ML17214A681

Rev 15 to Emergency Plan Implementing Procedure 3100021E, Duties & Responsibilities of Emergency Coordinator.

ML17214A681
Person / Time
Site:	Saint Lucie
Issue date:	01/09/1984
From:	Harris K FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17214A680	List: ML17214A679 ML17214A681 ML17214A682 ML17214A683 ML17214A684
References
3100021E, NUDOCS 8402070383
Download: ML17214A681 (112)

Text

Page 1 of 24

/

e FLORIDA POWER i LIGHT COMPANY ST. L>'0 IE PLANT E-PLAN IMPLEMENTING PROCEDURE NO- 3100 21E ~

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REVISION 15 +

1.0 Title

Duties And Res onsibilities Of The Emergency Coordinator

2.0 Approval

Reviewed by Plant Nu ear Safety Committee July 25, 1975 Approved by K N. Ha is Plant Manager July 29, 1975 Re vis i on 15 ewed by ci y Review Group 3E'c~~6w i~ 19f D Approved by / Vice Pres. Nuc. Ener 19

3.0 Scope

3. 1 Purpos e'.

This procedure provides the instr tions to be followed by the Emergency Coordinator when an emerg ncy occurs that requires thd implementation of the Emergency Plan. /R15

3.2 Discussion

3.2.1 The Nuclear Plant Supervisor and th shift operating staff represent the first-line of response to any developing emergency condition. The primary responsibilit of the Nuclear,.Plant Supervisor is to control the condition s well as possible. The Nuclear Plant Supervisor becomes the Eme gency Coordinator upon initiation of the Emergency Plans and, as such, directs the On-Site Emergency Organization to bring the emergency under control. The primary route of communication to the off-site, non-FPL organization is the Hot Ring down "Re Phone" with NAWAS as the alternate. Additional alternates are 1 ted.in EPIP 3100023 E, Emergency Roster. /R15 3.2.2 As conditions warrant, the Emergency Coordinator s ould identify someone from the existing plant staff or TSC if ope tional, (preferrably a licensed Operator) to assist in Contro Room activities such as communications (i.e., notification, telephone and radio), check off lists and logbook entries. This hould allow the EC to more adequately manage the e

situation.

3 3 -Authority:

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

SSOSOTOSSS SSOSO~a PDR. ADQCK 05000335 F - " PDR'

il 4

r Page 2 of 24 ST. LUG IE PLANT E-PL Ql IMPLEMENTING PROCEDURE NO. '3100021E, REVISION 15 DUTIFS AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 4.0

~ 'Precautions: ~

'4.1 The Emergency Plan and Procedures 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).

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. The actual

,notification can be done by the EC's assistant. 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" or "THIS IS AN EXERCISE".

4.4 Protective action recommendations to state and local authorities CANNOT be delegated by the Emergency Coordinator, however, these recommendations become 'the responsibility of the Recovery Manager when the Emergency Operating Facility is manned and operational. /R15 4

4.5 In any case where a GENERAL EMERGENCY has been declared, the minimum protective action recommendation shall be: "Shelter all people within a 2 mf.le radius and 5 miles in the downwind sectors".

4.6 If the GENERAL EMERGENCY has been declared due to loss; of physical control of the plant to intruders, including the Control Room or any other area(s) vital to the operation of the reactor system (as defined in the Security Plan), the minimum protective action recommendation shall be: "Evacuate all people within a 2 mile radius from the plant". /R15

5.0 Responsibilities

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

5.1.1 Assistant Nuclear Plant Supervisor 5.1.2 Any other Reactor Control Operator with a Senior Reactor Operator License.

5.2 The Emergency Coordinator shall grant permission for watch relief, including his own, only when it is safe in his judgement to do so. /R15 5.3 The Plant Manager, Operations Superintendent, or the Operations Supervisor may assume the Emergency Coordinator function following proper turnover. /R15

Page 3 of 24 ST. LUG IE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 5.0

~ Res onsibilities: (Continued) 5.4 If the TSC is activated, the Technical Support Center Supervisor shall

~

fill out the checklist as soon as for Notification of Significant Events (to NRC) possible after activating the TSC and preferably before calling the NRC.

5.5 The Emergency Coordinator is responsible for providing protective action recommendations to offmite authorities. This responsibility cannot be delegated, but becomes the responsibility of the Recovery Manager when the Emergency Operations Facility is manned and operational. /R15 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 Off-Site Dose Calculation. /R15

7.0 Records

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

Page 4 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES .AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

8. 0 Instructions:

8. 1 Class ification 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 becoaa the Emergency Coordinator. The Emergency Coordinator shall, until relieved, remain in the affected unit 's Control Room at all times during emergency situations that require Emergency Plan implementation unless, in his opinion, his personal evaluation of the situation is necessary to maintain plant safety. /R15 8.2 The Emergency Coordinator shall mobilize the On-Site Emergency Organization to begin required corrective actions. As conditions warrant, the Emergency Coordinator should identify and assign tasks to an assistant.

8 3 CHECKLISTS N

8.3.1 If the situation is a Plant/Radiological Emergency, utilize the Plant/Radiolo cal Emer ency Checklist (Page 6).

8.3.2 E

ii losion the situation is Emer ency a fire or explosion, Checklist (Page 12).

utilize the Fire or

/R15 8.3.3 If the situation is a medical emergency with or without contamination, utilize the Medical Emer ency Checklist (Page 16). /R15 8.4 Responsibilities for offmite communications and coordination shall be relinquished first to the Technical Support Center Supervisor and then to the Recovery Manager when the EOF is staffed and operational. /R15 8.5 OFF-SITE PROTECTIVE ACTION RECOMMENDATIONS The Emergency Coordinator is responsible for providing protective action recommendations to off-site authorities as indicated on Pages 19 through 24, "Guidelines for Protective Action Recommendations to Off-site Authorities". When the Recovery Manager has indicated that the Emergency Operations Facility is manned and operational, the Recovery Manager can relieve the Emergency Coordinator of this responsibility. /R15

II Page 5 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE 1 INITIAL,NOTIFICATION FLOW EMERGENCY COORDINATOR INTERIM EMERGENCY As Appears LOCAL SUPPORT TEAMS " On C ec list 1 FIRE AMBULANCE, ST ~

LUCIE COUNTY -FORT STATE OF FLORIDA PIERCE FIRE DISTRICT BUREAU OF EMERGENCY 2. MEDICAL, LAWNWOOD MANAGEMENT MEDICAL CENZER OR REEF AT MT. SINAI U NRC OPERATIONS CENTER OFFICE OF DISASTER PREPAREDNESS STATE DHRS OFFICE OF RADIATION CONTROL

/Rl'ES

)

DCS AVAILABL NO DUTY L SUPERVISOR POWER COORDINATOR I EMERGENCY CONTROL OFFICER ECO ALTERNATES NUCLEAR ENERGY DUTY OFFICER FPL OFFSITE EMERGENCY ORGANIZATION ADDI ZONAL PLANT SUPPORT EMERGENCY TEAM LEADERS

ll Page 6 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 310002 E, REVISION 15 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 TIME

1. Order initial corrective action per Emergency Operating Procedures.

IF UNUSUAL EVENT SKIP TO STEP 7

2. Notify personnel of the emergency condi"ion over the Unit 81 and/or 82 PA system, giving location, class, and type of emergency.

Repeat Announcement IF SITE AREA OR GENERAL - SKIP TO STEP 4

3. 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:

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, specify evacuation route/assembly area.

5. Repeat PA announcement.

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

7. Mobilize Interim Emergency Teams to respond as necessary.

8 Commence preparation of the Notificatio x Message Form (pages 7, and 8) including Protective Action Reco:nmendations (Ref. pgs 19 to 24) and,(if available) offmite dose data via EPIP 3100033E. /R15

Page 7 of 24 ST. LUCIE PLANT E PLAN 'MPLEMENTIN PROCEDURE NO P 3100021E P REVISION 15 DUTIES AND RESPONSI BILITIES OF THE EMERGENCY COORDINATOR

. STATE OF FLORIDA NOTIFICATION iKSSAGE FORM NUCLEAR POWER PLANTS (Page lof 2) 1 ~ TIME AND DATE OF MESSAGE / REPORTED BY /

, 2~ SITE 3. ACCIDENT CLASSIFICATION

~B] ST. LUCIE UNIT 1 A NOTIFICATION OF UNUSUAL EVENT

[C] ST. LUCIE UNIT 2 [B ] ALERT

[C] SITE AREA EMERGENCY

[D] GENERAL EMERGENCY

4. TIME AND DATE OF INCIDENT/EMERGENCY Time ~

Date 5~ INCIDENT INVOLVES:

6. ACCIDENT RELATED INJURIES [A] NO [B] YES [C] CONTAMINATED INJURY NUMBER OF INJURIES 7~ SITUATION INVOLVES:

[B] POTENTIAL (POSSIBLE) RELEASE

[C] A RELEASE IS OCCURING - EXPECTED DURATION OR MAGNITUDE fD] A RELEASE OCCUREDP BUT STOPPED DURATION OR MAGNITUDE 8 TYPE OF RELEASE IS:

Te * [D] PARTICULATE MATTER

[B] NON-RADIOACTIVE GASEOUS [E] NON-APPLICABLE

[C] RADIOACTIVE LIOUID

9. WIND DATA:

TAA WIND DIRECTION (PROM) DEGREES g 10 METERS

[B] WIND SPEED, MILES PER HOUR 8 10 METERS

[C] STABILITY CLASS

10. RECOMMENDED PROTECTIVE ACTIONS:

A NO RECOMMENDATIONS AT THIS TIME NOTIFY THE PUBLIC TO TAKE THE FOLLOWING PROTECTIVE ACTIONS:

No Action Shelter Evacuate 0-2 Mile Radius ~C 2-5 Miles for Sectors [E] [F] [G]

5-10 Miles for Sectors [Hl [Il [ J]

Miles [Kl [Ll

11. CURRENT OUTS IDE TEMPERATURE: fA] F Q 10 METERS

12. RELEASE RATE:

NOBLE GASES IODIWEE DEFAULT [A] Ci/Sec ]C] Ci /Eee MEASURED [B] , Ci/Sec [Dl Ci/Sec INSTRUMENT LOCATION N/A

13. SUPPLEMENTAL PAGES USED: A NO MESSAGE RECEIVED BY: / /

NAME OF STATE PERSON TIME . ~ DATE

Page 8 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR STATE OF FLORIDA NOTIFICATION MESSAGE FORM SUPPLEMENTAL DATA (Page 2 of 2)

14. WIND DIRECTION DATA S OR DIRECTION DEGREES DIRECTION SECTORS AFFE TED A N 349-11 S HJK B NNE 12-33 SSW JKL C NE 34-56 SW KLM ENE 57-78 WSW LM N E E 79-101 W MNP, F ESE 102-123 WNW NPQ SE 124-146 NW P QR H SSE 147-168 NNW QRA J S 169-191 N RAB K SSW 192-213 NNE AB C SW 214-236 NE B CD M WSW 237-258 ENE CDE W 259-281 E DEF P WNW 282-303 ESE EFG Q NW 304-326 SE FGH' R NNW 327-348 SSE H J 15 'ASIC DESCRIPTION OF RELEASE CHARACTERISTICS

16. Estimate- of Radioactive Material Released:

NOBLE GASES SOURCE TERM: [A] Ci/Sec TOTAL RELEASE: [B] Ci Radioiodines SOURCE TERM: [C] Ci/Sec TOTAL RELEASE: [D] Ci 23 ESTIMATE OF PROJECTED OFF-SITE DOSE RATE:

Dis=ance Thyroid (mrem/hr) Whole Body (mrem/hr) 1 Mile (Site Boundary) [A] [B]

2 3

4 Miles

.&les

'&les

[C]

I~* [D]

"7X 5'Ales [I] [J) 10 Miles [K] [L]

24. SPECIAL DATA: [Ai NO [B] YES MESSAGE RECEIVED BY: TIME DATE / /

NAM OF STATE PERSON)

Page 9 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES. AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR PLANT/RADIOLOGICAL EMERGENCY CHECKLIST continued

/

9. During business hours, notify the Plant Manager. During off hours and weekends relay information to the Duty Call Supervisor (see NPS Bulletin Board for scheduled supervisor and telephone number).

Order him to notify the following'. /R15 Plant Hanager Operations Superintendent Operations Supervisor Technical Department Supervisor Emergency Control Officer (or Nuclear Energy Duty Officer as last alternate)

(NOTE): If Duty Call Supervisor is unavailable Notify Emergency Control Officer via Systems Operations Power Coordinator Other Department Supervisors (Primary Team Leaders)

10. Notify the following within 15 minutes of classifying the emergency contact: e 10.1 Bureau of Emergency Management (BEM): Use "STATE" Red Phone, dial 22, when answered announce:

"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, cia'ss.

(ALTERNATE METHOD): NAWAS, using above "announcement:

II State Warning Point will call the Control Room via Commercial Phone to validate the notification. After validation, transfer the information on the Notification Message Form (pages 7 and 8) via "STATE" Red Phone or (as alternate, NAWAS)~ /R15 State Warning Point Acknowledgement Time 10.2 By telephone, the State Radiological Duty Officer at Office of Radiation Control in Orlando at 1-299-0580 (they have a beeper service for full tine coverage). When the Duty Officer is contacted, transfer the information on the Notification Message Form (pages 7 and 8). /R15 IF UNUSUAL EVENT OR ALERT, SKIP TO STEP 12

I U

n I

Page 10 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR PLANT/RADIOLOGICAL EMERGENCY CHECKLIST continued

11. Via BEM using "STATE" Red Phone (NAWAS alternate), contact St. Lucie and/or Martin County Disaster Preparedness. Inform them that site evacuation has started, location of assembly area(s ), evacuation route(s). Notify them when evacuation is completed. /R15

12. Prepare attached SIGNIFICANT EVENT REPORT (Page 11) and notify NRC via hot-line (within one hour). /R15 (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 ordered) lhas been completed and all personnel are accounted for.

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

4f

15. Activate the Technical Support Center'and the Operations Support Center. /R15

16. Brief the Technical Support Center Supervisor on events.

Order him to update'tate and county periodically and to refine dose progections when the Chemistry Department representative arrives.

17. Relinquish responsibilities for communications with offsite support agencies to the EOF when the Recovery Manager notifies the Emergency Coordinator that the EOF staff accepts these responsibilities. /R15

18. Reassess the Emergency Classification and if the situation escalates, recycle the Plant/Radiolo cal Emer ency. Checklist, excluding those entries already completed.

Page 11 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 1i DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINAT(>R SIGNIFICANT EVENT REPORT or NRC Noti ication Date Time Facility Name Power & Li ht St. Lucie Unit

'lorida (applicable Unit)

Caller Name

1. Description of Event Classification of Event Reactor'ystems Status

- Pressure Temperature , Power level Flow ECCS Operating/Operable PER 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/Elow Electrical Dist. Status: Normal Offmite Power Sources Available?

Ma)or Busses/Loads Lost Safeguards Busses Power Source D/G Running? Loaded' Personnel Casualties/Contamination?

2. Consequences of Event:

Actual and Potential Safety Hazards:

Tech. Spec. Violations?

State Notified? Press Release'lanned?

3'. Cause of Event:

Corrective Actions taken:

Planned:

Page 12 of 24 ST. LUCIE P'ANT E-PLAN IMPLEMENTING PROCEDURE N). 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF 'THE EMERGENCY COORDINATOR FIRE OR EXPLOSION EMERGENCY CHECKLIST

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

Site Area Emergency (time )

TIME

2. Order initial corrective action per Emergency Operating Procedures.

3. Sound Fire 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 via a PA announcement. /R15 6 If the evacuation of an area is necessary, initiate a local evacuation in accordance with EPIP 3100026E, "Criteria for and Conduct of Evacuati'ons". Announce the following: /R15 Area to be evacuated Areas to be avoided during the evacuation, if possible Assembly area

7. If off~ite assistance is necessary call St. Lucie;County-Ft. Pierce Fire District PHONE No. 911.

8. Prepare the following Notification Form:

Al Page 13 of 24 ST. LUCIE PLANT E-PLAN IM 'LEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIRE OR EXPLOSION EMERGENCY CHECKLIST continued STATE OF FLORIDA NOTIFICATION MESSAGE FORM NUCLEAR POWER PLANTS

1. Time and Date of Message / Reported by

2. Site 3a Accident Classification fK] St. Lucie Unit 1 oti ication o Unusual Event

[C]- St. Lucie Unit 2 [B] Alert

[ C] Site Area Emergency

4. Time and Date of Incident/Emer ency Time Date

• 5. Incident Involves:

6. Accident Related In urles: [A] No [B] Ies Number of In)urfes ITEMS 7 THROUGH 12 INCLUSIVE ARE N/A (NOT APPLICABLE)

13. Supplemental Pages Used: [A] No [B] Yes Page[a)

MESSAGE RECEIVED BY: / /

NAME OF STATE PERSON DATE For Item 5 (ONLY): If this is the only call for notification, then state "This is an Open 6 Close Notification" in this entry area after description of incident.

• • END OF NOTIFICATION MESSAGE FORM **

Page 14 of 24 LUCIE PLANT

'T.

E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIRE OR EXPLOSION EMERGENCY CHECKLIST continued

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 Etmrgency Control Officer (or Nuclear Energy Duty Officer)

(NOTS): If Duty Call Supervisor is unavailahle - Notify Emergency Control Officer via Systems Operations Power Coordinator Other Department Supervisors (Primary Team leaders)

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

10.1 Bureau of Emergency Management (BEM): Use "STATE" Red Phone, dial 22, when answered announce: /R15 "State Warning Point Tallahasse'e, 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.

s (ALTERNATE METHOD): NAWAS, using above announcement:

State Warning Point will call Control Room via Commercial Phone to validate the notification. After validation, transfer the information on the Notification Message Form via Red Phone or NAWAS ALTERNATE Form (page 13). /R15 State Warning Point Message Validation Time

0 Page 15 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. '3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIRE OR EXPLOSION EMERGENCY CHECKLIST continued ll. Prepare SIGNIFICANT EVENT REPORT (Page 11) 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 personnel 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 17

14. Activate the Technical Support Center and the Operations Support Center. /R15

15. Brief the Technical Support Center Supervisor on events. Order him to provide state and county with periodic updates and to consider dose progections when the Chemistry Department representative arrives. /R15

16. Relinquish responsibilities for communications with off-site support agencies to the EOF when the Recovery Manager notifies the Emergency Coordinator that the EOF staff accepts these responsibilities. /R15

17. If the accident involves actual or impending releases of radiation, go to the PLANT/RADIOLOGICAL EMERGENCY CHECKLIST.

18. Reassess the Emergen'cy Classification and update the Notification Message Form with Technical Support Center Supervisor (if TSC is activated).

0

(

I e

0

Page 16 o! 24

~ ST. LUCIE PLANT E-PLAN IMPLEMENTING'ROCEDURE NO. '3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR MEDICAL EMERGENCY CHECKLIST TIME I. Determine:

Name of Victim Employer (if rnot FPL)

Nature and Extent of In)ury Location Is victim contaminated?

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

3. Notify (via the Duty Call Supervisor. if necessary)

Health Physics Plant Manager, also request him to inform the Emergency Control Officer.

Operations Superintendent

4. Determine smde of transportation b'ased on nature aad extent of in)uries.

(Ensure victim's TLD, self-reading dosimeter, ID badge and key card are retained on site).

a. Medical treatment for minor in)uries.'PL Vehicle/Private Vehicle

b. Medical treatment for serious ingury:

AMBULANCE PHONE NO. 911

• • • Notify Captain of the Guard where to direct ambulance ***

5. Prom First Aid/Bacon Team Determine (Data for Hospital) is Victim conscious ) IYES ) )NO able to walk? I )YES ) }NO Problem is: (check one or more) Overexposure Contam Wound Internal Contam Whole Body Contam Will Victim be deconned at plant? YES ) jNO Vital Signs (if available) Pulse Rate Breathing Rate Other Information?

• Request that First Aid Team prepare information in Step 1 & 5 to acccmpany the victim.

6. Sand all victims to LANNNOOD NEDICAL CENTER PHONE NO. 465-4534 Be prepared to transfer the information contained in Steps 1 6.5 at this time OR they may call back for it.

Radioactively contaminated victims:

Notify REEF PHONE NO. 1-673-2183

i R ty 4

h I

Page 17 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR MEDICAL EMERGENCY CHECKLIST continued

7. Complete the following message form: (Page 18) 8'. Notify the following within 15 minutes of classifying the emergency contact 8.1 Bureau of Emergency Management (BEM): Use "STATE" Red Phone, dial 22, when answered announce: /R1.

."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.

(ALTERNATE METHOD): NAWAS, using above announcement:

State Warning Point will call Control Room via Commercial Phone to validate the notification. After validation, transfer the information on the Notification Message Form via Red Phone or NAWAS ALTERNATE Form (page 18) ~ /Rl!

State Warning Point Message Validation Time 8.2 Notify, by telephone the State Radiological Duty Officer at 1

have a beeper service for full time coverage) When the Duty Officer is contacted, transfer the information on the Notification Message Form (page 18).

9. Prepare attached SIGNIFICANT EVENT REPORT (Page 11) and notify NRC via hot-line (within one hour).

10. If the accident involves actual or impend'.ng releases of radiation,'o to the PLANT/RADIOLOGICAL EMERGENCY CH:-:CKLIST.

Reassess the Emergency Classification and update the Notification Message Form (page 18).

Page 18 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PR< CEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR MEDICAL. EMERGENCY CHECKLIST continued STATE OF FLORIDA NOTIFICATION MESSAGE FORM NUCL POWER P S Time and Date of Message / Reported by 2.

~Site St. Lucie Unit-1

[C] St. Lucie Unit 2

3. Accident Classification

$A oti ication II o Unusual Event 4 Time and Date of Incident/Emer ency Time Date

• 5 ~ Incident Involves:

6. Related In uries: [A] Contaminated Injury

'ccident No [B] Yes [C]

Number of Injuries ITEMS 7 THROUGH 12 INCLUSIVE ARE N/A (NOT APPLICABLE) 13 Supplemental Pages used: [A] NO Message received by: / /

RANE OF STATE PERSON TINE DATE

• For Item 5 (ONLY): If this is the only call for notification, then state "This is an Open & Close Notification" in this entry area

, after description of incident.

/R15 T'* END OF MESSAGE FORM **

it I

Page 19 of 24 ST. LUCIE PLANT IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15

'-PLAN 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 Emergency Management (BEM) and St. Lucie and Martin County Offices of Disaster Preparedness. /Rl!

Protective action recommendations should be made utilizing all of. the available data. This includes plant status (Fig A-l), offmite dose progections and/or field monitoring data (Fig A-2 or A-3). The more conservative recommendations should be made. /Rl!

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

I

l. In any case where a GENERAL EMERGENCY has been declared, the minimum protective action recommendation shall be: "Shelter all people within a 2 mile radius and 5 miles in the downwind sectors" ~

I the GENERAL EMERGENCY has been declared due

'f to loss of physibal control of the plant to intruders, including the Control Room or any other area(s) vital to the operation of the reactor system (as defined in the Security Plan), the minimum protective action recommendation shall be: "Evacuate all people within a 2 mile radius from the plant" ~

/R1.'f the emergency has been classified as a GENERAL EMERGENCY and NO OFFSITE dose pro4ections or field survey results are available, refer to figure A>>l to evaluate offsite protective action recommendations. /Rl.

2. If the emergency that has been classified is not a GENERAL EMERGENCY and the offsite doses are LESS THAN 0.5 Rem whole body or 1 Rem to the thyroid at 1 mile over the pro)ected duration of the release, no protective action is recommended. This should be reported to BEM and other outside agencies who inquire as: /R15 "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."

NOTE: If a controlled release is necessary to stabilize plant conditions or an uncontrolled release is anticipated, determine the approximate source term and duration of the release and the pro)ected off-site doses prior to making any protective action recommendations.

Page 20 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021K, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR PROTECTIVE ACTION RECOMMENDATIONS continued

3. If the emergency has been'lassified and offsite dose information is available (from any credible source), use the dose information to select the appropriate table. Use either Figure A-2 (PA with offsite 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 (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'an then be made.

FOR EXAMPLE, a release has occurred at the St. Lucie Plant with a pro)ected 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 pro)ected offsite integrated (2 hr) thyroid dose is 10 Rem at 1 mile, 2 Rem 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:

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

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, Page 7 Entry 10) /R15 No protective action is recommended between a 5 and 10 mile radius from the plant 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 formulate the appropriate message in the above format and transmit it to BEM. /R15

5. Protective action recommendations for a child have been incorporated into the figures.

Page 21 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. '3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE A-1 PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT CONDITIONS MIIES 2-5 MQES 5-10 MIIES USS QK KZ~ IE QNBKL M)

' S (Z SECCmZ(1) OF PLANK (5)

YES QKMi ammzmeir FA1LURE HAS

<yam umz) aXURam m m IS 28IMM'(~)p YES SEE RNMHZ (R E IN +S RS)

(3)

(1) "Potential core melt, any cause" *LEGEND OF ABBREVIATIONS in EPIP 3100022E, "Classification N o protective action recoame:

of Emergencies. S - Sheltering recommended (2) Represents greater than lOOX gas E Evacuation recoamended gap activity in containment. IM Downwind + 2 adgoining secto (3) See "Loss of Containment RS - Remaining sectors Integrity;" EPIP 3100022E. CR - Complete circle around plant

'(4) Determine whether a "Puff" type specified distance release is in progress (or imminent) using the conditions listed on next 'page.

(5) Loss of physical control of Control Room or vital reactor operating areas to intruders

II Page 22 of 24 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE A-1 (continued)

PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT CONDITIONS If a "PUFF" type release is imminent or in progress as indicated by the following conditions:

(1) Containment failure has occurred or is imminent, and (2) Rate of release is much greater than designed leak rate, and (3) Either the total or ma)or portion of radioactivity is pro)ected to be released within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or less, then in addition to the appropriate protective'ction recommendations the following statement and information should be given:

"Florida Power 6 Light Company recommends sheltering those areas that can' be evacuated before plume arrival."

WIND WIND TOWARD SECTOR DIRECTION DEGREES DIRECTION SECTORS A N 3 -11 S H J K

[Bl NNE 12 33 SSW JKL

[C] NE 34 56 II SW KLM tD] ENE 57 78 II WSW LMN

[El E 79 101 I I W MNP

[Fl ESE 102 123 WNW NP0

[G] SE 124 - 146 NW PQR

[H] SSE 147 168 NNW 0 RA S 169 191 II N RAB

[K] SSW 192 213 NNE ABC

[Ll SW 214 - 236 I I I I NE BCD

[M] WSW 237 258 II ENE CDE

[N] 'W 259 281 E DE F tP] WNW 282 303 ESE EFG

[Ol NW 304 326 SE FGH

[R] NNW 327 - 348 SSE GH'J

Page 23 of 24 ST. LUCIE PLAhT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE A-2 PROTECTIVE ACTION RECOMMENDATIONS BASED ON ACTUAL RELEASE (GREATER THAN OR EOUAL TO 2 HOUR DURATION) WITH OFFSITE DOSE ESTIMATES used in preference to Figure A-1 WHOLE BODY THYROID DOSE 0-2 MILES i I 2-5 MILES I I 5-10 MILES DOSE (REM) OR (REM)

< 0.5 1.0 >I

> 0 but

< 1.0 1

but

~

< 2.5 0

- >I S(CR) II S(DW) lt S(DW) (

> 1 ' > 2 '

but but -> I E CR) I E(DW) + S(RS)ll E(DW) + S(RS)I

< 5.0 < 25.0

> 5.0 I E(CR) I l~> ~

/R15 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 />, use Figure A-3.

• The dose 8 1 mile affects protective +LEGEND OF ABBREVIATIONS actions from 0-2 miles N No protective action recommended S Sheltering recommended The dose 8 2 miles affects protective E Evacuation recommended actions from 2-5 miles

'I 3W Downwind + 2 adjoining sectors RS Remaining sectors The dose 9 5 miles affects protective CR Complete circle around plant at actions from 5-10 miles specified distance The dose 9 10 miles can be used to evaluate protective actions for greater distances.

'P 0

0 0

ll Page 24 of 24 ST. LUCIE PLANT E>>PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE A-3 I

PROTECTIVE ACTION RECOMMENDATIONS BASED ON ACTUAL RELEASE (LESS THAN 2 HOUR DURATION) WITH OFFSITE DOSE ESTIMATES used in preference to Figure A<<l)

WHOLE BODY THYROID DOSE 0-2 MILES I I 2-5 MILES I I 5-10 MILES I DOSE (REM) OR (REM) )Use 1 Mi ValueI IUse 2 Mi Value( IUse 5 Mi ValueI

< 0.5 < 1.0 >I

> 0 ' 1 '

but but

< 1 ~ 0 < 2.5 0 > 1 but

< 5.0

> 2 but 25.0

> 5.0 > 25.0

/R15 NOTE:

If the duration of the release is pro)ected to be greater than or equal to 2 bours use Figure A-2.

• The dose 9 1 mile affects protective *LEGEND OF ABBREVIATIONS actions from 0-2 miles N No protective action recommended S Sheltering recommended The dose 9 2 miles affects protective E Evacuation recommended actions from 2-5 miles DW Downwind + 2 adjoini.ng sectors RS Remaining sectors The dose 8 5 miles affects protective CR Complet'e circle around plant at actions from 5-10 miles specified distance The dose 9 10 miles can be used to evaluate protective actions for greater distances.

I t

FLORIDA POWER & LIGHT COMPANY Page 1 DUTIES OF THE RECOVERY MANAGER, OFF-SITE EMERGENCY ORGANIZATION PROCEDURE 1102 12/15/83

1. 0 Tl t'l e:

DUTIES OF THE RECOVERY MANAGER, OFF-SITE EMERGENCY ORGANIZATION Recovery Manager: Manager, Nucl ear Energy Alternate: (1) Assistant Manager, Nuclear Energy Al tern ate: (2) Manager of Nuclear Energy Services, Nuclear Energy 2.0 A royal and List of Effective Pa es 2.1 ~Aroval Revi ewed by Emergency Planning Supervisor

$ 1984 Approved by Vice President, Nuclear Energy , 1984 2.2 List of Effective Pa es

~Pa e Date 1 through 21, inclusive 12/15/83

~Sco e 3.1 ~Per oae This procedure lists the duties and responsibilities of the Re(overy Manager (RM) in the Off-Site Emergency Organization.

3.2 Discussion The Off-Site Emergency Organization (see Figure 1) provides an expanded emergency response capability to assist the plant in administration, communications, engineering, technical support, security, and public relations. This organization, which is composed of company officials and a staff of assistants, is managed by the Emergency Control Officer and the Recovery Manager.

The RM is a designated Senior Manager who has knowledge of. nuclear plant

. operations and design and who is responsible for assisting the ECO in managing the Company's expanded emergency response organizatior. The RM can report to the General Office (for St. Lucie or Turkey Point.), or the Emergency Operations Facility (for St. Lucie) depending upon the ECO's assessment of the situation. Note: The designated EOF for Turkey Point is in the General Office Building and the St. Lucie EOF is located at the Midw~ Road/I-95 intersection approximately 10 1/2 miles west of the plant.

The RM will formulate protective action recommendations to offsite officials when the EOF is manned and operational relieving the EC of this responsibi i ty.

1 n

FLORIDA POWER 5 LIGHT OMPANY Page 2 DUTIES OF THE RECOVERY MANAGER, OFF-SITE EMERGENCY ORGANIZATION PROCEDURE 1102 12/15/83 3.3 ~Author( t This procedure.'implements the Turkey Point Plant Radiological Emergency Plan and- the St. Lucie Plant Radiologica'mergency Plan.

4.0 Precautions 4.1 The Checklists appearing at the end of this procedure serve as a guide to Recovery Manager regarding certain information that may be useful to have available when contacting offsite agencies and organizations. It is not a requirement of this procedure to complet~ these checklists during an emergency.

4.2 The Recovery Manager shall be notified o= all emergencies and mobilized for Site Area and General Emergencies. He m~ be mobilized for Alerts or Unusual Events.

.0 onsibi 1 i ti es 5.1. Inform the Emergency Control Officer periodically of the on-site status and immediately of any significant changes.

A S.2 Provide support and data as necessary to the Emergency Coordinator.

5.3 Obtai'n information on di agnosis and prognosis of the emergency, estimates of radioactive releases, prevailing meteorological conditions, projected radiological exposures, and recommended protective actions prior to declaring of the EOF operational.

5.4 Provide protective action recommendations to offsite authorities when the EOF is manned and operational.

5.5 Assume from the EC, the responsibility for communicating emergency information to and coordinating with the state and county response org ani zati ons. Thi s responsibility may be delegated.

5.6 Assure continuity of technical and admin strative support, and materi al resources.

5.7 Request additional support as necessary.

5.8 Provide for logistics support for emerge>cy personnel (e.g. transportation, communications, temporary quarters, food and water, sanitary facilities in the field, and special equipment and supplies procurement.)

5.9 Authorize voluntary personnel to exceed 10 CFR 20 limits for personnel exposure, not to exceed 5 rem to the whole body and/or 25 rem to the thyroid (if deemed necessary).

F -ORIDA POWER 5 LIGHT COMPANY Page 3 D TIES OF THE RECOVERY MANAGER~

Oi F-SITE EMERGENCY ORGANIZATION PROCEDURE 1102 12/15/83 References

6. 1 Turkey Point Plant Radiological Emergency Pl an 6.2 St. Luci e Plant Radiological Emergency Plan 6.3 10 CFR 20.403 6.4 10 CFR 50.72 6.5 10 CFR 50 Appendix E 6.6 Offsite Emergency 0."ganization Procedure 1101, Duties of the Emergency, Control Officer.

6.7 Offsite Emergency 0- ganization Procedure 1301, Emergency Roster 7.0 Records F

All significant information, events, and actions taken relative to his duties during the emergency period will,be recorded by the, Recovery Manager, his alternate, or his designee.

8.0 Instructi ons 8.1 Receive, notification of the emergency from the Emergency Control Officer and obtain from him information shown on the attached Checklist 1, as avail abl e.

8.2 Report to the General Office or the Emergency Operations Facility as directed by the Emergency Control Officer.

8.3 When operational at the EOF, notify the Emergency Coordinator and Emergency Control Officer and assume responsibility for communication with off-site agenci es.

8.4 Complete the activities shown on the attached Checklist 2 and periodically assess the status o; all such activities.

8.5 Use additional support agencies as necessary. Phone numbers are supplied in the Offsite Emergency Roster (Procedure 1301) 8.6 .When operational at the EOF provide protective action recommendations to offsite authorities. Appendix A (PSL) or Appendix B (PTP) of this procedure describes the methodology for determination of these protective actions. Protectiv ~ action recommendations should be formulated using avail able pl ant data and radiological conditions.

NOTE: If the EOF has been staffed with a health physicist designated to evaluate off-site doses, he should use the appropriate plant off-site dose calculation procedure (EPIP 3100033E: St. Lucie, EP 20126:

Turkey Point)

1>

PROCEDURE 1102 Page 4 11/15/83 CHECKLIST 1 STATE OF FLORIDA AOTIFÃlla EEE EE AOEII TIME AND DATE OF MESSAGE /'EPORTED BY /

SITE 3. ACCIDENT CLASSIFICATION

[Bj ST. LUCIE UNIT 1 [Aj NOTIFICATION OF UNUSUAL fVENT

[Cj ST. LUCIE UNIT 2 [Bj ALERT

[0 j TURKEY POINT UNIT 3 [C j SITE AREA EHERGf NCY

[E j TURKEY POINT UNIT 4 [03 GENERAL EMERGENCY 4~ TIME AND DATE OF INCIDENT / EMERGENCY TIME DATE

5. INCIDENT INVOLVES:

6. ACCIDENT RELATED INJURIES [Aj NO [Bg YfS [C3 CONTAMINATED INJURY NUMBER OF INJURIES

7. SITUATION INVOLVES:

A 'O RELEASE

[Bj POTENTIAL(POSSIBLE) RELEASE

[Cj A RELEASE IS OCCURRING - EXPECTfD DURATION OR MAGNITUDE

[0] A RELfASE OCCURRED, BUT STOPPED- DURATION OR MAGNITUDE TYPE OF RELEASE IS:

A EOOE

[B] NON-RAD IOACTIVE GASEOUS

[C1 RADIOACTIVE LIQUID

[03 PARTICULATE HATTER

[E3 NOT APPLICABLE

9. WIND DATA:

~J l~IND DIRECTION (FROM) DEGREES 9 10 METERS

[B TCT j WIND SPEED STABILITY CHTi MILES PER HOUR 9 10 HETERS

10. '0 AE E>> 0 ACTI ETOTIOEE:

A NO RfCOHHENDATIONS AT THIS TIME NO IFY THE PUBLIC TO TAKE THE FOLLOWING PROTECTIVE ACTIONS:

No Action Shelter Evacuate 0-2 2-5 Mile Radius Miles for Sectors

~B[Ej ~C 0

[F3 [Gj 5-:.0 Miles for Sectors [H3 [Ij [Jj Hi 1 es [Kl [Lj

11. CUf!RENT OUTSIDE TEMPERATURE: [Ag F 9 10 METERS

12. RELEASE RATE:

NOBLE GASES IOD INES DEFAULT [A3 Ci/sec [cj Ci/sec MEASURED [Bj Ci/sec [03 Ci/sec INSTRUMENT LOCATION N/A Ci/sec N A N/A Ci/sec SUPPLEMENTAL PAGES USED [Ag page s)

Hf.'iSSAGE RECEIVED BY:

PROCEDURE 1102 Page 5 12/15/83 STATE OF FLORIDA NOT IF ICATION MESSAGE FORM

14. N/A (Intentionally left e bl ank)

15. MIND DIRECTION DATA Wind from ~De rees Wind toward Sectors affected

[Aj 349-11 S HJK fBj NNE 12-33 SSW JKL

[C) NE 34'-56 SM KLM

[D7 ENE 57-78 WSW LMN

[Ej E 79-101 W MNP

[F) ESE 102-123 WNM NP Q I Gl SE 124-146 N PQR

[Hj SSE 147-168 NNW QRA

[Jl s 169-191 N RAB fxj SSW 192-213 NNE ABC

[L3 SW 214-236 NE B CD

[M] WSW 237-258 ENE COE

[N3 W 259-281 E DEF

[P j WNM 282-303 ESE EFG

[Q] N 304-326 SE FGH

[R) NNW 327-348 SSE GHJ BAS IC DESCRIPTION OF RELEASE CHARACTERISTICS

16. ESTIMATE OF RADIOACTIVE MATERIAL RELEASED:

NOBLE GASES SOURCE TERM'Aj Ci/sec TOTAL RELEASE: [Bj Ci RAD IOIOD INES SOURCE TERM: [Cj Ci/sec TOTAL RELEASE: [03 Ci

17. ESTIMATE OF PROJECTEO OFFSITE DOSE RATES:

DISTANCE THYROID (mrem/hr) WHOLE BODY (mrem/hr) 1 mile (Site Boundary) [Al [Bj 2 mi 1 es [C1 [03 3 mi 1 es [El fFj 4 mi 1 es [Gj [H]

5 mi1 es miles

[Ij [Jj 10 [X] fLj

18. SPECIAL DATA: [A3 NO [B1 YES MESSAGE RECEIVED BY:

l.

I 0

PROCEDURE 1102 Page 6 12/15/83 CHECKLIST 2 RECOVERY MANAGER Action ~Time Lo

1. 'Time of receipt of initial notification from ECO.

2. Obtain Checklist 1 data (to the extent available)

A. Ini ti al B. Update C. Checklist Complete

3. Establish contact with Emergency Coordinator

4. Organize response teans at the General Office Emergency Center =or Emergency Operations Facility, as specified by the ECO.

5. Relieve Emergency Coordinator of his off-site emergency communications responsibilities when the EOF is manned and operational.

6. Assume responsibility for communications with the following agenci es:

Note: Procedure 1301 contains of f-hours and/or alternate phone numbers.

6. 1 Bureau of Emergency Management State Marning Point Duty Officer, Tal l ah as see (1-904-488-1320) 6.2 Department of Health and Rehabilitative Services, Radi ol ogi c al Duty Of fi cer, Orlando(l-299-0580) 6.3 ~PTP onl a) Dade County EOC (596-8700) b) Monroe County EOC (294-9581)

~PSL onl a) St. Lucie County EOC (461-5201) b) Martin County EOC (287-1652) 6.4 Nuclear Regul.atory Commission Office of Inspection and Enforcement (1-404-221-4503)

PROCEDURE 1102 Page 7 12/15/83 CHECKLIST 2 Cont'd)

Action ~Time Lo

7. Assess status of assigned responsibilities for the fol lowing peri odi cal ly:

7.1 Emergency Control Officer (See Procedure 1101) 7.2 Emergency Security Manager (See Procedure 1104) 7.3 Emergency Technical Manager (See Procedure 1105)

8. Update Checklist 1 data periodically and communicate t~ state and county authorities

9. Assess need for additional off-site support from U.S.

Coast Guard, U.S. Department of Energy, REEF Associates, INPO, NSSS Vendor, Architect/Engineer, others.

10. Assist the ECO with considerations for de-escalation of an emergency when plant and radiological conditions warrant.

Close-out with verbal summary to al'1 Item 6 contacts when directed to do so by the EGO.

. Complete necessary written reports as follows:

Nuclear Regulatory Commission within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Bureau of Emergency Management within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

r PROC EO'E 1102 Page 8 12, 15/83 FIGURE 1 CON'NGL OFFICER VICE RKSIQEHT. MA%EAR EhKAQY NSCNeaTION MANNER ASSIST~ TO VICE RKSIDENT, VICE RKSIOEhfl; CERATE NKNC laNCIKNC CO444PIICATIONS MAll4QKR OF CXNLLNICATICN WCCNKRY MAl4MKR MANOR OF l4NXLAR EhCAQY VICE NKCIIKNT. VINCKIIIIL AFFIARS ASSISTANT MANrMKR OF lWCLEA$k ENEMY .PHCRAL IKOILLATORY IKNKIKNTLTNK NCINCIKV TKCNIICIL NINLINII ~ LKNNIKY M!1NITV NNCNKC CHIEF ENSlhKER, POWUI PLANTS $ 94IOR MCLRITY COIGNIHATOR.

l4JQLEAR ASSISTANT CHIEF KNOI~R, POWER PLJWTS MM4MKR CF &CLNITY I IN IIVNI, CICJIVIKCIINII CIL ENQIhKERINQ CLNITY COIXQINATCN, l4CLEAR MAl4MKR, ELECTRICAL ENQlhCKRINQ

~ICN PROST MANMKR.

TLNKEY POINT

~ICN PAOWCT MANOR.

ST. UJCIK

tl

,1 0

EHERGFNCv Additional notifica- EXECVF IVE COORDINATOR tions per Plan and VICE PRESIDENT procedures L2 Plant Duty call Supervisor alternates ESM or NEDO CD I

System Opns.

2 m I h) O Pover W C:

Coordinator CJl Pl Staf f=- Q7 H w

EIM 47 Support Nn'rsS:

<<Verify that EC has made or is in the process of making

• Federal and these notifications (for Unusual Event & Alert). For State Agencies Site brea Emergency & General Emergency, delegate com-munications responsibilities to these agencies to RM (after the EOF is manned and operational).

1 Notifications made pe" Procedure 1101 2 Notifications made per Procedure 1102

~P2 use 2 Notification Flov

1l

~~

I Ib 0

PROCEDURE 1102 Page 10 12/15/83 APPENDIX A PROTECTIVE ACTION RECOMMENDATIONS - ST. LUCIE PLANT FPL is required to provide county and state governmental authorities with recommendations for protective actions to be taken by the public during radiological emergencies at the St. Lucie Nuclear Power Plants.

The responsible authorities are the State Bureau of Emergency Management (BEM) and St. Lucie and Martin Counties Offices of Disaster Preparedness.

Protective action recommendations should be made utilizing all of the avail able data. This includes plant status (Fig. A-l), off-site dose projections and/or field monitoring data (Fig. A-2 or A-3). The more conservative recommendations should be made.

Due to the large political and legal ranifications of these recommendations and the potential impact on FPL, the following format and content should be used.

1. In any case where a GENERAL EMERGENCY has been declared, the minimum protective action recommendation shall be: "Shelter all people within a 2-mile radius and 5 miles in the downwind sectors".

If the GENERAL EMERGENCY has been declared due to lass of physical control of the plant, including the Control Room or any other area(s) vital to the operation of the reactor system (as defined in the Security Pl an), the minimum protective action recommendation shall be: "Evacuate all people within a 2-mile radius from the pl ant".

If the emergency has been classified as a GENERAL EMERGENCY 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 that has been classified is not a GENERAL EMERGENCY and the offsite doses are LESS THAN 0.5 Rem whole body or 1 Rem to the thyroid at 1 mile over the projected duration of the release, no protective action is recommended. This should be reported to BEM and other outside agencies who inquire as:

"Based on our current assessment of all the information now avail able to us, Florida Power and Light Company recommends that you consider taking no protective actions (PA) - NONE. This recommendation may change in the future, but we cannot now s@ when to."

it may change or what it may change NOTE: If a controlled release is necessary to stabilize plant conditions or an uncontrolled release is anticipated, determine the approximate source term, duration of the release, and the projected offsite doses prior to making any protective action recommend ati ons.

PROCEOURE 1102 Page 11 12/15/83 PROTECT I VE ACTION RECOMMENDATIONS continued)

3. If the emergency has been declared and offsite dose information is avail able (from any credible source), use the dose information to select the appropriate table. Use either Figure A-2 (PA with offsite dose estimates for greater than or equal to 2-hour duration) or Figure A-3 (PA with offsite dose estimates for less than 2-hour 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 Rem at 1 mile, 2 Rem 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 5 Light Company recommends that you consider taking the fol lowing protective actions

i. Evacuate all personnel betwe'en a 0 and 2 mile radius from the pl ant.

ii. Shelter all personnel between a 2 and 5 mile radius from the plant who are in sectors J, K 8 L (refer. to State of Florida Fixed Nuclear Facility Notification Message Form, Page 4 Entry 10) iii. No protective action is recommended between a 5 and 10 mile radius from, the pl ant.

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'he recommended protective actions and formul ate the appropriate 'message in the above format and transmit it to BEM.

5. Protective action recommendations for a child have been incorporated into the figures.

Ti PROCEDURE 1102 'age 12 12/15/83 FIGURE A-1

()T. LUCIE PLANT PROTECTIVE "ACTION RECOMMEt4)ATIONS BASED ON Pl ANT CONDITIONS DISTANCE FROM PLANTIAKCO4E14)ATION 2 5 MILES 5 10>>LES

~AL E4KAGENCY GOSK LILT LOSS NO OF CONTAQL 5 (CR) 5 tDW)

QF PLANT 1 (5)

E (CR)

CHAM ONTA I p4M4 RA% (2 (CORK DAMA FAII LjK HAS OCQJKO OR E (CR) (DW) i 5 (RS) 5 (CR) 15 IMMI~

(2)

E (CA) E (CR) 5 (CA)

SEE FOOTNOTE (i)

CONTA I tACN FAILLE HA5 E" (CA) E (CA) (DW) ~ 5 (RS)

OCCLiKD QR IMMI K (CR) E (CA) (DW) ~ 5 (AS)

SEE FOOTNOTE (4)

(I)

'2)

POTENTIAL CORE LCLT. ANY CAUSE IN EPIP S)00022K. 'CLASSIFICATION OF EL@AGENCY.

IKPfKSKNTS GREATER THAN 1002 GA5

~ IATI PAOTKCTIVE ACTION RECOMvChOED 5-RCLTKAING AECO4CI4)ED GAP ACTIVITY IN QNTAlhLCHT.

K~ACVATION AECQIACl4)ED 5EE LOSS OF CQN-Al aCMt (4) DETULIINE tOR IMMI~

~~ ~~

INTKRGAITY. ~IP 5100022K.

VSWG A

RELEASE 15 IN PROGRKSS TYPK CON)ITIQNS DW~IN) i 2 AS~ INING 5ECTORS ADJOINING SECTORS CAMOLOLETE CIACLE AAOLPO PLANT AT LI5TKD ON hEXT PAGE. SPECIFIED 015TANCE (IO LOSS Of CONTROL Of VITAL REACTOR L OPERATE AREAS TO anRuOKRS.

Oa.& I ISS IR

e 0

PROCEDURE 1102 Page 13 12/15/83 FIGURE A-1 (continued) 55RIE PIAIII PROTECTIVE ACTION RECOMMENDATIONS BASED 03 PLANT CONDITIONS If a "PUFF" type release is imminent or in progress a: indicated by the following condi ti ons:

(1) Containment failure has occurred or is imminent, and (2) Rate of rel ease i s much greater than designed leak rate, and (3) Either the total or major portion of radioactivity is projected to be released within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or less, then in addition to the appropriate protective action recor~mendations the following statement and information should be given:

"Florida Power 5 Light Company recommends sheltering those areas that can't be evacuated before plume arrival."

WIND FROM WIND TOWARD SECTOR DIRECTION DEGREES DIRECTION SECTORS AFFECTED CA] N 349 - 11 S HJK CB] NNE 12 - 33 SSW JKL Ccl NE 34 - 56 SW KLM LD] ENE 57 - 78 WSW LMN CE] E 79 -101 W MNP CF] ESE 102 -123 WNW NP Q CG] SE 124 -146 NW PQR SSE 147 -168 NNW QRA CJ] S 169'-191 N RAB CK] SSW 192 -213 NNE ABC LL] SW 214 -236 NE B CD CM] WSW 237 -258 ENE C DE CN] W 259 -281 E DEF LP] WNW 282 -303 ESE EFG CQ] NW 304 -326 SE FGH CR] NNW 327 -348 SSE GH J

PROCEDURE 1102 Page 14 12/15/83 FIGURE A-2 PROTECTIVE ACTION W(X44UK?4)ATIONS IASEI) ON ACTUAL aESS THAN 2 HOLR DELATION) WITh OFFSITE DOSE ESTIMATES) uSm IN TO FIR%K g-3

~ OCTO CN 0K

0 2 MILES UK l Ml VALlE QK 2 MI V UK 5 5 IO MILE5 Mt VPua C I) N x I)5 > Il)

IIEET SJT C ll) c L5 LIT jWTLS c 50 c 2SD E i IWl 5 0I5I E IWl + 5 IRSI IF TlK ORATION OF TlK FCLEA5E IS PACLKCTXD TO M <SKATER ~ CN N - NO PROTECTIVE ACTION KCO4lQIED

+Tlat ~

ECLIAL TO 2 54%%5 Llà A ~3e

~ l MILE AFFECT5 PROTECTIVE ACTICHS FROM 0 2 MIL!5 5

E DW

- SCLTRRIFC IKCOv$4ED

- EVACUATION IKCQ4l9IED

- DOWNWlle + 2 ADJOININO SECTORS TlC 00% ~ 2 MILE5 AFFEC;T5 PROTECTIVE ACTIONS FACULA 2-5 MILE5 R5 lSAAINI% SECTORS Tl+ ÃÃK ~ 5 MILE5 AFFEC:T5 PROTECTIVE CR CO4RETK CIRCLE AROIPO PLANT AT ACTICH5 RKM 5 10 MILES ~CIFIED DISTANCE TlK OAK ~ IO MILES CAN IK VRD TO EVALUATEPROTECTIVE ACTICNS FOR CHEATER DISTANCE

PROCEDURE 1102 Page 15 12/15/83 FIGURE A-3 PROTKCTIVK ACTION RECO4LKhATIONS 8ASED ON ACTQAL RELEASE (G$ KATER THAN OR EQUAL TO 2 HOCH DILATION WITH OFFSITE'OSE ESTIMATES)

MSED IN TO FIGLNE A 2 N4t TNTROIO aXr

~ 0 2 MILES ~ MILES 5-10 MILE5 OCR m4t I Ml VALLK QK2MI V QK 5 MI VALLE c 14 N

> QS 0/T j IAt SIT 5 (C$D -5 Wl c IAt c 25 2 25 c

NiT 54t c SlT 2LO EeW) iSIRSI EeWliSN 5 "CCRC E EDWI i5 N ATI IF TtC DNIATION tK Tt+ IKLEASE IS N - NO PROTECTIVE ACTION IKCOIACt4)ED PAOXCTXD TO M LES5 T14AN CN E~ r iTl% ~TO 2 tCX$5 UK A.2

~ 1 MILE AFFECT5 PROTECTIVE 5 SCLTERIW IKCCLC)4ED

~ UK' ACTICN5 E EVACUATION iKCOMrEM)ED 2 MILE5 DW - DOWNWI% i 2 ADJOINlt4 ACTORS

,TtK

~

~ 2 MILX5 AFFECTS PROTECTIVE ACTICN5 FACM MILE5 R5 IKL4AINING &CTtÃ5 TtK OAK ~ 5 MILES AFFECT5 PROTECTIVE CR - CCL5%ETK CIRCLE AAOLJQ PLANT AT ACTICP45 RK54 5 10 MILES PACIFIED 0I5TANCE TlK OCR ~ 10 MILES CAN IK URD TO EVALUATEPROTECTIVE ACTICHS FOR <SKATER DISTANCE

PROCEDURE 1102 Page 16 12/15/83 APPENDIX B Protective Action Recommendations - Turke Point Pl ant FPL is required to"provide county and state governmental authorities with recommendations for protective actions to be taken by the public during radiological emergencies at the Turkey Point Nuclear Power Plant. The responsible authorities are: (1) The State Bureau of Emergency Management, and (2) Dade and Monroe Counties. Due to the large political and legal ranifications of these recommendations and the potential impact on FPL, the following format and content should be used.

The contents of the recommendations are to be determined by using Figures B-1 through B-3 of this procedure as follows:

1. In ANY CASE where a GENERAL EMERGENCY has been cl assified, the MINIMUM

~

protective action recommendations SHALL be: Shelter all people within a 2-mile radius and 5 miles downwind from the plant. If the emergency has been classified as a General Emergency and no offsite dose estimates or field survey results are available, refer to Figures 8-1 and evaluate of fsi te protective action recommendations.,

NOTE: If a controlled release is necessary to stabilize pl ant conditions or an uncontrolled release i s anticipated, determine the approximate source term, duration of the release, and the projected offsite doses prior to making any protective action recommend ati ons.

2. If the emergency classification is not a GENERAL EMERGENCY and the offsite doses are less than 0.5 ran whole'body or 1 rem to the thyroid at 1 mile over the projected duration of the release; no protective action is recommended. This should be reported to BEM and other outside agencies who inquire as:

"Based on our current assessment of all the information now available to us, Florida Power and Light Company recommends that you consider taking no protective actions. This recommendation may change in the future, but we can not now say when change to."

it may change or what it may

3. If the emergency has been declared and, offsite dose information is available (from any credible source), use the dose information to enter the appropriate estimated offsite table (based on projected release duration of 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 />, use Figure B-2; for 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-B-3). The appropriate recommendations can then be made.

~Exes le: A release has occurred at the Turkey Point 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 accumul ated thyroid dose (i.e. accumul ated over a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration) is 10 rem at 1 mile, 2 rem at 2 miles, and less than 1 rem at 5 mi l es.

PROCEDURE 1102 Page 17 12/15/83 Referring to -Figure B-2, the following recommendation should be made:

"Based on our current assessment of all the information now avail able to us, Florida Power 8 Light Company recommends that you consider taking the following protective actions:

A. EVACUATE all people between 0 and 2 miles from the pl ant.

B. SHELTER all people between a 2 and 5 mile radius from the plant who are in sectors J, K, & L (refer to Emergency Information Checklist, item 12).

1 C. No protective ac'tion is recommended between a 5 and 10 mile radius from the plant.

This recommendation m~'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 figure for those conditions, determine the recommended protective actions and formul ate the appropriate message in the above format and transmit it to BEN and local agenci es.

5. Protective action recommendations for a child have been incorporated into the figures.

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PROCEDURE 1102 Page 19 12/1! /83 TURKEY POINT PLANT FIGURE B-1 (cont'd)

PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT COt'DITION!S - PTP

• Core Melt Se uence:

A Core Melt Sequence condition is based on a postulated reactor accident in which the fuel melts because of overheating. Plant conditions that qualify as a core melt sequence are:

1. A known LOCA as defined in Site Area Emergency and failure of ECCS to deliver flow to the core has occurred, resulting fn clad damage as fndfcated by Containment High Range Radiation Monitor alarming; OR

2. Reactor trip on low steam generator levels, with wide range levels decreasing toward zero, with one of the following two:

a. Loss of main condenser, loss of auxiliary feed flow, (with high head safety injection capability);

OR b.. Loss of main condenser, loss of auxiliary feed flow, and no high head safety injection capability, and 30 minutes has elapsed with no low head safety injection capability or auxiliary feed flow; OR 3~ A known LOCA as defined in Site Area Emergency has occurred and one of the following:

a. RHR flow indicator FI-*-605 reads zero for 1/2 hour after recirculation phase is attempted, and RCS temperature is rising; OR

b. Failure of containment spray and emergency coolers to prevent containment temperature from rising excessively.

Refer to Emergency Procedure 20103, Classification of Emergencies.

PROCEDURE 1102 - 12/15/83 Page 20 Turkey Point Plant FIGURE B-2 PROT'.CTIVE hCTION RECOMMENDATIONS BASED ON hCTUAL RELEASE DOSE ESTIMATES (GREATER TYZ:: OR EOUAL TO 2 HOU'R JRATION) WITH OFFSITE

. (used in preference to Figure B-1)

DISTANCE FROM PLANT/RECOMMENDATIONS~

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

. (REM) use 1 mil use 2 mile use 5 mlle value value value

< 0.5 0 5 1.0 S (CR) S (DW) S (DW) but but

< 1.O 2. 5

> l.o E (CR) E (DW) + E (DW) +

but but 5.0 <25.0 S (RS) S (RS)

I E (CR) E (CR) E (DW) +

> 5.0 > 25.0 l S (RS)

Note: If the duration of the release is pro)ected 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 Figu]'e B>>3.

• LEGEND OF ABBREVIATIONS

&he dose 8 1 m.le affects protective actions from 0-2 miles N- No protective action recommended S- Shelte~inn recomnended The dose 8 2 miles affects protective E- Evacuation recommended actions from 2-5 miles DW- Downwind sector + 2 adjoining sec ors The dose 9 5 m'les affects protective RS- Remaining sectors actions from 5-10 miles CR- Complete circle around plant h

at specified distance The dose 8 10 miles can be used to evaluate protective fcr greater distances action~

~

PROCFDURE 1102 Page 21 12/15/83 Turkey Point Plant n

FIGURE B- 3 PROTECTIX'E ACTION RECOMMENDATIONS BASED ON ACTUAL RELEASE (LESS'HAN 2 HOUR DURATION) WITH OFFSITE DOSE EST MATES (used in preference to Figures B-1)

DISTANCE FROM PLANT/RECOMMENDATIONS~

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

OR (REM) use 1 mil use 2 mil use 5 mile value value value

< 0.5 < 1.0 N I

0.5 > 1.0 but but S (CR) S (DW) S (DW) 1.0 2.5 I

1.0 2- 5 but but S (CR) S (CR) 5 (CR) 5 0 25.0 I

5.0 25.0 E (CR) E (DW) E(DW) +

I S (CR) S (CR)

'.QTE: If the duration of the release 'is projected to be 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 />, use Figure B-2. I

<<LEGEND OF ABBREVIATIONS

&he dose 8 1 mile affects protective - No protective action recommended actions from 0-2 miles N S - Sheltering recommended The dose 9 2 miles affects protective E - Evacuation recommended actions fram,2-5 miles DW- Downwind sector + 2 adjoining sect RS- Remaining sectors The dose 8 5 miles affects protective CR- Complete circle around plant at actions from 5-10 miles specif'ed distance The dose 9 10 miles can be used to evaluate protective actions for greater distances.

h PROCEDURE 1102 Page 18 12/15/83 TURKEY POINT PLANT FIGURE B-1 PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT COPDITIOPS - PTP GENERAL NO Line 1 EMERGENCY YES CHRRM NO NO LINE 2

> 1e3 E+4 SE R Hr YES Con"ider 2 mi e YES precautionary evacuation and shelter other parts of the downwind plane exposure pathway

~

see line 3 CORE

'ELT SE UENCE IMM NENT LOSS OF CONTAINMENT NO LIh'E 4 INTEGR ITY YES LINE 5 LINE 0-2 MILES 2-5 MILES 5-10 MILES Ni N S (CR) S (DW) fi E (CR) S DW) S (DW)

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

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

LEGEND OF ABBREVIATIONS N = No Protective Action Recornended

= Shel tering Recormended

= Evacuation Recormended W = Downwind Sector + 2 Adjoining Sectors RS Remaining Sectors CR ~ Complete Circle Around Plant at Specified Distance See Core Nelt Sequence explanation on the followinu oaoe

+ ~ Represents 100~ gas gap activity in containment

PROCEDURE 1102 Pag . 19 12/15/83 TURKEY POINT PLANT FIGURE B-1 (cont'd)

PROTECTIVE ACTION RECOHHENDATIONS BASED ON PLANT COt'DITIONS - PTP Core Melt Se uence:

A Core Helt Sequence condition is based on a postulated reactor accident in which the fuel melts because of overheating. Plant conditions that qualify as a core melt sequence are:

1. A known LOCA as defined in Site Area Emergency and failure of ECCS to deliver flow to the core has occurred, resulting in clad damage as frdicated by Contaii>>vent High Range Radiation Monitor alarming; OR

2. Reactor trip on low steam generator levels, with wide range level .

decreasing toward zero, with one of the following two:

a. Loss of main condenser, loss of auxiliary feed flow, (with high head safety injection capability);

OR

b. Loss of main condenser, loss of auxiliary feed flow, and no high head safety injection capability, and 30 minutes has elapsed with no low head safety injection capability or auxiliary feed flow; OR

3. A known LOCA as defined in Site Area Emergency has occurred and one of the following:

a. RHR flow indicator FI-*-605 reads zero for 1/2 hour after recirculation phase is attempted, and RCS temperature is rising; OR

b. Failure of containment spray and emergency'coolers to prevent containment temperature from rising excessively.

Refer to Emergency Procedure 20103, Classification of Emergencies.

PRPCfDURf 1102 - 12/1! /83 Page 20 Turkey Point Plant FIGURE B-2 PROTECTIVE ACTION RECOMMENDATIONS BASED ON ACTUAL RELEASE (GREATER THAN OR EOUAL TO 2 HOUR DURATION) WITH CFFSITE DOSE ESTIMATES (used in preference to Figure B-1)

DISTANCE FROM PLANT/RECOMMENDATIONS*

WHOLE BODY DOSE (REM) .,

'OR THYROID DOSE (REM) 0" 2 MILES use 1 value mil 2-5 MILES use 5-10 MILES 2 mile use 5 mile value value N N

<0.5 -

)

< 1.0 0.5 1.O S (DW) but S (CR) S (DW) but 1.0 2. 5 1.0 l 2-5 E (CR) E (DW) + E (DW) +

but but 5.0 <25.0 S (RS) '(RS)

I

>25.O E (CR) E (CR) E (DW) +

> 5.0 )

S (RS)

If the duration of the release is projected to be'ess than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 1'ote:

use Figure B-3.

+LE~~ OF ABBREVIATIONS

&he dose 8 1 mile affects protective actions from 0-2 miles N - No protective action recommended

- Shelte~ing recommended The dose 8 2 miles affects protective E - Evacuation recommended actions from 2-. 5 miles DW- Downwind sector + 2 adjoining sectors The dose 9 5 miles affects protective RS- Remaining sectors actions from 5-10 miles CR- Complete circle around plant at specified distance The dose 8 10 miles can be used to evaluate protective actions for greater distances.

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Page 1 of 20 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE

//3100022E, REV. 10

1.0 TITLE

CLASSIFICATION OF EMERGENCIES

2.0 APPROVAL

Reviewed by Facility Review Group ust 8 1975 Approved by K. N. Harri 19~

Revision ~ R iewe by Faci iey Group g 108 I 0 'r 19 c, Approved by V wr. Res. . < 6 19'/

Revision 9 R ewe b Facil ty eview Group jR 19 P/

Approved by P. Pwr. Res.

LL Revision 10 Rev'gdgby QG cp uoCA4 9 1982.

Approved by 4C A Dir., Nucl.".Energy -/ 1982.

0 SCOPE:

~4 .1 ~Pur ose This proce re provides instructions on the classi-fication emergencies at St. Lucie Plant.

.2 Discus on In o der of increasing seriousness, these are:

Unusual event Alert Site area emergency General emergency A gradation is provided to assure fuller. response preparations for more serious conditions.

This procedure implements the St. Lucie Plant Emergency Plan.

Page 2 of 20 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMBFZING PROCEDURE g3100022Ep REV. 10

3.0 SCOPE

Continued 3.4 Definitions 3 4 1 Unusual Event - This classification is represented by Off-normal events or conditions at the plant for which no sig-nify.cant degradation of the level of safety of the plant has occurred or is expected. Any releases of radioactive material which may have occurred or which may be expected are minor and constitute no appreciable health hazard.

3.4.2 Alert - This classification is represented by events which involve an actual or potential substantial degrada-tion of the level of safety of the plant combined with a potential for limited uncontrolled releases of radioactivity from the plant.

3.4.3 Site Area Emer enc - This classification is composed of events which involve actual or likely major failures of plant functioas needed for protection of the public combined with a potential for significant uncontrolled releases of radioactivity from the plant.

3.4.4 General Emer enc - Th& classification is composed of events which involve actual or imminent substantial core degradation and potential loss of containment integrity combined with a likelihood of significant uncontrolled releases of radioactivity from the plant.

4.0 Precautions 4.1 Conflictin Information When apparently conflicting information is available, the condition shall be classified at the most serious level indicated.

4.2 Jud ental Decision If, in the 5udgment of the Nuclear Plant Supervisor (Emergency Coordinator), a situation is more serious than indicated by instrument readings or other parameters, the emergency condition shall be classified at the more serious level.

Page 3 of 20 0 I FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 8'3100022E, REV. 10 5.0 Res onsibilities 5.1 Plant Personnel All plant personnel are required to promptly report the existence of an emergency condition to the Nuclear Plant Supervisor by the fastest means possible.

5.2 Nuclear Plant Su ervisor 5.2.1 The Nuclear Plant Supervisor shall promptly classify abnormal situations into one of the four defined categories.

5.2.2 If the diagnosis indicates that the condition is classified as an Alert, Site Area Emergency, or General Emergency the Nuclear Plant Supervisor shall declare an emergency.

5.2.3 IS an emergency has been decreed che Nuclear Plant Supervisor shall become the Emergency Coordinator and retain this position until relieved.

6.0

References:

6.1 St. Lucie Plant Radiological Emergency Plan 6.2 E-Plan Implementing Procedure 3100029E, Duties of Individual Discovering Emergency Condition 6.3 E-Plan Implementing Procedure 3100021E, Duties of Emergency Coodinator 7.0 Records and Notification The basis for classifying an emergency condition shall be recorded.

Page 4 of 20 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE

//3100022E, REV. 10

8.0 Instructions

8.1 The Nuclear Plant Supervisor shall initially classify a situation as soon as possible after becoming aware of the situation. The classification shall be made on the basis of readily available observations and/or calculations and should not rely on sampling and laboratory analysis.

NOTE: Within 15 minutes after the initial classification, the state and/or local agencies listed in the appropriate check list in EPIP 3100031E shall be notified. /Rlo 8.2 If subsequent information of a more detailed nature (e.g.

sampling results) becomes available after the initial classi-fication has been made, the event shall be reclassified by the Emergency Coordinator if appropriate.

8.3 The Nuclear Plant Supervisor shall classify events in accordance with the attached Classification Tables. The event shall be classified by matching the actual situation to the one most closely approximating it in the tables.

8.4 Classification Tables are provided for the following categories:

I Primary Depressurizatien Miscellaneous .

Abnormal Primary Leak Rate Abnormal Primary/Secondary Leak Rate Loss of Secondary Coolant

4) Accident Involving Fuel Fuel Element Failure Fuel Handling

2) Abnormal Radiation, Contamination of Effluent Release Values Uncontrolled Effluent Release High Radiation Levels in Plant

3) Fires Lasting More Than 10 Minutes

8) Degradation of Control Capabilities Engineered Safety Features Loss of Containment Integrity Loss of Alarms

Page 5 of 20 ~~

FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE

/33100022E, REV. 10

8. 0 Ins tructions:

8. 4 (Continued)

9) Hazards to Station Operation Aircraft Toxic or Flammable Gas Onsite Explosion Missile Turbine Failure

7) Electrical Malfunctions Loss of Power

10) Security

5) Natural Emergencies Earthquake

, Hurricane Tornado Water Level Abnormal

6) Miscellaneous Events Contaminated Injury Abnormal Temperature Abnormal Shutdown

Page 6 of 20 PRIMARY DEPRESSURIZATION Page 1 of 4 EVENT UNUSUAL EVENT SITE AREA EflERGENCY CENERAL EMERCEHCY MISCELLANEOUS h) Un lanned lniciacfon of ECCS Loss of 2 of 3 fission roducc

~B c coocf s e barrier ufth otencial for loss

l. ECCS punps running as indi- of the third cated by motor amps, AND

2. ElXS header isolation valves (hny tuo of the follouing coudf-open as indicated by valve cions exist and the third is position indication lights, imminent.)

OR B) Safct or relief valve fails 1. Confirmed fuel clad damage.

co close 2. Confirmed 10CA

1. Reactor coolanc s seem RCS 3. Confirmed concafnmcnt inte-

a. Indication of flou grity breached and cannot be through prcssuriter restored.

relief valves as indi-cated on che acouscic valve f lou monicor, AND

b. RCS prcssure drops to

< 1600 pain.

2. Main Steam S stem

a. Unusual decrease in pressuriter pressure aiul level uich decreasing Tave AND

b. Abnormal drop in steam genuracur pressure to less than 500 psia, AND

c. Visual or audible verifi-cacion or stcam relief lffcing.

ACTION 1. Complete accions lisced on 1. Complece actions listed on the UNUSUAL EVENT CllECKLIST. CEHERAL EMERGENCY CHECKLIST.

Pug<< 7 of 20 PRIHARY DEPRESSURIZATION Sheet 2 of 4 CLASS EVENf UHUSUAL EVENT ALERT SITE AREA EHERCENCY CENERAL EHKRCEHCY ABNORHAL PRIHARY RCS leak<< e rester chan ulloved RCS leak rehcer chan 50 LOCA reater than cu ucic uf A release has occurred or is in LEAK RATE b Technical S ecificacions rimar to atmos here char'in um s progress resulting in:

A. RCS vater inventory balance indicates (1) Charging/lecdovu mismacch (1) Unusual decrease in pres- LOCA Dose Calculutiou QPIP

1. greater 1 gpm unidentified backed up by RCS vacer. surirer level and pressure 3100033K Appendix B vorksheec leakage, OR inventory balance Indicating vith conscant T(ave), AHD values in excess of 1 R/IIR

2. greater than 10 gpm identi- > 50 CPH and <132 gpm (2) Hakeup rate greater chan (vhole body) or un integruced fied leakage, OR leakage, AHD capacicy of 3 charging dose of 5R (chyroid) or (2) Concainmenc or plane vent pumps (132) gpm) AIID cont<<lament high rungu radiation B. Inspection reveals any RCS radiation process. monitor (3) Concainmenc pressure .>2 monitor gfeater than nr equal to pressure boundary leakage. reading above pormal. psig, or containmcnc 1.47 x 10> R/lh (post IiICA radiation monitors indi- monitors greater. thun 1000 mr/hr cate <<bove normal values. if CIIRRH inoperablu)

ACfION 1. Complete actions listed on 1. Complete uccions listed on 1. Complete uccions listed l. Complete acclons listed on the UNUSUAL EVENT CHECKLIST. ALERT CHECKLIST on SITE AREA EHERCEHCY GENERAL fHERCEHCY CNECKI.IS'f CIIECKLIST

/Hl 0

c Page 8 of 20 PRIHARY DEPRESSURIZATION Sbeec 3 of 4 CLASS UNUSUAL EVEHT ALERT SITE AREA EHERCENCY CEHERAL EHERCENCY ABNORHAL PRIHARY RCS PRI SEC Leaka e Creater Than Ra id ross failure of one steam Rs id failure of sccsm TO SECONDARY 1 CPH ~enerator tuba wi h loss of cneracor cubes with a lose of i char in off-site ower > char in

l. RCS Mater invcncory balance indicaces:

~ic off~ice wer w Lc.

1. Unusual decrease in prcssuriser (1) Unusual decrease in pres-

h. Greater than 1 CPH pressure and level with surizer pressure and level unidcncified leakage AND conscanc T ave., followed by; with conscant T(ave), AND B. Blowdown process monitors 2. Above normal or increasing (2) Above normal readings on and condcnsace air effector steam generator blowdown and radiacion process monitors process monitor reading condensate air e)cctor radia- for steam generator blow-above normal or tion process monitor readings, down and condensate air increasing. ~AND e$ eccor, AND

3. Loss of che 6.9 KV and 4.16 (3) Loss of the 6.9 kV and KV busses (IA1, IA2, IBl, IB2) 4.16 kV busses (lhl, lA2, OR 151, 182), AND Ra id failure of steam cnerator (4) Simultaneous unusual tubes > char in ca acit increase in one steam generator's prcssure and

l. Unusual decrease in prcssurirer level.

pressure and level, with constant Tave> ANO'I

~ Simultaneous unusual increase in one stcam generator's pressure and level followed by;

3. Above normal steam generator blowdown and air e)actor radiation process monitor readings.

ACTION 1. Complete actions listed on 1. Complete actions listed on 1. Complete accions lisccd che UNUSUAL EVENT CllECKLIST. ALERT CNECKI.IST ~ on SITE AREA EHERCENCY CHECKLIST.

PRIMARY DEPRESSURIZATIOH Page 9 of 20 Sheet 4 of 4 UNUSUAL EVENT SITE AREA EHERGEHCY GENERAL EMERGENCY LOSS OF SECONDARY Ra id de ressurizacion of Ma or steam leak wicb rester Ma or steam leak with rester COOlANT seconder side with no rimar than 10 rimar seconder than 50 rimar seconder co seconder leaks e. leak race leak race and fuel dame e indi-dated

1. Unusual decrease in pressurize l. Unusual decrease in pressurizei pressure and level with pressure and level, with 1. Unusual decrease in decreasing Tave AND decreasing Tae, ~AND'.

pressurizer pressure and level with decreasing Tave/

2. Simultaneous abnormal drop in Abnormal drop in main sceam ~AND Main Steam or steam or sceam generator pressure generator pressure co less to < 500 psia, ~AND 2. Abnormal drop in main steam than 500 psia. or steam generator pressure

3. Sceam generator blowdown and to < 500 psia, ~AHD.

condensate sir effector radiation process monitors 3. Steam generator blowdown and indicate above normal, (OR, condensate air effector known pri-sec leak of > 10 radiacion process monitors Bpm) ~ indicate above normal, (OR, known pri-sec leak of >50 gpm)-

4. Fuel damage as indicated by last known primary sample.

ACTION 1. Complete actions lisced on 1. Complete actions listed on 1. Complece accions listed cbe UNUSUAL EVBIT CHECKLIST. ALERT CHECKLIST. on SITE AREA EMERGENCY CHECKLlST.

Page 10 of 20 ACCIDEtlT INVOLVIHG FUEL CLASS UNUSUAL EVEHT SITE AREA ENERGEHCY GEHERAL EHERGENCY EVEHT I'UEL ELENEftf Fuel dame e indication Severe loss of fuel claddin Cora dame e uich fnade uate core h release has occurred OR is FAILURE includfn coolant um failure coolfn determined b in progress resulting in:

h. Lecdou0 iodine process monitor leadin to ross fuel failure Loca Dose calculation alarm folloucd by (1) RCS 1-131 activity > EPIP 3100033K Appendix B uork-,

B. Confirmed RCS sample indicating (1) Letdown iodine process 275 uCi/ml, sheeC values in excR.ss of I R/Nk

l. Coolant accivicy greater monitor alarms, AHD (2) RCS temperature within 20 (uholebody) or an integrated than the Tech Spec limit for (2) RCS 1-131 activity > of T(sat), AHD dose of 5R (thyroid) or iodine spike Figure 3.4-1 AND 275 uCi/ml (3) Loop AT >44 P concafnox."nt hfph ra~ge radiation

2. Coolanc activity greacer chan monitor > 1.47 x 10 R/Nr 100/E uci/ ram s ecific acc-(post IANNA monicors >1000 mr/hr FUEL NANDLIHG Fuel handlin if CNRRH fnoperablu) accident uhich Ma or dame e co s ent fuel ACCIURIIF results in che release of radfo- in containment or Fuel Handlin /Rlo accivit to contafnmenc or Fuel ~RIIA LA Handlin Buildin (1) Step increase in che (I) Direct informacion from fuel readings of radiation handlfng personnel indi- monitors in che plane vent cating that an'rradiated and/or in the fuel handling fuel assembly has been building, AND damaged and gas bubbles are (2) Damage to more than onu escaping, AND fuR:1 assembly, OR (2) Associated area or process (3) Uncovering of more chan one monitor channels are spenc fuRAI assembly fn che alarming. spent fuel pic.

ACI'IOII 1. Complete actions listed on 1. Complete actions listed 1. Complete accions listed 1. Complete actions liscR.d on thc UHUSUAI, EVENT CHECKLIST. on ALERT CHECKLIST on SITE AREL EHERGENCY GENERAL EHERGENCV CHECKLIST.

CHECKLIST

ABNORHAL RADIATION CONTAHIHATION OR Pagh ll of 20 EFFLUEHT RELEASE VALUES CLASS UNUSUAL EVENT SITE AREA EIIERGENCY GENERAL EHERCL'HCY EVENT UNCONTROLLED Radiolo ical affluent Tech. S ecs. h release has occurred'or is in h release has occurred or is h release has occurred or is EFFLUEHT RELEASE Limits exceeded progress thee 1s 10 cimes che in progress resulting in: in progress resulcing 1n:

1. Plant effluent monitor(s) T.S. limit (as shown by sample/ LOCh Dose Calculation EP1P LOCh Dose Calculation EP1P exceed alarm secpoinc(a) survey) 3100033K Appendix B uorksheet 3100033E Appendix g uorksheet followed by values 1n excess of 50 HR/llR values in excess of 1 R/llR

2. Confirmed analysis resulcs for (whole body) 250 HR/HR (whole body) or an Integraced gaseous or liquid release (thyroid) for I/2 hour OR dose of 5 R (thyroid)or uhich exceeds Tcchnical Speci- 500 HR/llg (vhole body) 2500 contalnmenc high range radiation fication limits. HR/NR (thyroid) for tuo min ac monitor > 1.47 x 105 R/hr thu site boundry. or (Pose 1 or 2 Honitor >1000 mr/hr Containment Nigh Range if CNRRH inoperable)

Radiar1on Honitor >7.3 x 103 R/hr RIU ~

NICll RADIATIOH High radiacion levels or high LEVELS IN PLANT airborne contamination which indicaces a severe degradacion in the control of radioactive materials (1) Installed radiabion monitor-1ng scacions indicate abnormally high radiation levels, OR (2) Installed airborne particu-late or iodine accivicy monitors indicate abnormally high levels, AND (3) Levels >1000 times normal are confirmed by area surveys and/or analysis of grab samples.

ACTION

1. Complete accions lisced on l. Complete actions listed 1. Complete actions listed 1. Complete actions listed on on ALERT CllECKLIST on SITE AREA EHERGEHCY GENERAL EHERGEHCY CllECKLIST UNUSUAL EVENT CHECKLIST CNECKI.IST

FIRES LASTING BORE Page 12 of 20 TIUIN 10 MlNUTES CLASS UNUSUAL EVENT ALERT S1TE AREA ENERCENCY GENERAL ENERGENCY Uncontrolled fire not involving Uncontrolled fire, potentially Fire resulting in degradation a safety syscea, but requiring affecting safety systems and of safecy syntone.

off-site support. requiring off-site supporc.

ACY ION 1. Cosplece <<ecions lisced on 1. Couplers accions listed 1. Cospleca actions listed the UNUSUAL EVENT CNECKL1ST. on ALERT CUECKLIST on S1TE AREA EHEKCENCY CUECKLIST

Page 13 of 20 DEGRADATION OF CONTROL CAPABILITIES Sheet I of 2 CLASS EVENT UNUSUAL EVENT SITE AREA ENERGEHCY GENERAL ENERGEHCY EHGLNEERED SAFETY l. A safety features actuation 1. Loss of functions needed for ines of any function or system system functional unit shown cold shutdown, OR which precludes placing the PROTECTION SYSTEN in Technical Specification plant in Not Shutdown, OR SYSTENS TO PLACE table 3.3-3 becomes inoperable 2. Failure of tlute Reactor PIJWT IH COLD per Technical Specification Protection System to bring Control Room is evacuated

~Stilt-OONI 3.3.2.1 AND requires plant the reactor subcritical when (for other than drill purposes COHTROL ROOH shutdown, OR needed, OR and shutdown control cannot be OPERATION AND established locally at the Not FIRE PROTEGTIOH 2. The fire suppression system 3. Evacuation of control room Shutdown Control Panel within SYSTEH or a portion thereof becomes (for other than drill pur- 15 minutes.

inoperable per Technical poses) with'shutdown control Specification 3.7.11.1 AND established locally at the requires plant shutdown. Not Shutdown Control Panel.

LOSS OF ALARNS Significant loss of effluent hll annunciators lost. hll annunciator alarms lost monitoring capability, meterolo- >15 minutes with plant not in gicai monitoring instrumentation cold shutdown; OR coamLunications, indication and Plant transient occurs with alarm panels, etc., which impairs s11 alarms lost.

ability to perform accident or emergency assessment.

ACTION 1. Complete actions listed on 1. Complete actions listed on 1. Complete actions listed UNUSUAL EVENT CHECKLIST. ALERT CHECKLIST. on SITE AREA EHERGEHCY CHECKLIST.

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Page 15 of 20 NAZARDS TO STATION OPERATION EV BIT UNUSUAL EVENT S1TE AREA EMERGENCY GENERAL EMERGENCY AlRCRAPT Visual sighting of aircrafg crasb Aircraft crash onsite damaging hircraft crash on site on-site or of unusual alrciaft plant structures. damaging vital plant systems activity over facility, or structures.

ONSKTE Visual or audio indication of Damage to facility by explosion Damage to safe shutdown RXPIDSIDII an explosion near or on-site. wbicb affects plant oPeration. equipment from missiles or explosion TOXIC OR PULH- Indication (visual or otherwise) Entry of toxic or .flammable Alarm indication is received HABLE GAS of a near or on-site toxic or gss onto areas potentially on Detecto-Cblor or toxic or flammable gas release. affecting plant operation. flammable gas has diffused into vital areas.

MISSILES Visual or audible indication Damage to safe shutdown equip-of missile impact on plant ment from missiles or structures. explosion.

TURBINE FAILURE Visual indication tbat tbe turbine casing bas been penetrated by blading.

ACTION l. Complete actions listed on 1. Complete actions listed 1. Complete actions listed thu UNUSUAL EVP2Ã CUECKLIST. on ALERT CNECKLIST. on SITE AREA EMERGENCY CNECKLIST.

Page 16 of 20 ELECTRICAL MALFUNCTION CLASS UNUSUAL EUENr ALERT SITE AREA EHERCENCV GENERAL EHERCENCY LOSS OF POIIER Loss of off-site ower or loss Imss of offsite ower and loss Loss of offsite er and

'of on-site AC ower ca abilit of all onsite AC wer loss of onsite AC ower

> 15 minutes

l. Turbine generacor tripawich 1. Turbine generator 'trips plant scarcup cransformers wich plant acarcup crans- l. Turbine generator trips unavailable for servicet OR, formera non-functional, ~AND. with plant startup

2. Loss of voltage on both IA3 transformers unavailable AND l83 4.16 KU busses for 2. Failure of both auergency for service, AND; more than 15 seconds. diesel generators to start or synchronize 2. Sustained failure of boch emergency diesel genera-OR tors co scarc or synchronice for > 15 Loss of all onsice DC ower minutes.

Drop in A and 8 DC Bus OR voltages to < 70 volts.

Loss of all vical onsite DC ower for > 15 minutes Sustained drop in h and 8 DC bus voltages to 70 vdc for

> 15 minutes.

ACTION 1. Complete actions listed on 1. Complete actions listed 1. Complete actions listed UNUSUAL BURNT CIIECKLIST. on ALERT CHECKLIST. on SITE AREA MERCENCY CHECKLIST.

Page 17 of 20 SECURITY EHERGENCIES CLASS EVENT UNUSUAL EVEHT SITE AREA EHERGENCY GENERAL EHL'RGL'NCY A security alert has been called A security caerycncy has been A security esergcncy has A successful takeover of thu by the security force in res- called by the security force as progressed to the'point that plant including the Control ponse to one or nore of the itcas defined in the Safeguards takeover of the plant is Roon has occurred.

listed belou. Contingency Plan. probable

1. Bonb threat

2. Attack threat

3. Civil disturbance

4. Protected area intrusion

5. Sabotage attcapt

6. Internal disturbance

7. Vital area intrusiou

g. Security force strike listed l. Coeplete actions list~el t on 1. Couplete actions listed on 1. Cosplete actions listed on ACl ION 1. Coaplete actions on CENERAL EHERGENCY CHECKLIST UNUSUAL EVEHC CHECKLIST. ALERT CHECKLIST. SITE AREA EHERGENCY CHECK-LIST.

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Page 19 of '20 HISCELLANEOUS EVENTS Shoat 1 of 2 4

CLASS UNUSUAL EVENT ALERT SITE AREA ENERCENCY CENERAI ENCRCENCY EVENT ABNORNAL hbnornal coolant ceu erature

~TEHPRRATURE ANDlOR ressura abnoreLal fuel PRESSURE

1. Subcooling uargin a+niter o

indicates less chen 20 P sub-cooling, OR

2. Highest hoc leg teaperacure is less chan 20 P balou the saturation tenperature, OR

3. Plane Incurs chermocouplas indicate abnoraai fuel teuparatures.

COHTAH I HATED hny concaainaced Individual is INJURY transported off-site to a hospital for creataent of ingurias.

ACTION 1. Complete actions listed on che UNUSUAL EVEHT CHECKLIST.

Page 20 of 20 NISCEILANEOUS EVENTS Sheet 2 of 2 0

UNUSUAL EVEHT ALERT SITE AREA ENERGENCY CENERAL ENERCENCY OTHER CONDITIONS l. A pinup shutdown is required The Technical Supporc Center 1. The Emergency Centers sru An evenc resulting in escalation by Technical Specifications; ~AHD OR Hear Site Emergency acCivated; ~AND of the Emergency Classification CREASED AMARE- OR Operacions Facility are activated 2; Honitoring Teams are to Ceneral Emergency with NESS 2. The slant is shuc down under abnornah conditions (e.g.,

for other than drill purposes. mobilited; ~AND Imminent Subscantial Core Damage

3. A precautionary public and potential for release of exceeding cooldown races or notification is made con-primary system pipe large amouncs of radioactivity cracks're found during operation). cerning an abnormal plane in a short period of cime; such condition for other than asc drill purposes.

1. LOCA with failure of.ECCS.

2. Loss of Secondary Heat Sink.

3. Sustained station blackout with loss of secondary heat sink.

4. Failure of contalnmenc haut removal systems in the lacer stages of an accident result-ing in loss of containmenc.

ACTION l. Complete actions listed on 1. Complete actions listed 1. Complete actions listed 1. Complete actions listed che UNUSUAL EVENT CHECKLIST. on ALERT CllECKLIST. on SITE AREA ENERCEHCY on CEHERAL ENERCEHCY CHECKLIST. CHECKLIST.

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