ML20027B441

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 3100021E Re Duties of Emergency coordinator,3100025E Re Fire Emergency & 3100026E Re Criteria for Conduct of Evacuations

ML20027B441
Person / Time
Site:	Saint Lucie
Issue date:	08/06/1982
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17213A455	List: ML17213A456 ML20027B441
References
PROC-820806-01, NUDOCS 8209200461
Download: ML20027B441 (105)

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• Page 1 of 23 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E ~~

REVISION 12

1.0 Title

Duties And Responsibilities Of The Emergency Coordinator

2.0 Approval

Reviewed by Plant Nuclear Safety Committee ~ fuly 25, 19 3 Approved by K. N. Harris Plant Manager July 29, 19 3 Revision 12 Rev ,b Facility R iew Group Jun e, 7 19 82,,

Approved by 'M k ylice Pres. Nuc Energy 8, 4l 19_,_8,2_

7

3.0 Scope

3.1 Purpose

This procedure provides the instructions to be followed by the E:nergency Coordinator when an emergency occurs that requires the initiation of the Emergency Plan.

3.2 Discussion

TheNuclearPlantSupervisorbecomesthekmergencyCoordinatoruhn initiation of the Emergency Plans and, as such, directs the On-Site Emergency Organization to bring the emergency under control.

3 .3 Authority:

~~

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

4.0 Precautions

th 4.1 The Nuclear Plant Supervisor and the shift operating staff represent the first-line of response to any developing emergency condition.

The primary responsibility of the Nuclear Plant Supervisor is to control the condition as well as possible. However, the success of the Emergency Plan and Precedures requires prompt classification of the emergency (in accordance with E-Plan Implementing Procedure -

3100022E, Classifications of Emergencies) and notifications of designated off-site authorities as well as FPL's Off-Site Emergency Organization (see Figure 1 for notification flow).

8209200461 820901 PDR ADOCK 05000335 F PDR

-= %S e s Page 2 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

4.0 Precautions

(continued) 4.2 The Emergency Coordinator can delegate his responsibilities at his _ _

discretion with the exception of the decision to notify state and local authorities and the content of that notification. When the TSC is operational, the Emergency Coordinator can delegate all off-site communications to the TSC Supervisor.

4.3 During exercises, drills or tests, ALL MESSAGES shall begin and end with "THIS IS A DRILL MESSAGE" or "THIS IS AN EXERCISE MESSAGE".

4.4 Protective action recommendations to state and locaQut_horities CANNOT be delegated by the Emergency Coordinator, however, these recommendations become the responsibility of the Recovery Manager when the Interim Emergency Operating Facility is manned and operational.

5.0 Responsibilities :

. 5.1 If the Nuclear .lant Supervisor is incapacitated, the Emergency Coordinator shall be (in order of succession):

5.1.1 Nuclear Watch Engineer 5.1.2 Any other member of the plant staff with a_ Senior Reactor Operator License.

5.1.3 If no Senior Reactor Operator is available, any othet l Licensed Operator. . -. -

5.2 The Emergency Coordinator shall only grant permission for watch relief, including his own, when it is safe in his judgement to do so.

5.3 The Operations Superintendent, the Operations Supervisor or a , ~

Operations Duty Call Supervisor can assume the Emergen~cy Coordinator function at his discretion following the proper turnover procedure.-

5.4 The Technical Support Center Supervisor shall fill out the checklist for Notification of Significant Events (to NRC) as soon as possible af ter activating the TSC and preferably before calling the NRC.

5.5 The Emergency Coordinator is responsible for providing protective action recommendations to off-site authorities. This responsibility cannot be delegated, but becomes the responsibility of the Recovery Manager when the Interim Emergency Operations Facility is manned and -

operational.

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- o-'N a o Page 3 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 6.0

References:

6.1 St. Lucie Plant Radiological Emergency Plan , _

6.2 E-Plan Implementing Procedures, as follows:

EPIP-3100022E - Classification of Emergencies.

EPIP-3100026E - Criteria for and Conduct of Evacuations.

EPIP-3100033E - Radiation Release and Dose Projection.

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7 .0 Records:

All significant information, eients, and actions taken during the emergency period shall be recorded as directed by the Emergency Coordinator.

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_ __ _ . . . _ _ _ __.m_ _:. : d a s Page 4 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

8.0 Instructions

8.1 Classification _ _

Immediately upon becoming aware of an abnormal condition, the Nuclear Plant Supervisor shall classify the condition in accordance with the criteria given in E-Plan Implementing Procedure 3100022E, Classification of Emergencies. If the classification is, UNUSUAL -

EVENT, ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY, the Nuclear Plant Supervisor shall declare an emergency and become the Emergency Coordinator. The Emergency Coordinator shall, until relieved, remain in the Control Room at all times during emergency situations that require Emergency Plan implementation unless, in N'a opinion, his personal evaluation of the situation is necessary .tintain plant safety.

8.2 The Emergency Coordinator shall mobilize the On-Site Emergency Organization to begin required corrective and protective actions.

8.3 CHECKLISTS 8.3.1 If the situation is a Plant / Radiological Emergency, utilize the Plant / Radiological Emergency Checklist, (Page 6).

8.3.2 If the situation is a fire or explosion, utilize the Fire or Explosive Emergency Checklist, (Page 13).

8.3.3 If the situation is a medical emergency with or without contamination, utilize the Medical. Emergency Checklist, (Eage . _

16).

8.4 Responsibilities for off-site communications and coordination shall be relinquished first to the Technical Support Center Supervisor and then to the Emergency Control Officer when they establish contact and assume responsibilities. , _

8.5 0FF-SITE PROTECTIVE ACTION RECOMMENDATIONS -

The Emergency Coordinator is responsible for providing protective action recommendations to off-site authorities as indicated on Pages 19 through 23, " Guidelines for Protective Action Recommendations to Off-site Authorities". When the Emergency Control Officer has indicated that the Interim Emergency Operations Facility is manned and operational, the Recovery Manager can relieve the Emergency Coordinator of this responsibility. /R12

U?. u ..n w .. - . - - - - . . . . . . . . . ~ . - .. --w Lie f a e Page 5 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE 1 l EMERGENCY l - -

COORDINATOR l DUTY CALL EMERGENCY CONTROL OFFICER l FPL

& SUPERVISOR -~

OR ~ OFFSITE EMERGENCY ALT. E.C.O. I RADIOLOGICAL DUTY OFFICER l ORGANIZATION ADDITIONAL ~ ~' ~~ -

PLANT SUPPORT INTERIM _

EMERGENCY TEAM d TEAM MEMBERS l

~

2 EMERGENCY LEADERS l TEAMS STATE OF FLORIDA

- BUREAU OF DISASTER PREPAREDNESS I

ST. LUCIE/ MARTIN COUNTIES

• - 0FFICE OF DISASTER PREPAREDNESS I

STATE OF FLORIDA

< DEPT. OF BEALTH &

REHABILITATIVE SERVICES i LOCAL SUPPORT .

1. FIRE / AMBULANCE; ST.

LUCIE COUNTY - FORT

, PIERCE FIRE DISTRICT .

! 2. MEDICAL; LAWNWOOD MEDICAL CENTER OR REEF AT MT. SINAI

. USNRC OPERATIONS CENTER

• Via LGR for Site Area and General Emergency Status During Unusual and Alert BDP will notify the counties.

I ST. LUCIE PLANT INITIAL NOTIFICATION FLOW FIGURE 1 k

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Page 6 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR PLANT / RADIOLOGICAL EMERGENCY CHECKLIST Date Seq. # ~'

Class at Time of Unusual Event Alert Site Area General D Declaration D D D D E Escalation E E E TIME

1. Order initial corrective action per Emergency Operating Procedures.

IF UNUSUAL EVENT - SKIP TO STEP 7 __ _

2. Notify personnel of the emergency condition over the Unit #1 and/or #2 PA system, giving location, class, and type of emergency.

Repeat Announcement IF SITE OR GENERAL - SKIP TO STEP 4

3. If the evacuaton of an area is necessary, initiate a local evacuation in accordance with E-Plan Implementing Procedurc 3100026E, Criteria for and Conduct of Evacuations.

Announce the following:

Areas to be evacuated Areas to be avoided, if possible, during the Evacuation Assembly Area IF ALERT SKIP TO STEP 7

4. Sound Site Evacuation Alarm. Order all non essential personnel to commence evacuation of the owner controlled area in accordance with ~~

EPIP 3100026E, Criteria & Conduct of Evacuations. - -

5. Repeat PA announcement.

6. Order Security Team Leader to evacuate Owner Controlled Area and to report personnel accountability as soon as possible.

7. Mobilize Interim Emergency Teams to respond as necessary.

_ 8. Commence preparation of the attached State of Florida Fixed Nuclear Facility Notification Message Form and EMERGENCY -

INFORMATION CHECKLIST, including off-site dose projection using E-Plan Implementing Procedure 3100033E, Radiation Release and Dose Projection.

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Page 7 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 l DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR STATE OF FLORIDA FIXED NUCLEAR FACILITY NOTIFICATION MESSAGE FORM

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Date and time of message

1. SITE 2. ACCIDENT CLASSIFICATION 3. UNIT NUMBER (S)

@l St. Lucie A Unusual Event lA One (1)

B Alert [B, Two (2)

C Site Area Emergency D General Emergency

4. TIME AND DATE OF INCIDENT / EVENT: TIME _DATE

5. INCIDENT INVOLVES:

6. SITUATION INVOLVED: 7. TYPE OF RELEASE IS:

A No Release A Radioactive Gaseous B Potential (possible) release B Non-Radioactive Gaseoua

[ Imminent (probable) release [ Radioactive Liquid D A release is occurring D Non-Radioactive Liquid

[ A release that occurred, but stopped l[ Non-Applicable

8. RECOMMENDED PROTECTION ACTIONS:

A For Information only - (Unus'al Event or Alert)

B Prepare for possible action involving the public, to include notification.

(Alert or Site Area Emergency) ._. _

([l Notify public to take the following protective actions. (Site Area or General Emergency)

NO ACTION SHELTER EVACUATE lDj @ 0-2 Mile radius (Gaseous Release)

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[ l_E l Q 2-5 Miles for sectors (Gaseous Release)

O El L71 5-10 Miles for sector. -

(Gaseous Release) l[l ll Miles l[l Discontinue use of potentially affected water in Locations

9. RELEASE IS:

A, Continuing - Expected duration or magnitude B. Terminated - Approximate Duration or Magnitude

10. REPORT OF GASEOUS RELEASE IS: @l Ground Level

11. WIND SPEED: Miles per hour; Direction, FROM o j NOTE: USE NOT APPLICABLE (N/A) WHERE APPROPRIATE.

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- a Page 8 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY C00RDINATOR'

12. WIND DIRECTION DATA (CHECK ONE, READ ACROSS)

WIND FROM DEGREES WIND TOWARD SECTORS AFFECTED ' ~

[ N 349-11 S HJK I B NNE 12-33 SSW JKL ,

C NE 34-56 SW KLM I j ENE 57-78 WSW LMN )

E_ E 79-101 W MNP l F_ ESE 102-123 WNW NPQ G_ SE 124-146 NW PQR H_ SSE 147-168 NNW QRA J S 169-191 N __ _R A_B K SSW 192-213 NNE ABC

$ SW 214-236 NE BCD M_ WSW 237-258 ENE CDE N W 259-281 E DEF P WNW 282-303 ESE EFG j NW 304-326 SE FGH R NNW 327-348 SSE GHJ O

13. CURRENT OUTSIDE TEMPERATURE: @l F

14. WEATHER CONDITIONS: (Rain, Snow, Sleet, Etc.):

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15. TEMPERATURE DIFFERENCE (DELTA T): l[l Elevation of Temp. Difference Measurement:

F Stability Class (If Known):

16. RELEASE DETECTED BY: - - - -

A Visual B Sample Results Are:

] Instrumentation Location Release Rate (Ci/sec)

17. ACCIDENT RELATED INJURIES: @l NO @l YES ' Number of Injuries

18. OTHER INFORMATION:

19. MESSAGE REPORTED BY:

Name Organization Telephone (Outside f/)

< 20. MESSAGE RECEIVED BY:

Your Name Time

! Date CONTINUE TO NEXT PAGE FOR:

1. Plant Duty Call Supervisor

2. Emergency Control Officer / Recovery Manager / Nuclear Energy Duty Officer

3. DHRS Radiological Duty Officer

, NOTE: USE NOT APPLICA3LE (N/A) WHERE APPROPRIATE

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Page 9 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERPENCY COORDINATOR EMERGENCY INFORMATION CHECKLIST l ADDENDUM TO STATE OF FLORIDA FIXED NUCLEAR FACILITY I NOTIFICATION MESSAGE FORM

1. Date / / and Time of Message

2. Assessment of the Emergency (including potential for escalation to higher class l

3. Basic Description of the Event l

4. Estimate of Radioactive Material Released (Gaseous):

Noble Gases: Source Term: Ci/See Total Release: Ci . -

Radioiodines: Source Term: C1/Sec Total Release: Ci l.

5. Estimate of Projected Offsite Dose Rates: -- -

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, DISTANCE THYROID (ares /hr) WHOLE BODY (mres/hr) 1 mile (site boundary) l 2 miles l l

f 5 miles 1

10 miles -

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Page 10 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100C21E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR PLANT / RADIOLOGICAL EMERGENCY CHECKLIST (continued)

9. During current business day, notify the Plant Manager, during of f - -

hours and weekends relay information to the Duty Call Supervisor (see NPS Bulletin Board for scheduled supervisor and telephone number).

Order him to notify *.he followint;:

Plant Manager Operations Superintendent Operations Supervisor Technical Department Supervisor Emergency Control Officer (or NuclearWergy Duty Officer)

Other Department Supervisors (Primary Team Leaders)

(ALTERNATE METHOD: If Duty Call Supervisor is unavailable -

notify Emergency Control Officer.

10. Notify the following within 15 minutes of classifying the emergency:

10.1 NAWAS Announcement:

" State Warning Point Tallahassee, this is St. Lucie *

(State Warning Point will give a go-ahead)

" State Warning Point Tallahassee, this is St. Lucie * ,

• , repeat * ."

" Enter appropriate site, class.

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(ALTERNATE METHOD: If NAWAS is unavailable, tel'ephone' State Warning Point at PHONE NO., Florida Marine Patrol-Alternate State Warning Point State Warning Point will call via Phone to validate the notification. Af ter validation, transfer the information on the .

State of Florida Fixed Nuclear Facility Notification Message -

Form via NAWAS or ALTERNATE ROUTE. .

State Warning Point Acknowledgement Time 10.2 Notify, by telephone, the State Radiological Duty Officer at Radiological Healt.h Services in Orlando atN (they have a beeper service for full time coverage) When the Duty Officer is contacted, transfer the information on the State of Florida Fixed Nuclear Facility Notification Message Form and the Emergency Information Checklist.

IF UNUSUAL EVENT OR ALERT, SKIP TO STEP 12 m

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Page 11 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR PLANT / RADIOLOGICAL EMERGENCY CHECKLIST (continued)

11. When LGR system is activated by offsite organizations, contact S t .- -

Lucie County Disaster Preparedness, inform them of off site dose projectiors and that site evacuation has started, location of assembly area (s), evacuation route (s). Notify them of any wind changes, and when evacuation is completed.

12. Prepare attached SIGNIFICANT EVENT REPORT (if time permits) and notify NRC via hot-line (within one hour)

(To be done by TSC if properly staffed)

IF UNUSUAL EVENT, SKIP TO STEP 18

13. Verify from Security Team Leader that the evacuation (if orderad) has been completed and all personnel are accounced for.

14. Reassess corrective and protective actions. Verify activities underway, reassign personnel and teams as necessary.

15. Activate the Technical Support Center and the Operational Support Center.

16. Brief the Technical Support Center Supervisor on events.

Order him to update state and county periodically and to refine dose projections when the Chemistry Department representative arrives.

17. Relinquish responsibilities for communications with off-site support agencies when the Emergency Control Officer notifies the Emergency Coordinator that he accepts these responsibilities.

18. Reassess the Emergency Classification and if the situation escalates, recycle tha Plant / Radiological Emergency Checklist, excluding those entries already compleceu. .

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< _ . _ . . . , . . ~ . . ___._: _ _ _ . -_ ._ - . i . ,didd 6 0 Page 12 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PEOCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SIGNIFICANT EVENT REPORT (for NRC Notification)

Date Time Facility Nama Florida Power & Light St. Lucie Unit #1 Caller Name

1. Description of Event Classification of Event Reactor Systems Status Pressure Temperature Power level Flow ECCS Operating / Operable (Pumps on)

PZR or RX Level Cooling Mode Any Radioactive Release or Increased Release?

Path Stopped? Release Rate Monitored?

Steam Plant Status: S/G Levels Equip. Failures Feedwater Source / Flow Electrical Dist. Status: Normal Off-site Power Sources . _ . . _

Available?

Major Busses / Loads Lost Safeguards Busses Power Source D/G Running? Loaded? _

Personnel Casualties / Contamination? ,

2. Consequences of Event:

Actual and Potential Safety Hazards:

r Tech. Spec. Violations?

State Notified? Press Release Planned? _

3. Cause of Event:

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t Corrective Actions taken:

l Planned:

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Page 13 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIRE OR EXPLOSION EMERGENCY CHECKLIST

1. CLASS: Unusual Event (time) Alert (time)

NOTE: If class is SAE or GENERAL, go to Plant / Radiological Checklist. - -

TIME

2. Order initial corrective action per Emergency Operating Procedures.

3. Sound c' ire Alarm.

4. P.A. Announcement of location and extent of fire.

5. Activate the Fire Brigade and other appropriate emergency teams in accordance with Fire Emergencies EPIP 3100025E - PA announcement.

6. If the evacuation of an area is necessary, initiate a local evacuation in accordance with E-Plan Implementing Procedure 3100026E, Criteria for and Conduct of Evacuations. Announce the following:

Area to be evacuated Areas to be avoided, if possible, during the Evacuation Assembly area

7. If off-site assistance is necessary call St. Lucie County - - -

Ft. Pierce Fire District PHONE No. 911.

8. Prepare the following Notification Form:

STATE OF FLORIDA FIXED NUCLEAR FACILITY NOTIFICATION MESSACE FORM _

Date and time of message

~

1. SITE 2. ACCIDENT CLASSIFICATION 3. UNIT NUMBER (S)

Q[ St. Lucie A Unusual Event @ One (1)

B Alert @ Two (2)

4. TIME AND DATE OF INCIDENT / EVENT: TIME DATE

5. INCIDENT INVOLVES:

6. SITUATION INVOLVED:

A No Release

} Potential (possible) release

[C Imminent (probable) release D, . A release is occurring E A release that occurred, but stopped

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. e Page 14 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIRE OR EXPLOSION EMERGENCY CHECKLIST (continued)

ITEMS 7 THROUGH 16 INCLUSIVE ARE N/A (NOT APPLICABLE)

17. ACCIbENT RELATED INJURIES: @ NO @ YES Number of Inj uries

18. OTHER INFORMATION:

19. MESSAGE REPOR*ED BY:

Name Organization Telephone (Outside f/)

20. MESSAGE RECEIVED BY:

Your Name Time Date

9. Relay information to the Duty Call Supervisor (see NPS Bulletin Board for scheduled supervisor and telephone number). Order him to notify the following:

Plant Manager Operations Superintendent Operations Supervisor Technical Department Supervisor Emergency Control Officer (or Nuclear Energy Duty Officer)

Other Department Supervisors (Primary Team Leaders)

~

(ALTERNATE METHOD if Duty Call ~ Supervisor l's un'available -

Notify Emergency Control Officer

10. Notify the following within 15 minutes of classifying the emergency:

10.1 NAWAS ANNOCNCEMENT: - -

" State Warning Point Tallahassee, this is St. Lucie.*

(State Warning Point will give a go-ahead)

" State Warning Point Tallahassee, this is St. Lucie * ,

• , repeat * ."

• Enter appropriate site, class.

Time

" Acknowledge, over."

(ALTERNATE METHOD) if NAWAS is unavailable-celephone State Warning Point at PHONE NO.7 lorida Marine Patrol-Alternate State Warning Point M M

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 ROUTE.

State Warning Point Message Validation Time c,

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- ~n;2Al i Page 15 of 23 l

ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIRE OR EXPLOSION EMERGENCY CHECKLIST (continued) ,

10.2 Notify, by telephone the State Radiological Duty Officer at Radiological Health Services in Orlando at$

W (they have a beeper service for full time coverage) When the Duty Officer is contacted, transfer the information on the State of Florida Fixed Nuclear Facility Notification Message Form.

11. Prepare attached SIGNIFICANT EVENT REPORT (if time persics) and notify NRC via hot-line (within one hour):--(To be- done by TSC if properly staffed)

12. Verify from Security Team Leader that all persorinel are accounted for (if local evacuation was conducted).

13. Reassess corrective and protective actions. Verify activities underway, reassign personnel and teams as necessary.

IF UNUSUAL EVENT, SKIP TO STEP '.7

14. Activate the Technical Support Center and the Operational Support Center. Appoint OSC Supervisor.

15. Brief the Technical Support Center Supervisor on events. Order him to provide state and county with periodic updates and to refine dose projections when the Chemistry Department

" ' ~

representative arrives.

16. Relinquish responsibilities for communications with of f-site support agencies when the Energency Control Officer notifies the Emergency Coordinator that he accepts these responsibilities.

17. Reassess the Emergency Classification and update the State of -

Florida Fixed Nuclear Facility Notificatio.n Message Form with -

Technical Support Center Supervisor.

18. If the accident involses actual or impending releases of .

radiaton, go to the PLANT / RADIOLOGICAL EMERGENCY CHECKLIST.

.- .. ~. - . - - - - ~ . - - .

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Page 16 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR MEDICAL EMERGENCY CHECKLIST TIME _ .

1. Determine:

Name of 11ctim Employer (if not FPL)

Nature and Extent of Injury Location Is victim contaminated?

2. Activate First Aid and Personnel Decontamination Team (Notify Chemistry Supervisor).

3. Notify:

Health Physics Plant Manager Operations Superintendent

4. When determined, notify Captain of Guard where to direct ambulance, etc.

5. Determine mode of transportation based on nature and extent of inj uries. (Ensure victim's TLD, selfreader, ID badge -and key card are- -

retained on site).

1

a. Medical treatment for serious injury:

AMBULANCE PHONE NO. 911 b.

~

l Medical treatment for minor injuries: ~'

l FPL Vehicle / Private Vehicle

6. Send all victims to LAWNWOOD MEDICAL CENTER PHONE NO. N -

Radioactively contaminated victims:

Notify REEF PHONE NO.

7. If Plant Manager not available, notify Duty Call Supervisor and Health Physics Duty Call Supervisor-See Emergency Roster for Off-sita notifications.

8. Insure that completed Medical Notification form accompanies the victim.

9. Complete the following message form:

.a. . . . . - - - . . . . . . - . . . . . _ - ~ .a j Page 17 of 23 j ST. LUCIE UNITS 1 AND 2

! E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR I

MEDICAL EMERGENCY CHECKLIST 4

(continued)

STATE OF FLORIDA FIXED NUCLEAR FACILITY - .

NOTIFICATION MESSAGE FORM 1

Date and time of message

1. SITE 2. ACCIDENT CLASSIFICATION 3. UNIT NUMBER (S)

@j St. Lucie @l Unusual Event @l One (1) lBl Two (2)

4. TIME AND DATE OF INCIDENT / EVENT: TIME --DATE -

5. INCIDENT INVOLVES:

6. SITUATION INVOLVED:

A No Release

} Potential (possible) release C Imminent (probable) .elease D A release is occurring E A release that occurred, but stopped ITEMS 7 THROUGH 16 INCLUSIVE ARE N/A (NOT APPLICABLE) l 17. ACCIDENT RELATED INJURIES: @l NO @l YES Number of Injuries

18. OTHER INFORMATION:

19. MESSAGE REPORTED BY:

Name Organization Telephone (Outside 1) .

20. MESSAGE RECEIVED BY:

Your Name Time Date Continue to next page l

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Page 18 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 31u0021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR MEDICAL EMERGENCY CHECKLIST (continued)

10. Within 15 minutes of classifying the emergency: -

10.1 NAWAS Announcement:

" State Warning Point Tallahassee, this is St. Lucie * "

(State Warning Point will give a go-ahead)

" State Warning Point Tallahassee, this is St. Lucie * ,

UNUSUAL EVENT , repeat UNUSUAL EVENT."

• Enter appropriate site.

Time -- -" -

" Acknowledge, wa r . "

(ALTERNATE METHOD if NAWAS is unavailable-telephone State Warning Point at PHONE NO. or Florida Marine Patrol-Alternate State Warning Point M .

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 ROUTE.

State Warning Point Message Validation Time 10.2 Notify, by telephone the State Radiological Duty Officer at Radiological Health Services in Orlando at M (they have a beeper service for full time coverage) When the' Thity ~

Officer is contacted, transfer the information on the State of Florida Fixed Nuclear Facility Notification Message Form.

11. Prepare attached SIGNIFICANT EVENT REPORT (if time permits) and notify NRC via hot-line (within one hour). (To be done by TSC if

, properly staf fed.) . -

12. Reassess the Emergency Classification and update the State of Florida Fixed Nuclear Facility Notification Message Form.

13. If the accident involves actual or impending releases of radiation, go to the PLANT / RADIOLOGICAL EMERGENCY CHECiG IST.

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ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR PROTECTIVE ACTION RECOMMENDATIONS FPL is required to provide county and state governmental authorities with recommendations for protective action to be taken by the public during - -

radiological emergencies at the St. Lucie Nuclear Power Plant.

The responsible authorities are the State Bureau of Disaster Preparedness (BDP) and St. Lucie and Martin County Offices of Disaster Preparedness.

Due to the large political and legal ramifications of these recommendations and the potential bspact on FPL, the following format and content should be used:

1. If the emergency has been classified as a GENERAL ETERGENCY and NO OFFSITE dose estimates or field survey results are available, refer to figure A-1 to evaluate offsite protective action recommendations.

2. If the emergency has been classified, and the offsite doses are LESS THAN 0.5 Rem whole body or i Rea to the thyroid at 1 mile over the projected duration of the release, no protective action is recommended. This should be reported to BDP and other outside agencies who inquire is:

" Based on our current assessment of all the information now available to us, Florida Power & Light recommends that you consider taking the following protective actions (PA) - NONE.

{'

This recommendation may change in the future, but we cannot now say when it may change or what it may change to."

3. If the energency has been classified and of fsite dose information is available (from any credible source), use the do'se information to ente'r' ' ' ~

the appropriate estimated offsite table in Figure A-2 (PA with offsite 1

dose estimates for greater than or equal to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration) or Figure A-3 i (PA with offsite dose estimates for less than 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration). The appropriate recommendations can then be made. FOR EXAMPLE, a release has

! occurred at the St. Lucie Plant with a projected duration of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the .

wind direction is from the NNE and the projected offsite integrated (2 hr) thyroid dose is 10 Ren at 1 mile, 2 Ren at 2 miles, and less than 1 Rem at 5 miles. Referring to Figure A-2 (PA with offsite dose estimates for greater than or equal to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration) the following recommendation should be made:

" Based on our current assessment of all the information now available to us, Florida Power & Light Company recommends that you consider taking the following protective actions:

1. Evacuate all personnel between a 0 and 2 miles radius from the plant. .

11. Shelter all personnel between a 2 and 5 mile radius from the plant who are in sectors J, K & L (refer to State of

. Florida Fixed Nuclear Facility Notification Message Form, l Page 17 Entry 12) 111. No protective action is recommended between a 5 and 10

mile radius from the plant i

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! ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR PROTECTIVE ACTION RECOMMENDATIONS (continued) i 3. (continued) i This recommendation may change in the future, but we cannot

now say when it may change or what it may change to."

4. For other emergency conditions which may occur, enter the table for those conditions, determine the recommended protective actions and fomulate the appropriate message in the above format and transmit it to1DP.

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._.,<_. _: 6.i a Page 21 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE A-1 PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT CONDITIONS DISTANCE FROM PLANT / RECOMMENDATION

• l 0-2 MILES l 2-5 MILES j 5-10 MILES l GENERAL I I

EMERGENCY? NO 7 N l N l N l YES I

CHRRM NO

> 1.47 E5 M S(CR) l S(DW) i N l R/hr YES

'd . . . -

LOSS OF CONTAINMENT NO INTEGRITY? M E(CR) } E(DW) + l E(DW) + l YES ,

M E(CR) l E(CR) l E(DW) + l

• LEGEND OF ABBREVIATIONS N - No protective action recommended S - Sheltering recommended E - Evacuation recommended .,

DW - Downwind sector DW4- Downwind + 2 adjoining sectors RS - Remaining sectors CR - Complete circle around plant at specified distance

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Page 22 of 23 ST. LUCIE UNITS 1 AND 2 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 12 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE A-2 PROTECTIVE ACTION RECOMMENDATIONS BASED ON ACTUAL RELEASE (GREATER THAN OR EQUAL TO 2 HOUR DURATION) WITH OFFSITE DOSE ESTIMATES -

(used in preference to Figure A-1)

WHOLE BODY OR THYROID DOSE l 0-2 MILES l 2-5 MILES l5-10 MILES l DOSE (REM) l (REM) l

< 0.5 < 1.0 .

,1 N l N l N' l l

l 1 0.5 l 1 1.0 but but mj S(CR) l S(DW) i S(DW) l

< l.0 < 5.0

~

> 1.0 l ~

> 5.0 but but _l E( CR) l E(DW) + l E(DW) + l

< 25.0

< 5.0 S(RS) S(RS) l l > 5.0 > 25.0 ,1 E(CR) l E(CR) l E(DW) + l l S( RS)

NOTE- -

Ti The. duration of the release is ,

projected to be less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, use Figure A-3.

• LEGEND OF ABBREVIATIONS N - No protective action recommended S - Sheltering recommended E -

Evacuation recommended DW - Downwind sector DW+ - Downwind + 2 adjoining sectors .

RS -

Remaining sectors CR -

Complete circle around plant at specified distance e

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(used in preference to Figure A-1) 3 WHOLE BODY OR THYROID DOSE l 0-2 MILES l 2-5 MILES (5-10 MILES l DOSE (REM) l (REM) l < 0.5 < 1.0 ,1 N l N { N l l > 0.5 , > 1.0 but but l S(CR) { S(DW) l S(DW) l

< 1.0

~

< 5.0

> 1.0 > 5.0 but but _!

S(CR) l S(CR) { S(CR) l

< 5.0 < 25.0

> 5.0 > 25.0 _l

~

E(CR) l E(DW) l E(DW) + l S(RS) S(RS)

NOTE: .

If the duration of the release is projected to be less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, uca Figure A-3. .

• LEGEND OF ABBREVIATIONS N - No protective action recoinmended S - Sheltering recommended E - Evacuation recoiamended DW - Downwind sector .

DW+- Downwind + 2 adjoining sectors RS - Remaining sectors CR - Complete circle around plant at specified distance

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REVISION 7

1.0 Title

FIRE EMERGENCIES

2.0 Approval

Reviewed by Facility Review Group --July 2 5, 197 5 Approved by K. N. Harris Plant Manager July 29, 1975 Revision 7 Revie 4 y i' R G a 177e u // J~un a 7 19ffL Approved by [ // YN1 f / Vice-Pres. Nuc. Eng. b V' 19 [ V a

3.0 Scope

3.1 Purpose This procedure provides instructions to control and extinguish fires, minimize damage and prevent personal injuries.

3.2 Discussion 3.2.1 Any uncontrolled fire is considered a Fire Emergency. In ~' ~

order to control and extinguish a fire, a fire fight'ing organization has been established.

3.2.2 The Fire Team is composed of members of the Operating group assigned to the St. Lucie Plant. The members of the Fire Teams are qualified in fire fighting. .

3.2.3 For a list of the locations of fire fighting equipment, refer.

to the Mechanical Maintenance preventive maintenance program j as delineated in Admin. Procedure No. 0010431 " Preventive Maintenance Program".

3.2.4 The emergency classification system includes certain fire related events. Thus, fires may be classified as Unusual Events, Alerts, or Site Area Emergencies.

3.3 Authority ,

This procedure implements the St. Lucie Plant Emergency Plan and Fire Protection Plan.

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. LUCIE PLANT E-P LAN IM P LEME NT' ' v PR OC ED UR E 3100025E, REVISION 7 FIRR EMERGENCIES

4.0 Precautions

4.1 Class "C" fire extinguishers (CO2 or Dry Chemical) or fog type fire hose nozzles shall be used on combustible liquid fires, electrical - -

fires or on fires which might involve energized conductors and/or equipment.

4.2 Foam type fire extinguishing materials shall not be used on electrical fires.

4.3 When fighting fires in the Radiation Controlled Area that may involve radioactive materials, the members of the Fire Team shell use additional protective equipment specified by the-Radiation Team Leader and shall follow any instructions he issues regarding precautions to observe while fighting the fire.

5.0 Responsibilities

5.1 The Nuclear Watch Engineer is the Fire Team Leader. If he is not available, the Nuclear Turbine Operator acts as his alternate. It shall be the responsibility of the Fire Tean Leader to:

5.1.1 Direct all phases of the fire fighting activities.

5.1.2 Coordinate the activities of any outside fire fighting organization called in to assist with the emergency.

5.2 It shall be the responsibility of each Fire Tean member to be thoroughly familiar with the contents of this procedure and the

' ~ ' ~ -

location of fire fighting equipment in clie plant.

5.3 All personnel shall be familiar with the location of, and be f amiliar with operation of fire equipnent in their designated work stations.

5.4 On the basis of observations, the Nuclear Plant Supervisor is .--

responsible for classification of the emergency. He is also ,

responsible for making notifications and taking other actions appropriate to the emergency class.

6.0

References:

6.1 St. Lucie Plant Emergency Plan.

6.2 E-Plant Impelementing Procedure EPIP 3100021E, Duties of the Emergency Coordinator.

6.3 E-Plan Implementing Procedure EP3100023E , On-Site Emergency Organization /and Roster.

6.4 St. Lucie Plant Administrative Procedure No. 1800022 Fire Protection Plan".

6.5 St. Lucie Plant Administrative Procedure No. 0010431 " Preventive Maintenance Program". /R7

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Page 3 of 5 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 310002 SE , REVISION 7 FIRE EMERGENCIES

7.0 Records

Any actior.s taken shall be recorded as directed by the Nuclear Plant Supervisor. . - /R7

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Page 4 of 5 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100025E, REVISION 7 FIRE EMERGENCIES

8.0 Instructions

8.1 When an individual discovers a fire which can be safely extinguished using fire fighting equipment at hand, he shall do so and then -

promptly notify the Nuclear Plant Supervisor.

8.2 When an individual discovers a fire or explosion resulting in a fire which cannot be extinguished using fire fighting equipment at hand,be shall notify the Nuclear Plant Supervisor over the PA system or the control room by dialing 333 on any PAX telephone. The following information shall be given:

- ~

8.2.1 Location of the fire. -

8.2.2 Type of fire, if known.

8.2.3 Whether or not there are any injured personnel.

8.2.4 Extent of damage to plant components.

NOTE: Speed in notification is much more important than the completeness of the initial report.

8.3 The Nuclear Plant Supervisor shall instruct the individual to take any immediate action he is qualified to perform to extinguish the fire.

8.4 The Nuclear Plant Supervisor shall cross-connect the PA system, declare a Fire Emergency, announce the location of the fire, and_ , _ _

sound the fire alarm. If sufficient information is available, he shall classify the emergency and implement the Emergency Plan.

(1) The Nuclear Watch Engineer will direct, by use of the page system, which members will meet him at the fire site, and which members will go to the fire house. .

(2) If the fire is found to be in the Radiation Controlled Area, .

the Radiation Tema shall be activated by the Emergency Coordinator (Nuclear Plant Supervisor).

(3 ) If the fire or axplosion is in the Radiation Controlled Area, they shall wear appropriate protective clothing and respiratory equipment and personnel monitoring devices, attempt to stay upwind of the fire, and coordinate their actions with the Radiation Team.

(4 ) During normal working hours additional personnel are available from the maintenance department to support fire fighting efforts until outside assistance is obtained.

/R7 (5) The Emergency Coordinator (Nuclear Plant Supervisor) shall designate additional available on-site personnel to assist in extinguishing the fire, as required by the situation.

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. o Page 5 of 5 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100025E, REVISION 7 FIRE EMERGENCIES

8.0 Instructions

(continued) 8.4 (continued) . .

8.4.1 Requesting Outside Fire Assistance:

(1) If the fire is too large to be controlled by available plant forces, the St. Lucie County-Ft. Pierce Fire District shall be called by the Emergency Coordinator.

(2) The main guard station shall be notified of the location of the fire and the expected arrival of thn off-site fire i

fighting equipment. ,

(3) Working communications shall be established between the Emergency Coordinator, the person in charge of the of f-site fire fighting organization, the Radiation Team Leader, if the fire is in the Radiation Controlled Area, and the Fire Team Leader.

St. Lucie County-Ft. Pierce 461-1547

, or St. Lucie County Emergency Center 911 /R7 (4) In the case of an uncontrolled fire, not involving a safety system, but requiring off-site support, the Nuclear Plant Supervisor shall declare an UNUSUAL EVENT.

(5) In the case of an uncontrolled fire, potentially affecting safety systems and requiring off-site support, the Nuclear Plant Supervisor shall declare an ALERT.

(6) In the case of a fire resulting in degradation of safety systems, the Nuclear Plant Supervisor shall declare a SITE -

l AREA EMERGENCY.

~

NOTE: See E-Plan Implementing Procedure 3100023E, Daergency Roster, for specific information regarding means of communication and telephone numbers.

L. EUA LEA A A i O S A.?i d

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1. 3100026E, REV. 8

1.0 TITLE

CRITERIA FOR AND CONDUCT OF EVACUATIONS

2.0 APPROVAL

Reviewed by Facility Review Group July-25; ~ -1975 Approved by K. N. Harris Plant Manager July- 24, 1975 Revision 5 Qie,wejibyFac ity Review Group March 20 & 25 19 g8 ,

Approved by /Mhr/M V.P. Pwr. Res./g(Egef p(,_ ly_ /

Revision 6 R fe ed b Faci Review Group in ay 2. 2 19 ) !

Approved by /, V.P. Pwr. Res. Aw 2, 19#/

Revision 7 Rev djby Fa Review Group u%e 2g 1982.

Approved by EMh~qi1 '-

. Dir., Nucl. Energy f/ 1982.

(/

F;1ci1% Review Group Nucl. EnergyNac 19M Revisionby8 RevM'ed/

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3.0 SCOPE

' ~ - '

3.1 Purpose - ~

This procedure provides criteria for determining if evacuation of a local area on-site or the Ownar Controlled Area should be carried out. It provides instructions foc 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.

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FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100026E, REV. 8

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 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"Br" General Emergency.

3.3 Authority

This procedure Lsplements the St. Lucie Unit #1 Emergency Plan.

3.4 Definitions

3.4.1 Assembly Area 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 entran.ce, , _

to plant property, while non-FPL personnel and FPL personnel from outside the Protected Area assemble at J.C. Public Park on Highway A1A, 71/2 miles north of the plant. If necessary, other assembly areas can be specified by the Emergency Coordinator.

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.

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Paga 3 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100026E, REV. 8

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 dotted 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.

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Paga 4 of 13 l FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100026E, REV. 8

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 Responsibilities

5.1 The Nuclear Plant Supervisor is responsible for:

5.1.1 Classifying any emergency that may occur at Unic #1.

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.

5.1.4 Providing protective action recommendations to off-site /R6 authorities per Table 1 in 3100021E(Duties of Emer. Coordinator).

5.2 The Nuclear Plant Supervisor shall act as Emergency Coordinator.

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 by the Security Force to properly fulfill their responsibilities during the evacuation shall be provided to the Security Team Leader by the Emergency Coordinator. - -

(See E-Plan Laplementing 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. .

i 5.6 All personnel permanently or temporarily assigned to St. Lucie plant shall faniliarize themselves with:

5.6.1 The instruct 1 ns given in this procedure.

5.6.2 The access routes to the work location to which they are assigned.

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o Page 5 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100026E, REV. 8

5.0 Responsibilities

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 J. C. Public Park on Route ALA, north of the plant site.

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 Rev. 8 records available when required.

5.10 The Main Gate Guard shall maintain accurate records of all personnel entering or leaving the Gene ~ rating Station Area and' ' Rev. 8' ~

make the records available when required.

5.11 The Assembly Area Supervisor shall be responsible for personnel accounting at assembly area and liason between these personnel and the Emergency Coordinator. .

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.

5.13 Unit 2 Responsibilities are defined in ASP 5.0.

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FLORIDA POHER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE .

1. 3100026E, REV. 8 , ,

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 f h er~gency Coordinator.

6.4 HP207 Personnel Monitoring follow'.ng an Evacuation.

6.5 HP208 Personnel Decontamination.

7.0 Records and Notifications:

7.1 A list of all persons assembled at J. C. Public Park shall 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 Coora.in ator. - -- - -

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Page 7 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100026E, REV. 8

8.0 Instructions

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 Unevaluated direct radiation dose rate reading in excess of 100 mrem / hour.

8.1.4 Unevaluated airborne radioactivity concentration in excess of 1 X 10-9 micro C1/cc.

8.1.5 Removable radioactive surface contamination in an unposted area in excess of 1000 dpm/100 cm2 beta-gamma over an area of 100 ft2, 8.1.6 Removable radioactive surf ace 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 I

The Owner Controlled Area shall be evacuated in the following circumstances:

1. Site Area Emergency,

2. General Emergency,

3. If the Emergency Coordinator determines that the entire Protected Area should be evacuated. -

4. Any other situation in which the Emergency Coordinator determines that evacuation is appropriate.

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1. 3100026E, REV. 8

8.0 Instructions

(Continued) 8.3 Evacuation Preparedness 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 evacuat'ed.~

8.4 Local Area Evacuation Implementation 8.4.1 When the Emergency Coordinator (Nuclear Plant Supervisor) determines that a local evacuation is necessary, he shall, in following Emergency Procedure Duties of the Emergency 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.

8.4.4 The Radiation Monitor Team shall monitor evacuated ~-

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 Security Controlled Area.

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• a Page 9 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100026E, REV. 8

8.0 Instructions

(Continued) 8.4 Local Area Evacuation Implementation (Continued) , .

8.4.7 The Emergency Coordinator and 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 Implementation 8.5.1 When the Emergency Coordinator (Nuclear Plant Supervisor) determines that an evacuation of the Owner Controlled Area is necessary, he will, in the following Emergency Procedure Duties of the Emergency Coordinator, order an evacuation using the PA system and the evacuation alarm.

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 Unit #1 in a safe condition and not on an emergency team or otherwise required on site, shall evacuate to the appropriate Assembly Area. Emergency Teamashall report to the Administrative Building for assignment'.

8.5.3 Injured personnel shall be treated as discussed in E-Plan Implementing Procedure 3100021E, Duties of Emergency Coodinator. 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 ~

Air and Personnel Decontamination Team Leader. ._

8.5.4 Personnel shall remove protective clothing prior to

• leaving the Radiation Controlled Area.

8.5.5 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 Site Assembly Area (see Figure 2).

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Page 10 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100026E, REV. 8

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 J. C. Public Park 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 Security Force Evacuation Implementation 8.6.1 Upon notification of an evacuation, the Security Force .

Shift Supervisor (Interta Security Team Le~adar) 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 will 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 4 ' * *

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FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100026E, REV. 8 1

8.0 Instructions

(Continued)

- ~

8.6 (Continued) 8.6.2 go to the Main Gate with his personnel records and await instructions from the Security Team Leader.

8.6.3 Tha 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 Off-Site Emergency Security Manager of any circumstances which require his attention.

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• e Page 1 of 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100027E, REV. 5

1.0 TITLE

RE-ENTRY

2. APPROVAL:

Reviewed by Facility Review Group July 25, 19 75 Approved by K. N. Harris Plant Manager July 19_, _ 19_ 75 Revision 3 / 1teviewed by Facility Review Group ihru. W~ 19

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Approved y- by///M, I.n,7///M P. Power Resources'/. /zer4 M,19 h hevision Approved by/ M 4 evi ed by Facility Review Group H.1,2.3 ps. N P. Power Resources 19 3I

,.duu. J,19 # /

Revision 5 rev ed by FRG , M . $ 7, MN // 1982.

Approved by

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3.0 SCOPE

3.1 Purpose This procedure provides guidelines for the selection of the - - -

Re-entry Team members and provides instructions to follow during re-encry.

3.2 Discussion l

3.2.1 Re-entry into an evacuated area shall be mad _e only v'.en _.

authorized by the Emergency Coordinator and under the ~

supervision of the Radiological team leader (RTL) or Interim RTL. /R5

1. To ascertain that all personnel who were in the affected area have been evacuated and to search for ~

unaccounted for personnel.

2. To rescue any injured or trapped personnel from the affected area.

3. To perform operations which may decrease the -

severity of the emergency.

4 To determine the nature and extent of the emergency and the radiological conditions.

5. To establish definite personnel exclusion area boundaries.

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Pzg2 2 of 6 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100027E, REV.5 3.0 SCOPE (Continued 3.2 (Continued)

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3.2.2 The Emergency Coordinator should select individuals with appropriate qualifications in First Aid, Operations, Health Physics, and Maintenance for the Re-entry Team.

3.2.3 The initial entry of the Re-entry Team, and all subse-quent entries, until radiation areas have been properly marked, shall take place under the supervision of the Radiation Team Leader.

~~ ~

3.2.4 The Re-entry Team Leaders should be fully briefed concerning the nature of the emergency. Information for these briefings will be obtained from the applicable available sources including current operating records, interviews with evacuated employees, and surveys conducted by the Radiation Team.

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

4.0 Precautions

4.1 There shall be no re-entry into the area affected by the emergency after an emergency evacuation unless authorized by the Emergency Coordinator. - .- -

4.2 All Re-entry Team members shall wear protective clothing, dostmeters, respiratory devices, and other protective devices as specified by the Radiation Team Leader.

4.3 Tne team members should not deviate from the planned route, ._

unless required by un-anticipated conditions such as rescue, ,

performing an operation which would minimize the ~ emergency. condf-tions, etc.

l 4.4 If the monitored dose rates encountered during the re-entry exceed the limits set by the Emergency Coordinator and the Radiation Team Leader, the Re-entry Team shall return to the area from which they were dispatched.

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Page 3 of 6 FLORIDA POWER & LIGHT COMPANY ~

EMERGENCY PLAN IMPLEKGTING PROCEDURE

1. 3100027E, REV. 5

4.0 Precautions

(Continued) 4.5 The following guidelines for emergency exposure of personnel shall be followed during the re-entry operation:

4.5.1 The Emergency Coordinator and the Re-entry Team Leaders shall make every effort to minimize re-entry personnel exposures, utilizing radiacion survey and monitoring devices, pectective clothing, breathing apparatus, and other special equipment as required.

~ ' '

4.5.2 Under emergency conditions nc-c requiring action to prevent serious injury or a catastrophic incident, Re-entry Team personnel exposure in excess of 10 CFR 20 limits may be authorized by the Emergency Coordinator, but shall not exceed 5 Rem whole body exposure.

4.5.3 A planned eme.rdency dose to prevent serious injury or to prevent destructica of equipnent which could result in serious injury should not exceed 12 Rem whole body dose.

4.5.4 Under emergency conditions where immediate action is necessary to prevent serious injury or a catastro!.hte incident, Re-entry Team members' exposures authorized, by the Emergency Ccordinator, with the consent cf the individuals to be exposed, should not exceed 25 Rem whole body exposure, except.for life saving' actions. ' ~ ~

4.5.5 For life saving actions, an individual may receive a dose of up to 75 Rem whole body exposure.

4.6 A Re-entry Team shall consist of at least two persons. '

5.0 ,Responsib ilities : ,

5.1 The Emergency Coordinator has the responsibility for buthorizing re-entry into an area after it has been evacuased. It shall be.

his responsibility to select qualified personnel for the Re-entry Team and make clear what their assigned duties are prior to re-entry.

5.2 The Radiation Team Leader shall be responsible for the supervision of the initial entry into_an evacuated area, and for all subae-quent entries until radttrion areas have been properly marked and a safe route determined. He shall also make recommendations to the Emergency Coordinator as to the expected doses the Re-entry Team' .

personnel will be subjected to and the feasibility of attempting re-entry into a given area.

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1. 3100027E, REV. 5

-5.0 Responsibilities: (Continued) ,

5.3 It shall be the responsibility of the person appointed Re-entry Team Leader to strictly follow the orders given to him by the Radiation Team Leader and at all times to protect the members of the Re-entry Team from possible injury and excessive radiation exposure.

--6.0

References:

6.1 S t. Lucie Plant Radiological Emergency Plan _ , ,

i 6.21 St. Lucie Plant Radiation Protection Manual s .

6.3 HP 200 HP Emergency Organization j  ; 6.4 HP 201 Personnel Exposure Control

1 0

6.5> HP 203 Personnel Access Control /R5 7.0 Records and Notifications:

Detailed records of all significant actions of the Re-entry Team whall be recorded by the Emergency Coordinator.

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1. 3100027E, REV. 5

8.0 Instructions

8.1 The Emergency Coordinator or the Radiation Team Leader .

or their designee _shall:

8.1.1 Select at least two qualified persons to form a Re-entry Team. One of the members shall be qualified in Health Physics procedures.

8.1.2 Brief the team members concerning the natgI.e of the emergency and the possibility of hazards being present.

8.1.3 Instruct the team members as to what is required of them while in the emergency area. This may consist of the following :

1. Search for injured, trapped or unaccounted for personnel.

2. Operate equipment as needed.

3. Deternine the nature and extent of the emergency and radiological conditions.

4. Establish definite personnel exclusion areas and access routes.

8.2 The Radiation Team Leader shall:

8.2.1 Evaluate the emergency to determine the possible dose rates and stay times. Refer to Step 4.5 of'this procedure for guidelines.

~

8.2.2 Supervise the initial entry of the Re-entry' Teams into the ~

area of the emergency and any subsequent entries until readiation areas have been properly marked.

8.2.3 Based on the information available, select a route for the Re-entry Teams to follow into the affected area.

8.2.4 Assure that all Re-entry personnel are properly equipped l with protective clothing, high range dosimeters, low range dosimeter,TLD, respiratory devices, and other protective ~

equipment as required.

8.2.5 Specify self-monitoring and decontamination procedures

~

for the Re-entry Teams.

> -.:- . . . - . . -- - - .. . . - .. 2 d Page 6 of 6 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100027E, REV. 5

8.0 Instructions

(Continued) 8.3 The Re-entry Team members shall: . .

8.3.1 Wear protective clothing and other protective devices and dosimetry as specified by the Radiation /RS Team Leader.

8.3.2 Unless unanticipated conditions are encountered, follow the pre-planned route into the af fected area, and perform the assigned jobs quickly and safely.

8.3.3 Monitor the dose rate along the route followed, and identify high radiation areas.

8.3.4 Frequently observe their dosimeters and withdraw ta a safe area before established dose limits are received.

8.3.5 When re-entry is completed, follow the self-monitoring and personnel decontamination procedures as specified by the Radiation Team Leader.

8.3.6 Record and report to the Emergency Coordinator or his designee the radiological conditions and extent of damage in the affected area.

8.4 The Emergency Coordinator and the Recovery and Restoration Team Leader shall evaluate the existing conditions and plan further actions as required.

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< .: . . .. . m.4 Paga 1 of 3 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT R6 EMERGENCY PLAN IMPLEMENTING PROCEDURE

1. 3100029E, REV. # 6

1.0 TITLE

DUTIES OF AN INDIVIDUAL WHO DISCOVERS AN EMERGENCY CONDITION

2.0 APPROVAL

Reviewed by Facility Review Group July 25, --

1975 Approved by K. N. Harris Plant Manager /-D- 1913 Revision 5 R 1ewed by FRG .. March 20, 19 _81 i Approved by ///bf40 V.P. Pwr. Ressag M.lS6__

i Revision 6 Re b Facilit eview Group Z ,. 6 7 19 > '-

Approved by 6 ></y//>/A V . P. Nuc . En g . g, y 19] V J

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3.0 SCOPE

3.1 Purpose This procedure provides the actions to be taken by an individual who discovers an emergency condition.

3.2 Defininitions 3.2.1 An emergency condition is an incident which could result in personnel injury and/or damage to plant components.

It may or may not be accompanied by high radiation or radioactive contamination. Examples of an emergency condi-tion include but are not limited to: - -

3.2.1.1 Fire or explosion.

3.2.1.2 Steam line break.

3.2.1.3 Unanticipated high radiation field.

3.2.1.4 Accidental release of reactor coolant.

3.2.1.5 Accidental release of radioactive liquid .

waste.

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. s Piga 2 of 3 ST. LUCIE PLANT '

EMERGENCY PLAN IMPLEMENTING PROCEDURE #3100029E, REV #6 DUTIES OT AN INDIVIDUAL WHO DISCOVERS AN EMERGENCY CONDITION 3.0 Scope (Continued)

~

3.2 Definitions (Cont'd) 3.2.1 3.2.1.6 Accidental release of radioactive waste gas due to rupture or improper valve align-ment in system piping.

3.2.1.7 Accidental release of chlorine gas.

~~ " ~

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

4.0 Precautions

All personnel should be continuously alert to detect any unsafe situa-tion which, if not corrected, could result in an emergency condition.

Strict adherence to existing operating and maintenance procedures and safety rules, and the exercise of good judgement could prevent the occurrence of an emergency condition.

5.0 Responsibilities

5.1 All personnel permanently or temporarily assigned to the St. Lucie Plant shall familiarize themselves with: - -

3.1.1 The contents of this procedure.

5.1.2 The locations of area radiation monitors and fire fighting equipment in, and the entrances to and exits from the areas in which they work. ,

5.2 All personnel shall notify the Nuclear Plant Supervisor of all -

unusual or emergency conditions.

6.0

References:

St. Lucie Plant Radiological Emergency Plan

7.0 Records

All significant information, events, and actions taken during the emergency period shall be recorded by the Emergency Coordinator.

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, . o Page 3 of 3 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE # 310029E,REV #6 DUTIES OF AN INDIVIDUAL WHO DISCOVERS AN EMERGENCY CONDITION

8.0 Instructions

An individual who discovers an emergency condition shall: . .

8.1 Take any immediate action he is qualified to perform that will aid in controlling and minimizing the effects of the emergency such as:

8.1.1 Extinguishing a small fire with fire fighting equipment located in the i= mediate area.

8.1.2 Locally stopping machinery that is contributing to the severity of the emergency (stopping a pump when the downstream piping was ruptured, deenergizing a burning motor, e'tc.)

8.1.3 Closing an upstream valve when a system pipe rupture has occurred.

8.1.4 Helping injured personnel from the affected area, if necessary, to minimize their exposure to further injury.

Do not attempt to move seriously injured or unconscious personnel unless failure to act will obviously place the victim in grave danger.

8.1.5 Warning other personnel in the affected area to withdraw to a safe area.

8.2 Notify the Nuclear Plant Supervisor. Give the following - ~

info rmation:

8.2.1 Type of emergency (fire, pipe rupture, etc.)

8.2.2 Location of emergency. .

8.2.3 Any injury to personnel, including obvious signs that ,

would indicate the seriousness of the injury.

8.2.4 Extent of damage to plant components.

8.3 Withdraw to a safe area.

8.4 If possibility of radioactive contamination exists, remain in a safe area until monitorec.

~

8.5 Follow instructions issued by the Nuclear Plant Supervisor (Emergency Coordinator).

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Page 1-of 10 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E REVISION. 3

~ ~

1.0 Title

ON-SITE SUPPORT CENTERS

2.0 Approval

Reviewed by Fptility Reviey Group i ? . <- . ;L r 19 Approved by /.Of///[m /#h V. P. Power Resource nt F4A M ,19 Y Revision 3 wdbyTRG[ - . u //

19EA Approved 5 v

/./ #wAU j'

V. P., Nuclear'Enerav ' f . <_f t

19 D 3.u dcope:

3.1 Purpose This procedure provides guidelines and responsibilities for activation and use of the on-site Technical and Operational Support Centers. This procedure describes interim facilities and shall be revised when permanent facilities are operational.

3.2 Discussion The activities of plant management, technical, and engineering support personnel are an important part of the overall site. . . __

response to an accident, and must be properly defined and logistically supported. The need for additional operational support personnel, other than those required and allowed in the Control Room, is also recognized as vitally important in properly responding to an emergency.

~~'-

The intent of providing Technical and Operational-Support Centers is to provide bases where post-accident emergency planning can be conducted and required operational support personnel'ean assemble for potential duty. Both centers will be in close communication with the Control Room via the PAX phone system, without disrupting, congesting, or confusing the activities in the Control Room by the physical presence of additional personnel.

I .. .. -. .._ .: . _

_ _. __ _d Prg: 2 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 3 ON-SITE SUPPORT CENTERS 3.0 Scoce (cont):

3.3 Description - -

3.3.1 Technical Support Center (TSC)

The TSC is located in the training classroom area, adjacent rc the Unit #1 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 a of the Service Building.

3.3.3 Communications Equipment The Control Room contains necessary telephone and public address systems for com=unications within and outside the plant. The Control Room also contains NAWAS 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 w' th the Control Room, OSC, the General Office Emergency Center, the Emergency Operations Fac,ility and outside agencies. _ _

It also contains an ENS dedicated telephone to the NRC Operations Center and the NRC Region I office.

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, in addition, Health Physics -

Department shall provide an NMC portable monitor to the Technical Support Center for radioiodine monitoring. This monitor can also be used for monitoring the control room.

4.3 The Emergency Coordinator shall recommend a suitable location other than the designated areas if radiological conditions warrant such actions.

- .- ._ nit Page 3 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 3 ON-SITE SUPPORT CENTERS

5.0 Responsibilities

5.1 The Emergency Coordinator is responsible for activating the TSC, activating the OSC, and arranging for scaffing 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 Adyisor _

(See 3100023E, Emergency 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 enking -

accident recovery decisions.

5.6 The QC 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.

6.0

References:

6.1 St Lucie Plant Radiological Emergen'cy Plan 6.2 E-Plan Implementing Procedure 3100021," Duties of the Emergency Coordiantor". /R3 6.3 E-Plan Implementing Procedure 3100033E, "Of f Site Dose Calculations". /R3 6.4 E-Plan Implementing Procedure 3100022E, " Classification of Emergencies". /R3 -

7.0 Records

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

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Page 4 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 3 ,

ON-SITE SUPPORT CENTERS

8.0 Instructions

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

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

. requirements.

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 /R3 request the delegation. The TSC staff shall provide technical /R3 support as requested by the Emergency Coordinator and shall 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 O'SC 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 condition no longer exists.

8.6 Alternate OSC .

In the event that the OSC becomes untenablo, the Emergency Coordinator shall designate an alternate location.

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= =>42 .: w.uL6:.zs?l C 9 9 Page 5 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 3 ON-SITE SUPPORT CENTERS TABLE 1 RADIOLOGICAL EMERGENCY 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 Dosimetars

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 .

1 16. Industrial First Aid Kit t

I 17. Step-Off Pads

j. 18. Plastic Bags J

4 l

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Page 6 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 3 ON-SITE SUPPORT CENTERS TABLE 2 EMERGENCY DATA, DRAWINGS AND DOCUMENTS MAINTAINED AT THE TSC - -

ST LUCIE PLANT

1. Plant Technical Specifications

2. Plant Operating Procedures

3. Emergency Operating Procedures -- --

4. Emergency Plan and Implementing Procedures

5. Final Safety Analysis Report

6. Drawings, Schematics and Diagrams e

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o l Page 7 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE No. 3100032E, REV 3 ON-SITE SUPPORT CENTERS TABLE 3 TECHNICAL SUPPORT CENTER STAFFING

~ ~

ST LUCIE PLANT i

I TSC Supervisor Primary: Technical Supervisor 4 Alternate Off duty STA (per 3100023E, Emergency Roster)

Operations Representative (Off duty Duty Call Supervisor or NPS) i Health Physics Supervisor Chemistry Supervisor Reactor Engineering Supervisor Maintenance Superintendent i Quality Control Supervisor Support Staff as determined by these supervisors l

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je3 D 8 Page 8 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 3 ON-SITE SUPPORT CENTERS APPENDIX COMMUNICATIONS EQUIPMENT 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 energency. 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) " State Warning Point Tallahssee, this is'St. 'Lucie'0ne

- ~

(State Warning Point will give a go-ahead) R3

" State Warning Point Tallahssee, this is St. Lucie One,

• , repeat

• Time

" Acknowledge, over." ,

(ALTERNATE METHOD) If NAWAS is unavailable-telephone State Warning Point at PHONE NO. 6 or Florida Marine Patrol-Alternate State Warning Point h,

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 ROUTE. -

State Warning Point Message Validation Time

• Announce the class as indicated by EPIP 3100022E

" Classification of Emergencies"

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.. 4 Page 9 of 10 EMERGENCY PLAN IMPLEMENfING PROCEDURE No. 3100032E, REV 3 ON-SITE SUPPORT CENTERS APPENDIX (cont)

A. Use of the NAWAS System (cont) - '

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

3. Low Population Zone A. The Low Population Zone will extend outward *Fros~each nuclear power plant for a radius of five (5) miles, and 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 center and extending outward in mile increments One through Five.

Contaminated area, extending outward from the nuclear plant, will be located and reported as discussed in E-Plan Implementing Procedure 3100033E, "Off-Site Dose Calculations." R3 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 frequenci.es allocated by the state Bureau of Disaster Preparedness. R3 _

, 2. The LGR control unit is installed in the Control Room, and TSC. R3 C. Use of the ENS (OPX) Telephone Network -

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 & Light, St Lucie Plant".

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.2: ==_;.: Ash Page 10 of 10 4

EMERGENCY PLAN IMPLEMENTING PROCEDURE No. 3100032E, REV 3 ON-SITE SUPPORT CENTERS APPENDIX (cont)

C. Use of the ENS (OPX)-Telephone Network (cont) - -

4. Make the notification.

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

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FLORIDA POWER & LIGHT COMPANY

-[

ST. LUCIE PLANT L_ t E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E REVISION 5 - -

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 5 Reviewe by F R G n Mau // 192.2.-

Approved by )Q(/I[] '/ / m , V.P. Nuc Energy /e d 197 D r u

3.0 Scope

3.1 Purpose

3.1.1 This procedure provides a method for estimating whole body and thyroid dose races and integrated whole body and thyroid dose for the area surrounding the plant out to ten miles.

3.1.2 This procedure provides a method of comparing dose results, release rates, and radiation levels in containment to Emergency Classifications Guidelines. .. . _

3.2 Discussion

. 3.2.1 The Emergency Coordinator, his designee, or the Chemistry Department representative will estimate thyroid and whole body dose rates for off-site locations using this procedure , ~

whenever releases occur during an emergency. ~

3.2.2 The Emergency Cootdinator, his designee, or the Chemistry Department representative will use the thyroid and whole body dose rate estimated to calculate integrated dose during the duration of the event.

3.2.3 This activity can be delegated to the dose assessment group in the EOF when it is manned and operational.

3.3 Authority

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

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. - . ~. a . .- . ... ~..- -...w.. ...2, Page 2 of 22 ST. LUCIE PLANT '

E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS

4.0 Precautions

None

5.0 Responsibilities

The Emergency Coordinator or his designee has the responsibility for directing that thyroid and whole body dose rate estimates and integrated thyroid and whole body doses are calculated following an accident whien involves a release of radioactivity.

The Chemistry Department representative shall make the estimates upon arriving at the scene at the direction of the Emergency Cotredinator.

6.0

References:

6.1 St. Lucie Plant Radiological Emergency Plan 6.2 St. Lucie Plant Radiation Protection Manual 6.3 " Bases for Accident Dose Calculations for St. Lucie Nuclear Power Plant." (Bases prepared by HMM Associates of Waltham, Massachusetts.)

7.0 Records and Notification:

Detailed records of meteorological conditions used to estimate dose rates, the estimated thyroid and whole body dose rates and the integrated thyroid and whole body doses shall be kept on the attached worksheets.

^ ~

As deemed appropriate by the Emergency Coordinator, the off-site

~

authorities shall be notified of:

1. Meteorological conditions (wind speed, wind direction, stability, and precipitation).

2. Projected thyroid and whole body dose rates and integrated thyroid -

and whole body dose at 1, 2, 5, and 10 miles, including sectors .

affected, and

3. Whether default values or actual measurements were used for dose estimates.

,... _ . . . - , .. . = . . . . . _ . .. : .. . . ' . . ..-2 2.!!

s .

Page 3 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS J

8.0 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 available release rate data source and use the indicated forms.

8.2.1 Effluent monitors available, use:

MET Data Worksheet - -- -

(

Effluent Monitor Source Term Worksheets 8.2.2 Containment High Range Radiation Monitor is available during a LOCA, use:

MET Data Worksheet CHRRM Source Term Worksheet 8.2.3 Chemistry-Grab Sample data is available, use:

MET Data Worksheet Chemistry Data Worksheet 8.2.4 If none of the above, use Default Value Method Using Past Loca Monitor and Forms:

MET Data Worksheet Post LOCA Monitor Dose Worksheet

~~

8.3 Calculate doses, essaulative dose and Actiod Guidelines 'using ~ ~

forms:

Dose Calculation Worksheet Dose Conversion Tables Action Guidelines Cumulative Dose Distribution Worksheet .

8.4 The Emergency Coordinator or his designee shall monitor release ,

rates and meteorological conditions to determine how frequently to update the dose race estimates. Dose rate estimates shall be updated if any of the following averages change by the amounts indicated below.over a period not to exceed 30 minutes:

1. Release rates increase by more than 25%.

2. Wind speed decreases by two classes or more.

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

4. Wind direction changes by more than 22.5 0 (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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the accident unless it is determined that releases of radioactivity have been terminated.

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..:. . .-- . ::n .:. . 1. a _.: ._ .:L . uAV Page 4 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5  !

0FF-SITE DOSE CALCULATIONS I

8.0 Instructions

(continued) 8.5 The Emergency Coordinator shall track integrated thyroid and whole body dose once each hour for the duration of the event as follows: . .

8.5.1 The average thyroid and whole body dose rates shall be determined for each sector from the Dose Race Worksheets completed for the hour of interest.

8.5.2 Update the Cumulative Dose Distribution Worksheet, Taole 2, by adding the thyroid and whole body dose rate determined from 8.3.1 for each applicable sector / distance block to the integrated dose from event initiation to the present for that -

sector / distance block.

8.5.3 Integrated doses for sector / distance blocks with zero estimated dose rate for the current hour remain unchanged.

Note: In reporting doses and dose rates, to conservatively accommodate the ef fects that could conceivably result from a postulated potential stabilizing ef fect of the Indian River, those residents in sectors K, L, or M (between SW and WNW of the facility), should be considered to reside at 1.0 miles.

8.6 Projections of doses and dose rates should be nade on the basis that the most recently estimated dose rates and their distribution will persist for two hours. Projecting dose rates for periods other than two hours should be made on an ad hoc basis using best available data on release rate estimates and subsequent meteorological -

conditions.

8.7 The results of Calculated Release Rates, Dose Rate, and Integrated Dose should be compared to applicable Table 3 - 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.

8.8 Dose conversion tables for distances 1 to 12 miles, by 1 mile in.crements, are attached as Appendix A for calculations of dose at other than 1, 2, 5 and 10 miles.

.._ .. .. . ._ . . . _ . . ._.m - - _:w _ _. _ n; ._ . _ t, cJA Page 5 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS METEOROLOGICAL DATA WORKSHEET Calculation for (Date) / / (Time)  : -

1. Determine stability class, using Delta T (A or B or C)

A. MET Tower O O OF F minus F = Delta T 200 tt 32 ft Check left column of Table at bottom of page.

or ._ .

[

B. West Palm Beach Airport Stability Class Wind Speed From 0 or C. Default (No Other MET Data Available)

Daytime Nighttime Class D F Wind Speed >4 to 9 >2 to 4 aph

2. Wind Speed (Average of most recent 15 minute period)

A. Lower MET Tower Sensor sph or B. Upper MET Tower Sensor sph or C. West Palm Beach Airport or D. Default .. -

l' 3. Wind direction (Average of most recent 15 minute period)

Same as 2A, 2B or 2C.

i l lD31ta T Ranges l Stab. l Wind Speed Range Groups in mph Wind From 9 O , >9 to 18 1 F. l Class l 0 to 2 1 >2 to 4 1 >4 to 9 >18 to 36 Definition j l < -1.6 A Extremely unstable l -1.6 to < -1.5 8 I I Moderately unstable j -1.5 to < -1.3 C '

Slightly unstable -

' Neutral

-1.3 to < -0.4 D S

-0.4 to < +1.3 1 E '

I l 'Sligncly stable j l+1.3 to < +3.4 l F 1

• l l l Moderately stable l l > o r = +3 .4 I G I I ) l l Extremely stable l

• -Night DEFAULT $ Daytime DEFAULT l

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..- _ . . .  : 'l 2A Page 6 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE 00SE CALCULATIONS EFFLUENT MONITOR SOURCE TERM WORKSHEET NOTE: Read CHRRM and compare to ACTION GUIDES (Page 14)  %

J

1. Determine sum of Noble Gas Release (Ci/sec)

A. Edit the 10 minute average file of the applicable release point (s) on the Eberline Control Terminal A (or B) output the data by:

1) Turn keyboard keyswitch ON with key.

ii) Press HIST MIN.

[

iii) Enter the CHANNEL NUMBER (CH #) from the table below, iv) Press ENTER, data prints in C1/sec even though labeled otherwise, v) Use the NEXT-TO-LAST value on printout and enter on table below:

CHANNEL OUTPUT DATA C1/sec l RELEASE POINT LOW RANGE MID RANGE l tilGH RANGE l CH # \ DATA CH # 1 DATA l CH # l DATA IPiant Vent '

0105 i 0107 0109 l lECCSA 0205 I O207 0209  !

l'ECCS B 0305 0307 0309

,Fuei Bldg. 0405 0407 1 0409 Sceam Line A l N/A 1 0501 l 1 N/A Steam Line B l N/ A l 0502 l l l N/ A

2. Determine flow correction value from the below table. Check as appropriate.

PLANT VENT FUEL BUILDING HVE 10A (or 10B) running 1.0 HVE 15 and tiVE 17 running 1.0 HVE 10A and 10B running 2.0 HVE 17 only _.

- 0.34 HVE 10A (or 10B) and Cont Purge HVE 1.22 HVE 17 and HVE 16A (or 16B) 1.0 HVE 10A (or 10B) and HVE 6A (or 6B) 1.06 HVE 17 and HVE 15' and HVE 16A (or B) 1.66 HVE 10A (or 10B) and EVE 6A and 6B 1.13 HVE 15 only 0.66 No HVE 10A (or 10B), but HVE 6A (or 6B) 0.05 HVE 15 and HVE 16A (or 168) 1.32 No HVE 10A (or 10B), but HVE 6A and 6B 0.13 l

. .- . - .. . . .-.e-. . . .. a .. . z .x. . ... ~ . ca - w.u a h .;:1A Page 7 of ST. LUCIE PLANT i E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 l [

OFF-SITE DOSE CALCULATIONS {'

EFFLUENT MONITOR SOURCE TERM WORKSHEET (continued) m

)

3. Enter the highest upscale channel data for the release points flow correction y.wa.

l RELEASE POINT l RELEASE RATE l FLOW CORRECTION l ADJUSTED RATE l l Plant Vent l l l l lECCS-A \ l 1.0 l l lECCS-B l l 1.0 l l l Fuel Building l l l __ l_ g l Steam Line A \ l 1.0 l l l Steam Line B l l 1.0 l l

4. If a Loss of Coolant Accident is occuring, correct Plant Vent for bypass: Adjusted Plant Vent (X) 1.14 =

5. Calculate Noble Gas and Iodine Release values.

Carry from Step 3 (and 4) and Noble Gas release values and enter in table below. Multiply left to right and sum Nobles and Iodines down.

RELEASE POINT l ACCIDENT TYPE NOBLES CI/SEC X IODINE FACTOR = IODINE CI/SEC' Plant Vect l Steam Line Break l 1.4 i Plant Vent l S/G Tube Rupture 1 1.24' E - 6 l Plant Vent I LOCA .014 l lECCS-A l LOCA -

.014 l ECCS-B i LOCA .014 i l Fuel Bldg. Fuel Handling I .06 l l Fuel Bldg. Cas'I Drop l 1.54 l Steam Line A S/G Tube Rupture l 1.24 E - 6 I

! Steam Line B S/G Tube Rupture l 1.24 E - 6

~~

Total Nobles C1/sec Total Iodines Ci/sec ' _

6. Take the total Nobles and Iodine release rates to the Dose Calculation Worksheet.

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Page 8 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS V E CHRRM SOURCE TERM WORKSHSET #

t NOTE: Read CHRRM and compare to ACTION GUIDES (Page 14)

1. Read CHRRM and aote time af ter trip.

CHRRM R/hr Time since trip hrs.

2. Select conversion value. If between ti:ne af ter trip times, select next higher time.

CHECK TIME, HR. VALUE CHECK TIME, HR. VALUE 0 5.00 E-7 4.0 _ .6 . 2 5. E-6 .-

.5 1.00 V.-6 8.0 1.25 E-5 1.0 1.67 E-6 24.0 2.22 E-5 2.0 3.33 E-6 If >24 nrs., use 24 hr. value

3. Convert CHRRM to Core Fraction Airborne (CFA)

CHRRM (R/hr) Conv. Value CFA I =

ll tiI 't'l 'I -

!*I ' l'I -

I 'I t i

4. Find Reduction Value (RV) \ ' ' ' ' ' 8 ' ' ' ' _ ' -

for Noble Gas, from graph. s.s

\ ',

3

', tta: Use hgtruling meofvalue me calculatim of R carrougonuing 2erlos. to me Time used brs. 33 y , Per esmate. men catasisting asse g , for me perlos fra I s 2 neurs

• RV I' '\ ' "'"* ** '""IO * " *

• ei i i i . . i i . i 3 e e I ,~ ' ', \

5. Iodine Conversion Value (ICV) ', l l l l l ', l ', l Check used value. I 8' , . i i . ,

.s . . i . .

e ise i . e i i e i . i . .

Safeguards working ' ' ' ' ' ' ' ' " '

.6 '. 4ixiie i i i e i e i e . .

, , i N i i . . . i i - 1 No Safeguards 1.6 ,. , , , ,g , , , , , , ,

s.2 , , , , , , , , , , , ,

i i i e i i i i 88 .. . . , , e . . . . . .

i i ie i . . i i i i i . .

s 2 4 s is rz i4 to ts a s :4

6. Calculate Release Values nau unas ruser tris (nrn Nobles CFA X RV X Cony Value = C1/sec X 40 Noble Gas Iodines CFA ICV X 1.0 X Iodines

7. Take the Release Values to the Dose Calculation Worksheet.

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i Page 9 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS g ,

CHEMISTRY DATA WORKSHEET NOTE: Read CHRRM and compare to ACTION GUIDES (Page 14)

1. Acquire sample Assay Data.

Iodines and Noble gas concentrations in uCi/cc and enter in table below.

2. For Plant Vent and Fuel Building, check Vent Correction Factor.

PLANT VENT FUEL BUILDING HVE 10 A or 10 B running 1.00 HVE 15 and 17 runnias -- -

1.00  :

HVE 10A and 10B 2.00 HVE 17 only 0.34 HVE 10A (or 10B and 6A (or 68) 1.06 HVE 17 and HVE 16A (or 163) 1.00 HVE 10A (or 10B) and Cont Purge 1.22 HVE 17 and 15 and 16A (or 168) 1.66 HVE 10A (or 10B) and 6A and 6B 1.13 HVE 15 only 0.66 No 10A (or 108), but 6A (or 6B) 0.06 HVE 15 and 16A (or 168) 1.32 No 10A (or 10B), but 6A and 6B 0.13

3. Calculate Release Rates.

GROSS l FLOW VENT l CALCULATED, CI/SEC TIME PATHWAY TYPE uCI/CC l CONST CORRECTION l NOBLES I IODINE l ECCS-A l Gas l l 15.3 1.0 l l l l Iodine l l ****** l l ECCS-B j Gas l l 14.7 l 1.0 l l l Iodine l l l ****** l l Plant l Gas l l 44.1 l l ,

Vent l Iodine l l ,

l ****** l { - _

Fuel Gas 1 6.95 l Bldg. Iodine l ****** [

Total Noble Total Iodines

4. Take total Noble and Iodine release rates to the Dose Calculation Worksheet.

l l

l

.._ : . .-.2 :__ . m. u .1 , _ . . _ _ ,_m.__. . n .2 . merm.nc: a_.a s #' R:233 Page 10 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS DOSE CALCULATION WORKSHEET

1. From MET Worksheet: Stability Class' 0

, Wind Speed , From

2. From Source Term.Worksheet: Ci/sec Noble Gas Ci/sec Iodine

3. Calculate Dose Rates. Enter into table below:

NOTE: Dose factors found on pages 12 and 13.

l WHOLE BODY li TJtYROID E l r RANGE NOBLE GAS MULTIPLY BY MILE 3 CI/SEC (X) DOSE FACTOR (=) MREM /HR I CI/SEC (X) (=) MREM /HR 1I l l 2 l l l I 1 5 I l 10 ENTER DOSE RATE RESULTS FOR INDICATED SECTOR & AIlfACENT SECTOR ON EACH SIDE:

Wind Dir. l Downwind l mrem / hr Whole Sody @ 211e ll mrern/ hr Thyroid @ mile Indicated i Direction 1 l 2 5 1 10 ll 1 2 5 l 10 l 180 iN ALPHA I ,l l l 202.5 l NNE BRAVO l 1 1

' l l l l 225 l NE CHARLIE l l l l l 247.5 ENE DELTA l t I i: i ( l 270 1E ECHO l l l l l l l l 292.5 l ESE FOXTROT i l l 1 -l- 1 -

-l l 315 l SE GOLF 1 6 I i I l

337.5 l SSE HOTEL [  ! l l 1 l l l l

) 000 lS JULIET i l l l l l . 022.5 l SSW KILO *.

l { *l t 1

{ 045 l SW LIMA *:1 l l *l l l l i 067.5 1 WSW MIKE *l i l l *j l l. [

d90 iW NOVEMBER l 6 l l [

l 112.5 l WNW PAPA l l l l l l

135 l NW QUEBEC l t l l j 157.5 l NNW ROMEO l l l l 1 i I l [

l i

• Indian River Residents assumed to live at i mile and

! evacuation criteria shall be based accordingly.

COHPARE DOSE RATE RESULTS TO TABLE 3 ACTION GUIDELINES f

I

! Also enter Dose Rates into Plant / Radiological Emergency Checklist l Emergency Information Checklist.

l l

i REMARKS:

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Page 11 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 ,

0FF-SITE DOSE CALCULATIONS t

" .5 POST-LOCA MONITOR DOSE WORKSHEET

1. , Windspeed "

From HET Worksheet: Stability Class , From PLM Noble Iodines in Ci/sec mR/ hr C1/sec With Safeguards No Safeguards 30 to 90 *** *** ***

60 to 190 2 .03 .1 100 to 1000 10 .14 .4

>1000 40 .60 1.6

• • • = Negligible Release Race

~

NOTE: Verify PLM readings with portable dose rate instrument $ before going to step 3.

3. Calculate Dose.

NOTE: Dose factors found on pages 12 and 13.

WHOLE dODY tl THYROLD

RASGE NOBLE GAS MULTIPLY BY l MILES CI/SEC (X) DOSE FACTOR (=) MREM /HR I I CI/SEC (X) (=) MREM /HR l 1 l 2 l 5 l l l 10 l l l e

ENTER DOSE RATE RESULTS FOR INDICATED SECTOR & ADJACENT SECTOR ON EACil SIDE:

l l Wind Dir. I Downwind ares /hr Whole Body <! mile ll mrem /hr Thyroid (! mile -i

( ,_ Indicated Direction 1 1 2 l 5 l 10 1 l 1 l 2 l 5 l 10 l 3 1 180 1N ALPHA l l l l l l l r

l 202.5 i NNE BRAVO l , l I l i

( l 225 NE CHARLIE l l l l l l _

h 247.5 ENE DELTA I I II l l 270 E ECHO i l l I i l l .

292.5 I ESE FOXTROT I I l i l l l 315 '

SE GOLF l l l' l l l 337.5 l SSE dOTEL '

I I l

000 S JULIET i 022.5 SSW KILO l

• 1 *' '

l 045 SW LIMA

• l ' * '

l 067.5 I WSW MIXE * ' *'

1 090 W NOVEMBER I l l l l l 112.5 i WNW PAPA 135 NW QUEBEC l 157.5 l NNW ROMEO 1 I l l ll l l l l

• Indian River Residents assumed to live at 1 mile and evacuation criteria shall be based accordingly; ,

COMPARE DOSE RATE RESULTS TO TABLE 3 ACTION GUIDELINES Also enter Dose Rates into Plant / Radiological Emergency Checklist Emergency Information Checklist.

REMARKS:

l e -

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. . .2 Paga 12 of 22 ST. LUCIE PLANT ,

E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVI3 ION 5 0FF-SITE DOSE CALCULATIONS 4 I"_

[

DOSE CONVERSION TABLES mrem /hr STAP.ITY CLASS A WIND SPEED GFfUPS, MPH RANGE l 0 to 2 2 to 4 l 4 to 9 9 to 18 18 to 36 l-MILES l WB THY WB THY l WB THY ,

WB THY ,

WB THY ['

l 1 l1.25 3E+3 l .416 1E+3 -l.208 500 l .104 250 l .052 125 l

~

l 2 l .668 1.6E+3l .223 534 l .111 267 l .0556 134 l .0278 66.S l l 5 l .360 863 l .120 288 l .0559 144 l .0300 71.S-l 015. 36 l r l 10 l .360 863 l.120 288 l.0559 144 l .0300 71.9 l .015 '36 l STABILITY CLASS B WIND SPRED GROUPS, MPH l RANGE l 0 to 2 l 2 to 4 1 4 to 9 1 9 to 18 l 18 to 36' l l MILES l WB THY l WB THY l WB THY l WB THY l WB ' THY l g l 1 l8.9 2.1EM l 2.97 7100 l 1.43 3600 l .742 1300 l .371 690 l l 2 l2.26 54100 l .752 1800 l .376 902 l .188 451 l-.094 226 l l 5 l .702 1680 l .129 311 l .065 155 l .032 77.6' l .016 ~ 38.8 l l 10 l .650 1560 l .120 288 l .060 144 l .030 71.9 l. 015 36.0 l

~ ~ ~

STASILITY CLASS C WIND SPEED GROUPS, MPH RANGE O to 2 l 2 to 4 l- 4 to 9 l 9 co'18 l 18 to 36 l MILES ,

WB THY WB THY l WB THY l WB ..dY l WB THY l l 1 l22.5 5.4EM l 7.51 1.8E+4l3.75 9010 l 1.88 4i10 J. 939 2250 l - _

l 2 l6.54 1.6EM l 2.18 5240 l 1.09 2620 l .545 1310- l .273 654- l ,

l 5 l1.81 4340 l .417 1000 l .208 500 l .104 250 l .052 125 l l 10 l1.27 3050 l .225 541 l .073 187 l .039 93.6 l .020 46.8 l STABILITY CLASS D WIND SPEED GROUPS, MPH ~

RANGE O to 2 '

2 to 4  ; 4 to 9 9 to 18 18 roJ36 * -

MILES ,

WB THY WB THY i WB THY ,

WB THY WB THY

[ 1 l46.2 1.1E+5l15.4 3.7E+4 l 9.14 2.2EM l 5.40 1.3E+4l 2.70 5480 l l 2 l18.9 4.5E+4 l 6.31 1.5E+4]3.51 8410 l 1.96 4710 l .982 2360 l l 5 l5.5 1.3E+4l1.83 4400 l .964 2310 l .511 1230 l .255 613 l l 10 l2.1 5030 l .70 1680 l .36 863 l .186 446 l 093, 223 l

_ _m__ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _

_. . _ . . . - .. ' 'ci Page 13 of 22

~

ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS DOSE CONVERSION TALBES mrem /hr per C1/sec

/

)

(continued)

STABILITY CLASS E a WIND SPEED GROUPS, MPH l RANGE 0 to 2 l 2 to 4 4 to 9 9 to'18 l 18 to 36 l l MILES i WB THY WB THY WB THY i WB THY WB THY l l 1 l70.6 1.7E+5l 23.5 5.7EM l 15.9 3.8EMl10.2 2.5E+4j 5.1 1.2EMl l 2 l33.1 7.9EM ] 11.0 2.7E+4l6.73 1.6E+4 l 4.05 9710 l2.02 4860 l ,

l 5 l 11.6 2.8E+4 l 3.87 9280 l 2.15 5150 l1.18 2840 l .592 1420 l l 10 lS.07 1.2E+4l 1.69 4050 l .897 2150 l .475 1140 l .237 570 l STABILITY CLASS F WIND SPEED GROUPS, MPH l RANGE l 0 to 2 l 2 to 4 l 4 to 9 l 9 to 18 18 to 36 l l MILES l WB THY [ WB THY l WB THY l WB THY ,

WB THY l l 1 l 125 3E+5 l 42 1E+5 l 31 7.4E+4l 19 4.5E+4l 9.5 2.3EMl l 2 l 64 1.5E+5l 21.3 5.1E+4 l 14 3.4E+4 l 8.53 2E+4 l 4.3 1E+4 l l 5 l25.4 6E+4 l 8.5 2E+4 l5.0 1.2EM l 2.9 6660 l 1.4 3330 l l 10 l12.1 2.9 EM l 4.0 9670 l2.2 5300 l1.2 2840 l .60 1420 [

STABILITY CLASS G WIND SPEED GROUPS, MPH RANGE O to 2 2 to 4 4 to 9 9 to 18 18 to 36 l MILES WB THY WB THY WB THY WB THY ,

WB THY l l 1 l 196 4.7E+5l65.3 1.6E+5l 57 1.4E+5l 31 7.4EMT 15.4 3.7E+41 l 2 l 111 2.7E+5] 37 8.9E+4l 28 6.7E+4l 17 4.06t4 l 8.3 2.0 E+4 j l 5 l 52 1.3E+5l 17 4.1E+4l 11 2.7E+4[ 6.3 1.5E+4] 3.2 7540 l l 10 l27.5 6.6E+4l 9.2 2.2E+4l 5.4 1.3E+4l 2.9 6980 l 1.5 3490 l m.

V. o.. _. .:. . . . . . . . .. - . . ... n : ..: a.-.. -~ .  : h- -I Page 14 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS ACTION GUIDELINES ..

For the Containment High Range Radiation Monitor (CHRRM) . . u--

Case Instantaneous Event Classification l CHRRM l 21.47 E5 R/ hr i General Emergency l CHRRM l 17.3 E3 R/ hr Site Area Emergency CHRRM i <10 R/ hr Negligible As back up to the above/if using POST LOCA RAD MONITOR (or survey meter at saue).

l POST LOCA l >1000 mR/ hr l General Emergency l ._ .. . r l POST LOCA l < 60 mR/hr l Negligible l 1

For Noble Gas Release Rates i.e., Ci/sec from the Site i

i Case Instantaneous Situation Gas Rel. Rate { <0.083 C1/sec IWithin Technical Specification-No Action l l Gas Rel. Rate 10.083 but less Unusual Event-Tecn. Spec. possibly exceeded-than 0.83 Ci/sec see ETS-B & take steps to reduce rate l Gas Rel. Ratei 10.83 C1/sec l ALERT CLASSIFICATION For Dose Rate Results Or Duration or Duration Case Instantaneous For 2 minutes of For 1/2 hour of Situation i If Whole Bodyl 1500 150 Site Area - - -

@ 1 mile is N/A ares /hr mrem /hr Emergency If Whole Body. l i Generai

@ 1 mile is >1000 mres/hr l N/A N/A Emergency If Thyroid l >2500 1

>250 Site Area

@ l mile is N/A ares /hr arem/hr Emergency l ,

~

j For Cumulative Thyroid Integrated Dose If Thyroid Integrated l Dose 0 1 mile using >5000 arem then General Emergency actual met data 5

e i

-- e n - n-e e

..-..r. . . . . . . _ - - .. ~ ,-.

..w _ ., ... . . .. - _ . - . . .._.- .. ...- ......;...~ :C Page 15 of 22 ST. LUCIE PLANT l E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 1 0FF-SITE DOSE CALCULATIONS i

CUMULATIVE DOSE DISTRIBUTION WORKSHEET g i f

, Time release assumed to occur:

~

Time through which this distribution applies:

I l Met Station I i Whole Body Dose (ares) j 1 Thyroid Dose (ares) l Wind Direction Downwind Downwind Distance (miles)l Downwind Distance (miles) l (As Read) Direction 11,1 i 1l M l 1 2 l 1l 10, I l ll l l

! 180 N ALPHA I I l l 1 )

} 202.5 NNE BRAVO 1 l l l ll l _ _ l.. l e 225 lNE CHARLIE i I l ll l l l l 247.5 ENE DELTA l I I I l 1 l l 1 270 E ECHO '

i it I ) {

i 292.5 ESE FOXTROT l l l l I( l l 315 SE GOLF 1 l l il l 337.5 SSE HOTEL l I I ( l }

! 000 S JULIET I i l

022.5 SSW KILO * *-

]  ! l l 1 045 SW LIMA i

• l l

067.5  : WSW MIKE *l 1 l *1 l l

090 W NOVEMBER { l i j 112.5 QWNW PAPA l l l ll l l {

l 135 lNW QUEBEC l l l t

l l l l l 157.5 lNNW ROMEO l l l ll l l l

• Indian River Drive residents assumed to ;,1ve 9 1 mile and Evacuation criteria shall be based accordingly.

{ COMPARE RESULTS TO TABLE 3 ACTION GUIDELINES i

Date and time this worksheet was completed

Date Time .

l ... -

~

l REMARKS:

2

. . . - . . - . . . =.... 2.:.

Page 16 of 22 ST. LUCIE PLANT E-PLAN IMPLF.MENTING PROCEDURE 3100033E, REVISION 5 l OFF-SITE DOSE CALCULATIONS I 4 I

APPENDIX A

[

DOSE FACTORS FOR STA3ILITY CLASS A

/_

- r

'tDEI 4G.E 33f J1EE RIt 57ABL7f ass 4 - (MelMt). 3AEG JI 41.3 C:/SEi: GI33IDI Mit JEl

'SteiDEI DISTAIEE - 3!123 (M*H I 2 3 4 3 6 7 8 7_ _ to , 11 12 C

0-2

1. 3 *00 6.45-M 4.4241 140E-M LalE-M L40E-M th1E-11 3.40E-M L W M 3. 4 31 3.40E-M 2.4@

2-4 4.14E41 L&M 1.!AE-11 1.35-M !.. W M 1..W31 1..W11 1..'UE-M 1..W11 1..W)1 1.::lE-M 1..'tEMI 4-9 2.3rr01 1.115-01 7.73-2 5.79E-2 LME-u 3.79E-u .3.79E-U LME-M LME-u !.796-4 3.ME-4 f.79E-n 9,18 1.3aE-11 LSE-u L364-2 10@ u L30Ev02 3.3@ 2 3.0E-2 L30E-4 3.*4E-U 3.04-U L;E-U 3.Xr-u IM

! WU L75-2 1.XIE-4 1.30E-2 1.30E-E 1.$EM2 1.2E-2 1.50E-2 1.3@ 2 1.24-2t.20E-n 1.3Yr U 4 DEI 'IfflE13 : DIE At STABLif US$ 4 - (MetMll. 3AEG GI 41.3 C:/SE GISSIGI Mit 9 51 lGIAfDEI 3ISTABE2 - MILZ5 (NM) 1 2 3 4 3 6 7 3 '

7 to 11 1 ._

0-2 179E4C 1.4@03 1.11543 L43E+02 L43E42 L4E 02 1.4.*t 02 L4:IE42 L4242 3.ME-02 L4@ M 3.43E 2-4 7.7@d2 L'AE*02 17@e2 *.3lE42 2.JW42 2.JW42 2.JEEN2 *.3lE-02 2.3Erro2 :.3lE42 2.31E M

4.2902 L&&G2 1.3542 1.4442 !.4442 1.4@02 1.4@C2 1.446-02 1.4@02 1.44E 02 1.W t 4@0 .

9-18 2.J502 1.'AE42 7.3E41 7.17E41 7.17EN! 7.17641 7.17E*01 7.176 01 7.17E41 7.17E*01 7.1 i

IM

1. 3 4 2 6.4aE*01 4.43E+01 1 4 @ 01 3.4 @ ct L o @ 01 L4@01 3.40E01 2.act-01 3.o0E 01 l

l

y

~

-r y

.a Page 17 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PRCCEDURE 3100033E, REVISION 5 .

F i

0FF-SITE DOSE CALCULATIONS L I APPENDIX A

/

/

DOSE FACTORS FOR STABILITY CLASS 3 j j/

-6 a i t

l WG.E II!Y ISE FUt STABILITT CAi3 3 - OflEMel. IA3ED GI 41.3 C:/Ei: CitS3IQt ATE WDS "7GD 3naEDS DIS 7tJCI - MILE 3 (m) -- -- -

.r 1 2 3 4 5 6 7 3 7 10  !! 12 f

0-2 3.7 @ 00 2.2&E*00 1.11540 3. 5 -01 7.0241 LSE41 6.30E-11 L30E-)1 L5cE-31 6.3E-31 L50E-31 6.3E-01 2-4 2.77E40 7. 3 2 -21 L;5-31 1.39E41 1.226-21 1.25-01 1..W)1 1. 0 5 -11 1..%)1 1..":E41 1..%)1 1..W11 4-9 1.4E+00 17&E-11 1.46E-31 9.44E-22 6.47E-R L796-4 5.796-72 5.79E-U !.79E-U LhE-12 L79E-72 !.7M-n l HS 7.4 2 -11 1.3E-31 3.35-u 4.72-72 3.*E-72' 3.30E-E L:cE-72 3.0M-4 100E-U 100E-M L;CE-u *:. ace-2 IS-E 3.7*.E-)1 9.8)E-72 4.t?E42 * ~&E-02 1.42-M !.30E-12 1.!M-r1 1.30E-72 1.50E-M !.3E-u 1.5CE-72 1.35-2

?)fmOID 335E FGt STMILITT ".:.Mit 3 - QWEMR), 3ASED GI 41.3 0 /SEC E4IS3IJ1 ? ATE EDS 3'EED ;13selDC lIS77M2 - 6 .

l (m) . -

l 1 2 3 4 5 6 7 8 9 10 11 . 12 -

>Z 2.1 @ o4 L otf-43 2.42*c3 2.cei+c3 1.4aE43 1.3&E*at 1.!43-03 1.Sii,c3 1.3&E.03 1. &E-c3 1.!4E,03 !.3&Eva3 2-4 7.12+03 1.3@c3 3.S+02 4.3X+42 Lite 42 2.3E-02 2.3sE*02 2.3E-02 2.3aE42 2.JIE-02 2.3aE42 2.Jit,c2 t

f 4-*

14E+03 7.J2442 4.32+42 2.2242 1.3542 1.4@02 1.MG42 1.4@o2 1.uG42 1.4@02 1.uE 02 1.us.02 .

l l MS 1.7943 4.3tE*a2

• Otf+02 1.12+02 7.7&E41 7.t?t+01 7 t?t+01 7.t?t41 7. t?E*01 7.t?E 01 7.1 5 01 7.1541 1

IS-E 6.*cE+a2 2. aE42 1.J1E+02 L4sE*01 LJ@01 3.4CE-01 2.;dEact L4CE*01 L 4GE 01 0. Wra41 3.40E-01 :.lWE41 l

i e . - - - - - -

o., a . ~.. & s . , .- ,-n. ... l N f

Page la of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 I

0FF-SITE DOSE CALCULATIONS ,Ms

{'

-e-o '

=

APPENDIX A /

DOSE FACTORS FOR STABILITY CLASS C , j~

i

'acJ 3 turf Jost rGt STABILTf *.USS C - (NIEM/Ht). 3ASG 2 A 1.3 C /E MSS 3 Mii WDC 753 33IaiDS 31STTdC2 - MILZ3 (M) 1 2 3 4 5 6 7 3 i2 7 _. . to _

11 e 1-2 2.1E41 6.34E*c0 1 1 5 4 0 2. :9 00 1.31&oo 1..*:E*)0 1.02+00 1. 0 & 00 !. :"c*-00 1.Oi.uo I. rc*00 1. 7c-00 2-4 7.31E-00 1 : @ 00 1. 3 *)0 6.24E41 4.1541 13E41 2...T-31 2. 7E-11 2. 3 41 :.;5-31 2. ; 5 -31 L:5-11 4-9 3.7 & oo 1.3 9 00 L 5-21 115-31 2.3EE-31 1.3E-11 1.1 5 -01 7.24 3..*1E-i2 7.JE-n 7.775-n 7.??E-U 7-18 1.3@co 5.45-11 2.ME-)t 1.231 1. 31 7.49E-n 5.66E-n 4.7:iE-n 4. Mi-n, LJai-n 3.33E-n 3.32*-n

3-M  ?.0fE-11 2. .~5-21 1.01E-11 7.3E-n 5.21E-)2 3.74-n 2.3lE-n 2.dE-n 2.;5-n 1.75-u 1.77E-n 1.ME-U VDS MISID 305E FJt 5774IL 7Y CUSS C - (.9EM/Ht). 3ASE $141.3 C:/SE: 333IGI WJ PEG 33stfDS 3ISTANCE ,1ILES (m) 1 2 3 4 5 6 7 3 7 to 11 12 l . -

3-2 5.4tE*04

1. rc 04 7.SE+CI L31&G3 4.08E*n 3.4EE.c3 3. :E*23 3.1E-43 3.35-43 3.3*n 3.3+23 3.5-n 24 1.3 5 04

!.2@c3 2.35 c3 1.35*I3 1.3@e3 7.1@o2 !. GE*02 5.4tE*02 L41&o2 .415-42 !.41&o2 !.4tE-n M

7.3@43 2.ME*G3 1.1&E+03 7.49E42 !.3@c2 L 9E*12 2.75*02 2..H. 2.34&c2 1.55 02 1.rt,02 1.37E,02 9-18 4.31E+03 1.31E+43 6.35 42 175+G2 2.35*02 1.J502 1.3E*02 1.15 02 1.0242 7.3E*01 f.3 9 01 7.73E-01 -

IS-M 2.3+43 6.3@02 L15*02 1.25402 1.3+02 f.7@01 6.3cE*01 !.7 4*01 L;5 01 4.43E.ot 4.2?E41 3.T;E41 e

. :s'

. .a

. e l

cage 13 of 22 ST. LdCIE PLANT I E-PLAN ;MPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS l

l APPENDIX A DOSE FACTORS FOR STABILITY CLASS D e

' DELE 30DY 33EE fut 37AILT C:. Ass 3 - (MeUHt). 3AEED GI 41.3 C:/EC 2I55*01 Mit M

4 7E5 JosalDe 31574E2 - 3I1.!3 3

(frM) i f 2 3 4 5 6 7 3 7 to 11 ':

0-2 #

4.63+01 1.39E41 1.1 @ ot 7. 44E*00 3.3 @ 00 4.rE40 3. G -00 2.371H30 .

• 5 50 red) 1.3 5 00 1.76E-00 2-4 1.34 01 6.31600 3.4aE-00 2.49600 1.3 2,00 1.43-00 1.15&oo 7.23-n L10E-11 6. 7'E-M 6.1 E-M !.3EE-n 1

J i H 7.14E*00 1:1&oo 1.7@00 1.02+00 7.Wn 7.44E-n L?W-M A.74-)1 4.WH 140E-11 0.1; Pot 0.:3-31 l .

N.3 L 40E40 1.76E-00 1.6 7.095-31. L11E-n 3.715-31 3.12-n 2.37E-n

• ITa-n 1.36E-n 1.5"E-n 1.56E-M i

! 13 %

• 7@00 7.33-n L4tE-M L34E-11 2.35-31 1.76Tr-n 1.56E-31 1.3E-11 1.08E-)! 7.3E-72 3.1;E-02 7.73E-12

'~~ ~ ~

M *}fffE3I3 3EE r~3t 37ABI! T C. ASS 3 - (NIElt/Ht). 3AEED W 41.0 C:/SEC 2I33I01 Mit

! TED 33asiDe 31372E2 - MII.E3 arm t 2 3 4 5 6 7 3 7 to 11 12 0-2 1.11E+05 4.54E44 2.4E+04 1.7%C4 1..'2,04 1.;&os 3.."Wr*c3 6.3E03 L32-c3 3.:@o3 4.44E-c3 4.; 2-c3 .

2-4 L @os 1.315t04 3.23+43 L775+a3 4.4@03 L424 2.76E 43 2.3E*a3 1.74*c3 1..E03 t.:GE c3 1.41&C3 1

'44  :.1?E+44 3.41E+03 4.7"E+43 11543 2.;1&c3 1.7?E+43 1.43E*23 1.1 5 03 1.00E-03 3.4G02 7.5cE,02 7.75,02 i

P-18 1.J @ o4 4.71E+43 2.o@c3 1.7@a3 1.2243 7.09002 7.5@02 6.17&o2 LM 4.44rro2 2.7342 3.74 02 ^

l IE-E 6.4E943 L *JE*C3 1.32$43 N 6.1*E*d2 4.7%C2 173*02 L.M LJ0E-02 L 2 02 1.76Tr 02 :.37"c 02 f

- - : . d_

Page 20 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS 2 i a

APPENDIX A DOSE FACTORS FOR STABILITY CLASS E

/

/

~~

l M 4G.E 33r 335E A3t STABIL;TT C. ASS E - (Pfel/Ht). 3ASG 2 41.3 CAE a133I04 RATE YDe IPEED 358elDe 31377M:Z - MILi3 f.TH) 1 2 3 4 5 6 7 3 7 to 11 12

-- . . c

. 0-2 7.04 & 01 3.21&01 2.1 @ 01 1.31541 1.14E,01 7.3lE40 7.7 5 00 6.K & o0 L74E40 5.07E-00 4.!!&00 4.04 & 00 2-4 2.2+01 1.1 @ 01 6.79000 3.3lE,00 3.37600 3.12,00 2.9E-00 2.215-00 1. 7 2 ,00 1.47600 1.3 5 00 1.05+00 4-9 1.29601 6.7140 4.07Edo 2.3@o0 2.1540 1.7:P oo 1.416 00 [.19E-00 1.02 40 3.77E41 ,7. %)1 7.13-11 7-!8 1. 2 +01 4.05 40 2.05,00 1.37600 1.15+00 7.3E-31 7.!9E-11 6.*AE-)1 L 45-11 4.75-31 4. DE-31 3.72E-31

. j 13-% 1 : @ 00 2. 2 600 1.17 & 00 7. 775 -11 L7241 4.45-11 3.7541 3.:E 2.7"E-)! 2.07"c41 L;CE-11 1.115-31 i

7)mIOS 305E F3t STABILITT C. ASS I - (.1et/Ht). 3ASED 3 41.3 CMEC O!!S3:GI 7 ATE VDe

! PEE 3 338EfDS 3tS77JE2 - 3ILi3 f.Yt0 i

1 2 3 4 5 6 7 8 9 10 11 12 i _

0-2 1.7@c5 7.7+04 133E*04 L41E+04 2.7504 2.24E*04 1.77E 44 1.39604 1.;8E44 1. 2 04 1.0604 7.7 3 -03 24 L4544 2.444 1.4GE*04 1. S O4 7.2503 7.4E,03 6.2,03 Late-43 4.4tsc3 4.05.c3 3.415,c3 3.2,.a 1

4-f L31E+04 I.E&o4 7.74E+GI 4.3:E*c! 5.15+c1 4.;@c3 3.3E+c3 2.35+03 2.44E+03 2.15a3 1.71643 1.716c3 P !8 2.45+04 7.715,03 142+c3 L32+03 2.3643 2.3,43 1.32403 1.33&c3 1.21243 1.14&G3 1.012 ,a! 3.796 02 -

'6E 1.22+44 4.34E*a3 2.31& a! 1.715,a3 1.42+4R !.12,03 f.10E42 7.442 6.'AE-02 LT@c2 !.2-02 4.4502 l

l

^ ~

. :- ==$

Page 21 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS e i APPENDIX A E '

DOSE FACTORS FOR STABILITY CLASS F

_1 JEli 31I17 335E FR STABIL.'Tf Cuss F - (Net /Ht). 3AEED 2 A 1.3 C2/SEi: DIS 3IQt WE m

PED 330ddDS 215774CE - 3ILZ3 m) ~~ ~

1 2 3 4 5 6 7 3 7 '!O 11 12 e 0-2 1. 5 02 6. 5 01 4.2 @ 01 12:5+01 2. '.AE41 2.09E01 1.7 @ 01 1.'#r01 1. *4E,01 1.211-01 1. M ,01 7.39E40 2-4 4.15,01 2.1241 1. G +01 1.37E+01 L 4@00 6.7eE400 5.7240 !.12,00 4. 2 ,00 4. 5 00 3.4:iE400 3.3:600

. 4-9 3.09E*01 1.411,01 L39E+00 L 4 +00 4.7 5 00 4.30EH)0 1 2 ,00 2.37E-00 2.5C600 L21--00 1.78E,00 1.7 S 00 MS 1.39601 3.2 2 ,00 5.212+00 14X,00 2. M +00 2.22-00 1.3:I40 1. &E-00 1.;5-00 1.1 5 00 1.04E40 7.49N1 13-36 7.44E+00 4.25E*00 2.4 @ 00 1.3500 1.0 5 00 1.11E*00 7.17H1' 7.IM-11 s.74E-31 5.73E-31 5. *3E-31 4.72-11 MIt!!D 105E r"Ut STABILITT USS F - (Net /Mt). 3ASED 3141.3 :2/Sil: DIS 3*06 WE VDQ 7ED 23s14D 0 OIS77dCE - MIlii

(NH) -

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Page 22 of 22 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 5 0FF-SITE DOSE CALCULATIONS F

APPENDIX A DOSE FACTORS FOR STABILITY CIASS G *j/~

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Page 1 of 7 FLORIDA POWER & LIGHT COMPANY i ST. LUCIE PLANT UNIT NO.1 & 2 EMERGENCY PLAN UfPLEMENTING PROCEDURE No. 3100034E REVISION 3

1.0 Title

MAINTAINING EMERGENCY PREPAREDNESS - RADIOLOGICAL EMERGENCY PLAN TRAINING

2.0 Approvals

Reviewed by Facility Review Group ','~t' 3 ' --

19 *I f Approved by *l' ,, */i V.P. Pwr. Res.  ; - -- 19 -

4 fg e C ,' / r; -d C * .* v e' .5'd if T

• Rev. 1 Revip*Gtd by FRG M7~' -

19 2 /

Approved by /,////X,d, zh

, - V. P. Pwr.' Rei ,,M, / 4, 19 M Rev. _ by,FRG ,, 1982 3 Reviewed,[///ul>/

Approved by 5d w/J., (/ V. P. Nuc. Energy f,e 1982 V

3. 0 Scope:

/

3.1 Purpose This procedure provides requirements for a periodic training of individuals, onsite, who may have some response upon initiation of the St. Lucie Plant Radiological Emergency Plan.

3.2 Discussion In ordar to maintain emergency preparedne,ss, personnel working at.the _

St. Lucie Plant must be familiar with certain preplanned actions in the Emergency Plan and its implementing procedures.

Any changes in required actions or response due to revision of the Plan or procedures must be presented to appropriate personnel on a neriodic basis. -

3.3 Authority St. Lucie Plant Radiological Emergency Plan 3.4 Definition Throughtout this procedure, the terms Emergency Plan and Plan will be used to mean St. Lucie Plant Radiological Emergency Plan.

M

3. ,

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O 8

\

Page 2 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO.1 & 2 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 31000347.

REVISION 3 4.0 Precautions 4.1 This procedure does not cover requirements for periodic training of the FPL Offsite Emergency Organization.

5.0 Responsibilities

5.1 The Plant Manager has the overall responsibility for Emergency Plan Training.

5.2 The Plant Training Supervisor is responsible to the ' Plant Manager for ensuring all Emergency Plan Training is conducted in accordance with the references listed herein.

5.3 The primary team leader of each emergency team is responsible for the development and implementation of his team's training and retraining program. He may assign competent individuals to assist him in accomplishing this task.

5.4 The Operations Superintendent is responsible for the development and implementation of the Emergency Coordinator training and

, retraining program. He may assign competent individuals to

[

i assist him in accomplishing this task.

5.5 The Plant Training Supervisor is responsible for development and implementation of Emergency Plan Training of all candidates for reactor operator or senior reactor operator licenses.. .- - -

5.6 The Plant Training Supervisor shall provide for training all individuals requiring unescorted access on site describing the action to be taken by an individual discovering an emergency condition, the location of assembly areas, the identification of emergency alarms, and the action to be taken on hearing those _ ~

~

alarms. ~ ~

6.0 References 6.1 St. Lucie Plant Radiological Emergency Plan -

6.2 10 CFR 50.47 6.3 10 CFR 50 Appendix E 6.4 NUREG 0654, Revision 1 '

_ 1 iRu . r - .- - _ a_ . .c _ . . . _ _ _ _ . ___: _;._..._. . .  :- . _ . _ . .

.2.ln .u:2 Li15C;di-Page 3 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 & 2 EMERGENCY PLAN IlfPLEMDITING PROCEDURE NO. 3100034E REVISION 3 7.0 Records and Notifications:

• Records documenting the Emergency Plan Training received by individuals are quality assurance records and, therefore, shall be retained in accordance with Quality Instruction, QI-17-PR/PSL-1, Quality Assurance Records.

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t_ _ .;. ~ ' ~.c.i T Z E .  ;, _ . j, 23 Page 4 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO.1 & 2 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100034E REVISION 3

8.0 Instructions

~'

8.1 Emergency Coordinator Training All ' Nuclear Plant Supervisors, Duty Call Supervisors (Operations),

Nuclear Watch Engineers, Reactor Control Operators (who are holders of Senior Reactor Operator licenses) shall receive training in categories provided in this section, annually: (1 3 months) a) Interpretation of plant and field data and how it r' elates to

~

l emergencies and their classification (i.e. emergency action level determination).

b) Prompt and effective notification methods, including the types of communication system c) Method of activating the Florida Power & Light Company Emergency Organization, d) The methods used for estimating radiation doses.

8.2 Other Operational Assistance Other control room shift personnel who may be required during an emergency shall receive training in the following areas on an annual basis: . - . --

a) Emergency Plan familiarization, b) Emergency implementing procedures familiarization. .

c) Communications and record keeping methods. ._

~

d) Accident assessment and corrective action. -

e) Shift relief policy.

f) Specific emergency team training (for individuals assigned to interim emergency teams).

f. y  : :w . .. w-:. -. . - .- - . ~ . . - . = - ~ L E2T Page 5 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO.1 & 2 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100034E REVISION 3

8.0 Instructions

(cont'd) . -

8.3 Shift Technical Advisor All Shift Technical Advisors shall receive the following annual training: (+ 3 months) a) Emergency Plan familiarization b) Emergency implementing procedures familiarization.,_ ,

c) Technical Specifications (in-depth understanding).

d) Specialized training in power plant and reactor specific core operating characteristics (normal and abnormal) and accident assessment.

8.4 Emergency Teams 8.4.1 Primary and interim Emergency Team Leadera, their alternates, and emergency team members shall have successfully completed radiation protection training conducted by the Health Physics group. Successful completion of this training is acknowledged by the issuance of a " Red Badge" identification card.

8.4.2 All assigned primary and interim leaders shall participate in -

an annual training exercise designed to have them.and their - -

teams respond to simulated situations.

8.4.3 Specific emergency team training shall be conducted by the primary team leader or his qualified designee familiarizing team members with their responsibilities described in the Emergency Plan and its implementing procedures, communications _ _

and coordination with other emergency teams and the following team-specific topics: -

~

i 8.4.3.1 Radiation Emergency Team a) Use of air sampling equipment.

b) Performance of contamination surveys, c) Determination of air activity and stay times based on MPC values. -

d) Determination of radiation levels and allowable dose limits in emergency conditions.

1 J

- . + . . . -. a ..  :-.... - . - - AV Page 6 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO.1 & 2 EMERGENCY PLAN IMPLEMENTING PROCEDURE No. 3100034E REVISION 3

8.0 Instructions

(cont'd) - -

8.4 Emergency Teams (cont'd) 8.4.3 (cont'd) 8.4.3.1 (cont'd) e) Record keeping methods.

f) In-depth knowledge of personnel and field monitoring / analyzing techniques, g) Responsibilities of the Emergency Radiation Team.

8.4.3.2 Security Team a) Personnel accountability procedures, b) Site ingress and egress control procedures, c) Deployment of Security Peraonnel.

8.4.3.3 First Aid / Decontamination Team

'- ~

a) Description, storage' location, and application of supplies and equipment, b) Sequential steps for the assessment of contamination levels and treatment of injured personnel. -

c) Allowable radiation exposures and advisable -

radiological environments.

d) Personnel decontamination procedures.

e) Procedures for the evacuation of contaminated persons to off-site medical facilities, f) At least three nembers will satisfactorily complete the American National Red Cross Multi- -

Media First Aid Course and will requalify every three years (+ 6 monthd.

h

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Page 7 of 7 FLORIDA POWER & LIGHT COMPAhi ST. LUCIE PLANT UNIT NO.1 & 2 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 31dOO34E REVISION 3

8.0 Instructions

(cont'd) 8.4 Emergency Teams (cont'd) * '

8.4.3 (cont'd) 8.4.3.4 Fire Team Fire Team training is covered by the Fire Protection manual, Administrative Procedure 1800022.

8.4.3.5 Recovery and Restoration & Re-entry'Teahs -

These teams are conposed of personnel previously described teams and as such receive adequate training with respect to the Emergency Plan and its implementing procedures.

8.4.3.6 Other Personnel Requiring Unescorted Access On Site a) Emergency Plan Familiarization, b) Selected Emergency implementing procedures familiarization.

8.4.3.7 Technical Support Center Supervisor a) Emergency Plan famili,arization. .. . _

b) Emergency implementing procedures familiarization.

c) Technical Specifications (in-depth understanding). -

d) Specialized training in power plant and reactor -

specific core operating characteristics (normal and abnormal) and accident assessment.

8.4.3.7.1 Those personnel designated as " Support Staff" on Table 3 of Emergency Plan Implenting Procedure 3100032E need not receive the above training.

l 1

~

-- . . - - . - . . -. .- . JihaLL

. o Page 1 of 10 FLORIDA POWER & LIGHT ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100035E REVISION 2 - -

1.0 Title

Offsite Radiological Monitoring and Dose Assessment 2.0 Review and Approval:

Reviewed by Facility Review Group --

-July 7, 1911 Approved by A. D. Schmidt Vice Pres. Pwr.Res. July 13, 1981 Revision 2 Reviewed by F R G _ fY11 v // 774 a e ? 1932-Approved by e //I' Nu h V. P. Nuc. Energy [_ (/ 19 [F

3.0 scope

3.1 Purpose

This procedure gives guidelines for assessment of thyroid and whole body doses based on offsite radiological monitoring

3.2 Authority

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

4.0 Precautions

4.1 The Radiation Team Leader shall control the exposures of the of f-site and on-site out-of plant monitoring teams within 10 CFR 20 .

limits unless higher levels are authorized by the Emergency --

Coordinator or Recovery Manager. These higher limits should be less than 5 Rem whole body and 25 Rem thyriod.

4.2 Field measuremente indicating doses and dose rates that are less than those predicted by using plant instrumentation shall not be used to relax recommended protective actions while releases are in progress.

4.3 Field measurements indicating doses and dose rates greater than those predicted by using plant instrumentation should be used to recommend protective actions as appropriate.

. - . . . . - .~ . . . . - ab P, age 2 of 10 ST. LUCIE PLANT E ME RGE NCY PLA N IMPLEMENTING PROCEDURE 3100035E, REVISION 2

0FFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT

)

4.0 Precautions

(continued) l 4.4 Doses to personnel in the OSC and Interim EOF shall be maintained to i the limits of 4.1. - -

5.0 Re s ponsibilities:

5.1 The Emergency Coordinator, or his designee, is rerponsible for ensuring that offsite monitoring is performed during plant emergencies which involve the release of radioactive material to the

environment.

5.2 The Emergency Coordinator is responsible for detecarning the~

protective actions that will be recommended to off-site agencies.

. The TSC Supervisor is responsible for notification of of f-site agencies of the recommended protective actions.

5.3 The Radiation Team Leader or his designee is responsible for the activation and direction of offsite monitoring team (s).

5.4 The Radiation Team Leader is responsible for providing dose projections based upon offsite monitoring data to the TSC Supe rviso r.

5.5 The State of Florida's Department of Health and Rehabilitative Services assumes responsibility for offsite monitoring and dose projections af ter arrival of the Mobile Emergency Radiological Laborato ry. The transfer of this responsibility' from the plant to MERLE will be made when the State informs the plant that they are

' ~ ~ '

ready. ' ~

5.6 The TSC Supervisor shall inform the appropriate of fsite agencies concerning off-site monitoring data and projected doses until relieved of this responsibility by the Recovery Manager.

6.0

References:

6.1 St. Lucie Plant Radiological Emergency Plan 6.2 Florida Radiological Emergency Plan for Fixed Nuclear Facilities .

6.3 HP-202, "Of fsite Environmental Monitoring During Emergencies".

6.4 St. Lucie Plant Emergency Plan Implementing Procedures.

7.0 Records and Notifications: .

7.1 Of f-site monitoring data and projected thyroid and whole body doses will be recorded on Appendix A.

7.2 Integrated Of f-Site Dose Table.

, . - . _ . u a .. .

. .. . . . . . ~. . . ~ :c .:_m . a Page 3 of 10 ST. LUCIE PLANT E ME RGE NCY PLAN IMPLEMENTING PROCEDURE 310003 5E , REVISION 2 0FFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT 8.0 Ins truc tions:

8.1 Upon the classification of an ALERT level emergency the on-site out-of plant field monitoring team shall be activated and the off-site - -

field teams may be activated at the discretion of the Emergency Coordinator. At the SITE AREA and CENERAL EMERGENCY Level, the on-site and of f-site field monitoring teams shall be activated. The staffing and control of these teams is the responsibility of the Radiation Team Leader.

8.2 The Radiation Team Leader shall determine monitoring points based upon meteorological conditions and population zones 8.2.1 Preselected monitoring points are listed in Appendix B and indicated on the area maps contained in the off-site monitoring kits. The preselected points are possible monitoring points and may be used as reference points to direct monitoring tems.

8.3 Communication with monitoring teams will be through the FPL two-way radio systen or telephone.

8.4 Monitoring teams will take direct radiation readings and air samples and analyze air samples for radioiodine concentration.

8.4.1 Radioiodine analysis will normally be performed using portable analyzers with scint,111ation detectors.

Note: In the event radioiodine analysis cannot be done in the field, the Radiation Team Leader will provide Tor

- ~

the transport of air samples to the plant site for analysis.

8.5 Thyroid dose projections shall be done using the nomagra in Appendix C. The projected release time should be for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> unless .

otherwise indicated. ... -

8.5.1 The projected thyroid dose is determined by matching the radioiodine concentration, on the right, vertical scale, with the projected exposure time, on the horizontal scale, and reading the projected thyroid dose off the nomagram.

8.6 Whole body dose projections will be determined by multiplying the gamma exposure rate by the projected exposure time.

8.7 Projected doses and survey data will be recorded on Appendix A. .

8.8 The Radiation Team Leader will inform the TSC Supervisor and the Emergency Coordinator in regard to monitoring data and projected doses. Recommended protective actions shall be based on whole body and thyroid dose projections for adults.

L. .....u.

's . - :- nS Page 4 of 10 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100035E, REVISION 2 0FFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT 8.0 Ins truc tions: (continued) 8.9 Projected doses to field tems are computed by using the measured dose rates and iodine concentrations in the plume and the time the - ~

tem was in the plume. Record the information on Appendix D.

8.10 If it appears that a team will receive doses in excess of those listed in 4.1, the Radiation Tem Leader will make the necessary arrangements for replacing the team.

8.11 When the EOF is manned and operational, the previously gained of f-site monitoring data dose assessment will be forwarded to the dose

~ ~ ~

assesment group in the EOF.

8.12 When the EOF is manned and operational, the dose assessment group in the EOF will select the locations for of f-site monitoring and forward *h.st information to the TSC where the teams will be dispatched. /R2 e

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Page 6 of 10 FLORIDA POWER & LIGHT

• COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100035E REVISION 2 l OFFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT l

l APPENDIX B PRESELECTED OFFSITE MONITORING POINTS (Page 1 of 3) . .

Survey Distance EPZ Point Location Fros Plant Sector A-1 S.R. A1A, North of plant site 6.0 mi. NNW B-1 Intersection S.R. 707 and S.R. 712 3.9 mi. NW E. of White City & S. of Ft. Pierce B-2 Intersection U.S. 1 & S.R. 611, S. 6.5.mi.. . NW side of Ft. Pierce near RR crossing B-3 S.R. 707, S.E. side of Ft. Pierce 6.7 mi. NW B-4 Intersection U.S. I and S.R. 70 8.1 31. NW C-1 Intersection U.S. 1 & S.R. 712 5.1 mi. WNW White City C-2 3.R. 70 near Florida Turnpike 10.1 mi. WNW D-1 5.R. 707 W. of plant site 1.1 mi. W D-2 U.S.1, S. of White City 4.9 mi. W E-1 Intersection U.S. 1 & Prima Vista 4.9 mi. WSW Blvd. , Port St. Lucie F-1 Intersection U.S. 1 & Walton Rd., 5.0 31. SW Port St. Lucie

~

Port St. Lucie Blvd. at F1. Turnpike' F-2 8.6 mi. ' SW' G-1 Intersection S.R. 707 & Walton Rd. 3.5 mi. S G-2 Intersection U.S. 1 & Port St. Lucie ,5.9 mi. SSW Blvd., Port St. Lucie H-1 S.R. 707 in Eden, 2 mi. N. of 3.5 mi. S ._

Jensen Beach Causeway ,

H-Z S.R. 707 & Jensen Beach Causeway 6.9 mi. S H-3 Intersection S.R. 707 & Palmer Rd., 8.1 mi. S

~

S. of Jensen Beach H-4 S.R. 707 in Rio 8.9 mi. S H-5 Martin Memorial Hospital in Stuart 10.2 mi. S I-1 S.R. A1A, S. of plant site 4.0 mi. SSE I-2 S.R. A1A & Causeway in Sewell's Point 10.3 mi. SSE

^

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y Page 7 of 10 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100035E REVISION 2 0FFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT

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EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100035E REVISION 2 l OFFSITE RADIOLOGICAL MONITORING AND DOSE ASSES 94F9? -

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Page 1 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100050E REVISION 5

1.0 Title

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

2.0 Approvals

Reviewed by Facility Review Group July 25, 19 75 Approved by K. N. Harris Plant Manager July 29, 19 3 Rev. 4 Reviewjed by FRG M aco$ 10 -- -- -

19 2 l Approved by /////Jgo, 7/2. . V. P. Power Resources /4/m M , 19 1 Rev. 5 Review b G -

/7 7u n e ~I , / Mas //. 19g Approved by #14h(/ V. P. Nuclear Energv '

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3.0 Scope

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.

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.

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3.0 Scope

(cont'd) . .

j 3.3 Authority l 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 Responsibilities

5.1 The FPL Emergency Planning Supervisor shall be responsible for RS 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: R5 a) Schedule a date for the exercise in coordination with the Plant Manager and the primary State and county emergency response agencies.

b) Request that the Plant Manager assign personnel to assist the Emergnecy Planning Supervisor prepare a scenario. R5

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. ,,, ._

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f) Discuss and evaluate the exercise with observers and principal ~

participants, g) Ensure that for all identified deficiencies, corrective measur'es are recommended.

h) Prepare and retain documentation for record keeping.

4 5.2 The Operations Superintendent shall be responsible for planning, scheduling, and coordinating all onsite emergency drills. When a ~

drill is to be conducted, he shall:

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., 1 Page 3 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100050E REVISION 5

5.0 Responsibilities

(cont'd) 5.2 (cont'd) a) Schedule a date for the drill in coordination with the Plant Manager and the Emergency Planning Supervicor. /R5 b) Assure that a scenario is prepared.

c) Assign observers for specific portions of the drill.

d) Obtain the approval fo the Plant Manager, i

e) Discuss and evaluate the exercise with observers and principal participants.

f) Ensure that for all identified deficiencies corrective measures are recommended.

g) Prepare and retain documentation for record keeping.

5.3 When an exercise or a major drill is to be conducted, the Plant Manager shall assure that the following is accomplished:

a) Assign personnel to prepare a scenario, b) Coordinate through the Emergency Planning Supervisor all /RS activities which involve off-site personnel organizations or"' - ~

agencies.

, c) Schedule a date for this activity in , coordination with the l Emergency Planning Supervisor and assign observers. /R5 d) Review evaluations of exervise or drill with the observers and -

the Facility Review Group. ,

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

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! f) Prepare and submit documentation to the Emergency Plan Administrator for record keeping.

i These exercises and drills will simulate emergency conditions and may be scheduled such that two or more exercises or drills are __

conducted simultaneously, l

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. e Page 4 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE No. 3100050E REVISION 5 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 Uritten evaluation to FRG, Plant Manager, and EmerfeFicy Planning -

Supervisor by the Operations Superintendent /R5 7.3 Consolidated exercise summary by the Emergency Planning Supervisor. /R5 1

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3 Page 5 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100050E REVISION 5 8.0 Instructions 8.1 The following emergency exercises, drills, and tests shall be . -

conducted at the frequency indicated:

l a) Exercises (Integrated Drills)

A major radiological emergency response exercise shall be conducted at least once every twelve (12) months (plus or ninus 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 pcnyide 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.

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, b) Radiological Monitoring Drill, 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).

c) Health Physi'es Drills -

The Health Physics Department shall conduct h'alth e physics _

drills semi-annually and one of the semi-annual drills may be incorporated into the radiological monitoring drill. '

d) Medical Emergency 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). ,

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Page 6 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100050E REVISION 5 8.0 Instructions (cont'd) l 8.1 (cont'd) - -

e) Fire Emergency 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 postdrill critique 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 Disaster Preparedness, 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 thdt the drill will~not ~~ ~

adversely affect plant equipment or operations.

8.2,2 The operations Superintendent shall designate specific membe:s of the plant staff to act as observers durin, the drill These observers 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 serve and what specific areas the observers should be concerned with.

Theseiobservers 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.

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100050E REVISION 5 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 Operations SuperintendeDC .shall assimilate all information and data concerning the emergency procedure drill and hold a critique on the drill with the FRG.

The FRG shall recommend changes to the Emergency Procedures as necessary.

8.3.2 Following an exercise, the Emerge.ncy Planning Supervisor, /RS plant management, FPL observers and 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 an necessary changes in the Plant Emergency Procedures and for -

recommending changes in the Emergency Plan to the Emergency Planning Supervisor. Recommended changes in the Emergency /RS Plan shall be submitted to the Emergency Planning Supervisor. /RS 8.3.3 The FRG shall submit a written evaluation following an exercise to the Emergency Planning Supervisor. These fR5

~

comments will be incorporated, with comments from other principal participants and observers, into a~ consolidated -

exercise summary. Ihe summary will be distributed as described in the " Duties and Responsibilities of the Emergency Planning Supervisor" procedure. /R5

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