5.1 The Nuclear Plant Supervisor is responsible for: 5.1.1 Classifying and declaring any emergency that may occur at /R9 the site+". 5.1.2 Initiating the Emergency Plans when appropriate. 5.1.3 Initiating the evacuation of any area in which the criteria for evacuation, as expressed in steps 8.1 8.2 are met. /R9 5.2 The Nuclear Plant Supervisor shall act as Emergency Coordinator after declaration of an emergency. /R9 5.3 The Emergency Coordinator is responsible for advising the Security Team Leader of a local evacuation or an Owner Controlled Area evacuation. This notification will be by the alarm or the PA system. Information needed the Security Force to properly fulfilltheir responsibilities by during the evacuation shall be provided to the Security Team Leader by the Emergency Coordinator. (See E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator). 5.4 The Security Guard Force is under the supervision of the Plant Security Supervisor. He serves as the Primary Security Team. Leader. The Security Force Shift Supervisor is the Interim Security Team Leader. 5.5 The responsibilities of individuals acting as escorts are contained in Sections 5.12 and 8.4;5 of this procedure. 5.6 All personnel permanently or temporarily assigned to St. Lucie plant shall familiarize themselves with: 5.6.1'he instructions given in this procedure. 5.6.2 The access routes to the work location to which they are assigned.
The statement applies to Unit 2 upon initial fuel load.
~ H ~ Page 5 ot 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
//3100026E, REV. 9 5.0 Res onsibilities:
5.6 (Continued) 5.6.3 The locations of the evacuation assembly areas:
a. The Radiation Control Point in the Auxiliary Building.

b. The Site Assembly Station.

c. The Jaycee Public Park on Route AlA, north of the plant site. /R9 5.7 It shall be the responsibility of each supervisor and depart-ment foreman not involved in the emergency response to report to the assembly area to assist in accounting for all personnel under his supervision.
5.8 Security Department Responsibilities are defined in Security Procedure 0006123. 5.9 The Control Point Guard shall maintain accurate records of all personnel entering or leaving the controlled area and make the records available when required. 5.10 The Main Gate Guard shall maintain accurate records of ~ personnel entering or leaving the protected area an/ /R9 make the records available when required. 5.11 The Assembly Area Supervisor shall be responsible to ensure that personnel accounting at assembly area is being done and liason between the assembly area and the Emergency Coordinator. /R9 5.12 Tour Guides are assigned to escort groups of visitors during tours of the plant site. In an emergency, Tour Guides are responsible for personnel accountability of their respective groups and the evacuation of their group to the Site Assembly Station in cooperation with the Security Force. F 13 Prior to fuel loading, Unit 2 responsibilities are defined in ASP, 5.0.
Page 6 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
!/3100026E, REV. 9 6.0
References:
6.1 St. Lucie Plant Radiological Emergency Plan. 6.2 St. Lucie Plant Security Plan. 6.3 E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator. 6.4 HP207 Personnel Monitoring following an Evacuation. 6.5 HP208 Personnel Decontamination. 7.0 Records and Notifications: 7.1 A list of all persons assembled at Jaycee Public Park shall /R9 be prepared by a member of the Plant Staff who will travel to that location with evacuees. 7.2 Records showing that all personnel in the area affected by the emergency were accounted for shall be kept as part of the records of the emergency and recorded by the Emergency Coordinator.
I t ~ Page 7 of 13 FLORIDA POWER 6 LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE f/3100026E, REV. 9
8. 0 Ins true tions:
8.1 Criteria for Local Area Evacuation If an incident involves a high radiation field or has caused the release of radioactive material to the environ-ment, the need to evacuate the affected area shall be determined in accordance with the following criteria: Evacuate the affected local area in which any of the following conditions occur: 8.1.1 Area Radiation Monitor Alarm. 8.1.2 Containment Evacuation Alarm. 8.1.3 Direct radiation dose rate reading,d.n..excess of 100mRem/hour, from an.unevaluated source.
-9 8.1.4 Airborne radioactivity concentration in excess of 1 x 10 ~ micro Ci/cc, from an unevaluated source. /R9 8.1.5 Removable radioactive surface contamination in an unposted area in excess of 1000 dpm/100 cm beta-gamma over an area of 100 ft 8.1.6 Removable radioactive surface contamination in an unposted area in excess of 50 dpm/100cm alpha over an area of 100 ft2.
8.1.7 The Emergency Coordinator determines that a situation exists for which local evacuation is appropriate. 8.2 Criteria for Owner Controlled Area Evacuation The Owner Controlled Area shall be evacuated in the following circumstances: 8 '.1 Site Area Emergency, 8.2.2 General Emergency, 8.2.3 If the Emergency Coordinator determines that the entire owner controlled area should be evacuated. /R9
~ f ~ Page 8 of 13 FLORIDA POWER 6 LIGHT COMi ANY EtiERGENCY PLAN DiPLEMENTING PROCEDURE
//3100026E, REV. 9
8.0 Instructions
(Continued) 8.3 Evacuation Pre aredness 8.3.1 All visitors shall have adequate transportation available on-site to evacuate all members of their respective groups. 8.3.2 Escorts shall maintain control of groups or individuals to which they are assigned to enable all members of the groups to be located, notified and evacuated. 8.4 Local Area Evacuation Im lementation 8.4.1 When the Emergency Coordinator (Nuclear Plant Supervisor) determines that a local area evacuation is necessary, he shall, in following Emergency Procedure Duties of the Emergency /R9 Coordinator, announce an evacuation using the PA system, giving the area affected, the assembly area and other instructions as required. 8.4.2 All personnel in the evacuated area shall stop work, turn off potentially hazardous equipment, such as cutting torches, and leave the area by the same route taken to enter the area, unless otherwise instructed by the Emergency Coordinator. 8.4.3 All personnel in the evacuated area shall report to the Radiation Control Point in the Auxiliary Building for monitoring and accountability, unless otherwise directed
'y the Emergency Coordinator.
8.4.4 The Radiation Team shall monitor evacuated /R9 personnel for contamination, (for areas where contamination may be present). 8.4.5 Injured personnel shall be treated as discussed in E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator. If an injured person is evacuated from the plant site, the person's TLD, selfreading dosimeter, identification badge, and keycard should be removed and given to the First Aid and Personnel Decontamination Team Leader. 8.4.6 The Control Point Guard shall make available to the Emergency Coordinator his records showing the personnel who are in the Radiation Controlled Area. /R9
Page 9 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
//3100026E, REV. 9 8.0 Instructions (Continued) 8.4 Local Area Evacuation Im lementation (Continued) 8.4.7 The Emergency Coordinator, department supervisors and foremen having personnel working in the evacuated area shall verify that all personnel in the evacuated area are accounted for.
8.4.8 The Emergency Coordinator shall initiate a search for the personnel who have not been accounted for. 8.5 Owner Controlled Area Evacuation Im lementation 8.5.1 When the Emergency Coordinator (Nuclear Plant Supervisor) determines that an evacuation of the Owner Controlled Area is necessary, he will order an evacuation using the PA system and the evacuation alarm as described in E-Plan Implementating Procedure 3100021E, Duties of Emergency Coordinator. 8.5.2 All personnel in the evacuated area shall stop work, turn off potentially hazardous equipment, such as cutting torches, and leave the area. All personnel not needed to place the affected unit*in a safe con-dition and not on an emergency team or otherwise required on site, shall evacuate to the appropriate Offsite Assembly Area. Emergency Teams shall report to the OSC for assignment. 8.5.3 Injured personnel shall be treated as discussed in E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator. If an injured person is evacuated from the plant site, the person's TLD, self-reading dosimeter, identification badge, and keycard should be removed and given to the First Aid and Personnel Decontamination Team Leader. 8.5.4 Personnel shall remove protective clothing prior to leaving the Radiation Controlled Area. 8.5.5 Personnel shall proceed to the Main Guard Station by the most direct route, unless an alternate route is specified by the Emergency Coordinator. 8.5.6 Each person shall then proceed to the appropriate Site Assembly Area (see Figure 2), unless otherwise directed by the Emergency Coordinator.
Applicable upon initial fuel load of Unit 2.
R9
~ W ~ Page 10 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE f/3100026E, REV.
8.0 Instructions
(Continued) 8.5 (Continued) 8.5.7 Assemble by department for accounting and monitoring, and remain at the assembly area until given instruc-tions by the Assembly Area Supervisor. 8.5.8 If the conditions associated with the emergency are such that the site assembly station area is untenable, the Emergency Coordinator shall direct all personnel to report to the Jaycee R9 Public Park or other suitable alternative and specify the route to be followed. 8.5.9 The department supervisors and foremen shall account for their personnel and report the results to the Assembly Area Supervisor. 8.5.10 The Assembly Area Supervisor shall assure that all personnel are monitored for contamination prior to leaving the Assembly Area. 8.5.11 The Assembly Area Supervisor, the Security Force Shift Supervisor and the department supervisors and foreman shall examine all the personnel records available to determine if any personnel are unaccounted for. 8.5.12 The Emergency Coordinator shall initiate a search for the personnel who have not been accounted for. 8.6 Securit Force Evacuation Im lementation 8.6.1 Upon notification of an evacuation, the Security Force Shift Supervisor (Interim Security Team Leader) shall advise by radio all other guards on duty that an evacuation is in progress. The Security Force will proceed with the evacuation of persons and with personnel accountability activities. 8.6.2 The Control Point Guard and the Main Gate Guard shall immediately review logs and badge records to determine what persons are in the affected area. These guards shall R9 be prepared to brief the Emergency Coordinator. The Control Point Guard shall verify that all personnel have evacuated the area and report to the Security Team Leader for further instructions. The Control Point Guard shall then R9
Page ll of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE f/3100026E, REV. 9
8.0 Instructions
Continued 8.6 (Continued) 8.6.2 go to the Hain Gate with his personnel records and await instructions from the Security Team Leader. 8.6.3 The Security Team shall: 1~ Sweep the plant site to verify that all personnel have evacuated.
2. Notify any Special Guards on duty.

3. Perform additional duties as specified in the Security Guard Force Post and Force Orders.
8.6.4 The Security Team Leader, after completion of sweeps by members of the Security Team shall instruct guards concerning special assignments which may be required as a result of the evacuation. He shall advise the FPL Off- R9 Site Emergency Security Manager of any circumstances '9 which require his attention or assistance.
l' p.
FLORA, POWER 6. LEGS COMPANY EMERGENCY PLAN IMPLEHENTXHG PROCEDURE 83100026E, REV. 4 ZXGURZ 1 St. Luc~e P~t Owner Contro1led Area Z. C'0 7 0
PLORXDA POWER h. LZGEZ COMPANY EMERGENCY PLAN QPLZK2iTXHG PROCEDURE f3100026E, REV. 9 Sita Assemb1y Ares JAYCEE;PARK R9
+4 IJ II Cov~O OP-SITE hSS LT hREh W JVIOIOI fk PVC pf ogcv)
AT'LAMTIC C octet 0 VI
'I S ~
hSSEHBLT hREA.
'Met T wer) 4 C o ~>If ST+ LUC PC Rl- ~ ~~ +owli+
Z,O'C.is Neer& 4 vlf'oT}}

ML17214A683: Difference between revisions

Latest revision as of 14:08, 4 February 2020

Contents

Text

1.0 Title

4.0 Precautions

7.0 Records

8.0 Instructions

Title:

4.0 Precautions

1.0 TITLE

3.0 SCOPE

Purpose:

3.2 Discussion

3.0 SCOPE

3.3 Authoritv

4.0 PRECAUTIONS

8.0 INSTRUCTIONS

1.0 TITLE

2.0 APPROVAL

3.0 SCOPE

3.0 SCOPE

3.4 Definitions

3.4 Definitions

4.0 Precautions

4.0 Precautions

References:

8.0 Instructions

8.0 Instructions

8.0 Instructions

Navigation menu

ML17214A683: Difference between revisions

Latest revision as of 14:08, 4 February 2020

Text

1.0 Title

4.0 Precautions

7.0 Records

8.0 Instructions

Title:

4.0 Precautions

1.0 TITLE

3.0 SCOPE

Purpose:

3.2 Discussion

3.0 SCOPE

3.3 Authoritv

4.0 PRECAUTIONS

8.0 INSTRUCTIONS

1.0 TITLE

2.0 APPROVAL

3.0 SCOPE

3.0 SCOPE

3.4 Definitions

3.4 Definitions

4.0 Precautions

4.0 Precautions

References:

8.0 Instructions

8.0 Instructions

8.0 Instructions

Navigation menu

Search